ML111010634

Initial Exam 2011-301 Final Sim-IN Plant JPMs

ML111010634
Person / Time
Site:	Browns Ferry
Issue date:	04/04/2011
From:	NRC/RGN-II/DRS/OLB
To:	Tennessee Valley Authority
References
50-259/11-301, 50-260/11-301, 50-296/11-301
Download: ML111010634 (150)

Text

JPM a

PAGE 1

OF 14 OPERATOR:

RO___

SRO DATE:________

JPM NUMBER:

a TASK NUMBER:

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

LOCATION OF PERFORMANCE:

Simulator REFERENCES/PROCEDURES NEEDED:

2-01-85 and 2-AOI-85-3 VALIDATION TiME:

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

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS:

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

INITIATING CUE:

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

JPM a

PAGE 3

OF 14 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

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

INITIATING CUE:

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

NRC Examinei Siep, I through 9 are for Continuous ithi1ra1, stçps 10 tlg9ugh 14 arçf Notch withdrawaL

JPM a

PAGE 4

OF 14 START TIME____

Performance Step 1:

Critical X Not Critical 6.6.4 Continuous Rod 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:

JPM a

PAGE 5

OF 14 Performance Step 3:

Critical Not Critical

[3]

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

Standard:

Verifies Rod Worth Minimizer responded correctly.

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 4:

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:______________________________

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PAGE 6

OF 14 Performance Step 5:

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:_____________________________

Drivei: When coupling check complete for control rod 30-35, trip operating CRD Pump.

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PAGE 7

OF 14 Performance Step 6:

X Not Critical

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

[6.4]

CHECK control rod coupled by observing the following:

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

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

[6.5]

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

[6.6]

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

Standard:

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

SAT UNSAT N/A COMMENTS:__________________________

Driver: When coupling check complete fr control rod 30-35, trip operating CRD Pump.

JPM a

PAGE 8

OF 14 N[CNCTEthçsçarecontingency Conpling Check Performance Step 7:

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:_______________________________

Performance Step 8:

• Critical X Not Critical

[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:______________________________

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PAGE 9

OF 14 Performance Step 9:

• Critjcal 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:_____________________________

Driver: When coupling check complete for control rod 30-35, trip operating CRD Pump.

JPM a

PAGE 10 OF 14 9jiifeps Performance Step 10:

Critical Not Critical X 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 38-43 by depressing 3 8-43 pushbutton.

SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 11:

Critical

- Not Critical X

[2]

OBSERVE the following for selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED.

White light on the Full Core Display ILLUMiNATED.

Rod Out Permit light ILLUMINATED.

Standard:

Observes the above indications.

SAT_ UNSAT N/A COMMENTS:

JPM a

PAGE 11 OF 14 Performance Step 12:

Critical Not Critical X

[3]

VERIFY ROD WORTH M11fIMIZER 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 38-43 is going from position 16 to 48.

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 13:

• 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 SEHLE light extinguishes.

Standard:

Withdraws control rod 38-43.

SAT UNSAT N/A COMMENTS:____________________________

JPM a

PAGE 12 OF 14 Performance Step 14:

• 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:______________________________

Driver: When coupling check complete for control rod 30-35, trip operating CR]) Pump.

JPM a

PAGE 13 OF 14 Performance Step 15:

Critical X Not Critical Operator Ranges IRMs as necessary; to maintain greater than the downscale reading of 7.5/1 25 and less than the upscale reading of 90/1 25.

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

Standard:

Ranges IRMs to clear or prevent a Rod Block signal.

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

SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 16:

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 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:______________________________

JPM a

PAGE 14 OF 14 Performance Step 17:

Critical Not Critical X

[1.2]

START associated standby CRD Pump using one of the following:

• CRD Pump 1B, using 2-HS-85-2A

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

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

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 18:

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 anothex operator will continue in 2-AOI-100-1.

END OF TASK STOP TIME

JPM a

PAGE 1

OF 14 OPERATOR:

RO SRO DATE:_______

JPM NUMBER:

a TASK NUMBER:

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

LOCATION OF PERFORMANCE:

Simulator REFERENCES/PROCEDURES NEEDED:

3-01-85 and 3-AOI-85-3 VALIDATION TIME:

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

PERFORMANCE TIME:

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

IMTIAL CONDITIONS:

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

INITIATING CUE:

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

JPM a

PAGE 3

OF 14 IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge Thats Correct. (OR Thats Incorrect, if applicable). When you have completed your assigned task, you will say, my task is complete and I will acknowledge that your task is complete.

INITIAL CONDITIONS:

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

INITIATING CUE:

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

W

%RC?Examner Steps I through9 are for Continuous withdval, steps 1Qtbroiigh 14 ate fot Notch vithdrawaI.

JPM a

PAGE 4

OF 14 START TIME____

Performance Step 1:

Critical X Not Critical 6.6.4 Continuous Rod 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:

JPM a

PAGE 5

OF 14 Performance Step 3:

Critical Not Critical

[3]

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

Standard:

Verifies Rod Worth Minimizer responded correctly.

SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 4:

Critical Not Critical

[4]

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

Standard:

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

SAT_ U1SAT N/A COMMENTS:_______________________________

JPM a

PAGE 6

OF 14 Performance Step 5:

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[61.

[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: When coupling cheók complete for control rod 30-35, trip operating CRD Pump.

JPM a

PAGE 7

OF 14 Performance Step 6:

Critical X Not Critical

[6.3]

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

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

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

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

[6.5]

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

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

Standard:

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

SAT UNSAT N/A COMMENTS:___________________

JPM a

PAGE 8

OF 14 NRC 11OTEtkci co cyoupiiug &ck Performance Step 7:

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:_______________________________

Performance Step 8:

• 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:_____________________________

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PAGE 9

OF 14 Performance Step 9:

• 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 SEYILE light extinguishes.

Standard:

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

SAT_U1SAT N/A COMMENTS:

Driver: When coupling check complete for control rod 30-35, trip operating CRD Pump;

JPM a

PAGE 10 OF 14 NRfE WotcdraiISeps Performance Step 10:

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 30-3 5 by depressing 30-3 5 pushbutton.

SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 11:

Critical

- Not Critical X

[2]

OBSERVE the following for selected control rod:

CRD ROD SELECT pushbutton is brightly ILLUMINATED.

White light on the Full Core Display ILLUMINATED.

Rod Out Permit light ILLUMINATED.

Standard:

Observes the above indications.

SAT UNSAT N/A COMMENTS:

JPM a

PAGE 11 OF 14 Performance Step 12:

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 13:

• 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:____________________________

JPM a

PAGE 12 OF 14 Performance Step 14:

• 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:_______________________________

Driver: When coupling check complete for control rod 30-35, trip operating CRD Pump.

JPM a

PAGE 13 OF 14 Performance Step 15:

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 wifi be a failure.

SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 16:

Critical Not Critical 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:_____________________________

JPM a

PAGE 14 OF 14 Performance Step 17:

Critical Not Critical

[1.2]

START associated standby CRD Pump using one of the following:

• CRD Pump 3B, using 3-HS-85-2A

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

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

SAT_ UNSAT N/A _COMMENTS:______________________________

Performance Step 18:

Critical 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-I.

END OF TASK STOP TIME

JPM b

PAGE 1

OF 5

OPERATOR:_______________________

RO___

SRO___

DATE:

JPM NUMBER:

b TASK NUMBER:

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

LOCATION OF PERFORMANCE:

Simulator REFERENCES/PROCEDURES NEEDED:

2-AOI 1 VALIDATION TIME:

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

PERFORMANCE TIME:

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS:

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

INITIATING CUE:

The Unit Supervisor directs you to restore RFPT C for level control using Manual Governor Control in accordance with 2-AOI-3-1, Loss of Reactor Feedwater or Reactor Water Level High/Low starting at step 8. Level band is the normal operating band.

JPM b

PAGE 3

OF 5

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

INITIAL CONDITIONS:

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

INITIATING CUE:

The Unit Supervisor directs you to restore RFPT C for level control using Manual Governor Control in accordance with 2-AOI-3-1, Loss of Reactor Feedwater or Reactor Water Level High/Low starting at step 8. Level band is the normal operating band.

JPM b

PAGE 4 OF 5

START TIME____

Performance Step 1:

• Critjcal X Not Critical

[8]

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

[8.1]

OBTAIN SRO permission to restart RFPT.

• [8.2] RESET trip by using pushbutton.

Standard:

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

Performance Step 2:

Critical X Not Critical

[8.3]

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

Standard:

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

SAT_ UNSAT N/A COMMENTS:____________________________

Performance Step 3:

Critical X Not Critical

[8.4]

PLACE RFPT StartlLocal enable switch to START.

Standard:

Places RFPT C Start/Local enable switch to Start.

SAT_ USAT N/A COMMENTS:______________________________

JPM b

PAGE 5

OF 5

Performance Step 4:

Critical Not Critical X

[8.5]

VERIFY RFPT accelerates to approximately 600 rpm.

Standard:

Verifies RFPT C accelerates SAT_ UNSAT N/A COMMENTS:_____________________________

Performance Step 5:

Critical Not Critical

[8.7]

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

Standard:

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

END OF TASK STOP TiME

JPM b

PAGE 1

OF 5

OPERATOR:_______________________

RO___

SRO___

DATE:________

JPM NUMBER:

b TASK NUMBER:

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

LOCATION OF PERFORMANCE:

Simulator REFERENCES/PROCEDURES NEEDED:

3-AOI 1 VALIDATION TIME:

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

PERFORMANCE TIME:

COMMENTS:_____________________________

Additional connuent sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMiNER

INITIAL CONDITIONS:

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

INITIATING CUE:

The Unit Supervisor directs you to restore RFPT C for level control using Manual Governor Control in accordance with 3-AOI-3-l, Loss ofReactor Feedwater or Reactor Water Level HighlLow starting at step 11. Level Band is the normal operating band.

JPM b

PAGE 3

OF 5

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

INITIAL CONDITIONS:

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

INITIATING CUE:

The Unit Supervisor directs you to restore RFPT C for level control using Manual Governor Control in accordance with 3-AOI 1, Loss of Reactor Feedwater or Reactor Water Level High/Low starting at step 11. Level Band is the normal operating band.

JPM b

PAGE 4

OF 5

START TIME____

Performance Step 1:

• Critical X Not Critical

[11]

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

[11.11 OBTAIN Unit Supervisor permission to restart RFPT.

• [1 1.2] RESET trip by using pushbutton.

Standard:

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

Performance Step 2:

Critical X Not Critical

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

Standard:

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

SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 3:

Critical X Not Critical

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

Standard:

Places RFPT C Start/Local enable switch to Start.

SAT UNSAT N/A COMMENTS:____________________________

JPM b

PAGE 5

OF 5

Performance Step 4:

Critical Not Critical X

[11.5] VERIFY RFPT accelerates to approximately 600 rpm.

Standard:

Verifies RFPT C accelerates SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 5:

Critical Not Critical

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

Standard:

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

END OF TASK STOP TIME

JPM c

PAGE 1

OF 7

OPERATOR:_____________________

RO___

SRO___

DATE:

JPM NUMBER:

c TASK NUMBER:

U-000-EM-50 TASK TITLE:

2-EOI APPENDIX-i 1D Alternate RPV Pressure control Systems-Main Steamline Drains and/or Turbine and RFPT Drains K/A NUMBER:

239001 A1.08 K/A RATING: RO 3.8 SRO 3.8 TASK STANDARD: Establish alternate pressure control with Main Steamline drains, Turbine and RFPT draifs LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED:

2-EOI APPENDIX-i 1D VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS:

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

INITIATING CUE:

The Unit Supervisor directs you to establish alternate pressure control as directed by 2-EOI Appendix liD Alternate RPV Pressure control Systems-Main Steamline Drains and/or Turbine and RFPT Drains and maintain Reactor Pressure 700 to 900 psig.

JPM c

PAGE 3

OF 7

IN-SIMULATOR:

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

INITIAL CONDITIONS:

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

INITIATING CUE:

The Unit Supervisor directs you to establish alternate pressure control as directed by 2-EOI Appendix liD Alternate RPV Pressure control Systems-Main Steamline Drains and/or Turbine and RFPT Drains and maintain Reactor Pressure 700 to 900 psig.

3PM c

PAGE 4 OF 7

START TIME____

Performance Step 1:

Critical Not Critical 1.

IF BOTH ofthe following exist:

Emergency RPV Depressurization is required, AND Group 1 Isolation Signal exists, THEN EXIT this procedure and ENTER EOI Appendix 1 1H.

Standard:

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

Performance Step 2:

Critical Not Critical X 2.

VERIFY hotwell pressure below -7 in. Hg.

Standard:

Verifies hotwell pressure less than -7 in. Hg.

SAT UNSAT N/A COMMENTS:____________________________

JPM c

PAGE 5

OF 7

Performance Step 3:

Critical Not Critical X 3.

CONTROL RPV pressure with Main Steam line drains as follows:

a.

VERIFY PCIS reset.

Standard:

Verifies PCIS Reset SAT UNSAT N/A COMMENTS:__________________________

Performance Step 4:

Critical X Not Critical b.

OPEN the following valves (Panel 9-3):

2-FCV-l-55, MN STM LThJE DRAIN INBD ISOLATION VLV 2-FCV-l-56, MN STM LINE DRAIN OUTBD ISOLATION VLV 2-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER Standard:

Opens 2-FCV-1-55, 2-FCV-1-56, and 2-FCV-l-58 SAT UNSAT N/A _COMMENTS:________

JPM c

PAGE 6

OF 7

Performance Step 5:

Critical Not Critical 4.

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

Standard:

Throttles 2-FCV-l-59 open and control cooldown rate SAT_ UNSAT N/A COMMENTS:___________

CITE:

Iiecessary when2FCV-1-59is<IhII opex, DireeI OeratorthatAdditioiiaI RPVPrsureConto1 isneeessarf Performance Step 6:

Critical X Not Critical 5.

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

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

a.

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

2-FCV-6-100, STOP VALVE 1 BEFORE SEAT DR VLV 2-FCV-6-1O1, STOP VALVE 2 BEFORE SEAT DR VLV 2-FCV-6-102, STOP VALVE 3 BEFORE SEAT DR VLV 2-FCV-6-103, STOP VALVE 4 BEFORE SEAT DR VLV Standard:

Opens 2-FCV-6-100, 2-FCV-6-1O1, 2-FCV-6-102, and 2-FCV-6-103 SAT_ UNSAT N/A COMMENTS:

JPM c

PAGE 7

OF 7

Performance Step 7:

Critical X Not Critical b.

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

2-FCV-6-122, RFPT 2A HP STOP VLV ABOVE SEAT DR 2-FCV-6-127, RFPT 2B HP STOP VLV ABOVE SEAT DR 2-FCV-6-l32, RFPT 2C HP STOP VLV ABOVE SEAT DR Standard:

Opens 2-FCV-6-122, 2-FCV-6-l27, and 2-FCV-6-132 SAT UNSAT N/A COMMENTS:_________

CUE:

Another Operator is working on other means ofPressure ContrOl END OF TASK STOP TIME____

JPM c

PAGE 1

OF 7

OPERATOR:_____________________

RO___

SRO DATE:

JPM NUMBER:

c TASK NUMBER:

U-000-EM-50 TASK TITLE:

3-EOI APPENDIX-i 1D Alternate RPV Pressure control Systems-Main Steamline Drains and/or Turbine and RFPT Drains K/A NUMBER:

239001 Ai.08 K/A RATING: RO 3.8 SRO 3.8 TASK STANDARD: Establish alternate pressure control with Main Steamline drains, Turbine and RFPT drains LOCATION OF PERFORMANCE: Simulator REFERENCES/PROCEDURES NEEDED:

3-EOI APPENDIX-i 1D VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS:

You are a Unit 3 Operator. Unit 3 reactor has scrammed. Emergency depressurization is not required but alternate means ofpressure control is required. Turbine Bypass valves are NOT available. EOI-1 has been followed to RC/P-11. Another Operator is assigned Reactor Level Control.

INITIATING CUE:

The Unit Supervisor directs you to establish alternate pressure control as directed by 3-EOI Appendix-i 1D Alternate RPV Pressure Control Systems Main Steam Line Drains and/or Turbine and RFPT Drains and maintain Reactor Pressure 700 to 900 psig.

JPM c

PAGE 3

OF 7

IN-S1M1JLATOR:

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

INITIAL CONDITIONS:

You are a Unit 3 Operator. Unit 3 reactor has scrammed. Emergency depressurization is not required but alternate means ofpressure control is required. Turbine Bypass valves are NOT available. EOI-1 has been followed to RC/P-11. Another Operator is assigned Reactor Level Control.

INITIATiNG CUE:

The Unit Supervisor directs you to establish alternate pressure control as directed by 3-EOI Appendix-i 1D Alternate RPV Pressure Control Systems Main Steam Line Drains and/or Turbine and RFPT Drains and maintain Reactor Pressure 700 to 900 psig.

JPM c

PAGE 4 OF 7

START TIME____

Performance Step 1:

Critical Not Critical X 1.

IF BOTH ofthe following exist:

Emergency RPV Depressurization is required, AND Group 1 Isolation Signal exists, THEN EXIT this procedure and ENTER EOI Appendix 1 1H.

Standard:

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

Performance Step 2:

Critical Not Critical 2.

VERIFY hotwell pressure below -7 in. Hg.

Standard:

Verifies hotwell pressure less than -7 in. Hg.

SAT UNSAT N/A COMMENTS:_______________________________

JPM c

PAGE 5

OF 7

Performance Step 3:

Critical Not Critical 3.

CONTROL RPV pressure with Main Steam line drains as follows:

a.

VERIFY PCIS reset.

Standard:

Verifies PCIS Reset SAT UNSAT N/A COMMENTS:__________________________

Performance Step 4:

Critical X Not Critical b.

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

3-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV 3-FCV-l-56, MN STM LINE DRAIN OUTBD ISOLATION VLV 3-FCV-l-58, UPSTREAM MSL DRAIN TO CONDENSER Standard:

Opens 3-FCV-l -55, 3-FCV-l -56, and 3-FCV-l -58 SAT_ UNSAT N/A _COMMENTS:_______

JPM c

PAGE 6

OF 7

Performance Step 5:

V Critical X Not Critical 4.

THROTTLE 3-FCV-1-59, DOWNSTREAM MSL DRAIN TO CONDENSER, as necessary to control cooldown rate.

Standard:

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

ECUE V

fViiecsrywhen 3-VFO1-$9 is full cpex,Direct Operator IiatAdditiona1.

j RPVJressControIiçiccessaiy V

Performance Step 6:

Critical Not Critical 5.

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

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

a.

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

3-FCV-6-lOO, STOP VALVE 1 BEFORE SEAT DR VLV 3-FCV-6-1O1, STOP VALVE 2 BEFORE SEAT DRVLV 3-FCV-6-102, STOP VALVE 3 BEFORE SEAT DR VLV 3-FCV-6-103, STOP VALVE 4 BEFORE SEAT DR VLV Standard:

Opens 3-FCV-6-100, 3-FCV-6-1O1, 3-FCV-6-102, and 3-FCV-6-103 SAT_ UNSAT N/A COMMENTS:____________________________

JPM c

PAGE 7

OF 7

Performance Step 7:

Critical X Not Critical b.

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

3-FCV-6-122, RFPT 3A HP STOP VLV ABOVE SEAT DR 3-FCV-6-127, RFPT 3B HP STOP VLV ABOVE SEAT DR 3-FCV-6-132, RFPT 3C HP STOP VLV ABOVE SEAT DR Standard:

Opens 3-FCV-6-122, 3-FCV-6-127, and 3-FCV-6-132 SAT_ UNSAT N/A COMMENTS:_________

CUE:

Ailother Qperatoris working on othermeans ofPressure Control END OF TASK STOP TIME____

JPM d

PAGE 1 of9 OPERATOR:

RO___

SRO DATE:

JPM NUMBER:

d TASK NUMBER:

U-000-EM-50 TASK TITLE:

2-EOI-APPENDIX-8F Restore Reactor and Refuel Zone Ventilation Fans following a Group 6 Isolation KIA NUMBER: 295032 EA1.03 K/A RATING: RO 3.7 SRO 3.7 TASK STANDARD: Restore Reactor and Refuel Zone Ventilation Fans following a Group 6 Isolation PERFORMANCE LOCATION:

Simulator REFERENCES/PROCEDURES NEEDED: 2-EOI-Appendix-8F VALIDATION TIME: 10 minutes MAX. TIME ALLOWED:

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS:

You are an Operator. Unit 2 reactor has scrammed and a Group 6 isolation has occurred from RPV low level. EOI-1 has been entered and followed to RC/P-8. The US wants the reactor and refueling zone ventilation systems restored. No other Group 6 isolation signals exist. Appendix 8E, Bypassing Group 6 RPV Low Level and High Drywell Pressure Isolation Interlocks, has been completed.

INITIATING CUE:

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

JPM d

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

INITIAL CONDITIONS:

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

INITIATING CUE:

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

JPM d

PAGE 4 of 9 START TIME____

Performance Step 1:

Critical X Not Critical 1.

VERIFY PCIS Reset.

Standard:

Resets PCIS SAT UNSAT N/A _COMMENTS:_______________________________

Performance Step 2:

Critical Not Critical 2.

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

a.

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

Standard:

Places 2-HS-64-3A in the Offposition.

SAT UNSAT N/A _COMMENTS:________________________________

Performance Step 3:

Critical X Not Critical b.

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

Standard:

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

SAT UNSAT N/A COMMENTS:_______________________________

JPM d

PAGE 5 of 9 Performance Step 4:

Critical Not Critical c.

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

Standard:

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

SAT UNSAT N/A _COMMENTS:______________________________

Performance Step 5:

Critical Not Critical X d.

VERIFY OPEN the following dampers:

2-FCO-64-5, REFUEL ZONE SPLY OUTBD ISOL DMPR 2-FCO-64-6, REFUEL ZONE SPLY INBD ISOL DMPR 2-FCO-64-9, REFUEL ZONE EXH OUTBD ISOL DMPR 2-FCO-64-1O, REFUEL ZONE EXH 11BD ISOL DMPR Standard:

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

JPM d

PAGE 6 of 9 Performance Step 6:

Critical Not Critical 3.

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

a.

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

Standard:

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

SAT UNSAT N/A _COMMENTS:______________________________

Performance Step 7:

Critical X Not Critical b.

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

Standard:

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

SAT UNSAT N/A _COMMENTS:____________

JPM d

PAGE 7 of 9 Performance Step 8:

Critical Not Critical c.

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

Standard:

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

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 9:

Critical Not Critical d.

VERIFY OPEN the following dampers:

2-FCO-64-13, REACTOR ZONE SPLY OUTBD ISOL DMPR 2-FCO-64-14, REACTOR ZONE SPLY INBD ISOL DMPR 2-FCO-64-42, REACTOR ZONE EXH INBD ISOL DMPR 2-FCO-64-43, REACTOR ZONE EXH OUTBD ISOL DMPR Standard:

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

JPM d

PAGE 8 of 9 Performance Step 10:

Critical Not Critical X 4.

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

Standard:

Given in Initial conditions that SGTS is required.

SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 11:

Critical Not Critical 5.

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

Standard:

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

CUE: Five Minutes has elapsed

JPM d

PAGE 9 of 9 Performance Step 12:

Critical Not Critical 6.

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

Standard:

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

SAT UNSAT N/A COMMENTS:

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

JPM d

PAGE 1 of 9 OPERATOR:

RO SRO DATE:_____

JPM NUMBER:

d TASK NUMBER:

U-000-EM-50 TASK TITLE:

3-EOI APPENDIX-8F Restore Reactor and Refuel Zone Ventilation Fans following a Group 6 Isolation K/A NUMBER: 295032 EA1.03 KJA RATING: RO 3.7 SRO 3.7 TASK STANDARD: Restore Reactor and Refuel Zone Ventilation Fans following a Group 6 Isolation PERFORMANCE LOCATION:

Simulator REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-8F VALIDATION TIME: 10 minutes MAX. TIME ALLOWED:

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS:

You are an Operator. Unit 3 reactor has scrammed and a Group 6 isolation has occurred from RPV low level. EOI-1 has been entered and followed to RC/P-8. The US wants the reactor and refueling zone ventilation systems restored. No other Group 6 isolation signals exist. Appendix 8E, Bypassing Group 6 RPV Low Level and High Drywell Pressure Isolation Interlocks, has been completed.

INITIATING CUE:

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

JPM d

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

INITIAL CONDITIONS:

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

INITIATING CUE:

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

JPM d

PAGE 4 of 9 START TIME____

Performance Step 1:

Critical X Not Critical 1.

VERIFY PCIS Reset.

Standard:

Resets PCIS SAT UNSAT N/A _COMMENTS:_______________________________

Performance Step 2:

Critical X Not Critical 2.

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

a.

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

Standard:

Places 3-HS-64-3A in the Offposition.

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 3:

Critical X Not Critical b.

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

Standard:

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

SAT_ UNSAT N/A COMMENTS:_______________________________

JPM d

PAGE5of9 Performance Step 4:

Critical Not Critical X c.

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

Standard:

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

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 5:

Critical Not Critical X d.

VERIFY OPEN the following dampers:

3-FCO-64-5, REFUEL ZONE SPLY OUTBD ISOL DMPR 3-FCO-64-6, REFUEL ZONE SPLY INBD ISOL DMPR 3-FCO-64-9, REFUEL ZONE EXH OUTBD ISOL DMPR 3-FCO-64-1O, REFUEL ZONE EXH lNBD ISOL DMPR Standard:

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

JPM d

PAGE 6 of 9 Performance Step 6:

Critical X Not Critical 3.

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

a.

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

Standard:

Places 3-HS-64-11A in the Offposition.

SAT UNSAT N/A COMMENTS:______________________________

Performance Step 7:

Critical X Not Critical b.

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

Standard:

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

SAT U1SAT_ N/A COMMENTS:___________

JPM d

PAGE 7 of 9 Performance Step 8:

Critical Not Critical X c.

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

Standard:

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

SAT U14SAT_ N/A COMMENTS:______________________________

Performance Step 9:

Critical Not Critical d.

VERIFY OPEN the following dampers:

3-FCO-64-13, REACTOR ZONE SPLY OUTBD ISOL DMPR 3-FCO-64-14, REACTOR ZONE SPLY INBD ISOL DMPR 3-FCO-64-42, REACTOR ZONE EXH INBD ISOL DMPR 3-FCO-64-43, REACTOR ZONE EXH OUTBD ISOL DMPR Standard:

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

JPM d

PAGE 8 of 9 Performance Step 10:

Critical Not Critical X 4.

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

Standard:

Given in Initial conditions that SGTS is required.

SAT UNSAT N/A _COMMENTS:_______________________________

Performance Step 11:

Critical Not Critical 5.

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

Standard:

Places 3-HS-64-11A in either FAST A or FAST B position in accordance with which set of fans were started in slow SAT UNSAT N/A _COMMENTS:______________________________

CUB Five Minutes has elpsed

JPM d

PAGE 9 of 9 Performance Step 12:

Critical Not Critical X 6.

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

Standard:

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

SAT UNSAT N/A_COMMENTS:________

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

JPM e

PAGE 1

OF 9

OPERATOR:______________________

RO___

SRO DATE:

JPM NUMBER:

e TASK NUMBER:

U-000-SS-25 TASK TITLE:

Energize 4 KV SD BDs A, C, and D from Unit 3 DGs KJA NUMBER: 264000 A4.04 K/A RATING: RO 3.7 SRO 3.7 TASK STANDARD: 4 KV SD BDs A and C energized from Unit 3 DGs during a Unit 1 and 2 Diesel Generator Building Fire. DG D Emergency Shutdown due to Low Lube Oil Pressure LOCATION OF PERFORMANCE:

Simulator REFERENCES/PROCEDURES NEEDED:

0-SSI-20 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: NOT TIME CRITICAL Alternate Path PERFORMANCE TIME:

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS:

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

INITIATING CUE:

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

Time Critical

JPM e

PAGE 3

OF 9

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

INITIAL CONDITIONS:

You are an Operator on Unit 3, the plant is operating in 0-S51-20 Unit 1 and 2 Diesel Generator Building fire. All three units have been scrammed. An Assistant Unit Operator has been dispatched to the DGs.

INITIATING CUE:

The Unit Supervisor directs you to complete attachment 6, Unit 3 Panel 9-23 Actions of 0-SSI-20.

Time Critical

JPM e

PAGE 4

OF 9

START TIME Performance Step 1:

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

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

[1]

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

[2]

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

[2.1]

VERIFY DG 3A CONTROL switch, 3-HS-82-3AJ1A, in START.

Standard:

Starts DG 3A SAT_ U1JSAT N/A COMMENTS:_______________________________

Performance Step 2:

Critical X Not Critical

[2.2]

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

Standard:

Depresses 3-HS-21 1-3EA SAT_ UNSAT N/A COMMENTS:_____________________________

NRC NOTE Trip to Manual allows the]orinal1?eeder 1çaker to Open, ifnot in Manual N9mLi!c4cnLQpe!1JI1 next step

JPM e

PAGE 5

OF 9

Performance Step 3:

Critical X Not Critical

[2.3]

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

Standard:

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

Performance Step 4:

Critical Not Critical X

[2.4]

VERIFY DG 3A BKR 1838 CLOSED.

Standard:

Verifies DG Breaker 1838 closes SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 5:

Critical X Not Critical

[2.5]

PLACE 4KV SD BD 3EA EMER FDR BKR 1844, 3-HS-21 1-3EAJ1A, in CLOSE.

Standard:

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

JPM e

PAGE 6

OF 9

Performance Step 6:

Critical X Not Critical

[3]

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

[3.1]

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

Standard:

StartsDG3C SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 7:

Critical Not Critical

[3.2]

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

Standard:

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

Performance Step 8:

Critical X Not Critical

[3.3]

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

Standard:

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

JPM e

PAGE 7

OF 9

Performance Step 9:

Critical Not Critical X

[3.4]

VERIFY DG 3C BKR 1832 CLOSED.

Standard:

Verifies DG Breaker 1832 closes SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 10:

Critical X Not Critical

[3.5]

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

Standard:

Closes Emergency Feeder Breaker 1834 SAT_ UNSAT N/A _COMMENTS:______________________________

JPM e

PAGE 8

OF 9

Performance Step 11:

Critical Not Critical

[4]

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

[4.1]

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

Standard:

Starts DG 3D SAT_ UNSAT N/A _COMMENTS:_______________________________

PjJVER: aftçriXjs spir4ente frigr1 for LjAçiPressure Performance Step 12:

Critical Not Critical RESPONDS to the Alarm 9-23D WIN 4 (DIESEL GEN D LUBE OIL ABNORMAL) and notices the AMBER LIGHT (LOW LOW OIL PRESSURE)

Standard:

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

SAT UNSAT_ N/A COMMENTS:______________________________

CiJ If Assistant thiit Operatoris callcd, After Lub oil presure alarm is received t1 9-23, report lube oil pressure low at5psig and Lube Oil is spraying ontoIa damaged.

JPM e

PAGE 9 OF 9

Performance Step 13:

Critical Not Critical DIESEL GEN 3D LUBE OIL ABNORMAL Window 4 SHUT DOWN the DG by Emergency Stop Pushbutton Standard:

Shuts Down the DG with the Emergency Stop Pushbutton.

SAT_ UNSAT N/A _COMMENTS:_____________________________

tdonnicfDGHsnotabJiie1yecessary Examiner note: ALARM on 9-23D win 4 DG D LUBE OIL ABNORMAL will alarm and LOW LOW OIL PRESSURE LIGHT for D DG will illuminate, the operator should respond per the ARP.

Performance Step 15:

Critical Not Critical X

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

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

Standard:

Notifies Unit Supervisor SAT UNSAT N/A _COMMENTS:______________________________

CUE::

Rmain in Control Room another Operator has beeii dispatched to 480V RMOV Board3C.JPMComplete END OF TASK STOP TIME

JPM f

PAGE 1 OF 9

OPERATOR:

RO___

SRO___

DATE:_______

JPM NUMBER:

f TASK NUMBER:

0-74-AB-Ol TASK TITLE: Loss of Shutdown Cooling K/ANUMBER: 295021 AA1.02 K/A RATING: R03.5 SRO3.5 TASK STANDARD: Restores shutdown cooling following an inadvertent RPS actuation, will restore shutdown cooling with RHR Pump 2A and establish a cooldown JAW 2-AOI 1.

LOCATION OF PERFORMANCE:

Simulator REFERENCES/PROCEDURES NEEDED:

2-AOI 1 VALIDATION TJME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS: You are a Unit 2 operator. Unit 2 is in Mode 3 (Recirc Loop B temp

> 2 12°F) heading towards cold conditions for a refueling outage. RHR Loop I using 2A RHR Pump was in shutdown cooling. Unit 1 is carrying 2000 gpm for RHRSW Pumps A2 and C2.

An inadvertent loss of 2B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 2B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 2B RPS. An Auxiliary Operator is standing by for 2A RHR Pump start.

INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 2A RHR pump in accordance with 2-AOI-74-1 starting at step 12.

JPM f

PAGE 3

OF 9

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

INITIAL CONDITIONS: You are a Unit 2 operator. Unit 2 is in Mode 3 (Recirc Loop B temp

> 2 12°F) heading towards cold conditions for a refueling outage. RHR Loop I using 2A RHR Pump was in shutdown cooling. Unit 1 is carrying 2000 gpm for RHRSW Pumps A2 and C2.

An inadvertent loss of 2B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 2B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 2B RPS. An Auxiliary Operator is standing by for 2A RHR Pump start.

INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 2A RHR pump in accordance with 2-AOI-74-1 starting at step 12.

JPM f

PAGE 4 OF 9

START TIME Performance Step 1:

Critical Not Critical

[12]

IF the loss of Shutdown Cooling is due to Group 2 PCIS isolation, THEN (Otherwise N/A)

WHEN conditions permit resetting Group 2 PCIS isolation are met, PERFORM the following:

[12.1] RESET Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 2-HS-64-16A-S32, and PCIS DIV II RESET, 2-HS-64-16A-S33, in reset.

Standard:

On Panel 2-9-4, RESETS Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 2-HS-64-16A-S32, in reset and PCIS Div II RESET, 2-HS-64-16A-S33 to reset.

SAT_ U14SAT N/A COMMENTS:______________________________

Performance Step 2:

Critical Not Critical X

[12.2] MOMENTARILY DEPRESS RHR SYS 1(11) SD CLG INBD INJECT ISOL RESET, 2-XS-74-126 and 2-XS-74-132. VERIFY 2-IL-74-126 and 2-IL-74-1 32 extinguished.

Standard:

Momentarily Depresses RHR SYS I SD CLG INBD INJECT ISOL RESET, 2-XS-74-132 and verifies 2-IL-74-132 extinguished.

SAT ITh4SAT N/A COMMENTS:_____________________________

JPM f

PAGE 5

OF 9

Performance Step 3:

Critical Not Critical X

[13]

IF the loss of Shutdown Cooling is due to Group 2 PCIS AND the isolation signal fails to reset, or remain reset due to invalid and/or sporadic signals, THEN (Otherwise N/A)

Standard:

N/As all Step 4.2[13], the PCIS signal is reset in step 12.

SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 4:

Critical X Not Critical

[14]

IF the Group 2 PCIS Isolation has been reset, THEN (otherwise N/A)

RETURN the affected ioop of RHR to Shutdown Cooling as follows:

[14.1] CLOSE RHR SYS I LPCI OUTBD INJECT VALVE, 2-FCV-74-52.

Standard:

Closes 2-FCV-74-52 SAT U14SAT N/A COMMENTS:____________________________

Performance Step 5:

Critical Not Critical

[14.2] OPEN RHR SYS I LPCI INBD INJECT VALVE, 2-FCV-74-53.

Standard:

Opens 2-FCV-74-53 SAT_ UNSAT_ N/A COMMENTS:______________________________

JPM f

PAGE 6 OF 9

Performance Step 6:

Critical Not Critical

[14.3] VERIFY RHR SYSTEM I MIN FLOW iNHIBIT switch, 2-HS-74-148 in INHIBIT Standard:

Verifies 2-HS-74-148 in INHIBIT.

SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 7:

Critical Not Critical X

[14.4] VERIFY CLOSED RHR SYSTEM I MN FLOW VALVE, 2-FCV-74-7.

Standard:

Verifies 2-FCV-74-7 is closed.

SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 8:

Critical Not Critical

[14.5] VERIFY CLOSED RHR PUMP 2A and 2C SUPPR POOL SUCT VLVs, 2-FCV-74-1 and 2-FCV-74-12.

Standard:

Verifies 2-FCV-74-l & 12 are closed.

SAT UNSAT N/A COMMENTS:

JPM f

PAGE 7

OF 9

Performance Step 9:

Critical Not Critical

[14.6] VERIFY OPEN RHR PUMP 2A and 2C SD COOLING SUCT VLVs, 2-FCV-74-2 and 2-FCV 13.

Standard:

Verifies 2-FCV-74-2 & 13 are open.

SAT UNSAT N/A COMMENTS:_______________________________

Performance Step 10:

• Critical X Not Critical

[14.7] OPEN RHR SHUTDOWN COOLING SUCT OUTBD and INBD ISOL VLVs, 2-FCV-74-47 and 2-FCV-74-48.

Standard:

Opens *2.Hs7447 and verifies 2-FCV-74-48 open.

SAT_ UNSAT N/A COMMENTS:_______________________________

Performance Step 11:

Critical Not Critical

[14.8] IF the tripped pump has been determined to be in operating condition and with Unit Supervisor permission, THEN: RESTART tripped RHR pump(s) RHR PUMP 2A using 2-HS-74-5A Standard:

Starts 2A RHR Pump SAT_ UNSAT N/A _COMMENTS:________________________

teTijiayQ tjjijjtieptindItionJ, RHR Pump Start Time

JPM f

PAGE 8

OF 9

Performance Step 12:

Critical X Not Critical

[14.9] THROTTLE RHR SYS I LPCI OUTBD INJECT VALVE, 2-FCV-74-52, to establish and maintain RHR flow as indicated by 2-FI-74-50, RHR SYS I FLOW, as follows:

RIIR Pumps in 1

2 Operation Loop Flow 7,000 to 10,000 gpm 14,000 to 20,000 gpm Loop Flow (1 or more fuel 6,000 to 6,500 gpm N/A bundles removed from_core)

Standard:

Manipulates 2-HS-74-52 to obtain RHR System I Loop flow between 7,000 and 10,000 gpm on 2-FI-74-50.

SAT UNSAT N/A COMMENTS:______________________

RHR Flow Established Time kYSmmvkwGdance rT iiiiiimize syste ibaiion,RH1pima peiaio o4d6e mniedbeIo QQgp abo QQQgpfqripqrean3 thiuj nfjq

JPM t

PAGE 9

OF 9

Performance Step 13:

Critical Not Critical X

[14.101 WHEN time permits after RHR pump is started, THEN VERIFY RHR Pump Breaker charging spring recharged by observing amber breaker spring charged light is on and closing spring target indicates charged.

Standard:

Dispatched personnel to verify RHR Pump 2A breaker closing spring recharged.

SAT_ UNSAT N/A _COMMENTS:_______________________________

CUE: If.eqnested, oJdgçjindstate9pcratoiJnputé.

Performance Step 14:

Critical X Not Critical

[14.11] SLOWLY THROTTLE RHR HX 2A RHRSW OUTLET VALVE, 2-FCV-23-34, to obtain desired cooldown rate.

Standard:

Throttles 2-FCV-23-34 open to commence cooldown SAT_ UNSAT N/A _COMMENTS:________________________________

I CUE: That completes this task.

END OF TASK STOP TIME:

JPM f

PAGE 1

OF 9

OPERATOR:

RO SRO DATE:

JPM NUMBER:

f TASK NUMBER:

0-74-AB-Ol TASK TiTLE: Loss of Shutdown Cooling KJA NUMBER: 295021 AA1.02 KJA RATING: RO 3.5 SRO 3.5 TASK STANDARD: Restores shutdown cooling following an inadvertent RPS actuation, will restore shutdown cooling with RHR Pump 3A and establish a cooldown JAW 3-AOI-74-l.

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

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS: You are a Unit 3 operator. Unit 3 is in Mode 3 (Recirc Loop B temp

> 2 12°F) heading towards cold conditions for a refueling outage. RHR Loop I using 3A RHR Pump was in shutdown cooling. Unit 1 is carrying 2000 gpm for RHRSW Pumps A2 and C2.

An inadvertent loss of 3B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 3B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 3B RPS. An Auxiliary Operator is standing by for 3A RHR Pump start.

INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 3A RHR pump in accordance with 3-AOI-74-1 starting at step 9.

JPM f

PAGE 3

OF 9

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

INITIAL CONDITIONS: You are a Unit 3 operator. Unit 3 is in Mode 3 (Recirc Loop B temp

> 2 12°F) heading towards cold conditions for a refueling outage. RHR Loop I using 3A RHR Pump was in shutdown cooling. Unit 1 is carrying 2000 gpm for RHRSW Pumps A2 and C2.

An inadvertent loss of 3B RPS bus resulted in a partial isolation of RHR shutdown cooling. RPS 3B has been restored on the alternate supply. Another operator is assisting with recovery from the loss of 3B RPS. An Auxiliary Operator is standing by for 3A RHR Pump start.

INITIATING CUES: The Unit Supervisor directs you to restore shutdown cooling using 3A RHR pump in accordance with 3-AOI-74-1 starting at step 9.

JPM f

PAGE 4

OF 9

START TIME Performance Step 1:

Critical Not Critical X

[9]

IF the loss of Shutdown Cooling is due to Group 2 PCIS isolation, THEN (Otherwise N/A)

WHEN conditions permit resetting Group 2 PCIS isolation are met, PERFORM the following:

[9.1]

RESET Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 3-HS-64-16A-S32, and PCIS DIV II RESET, 3-HS-64-16A-S33, in reset.

Standard:

On Panel 3-9-4, RESETS Group 2 isolation by momentarily PLACING PCIS DIV I RESET, 3-HS-64-16A-S32, in reset and PCIS Div II RESET, 3-HS-64-16A-S33 to reset.

SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 2:

Critical Not Critical X

[9.2]

MOMENTARILY DEPRESS RHR SYS 1(11) SD CLG INBD INJECT ISOL RESET, 3-XS-74-126 and 3-XS-74-132. VERIFY 3-IL-74-126 and 3-IL-74-l 32 extinguished.

Standard:

Momentarily Depresses RHR SYS I SD CLG INBD INJECT ISOL RESET, 3-XS-74-132 and verifies 3-IL-74-132 extinguished.

SAT_ UNSAT N/A COMMENTS:_____________________________

JPM t

PAGE 5

OF 9

Performance Step 3:

Critical Not Critical X

[10]

IF the loss of Shutdown Cooling is due to Group 2 PCIS AND the isolation signal fails to reset, or remain reset due to invalid and/or sporadic signals, THEN (Otherwise N/A)

Standard:

N/As all Step 4.2[10], the PCIS signal is reset in step 9.

SAT UNSAT N/A COMMENTS:____________________________

Performance Step 4:

Critical X Not Critical

[11]

IF the Group 2 PCIS Isolation has been reset, THEN (otherwise N/A)

RETURN the affected loop of RHR to Shutdown Cooling as follows:

[11.1] CLOSE RHR SYS I LPCI OUTBD iNJECT VALVE, 3-FCV-74-52.

Standard:

Closes 3-FCV-74-52 SAT_ UNSAT N/A _COMMENTS:_____________________________

Performance Step 5:

Critical Not Critical X

[11.2] OPEN RHR SYS I LPCI INBD iNJECT VALVE, 3-FCV-74-53.

Standard:

Opens 3-FCV-74-53 SAT UNSAT N/A COMMENTS:_____________________________

JPM f

PAGE 6

OF 9

Performance Step 6:

Critical Not Critical

[11.3] VERIFY RHR SYSTEM I M1N FLOW INHIBIT switch, 3-HS-74-148 in iNHIBIT Standard:

Verifies 3-HS-74-148 in INHIBIT.

SAT UNSAT N/A COMMENTS:________________________________

Performance Step 7:

Critical Not Critical X

[11.4] VERIFY CLOSED RHR SYSTEM I MIN FLOW VALVE, 3-FCV-74-7.

Standard:

Verifies 3-FCV-74-7 is closed.

SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 8:

Critical Not Critical

[11.5] VERIFY CLOSED RHR PUMP 3A and 3C SUPPR POOL SUCT VLVs, 3-FCV-74-1 and 3-FCV-74-12.

Standard:

Verifies 3-FCV-74-1 & 12 are closed.

SAT_ UNSAT N/A COMMENTS:_____________________________

JPM f

PAGE 7

OF 9

Performance Step 9:

Critical Not Critical X

[11.6] VERIFY OPEN RHR PUMP 3A and 3C SD COOLING SUCT VLVs, 3-FCV-74-2 and 3-FCV-74-13.

Standard:

Verifies 3-FCV-74-2 & 13 are open.

SAT U1\\TSAT N/A COMMENTS:_____________________________

Performance Step 10:

• Critical X Not Critical

[11.7] OPEN RHR SHUTDOWN COOLING SUCT OUTBD and INBD ISOL VLVs, 3-FCV-74-47 and 3-FCV-74-48.

Standard:

Opens *3..Hs7447 and verifies 3-FCV-74-48 open.

SAT_ UNSAT N/A COMMENTS:______________________________

Performance Step 11:

Critical X Not Critical

[11.8] RESTART RHR PUMP 3A using 3-HS-74-5A.

Standard:

Starts 3A RHR Pump SAT UNSAT N/A COMMENTS:

RHR Pump Start Time

JPM f

PAGE 8

OF 9

Performance Step 12:

Critical X Not Critical

[11.9] THROTTLE RHR SYS I LPCI OUTBD iNJECT VALVE, 3-FCV-74-52, to establish and maintain RHR flow as indicated by 3-FI-74-50, RHR SYS I FLOW, as follows:

RHR Pumps in 1

2 Operation Loop Flow 7,000 to 10,000 gpm 14,000 to 20,000 gpm Loop Flow (1 or more fuel 6,000 to 6,500 gpm N/A bundles removed from_core)

Standard:

Manipulates 3-HS-74-52 to obtain RHR System I Loop flow between 7,000 and 10,000 gpm on 3-FI-74-50.

SAT UNSAT N/A COMMENTS:______________________

RHR Flow Established Time RHRSYSTEM Mmimum.Flow Guidane Jo mihhiizesystenvi 6

ration3 RBRpuinp operatiot shouldbe iiniizedbebi

,Ogppot aovp1O rjr than 3s4inwmfló

JPM f

PAGE 9

OF 9

Performance Step 13:

Critical Not Critical

[11.10] WHEN time permits after RHR pump is started, THEN VERIFY RHR Pump Breaker charging spring recharged by observing amber breaker spring charged light is on and closing spring target indicates charged.

Standard:

Dispatched personnel to verify RHR Pump 3A breaker closing spring recharged.

SAT UNSAT N/A COMMENTS:_______________________________

CUE. Ifrequested, Acknowledge and state Operator inrutç Performance Step 14:

Critical Not Critical

[11.11] SLOWLY THROTTLE RHR HX 3A RHRSW OUTLET VALVE, 3-FCV-23-34, to obtain desired cooldown rate.

Standard:

Throttles 3-FCV-23-34 open to commence cooldown SAT UNSAT N/A _COMMENTS:_____________________________

I CUE: That completes this task.

END OF TASK STOP TIME:

JPM g

PAGE1OF8 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 MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

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

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

JPM g

PAGE 3

OF 8

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

INITIAL CONDITIONS: You are an Operator. The Unit 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

PAGE 4 OF 8

START TIME____

Performance Step 1:

Critical X Not Critical 1.

OPEN the following valves:

O-FCV-84-5, CAD SYSTEM AN2 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 2.

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

Standard:

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

SAT UNSAT N/A _COMMENTS:_____________________________

JPM g

PAGE 5

OF 8

Performance Step 3:

• Critical Not Critical

• 3*

PLACE keylock switch 2-HS-84-48, CAD A CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 2, Panel 9-54) 4.

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

Standard:

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

Performance Step 4:

• Critical Not Critical

• 5 PLACE keylock switch 2-HS-84-49, CAD B CROSS TIE TO DW CONTROL AIR, in OPEN (Unit 2, Panel 9-55) 6.

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

Standard:

Places keylock switch 2-HS-84-49 in Open and verifies 2-FSV-84-49 open SAT UNSAT_ N/A COMMENTS:______________________________

JPM g

PAGE 6

OF 8

Performance Step 5:

Critical 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, Win. 18) still in Alarm (would Not clear) and continues with procedure.

SAT UNSAT N/A _COMMENTS:_____________________________

Performance Step 6:

Critical Not Critical X 8.

IF MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 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-84-5 1, 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-84-5 1 and 2-PI-84-50 for low pressure.

SAT UNSAT N/A COMMENTS:______________________________

CUE: DO NOT Report Unless directed by NRC [reportj 2-PI-84-51, CAD N2 Pressure to DWCA indicator, for CAD A is reading 110 psig. 2-PI-84-50 for CAD B is reading 5 psig.

JPM g

PAGE 7

OF 8

Performance Step 7:

Critical X Not Critical b.

MONITOR 0-FI-84-7(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 scfl and 0-FI 18 flow 90 scfi 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:_________________________________

JPM g

PAGE 8

OF 8

Performance Step 9:

Critical Not Critical X 9.

IF Drywell Control Air header supplied from CAD System A shows indications ofbeing 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 ofbeing depressurized SAT UNSAT N/A _COMMENTS:_____________________________

Performance Step 10:

Critical Not Critical 10.

IF Drywell Control Air header supplied from CAD B shows indications ofbeing 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

JPM g

PAGE 1 OF 8

OPERATOR:____________________

RO___

SRO DATE:

JPM NUMBER:

g TASK NUMBER:

U-000-EM-74 TASK TITLE:

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

LOCATION OF PERFORMANCE:

Simulator REFERENCES/PROCEDURES NEEDED:

3-EOI Appendix-8G VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

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

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

JPM g

PAGE 3

OF 8

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

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

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

JPM g

PAGE 4

OF 8

START TIME Performance Step 1:

Critical Not Critical 1.

OPEN the following valves:

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

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

Standard:

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

Performance Step 2:

Critical Not Critical X 2.

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

Standard:

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

SAT UNSAT N/A COMMENTS:_____________________________

JPM g

PAGE 5 OF 8

Performance Step 3:

• Critical 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 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 AR (Unit 3, Panel 3-9-55)

Standard:

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

JPM g

PAGE 6 OF 8

Performance Step 5:

Critical 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, Win. 18) still in Alarm (would NOT clear) and continues with procedure.

SAT UNSAT N/A _COMMENTS:_______________________________

Performance Step 6:

Critical Not Critical 8.

IF MAIN STEAM RELIEF VLV AIR ACCUM PRESS LOW, 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 1NDR, 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 [reportj 3-PI-84-5 1, CAD N2 Pressure to DWCA indicator, for CAD A is reading 110 psig and 3-PI-84-50 reading 5 psig.

JPM g

PAGE 7

OF 8

Performance Step 7:

Critical Not Critical b.

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

Standard:

Recognizes 0-FI-84-7/3 flow is 0 scfrn and that 0-FI 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 JJNE 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-l-51, MSIV LINE D INBOARD Performance Step 8:

Critical Not Critical c.

MONITOR inboard MSIV indication status for valves drifting closed.

Standard:

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

JPM g

PAGE 8

OF 8

Performance Step 9:

Critical Not Critical X 9.

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

0-FCV-84-16, CAD SYSTEM B N2 SHUTOFF VALVE (Unit 3, Panel 3-9-55) 3-FSV-84-49, CAD B CROSS TIE TO DW CONTROL AIR (Unit 3, Panel 3 55)

Standard:

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

STOP TIME____

END OF TASK

JPM h

PAGE 1

OF S

OPERATOR:_______________________

RO SRO DATE:

JPM NUMBER:

h TASK NUMBER:

U-090-NO-03 TASK TITLE:

Bypassing Radiation Monitors on Workstation Touch Screen K/A NUMBER:

272000 A4.02 K/A RATING: RO 3.0 SRO 3.0 TASK STANDARD: Radiation Monitors 3-RM-90-59 and 3-RM-90-51 bypassed lAW 3-01-90 section 6.3.10.

LOCATION OF PERFORMANCE:

Simulator REFERENCES/PROCEDURES NEEDED:

3-01-90 VALIDATION TIME: 5 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS:

You are a Unit Operator. The condition of alarms and indications on Radiation Monitors on the 3-MON-90-50 Workstation are being addressed by the Unit Supervisor.

INITIATING CUE:

The Unit Supervisor directs you to bypass Radiation Monitors 3-RM-90-59 and 3-RM-90-51, in accordance with 3-01-90 Radiation Monitoring System section 6.3.10.

JPM h

PAGE 3

OF 6

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

INITIAL CONDITIONS:

You are a Unit Operator. The condition of alarms and indications on Radiation Monitors on the 3-MON-90-50 Workstation are being addressed by the Unit Supervisor.

INITIATING CUE:

The Unit Supervisor directs you to bypass Radiation Monitors 3-RM-90-59 and 3-RM-90-51, in accordance with 3-01-90 Radiation Monitoring System section 6.3.10.

JPM h

PAGE 4

OF 6

START TIME____

Performance Step 1:

Critical Not Critical X 6.3.10 Bypassing Radiation Monitors on Workstation Touch Screen

[1]

NOTIFY Unit Supervisor of the radiation monitor(s) to be bypassed.

Standard:

Notifies the Unit Supervisor which radiation monitors will be bypassed.

SAT_ UNSAT N/A COMMENTS:___________________

f CUE: AcknodgNoffiction I

Performance Step 2:

Critical Not Critical X

[2]

REVIEW Precautions and Limitations listed in Section 3.0 Standard:

Reviews Precautions and Limitations SAT UNSAT N/A COMMENTS:_____________________________

Performance Step 3:

Critical Not Critical X

[3]

IF 3-RM-90-256, Drywell Air Monitor, is being bypassed, THEN REFER to Technical Specifications 3.4.5, 3.4.4 and 3.6.1.3.

Standard:

Step is NA, 3-RM-90-256 is not being bypassed.

SAT UNSAT N/A COMMENTS:___________________________

JPM h

PAGE 5

OF 6

Performance Step 4:

Critical X Not Critical

[4]

Using Air Particulate Monitor Controller, 3-MON-90-50, SELECT Bypass CAM(s).

Standard:

Selects Bypass Cams on 3-MON-90-50 SAT_ UNSAT N/A _COMMENTS:______________________________

Performance Step 5:

Critical X Not Critical

[5]

WHEN the Channel Bypass window appears, THEN use the toggle switches to place the desired CAM in BYPASS (red indicator will change to green).

Standard:

Selects radiation monitors 3-RM-90-59 and 3-RM-90-5 1 for Bypass SAT UNSAT N/A _COMMENTS:____________________________

Performance Step 6:

Critical X Not Critical

[6]

WHEN desired CAMS have been toggled to bypass, then SELECT Set Bypass Config.

Standard:

Selects Set Bypass Configuration SAT_ UNSAT N/A COMMENTS:____________________________

JPM h

PAGE 6

OF 6

Performance Step 7:

Critical Not Critical X

[7]

VERIFY the CAMs selected for bypass now have a beige border around the CAM on the main display screen.

Standard:

Verifies radiation monitors 3-RM-90-59 and 3-RM-90-51 are bypassed SAT UNSAT N/A COMMENTS:______________________________

Performance Step 8:

Critical Not Critical X

[8]

NOTIFY Chemistry and/or RADCON to begin sampling affected systems at the required frequency.

Standard:

Notifies Radcon SAT UNSAT N/A _COMMENTS:_______________________________

CUE; AomowJedgeNtifieati9n END OF TASK STOP TIME

JPM

+/-

PAGE 1

OF 7

OPERATOR:________________________

RU___

SRO___

DATE:

JPM NUMBER:

i TASK NUMBER:

U-000-EM-19 TASK TiTLE:

2-EOI Appendix-lA Removal of RPS SCRAM Fuses KJA NUMBER: 212000 A2.20 KJA RATiNG: RU 4.1 SRO 4.2 TASK STANDARD: Simulate removal of SCRAM Fuses lAW 2-EOI Appendix-lA LOCATION OF PERFORMANCE:

Plant REFERENCES/PROCEDURES NEEDED:

2-EOI Appendix-lA VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS: You are the Extra Operator. The Unit 2 reactor has scrammed and all control rods did not fully insert. All eight scram solenoid lights on Panel 9-5 are still illuminated.

EOI-1 has been entered and followed to RC/Q-23. The Scram Discharge Volume VenffDrain 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 ofRPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM

+/-

PAGE 3

OF 7

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

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

INITIAL CONDITIONS: You are the Extra Operator. The Unit 2 reactor has scrammed and all control rods did not fully insert. All eight scram solenoid lights on Panel 9-5 are still illuminated.

EOI-l has been entered and followed to RC/Q-23. The Scram Discharge Volume Vent/Drain Valves indicate closed on panel 2-9-5.

INITIATING CUE: The Unit Supervisor directs you to remove the RPS scram solenoid fuses in accordance with 2-EOI Appendix 1A, Removal and Replacement of RPS Scram Solenoid Fuses.

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM

+/-

PAGE 4

OF 7

START TIME____

Performance Step 1:

Critical Not Critical 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:____________________________

JPM

+/-

PAGE 5

OF 7

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 ofterminal 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:

Vien location ofjropefRuse is indicateaheFusehas beenremoved

JPM

+/-

PAGE 6

OF 7

Performance Step 4:

Critical X Not Critical d.

LOCATE Terminal Strip CC inside Panel 9-17, Bay 2, Rear.

e.

REMOVE the following fuses (located at bottom of tenninal 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:

W4inlocation ofproper1use is indicate&the Fiishas beenemoved

JPM

+/-

PAGE 7

OF 7

Performance Step 5:

Critical Not Critical 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:

Aeknoy)e4ge Notification, SRO Does not direct replacementoffusçs END OF TASK STOP TIME____

JPM j

PAGE 1

OF 9

OPERATOR:

RO___

SRO___

DATE:

JPMN1JMBER:

j TASK NUMBER:

U-001-AL-06 TASK TITLE:

Field actions for stuck open SRV KIA NUMBER: 239002 A2.03 KIA RATING: RO 4.1 SRO 4.2 TASK STANDARD: Stuck Open SRV is closed when power is removed from the SRV by opening the breakers LOCATION OF PERFORMANCE:

Plant REFERENCES/PROCEDURES NEEDED:

2-AOl-1-1 VALIDATION TIME: 25 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME:

COMMENTS:______________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

IMTIAL CONDITIONS: You are an Operator, the Unit Supervisor has entered 2-AOl-i-i Relief Valve Stuck Open. Control Room actions to close SRV 2-PCV-i-22 have been unsuccessful. Reactor Power is 85%.

INITIATING CUE: The Unit Supervisor directs you to attempt to close SRV 2-PCV-l-22 from outside the Control Room in accordance with 2-AOl-i-i step 4.2.3[2].

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM j

PAGE 3

OF 9

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

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

INITIAL CONDITIONS: You are an Operator, the Unit Supervisor has entered 2-AOl-i-i Relief Valve Stuck Open. Control Room actions to close SRV 2-PCV-i-22 have been unsuccessful. Reactor Power is 85%.

INITIATING CUE: The Unit Supervisor directs you to attempt to close SRV 2-PCV-i-22 from outside the Control Room in accordance with 2-AOl-i-i step 4.2.3[2].

CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM j

PAGE 4

OF 9

START TIME____

Performance Step 1:

Critical Not Critical X NOTES 1) 2-PCV-l-22 is an ADS Valve 2) 2-PCV-1-22 has two power supplies, it will auto transfer on loss ofpower and is Normal Seeking.

3) may be addressed for fuse and breaker information.

[2]

IF 2-PCV-l-22 is NOT closed, THEN PERFORM the following:

[2.1]

On Panel 2-25-32 PLACE the associated transfer switch MAIN STM LINE B RELIEF VALVE XFR, 2-XS-1-22 in EMERG position.

Standard:

Simulate placing 2-XS-l-22 in emergency SAT_ UNSAT N/A COMMENTS:___

CUE:

When iimülated 2-XS4-22 isin Emergency. When ControLRoom called SRV remains OPEN.

JPM j

PAGE 5

OF 9

Performance Step 2:

Critical Not Critical X

[2.2]

IF the SRV does NOT close, THEN PERFORM the following while OBSERVING the indications for the 2-PCV-l-22 on the Acoustic Monitor:

CYCLE the MAIN STM LINE B RELIEF VALVE, 2-HS-1-22C to the following positions several times.

CLOSE/AUTO to OPEN to CLOSE/AUTO Standard:

Simulates cycling 2-HS-l-22C from CLOSE/AUTO to OPEN to CLOSE/AUTO SAT_ UNSAT N/A COMMENTS:______________________________

f CUE:

The SkYremains opn Performance Step 3:

Critical Not Critical X

[2.3]

IF the SRV does NOT close, THEN PERFORM the following:

A.

VERIFY the MAIN STM LINE B RELIEF VALVE, 2-HS-l-22C, in the CLOSE/AUTO position.

B.

PLACE the associated transfer switch MAIN STM LINE B RELIEF VALVE XFR, 2-XS-l-22 in NORM position.

Standard:

Simulates verifying 2-HS-1-22C is in Close/Auto and simulates placing 2-XS-l-22 in Norm SAT_ UNSAT N/A COMMENTS:_____________________________

CUE:

2-XS-l -22 is in Norm

NRC NOTE IF BREAKERS are USED JPM j

PAGE 6

OF 9

Performance Step 4:

Critical X Not Critical

[2.4]

IF the SRV does NOT close, THEN REMOVE the power from 2-PCV-1--22 by performing one of the following: (Opening breakers are the preferred method)

A.

OPEN the following breakers: (Preferred method) 2A 250V RMOV, Compartment 11 C2 CUE:

11C2 at 2A 250V RMOV is open.

• 2B 250V RMOV, Compartment 1C1 CUE:

IC1 at 213 25OVRMOV is open.

SRV 1-22 is closed.

17Operatorsimu1ates 1oshgbreakers breakers areclose4 SRS/is Open. 3PM Fabre Standard:

Simulates opening Compartment 11C2 at 2A 250V RMOV and Compartment 1C1 at 2B 250V RMOV SAT UNSAT N/A COMMENTS:

JPM j

PAGE 7

OF 9

Performance Step 5:

Critical Not Critical X

[2.5]

IF the valve does NOT close, THEN CLOSE the breakers or REINSTALL fuses removed in Step 4.2.3[2.4].

CUE:

If Operator simulates closing breakers, breakers are closed. SRV 1-22 is Opeu. JPM Failure Standard:

SRV Closed Operator does NOT close breaker, Step is NA SAT_ UNSAT N/A COMMENTS:_____________________________

IF BREAKERS ARE OPENED THAN THE JPM IS COMPLETE STOP TIME____

END OF TASK

JPM j

PAGE 8

OF 9

NRC NO1E are USJFD Performance Step 6:

Critical X Not Critical B. In Panel 2-25-32 PULL the following fuses as necessary

• Fuse 2E-F6E (Block EE, F 15)

• Fuse 2E-F4E (Block EE, F7)

CUE:

Fuse 2E-F6E is PULLED Fuse 2E-F4E is PULLED If Oeratox simitats installing fuse fuses are $nstalled. S1V. 1-22 is Open. 3PM Failure Standard:

Simulates pulling fuses: Fuse 2E-F6E and Fuse 2E-F4E SAT UNSAT N/A _COMMENTS:___________

JPM j

PAGE 9 OF 9

Performance Step 7:

Critical Not Critical

[2.5]

IF the valve does NOT close, THEN CLOSE the breakers or REINSTALL fuses removed in Step 4.2.3[2.4].

If Operator simulates installing fuses, fuses are installed. SRV 1-22 is Open.JPM Failure CUE:

Standard:

SRV Closed Operator does NOT install fuses, Step is NA SAT_ UIJSAT N/A COMMENTS:_____________________________

IF FUSES ARE REMOVED THAN THE JPM IS COMPLETE STOP TIME____

END OF TASK

JPM k

(16+/- op6)

PAGE1OF9 OPERATOR:______________________

RO___

SRO___

DATE:

JPM NUMBER:

k (16 op6)

TASK NUMBER:

U-000-SS-08 TASK TITLE:

Align 480V RMOV BD 3B for a fire and Start RHR Pump 3A KJA NUMBER: 600000 AA2.16 K/A RATING: RO 10 SRO: 15 TASK STANDARD: Operator 6 Manual Actions 0-SSI-16 section 2.0 and 3.0 completed LOCATION OF PERFORMANCE:

Plant REFERENCES/PROCEDURES NEEDED:

0-SSI-16 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: 20 minutes for section 2.0 and 120 minutes for section 3.0.

PERFORMANCE TIME:

COMMENTS:_____________________________

Additional comment sheets attached? YES NO RESULTS:

SATISFACTORY___

UNSATISFACTORY SIGNATURE:

DATE:

EXAMINER

INITIAL CONDITIONS: You are Operator 6, the plant is operating in 0-SSI-16 Control Building Fire EL 593 Through EL 617. Operator 6 Manual Actions Section 1.0 is complete.

INITIATING CUE: The Unit Supervisor directs you as Operator 6 to continue Attachment 6 at section 2.0 of 0-SSI-16.

Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k

(16 op6)

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

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

INITIAL CONDITIONS: You are Operator 6, the plant is operating in 0-SSI-l6 Control Building Fire EL 593 Through EL 617. Operator 6 Manual Actions Section 1.0 is complete.

INITIATING CUE: The Unit Supervisor directs you as Operator 6 to continue Attachment 6 at section 2.0 of 0-SSI-16.

Time Critical CAUTION: DO NOT OPERATE ANY PLANT EQUIPMENT!

JPM k

(16 op6)

PAGE 4 OF 9

START TIME____

Performance Step 1:

Critical Not Critical 2.0 480V REACTOR MOV BOARD 3B ALIGNMENT (20 Mm)

[1]

Notification has been received from the Unit 3 Unit Supervisor to perform this section.

[2]

PERFORM the following to align 480V Reactor MOV Board 3B:

[2.1]

PROCEED TO Compt 2A, AND PLACE NORMAL FEEDER CONTROL SWITCH, 3-HS-268B/2A-A, in TRIP.

3-HS.268BI2A-A is in Trip, Green light On Red light Off j CUE:

[2.2]

PROCEED TO Compt 16A, AND PLACE EMERGENCY FEEDER CONTROL SWITCH, 3-HS-268-B/16A-A, in CLOSE.

CUE:

3-HS-268-BI16A-Ais in Close, Red light On Green Light Off Standard:

Simulates placing 3-HS-268B/2A-A in Trip and 3-HS-268-B/16A-A in Close SAT_ UNSAT N/A COMMENTS:_____________________________

JPM k

(16 op6)

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Performance Step 2:

• Critical X Not Critical

[2.3]

PROCEED TO Compt 1C, AND PERFORM the following:

• [23l]

PLACE RCIC STM LiNE EMER TRANS SWITCH 3-XS-071-0002, in EMERG.

[2.3.2]

VERIFY OPEN RCIC STM LINE 1NBD ISOL VALVE, 3-HS-071-0002B.

CUE:

3-XS-Q71-OOO2 is in Emergency and RCICStcanttine hiboard Isolation Valve has RedLight Oil, Green Light Off Standard:

Simulates placing 3-XS-071-0002 in Emergency and verifies RCIC STM LINE INBD ISOL VALVE Open SAT UNSAT N/A COMMENTS:______________________________

Performance Step 3:

Critical X Not Critical

[2.4]

PROCEED TO Compt 4C, AND PLACE O-BKR-084-0016A CONTAINMENT ATMOSPHERE DILUTION SYSTEM B HEATER, breaker in OFF.

j CUE:

O-BKR-084-0016A is in Off Standard:

Simulates placing O-BKR-084-0016A in Off SAT_ UNSAT N/A COMMENTS:_____

STOP TiME____

JPM k

(16 op6)

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Performance Step 4:

Critical Not Critical X

[3]

NOTIFY Unit 3 Unit Supervisor of completion of this section.

[4]

PROCEED TO 4160V Shutdown Board 3EA in preparation of performing Section 3.0.

Standard:

Notifies Unit 3 Unit Supervisor and proceeds to 4160 SD BD 3EA SAT UNSAT N/A COMMENTS:_____________________________

CUE; Acknowledge notification arid Notify Operator to perform section 3.0

JPM k

(16 op6)

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START TIME____

Performance Step 5:

• Critical Not Critical 3.0 RHR PUMP 3A LOCAL START (120 Mm)

[1]

Notification has been received from the Unit 3 Unit Supervisor to perform this section.

NOTE If RHR pump fails to start, pushbutton on breaker must be used.

[2]

PROCEED TO 4160V Shutdown Board 3EA, Compt 12, 3-BKR-074-0005 RHR PUMP 3A, AND PERFORM the following:

• [2.1] PLACE RHR PUMP 3A TRANSFER, 3-43-074-0005, in EMERG.

f CUE:

343-O74-OOO5 is in Emergency

[2.2]

PLACE RHR PUMP 3A, 3-HS-074-0005C, in CLOSE.

[2.3]

VERIFY RHR Pump 3A has started by observing breaker AMMETER indications.

CUE:

3-HS-O74-O005Cis in CIos No AMPS are indieated Reduight OF, Green LigI On Yellow light remaineL On.

If asked No breaker trips ar inicated.,

Standard:

Simulates placing 3-43-074-0005 in Emergency and 3-HS-074-0005C in Close SAT_ UNSAT N/A COMMENTS:_____________________________

JPM k

(16 op6)

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Performance Step 6:

• Critical Not Critical 3.0 RHR PUMP 3A LOCAL START (120 Mm)

• NOTE

• IfpJIR pump fails to start, pushbutton on breaker must be used.

CUE:

Breaker 3-BKR-074-0005 pushbutton is depressed

[2]

PROCEED TO 4160V Shutdown Board 3EA, Compt 12, 3-BKR-074-0005 RHR PUMP 3A, AND PERFORM the following:

[2.3]

VERIFY RHR Pump 3A has started by observing breaker AMMETER indications.

CUE:

AMPS pegged high, Red light ON and Green Light OFF Breaker CLOSED, current AMP reading is 180 AMPS Standard:

Simulates depressing pushbutton on 3-BKR-074-0005 and verifies Amps SAT_ UNSAT_ N/A COMMENTS:_____________________________

STOP TIME____

JPM k

(16 op6)

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Performance Step 7:

Critical Not Critical X

[3]

NOTIFY Unit 3 Unit Supervisor ofthe completion of this section.

[4]

PROCEED TO 4160 Shutdown Board A in preparation ofperforming Section 4.0.

Standard:

Notifies Unit 3 Unit Supervisor SAT_ UNSAT N/A COMMENTS:

CUE:

AnotherOperator will continue with section 4.0 END OFTASK