ML053330017

CNS - 06-2005 - Initial Final Ro/Sro Admin Examination

ML053330017
Person / Time
Site:	Cooper
Issue date:	06/27/2005
From:	Nebraska Public Power District (NPPD)
To:	Office of Nuclear Reactor Regulation
References
Download: ML053330017 (206)

Text

Nebraska Public Power District SKL034-11-106 (16527)

Cooper Nuclear Station Page 1 of 7 Job Performance Measure for Operations Revision 00 Task No.:

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Task

Title:

Verify Valve Positions (Mockup) (ALT Path)

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Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

NOTE: This is an ALTERNATE PATH JPM requiring the student to identify a valve out of position, report the valve to the CRS and correct the mis-positioned valve.

Additional Program Information:

1. Appropriate Performance Locations: MTF Mockup Facility

2. Appropriate Trainee Levels: SO / RO / SRO

3. Evaluation Method: Simulate Perform

4. Performance Time: 15 minutes

5. NRC K/A:

Directions to Examiner:

1. The Instructor will have to insure that the valves are aligned properly prior to presenting this JPM.

The TM-10 should be closed prior to starting this JPM, which is the wrong position according to the valve lineup. The other valves should be in their correct alignment.

2. This JPM evaluates the trainee's ability to determine the position of two different types of valves.

3. Give the trainee his copy of the Directions to the Trainee (Attachment 1) and Attachment 2 TM Valve Lineup when ready to start the JPM.

4. Brief the trainee and tell the trainee to begin.

5. All blanks must be filled out with either initials or an "NP" for "not performed", and an explanation may also be written in the space if desired by the examiner.

NOTE: This JPM requires the instructor to position the valves on Attachment 2 to the desired position prior to performing this JPM.

Directions to Trainee:

When I tell you to begin, you are to complete the valve lineup on the TM system. The Valve lineup is partially completed and only requires three valves to be checked. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.

You are to notify the CRS when you have completed the lineup.

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General Conditions:

Nebraska Public Power District SKL034-11-106 (16527)

Cooper Nuclear Station Page 2 of 7 Job Performance Measure for Operations Revision 00 Task No.:

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Task

Title:

Verify Valve Positions (Mockup) (ALT Path)

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1. The plant is at rated power.

2. There are three valves on the attached lineup that still need to be verified.

3. The valves are located in a non-radioactive and non-contaminated area.

General

References:

1. Attachment 2, TM System Valve Lineup

2. Procedure 0.31, Equipment Status Control General Tools and Equipment:

1. Gloves

2. Hardhat

3. Safety Glasses Special Conditions, References, Tools, Equipment:

4. Critical checks denoted by "*".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

The CRS has directed you to complete Attachment 2, TM System Lineup and report when you have completed that lineup.

Nebraska Public Power District SKL034-11-106 (16527)

Cooper Nuclear Station Page 3 of 7 Job Performance Measure for Operations Revision 00 Task No.:

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Task

Title:

Verify Valve Positions (Mockup) (ALT Path)

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Performance Checklist Standards Initial NOTE: The valves to be verified are in classroom 7 of the MTF. The piping and valves are located on the mockup.

NOTE: Any order can be used while performing the lineup.

1. Obtain a copy of Attachment Obtains a copy of Attachment 2.

2.

2. Note that the three valves are Notes that the three valves are TM-V20, TM-V22 not signed off on the list. and TM-V11.

3. Locates first valve TM-V20. The operator locates TM-V20 on the piping mockup.

4. Verifies valve tag versus the The operator verifies that the valve number is lineup sheet. correct with the lineup sheet (Attachment 2)

5. Takes valve handwheel to The operator rotates the handwheel in the closed. clockwise direction enough to verify stem movement. *

6. Takes valve handwheel to The operator rotates the valve handwheel in the open direction. counterclockwise direction until the valve is on the backseat. *

7. Takes valve handwheel to The operator rotates the valve handwheel in the closed direction. clockwise direction until the valve is off the backseat. _______

8. Signs off Attachment 2. The operator signs off Attachment for TM-V20.

9. Locates next valve TM-V22. The operator locates TM-V22 on the piping mockup.

Nebraska Public Power District SKL034-11-106 (16527)

Cooper Nuclear Station Page 4 of 7 Job Performance Measure for Operations Revision 00 Task No.:

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Task

Title:

Verify Valve Positions (Mockup) (ALT Path)

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Performance Checklist Standards Initial

10. Verifies valve tag versus the The operator verifies that the valve number is lineup sheet. correct with the lineup sheet (Attachment 2)

11. Takes valve handwheel to The operator rotates the handwheel in the closed. clockwise direction without excessive force and verifies no movement. *

12. Takes valve handwheel to The operator rotates the valve handwheel in the open direction. counterclockwise direction until the handwheel is free moving.

13. Signs off Attachment 2. The operator signs off Attachment for TM-V22.

14. Locates last valve TM-V10. The operator locates TM-V10 on the piping mockup.

15. Verifies valve tag versus the The operator verifies that the valve number is lineup sheet. correct with the lineup sheet (Attachment 2)

NOTE: The operator my notice that the valve indicates that it is closed before operating it and may call the CRS for direction on how to proceed.

CUE: As the CRS tell the operator to proceed with the lineup and when he is done the CRS will ensure that a notification is written to document the problem if one is found.

16. Takes valve handwheel to The operator rotates the handwheel in the closed. clockwise (Closed) direction and with normal force and notices that the handwheel and stem did not

• move. He may call the control room for direction on how to proceed.

CUE: If called, as the CRS tell the operator to proceed with the lineup and when he is done the CRS will ensure that a notification is written to document the problem.

17. Takes valve handwheel to The operator rotates the valve handwheel in the open direction. counterclockwise direction until the valve is on the backseat.

• Nebraska Public Power District SKL034-11-106 (16527)

Cooper Nuclear Station Page 5 of 7 Job Performance Measure for Operations Revision 00 Task No.:

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Task

Title:

Verify Valve Positions (Mockup) (ALT Path)

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Performance Checklist Standards Initial

18. Takes valve handwheel to The operator rotates the valve handwheel in the closed direction. clockwise direction until the valve is off the backseat.

19. Signs off Attachment 2. The operator signs off Attachment for TM-V10 and notes a discrepancy in the comment section.

20. Notifies the CRS when the The operator contacts the CRS when he has lineup is completed. completed the Lineup.

CUE: As the CRS respond to the report.

NOTE: Examiner have the student reposition TM-V10 to the CLOSED position to set this JPM up for the next person.

Nebraska Public Power District SKL034-11-106 (16527)

Cooper Nuclear Station Page 6 of 7 Job Performance Measure for Operations Revision 00 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to complete the valve lineup on the TM system. The Valve lineup is partially completed and only requires three valves to be checked. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.

You are to notify the CRS when you have completed the lineup.

General Conditions:

1. The plant is at rated power.

2. There are three valves on the attached lineup that still need to be verified.

3. The valves are located in a non-radioactive and non-contaminated area.

Initiating Cue(s):

The CRS has directed you to complete Attachment 2, TM System Lineup and report when you have completed that lineup.

Nebraska Public Power District SKL034-11-106 (16527)

Cooper Nuclear Station Page 7 of 7 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 VALVE CONTROL NORMAL PERFORMED NUMBER DESCRIPTION LOCATION LOCATION POSITION BY COMMENTS TM -V17 TM Pump suction TM Skid Local Closed MAB TM discharge TM -V18 TM Skid Local Closed MAB isolation TM -V19 TM Pump suction TM Skid Local Closed MAB TM upstream TM -V20 TM Skid Local Open isolation TM downstream TM -V22 TM Skid Local Closed isolation TM Skid -

TM keep fill TM -V10 above TM Local Open isolation V21 TM Skid -

TM -V11 TM keep fill drain above TM Local Closed MAB V21 Initials Printed Name Initials Printed Name MAB / Michael A. Barton /

/ /

/ /

Nebraska Public Power District SKL034-20-19 (2121)

Cooper Nuclear Station Page 1 of 8 Job Performance Measure for Operations Revision 08 Task No.: 215040A0101

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Task

Title:

Perform APRM Gain Adjustment (With a Valid CTP) for Single Loop (Alternate Path)

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Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: SIM

2. Appropriate Trainee Level: RO/SRO

3. Evaluation Method: Perform

4. Performance Time: 15 min

5. NRC K/A 215005 A1.07(3.0.3.4)

Directions to Examiner:

NOTE: THIS IS A FAULTED JPM. APRM D GAF WILL NOT ADJUST.

1. This JPM evaluates the trainee's ability to perform APRM calibration with a valid CTP available with only one RR loop in operation.

2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.

3. Observe the trainee during performance of the JPM for proper use of self-checking methods.

4. All blanks must be filled out with either initials or an NP for not performed.

5. Brief the trainee, place the simulator in run, and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to perform APRM gain adjustment with a valid CTP available with only one RR loop in operation. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them to perform APRM gain adjustment with a valid CTP available with only one RR loop in operation. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

General Conditions:

1. Recirc Pump B has been secured IAW SOP 2.2.68.1 for rebrushing the RRMG set.

Nebraska Public Power District SKL034-20-19 (2121)

Cooper Nuclear Station Page 2 of 8 Job Performance Measure for Operations Revision 08 Task No.: 215040A0101

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Task

Title:

Perform APRM Gain Adjustment (With a Valid CTP) for Single Loop (Alternate Path)

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General

References:

1. Procedure 10.1 General Tools and Equipment:

1. Small screwdriver

2. NPP 10.1, Attachment 2 and 4 Special Conditions, References, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

2. Critical checks denoted by "*".

3. Simulator cues denoted by "#".

4. Faulted steps denoted by ".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

Conditions have stabilized since securing Recirc Pump B and the Control Room Supervisor directs you to obtain an Official Case or OD-3 and adjust APRM AGAFs for single loop operation. Inform the CRS when the task is complete and provide him with completed Attachment(s) for his review.

Note: Place the Simulator in RUN and tell the trainee to begin.

Nebraska Public Power District SKL034-20-19 (2121)

Cooper Nuclear Station Page 3 of 8 Job Performance Measure for Operations Revision 08 Task No.: 215040A0101

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Task

Title:

Perform APRM Gain Adjustment (With a Valid CTP) for Single Loop (Alternate Path)

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Performance Checklist Standards Initials

1. Obtain Official Case or Demand and obtain an Official Case or OD-OD-3 (PMIS Terminal) 3 from PMIS/typer. _________*

2. Obtain Procedure Obtain NPP 10.1, Attachment 2.

3. Ensure APRM recorder Ensures APRM recorder energized, energized, APRM/IRM APRM/IRM switch in APRM and pen not _________

switch in APRM and pen stuck.

not stuck

4. Record CTP on Record CTP from Official Case or OD-3 on Attachment 2 Attachment 2. _________*

5. Calculate FRP and record Calculate and record FRP on Attachment 2.

on Attachment 2 (FRP = CMWT/2381) _________*

6. Record IMPULSE Record impulse pressure.

pressure. _________

7. Compare recorded Impulse Operator marks SAT for Impulse pressure pressure with Attachment comparison. _________

4, record SAT or UNSAT.

8. Calculate and record Calculate and record APRM Desired (APRM APRM Desired value. Desired = Core Thermal Power + 6.6). _________*

9. Record APRM - % CTP Record APRM - %CTP Initial from Official Initial Case or OD-3. _________*

Nebraska Public Power District SKL034-20-19 (2121)

Cooper Nuclear Station Page 4 of 8 Job Performance Measure for Operations Revision 08 Task No.: 215040A0101

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Task

Title:

Perform APRM Gain Adjustment (With a Valid CTP) for Single Loop (Alternate Path)

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Performance Checklist Standards Initials NOTE: Both APRM A and APRM D will need to be adjusted. If A is selected first then mark steps 10 through 13 first. If D is selected first then mark steps 14 through 17 first and come back to 10 through 13.

10. Bypass APRMs that Bypass APRM A with the MANUAL require adjustment BYPASS JOYSTICK. _________

11. Verify APRM A Meter Verify APRM A meter switch is in the Switch is in AVERAGE AVERAGE. _________

12. Adjust APRM A to Adjust to APRM Desired.

Desired _________*

13. Unbypass APRM A Unbypass APRM A with the MANUAL BYPASS JOYSTICK. _________

14. Verify APRM D Meter Verify APRM D meter switch is in the Switch is in AVERAGE AVERAGE. _________

15. Adjust APRM Desired Attempts are made to adjust the Gain Adjustment Potentiometer _________

16. Determine APRM D Recognize ARPM D GAF cannot be GAF cannot be adjusted, report to the CRS.

adjusted. _________

1. CUE: CRS acknowledges the report.

Maintain the D APRM in bypass.

17. Leave APRM D Leave APRM D bypassed.

bypassed.

18. Generate OD-3 report Demand an OD-3 (PMIS Terminal).

(PMIS terminal) _________*

Nebraska Public Power District SKL034-20-19 (2121)

Cooper Nuclear Station Page 5 of 8 Job Performance Measure for Operations Revision 08 Task No.: 215040A0101

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Task

Title:

Perform APRM Gain Adjustment (With a Valid CTP) for Single Loop (Alternate Path)

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Performance Checklist Standards Initials

19. Record APRM %CTP Record (APRM %CTP) from official case or Final from OD-3 Core Power & Flow Log & Attach to _________*

Attachment 2. Ensure all are reading 4.6 to 8.6.

20. Complete NPP 10.1 Sign, date, and enter time on Attachment 2.

Attachment 2 _________

21. Check Acceptance Determine Acceptance Criteria is satisfied Criteria (except for APRM D). _________

22. Inform the CRS that the Inform the Control Room Supervisor that task is complete APRM AGAFs have been adjusted with the _________

exception of APRM D and provide him with the completed Attachment 2 for his review.

1. CUE: The CRS acknowledges the report.

Nebraska Public Power District SKL034-20-19 (2121)

Cooper Nuclear Station Page 6 of 8 Job Performance Measure for Operations Revision 08 Task No.: 215040A0101

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Task

Title:

Perform APRM Gain Adjustment (With a Valid CTP) for Single Loop (Alternate Path)

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ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the simulator to any full power IC (suggested). Any IC that supports power operation above 25% power in single loop will work.

Batch File Name - JPM\342019.

C. Change the simulator conditions as follows:

1. Triggers - None

2. Malfunctions - None

3. Remotes - None

4. Overrides Instrument Tag Trigger TD Value Ramp APRM Ch. D Gain Adjust ZAINMPOTR4D A 0 0.29 0 Potentiometer

5. Panel Setup

a. Initialize Simulator to any full power IC and place both 1DN and 1DS in pulled to lock.

b. Ensure total core flow is . 42 Mlbm/hr with A RR Pump.

c. Allow conditions to stabilize and ensure that PMIS/typer will provide proper edits/options when requested.

d. Hang Danger tags on 1DN and 1DS.

e. Adjust GAFs so 4 APRMs read 1.066 X FRTP (i.e. 75% pwr thermal, make 4 APRMs read 80%)

Nebraska Public Power District SKL034-20-19 (2121)

Cooper Nuclear Station Page 7 of 8 Job Performance Measure for Operations Revision 08 Task No.: 215040A0101

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Task

Title:

Perform APRM Gain Adjustment (With a Valid CTP) for Single Loop (Alternate Path)

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f. Ensure APRM calibration is needed for A and D APRMs.

Note: If this JPM is to be performed more than once, snap the simulator into an IC after the panel setup is complete.

Nebraska Public Power District SKL034-20-19 (2121)

Cooper Nuclear Station Page 8 of 8 Job Performance Measure for Operations Revision 08 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to perform APRM gain adjustment with a valid CTP available with only one RR loop in operation. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders, and controls you would be using. State the position of controls as you would have manipulated them to perform APRM gain adjustment with a valid CTP available with only one RR loop in operation. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

General Conditions:

1. Recirc Pump B has been secured IAW SOP 2.2.68.1 for rebrushing the RRMG set.

Initiating Cues:

Conditions have stabilized since securing Recirc Pump B and the Control Room Supervisor directs you to obtain an Official Case or OD-3 and adjust APRM AGAFs for single loop operation. Inform the CRS when the task is complete and provide him with completed Attachment(s) for his review.

Nebraska Public Power District SKL034-21-24 (2179)

Cooper Nuclear Station Page 1 of 7 Job Performance Measure for Operations Revision 02 Task No.:208028P0101

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Task

Title:

Separation of REC Critical Loops

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Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: CR/SIM

2. Appropriate Trainee level: RO/SRO

3. Evaluation Method: Simulate Perform

4. Performance Time: 5 minutes

5. NRC K/A 295018; AA1.03 (3.3/3.4), AK3.07 (3.1/3.2)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to separate the REC Critical Loops.

2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.

3. Observe the trainee during performance of the JPM for proper use of self-checking methods.

4. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space if desired by the examiner.

5. Brief the trainee, place the simulator in run, and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to separate the REC Critical Loops. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated to separate the REC Critical Loops. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

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Nebraska Public Power District SKL034-21-24 (2179)

Cooper Nuclear Station Page 2 of 7 Job Performance Measure for Operations Revision 02 Task No.:208028P0101

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Task

Title:

Separation of REC Critical Loops

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General Conditions:

1. Reactor was Shutdown, when a transient occurred in the REC system.

2. Several alarms associated with the REC system have been received in the Control Room.

2. Emergency Procedure 5.2REC, Loss of REC, has been entered and actions taken up to separating the REC Critical Loops.

General

References:

1. Procedure 5.2REC

2. Procedure 2.2.65.1 General Tools and Equipment:

1. None Special Conditions, References, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

2. Critical checks denoted by "*".

3. Simulator cues denoted by "#".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

The Control Room Supervisor directs you to separate the REC Criticial Loops per 2.2.65.1, using the NORTH Critical Loop. Inform the CRS when you have separated the REC Critical Loops.

NOTE: Place the Simulator in RUN and tell the trainee to begin. (Delete malfunction SW12b).

Nebraska Public Power District SKL034-21-24 (2179)

Cooper Nuclear Station Page 3 of 7 Job Performance Measure for Operations Revision 02 Task No.:208028P0101

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Task

Title:

Separation of REC Critical Loops

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Performance Checklist Standards Initials

1. Obtain a copy of 2.2.65.1 The operator obtains a current revision of 2.2.65.1, section 14. ________

2. Close REC-MO-695. The operator closes REC-MO-695, CRITICAL LOOP SUPPLY CROSSTIE _________*

CUE: GREEN light ON, RED light OFF.

3. Close REC-MO-694. The operator closes REC-MO-694, CRITICAL LOOP SUPPLY CROSSTIE _________*

CUE: GREEN light ON, RED light OFF.

4. Close REC-MO-721. The operator closes REC-MO-721, NON CRITICAL HEADER RETURN _________*

CUE: GREEN light ON, RED light OFF.

5. Close REC-MO-722. The operator closes REC-MO-722, NON CRITICAL HEADER RETURN _________*

CUE: GREEN light ON, RED light OFF.

6. Ensure Station Operator The operator directs the S.O. to perform steps performs steps 14.6 14.6 through 14.9 and inform him when they _________

through 14.9. are completed.

1. CUE: As the S.O., report steps 14.6 through 14.9 are completed.

7. Ensure REC-TCV-451A The operator Ensure REC-TCV-451A, REC switch is in open. HX A SW OUTLET TEMPERATURE _________

CONTROL, switch is in OPEN.

CUE: Switch is in OPEN.

8. Throttle open SW-MO- The operator Throttle open SW-MO-650 to 650 obtain 400 to 1200 gpm flow on SW-FI-387A, _________*

REC HX A SW OUTLET.

CUE: SW-FI-387A indicates 600 gpm.

Nebraska Public Power District SKL034-21-24 (2179)

Cooper Nuclear Station Page 4 of 7 Job Performance Measure for Operations Revision 02 Task No.:208028P0101

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Task

Title:

Separation of REC Critical Loops

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Performance Checklist Standards Initials

9. Ensure REC-MO-712 is The operator Ensure REC-MO-712, HX A closed OUTLET VLV, is closed. _________*

CUE: GREEN light On, RED light Off.

10. Ensure REC-MO-711 Operator ensures REC-MO-711, NORTH is open CRITICAL LOOP SUPPLY is open _________*

CUE: GREEN light OFF, RED light ON.

NOTE: The student my direct the Station Operator to obtain a surge tank level. Student may make decision about weather REC Surge Tank is available by status of annunciator M1/A3, REC SURGE TANK LOW Level and if it is clear or not.

1. CUE: If contacted as the Station Operator, report that the Level in the REC Sight Glass is low but still within the sight glass.

11. Open REC-MO-722 The operator opens REC-MO-722 if the REC Surge Tank is available,

1. CUE: If contacted as the Station Operator, report that the Level in the REC Sight Glass is low but still within the sight glass.

12. Ensure REC PUMP C or The operator Ensure REC PUMP C or D is D is running running. _________*

CUE: REC PUMP C or D is running

13. Inform CRS The operator informs the CRS that REC Critical Loops are separated. _________

CUE: CRS responds that he understands the REC Critcal Loops are separated.

Nebraska Public Power District SKL034-21-24 (2179)

Cooper Nuclear Station Page 5 of 7 Job Performance Measure for Operations Revision 02 Task No.:208028P0101

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Task

Title:

Separation of REC Critical Loops

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ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in any IC that will support this JPM.

Batch File Name - none.

C. Change the simulator conditions as follows:

1. Triggers None

2. Malfunctions Number Title Trigger TD Severity Ramp Initia l

SW12b REC HX 1B Tube Leak N/A N/A 60% N/A N/A

3. Remotes Number Title Trigger Value Ramp SW02 REC HX1B Inlet Isol Vlv (REC- 2 CLOSE N/A V-18)

SW04 REC HX1A Inlet Isol Vlv (REC- 2 CLOSE N/A V-20)

4. Overrides None

Nebraska Public Power District SKL034-21-24 (2179)

Cooper Nuclear Station Page 6 of 7 Job Performance Measure for Operations Revision 02 Task No.:208028P0101

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Task

Title:

Separation of REC Critical Loops

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5. Panel Setup

a. Place the Simulator in RUN. Insert above listed malfunction.

b. Perform actions of EP 5.2REC up to the point of splitting the REC Critical Loops (all REC pumps off).

c. Activate Trigger 2.

d. FREEZE the simulator.

e. When JPM begins and simulator is taken to RUN, DELETE the malfunction.

Note: If this JPM is to be performed more than once, snap the simulator into an IC after the panel setup is complete.

Nebraska Public Power District SKL034-21-24 (2179)

Cooper Nuclear Station Page 7 of 7 Job Performance Measure for Operations Revision 02 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to separate the REC Critical Loops. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to separate the REC Critical Loops. During performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

General Conditions:

1. Reactor was operating at 100% rated power,when a transient occured in the REC system.

2. Several alarms associated with the REC system have been recieved in the Control Room.

3. Emergency Procedure 5.2REC, Loss of REC, has been entered and actions taken up to separating the REC Critical Loops.

Initiating Cues:

The Control Room Supervisor directs you to separate the REC Criticial Loops per 2.2.65.1, using the NORTH Critical Loop. Inform the CRS when you have separated the REC Critical Loops.

Nebraska Public Power District SKL034-20-25 Cooper Nuclear Station Page 1 of 8 Job Performance Measure for Operations Revision 09 Task No.: 200267A0501

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Task

Title:

Primary Containment Venting for PCPL

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Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: SIM

2. Appropriate Trainee Level: RO/SRO

3. Evaluation Method: Perform

4. Performance Time: 15 minutes

6. NRC K/A 295024 EA1.20(3.5/3.6)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to vent primary containment under accident or post accident conditions.

2. This JPM is performed on the Simulator, only the cues preceded by "#" should be given.

3. Brief the trainee, and tell the trainee to begin.

4. Observe the trainee during performance of the JPM for proper use of self-checking methods.

5. All blanks must be filled out with either initials or an "NP" for "not performed", and an explanation may also be written in the space if desired by the examiner.

Directions to Trainee:

When I tell you to begin, you are to maintain drywell pressure during accident conditions.

Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to maintain drywell pressure during accident conditions.

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General Conditions:

1. The plant has experienced a LOCA.

2. The Containment Spray Mode of RHR is not operable.

3. Primary Containment pressure is approaching 66 psi slowly.

4. Suppression pool water level is 33'.

Nebraska Public Power District SKL034-20-25 Cooper Nuclear Station Page 2 of 8 Job Performance Measure for Operations Revision 09 Task No.: 200267A0501

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Task

Title:

Primary Containment Venting for PCPL

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General

References:

ESP 5.8.18 General Tools and Equipment:

1PA-2235 Key Special Conditions, References, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

2. Critical checks denoted by "*".

3. Simulator cues denoted by "#".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

The Shift Supervisor has declared a Site Area Emergency. The Control Room Supervisor has reached step PC/P-5 on Flowchart 3A and directed you to vent the Primary Containment using the one inch drywell vent line to reduce pressure below the Primary Containment Pressure Limit determined by Graph 11, EOP Support Procedure 5.8.18 Attachment 1. The other RO has initiated the appropriate EPIPs for release rate determination. You are to inform the CRS when you have reduced primary containment pressure to just below the PCPL.

Note: Place the Simulator in RUN and tell the Trainee to begin.

Nebraska Public Power District SKL034-20-25 Cooper Nuclear Station Page 3 of 8 Job Performance Measure for Operations Revision 09 Task No.: 200267A0501

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Task

Title:

Primary Containment Venting for PCPL

===================================================

Performance Standards Intials Checklist

1. Obtain a Operator obtains a copy of Procedure 5.8.18.

current copy of ________

Procedure 5.8.18

2. Monitor DW Operator continuously monitors Drywell pressure and Pressure and Suppression Pool level.

Torus Level ________

3. Verify that The operator verifies either SGT Fan A or B is operating.

SGT is operating ________

4. Verify dampers The operator verifies damper control switch for AD-R-1A and AD-R-1B Control are in SGT on Panel-K.

5. Verifies PC- The operator verifies that the control switch for the PC-AD-R-1A is AD-R1A is in the CLOSED position.

CLOSED ________

6. Verifies PC- The operator verifies that the control switch for the PC-AD-R-1B is AD-R1B is in the OPEN position.

OPEN ________

7. OPEN PC- The operator places control switch for PC-MO-1310 to MO-1310, the OVERRIDE position on Panel P1.

8. OVERRIDE The operator places the ISOLATION OVERRIDE switch PC-MO-306 for PC-MO-306 to OVERRIDE on Panel P1

9. Open The operator OPENS PC-MO-306 on Panel H.

PC-MO-306,

Nebraska Public Power District SKL034-20-25 Cooper Nuclear Station Page 4 of 8 Job Performance Measure for Operations Revision 09 Task No.: 200267A0501

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Task

Title:

Primary Containment Venting for PCPL

===================================================

Performance Standards Intials Checklist

10. Monitor ERP At Panel Q, operator monitors the ERP Effluent radiation effluent monitors for response to release.

radiation ________

monitors. #CUE: ERP High Range Kaman is responding and indicating 4 x 104 :ci/cc.

NOTE: At this point, when monitoring PC/Drywell pressure, the operator may either ask for pressure or monitor it on Panels P1, 9-3, 9-4, or any PMIS IDT.

11. THROTTLE The operator THROTTLES PC-MO-306 to reduce and PC-MO-306 maintain PC pressure to just below the PCPL (Att. 1 Graph 11). ________

10 Inform CRS The operator informs the CRS that he has reduced and is maintainingPC pressure just below the PCPL.

1. CUE: As the CRS acknowledge the report.

Nebraska Public Power District SKL034-20-25 Cooper Nuclear Station Page 5 of 8 Job Performance Measure for Operations Revision 09 Task No.: 200267A0501

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Task

Title:

Primary Containment Venting for PCPL

===================================================

ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in a high power IC. Suggested 18.

Batch File Name - none.

C. Change the simulator conditions as follows:

1. Triggers None

2. Malfunctions Number Title Trigge TD Severity Ramp r

RR20a Coolant Leakage Inside N/A N/A 10 N/A PC PC02a Torus To DW Vacuum N/A N/A 100 N/A Breaker Failure PC02b Torus To DW Vacuum N/A N/A 100 N/A Breaker Failure HP01 HPCI System Failure To N/A N/A N/A N/A Auto Start RC01 RCIC System Failure N/A N/A N/A N/A To Auto Start FW18a FW Line Break Inside N/A N/A 100 N/A PC MS01 Steam leak inside D/W N/A N/A 8 N/A

Nebraska Public Power District SKL034-20-25 Cooper Nuclear Station Page 6 of 8 Job Performance Measure for Operations Revision 09 Task No.: 200267A0501

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Task

Title:

Primary Containment Venting for PCPL

===================================================

ED18 PMIS System Power N/A N/A N/A N/A Failure

3. Remotes None

4. Overrides Tag Trigger TD Value Ramp ZAOPCLR1A[1] N/A N/A 33 N/A ZAOPCLR1A[2] N/A N/A 30 N/A ZAOPCLI10 N/A N/A 6 N/A ZAOPCLI12 N/A N/A 10 N/A ZAOPCLI13 N/A N/A 10 N/A ZAOPCLR11[2] N/A N/A 6 N/A ZAOPCLR1B[1] N/A N/A 33 N/A ZAOPCLR1B[2] N/A N/A 30 N/A RA:MUX07C120 N/A N/A OFF N/A ZDIMSSWS3A[1] N/A N/A INHIB N/A ZDIMSSWS3B[1] N/A N/A INHIB N/A ZDIRFCLCL130[1] N/A N/A MANUAL N/A ZAIRFCLCL130[1] N/A N/A 0 N/A ZDIRHRSWS3A[3] N/A N/A PTL N/A ZDIRHRSWS3B[3] N/A N/A PTL N/A ZDIRHRSWS3C[3] N/A N/A PTL N/A ZDIRHRSWS3D[3] N/A N/A PTL N/A ZDICSSWS5A[3] N/A N/A PTL N/A

Nebraska Public Power District SKL034-20-25 Cooper Nuclear Station Page 7 of 8 Job Performance Measure for Operations Revision 09 Task No.: 200267A0501

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Task

Title:

Primary Containment Venting for PCPL

===================================================

Tag Trigger TD Value Ramp ZDICSSWS5B[3] N/A N/A PTL N/A

5. Panel Setup

a. Initialize the Simulator.

b. Insert batch jpm/342025

c. Place in RUN.

d. Delete MS01 after D/W pressure ~66psig

e. Freeze simulator after all valves reposition, until student comes in.

Note: If this JPM is to be performed more than once, snap the simulator into an available IC after the panel setup is complete.

Nebraska Public Power District SKL034-20-25 Cooper Nuclear Station Page 8 of 8 Job Performance Measure for Operations Revision 09 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to maintain drywell pressure during accident conditions.

Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to maintain drywell pressure during accident conditions.

General Conditions:

1. The plant has experienced an LOCA.

2. The Containment Spray Mode of RHR is not operable.

3. Primary Containment pressure is 66 psi and rising slowly.

4. Suppression pool water level is 33'.

Initiating Cues:

The Shift Supervisor has declared a Site Area Emergency. The CRS has reached step PC/P-5 on Flowchart 3A and directed you to vent the Primary Containment using the one inch drywell vent line to reduce pressure below the Primary Containment Pressure Limit determined by Graph 11, EOP Support Procedure 5.8.18 Attachment 1. The other RO has initiated the appropriate EPIPs for release rate determination. You are to inform the CRS when you have reduced primary containment pressure to just below the PCPL.

Nebraska Public Power District SKL034-21-68 (16778)

Cooper Nuclear Station Page 1 of 6 Job Performance Measure for Operations Revision:00 Task Nos.:

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Task

Title:

RHR Shutdown Cooling Cooldown Rate Adjustment

=======================================================

Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: CR/SIM

2. Appropriate Trainee level: RO/SRO

3. Evaluation Method: Perform Simulate

4. Performance Time: 20 minutes

5. NRC K/As 259002 A1.04 (3.6/3.6) and 259002 A1.05 (2.9/2.9)

Directions to Examiner:

1. This JPM evaluates the trainees ability to perform a cooldown rate adjustment on the RHR system in Shutdown Cooling.

2. If this JPM is performed on the Simulator, only the cues preceded by # should be given.

4. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.

6. Brief the trainee, place the Simulator in RUN, and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to calculate the current cooldown rate and make the necessary adjustments to RHR to stabilize coolant temperature at approximately 115°F. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to perform the required task.

During actual performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

=======================================================

Nebraska Public Power District SKL034-21-68 (16778)

Cooper Nuclear Station Page 2 of 6 Job Performance Measure for Operations Revision:00 Task Nos.:

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Task

Title:

RHR Shutdown Cooling Cooldown Rate Adjustment

=======================================================

General Conditions:

1. The Reactor is shutdown (Mode 4).

2. Reactor Coolant System temperature is approximately 120°F.

3. RHR loop B is operating in Shutdown Cooling.

General

References:

1. Procedure 2.2.69.2, RHR Shutdown Cooling General Tools and Equipment:

1. None Special Conditions, References, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

2. Critical steps denoted by *.

3. Simulator cues denoted by #.

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

The Control Room Supervisor directs you to calculate the current cooldown rate and perform the necessary adjustments to the RHR system to stabilize coolant temperature at this point. Inform the CRS when the you have stabilized coolant temperature at approximately 115°F.

NOTE: Place the Simulator in RUN and tell the trainee to begin.

Nebraska Public Power District SKL034-21-68 (16778)

Cooper Nuclear Station Page 3 of 6 Job Performance Measure for Operations Revision:00 Task Nos.:

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Task

Title:

RHR Shutdown Cooling Cooldown Rate Adjustment

=======================================================

Performance Checklist Standards Initials

1. Obtains Procedure. The Operator obtains a current copy of Procedure 2.2.69.2. ________

2. Calculates current The Operator calculates the current cooldown rate at cooldown rate. approximately 40°F per hour. ________

CUE: Last hours temperature was 160°F NOTE: The Operator may perform multiple small adjustments to secure the cooldown rate, by reperforming the next two steps.

3. Adjust RHR flows to The Operator adjusts one or more of the following stop the cooldown. valves to control the cooldown: ________

• _____ RHR-MO-27B.

_____ RHR-MO-66B.

_____ RHR-MO-12B.

CUE: As flow is adjusted through or around the RHR Heat Exchanger indicate that temperature is changing depending on how much and in what direction the valves are manipulated.

4. Recalculates cooldown The Operator recalculates the cooldown rate.

rates. ________

• CUE: When sufficient flow has been bypassed and or reduced indicate that coolant temperature is approximately 120°F.

Nebraska Public Power District SKL034-21-68 (16778)

Cooper Nuclear Station Page 4 of 6 Job Performance Measure for Operations Revision:00 Task Nos.:

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Task

Title:

RHR Shutdown Cooling Cooldown Rate Adjustment

=======================================================

5. Reports completion of The Operator reports to the CRS that coolant the task. temperature cooldown rate has been secured, and ________

coolant temperature is approximately 115°F.

1. CUE: As the CRS acknowledge the report.

CUE: As the CRS Acknowledge the report.

Nebraska Public Power District SKL034-21-68 (16778)

Cooper Nuclear Station Page 5 of 6 Job Performance Measure for Operations Revision:00 Task Nos.:

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Task

Title:

RHR Shutdown Cooling Cooldown Rate Adjustment

=======================================================

ATTACHMENT 1 SIMULATOR SET-UP A. Materials required None B. Initialize the Simulator in an IC that will support the JPM.

Batch File name - none.

C. Change the Simulator conditions from those of the IC as follows:

1. Triggers None

2. Malfunctions None

3. Remotes None

4. Overrides None

5. Panel Set-up

a. Place the Simulator in RUN.

b. Ensure RPV water level is established (and stable) between 45 to 50 inches on the Panel 9-5 Narrow Range instruments.

c. Ensure that the cooldown rate is approximately 40°F per hour.

d. Mark the placard next to the RHR throttle valves with the amount of seconds that each valve is open or closed. (22 sec Open) on 12B

e. Place the Simulator in FREEZE.

Note: If this JPM is to be performed more than once, snap the Simulator into an IC after the panel set-up is complete.

Nebraska Public Power District SKL034-21-68 (16778)

Cooper Nuclear Station Page 6 of 6 Job Performance Measure for Operations Revision:00 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to calculate the current cooldown rate and make the necessary adjustments to RHR to stabilize coolant temperature at approximately 115°F. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to perform the required task.

During actual performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

General Conditions:

1. The Reactor is shutdown (Mode 4).

2. Reactor Coolant System temperature is approximately 120°F.

3. RHR loop B is operating in Shutdown Cooling.

Initiating Cues:

The Control Room Supervisor directs you to calculate the current cooldown rate and perform the necessary adjustments to the RHR system to stabilize coolant temperature at this point. Inform the CRS when the you have stabilized coolant temperature at approximately 115°F.

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 1 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

NOTE: THIS IS AN ALTERNATE PATH JPM. The first valve tested will not close requiring entry into 2.4SRV.

Additional Program Information:

1. Appropriate Performance Locations: SIM

2. Appropriate Trainee level: RO/SRO

3. Evaluation Method: Perform

4. Performance Time: 20 minutes

5. NRC K/A 218000 A4.01 (4.4/4.4)

Directions to Examiner:

NOTE: A MARKED UP COPY OF 6.ADS.201 (THROUGH STEP 3.9) WILL BE PROVIDED TO THE OPERATOR.

1. This JPM evaluates the trainee's ability to perform an ADS manual valve actuation surveillance.

2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.

3. Observe the trainee during performance of the JPM for proper use of self-checking methods.

4. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space if desired by the examiner.

5. Brief the trainee, place the simulator in run, and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to perform the ADS manual valve actuation surveillance.

Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to perform the ADS manual valve actuation surveillance. During performance, state the actions you are taking, e.g.:

repositioning controls and observing instrumentation.

==================================================

General Conditions:

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 2 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

1. Reactor Mode switch is in Run and Bypass valves are. 50% open.

2. Procedure 6.ADS.201 has been completed through step 3.9.

3. RHR Loop B has been placed in service in suppression pool cooling.

4. An operator is positioned to monitor bypass valve position during the test.

General

References:

1. Procedure 6.ADS.201

2. Procedure 2.4SRV General Tools and Equipment:

1. Marked up copy of 6.ADS.201

2. Stopwatch Special Conditions, References, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

2. Critical checks denoted by "*".

3. Simulator cues denoted by "#".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

The Control Room Supervisor directs you to perform the ADS manual valve actuation surveillance for MS-RV-71A and MS-RV-71E. You are to inform the CRS when testing is complete and you are ready to perform the restoration section of 6.ADS.201.

NOTE: Provide operator with a marked up copy of 6.ADS.201.

NOTE: Place the Simulator in RUN and tell the trainee to begin.

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 3 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

Performance Standards Initials Checklist

1. Obtains the The Operator obtains the marked up copy of the marked up copy surveillance. _________

of the surveillance

2. Display ADS The Operator depresses the ADS TEST push-button at TEST the Safety System Status Panel. _________

3. Mark recorders The Operator starts observing and marking PC-TR-24 every five and PC-TR-25 every five minutes. _________

minutes.

1. CUE: (When checked) state that a second operator will monitor and mark recorders.

5. Verify The Operator verifies the SAFETY OR RELIEF VALVE annunciators are LEAKING (9-3-1/C-1) alarms clears. _________

clear

5. Verify The Operator verifies the RELIEF VALVE OPEN (9 annunciators are 1/A-2) alarms clear. _________

clear NOTE: Testing of MS-RV-71A and -71E may be performed in either order.

NOTE: The trainee may record closed valve data for both valves at the same time. Go to step number 14 for MS-RV-71E.

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 4 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

Performance Standards Initials Checklist

6. Record data for The Operator records the following data on 6.ADS.201 closed valve. Attachment 1 for MS-RV-71A in the CLOSED position:

RELIEF VALVE OPEN annunciator status (9 1/A-2) _________*

SAFETY/RELIEF VALVE LEAKING annunciator status (9-3-1/C-1)

Green CLOSED indicating lamp status Amber indicating light status Red OPEN indicator light status Indicated temperature on MS-TR-166 Indicated temperature from computer points T142 and T146 Bypass Valve position

7. Monitor Bypass The Operator ensures another Operator is monitoring Position. bypass valve position. _________

1. CUE: Operator is positioned to monitor bypass valve position.

8. Place control The Operator places to OPEN the control switch for MS-switch in OPEN RV-71A. _________*

9. Record Time The Operator Record opening time on Attachment 2. _________*

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 5 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

Performance Standards Initials Checklist

10. Record data The Operator records the following data on 6.ADS.201 Attachment 1 for the selected valve: _________*

RELIEF VALVE OPEN Annunciator Status (9-3-1/A-2)

SAFETY/RELIEF VALVE LEAKING annunciator status (9-3-1/C-1)

Green indicating light status Amber indicating light status Red OPEN indicating light status Indicating temperature on MS-TR-166 Indicated temperature from computer points T142 (T146)

Bypass valve position

1. CUE: Tell the Operator that the Bypass valve position is as indicated.

11. Place control The Operator places the control switch for MS-RV-71A switch in in CLOSE. _________*

CLOSE

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 6 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

Performance Standards Initials Checklist

12. Record data for The Operator records the following data on 6.ADS.201 closed valve Attachment 1 for MS-RV-71A in the CLOSED position: _________*

RELIEF VALVE OPEN annunciator status(9 1/A-2)

SAFETY/RELIEF VALVE LEAKING annunciator status (9-3-1/C-1)

Green CLOSED indicating lamp status Amber indicating light status Red OPEN indicator light status Indicated temperature on MS-TR-166 Indicated temperature from computer points T142 and T146 Bypass Valve position

1. CUE: Tell the Operator that the Bypass valve position is as indicated.

13. Calculate and The Operator calculates and records change in Bypass record change Valve Position. _________*

in bypass valve position

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 7 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

Performance Standards Initials Checklist

14. Record data for The Operator Record the following data on 6.ADS.201 closed valve. Attachment 1 for MS-RV-71E in the CLOSED position: _________*

RELIEF VALVE OPEN annunciator status (9 1/A-2)

SAFETY/RELIEF VALVE LEAKING annunciator status (9-3-1/C-1)

Green CLOSED indicating lamp status Amber indicating light status Red OPEN indicator light status Indicated temperature on MS-TR-166 Indicated temperature from computer points T142 and T146 Bypass Valve position

15. Monitor The Operator ensures the Operator is still monitoring Bypass bypass valve position. _________

Position.

1. CUE: Operator is positioned to monitor bypass valve position.

16. Place control The Operator Place to OPEN control switch for MS-RV-switch for 71E.

selected relief _________*

valve in OPEN

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 8 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

Performance Standards Initials Checklist

17. Records data The Operator Record following data on 6.ADS.201 Attachment 1 for the selected valve: _________*

RELIEF VALVE OPEN Annunciator Status (9-3-1/A-2)

SAFETY/RELIEF VALVE LEAKING annunciator status (9-3-1/C-1)

Green indicating light status Amber indicating light status Red OPEN indicating light status Indicating temperature on MS-TR-166 Indicated temperature from computer points T142 (T146)

Bypass valve position

1. CUE: Tell the Operator that the Bypass valve position is as indicated.

18. Place control The Operator Place the control switch for MS-RV-71E in switch in CLOSE. _________*

CLOSE

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 9 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

Performance Standards Initials Checklist

19. Record data for The Operator reports to the CRS that the SRV is stuck closed valve OPEN and did not close. And that it is an entry into _________*

2.4SRV.

1. CUE: As the CRS tell the Operator to enter 2.4SRV and perform the subsequent actions.

NOTE: Once the Operator pulls 2.4SRV indicate that the JPM is complete.

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 10 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in an IC that has the Mode Switch in RUN and the bypass valves in Auto at 50% open.

Batch File Name - SKL03420103.

C. Change the simulator conditions as follows:

1. Triggers Trigset E1 = AD06E

2. Malfunctions AD06E set at 100%

3. Remotes None

4. Overrides None

5. Panel Setup

a. Initialize the Simulator in IC-10.

b. Complete Procedure 6.ADS.201, steps 2.1 through 3.9 and provide a marked up copy to the Operator to use. Indicate MS-RV-71A and MS-RV-71E as the valves requiring testing.

c. Place B RHR loop in Supression Pool Cooling.

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 11 of 12 Job Performance Measure for Operations Revision 00 Task No.: 218005P0201

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Task

Title:

Perform ADS Manual Valve Actuation Surveillance (Alt Path)

==================================================

Note: If this JPM is to be performed more than once, snap the simulator into an IC after the panel setup is complete.

Nebraska Public Power District SKL034-20-103 (16802)

Cooper Nuclear Station Page 12 of 12 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to perform the ADS manual valve actuation surveillance.

Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to perform the ADS manual valve actuation surveillance. During performance, state the actions you are taking, e.g.:

repositioning controls and observing instrumentation.

General Conditions:

1. Reactor Mode switch is in Run and Bypass valves are. 50% open.

2. Procedure 6.ADS.201 has been completed through step 7.5.

3. RHR Loop B has been placed in service in suppression pool cooling.

4. An operator is positioned to monitor bypass valve position during the test.

Initiating Cues:

The Control Room Supervisor directs you to perform the ADS manual valve actuation surveillance for MS-RV-71A and MS-RV-71E. You are to inform the CRS when testing is complete and you are ready to perform the restoration section of 6.ADS.201.

Nebraska Public Power District SKL034-21-21(2177)

Cooper Nuclear Station Page 1 of 9 Job Performance Measure for Operations Revision:01 Task Nos.:259032P0101, 200273A0101

=======================================================

Task

Title:

Perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test)

=======================================================

Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: CR/SIM

2. Appropriate Trainee level: RO/SRO

3. Evaluation Method: Perform Simulate

4. Performance Time: 20 minutes

5. NRC K/As 259002 A1.04 (3.6/3.6) and 259002 A1.05 (2.9/2.9)

Directions to Examiner:

1. This JPM evaluates the trainees ability to perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test.

2. If this JPM is performed on the Simulator, only the cues preceded by # should be given.

4. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.

6. Brief the trainee, place the Simulator in RUN, and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them to perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test. During performance, state the actions you are taking (e.g.: repositioning controls and observing instrumentation).

=======================================================

Nebraska Public Power District SKL034-21-21(2177)

Cooper Nuclear Station Page 2 of 9 Job Performance Measure for Operations Revision:01 Task Nos.:259032P0101, 200273A0101

=======================================================

Task

Title:

Perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test)

=======================================================

General Conditions:

1. Reactor is shutdown (Mode 4).

2. RHR loop B is in Shutdown Cooling

3. Reactor Coolant System temperature approximately 120°F.

4. Performance of 15.RF.201 is dictated by Procedure 2.1.1, Startup Procedure.

5. Another Operator has been assigned to monitor vessel metal temperatures and perform 6.RCS.601.

General

References:

1. Procedure 2.1.1

2. Procedure 15.RF.201 General Tools and Equipment:

1. None Special Conditions, References, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

2. Critical steps denoted by *.

3. Simulator cues denoted by #.

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

The Control Room Supervisor directs you to perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test. Inform the CRS when the surveillance has been completed. Shift Supervisors permission has been granted to perform the test and the Control Room Operator has already logged the start of this procedure.

NOTE: Place the Simulator in RUN and tell the trainee to begin.

Nebraska Public Power District SKL034-21-21(2177)

Cooper Nuclear Station Page 3 of 9 Job Performance Measure for Operations Revision:01 Task Nos.:259032P0101, 200273A0101

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Task

Title:

Perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test)

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Performance Standards Initials Checklist

1. Obtains Procedure. The Operator obtains a current copy of Procedure 15.RF.201 ________

CUE: One Reactor Recirc Pump is running.

2. Ensure that RF-MO- The Operator ensures that RF-MO-31 is CLOSED.

31 is CLOSED. ________

3. Ensure that RF-MO- The Operator ensures that RF-MO-32 is CLOSED.

32 is CLOSED. ________

4. Ensure that RF-MO- The Operator ensures that RF-MO-33 is CLOSED.

33 is CLOSED. ________

5. Ensure that RF-MO- The Operator ensures that RF-MO-34 is CLOSED.

34 is CLOSED. ________

6. Ensure that FCV11AA The Operator ensures that RFC-CS-FCV11AA is in is in AUTO. AUTO. ________

7. Ensure bias setting on The Operator ensures bias setting on RFC-CS-FCV11AA is set at FCV11AA is set at zero. ________

zero.

8. Ensure that FCV11BB The Operator ensures that RFC-CS-FCV11BB is in is in AUTO. AUTO. ________

9. Ensure bias setting on The Operator ensures bias setting on RFC-CS-FCV11BB FCV11BB is set at is set at zero. ________

zero.

10. Ensure SUMAST is in The Operator ensures RFC-CS-SUMAST is in AUTO.

AUTO. ________

11. Ensure LEVEL The Operator ensures LEVEL SETPOINT on RFC-CS-SETPOINT on SUMAST is set ~10" below current water level ________

SUMAST is set ~10" below current water level.

12. Verifies OUTPUT on The Operator verifies OUTPUT on RFC-CS-FCV11AA FCV11AA is at is at minimum. ________

minimum.

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Task

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Perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test)

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13. Verifies OUTPUT on The Operator verifies OUTPUT on RFC-CS-FCV11BB FCV11BB is at is at minimum. ________

minimum.

14. Verifies OUTPUT on The Operator verifies OUTPUT on RFC-CS-SUMAST SUMAST is at is at minimum. ________

minimum.

Depending on which FCV is in the lead the Operator will either perform steps 16 through 20 or 21 through 25 and N/A the others.

15. Determines Lead The Operator determines Lead SFCV.

SFCV. ________

16. Transfer Lead SFCV The Operator transfers Lead SFCV by placing RFC-CS-FCV11AA in MAN ________

17. Verify Memic The Operator verifies Memic indicates that FCV11BB is indicates lead. lead. ________

18. Transfer Lead SFCV The Operator transfers Lead SFCV back to FCV11AA by back to FCV11AA. placing RFC-CS-FCV11AA in AUTO. ________

19. Ensure Bias on The Operator ensures Bias on FCV11AA is zero.

FCV11AA is zero. ________

20. Verify FCV11AA is The Operator verifies FCV 11AA is Lead Startup Flow Lead SFCV. Control Valve on RFC-M-OITA Startup Valve Mimic ________

screen.

21. IF B SFCV is in the The Operator transfers Lead SFCV by placing RFC-CS-lead then Transfer FCV11BB in MAN ________

Lead SFCV.

22. Verify Memic The Operator verifies Memic indicates that FCV11AA is indicates lead. lead. ________

23. Transfer Lead SFCV The Operator transfers Lead SFCV back to FCV11BB by back. placing RFC-CS-FCV11AA in AUTO. ________

24. Ensure Bias is zero. The Operator ensures Bias on FCV11BB is zero.

25. Verify Lead SFCV. The Operator verifies FCV 11BB is Lead Startup Flow Control Valve on RFC-M-OITA Startup Valve Mimic ________

screen.

Nebraska Public Power District SKL034-21-21(2177)

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Task

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Perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test)

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26. Establish The Operator contacts the Station Operator in the communication with Reactor Feed Pump Room. ________

SO in Feed Pump Room #CUE: When contacted as the Station Operator indicate that you are standing by to monitor the Startup Flow Control Valves.

27. Adjusts SUMAST The Operator adjusts RFC-CS-SUMAST using the UP/DOWN arrows to >2" above current water level. ________

28. Verifies OUTPUT The Operator verifies that the OUTPUT rises up to rises to ~100% ~100% and MAX light is lit for the RFC-CS-FCV11AA. ________*

29. Verifies OUTPUT The Operator verifies that the OUTPUT rises up to rises to ~100% ~100% and MAX light is lit for the RFC-CS-FCV11BB. ________*

30. Verifies OUTPUT The Operator verifies that the OUTPUT rises up to rises to ~100% ~100% and MAX light is lit for the RFC-CS-SUMAST. ________*

31. Contacts the SO in the The Operator contacts the SO in the feeed pump room feeed pump room to and has him verify that the Startup Flow Control Valves ________*

verify SFCVs OPENED.

OPENED

1. CUE: Respond as the SO and report that the Startup Flow Control valves OPENED.

32. Verifies that the The Operator verifies that the VALVE POSITION rises VALVE POSITION to ~100% one the RFC-CS-FCV11AA. ________

rises to ~100%

33. Verifies that the The Operator verifies that the VALVE POSITION rises VALVE POSITION to ~100% one the RFC-CS-FCV11BB. ________

rises to ~100%

34. Verifies [A-63] The Operator verifies on the RFC-M-OITA(B) [A-63]

Controller High Controller High Saturation Limit alarms. ________

Saturation Limit alarms

35. Verifies that If RFC-CS-FCV11AA is the lead then the Operator Annunciator A-1/E-6 verifies that Annunciator A-1/E-6 alarms ________

alarms

36. Verifies that If RFC-CS-FCV11BB is the lead then the Operator Annunciator A-2/E-3 verifies that Annunciator A-2/E-3 alarms ________

alarms

Nebraska Public Power District SKL034-21-21(2177)

Cooper Nuclear Station Page 6 of 9 Job Performance Measure for Operations Revision:01 Task Nos.:259032P0101, 200273A0101

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Task

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Perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test)

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37. Adjusts the level The Operator adjusts the level setpoint on RFC-CS-setpoint SUMAST using the UP/DOWN arrows to 10" below the ________

current water level.

38. Checks that the The Operator checks that the OUTPUT lowers to ~0%

OUTPUT and MIN light is lit on the RFC-CS-FCV11AA. ________*

39. Checks that the The Operator checks that the OUTPUT lowers to ~0%

OUTPUT and MIN light is lit on the RFC-CS-FCV11BB. ________*

40. Checks that the The Operator checks that the OUTPUT lowers to ~0%

OUTPUT and MIN light is lit on the RFC-CS-SUMAST. ________*

41. Contacts the SO to The Operator contacts the SO in the feeed pump room verify that the SFCVs and has him verify that the Startup Flow Control Valves ________*

CLOSED. CLOSED.

1. CUE: Respond as the SO and report that the Startup Flow Control valves CLOSED.

42. Checks that the % The Operator checks that the % VALVE POSITION VALVE POSITION lowers to ~0% on RFC-CS-FCV11AA. ________*

lowers

43. Checks that the % The Operator checks that the % VALVE POSITION VALVE POSITION lowers to ~0% on RFC-CS-FCV11BB. ________*

lowers

44. Verifies that the alarm The Operator verifies that the alarm that was received is that was received is clear ________

clear

45. Verifies [A-63] The Operator verifies on RFC-M-OITA (B) that the [A-Controller High 63] Controller High Saturation Limit clears. ________

Saturation Limit clears.

46. Verifies [A-64] alarm The Operator verifies on RFC-M-OITA and RFC-M-did not alarm OITB that the [A-64] alarm did not alarm during the ________*

performance of the surveillance.

NOTE: CUE the Operator as the Control Room Supervisor (CRS) to adjust the level setpoint on RFC-CS-SUMAST to 15", and there is no need to raise level to > 48" or secure a Reactor Recirc Pump.

47. Adjusts the SUMAST The Operator, using the UP/DOWN arrows adjust the setpoint to 15" RFC-CS-SUMAST setpoint to 15" ________

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Task

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Perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test)

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48. Operator completes The Operator then completes the surveillance and turns it surveillance. in for review. ________

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Task

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Perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test)

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ATTACHMENT 1 SIMULATOR SET-UP A. Materials required None B. Initialize the Simulator in IC-1 Batch File name - none.

C. Change the Simulator conditions from those of the IC as follows:

1. Triggers None

2. Malfunctions None

3. Remotes None

4. Overrides None

5. Panel Set-up

a. Place the Simulator in RUN.

b. Ensure RPV water level is established (and stable) between 30" and 40" on the Panel 9-5 Narrow Range instruments.

c. Ensure that Startup Level Controllers RFC-CS-SUMAST, RFC-CS-11AA, RFC-CS-11BB are all in MAN with their OUTPUTs indicating 0%.

d. Place the Simulator in FREEZE.

Note: If this JPM is to be performed more than once, snap the Simulator into IC-0 after the panel set-up is complete.

Nebraska Public Power District SKL034-21-21(2177)

Cooper Nuclear Station Page 9 of 9 Job Performance Measure for Operations Revision:01 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to perform Surveillance Procedure 15.RF.201, STARTUP LEVEL CONTROL SYSTEM FUNCTIONAL TEST. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to perform Surveillance Procedure 15.RF.201, STARTUP LEVEL CONTROL SYSTEM FUNCTIONAL TEST. During actual performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

General Conditions:

1. Reactor is shutdown (Mode 4).

2. RHR loop B is in Shutdown Cooling

3. Reactor Coolant System temperature approximately 120°F.

4. Performance of 15.RF.201 is dictated by Procedure 2.1.1, Startup Procedure.

5. Another Operator has been assigned to monitor vessel metal temperatures and perform 6.RCS.601.

Initiating Cues:

The Control Room Supervisor directs you to perform Surveillance Procedure 15.RF.201, Startup Level Control System Functional Test. Inform the CRS when the surveillance has been completed. Shift Managers permission has been granted to perform the test and the Control Room Operator has already logged the start of the procedure.

Nebraska Public Power District SKL034-21-67 (16803)

Cooper Nuclear Station Page 1 of 9 Job Performance Measure for Operations Revision: 00 Task No.: 202022C0401

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Task

Title:

Respond to a Trip of a Reactor Recirc pump

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Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: CR / SIM

2. Appropriate Trainee level: RO / SRO

3. Evaluation Method: Perform Simulate

4. Performance Time: 20 minutes

5. NRC K/As 202001 A2.03 (3.6/3.7)

Directions to Examiner:

1. This JPM evaluates the trainees ability to respond to a Reactor Recirculation pump trip per 2.4RR, Reactor Recirculation Abnormal.

2. If this JPM is performed on the Simulator, only the cues preceded by # should be given.

3. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.

4. Give the trainee his copy of the Directions to the Trainee (Attachment 2) when ready to start the JPM.

5. Brief the trainee, place the Simulator in RUN, and tell the trainee to begin.

Nebraska Public Power District SKL034-21-67 (16803)

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Task

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Respond to a Trip of a Reactor Recirc pump

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Directions to Trainee:

When I tell you to begin, you are to perform actions as appropriate to panel 9-4 and 9-5 indications.

Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

If being simulated In-Plant or Control Room:

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to complete the assigned task.

If being performed in the Simulator:

During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

========================================================

General Conditions:

1. The plant is operating at power.

2. You are the Control Room Operator.

General

References:

1. Procedure 2.4RR, Reactor Recirculation Abnormal

2. Procedure 2.2.68.1, Reactor Recirculation System Operations

Nebraska Public Power District SKL034-21-67 (16803)

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Task

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Respond to a Trip of a Reactor Recirc pump

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General Tools and Equipment:

1. None Special Conditions, References, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

2. Critical steps denoted by *.

3. Simulator cues denoted by #.

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

The Control Room Supervisor directs you to perform actions as appropriate to panel 9-4 and panel 9-5 indications.

Nebraska Public Power District SKL034-21-67 (16803)

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Task

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Respond to a Trip of a Reactor Recirc pump

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Performance Checklist Standards Initials

1. Assume the watch at panel 9-5. The operator positions himself in a position to monitor panel 9-5.

ACTION: After the candidate assumes the watch, activate TRIGGER E1 to trip B Reactor Recirculation Pump.

2. Recognize and report trip of The operator recognizes and reports the trip of B Recirc pump. Reactor Recirculation pump. *

1. CUE: Acknowledge the report as CRS.

Dirrects the operator to perform his actions per the abnormal.

3. Take appropriate immediate The operator evaluates 2.4RR immediate actions; actions. determines none apply.

4. Obtain procedure 2.4RR. The operator obtains a copy of 2.4RR.

5. Enter Attachment 1 of 2.4RR Operator enters Attachment 1 of 2.4RR.

6. Evaluate need to enter Operator evaluates the need to enter Attachment 4 Attachment 4 for stability for stability exclusion region; determines entry is exclusion region. required.

7. Ensure RRMG Set B GEN Operator ensures RRMG Set B GEN FIELD BKR FIELD BKR open. open.

• CUE: RRMG Set B GEN FIELD BKR green light is illuminated, the red light is out.

Nebraska Public Power District SKL034-21-67 (16803)

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Task

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Respond to a Trip of a Reactor Recirc pump

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Performance Checklist Standards Initials

8. Close RR-MO-53B, PUMP Operator closes RR-MO-53B, PUMP DISCHARGE VLV. DISCHARGE VLV.

• CUE: RR-MO-53B green light is lit and the red light is out.

NOTE: The operator should continue with the remaining 2.4RR steps while waiting for the RR-MO-53B valve.

9. After RR-MO-53B has been Operator opens RR-MO-53B after it has has been closed for 5 minutes, open closed for 5 minutes (-0, + 5 minutes).

valve.

CUE: RR-MO-53B green light is out and red light is lit (after valve has been opened).

10. Ensure operating RRMG is Operator ensures A RRMG is powered by the transferred to Startup Startup Transformer.

Transformer per Procedure 2.2.18. CUE: A RRMG is powered by the Startup Transformer (Breaker 1CS is closed).

11. Maintain oil outlet temperature Operator directs Station Operator to maintain oil for tripped RRMG 90°F to outlet temperature for tripped RRMG 90°F to 130°F. 130°F.

1. CUE: Acknowledge/repeat back order as Station Operator.

12. Monitor loop cooldown rate on Operator monitors loop cooldown rate on RR-TR-165, RR SUCTION & RR-TR-165, RR SUCTION & FEEDWATER FEEDWATER TEMP. TEMP.

CUE: Loop temperature has dropped 6/F over the last 5 minutes.

Nebraska Public Power District SKL034-21-67 (16803)

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Task

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Respond to a Trip of a Reactor Recirc pump

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Performance Checklist Standards Initials

13. Concurrently enter Single Loop Operator obtains a copy of 2.2.68.1.

Operation per Procedure 2.2.68.1.

14. Dispatch Operators to R-976-W Operator dispatches Operators to R-976-W and and Non-Critical Switchgear Non-Critical Switchgear Room to record lockout Room to record lockout relays relays and targets for tripped pump.

and targets for tripped pump.

1. CUE: Overcurrent (51 relay) is tripped for breaker 1DN (in Non-Critical Switchgear Room). There are no lockouts at Reactor Building 976 West.

15. If total core flow < 20%, Operator determines Core Flow is below 20%

concurrently enter Attachment rated.

2.

CUE: Indicated core flow is 10 Mlbm/hr.

NOTE: Cue the student and tell him that the JPM is complete.

Nebraska Public Power District SKL034-21-67 (16803)

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Task

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Respond to a Trip of a Reactor Recirc pump

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ATTACHMENT 1 SIMULATOR SET-UP A. Materials required None B. Initialize the Simulator in any IC that will support this JPM.

Batch File name - none.

C. Change the Simulator conditions from those of the IC as follows:

1. Triggers Number File Name Description None N/A N/A

2. Malfunctions Number Title Trigger TD Severity Ramp Initial RR04D B Reactor Recirculation E1 N/A N/A N/A N/A Pump Drive Motor Breaker Trip (1DN)

3. Remotes Number Title Trigger TD Value Ramp None

Nebraska Public Power District SKL034-21-67 (16803)

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Task

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Respond to a Trip of a Reactor Recirc pump

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4. Overrides Instrument Tag Trigger TD Value Ramp None N/A N/A N/A N/A N/A

5. Panel Set-up (suggested.)

a. Insert listed overrides and malfunctions.

b. Place the Simulator in RUN.

c. Ensure A Reactor Recirculation pump is aligned to the Startup Transformer.

d. Ensure B Reactor Recirculation pump is aligned to the Normal Transformer.

e. Ensure that the curser on the power to flow map is within the normal operating region.

Note: If this JPM is to be performed more than once, snap the Simulator into an IC after the panel set-up is complete.

Nebraska Public Power District SKL034-21-67 (16803)

Cooper Nuclear Station Page 9 of 9 Job Performance Measure for Operations Revision: 00 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to perform actions as appropriate to panel 9-4 and 9-5 indications.

Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

If being simulated In-Plant or Control Room:

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to complete the assigned task.

If being performed in the Simulator:

During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

General Conditions:

1. The plant is operating at power.

2. You are the RO (9-5 PNL).

3. Optimum Water Chemistry is out of service.

Initiating Cue(s):

The Control Room Supervisor directs you to perform actions as appropriate to panel 9-4 and panel 9-5 indications.

Nebraska Public Power District SKL034-10-97 (16777)

Cooper Nuclear Station Page 1 of 8 Job Performance Measure for Operations Revision 00 Task No.:

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Task

Title:

5.3ALT-Strategy - RCIC Manual Operation

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Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: Plant

2. Appropriate Trainee Level: SO / RO / SRO

3. Evaluation Method: Simulate

4. Performance Time: 30 minutes

5. NRC K/A: 2.4.34 Directions to Examiner:

1. This JPM evaluates the trainee's ability to operate RCIC with no power available.

2. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.

3. Brief the trainee and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin you are to perform Attachment 4 of 5.3ALT-Strategy to start RCIC. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to complete the assigned task.

========================================================

General Conditions:

1. The plant has experienced a loss of all AC and DC power.

2. The Rx has scrammed.

3. RCIC is in the standby lineup.

General

References:

1. 5.3ALT-STRATEGY

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Task

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5.3ALT-Strategy - RCIC Manual Operation

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General Tools and Equipment:

1. Handheld Tachometer. Kept in R-903-NE Quad stairwell Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

You have been assigned to carry out actions for Manual RCIC operation in accordance with Procedure 5.3ALT-STRATEGY Attachment 4. The Control Room Supervisor (CRS) directs you to perform all the necessary steps to maintain water level between 15 and 40 inches. Notify the CRS when the RCIC is in service and water level is being maintained.

Nebraska Public Power District SKL034-10-97 (16777)

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Task

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5.3ALT-Strategy - RCIC Manual Operation

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Performance Checklist Standard Initials

1. Obtain a copy of CUE: Provide the candidate with Attachment 4 of 5.3ALT-STRATEGY 5.3ALT-STRATEGY, Alternate Core Cooling ___NP_____

Mitigating Strategies.

2. Checks if the RCIC The Operator Checks if the RCIC Turbine needs to Turbine needs to be reset. be reset. __________

CUE: Indicate that the Trip lever is as found.

NOTE: All AC and DC power has been lost.

3. Ensures the RCIC The Operator ensures that the following breakers are Breakers are OFF. in the OFF condition.

1. RCIC-MO-15, BREAKER 10B on MCC-Y (R- ___________

903-S).

CUE: It is in the OFF position.

2 RCIC-MO-41, BREAKER on 125 VDC RCIC ___________

STARTER RACK.

CUE: It is in the OFF position.

3 RCIC-MO-18, BREAKER on 125 VDC RCIC ____________

STARTER RACK.

CUE: It is in the OFF position.

4. RCIC-MO-131, BREAKER on 125 VDC RCIC ____________

STARTER RACK.

CUE: It is in the OFF position.

Nebraska Public Power District SKL034-10-97 (16777)

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Task

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5.3ALT-Strategy - RCIC Manual Operation

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Performance Checklist Standard Initials Continued 5. RCIC-MO-27, BREAKER on 125 VDC ____________

RCIC STARTER RACK.

CUE: It is in the OFF position.

6. RCIC-MO-21, BREAKER on 125 VDC RCIC ____________

STARTER RACK.

CUE: It is in the OFF position.

7. RCIC-MO-132, BREAKER on 125 VDC RCIC ____________

STARTER RACK.

CUE: It is in the OFF position.

8. RCIC-MO-14, BREAKER on 125 VDC RCIC ____________

STARTER RACK.

CUE: It is in the OFF position.

9. RCIC-MO-33, BREAKER on 125 VDC RCIC ____________

STARTER RACK.

CUE: It is in the OFF position.

10. RCIC-MO-20, BREAKER on 125 VDC RCIC ____________

STARTER RACK.

CUE: It is in the OFF position.

11. RCIC-MO-30, BREAKER on 125 VDC RCIC ____________

STARTER RACK.

CUE: It is in the OFF position

Nebraska Public Power District SKL034-10-97 (16777)

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Task

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5.3ALT-Strategy - RCIC Manual Operation

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Performance Checklist Standard Initials Continued 12. RCIC-MO-16, EE-STR-125 RCIC (MO16). __________*

CUE: It is in the OFF position

13. GLAND SEAL TANK CONDENSATE PUMP ___________

on 250 VDC RCIC STARTER RACK.

CUE: It is in the OFF position. If asked no lights are lit.

14. GLAND SEAL VACUUM PUMP on 250 VDC RCIC STARTER RACK. ____________

CUE: It is in the OFF position. If asked no lights are lit.

15. Ensures valve Closed. The Operator ensures that the RCIC-MO-14, Trip Valve in the RCIC Pump Room is CLOSED. __________*

CUE: If simulated checking the valve in the closed direction indicate the valve is in the CLOSED position.

16. Ensures valve Closed. The Operator ensures that the RCIC-MO-41, Torus Pump Suction Valve in the RCIC Pump Room is __________*

CLOSED.

CUE: If simulated checking the valve in the closed direction indicate the valve is in the CLOSED position.

17. Ensures valve Closed. The Operator ensures that the RCIC-MO-27, Minimum Flow Bypass Valve in the RCIC Pump __________*

Room is CLOSED.

CUE: If simulated checking the valve in the closed direction indicate the valve is in the CLOSED position.

Nebraska Public Power District SKL034-10-97 (16777)

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Task

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5.3ALT-Strategy - RCIC Manual Operation

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Performance Checklist Standard Initials

18. Ensures valves OPEN. The Operator ensures that the RCIC-MO-131, Steam Supply to the Turbine Valve in the RCIC Pump __________*

Room is OPEN.

CUE: If simulated checking the valve in the open direction indicate the valve is in the OPEN position.

19. Ensures valves OPEN. The Operator ensures that the RCIC-MO-21, Pump Discharge to the Reactor Valve in the Steam Tunnel ___NP_____*

903 is OPEN.

CUE: Because the valve is in a Locked High Radiation Area, inform the candidate RCIC-MO-21 is open. (The valve is in the steam tunnel.)

20. Ensures valves OPEN. The Operator ensures that the RCIC-MO-20, Pump Discharge Valve in the NE Quad 881 is OPEN. __________*

CUE: If simulated checking the valve in the open direction indicate the valve is in the OPEN position.

21. Ensures valves OPEN. The Operator ensures that the RCIC-MO-33, ECST Shutoff Valve in the NE Quad 881 is OPEN. __________*

CUE: If simulated checking the valve in the open direction indicate the valve is in the OPEN position.

22. Ensures valves OPEN. The Operator ensures that the RCIC-MO-132, Turbine Oil Cooling Water Supply Valve in the __________

RCIC Pump Room is OPEN.

CUE: If simulated checking the valve in the open direction indicate the valve is in the OPEN position.

Nebraska Public Power District SKL034-10-97 (16777)

Cooper Nuclear Station Page 7 of 8 Job Performance Measure for Operations Revision 00 Task No.:

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Task

Title:

5.3ALT-Strategy - RCIC Manual Operation

=========================================================

Performance Checklist Standard Initials

23. Ensures valves OPEN. The Operator ensures that the RCIC-MO-18, ECST Pump Suction Valve in the RCIC Pump Room is __________*

OPEN.

CUE: If simulated checking the valve in the open direction indicate the valve is in the OPEN position.

24. Ensures valves OPEN. The Operator disconnects the electrical connector going to RCIC-CHA-3067 in the RCIC Pump Room. __________

CUE: Indicate the connector is disconnected.

Nebraska Public Power District SKL034-10-97 (16777)

Cooper Nuclear Station Page 8 of 8 Job Performance Measure for Operations Revision 00 ATTACHMENT 1 Directions to the Trainee:

When I tell you to begin you are to perform steps 1.1 through 1.5 of Attachment 4 of 5.3ALT-Strategy to start RCIC. Before you start, I will state the general plant conditions, the initiating cues. I will answer any questions you may have.

This JPM is simulated and consequently no plant components will be manipulated. When simulating, physically point to any meters, gauges, valves and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.

General Conditions:

1. The plant has experienced a loss of all AC and DC power.

2. The Rx has scrammed.

3. RCIC is in the standby lineup.

Initiating Cue(s):

You have been assigned to complete steps 1.1 through 1.5 for Manual RCIC operation in accordance with Procedure 5.3ALT-STRATEGY Attachment 4. Notify the CRS when these steps of Procedure 5.3ALT-STRATEGY Attachment 4 are complete.

Job Performance Measure Examination JPM #CNS-Plant-J, Revision 0 Plant Systems 5.1ASD Failure to Scram SKL05*********

System Reactor Protection Mode 3 System Estimated Time 25 minutes Location(s) Control Room 4160V Switchgear Room Auxiliary Rely Room RPS MG Set Room 1A Evaluation Method(s) Simulated Performance of Directed Activities Alternate Path Yes (Reactor does not scram when a manual reactor scram is inserted per 5.1ASD step 4.2.1, contact failure in one Scram pushbutton)

References:

Procedure 2.1.5, Reactor SCRAM, Revision 51 Procedure 5.1ASD, Alternate Shutdown, Revision 2 Examiner Trainee Observer Examination Date Result: SATISFACTORY UNSATISFACTORY Page 1 of 7

Job Performance Measure Examination JPM #CNS-Plant-J, Revision 0 Examiner Directions to Candidate:

I will explain or provide initial conditions, inform you about which step(s) to discuss or simulate (if any), and provide initiating and followup cues. It is necessary that you verbalize your actions and, for simulations, request information concerning indications and expected responses to your actions. When you complete the task, the objective for this job performance measure will be satisfied.

Task Evaluation Standard(s):

• Procedure 5.1ASD, Alternate Shutdown, Revision 2 Safety Considerations:

• Actual performance of 5.1ASD in the Control Room, Auxiliary Relay Room, or RPS MG Set Room 1A, could result in a plant SCRAM. The candidate shall not manipulate any actual controls during this JPM.

Performance Consequences:

• Incorrect application of 5.1ASD could lead to personnel injury to the operations crew, as well as to increasing the probability and/or severity of fuel damage in an accident situation.

Tools and Methods:

• Simulation of performing steps in 5.1ASD in the actual Control Room and at the Auxiliary Relay Room, or RPS MG Set Room 1A.

Human Interfaces:

• The candidate must obtain permission in the Control Room prior to simulating activities necessary to complete this JPM.

Examiner Notes:

• This JPM begins in the plant Control Room.

• This JPM requires entry into the Radiologically Controlled Area (RCA). The candidate and examiner should enter using RWP ********

• The candidate should not simulate tripping all Reactor Feed Pumps, Condensate Booster Pumps, and Condensate Pumps per 5.1ASD step 4.2.4.2 through 4.2.4.4. One pump train should remain in operation.

• The candidate should not simulate tripping the Recirc MG Sets from the Control Room because a PCIS Group 6 signal is not present Page 2 of 7

Job Performance Measure Examination JPM #CNS-Plant-J, Revision 0 Initial Condition(s):

• The plant has been operating at 100% rated thermal power.

• A strong chemical odor has been detected in the Control Room. Operators also notice eye and lung irritation.

Provide the Candidate initial conditions located at page 7 of 7 Terminating Condition(s):

• After the candidate simulates opening the AC INPUT MOT Breaker to RPS MG Set 1A, the JPM is complete.

Page 3 of 7

Job Performance Measure Examination JPM #CNS-Plant-J, Revision 0 Initiating Cue:

The Shift Manager has ordered an evacuation of the Control Room due to toxic gas using 5.1ASD. You have been directed to:

• Perform 5.1ASD steps 4.2.1 to 4.2.5

• Perform 5.1ASD Attachment 2, Control Building/Critical Switchgear Room Operator

• Obtain any supplies or equipment necessary to perform Attachment 2 Candidate Action Responding Cue Completed Observes panel 9-5 (as found No annunciators are lit. G YES G NO condition) Conditions are normal for 100% power operations.

Simulates plant SCRAM using the Reactor SCRAM Pushbutton A G YES G NO SCRAM pushbuttons is not lit Reactor SCRAM Pushbutton B is lit red Observes SCRAM Indicating lights 4 Group A lights are lit G YES G NO 4 Group B lights are out (not lit)

Observes Panel 9-5 Annunciators 9-5-2/A-1 is not lit G YES G NO 9-5-2/A-3 is lit Simulates tripping the Main Turbine is tripped; expected G YES G NO Turbine Generator annunciators are lit Simulates tripping the Reactor Feed Pump is tripped with G YES G NO Feed Pump(s) expected indications [note 1 RFP should remain running]

Comments:

Page 4 of 7

Job Performance Measure Examination JPM #CNS-Plant-J, Revision 0 Candidate Action Responding Cue Completed Simulates tripping the Condensate Condensate Booster Pump is G YES G NO Booster Pump(s) tripped with expected indications [note 1 CBP should remain running]

Simulates tripping the Condensate Condensate Pump is tripped G YES G NO Pump(s) with expected indications [note 1 Condensate Pump should remain running]

Simulates obtaining required Equipment is obtained [to be G YES G NO standard equipment: radio, successful, the candidate must flashlight, keys, screwdriver show the examiner each piece of required equipment]

NOTE: 5.1ASD §4.1.2 directs personnel NOT to enter the Cable Spreading Room Simulates obtaining manual Ratchet is obtained [to be G YES G NO breaker charging ratchet in the successful, the candidate must 4160V Switchgear Room show the examiner the ratchet]

IF candidate simulates calling the CRS for direction whether to isolate RCIC and/or de-energize the RPS MG Sets, THEN respond that the candidate is directed to isolate RCIC and de-energize the RPS MG Sets Goes to the Auxiliary Relay Room N/A Locates the RCIC Isolation Switch RCIC Isolation Switch is in G YES G NO NORMAL Simulates placing the RCIC RCIC Isolation switch is in G YES G NO Isolation switch to ISOLATE ISOLATE Goes to RPS MG Set Room 1A N/A Locates CDP-1A Breaker 2 CDP-1A Breaker 2 is CLOSED G YES G NO Simulates opening CDP-1A CDP-1A Breaker 2 is OPEN G YES G NO Breaker 2 Comments:

Page 5 of 7

Job Performance Measure Examination JPM #CNS-Plant-J, Revision 0 Candidate Action Responding Cue Completed Locates AC INPUT MOT Breaker AC INPUT MOT Breaker is G YES G NO to RPS MG Set 1A CLOSED Simulates opening AC INPUT AC INPUT MOT Breaker is G YES G NO MOT Breaker to RPS MG Set 1A OPEN Comments:

Termination Cue:

After the candidate simulates opening the AC INPUT MOT Breaker to RPS MG Set 1A, the JPM is complete.

Page 6 of 7

Job Performance Measure Examination JPM #CNS-Plant-J, Revision 0 Information for Candidate Candidate Instructions:

The examiner will explain or provide initial conditions, inform you about which step(s), if any, to discuss or simulate, and will provide initiating and followup cues. It is necessary that you verbalize your actions and, for simulations, specifically request information concerning indications and expected responses to your actions. When you complete the task, the objective for this job performance measure will be satisfied.

Initial Condition(s):

• The plant has been operating at 100% rated thermal power.

• A strong chemical odor has been detected in the Control Room. Operators also notice eye and lung irritation.

Initial Cue or Direction:

The Shift Manager has ordered an evacuation of the Control Room due to toxic gas using 5.1ASD. You have been directed to:

• Perform 5.1ASD steps 4.2.1 to 4.2.5

• Perform 5.1ASD Attachment 2, Control Building/Critical Switchgear Room Operator

• Obtain any supplies or equipment necessary to perform Attachment 2 Page 7 of 7

Nebraska Public Power District SKL034-10-95 (7456)

Cooper Nuclear Station Page 1 of 5 Job Performance Measure for Operations Revision 01 Task No.: 200134I0504

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Task

Title:

Respond to No Break Power Panel Failure (Control Bldg. Actions) (Alternate Path)

=========================================================

Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

ALTERNATE PATH Additional Program Information:

1. Appropriate Performance Locations: Plant

2. Appropriate Trainee Level: SO / RO / SRO

3. Evaluation Method: Simulate

4. Performance Time: 25 minutes

5. NRC K/A: 262002 K4.01(3.4/3.4)

Directions to Examiner:

NOTE: This is an Alternate Path JPM. The alternate source supplying load will not work and the manual bypass switch must be used.

1. This JPM evaluates the trainee's ability to respond to a no-break power panel failure

2. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.

3. Give the trainee his copy of the Directions to the Trainee (Attachment 1) when ready to start the JPM.

4. Brief the trainee and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin you are to perform the assigned Control Building Operators actions to respond to a no break power panel failure. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to complete the assigned task.

=========================================================

Nebraska Public Power District SKL034-10-95 (7456)

Cooper Nuclear Station Page 2 of 5 Job Performance Measure for Operations Revision 01 Task No.: 200134I0504

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Task

Title:

Respond to No Break Power Panel Failure (Control Bldg. Actions) (Alternate Path)

=========================================================

General Conditions:

1. The plant has experienced a no break power panel failure.

2. The Rx has scrammed.

3. An attempt to transfer NBPP to MCC-R by placing NBPP PWR TRANSFER switch to MCC-R has failed.

4. The electricians have determined that the fault is not in the NBPP itself.

5. Both switches have been placed to ALT at the 120v AC supplies for the gaitronics.

6. Control Room Operators have performed actions 4.1 through 4.3.14 of 5.3NBPP.

General

References:

1. 5.3NBPP (NO BREAK POWER FAILURE)

General Tools and Equipment:

1. Key for access to Control Building 903' doors.

Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

You have been assigned to carry out actions for a no break power panel failure in accordance with 5.3NBPP. The Control Room Supervisor (CRS) directs you to perform all the necessary Control Building Operators actions for restoring power from the Alternate Supply (MCC-R). Notify the CRS when the NBPP is energized.

Nebraska Public Power District SKL034-10-95 (7456)

Cooper Nuclear Station Page 3 of 5 Job Performance Measure for Operations Revision 01 Task No.: 200134I0504

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Task

Title:

Respond to No Break Power Panel Failure (Control Bldg. Actions) (Alternate Path)

=========================================================

Performance Checklist Standard Initials

1. Obtain a copy of Obtain a copy of 5.3NBPP, NO BREAK POWER 5.3NBPP FAILURE __________

2. Ensure MCC-R FEED Ensure EE-DSC-NBPP(AC), MCC-R FEED TO TO NBPP is in ON. NBPP TRANSFORMER (Cable Spreading near __________*

NBPP), is in ON.

CUE: Indicate the handle is in the UP position.

3. Contact the Rx Building Contacts the Reactor Building Operator to ensure that Operator. MCC-R, Breaker 2B, NO BREAK AC POWER __________*

SUPPLY, is closed and reset.

CUE: Respond as the Rx Bldg Operator, that MCC-R, Breaker 2B, NO BREAK AC POWER SUPPLY, is closed and reset.

4. Open breaker Open INVERTER OUTPUT breaker.

CUE: Indicate the handle is in the DOWN position.

5. Ensure breaker is closed. Ensure SUPPLY TO NBPP breaker is closed.

CUE: Indicate the handle is in the UP position.

6. Ensure breaker is closed. Ensure ALTERNATE AC INPUT TO STATIC SWITCH breaker is closed. __________

CUE: Indicate the handle is in the UP position.

Nebraska Public Power District SKL034-10-95 (7456)

Cooper Nuclear Station Page 4 of 5 Job Performance Measure for Operations Revision 01 Task No.: 200134I0504

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Task

Title:

Respond to No Break Power Panel Failure (Control Bldg. Actions) (Alternate Path)

=========================================================

Performance Checklist Standard Initials

7. Depress button. Depress ALTERNATE SOURCE SUPPLYING LOAD button. __________

CUE: The red light is off.

8. Place MAN BP SW to Place MANUAL BYPASS SWITCH to ALT SOURCE TO ALTERNATE SOURCE TO LOAD. __________*

LOAD.

CUE: Point to ALTERNATE SOURCE TO LOAD position.

9. Depress ALT SOURCE Depress ALTERNATE SOURCE SUPPLYING SUPPLYING LOAD LOAD button. __________*

button.

CUE: The red light is on.

NOTE: The Gaitronics do not need to be transferred

10. Notifies CRS. Notifies CRS that NBPP is energized.

CUE: As the CRS respond to the report.

Nebraska Public Power District SKL034-10-95 (7456)

Cooper Nuclear Station Page 5 of 5 Job Performance Measure for Operations Revision 01 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin you are to perform the assigned Control Building Operators actions to respond to a no break power panel failure. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to complete the assigned task.

General Conditions:

1. The plant has experienced a no break power panel failure.

2. The Rx has scrammed.

3. An attempt to transfer NBPP to MCC-R by placing NBPP PWR TRANSFER switch to MCC-R has failed.

4. The electricians have determined that the fault is not in the NBPP itself.

5. Both switches have been placed to ALT at the 120v AC supplies for the gaitronics.

6. Control Room Operators have performed actions 4.1 through 4.3.14 of 5.3NBPP.

Initiating Cues:

You have been assigned to carry out actions for a no break power panel failure in accordance with 5.3NBPP. The Control Room Supervisor (CRS) directs you to perform all the necessary Control Building Operators actions for restoring power from the Alternate Supply (MCC-R). Notify the CRS when the NBPP is energized.

Nebraska Public Power District SKL034-30-50 (11653)

Cooper Nuclear Station Page 1 of 7 Job Performance Measure for Operations Revision 00 Task No.: 200335G0503

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Task

Title:

PAR Table Top (#5)

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Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: Classroom / Simulator

2. Appropriate Trainee Levels: SRO / STE

3. Evaluation Method: Simulate Perform

4. Performance Time: 10 minutes

5. NRC K/A: 2.4.44 (2.1 / 4.0)

Directions to Examiner:

NOTE: THIS IS A TIME CRITICAL JPM

- 10 minute time limit

- The time starts when in the control room or simulator and the examiner has told the student to begin.

- The clock ends when the completed Attachment 1 is returned to the examiner.

1. This JPM evaluates the trainee's ability to make a PAR Recommendation.

2. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.

3. Give the trainee his copy of the Directions to the Trainee (Attachment 1) when ready to start the JPM.

4. DO NOT allow the trainee to pre-review the associated procedures.

5. Brief the trainee and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to determine Protective Action Recommendations for the provided conditions. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

During task performance, it is recommended that you limit your discussion/demonstration to the minimum required. The examiner will as questions of you if necessary to understand your actions..

Nebraska Public Power District SKL034-30-50 (11653)

Cooper Nuclear Station Page 2 of 7 Job Performance Measure for Operations Revision 00 Task No.: 200335G0503

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Task

Title:

PAR Table Top (#5)

=========================================================

THIS IS A TIME CRITICAL JPM.

=========================================================

General Conditions:

1. A General Emergency has been declared under EAL 2.4.1.

2. There IS a radioactive release in excess of ODAM limits at this time.

3. A steam leak exists in the Turbine Building.

4. Both Inboard and Outboard MSIV on B Main Steam Line will not close.

5. The core IS degraded.

6. The stability class is E.

7. The wind is at 15 mph.

8. The wind is from 0 /

9. There is NO precipitation DOSE Projection Data Distance From Projected Integrated Dose (Rem) Projected Dose Rate (Rem/hr)

Plant TEDE CDE (Thyroid) TEDE CDE (Thyroid)

Site Boundary 2.60E+00 4.12E+01 6.51E-01 1.03E+01 2 Miles 9.21E-01 1.46E+01 2.30E-01 3.65E+00 5 Miles 2.98E-01 4.72E+00 7.46E-02 1.18E+00 10 Miles 1.53E-01 2.43E+00 3.84E-02 6.07E-01 General

References:

1. Procedure 5.7.1, EAL Matrix

2. Procedure 5.7.6, Attachment 3

3. Procedure 5.7.20 General Tools and Equipment:

1. None

Nebraska Public Power District SKL034-30-50 (11653)

Cooper Nuclear Station Page 3 of 7 Job Performance Measure for Operations Revision 00 Task No.: 200335G0503

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Task

Title:

PAR Table Top (#5)

=========================================================

Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

3. This JPM must be completed within 10 minutes. The time starts when the examiner tell the student to begin and ends when the completed Attachment 1 has been returned to the evaluator.

Initiating Cue(s):

You are to determine the appropriate Protective Action Recommendations (PARs) for the provided conditions. Complete the PAR table below and return this Attachment to the examiner when you have completed this task.

Nebraska Public Power District SKL034-30-50 (11653)

Cooper Nuclear Station Page 4 of 7 Job Performance Measure for Operations Revision 00 Task No.: 200335G0503

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Task

Title:

PAR Table Top (#5)

=========================================================

Performance Checklist Standards Initials RECORD START TIME _____________________________

NOTE: Per 5.7.2, the trainee must reference 5.7.20 for the provided conditions.

1. Refer to Procedure 5.7.2. The operator refers to Procedure 5.7.2. Determine 5.7.20 must be used for PARs. _________

2. Refer to Procedure 5.7.20. The operator refers to Procedure 5.7.20.

3. Determines affected The operator determines the affected sectors for wind sectors. direction of 0°.

Sectors H, J, K

4. Determines Sectors to The Operator determines the following Evacuation Evacuate sectors:

Evacuate 0 - 2 miles All sectors 2 - 5 miles Sectors H, J, K 5 - 10 miles

5. Determines Sectors that The Operator determines the following GO INDOORS must Go Indoors and sectors:

monitor EAS/EBS _________*

GO INDOORS 2 - 5 miles All remaining sectors 5 - 10 miles All remaining sectors

6. Determines no protective Determines no protective actions affect areas beyond 10 actions are required past miles. _________

10 miles.

Nebraska Public Power District SKL034-30-50 (11653)

Cooper Nuclear Station Page 5 of 7 Job Performance Measure for Operations Revision 00 Task No.: 200335G0503

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Task

Title:

PAR Table Top (#5)

=========================================================

Performance Checklist Standards Initials

7. Turns in completed Returns completed Attachment 1 to evaluator.

paperwork. _________

RECORD STOP TIME ______________________ TOTAL TIME _______________

8. JPM completion time JPM completed in 10 minutes or less.

Nebraska Public Power District SKL034-30-50 (11653)

Cooper Nuclear Station Page 6 of 7 Job Performance Measure for Operations Revision 00 ATTACHMENT 1 (Page 1 of 2)

Directions to Trainee:

When I tell you to begin, you are to determine Protective Action Recommendations for the provided conditions. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

During task performance, it is recommended that you limit your discussion/demonstration to the minimum required. The examiner will as questions of you if necessary to understand your actions..

THIS IS A TIME CRITICAL JPM.

General Conditions:

1. A General Emergency has been declared under EAL 2.4.1.

2. There IS a radioactive release in excess of ODAM limits at this time.

3. A steam leak exists in the Turbine Building.

4. Both Inboard and Outboard MSIV on B Main Steam Line will not close.

5. The core IS degraded.

6. The stability class is E.

7. The wind is at 15 mph.

8. The wind is from 0 /

9. There is NO precipitation DOSE Projection Data Distance From Projected Integrated Dose (Rem) Projected Dose Rate (Rem/hr)

Plant TEDE CDE (Thyroid) TEDE CDE (Thyroid)

Site Boundary 2.60E+00 4.12E+01 6.51E-01 1.03E+01 2 Miles 9.21E-01 1.46E+01 2.30E-01 3.65E+00 5 Miles 2.98E-01 4.72E+00 7.46E-02 1.18E+00 10 Miles 1.53E-01 2.43E+00 3.84E-02 6.07E-01

Nebraska Public Power District SKL034-30-50 (11653)

Cooper Nuclear Station Page 7 of 7 Job Performance Measure for Operations Revision 00 ATTACHMENT 1 (Page 2 of 2)

Initiating Cue(s):

You are to determine the appropriate Protective Action Recommendations (PARs) for the provided conditions. Complete the PAR table below and return this Attachment to the examiner when you have completed this task.

Protective Action Recommendations (PARS)

None Evacuate Sectors Go indoors and monitor EAS/EBS in Sectors 0-2 Miles 2-5 Miles 5-10 Miles REMARKS for 5.7.6 Attachment 3:

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 1 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 341013O0303

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Task

Title:

Approve Radioactive Discharge / Release Permit

========================================================

Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: CR / SIM

2. Appropriate Trainee level: SRO

3. Evaluation Method: Perform

4. Performance Time: 10 minutes

5. NRC K/As 2.1.34 (2.9); 2.1.32 (3.4/3.8)

Directions to Examiner:

1. This JPM evaluates the trainees ability to complete a radioactive discharge / release permit.

2. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.

3. Give the trainee his copy of the Directions to the Trainee (Attachment 2) and Liquid Radwaste Discharge Form (Attachment 1) when ready to start the JPM.

4. Brief the trainee, and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to review and complete the radioactive discharge/release permit as Shift Manager. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

========================================================

General Conditions:

1. The plant is operating at 100%.

2. CWP A, B, and D are in service.

3. De-icing is in progress.

4. The FDST radioactive discharge was started at 0905, Jan 6.

5. The FDST radioactive discharge was stopped at 1355, Jan 6.

6. FDST final level is 10.5%.

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 2 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 341013O0303

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Task

Title:

Approve Radioactive Discharge / Release Permit

========================================================

General

References:

1. 8.8.11, Liquid Radioactive Waste Discharge Authorization General Tools and Equipment:

1. Scientific calculator Special Conditions, References, Tools, Equipment:

1. Critical steps denoted by *.

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

As Shift Supervisor complete the Liquid Radioactive Waste Discharge Form for the FDST and inform me when all required actions are complete.

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 3 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 341013O0303

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Task

Title:

Approve Radioactive Discharge / Release Permit

========================================================

Performance Checklist Standards Initials

1. Records Stop Run Data in Operator records Date as 1/6/xx, records time as Section 5. 1355 and records % tank level as 10.5.

2. Records dilution flow. Operator refers to Section 4.1 and records dilution flow of 308400 gpm. *

3. Records volume of release. Operator calculates volume of release as 16368.625 (using Usable tank volume and start

• and stop tank %).

NOTE: Acceptable value: 16368 to 16369 gallons.

4. Records total time of discharge. Operator calculates total time of discharge in minutes (subtracting start time from end time) and

• records 290 minutes.

5. Records discharge flow. Operator calculates discharge flow (divides volume of release by total time of discharge) and

• records 56.44 gpm.

6. Records River Level. Operator records river level as 880 ft MSL.

1. CUE: River level is 880 ft MSL.

7. Removes Discharge In Progress Operator would remove or direct control room Tags from running CWPs. operator to remove the tags from the running CWPs.

1. CUE: Tags are removed.

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 4 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 341013O0303

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Task

Title:

Approve Radioactive Discharge / Release Permit

========================================================

Performance Checklist Standards Initials

8. Records total river flow. Operator contacts chemistry for total river flow and records 5.9E7 l/min..

1. CUE: Chemistry reports total river flow is 5.9 E7 l/min. (This may be completed by the Chemist after SS signature.)

9. Completes discharge permit. Operator signs form as Shift Manager and forwards to Chemistry for review.

1. CUE: Accept form as Chemist.

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 5 of 8 Job Performance Measure for Operations Revision: 01 ATTACHM ENT 1 LIQUID RADWASTE DISCHARGE FORM Section 1. REQUEST FOR ANALYSIS OF RADIOACTIVE LIQUID WASTE PRIOR TO DISCHARGE To : Chem istry From : Shift Sup ervisor Tank T o B e Discharged: FDST Started Recirculation For Sam ple: T ime: 0300 Date: 1/6/XX Estimated V olume To B e Discharged: 98-10.5% = 87.5%

Shift Supervisor: Mark Helen Time: 0555 Date: 1/6/xx Section 2. THIS SECTION TO BE COM PLETED BY PER SON TA KING SAM PLE Monitor Source Check Inform ed C ontro l Roo m And P erform ed Source Check - Initials: R EW Sam ple P oint: 18 Time: 0635 Date: 1/6/xx Signature: Ray Monamo Section 3. AUTHORIZATION TO RELEASE RADIOACTIVE LIQUID WASTE To : Shift Sup ervisor From: Ch emistry R elease Autho rization Num ber:

To tal :Ci/ml: 3.74E-5 Total Concentration is < 1.0E-02 :Ci/ml Y ES/NO Signature: Ray Monamo 31 D ay Dose, Percent Of Annua l Limit For Each Value Is # 2.0E+00 YE S/NO Signature : Ray Monamo You Are Authorized T o Release Subject Tank W ith Either Of Following Restrictions:

Maximum Liquid Waste Discharge Rate (gpm)

1) 100 2) N/A 3) N/A Minimum Dilution Flow To Canal (gpm)

1) 159,000 2) 159,000 3) 159,000 Discharge Monitor Alarm Setpoint ( :Ci/ml)

1) 6.22E-3 2) N/A 3) N/A NOTE - Terminate Disc harge If Abo ve Sp ecifications Cannot B e M aintained. Co ntents O f This T ank A re W ithin Chemical Parameters For Discharge.

Chemistry: Ray Monamo Time: 0707 Date: 1/6/xx

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 6 of 8 Job Performance Measure for Operations Revision: 01 ATTACHM ENT 1 LIQUID RADWASTE DISCHARGE FORM Section 4 SHIFT SUPERV ISOR APPROV AL TO RELEA SE 4.1 Circle Appropriate Discharge Canal Flow Rate:

AVERAGE CW DISCHARGE FLOWRATE (gpm)

NUMB ER OF OPERATING CW PUMPS DE-ICING NO DE-ICING 4 378,600 631,000 3 308,400 514,000 2 193,200 322,000 1 118,800 198,000 4.2 To: Operations Personnel From: Shift Supervisor The Sub ject Tank Contents Are App roved For Re lease Subject To T he Following Restrictions:

1) M aximu m Liq uid D isch Rate: 100 gpm (Section 3)

2) M inimum Dilution Flow To Canal O f: 159000 gpm (Section 3)

3) Alarm Limits Specified (Section 3)

4) T ank V olume Verified: 98 (Compare To Section 1)

5) DISCHAR GE IN P ROG RESS tags Installed On Running Circ Water Pump s.

Approval To Release:

Shift Supervisor: Mark Helen Time: 0804 Date: 1/6/xx

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 7 of 8 Job Performance Measure for Operations Revision: 01 ATTACHM ENT 1 LIQUID RADWASTE DISCHARGE FORM Section 5 To: Chemist From: Shift Supervisor The Subject Discharge Has Been Completed And The Following Data Obtained During The Discharge:

START  % STOP  %

RUN TANK RUN TANK NUMBER DATE T IM E LEVEL NUMBER DATE TIM E LEVEL 1 1/6/xx 0905 98 1 2 2 3 3 4 4 Usable Tank Volumes (0% to 100%)

FDST - 18,707 gal W ST A - 20,015 gal W ST B - 20,015 gal

1) Dilution Flow (Section 4 .1): gpm

2) Vo lume O f Relea se: gal

3) To tal Tim e Of Discharge: min

4) Discharge Flow: gpm

5) River Leve l: ft MSL

6) Remove D ISCH ARG E IN PRO GR ESS tags from running C irc W ater Pum ps.

7) To tal River Flow : l/min (De termined B y The Chemist)

Shift Supervisor: Time: Date:

Chemist Re view: Date:

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 8 of 8 Job Performance Measure for Operations Revision: 01 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to review and complete the radioactive discharge/release permit as Shift Manager. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

General Conditions:

1. The plant is operating at 100%.

2. CWP A, B, and D are in service.

3. De-icing is in progress.

4. The FDST radioactive discharge was started at 0905, Jan 6.

5. The FDST radioactive discharge was stopped at 1355, Jan 6.

6. FDST final level is 10.5%.

Initiating Cue(s):

As Shift Manager complete the Liquid Radioactive Waste Discharge Form for the FDST and inform me when all required actions are complete.

Nebraska Public Power District SKL034-50-49 (16779)

Cooper Nuclear Station Page 1 of 5 Job Performance Measure for Operations Revision: 00 Task No.: 200311G0303

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Task

Title:

Assess the Impact of a Missed TS-TRM Surv on Safety Related Equip.

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Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: CR / SIM

2. Appropriate Trainee level: SRO

3. Evaluation Method: Perform

4. Performance Time: 20 minutes

5. NRC K/As 2.2.12 (3.0/3.4)

Directions to Examiner:

1. This JPM evaluates the trainees ability to assess the impact of a missed TS-TRM surveillance on safety related equipment.

2. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.

3. Give the trainee his copy of the Directions to the Trainee (Attachment 2) when ready to start the JPM.

4. Brief the trainee, and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to assess the impact of the missed RCIC surveillance 6.RCIC.102 on safety related equipment in accordance with Procedure 0.49. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

========================================================

General Conditions:

1. The plant is operating at 100%.

2. Core Spray Div I is tagged out for maintenance, day 2 of its LCO, expected back Tomorrow at 13:00 hours.

3. It is 21:00 Saturday Night.

4. SAP is unavailable General

References:

Nebraska Public Power District SKL034-50-49 (16779)

Cooper Nuclear Station Page 2 of 5 Job Performance Measure for Operations Revision: 00 Task No.: 200311G0303

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Task

Title:

Assess the Impact of a Missed TS-TRM Surv on Safety Related Equip.

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1. 0.26, Surveillance Program

2. 0.49, Schedule Risk Assessment General Tools and Equipment:

1. None Special Conditions, References, Tools, Equipment:

1. Critical steps denoted by *.

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

As the Shift Manager you have just been notified that RCIC Surveillance 6.RCIC.201, RCIC IST and 92 Day Test, was missed last month and needs to be performed. The RCIC Surveillance drop dead date was 7 days ago at 21:00. You will need to perform an assessment to see if it can be run and when. Contact the Operations Manager with the results.

Nebraska Public Power District SKL034-50-49 (16779)

Cooper Nuclear Station Page 3 of 5 Job Performance Measure for Operations Revision: 00 Task No.: 200311G0303

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Task

Title:

Assess the Impact of a Missed TS-TRM Surv on Safety Related Equip.

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Performance Checklist Standards Initials

1. Obtain Procedure 0.49. The SM obtains a current copy of procedure 0.49.

2. Performs risk assessment. The SM performs a missed surveillance risk assessment in accordance with Procedure 0.49, Schedule Risk Assessment Section 6.

3. Components identified. The SM ensures that the components have been identified, per Procedure 0.26, that have not had the surveillance requirements met.

4. Identifies the risk codes. The SM identifies the risk codes associated with these components from the nuclear characteristics in SAP.

CUE: SAP is unavailable

5. Determines risk code color. The SM determines that the Risk Code color is ORANGE from Attachment 1. And notifies Risk

• Management to modify the schedule or restore the availability of Core Spray Div I.

CUE: As Risk Management respond that the schedule does not need to be changed, and that Core Spray is due back tomorrow at 13:00.

6. Schedules RCIC The SM will schedule the RCIC surveillance at the Surveillance. first reasonable opportunity following Core Sprays

• return to service, but not to exceed three days.

Nebraska Public Power District SKL034-50-49 (16779)

Cooper Nuclear Station Page 4 of 5 Job Performance Measure for Operations Revision: 00 Task No.: 200311G0303

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Task

Title:

Assess the Impact of a Missed TS-TRM Surv on Safety Related Equip.

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Performance Checklist Standards Initials

7. Notifies OM. The SM notifies the Operations Manager that the RCIC surveillance will be scheduled to be performed following Core Spray Div I return to service, but not to exceed three days.

CUE: Respond as the Operations Manger and acknowledge the report.

Nebraska Public Power District SKL034-50-49 (16779)

Cooper Nuclear Station Page 5 of 5 Job Performance Measure for Operations Revision: 00 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to assess the impact of the missed RCIC surveillance 6.RCIC.102 on safety related equipment in accordance with Procedure 0.49. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

General Conditions:

1. The plant is operating at 100%.

2. Core Spray Div I is tagged out for maintenance, day 2 of its LCO, and is expected back tomorrow at 13:00 hours.

3. It is now 21:00 Saturday Night.

4. SAP is unavailable.

Initiating Cue(s):

As the Shift Manager you have just been notified that RCIC Surveillance 6.RCIC.201, RCIC IST and 92 Day Test, was missed last month and needs to be performed. The RCIC Surveillance drop dead date was 7 days ago at 21:00. You will need to perform an assessment to see if it can be run and when. Contact the Operations Manager with the results.

Job Performance Measure Examination JPM #CNS-SRO-2, Revision 0 Conduct of Operations, Determine Required On-Shift Staffing System Administrative Mode 2 Estimated Time 10 minutes Location Not Applicable Evaluation Method(s) Perform using Procedure 2.0.3 Alternate Path No

References:

Procedure 2.0.3, Revision 49, Section 10, Control Room and Station Shift Staffing Requirements Examiner Trainee Observer Examination Date Result: SATISFACTORY UNSATISFACTORY Page 1 of 6

Job Performance Measure Examination JPM #CNS-SRO-2, Revision 0 Examiner Directions to Candidate:

I will explain or provide initial conditions, inform you about which step(s) to discuss or simulate (if any), and provide initiating and followup cues. When you complete the task, the objective for this job performance measure will be satisfied.

Task Evaluation Standard(s):

• Procedure 2.0.3, Revision 49, Section 10.

Safety Considerations:

• No safety considerations are associated with performing this JPM.

Performance Consequences:

• Incorrectly determining required on-shift staffing could result in a crew not being staffed to respond to plant transients or implement the station Emergency Plan as required.

Tools and Methods:

• Not Applicable.

Human Interfaces:

• None.

Examiner Notes:

• None.

Initial Condition(s):

• The plant is operating in Mode 2.

• You are taking the watch as Shift Manager during day shift.

• The first reactor feedwater pump discharge valve is scheduled to be opened at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> today.

Provide the Candidate initial conditions located at page 5 of 6 Terminating Condition(s):

• The candidate has determined which additional on-shift positions are required to be filled.

Page 2 of 6

Job Performance Measure Examination JPM #CNS-SRO-2, Revision 0 Initiating Cue:

The following personnel are present on-shift:

• Shift Manager

• Control Room Supervisor

• Licensed Operator (ATCO)

• Licensed Operator (BOP)

• Station Operator (Shift Communicator)

• Station Operator (Fire Brigade)

• Station Operator (Fire Brigade)

• SRO (Observing Panel 9-5)

• Utility Personnel (Fire Brigade)

Are any additional personnel REQUIRED to be on shift? IF SO, determine by position which additional personnel are required. If any on-shift FUNCTIONS (e.g. Shift Communicator, Fire Brigade) are also REQUIRED to be filled, determine which function(s) are required.

The required on-shift crew when the plant is in Mode 2 prior to opening the first reactor feed pump discharge valve is:

Reference Initial Conditions Determined by Candidate 10.1.1 Shift Manager (SRO) 10.1.1 Control Room Supervisor (SRO) 10.1.5 Shift Technical Engineer 10.1.2 Licensed Operator (ATCO) 10.1.6.2 10.1.2 Licensed Operator (BOP) 10.1.2 Licensed Operator (WCO, Fire Brigade 10.2.4.2 Leader) 10.1.3 Station Operator 1 (Shift 10.1.6.4 Communicator) 10.1.3 Station Operator 2 (Fire Brigade 2) 10.2.4.2 Page 3 of 6

Job Performance Measure Examination JPM #CNS-SRO-2, Revision 0 10.1.3 Station Operator 3 (Fire Brigade 3) 10.2.4.2 10.1.4 Health Physics Technician 10.3.1 Additional SRO (Panel 9-5) 10.3.2 Additional RO (Control Rod Verification) 10.3.3 Additional Station Operator 10.2.4.2 Utility Staff 1 (Fire Brigade 4) 10.2.4.2 Utility Staff 2 (Fire Brigade 5)

Termination Cue:

This JPM is complete when the candidate determines which additional on-shift positions are required to be filled.

Page 4 of 6

Job Performance Measure Examination JPM #CNS-SRO-2, Revision 0 Information for Candidate Candidate Instructions:

The examiner will explain or provide initial conditions, inform you about which step(s), if any, to discuss or simulate, and will provide initiating and followup cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Condition(s):

• The plant is operating in Mode 2.

• You are taking the watch as Shift Manager during day shift.

• The first reactor feedwater pump discharge valve is scheduled to be opened at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> today.

Initial Cue or Direction:

The following personnel are present on-shift:

• Shift Manager

• Control Room Supervisor

• Licensed Operator (ATCO)

• Licensed Operator (BOP)

• Station Operator (Shift Communicator)

• Station Operator (Fire Brigade)

• Station Operator (Fire Brigade)

• SRO (Observing Panel 9-5)

• Utility Personnel (Fire Brigade)

Are any additional personnel REQUIRED to be on shift? IF SO, determine by position which additional personnel are required. If any on-shift FUNCTIONS (e.g. Shift Communicator, Fire Brigade) are also REQUIRED to be filled, determine which function(s) are required.

If additional personnel or functions are required, record your answer(s) on the attached form.

Page 5 of 6

Job Performance Measure Examination JPM #CNS-SRO-2, Revision 0 Answer Sheet Are any additional personnel REQUIRED to be on shift? IF SO, determine by position which additional personnel are required. If any on-shift FUNCTIONS (e.g. Shift Communicator, Fire Brigade) are also REQUIRED to be filled, determine which function(s) are required.

Position(s) Required Function(s) Required Page 6 of 6

Nebraska Public Power District SKL034-30-28 (7457)

Cooper Nuclear Station Page 1 of 6 Job Performance Measure for Operations Revision 01 Task No.341014O0303

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Task

Title:

Reportable Occurrences to the NRC (#3)

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Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: SIM

2. Appropriate Trainee Level: SRO / STE

3. Evaluation Method: Perform

4. Performance Time: 15 Minutes

5. NRC K/A 2.1.2; 2.1.17; 2.1.20 Directions to Examiner:

1. This JPM evaluates the trainee's ability to perform the required actions for a 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> non-emergency NRC notification due scram that occur during startup prior to criticality.

2. Another instructor in the booth should have a copy of the notification form (Attachment 6) and complete it as the information is relayed over the phone.

3. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space, if desired, by the examiner.

4. Give the trainee his copy of the Directions to the Trainee (Attachment 1) when ready to start the JPM.

5. Brief the trainee and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to determine NRC reportability and make any associated communications. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

Any check of your work by another person will always be in agreement, regardless of the accuracy of your information or action.

Nebraska Public Power District SKL034-30-28 (7457)

Cooper Nuclear Station Page 2 of 6 Job Performance Measure for Operations Revision 01 Task No.341014O0303

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Task

Title:

Reportable Occurrences to the NRC (#3)

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General Conditions:

1. A plant startup was in progress.

2. 15 minutes ago the reactor was approaching criticality when a reactor scram occurred due to an actual high scram discharge volume level (leaking scram outlet valves).

3. All control rods fully inserted on the scram.

4. The lowest RPV water level reached was + 20" (NR).

5. Current reactor coolant temperature is 195/F.

6. Estimated restart date is two days.

7. The Shift Supervisor is unavailable and has delegated you to handle this situation in his place.

8. The board operators are busy with the plant transient and are unavailable to support your evolution. You must personally perform any communications required for this situation.

General

References:

1. Conduct of Operations Procedure 2.0.5 General Tools and Equipment:

1. Site communication System.

2. Communicator Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*".

2. NUREG 1022 Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Nebraska Public Power District SKL034-30-28 (7457)

Cooper Nuclear Station Page 3 of 6 Job Performance Measure for Operations Revision 01 Task No.341014O0303

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Task

Title:

Reportable Occurrences to the NRC (#3)

=========================================================

Initiating Cue(s):

Determine what notification requirements exist for the NRC (if any) and complete any forms and/or communications required by this event (if any).

Nebraska Public Power District SKL034-30-28 (7457)

Cooper Nuclear Station Page 4 of 6 Job Performance Measure for Operations Revision 01 Task No.341014O0303

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Task

Title:

Reportable Occurrences to the NRC (#3)

=========================================================

Performance Checklist Standards Initials

1. Refers to 2.0.5. Refers to body of procedure, Attachment 2 and Attachment 5. _________

2. Determine appropriate Determines a 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report is required (per reporting category per 2.0.5. 50.72(b)(3)(iv)(A) Specified System Actuation). _________*

3. Determine appropriate Determines a 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report is required.

reporting category per _________*

NUREG 1022.

4. Performs step 4.3.3.1 by Time entered on Attachment 7 is the current time.

documenting EVENT TIME Zone is Central Standard Time (Central Daylight _________*

& ZONE Savings Time)

1. CUE: IF asked, the scram occurred 15 minutes ago.

5. Document the time that Include time the condition was reportable and event was determined to be description of the condition. _________*

reportable in the EVENT DESCRIPTION section. #CUE: IF asked, the scram occurred 15 minutes ago.

6. Complete remaining sections Notify resident only, everything is understood, of Attachment 7 Event Systems functional as applicable, Modes 4, no _________*

Notification Worksheet release.

Nebraska Public Power District SKL034-30-28 (7457)

Cooper Nuclear Station Page 5 of 6 Job Performance Measure for Operations Revision 01 Task No.341014O0303

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Task

Title:

Reportable Occurrences to the NRC (#3)

=========================================================

Performance Checklist Standards Initials

7. Ensure report is accurate. Ensures that the report is accurate and properly filled out. _________

1. CUE: Another qualified person has reviewed the report and has signed Attachment 8 that the Event Notification Form has been completed and is accurate. He is now unavailable.

8. Make the report. Calls the NRC using the numbers provided on Attachment 7 and provides all the information on that _________*

NOTE: The other instructor in Attachment 7. In addition he shall record the Event the booth should have a copy of Number and Notification time on Attachment 7.

the notification form (Attachment 7) and complete it # CUE: Read the information back as provided by as the information is relayed the trainee. Then state the event number over the phone. is YY-0076 and the time is (current time).

I have no additional questions at this time.

Nebraska Public Power District SKL034-30-28 (7457)

Cooper Nuclear Station Page 6 of 6 Job Performance Measure for Operations Revision 01 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to determine NRC reportability and make any associated communications. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

Any check of your work by another person will always be in agreement, regardless of the accuracy of your information or action.

General Conditions:

1. A plant startup was in progress.

2. 15 minutes ago the reactor was approaching criticality when a reactor scram occurred due to an actual high scram discharge volume level (leaking scram outlet valves).

3. All control rods fully inserted on the scram.

4. The lowest RPV water level reached was + 20" (NR).

5. Current reactor coolant temperature is 195/F.

6. Estimated restart date is two days.

7. The Shift Supervisor is unavailable and has delegated you to handle this situation in his place.

8. The board operators are busy with the plant transient and are unavailable to support your evolution.

You must personally perform any communications required for this situation.

Initiating Cue(s):

Determine what notification requirements exist for the NRC (if any) and complete any forms and/or communications required by this event (if any).

Nebraska Public Power District SKL034-50-22 (8787)

Cooper Nuclear Station Page 1 of 6 Job Performance Measure for Operations Revision 00 Task No.:299007O0304

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Task

Title:

Determine the Radiological Protection Requirements

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Trainee: Examiner:

Score: Pass Fail Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: Any

2. Appropriate Trainee Levels: RO / SRO / STE

3. Evaluation Method: Simulate

4. Performance Time: 10 minutes

5. NRC K/A 2.3.10 (2.9/3.3)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to determine the radiation protection requirements required to perform CRD system venting.

2. All blanks must be filled out with either initials or an "NP" for "not performed, " and an explanation may also be written in the space if desired by the examiner.

3. Give the trainee his copy of the Directions to the Trainee (Attachment 1) when ready to start the JPM.

4. Brief the trainee and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to determine the radiation protection requirements required to perform CRD Drive System Venting above the HCUs in the Reactor Building 903 South. This includes removal of any tools from the area following task completion.

During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

General Conditions:

1. The plant is shutdown for a refueling outage.

2. The CRD system has been placed in service.

3. CRD Drive System Venting per 2.2.8 is scheduled for this shift.

4. The Area over the CRD HCUs is a radiation area and a contaminated area.

Nebraska Public Power District SKL034-50-22 (8787)

Cooper Nuclear Station Page 2 of 6 Job Performance Measure for Operations Revision 00 Task No.:299007O0304

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Task

Title:

Determine the Radiological Protection Requirements

==========================================================

General

References:

1. Procedure 9.ALARA.4, Radiation Work Permits General Tools and Equipment:

None Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*."

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

3. All RWP requirements checked.

Initiating Cue(s):

Evaluate RWP 20051010 and checkmark the minimum radiological protection requirements needed in order to perform CRD drive system venting.

Nebraska Public Power District SKL034-50-22 (8787)

Cooper Nuclear Station Page 3 of 6 Job Performance Measure for Operations Revision 00 Task No.:299007O0304

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Task

Title:

Determine the Radiological Protection Requirements

==========================================================

Performance Checklist Standards Initials NOTE: Some candidates may not need to perform the first two elements of this JPM due to familiarity with this particular CRD system evolution.

1. Obtains procedure 2.2.8. Obtains the current revision of Procedure 2.2.8.

2. Evaluates procedure 2.2.8 Determines that entry above the CRD HCUs and to determine what actions venting of potentially contaminated fluid is required by are required by procedure. the procedure.

3. Compares the requirements Compares the actions required by Procedure 2.2.8 to of RWP20051010 to actions those specified in the RWP.

required by the CRD drive system venting.

4. Highlights the requirements Highlights the minimum requirements on the RWP.

on the RWP.

• NOTE: The following step is completed by the JPM evaluator ONLY.

5. Compare the highlighted Checkmarked portions of the RWP received from the items on the students copy candidate match the checkmarked portions on

• to those on Attachment one. Attachment 1. (Highlighted portion indicates item the candidate may check but is not required to pass)

Nebraska Public Power District SKL034-50-22 (8787)

Cooper Nuclear Station Page 4 of 6 Job Performance Measure for Operations Revision 00 Task No.:299007O0304

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Task

Title:

Determine the Radiological Protection Requirements

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ATTACHMENT 1 R W P C A T E G O R Y /T Y P E ROUTINE/PSE AL AR M S (M r) C O ND IT IO N RE QU IR IN G SW P SWP / Routine Routine RATE: 1200 HIGH RADIATION AREA DOSE: 30 HIGHLY CONTAM INATED AREA DOSIMET RY REQU IREMENTS U T LD A N D D R D R E Q U IR E D INFORMATION ONLY WORKER INSTRUCTIONS 9 ENSURE HIGH RADIATION AREA BOU NDARY IS IN PLACE UPON ENTRY AN D AT EXIT U CONTACT RP PRIOR TO VENTING OR DRAINING CONTAM INATED SYSTEMS 9 RP MUST BE PRESENT TO REM OVE ITEMS FROM CONTAM INATED AREA (There is a toolbox in each area, no need to remove tools) 9 BREACHING RADIOLOGICAL ROPE BOUN DARY IS NOT ALLOWED U NLESS APPROVED BY RP 9 CONTACT RP PRIOR TO ACCESSING OVERHEAD AREAS U DR ES S R EQ UIR EM EN TS FO R C ON TA M INA TE D A RE A W OR K:

F O LL OW D R E SS R EQ U IR E M E NT S AT S TE P O FF PA D 9 DR ES S R EQ UIR EM EN TS FO R H IGH LY CO NT AM INA TE D A RE A W OR K:

GR EEN S, H I-TOP S, S HO E R UB BE RS , CO TTO N LIN ER S, S UR GICA LS, R UB BE R G LOV ES ,

D O U B LE C O TT O N C OV E RA LL S. A S IN G LE FR A M /N Y LO N S U IT M A Y B E U S E D IN LIEU OF 2 PAIR OF COVERALLS. A SINGLE FRAM/NYLON SUIT OR COTTON CO VERALLS W ITH A W AT ER RE SIST AN T S UIT IS RE QU IRED FO R W OR KIN G IN W ET E NV IRO NM EN TS .

U TAPE WRIST AND ANKLES 9 INFORMATION ONLY IF DIGITA L DO SIM ETE R A LAR M S, P LAC E EQ UIPM EN T IN A SA FE C ON DITIO N, INFORM O THERS, EXI T AREA AND CON TACT RP. (conditional) 9 DOUBLE STEP-OFF-PAD -ADD A PAIR OF HI-TOPS PLACE PD-1 & TLD IN BAG W/BETA WINDOW OUTWARD AND SECURE ON OUTSIDE OF COVERALLS DRESS REQUIREMENTS FOR TOURS IN HCA' S: FULL SET OF PC'S W /FLIGH T C AP .

U WORKERS MUST PERIODICALLY CHECK THEIR DOSIMETER RP PERSONEL INSTRUCTIONS CONTINUOUS COVERAGE REQUIRED FOR WORK IN AREAS > 1,000 MREM/HOUR AT 12" LOCKED HIGH RADIATION AREA -ENSURE D O O R IS LO C K ED L OC K ED H IG H R AD IA T IO N A R EA -C O N T RO LL ED A C C ES S TO A R EA R EQ U IR E D ATTENDANCE COVERAGE REQ UIRED FOR ENTRY INTO LOCKED HIGH RADIATION AREAS IF AIRBORNE CONCENTRATIONS EXCEED 30% OF A DAC, STOP WORK AND EVALUATE ENGINEERING CONTROLS FOR ADEQUACY AN D PO SS IBL E R W P R EV ISIO N . A LL E N TR IES IN TO H RA'S AN D LH RA'S REQ U IRE A P RE-JO B BRIEF IN G B Y AN RP T EC H N ICIA N U SIN G TH E RP -800 FO RM PRIO R TO EN TRY . BRIEFIN GS F OR EN TRIES INTO LHR A'S W ILL BE DO CU M EN TED . TH IS BRIEFIN G W ILL INC LUD E ES TA BLISH ED ST AY TIM ES , AN D W OR K A RE AS W ILL HA VE TU RN BA CK DO SE RA TES .

COMMENTS PD-l ALARM SETPOINTS LISTED ARE DEFAULT SETTINGS ONLY. ACTUAL SETPOINTS USED M AY BE DIFFERENT BASED ON TASK(S)

BEING PERFORMED. ACTUAL SETPOINTS WILL BE DISPLAYED WHEN LOGGING ONTO THE RWP. NO SPOT OR MINOR MAINTENANCE TO BE PERFORMED ON THIS SWP. REV #4 -BASED ON CHANGES TO RP & WORKER I S R EQ UIR EM EN TS . .

Nebraska Public Power District SKL034-50-22 (8787)

Cooper Nuclear Station Page 5 of 6 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to determine the radiation protection requirements required to perform CRD Drive System Venting above the HCUs in the Reactor Building 903 South. This includes removal of any tools from the area following task completion.

During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation.

General Conditions:

1. The plant is shutdown for a refueling outage.

2. The CRD system has been placed in service.

3. CRD Drive System Venting per 2.2.8 is scheduled for this shift.

4. The Area over the CRD HCUs is a radiation area and a contaminated area.

Initiating Cues:

Evaluate RWP 20051010 and checkmark the minimum radiological protection requirements neede d in order to perform CRD drive system venting.

Nebraska Public Power District SKL034-50-22 (8787)

Cooper Nuclear Station Page 6 of 6 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 RWP# TASK# R E V I SI O N B U IL D IN G E L E V A T IO N AREA 20051010 01 04 RCA ALL V A R IO U S INFORMATION ONLY RWP TITLE TASK TITLE OPERATOR ROUNDS IN SWP AREAS MIGRATED TASK DATA W O R K D E S C R I P T IO N OPERATOR ROUNDS IN SWP AREAS M AX RA D LE VELS (mrem /hr) 2200@CON TACT 1400@1 2" 200@ G E N ER A L R O O M CO NT AC T R P F OR CU RR EN T R AD IOL OG ICA L C ON DIT ION S!!!

R W P C A T E G O R Y /T Y P E ROUTINE/PSE AL AR M S (M r) C O ND IT IO N RE QU IR IN G SW P SWP / Routine Routine RATE: 1200 HIGH RADIATION AREA DOSE: 30 HIGHLY CONTAM INATED AREA DOSIMETRY REQUIREMENTS 9 T LD A N D D R D R E Q U IR E D WORKER INSTRUCTIONS 9 ENSURE HIGH RADIATION AREA BOU NDARY IS IN PLACE UPON ENTRY AN D AT EXIT 9 CONTACT RP PRIOR TO VENTING OR DRAINING CONTAM INATED SYSTEMS 9 RP MUST BE PRESENT TO REMOVE ITEMS FROM CONTAMINATED AREA 9 BREACHING RADIOLOGICAL ROPE BOUN DARY IS NOT ALLOWED U NLESS APPROVED BY RP 9 CONTACT RP PRIOR TO ACCESSING OVERHEAD AREAS 9 DR ES S R EQ UIR EM EN TS FO R C ON TA M INA TE D A RE A W OR K:

F O LL OW D R E SS R EQ U IR E M E NT S AT S TE P O FF PA D 9 DR ES S R EQ UIR EM EN TS FO R H IGH LY CO NT AM INA TE D A RE A W OR K:

GR EEN S, H I-TOP S, S HO E R UB BE RS , CO TTO N LIN ER S, S UR GICA LS, R UB BE R G LOV ES ,

D O U B LE C O TT O N C OV E RA LL S. A S IN G LE FR A M /N Y LO N S U IT M A Y B E U S E D IN LIEU OF 2 PAIR OF COVERALLS. A SINGLE FRAM/NYLON SUIT OR COTTON CO VERALLS W ITH A W AT ER RE SIST AN T S UIT IS RE QU IRED FO R W OR KIN G IN W ET E NV IRO NM EN TS .

9 TAPE WRIST AND ANKLES 9 IF DIGITA L DO SIM ETE R A LAR M S, P LAC E EQ UIPM EN T IN A SA FE C ON DITIO N, INFO RM OT HE RS , EX I T AR EA AN D C ON TA CT RP .

9 DOUBLE STEP-OFF-PAD -ADD A PAIR OF HI-TOPS PLACE PD-1 & TLD IN BAG W/BETA WINDOW OUTWARD AND SECURE ON OUTSIDE OF COVERALLS DRESS REQUIREMENTS FOR TOURS IN HCA' S: FULL SET OF PC'S W /FLIGH T C AP .

9 WORKERS MUST PERIODICALLY CHECK THEIR DOSIMETER RP PERSONEL INSTRUCTIONS CONTINUOUS COVERAGE REQUIRED FOR WORK IN AREAS > 1,000 MREM/HOUR AT 12" LOCKED HIGH RADIATION AREA -ENSURE D O O R IS LO C K ED L OC K ED H IG H R AD IA T IO N A R EA -C O N T RO LL ED A C C ES S TO A R EA R EQ U IR E D ATTENDANCE COVERAGE REQ UIRED FOR ENTRY INTO LOCKED HIGH RADIATION AREAS IF AIRBORNE CONCENTRATIONS EXCEED 30% OF A DAC, STOP WORK AND EVALUATE ENGINEERING CONTROLS FOR ADEQUACY AN D PO SS IBL E R W P R EV ISIO N . A LL E N TR IES IN TO H RA'S AN D LH RA'S REQ U IRE A P RE-JO B BRIEF IN G B Y AN RP T EC H N ICIA N U SIN G INFORMATION ONLY TH E RP -800 FO RM PRIO R TO EN TRY . BRIEFIN GS F OR EN TRIES INTO LHR A'S W ILL BE DO CU M EN TED . TH IS BRIEFIN G W ILL INC LUD E ES TA BLISH ED ST AY TIM ES , AN D W OR K A RE AS W ILL HA VE TU RN BA CK DO SE RA TES .

COMMENTS PD-l ALARM SETPOINTS LISTED ARE DEFAULT SETTINGS ONLY. ACTUAL SETPOINTS USED M AY BE DIFFERENT BASED ON TASK(S)

BEING PERFORMED. ACTUAL SETPOINTS WILL BE DISPLAYED WHEN LOGGING ONTO THE RWP. NO SPOT OR MINOR MAINTENANCE TO BE PERFORMED ON THIS SWP. REV #4 -BASED ON CHANGES TO RP & WORKER I S R EQ UIR EM EN TS . .

PREPARED BY DATE APPROVED BY DATE R. ENGE BRETS ON 3/01/05 TJFRAN CIS 3/01/05

Job Performance Measure Examination JPM #RO-ADMIN-4, Revision 0 Radiation Control, Perform Dose Assessment (#3)

System Administrative Mode 3 Estimated Time 10 minutes Location Simulator Evaluation Method(s) Perform the Calculation using PMIS and Simulator Alternate Path No

References:

EPIP 5.7.17, Dose Assessment, Revision 32 Examiner Trainee Observer Examination Date Result: SATISFACTORY UNSATISFACTORY Page 1 of 7

Job Performance Measure Examination JPM #RO-ADMIN-4, Revision 0 Examiner Directions to Candidate:

I will explain or provide initial conditions, inform you about which step(s) to discuss or simulate (if any), and provide initiating and followup cues. It is necessary that you verbalize your actions and, for simulations, request information concerning indications and expected responses to your actions. When you complete the task, the objective for this job performance measure will be satisfied.

Task Evaluation Standard(s):

• Procedure 5.7.17.

• Integrated Dose (TEDE, CDE) and Downwind Affected Sectors as calculated by the Candidate using CNS Dose matches the example CNS Dose Report Answer Key (Attachment 1).

• This task must be completed in less than 15 minutes in order to supply information needed to perform an emergency notification Safety Considerations:

• There are no safety considerations associated with performing this JPM.

Performance Consequences:

• Incorrect usage of CNS Dose could result in the Emergency Director (Shift Manager) making an inaccurate protective action recommendation to offsite authorities.

Tools and Methods:

• PMIS Terminal (located in the Simulator)

• Necessary data to be acquired from PMIS and simulator Control Boards, as necessary.

Human Interfaces:

• The examiner plays the role of Shift Manager (Emergency Director) in the Control Room.

Examiner Notes:

• The Turbine Building release point results in a ground-level release. The 10 meter meteorological data is the appropriate data for performing the dose projection. A wind direction of 255/ results in CDE being the affected downwind sectors.

• If the candidate uses the 100 meter meteorological data, a wind direction of 265/ results in DEF being the affected downwind sectors.

• The candidate is to obtain all required numerical information from the simulator / PMIS except for 10 meter and 100 meter wind direction and wind speed, which are given in the initial conditions. This is because the simulator forces the 10 meter and 100 meter data for these points be the same.

• The candidate is required to determine core status from data available in the simulator using their event and system knowledge.

Page 2 of 7

Job Performance Measure Examination JPM #RO-ADMIN-4, Revision 0 Initial Condition(s):

• A GENERAL EMERGENCY was declared 2 minutes ago under EAL 2.4.1

• The reactor has been shutdown for 45 minutes

• A release is in progress through the Turbine Building, due to a steam line break with open MSIVs in one line

• The STE estimates it will take 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to depressurize and stop the release

• Point MET023, 10M Lvl. Wind Direction (15 Min. Avg.) = 255.3/

• Point MET024, 10M Lvl. Wind Speed (15 Min. Avg.) = 12 mph

• Point MET006, 100M Lvl. Wind Direction (15 Min. Avg.) = 265.8

• Point MET007. 100M Lvl. Wind Speed (15 Min. Avg.) = 13.8 mph Provide the Candidate initial conditions located at page 6 of 7 Terminating Condition(s):

• The Candidate provides a completed CNS Dose Report to the Examiner.

Simulator Setup:

A. Initialize the simulator to IC20, and batch file ************

B. Set malfunctions as follows:

Malfunction Title Trigger TD Value Ramp IMF ms07d MSIV Failure AOV80D A 0 True 0 IMF ms07h MSIV Failure AOV86D A 0 True 0 IMF cro3 Fuel Cladding Failure A 0 100% 0 IMF rr31a Recirc Suction Loop A Rupture A 0 50% 0 IMF MS10 Steam Line Break in Turbine Bldg. A 0 15% 0 IRF HV02 Wind Speed A 0 12 mph 0 IRF HV03 Wind Direction A 0 255 DEG 0 IRF HV17 100m Temperature A 0 74 DEG 0 IRF HV18 Sigma Theta A 0 95 DEG 0 IRF HV19 60m Temperature A 0 74 DEG 0 Page 3 of 7

Job Performance Measure Examination JPM #RO-ADMIN-4, Revision 0 Initiating Cue:

The Shift Manager directs you to perform a computer dose projection using PMIS and to provide him with a printed copy of the completed dose projection.

Candidate Action Evaluation Standard Obtains procedure 5.7.17 Current procedure 5.7.17 (Revision 32)

Starts dose projection program on PMIS DOSE entered on PMIS terminal Selects origin of release TURBINE BUILDING is selected Enters the release rate 1.5E+6 :Ci/s (NG) is entered Selects SBGT status NO is entered Enters the release duration 3 HOURS is entered Determines core status Determines that CORE IS DEGRADED based on either (1) Main Steam Line Radiation Monitor(s) > 1500 mR/h or in Hi-Hi alarm, or (2) Drywell radiation levels > 1000 R/h Enters degraded core status YES is selected Enters wind direction 255.3 DEG is entered from the 10m Tower Enters wind speed 12 MPH is entered from the 10m Tower Enters stability class D is entered Enters time since reactor shutdown 0.8 HRS is entered Enters status of release through Reactor NO is entered Building Calculated dose projection results RESULTS is selected using F3 key Prints dose projection results PRINT is selected using F5 key and printer is selected (default)

Provides Emergency Director (Shift Printed dose projection is provided to Manager) the completed dose projection Examiner Page 4 of 7

Job Performance Measure Examination JPM #RO-ADMIN-4, Revision 0 Comments:

Termination Cue:

The Candidate provides a printed dose projection report from CNS Dose.

Page 5 of 7

Job Performance Measure Examination JPM #RO-ADMIN-4, Revision 0 Information for Candidate Candidate Instructions:

The examiner will explain or provide initial conditions, inform you about which step(s), if any, to discuss or simulate, and will provide initiating and followup cues. It is necessary that you verbalize your actions and, for simulations, specifically request information concerning indications and expected responses to your actions. When you complete the task, the objective for this job performance measure will be satisfied.

Initial Condition(s):

• A GENERAL EMERGENCY was been declared 2 minutes ago under EAL 2.4.1

• The reactor has been shutdown for 45 minutes

• A release is in progress through the Turbine Building, due to a steam line break with open MSIVs in one line

• The STE estimates it will take 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to depressurize and stop the release

• Point MET023, 10M Lvl. Wind Direction (15 Min. Avg.) = 255.3/

• Point MET024, 10M Lvl. Wind Speed (15 Min. Avg.) = 12 mph

• Point MET006, 100M Lvl. Wind Direction (15 Min. Avg.) = 265.8

• Point MET007. 100M Lvl. Wind Speed (15 Min. Avg.) = 13.8 mph Initial Cue or Direction:

• The Shift Manager directs you to perform a computer dose projection using PMIS and to provide him with a printed copy of the completed dose projection.

Page 6 of 7

Job Performance Measure Examination JPM #RO-ADMIN-4, Revision 0 JPM #RO-ADMIN-4, Revision 0 Attachment 1 Answer Key Affected Downwind Sectors C, D, E CNS Dose Results Distance from Plant Projected Dose, rem TEDE Thyroid CDE 1 mile 1.68E-01 2.57E+00 2 miles 5.85E-02 8.97E-01 5 miles 1.64E-02 2.51E-01 10 miles 6.80E-03 1.04E-01 Page 7 of 7

Nebraska Public Power District SKL034-50-34 (9584)

Cooper Nuclear Station Page 1 of 15 Job Performance Measure for Operations Revision 01 Task No.: 299012O0301

==========================================================

Task

Title:

Develop, Verify & Implement Tagouts (Alt Path)

==========================================================

Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

NOTE: THIS IS AN ALTERNATE PATH JPM. THE MOTOR HEATER CIRCUIT AND THE CST SUCTION VALVE ARE OMITTED FROM THIS CLEARANCE ORDER.

Additional Program Information:

1. Appropriate Performance Locations: CR, SIM, EOF

2. Appropriate Trainee level: RO

3. Evaluation Method: Perform

4. Performance Time: 15 minutes

5. NRC K/A 2.1.23 (3.9/4.0)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to perform an RO review of a Tagout.

2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.

3. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space if desired by the examiner.

4. Brief the trainee, place the simulator in run, and tell the trainee to begin.

5. Hand the candidate ATTACHMENT 1.

Directions to Trainee:

When I tell you to begin, you are to perform an RO review of this Tagout. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

==========================================================

Nebraska Public Power District SKL034-50-34 (9584)

Cooper Nuclear Station Page 2 of 15 Job Performance Measure for Operations Revision 01 Task No.: 299012O0301

==========================================================

Task

Title:

Develop, Verify & Implement Tagouts (Alt Path)

==========================================================

General Conditions:

1. The plant is operating at 100% power.

2. The A Core Spray Pump and Motor are damaged and require maintenance.

3. Clearance Order CSA-1-1234567 CS-P-A has just been written and requires an independent review.

4. NOMS is unavailable.

General

References:

1. Procedure 0.9 Tagout General Tools and Equipment:

1. None Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*".

2. Simulator cues denoted by "#".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

(RO) You are to review the provided Tagout as the Verifier. If necessary make any corrections in pencil on the Tagout form provided. Inform the CRS when the review is complete.

Nebraska Public Power District SKL034-50-34 (9584)

Cooper Nuclear Station Page 3 of 15 Job Performance Measure for Operations Revision 01 Task No.: 299012O0301

==========================================================

Task

Title:

Develop, Verify & Implement Tagouts (Alt Path)

==========================================================

Performance Checklist Standards Initials

1. Refer to Procedure. Refers to Procedure 0.9.

2. Reviews the provided Determines the components to be tagged for the Tagout for applicable planned activities. ________

components to be tagged.

3. Determines that the Determines that the Core Spray Motor Heater should Motor Heater and CST have been included on the original Tagout along with ________*

suction valve have been the Core Spray CST Suction CS-V-66 and added them omitted and adds them to to the Tagout.

the Tagout.

4. Determines the required Determines the required position for each of the position for each of the components listed on the provided Tagout and adds the ________*

components and adds the new positions for the Motor Heater and the CST new positions for the Suction valve.

Motor Heater and the CST Suction valve.

Nebraska Public Power District SKL034-50-34 (9584)

Cooper Nuclear Station Page 4 of 15 Job Performance Measure for Operations Revision 01 Performance Checklist Standards Initials

5. Determines the required Determines the required sequence for each of the sequence for each of the components and adds the new sequence for the Motor ________*

components and adds the Heater and the CST Suction valve.

new sequence for the Motor Heater and the CST Suction valve.

6. Notifies CRS. The trainee informs the CRS that the Tagout has been ________

reviewed.

CUE: As the CRS, acknowledge the report.

Section Coversheet Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2005 14:17 Component to be Worked:

CS-P -A CORE SPRAY PUM P A R-859-NE QUAD

==

Description:==

Fo r Training U se Only Rebuild Pump. Replace Motor Special Instructions Wo rker Notes Release Notes Section Attributes:

MRRS LCO ACTION REQ UIRED Attribute Description KEY Perform Valve Lineup prior to releasing clearance Attribute Value YES YES FIRE IMPAIRMENT REQ UIRED NO CONT AINMENT AFFECTED NO REQUIRED PLANT CONDITION EQUIPMENT OUT OF SERVICE W ork O rder List:

Section Verification:

Status Description User Verification Da te Section Prepared Michael Barton To days date Section Verified Section Authorized Equip. Ready for Maintenance Release Prepared Release Verified Release Authorized Section C om plete Tem porary Sa fety Dev ices List:

Page 1 of 1

Section Tag List Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2005 14:17 Tag Tag Type Equipment Ver. Pla. Placement Place. 1st Pla ce . 2 n d Re st. Restoration As L eft Re st. 1 st Re st. 2 n d Tag Tag Serial Equipment Description Req. Seq. Configuration Ve rif Ve rif Seq. Configuration Configuration Ve rif Ve rif Placement Removal No. D a te /T im e D a te /T im e D a te /T im e Notes Notes Equipment Location D a te /T im e 0 Danger *CS-SW-S5A 1 PULL TO 23 NORM AL NORM AL

• CONTROL SWITCH LOCK AFTER AFTER FOR CS PUMP A STOP STOP

• CONTROL ROOM PANEL 9-3 0 Danger *CS-SW-S2A 2 NORM AL 22 NORM AL NORM AL

• CONTROL SWITCH AFTER AFTER AFTER FOR CS-MO-11A, CLOSED OPEN OPEN OUTBD INJECTION VLV

• CONTROL ROOM PANEL 9-3 KEY 0 Danger *CS-SW-S1A 3 NORM AL 21 NORM AL NORM AL

• CONTROL SWITCH AFTER AFTER AFTER FOR CS-MO-12A, INJ CLOSED CLOSED CLOSED THROTTLE VLV

• CONTROL ROOM PANEL 9-3 0 Danger *CS-SW-S4A 4 NORM AL 20 NORM AL NORM AL

• CONTROL SWITCH AFTER AFTER AFTER FOR CS-MO-26A, CLOSED CLOSED CLOSED TEST LINE RECIRC VLV

• CONTROL ROOM PANEL 9-3 0 Danger *CS-SW-S7A 5 CLOSED 19 KEYLOCK KEYLOCK

• CONTROL SWITCH ED OPEN ED OPEN FOR CS-MO-7A, PUMP TORUS SUCTION VLV

• CONTROL ROOM PANEL 9-3

• C-932 (VBD-R)

Page 1 of 4

Section Tag List Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2003 14:17 Tag Tag Type Equipment Ver. Pla. Placement Place. 1st Pla ce . 2 n d Re st. Restoration As L eft Re st. 1 st Re st. 2 n d Tag Tag Serial Equipment Description Req. Seq. Configuration Ve rif Ve rif Seq. Configuration Configuration Ve rif Ve rif Placement Removal No. D a te /T im e D a te /T im e D a te /T im e Notes Notes Equipment Location D a te /T im e 0 Danger *EE-CB-4160F 6 RACKED 18 RACKED RACKED (CSP1A) OUT IN IN

• CORE SPRAY PUMP A ***THIS COMPONENT HAS A MOTOR HEATER***

• 4160 V F CRITICAL SWGR RM 0 Danger *EE-PNL-SPR1(7) 7 OFF 17 ON ON

• CS PUMP MOTOR HEATER AND ELAPSED TIME METER KEY

• CRIT SWGR ROOM F, SOUTH WALL 0 Danger *EE-MCC-Q(5D) 8 OFF 16 ON ON

• CS-MO-11A CS LOOP A OUTBD INJECTION

• MCC-Q RX BLDG 903 NORTH WEST 0 Danger *EE-MCC-Q(6A) 9 OFF 15 ON ON

• CS-MO-12A CS LOOP A INBD INJECTION

• MCC-Q RX BLDG 903 NORTH WEST 0 Danger *EE-MCC-Q(10B) 10 OFF 14 ON ON

• CS-MO-26A CS LOOP A TEST LINE RECIRC

• MCC-Q RX BLDG 903 NORTH WEST 0 Danger *EE-MCC-Q(5C) 11 OFF 13 ON ON

• CS-MO-7A CS PUMP A SUCTION

• MCC-Q RX BLDG 903 NORTH WEST Page 2 of 4

Section Tag List Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2003 14:17 nd st nd Tag Tag Type Equipment Ver. Pla. Placement Place. 1st Pla ce . 2 Re st. Restoration As L eft Re st. 1 Re st. 2 Tag Tag Serial Equipment Description Req. Seq. Configuration Ve rif Ve rif Seq. Configuration Configuration Ve rif Ve rif Placement Removal No. D a te /T im e D a te /T im e D a te /T im e Notes Notes Equipment Location D a te /T im e 0 Danger *CS-MOV-M011A 12 DO NOT 12 PULL TAG PULL TAG

• CS SYSTEM A OPERATE INJECTION THROTTLE

• CS A INJECT VALVE PLATFORM 0 Danger CS-MOV-M012A 13 DO NOT 11 PULL TAG PULL TAG

• CS SYSTEM A OPERATE INJECTION BLOCK

• CS A INJECT VALVE PLATFORM 0 Danger CS-MOV-M026A 14 DO NOT 10 PULL TAG PULL TAG

• CS SYSTEM A TEST KEY OPERATE LINE ISOLATION

• RCIC (NE) QUAD MID LEVEL 0 Danger CS-MOV-M07A 15 DO NOT 9 PULL TAG PULL TAG

• CS PUMP A OPERATE SUCTION

• RCIC (NE) QUAD LOWER LEVEL 0 Danger CS-V-26 16 CLOSED 8 SEALED SEALED

• CS PUMP A OPEN OPEN DISCHARGE CHECK BYPASS

• RCIC (NE) QUAD LOWER LEVEL 0 Danger CS-V-24A 17 CLOSED 7 SEALED SEALED

• CS PUMP A MIN CLOSED CLOSED FLOW RECIRC

• RCIC (NE) QUAD LOWER LEVEL 0 Danger CS-V-66 18 CLOSED 7 SEALED SEALED

• CS PUMP A CLOSED CLOSED CONDENSATE SUPPLY

• RCIC (NE) QUAD LOWER LEVEL Page 3 of 4

Section Tag List Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2003 14:17 nd st nd Tag Tag Type Equipment Ver. Pla. Placement Place. 1st Pla ce . 2 Re st. Restoration As L eft Re st. 1 Re st. 2 Tag Tag Serial Equipment Description Req. Seq. Configuration Ve rif Ve rif Seq. Configuration Configuration Ve rif Ve rif Placement Removal No. D a te /T im e D a te /T im e D a te /T im e Notes Notes Equipment Location D a te /T im e 0 Danger CM-V-40 19 CLOSED 6 CLOSED CLOSED

• PCV-73A OUTLET

• RX BLDG 931 NORTH EAST 0 Danger CM-V-41 20 CLOSED 5 OPEN OPEN

• PCV-73A BYPASS

• RX BLDG 931 NORTH EAST 0 Danger CS-V-20 21 OPEN 4 CLOSED CLOSED

• CS PUMP A DRAIN ROOT

• RCIC QUAD (NE)

KEY LOWER LEVEL 0 Danger CS-V-21 22 OPEN 3 CLOSED CLOSED

• CS PUMP A DRAIN SHUTOFF

• RCIC QUAD (NE)

LOWER LEVEL 0 Danger CS-V-16 23 OPEN 2 CLOSED CLOSED

• CS PUMP A VENT ROOT

• RCIC QUAD (NE)

LOWER LEVEL 0 Danger CS-V-17 24 OPEN 1 CLOSED CLOSED

• CS PUMP A VENT SHUTOFF

• RCIC QUAD (NE)

LOWER LEVEL Page 4 of 4

Nebraska Public Power District SKL034-50-34 (9584)

Cooper Nuclear Station Page 10 of 15 Job Performance Measure for Operations Revision 01 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to review the provided Clearance Order CSA-1-1234567 CS-P-A as the Originator. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them in order to complete the assigned task.

General Conditions:

1 The plant is operating at 100% power.

2. The A Core Spray Pump and Motor are damaged and require maintenance.

3. Clearance Order CSA-1-1234567 CS-P-A has just been written and requires a review.

4. NOMS is unavailable.

Initiating Cues:

(RO) You are to review the provided Tagout as the Verifier. If necessary make any corrections in pencil on the Tagout form provided. Inform the CRS when the review is complete.

Section Coversheet Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2005 14:17 Component to be Worked:

CS-P -A CORE SPRAY PUM P A R-859-NE QUAD

==

Description:==

Fo r Training U se Only Rebuild Pump. Replace Motor Special Instructions Wo rker Notes Release Notes Perform Valve Lineup prior to releasing clearance Section Attributes:

Attribute Attribute Description Value MRRS YES LCO ACTION REQ UIRED YES FIRE IMPAIRMENT REQ UIRED NO CONT AINMENT AFFECTED NO REQUIRED PLANT CONDITION EQUIPMENT OUT OF SERVICE W ork O rder List:

Section Verification:

Status Description User Verification Da te Section Prepared Michael Barton To days date Section Verified Section Authorized Equip. Ready for Maintenance Release Prepared Release Verified Release Authorized Section C om plete Tem porary Sa fety Dev ices List:

Page 1 of 1

Section Tag List Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2005 14:17 Tag Tag Type Equipment Ver. Pla. Placement Place. 1st Pla ce . 2 n d Re st. Restoration As L eft Re st. 1 st Re st. 2 n d Tag Tag Serial Equipment Description Req. Seq. Configuration Ve rif Ve rif Seq. Configuration Configuration Ve rif Ve rif Placement Removal No. D a te /T im e D a te /T im e D a te /T im e Notes Notes Equipment Location D a te /T im e 0 Danger *CS-SW-S5A 1 PULL TO 23 NORM AL NORM AL

• CONTROL SWITCH LOCK AFTER AFTER FOR CS PUMP A STOP STOP

• CONTROL ROOM PANEL 9-3 0 Danger *CS-SW-S2A 2 NORM AL 22 NORM AL NORM AL

• CONTROL SWITCH AFTER AFTER AFTER FOR CS-MO-11A, CLOSED OPEN OPEN OUTBD INJECTION VLV

• CONTROL ROOM PANEL 9-3 0 Danger *CS-SW-S1A 3 NORM AL 21 NORM AL NORM AL

• CONTROL SWITCH AFTER AFTER AFTER FOR CS-MO-12A, INJ CLOSED CLOSED CLOSED THROTTLE VLV

• CONTROL ROOM PANEL 9-3 0 Danger *CS-SW-S4A 4 NORM AL 20 NORM AL NORM AL

• CONTROL SWITCH AFTER AFTER AFTER FOR CS-MO-26A, CLOSED CLOSED CLOSED TEST LINE RECIRC VLV

• CONTROL ROOM PANEL 9-3 0 Danger *CS-SW-S7A 5 CLOSED 19 KEYLOCK KEYLOCK

• CONTROL SWITCH ED OPEN ED OPEN FOR CS-MO-7A, PUMP TORUS SUCTION VLV

• CONTROL ROOM PANEL 9-3

• C-932 (VBD-R)

Page 1 of 5

Section Tag List Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2003 14:17 Tag Tag Type Equipment Ver. Pla. Placement Place. 1st Pla ce . 2 n d Re st. Restoration As L eft Re st. 1 st Re st. 2 n d Tag Tag Serial Equipment Description Req. Seq. Configuration Ve rif Ve rif Seq. Configuration Configuration Ve rif Ve rif Placement Removal No. D a te /T im e D a te /T im e D a te /T im e Notes Notes Equipment Location D a te /T im e 0 Danger *EE-CB-4160F 6 RACKED 18 RACKED RACKED (CSP1A) OUT IN IN

• CORE SPRAY PUMP A ***THIS COMPONENT HAS A MOTOR HEATER***

• 4160 V F CRITICAL SWGR RM 0 Danger *EE-MCC-Q(5D) 7 OFF 16 ON ON

• CS-MO-11A CS LOOP A OUTBD INJECTION

• MCC-Q RX BLDG 903 NORTH WEST 0 Danger *EE-MCC-Q(6A) 8 OFF 15 ON ON

• CS-MO-12A CS LOOP A INBD INJECTION

• MCC-Q RX BLDG 903 NORTH WEST 0 Danger *EE-MCC-Q(10B) 9 OFF 14 ON ON

• CS-MO-26A CS LOOP A TEST LINE RECIRC

• MCC-Q RX BLDG 903 NORTH WEST 0 Danger *EE-MCC-Q(5C) 10 OFF 13 ON ON

• CS-MO-7A CS PUMP A SUCTION

• MCC-Q RX BLDG 903 NORTH WEST Page 2 of 5

Section Tag List Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2003 14:17 nd st nd Tag Tag Type Equipment Ver. Pla. Placement Place. 1st Pla ce . 2 Re st. Restoration As L eft Re st. 1 Re st. 2 Tag Tag Serial Equipment Description Req. Seq. Configuration Ve rif Ve rif Seq. Configuration Configuration Ve rif Ve rif Placement Removal No. D a te /T im e D a te /T im e D a te /T im e Notes Notes Equipment Location D a te /T im e 0 Danger *CS-MOV-M011A 11 DO NOT 12 PULL TAG PULL TAG

• CS SYSTEM A OPERATE INJECTION THROTTLE

• CS A INJECT VALVE PLATFORM 0 Danger CS-MOV-M012A 12 DO NOT 11 PULL TAG PULL TAG

• CS SYSTEM A OPERATE INJECTION BLOCK

• CS A INJECT VALVE PLATFORM 0 Danger CS-MOV-M026A 13 DO NOT 10 PULL TAG PULL TAG

• CS SYSTEM A TEST OPERATE LINE ISOLATION

• RCIC (NE) QUAD MID LEVEL 0 Danger CS-MOV-M07A 14 DO NOT 9 PULL TAG PULL TAG

• CS PUMP A OPERATE SUCTION

• RCIC (NE) QUAD LOWER LEVEL 0 Danger CS-V-26 15 CLOSED 8 SEALED SEALED

• CS PUMP A OPEN OPEN DISCHARGE CHECK BYPASS

• RCIC (NE) QUAD LOWER LEVEL 0 Danger CS-V-24A 16 CLOSED 7 SEALED SEALED

• CS PUMP A MIN CLOSED CLOSED FLOW RECIRCULATION

• RCIC (NE) QUAD LOWER LEVEL 0 Danger CM-V-41 17 CLOSED 5 OPEN OPEN

• PCV-73A BYPASS

• RX BLDG 931 NORTH EAST Page 3 of 4

Section Tag List Tagout: CLEARANCE ORDER Section : CSA-1-123 4567 C S-P-A 07/01/2003 14:17 nd st nd Tag Tag Type Equipment Ver. Pla. Placement Place. 1st Pla ce . 2 Re st. Restoration As L eft Re st. 1 Re st. 2 Tag Tag Serial Equipment Description Req. Seq. Configuration Ve rif Ve rif Seq. Configuration Configuration Ve rif Ve rif Placement Removal No. D a te /T im e D a te /T im e D a te /T im e Notes Notes Equipment Location D a te /T im e 0 Danger CS-V-20 18 OPEN 4 CLOSED CLOSED

• CS PUMP A DRAIN ROOT

• RCIC QUAD (NE)

LOWER LEVEL 0 Danger CS-V-21 19 OPEN 3 CLOSED CLOSED

• CS PUMP A DRAIN SHUTOFF

• RCIC QUAD (NE)

LOWER LEVEL 0 Danger CS-V-16 20 OPEN 2 CLOSED CLOSED

• CS PUMP A VENT ROOT

• RCIC QUAD (NE)

LOWER LEVEL 0 Danger CS-V-17 21 OPEN 1 CLOSED CLOSED

• CS PUMP A VENT SHUTOFF

• RCIC QUAD (NE)

LOWER LEVEL Page 5 of 5

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 1 of 11 Job Performance Measure for Operations Revision 00 Task No.: 299015O0301

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Task

Title:

Perform RO Review of Daily Logs (Alt Path)

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Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

NOTE: This is an ALTERNATE PATH JPM.

Additional Program Information:

1. Appropriate Performance Location: SIM / Classroom

2. Appropriate Trainee level: RO

3. Evaluation Method: Perform

4. Performance Time: 10 minutes

5. NRC K/A 2.1.23 (3.9/4.0)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to perform an RO review of the daily logs.

2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.

3. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space if desired by the examiner.

4. Brief the trainee, place the simulator in run, and tell the trainee to begin.

5. Hand the candidate the correct ATTACHMENT, 1 for use in the Simulator.

2 for use in the Classroom.

Directions to Trainee:

When I tell you to begin, you are to perform an RO review of the daily logs. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to complete the assigned task.

==========================================================

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 2 of 11 Job Performance Measure for Operations Revision 00 Task No.: 299015O0301

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Task

Title:

Perform RO Review of Daily Logs (Alt Path)

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General Conditions:

1. The plant is operating at 100% power.

NOTE: only provide the 19:00 reading when performing this in the classroom.

2. The 19:00 readings from PC-TR-24 are: PC-TR-25 are:

Pt. 0 = 95°F Pt. 0 = 96°F Pt. 1 = 90°F Pt. 1 = 91°F Pt. 2 = 94°F Pt. 2 = 92°F Pt. 3 = 95°F Pt. 3 = 95°F Pt. 4 = 92°F Pt. 4 = 93°F Pt. 5 = 94°F Pt. 5 = 95°F Pt. 6 = 90°F Pt. 6 = 92°F Pt. 7 = 95°F Pt. 7 = 97°F

3. It is 19:00 and the readings from PC-TR-24 need to be entered into 6.LOG.601 General

References:

1. Procedure 6.LOG.601 General Tools and Equipment:

1. None Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*".

2. Simulator cues denoted by "#".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cues:

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 3 of 11 Job Performance Measure for Operations Revision 00 Task No.: 299015O0301

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Task

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Perform RO Review of Daily Logs (Alt Path)

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For the Classroom:

You are to fill out Attachment 15, Torus Average Temperature and Drywell Bulk Average Temperature, for Div I, using the data provided and complete an RO review of the log sheet per 6.LOG.601. Provide the CRS the log sheet when the review is completed.

For the Simulator:

You are to fill out Attachment 15, Torus Average Temperature and Drywell Bulk Average Temperature, for Div I, using the data provided and complete an RO review of the log sheet per 6.LOG.601. Provide the CRS the log sheet when the review is completed.

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 4 of 11 Job Performance Measure for Operations Revision 00 Task No.: 299015O0301

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Task

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Perform RO Review of Daily Logs (Alt Path)

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SIMULATOR SET-UP A. Materials required None B. Initialize the Simulator in any IC that will support full power operation (IC-18, 19 or 20 suggested)

Batch File name - JPM/345048 C. Change the Simulator conditions from those of the IC as follows:

1. Triggers Number File Name Description None

2. Malfunctions Number Title Trigger TD Severity Ramp Initial None N/A N/A N/A N/A N/A

3. Remotes Number Title Trigger TD Value Ramp None N/A N/A N/A N/A

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 5 of 11 Job Performance Measure for Operations Revision 00 Task No.: 299015O0301

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Task

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4. Overrides Instrument Tag Trigger TD Value Ramp zaopctr24A (1) Suppression Pool Temperature A N/A 95 N/A Recorder Pt 0 zaopctr24A (2) Suppression Pool Temperature A N/A 90 N/A Recorder Pt 1 zaopctr24A (3) Suppression Pool Temperature A N/A 94 N/A Recorder Pt 2 zaopctr24A (4) Suppression Pool Temperature A N/A 95 N/A Recorder Pt 3 zaopctr24A (5) Suppression Pool Temperature A N/A 92 N/A Recorder Pt 4 zaopctr24A (6) Suppression Pool Temperature A N/A 94 N/A Recorder Pt 5 zaopctr24A (7) Suppression Pool Temperature A N/A 90 N/A Recorder Pt 6 zaopctr24A (8) Suppression Pool Temperature A N/A 95 N/A Recorder Pt 7 zaopctr25A (1) Suppression Pool Temperature A N/A 96 N/A Recorder Pt 0 zaopctr25A (2) Suppression Pool Temperature A N/A 91 N/A Recorder Pt 1 zaopctr25A (3) Suppression Pool Temperature A N/A 92 N/A Recorder Pt 2 zaopctr25A (4) Suppression Pool Temperature A N/A 95 N/A Recorder Pt 3 zaopctr25A (5) Suppression Pool Temperature A N/A 93 N/A Recorder Pt 4 zaopctr25A (6) Suppression Pool Temperature A N/A 95 N/A Recorder Pt 5 zaopctr25A (7) Suppression Pool Temperature A N/A 92 N/A Recorder Pt 6

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 6 of 11 Job Performance Measure for Operations Revision 00 Task No.: 299015O0301

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Task

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Perform RO Review of Daily Logs (Alt Path)

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zaopctr25A (8) Suppression Pool Temperature A N/A 97 N/A Recorder Pt 7

5. Panel Set-up

a. Place Simulator in RUN.

b. Run batch file JPM/345048

c. Verify that the temperatures readings on PC-TR-24 and PC-TR-25 are those inputted by running the batch file.

Note: If this JPM is to be performed more than once, snap the Simulator into an IC after the panel set-up is complete.

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 7 of 11 Job Performance Measure for Operations Revision 00 Task No.: 299015O0301

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Task

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Perform RO Review of Daily Logs (Alt Path)

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Performance Checklist Standards Initials

1. Refer to 6.LOG.601 Refers to 6.LOG.601 Attachment 15.

2. Record Values. Records PC-TR_24 reading on Attachment 15. ________*

3. Sums OPERABLE Sums reading from PC-TR-24 in appropriate block.

points. ________

4. Calculates Average Divides Sum by total number of OPERABLE points Temperature. and records that value in appropriate block. ________*

5. Performs a review of the While reviewing the data the trainee should indicate Data. that the suppression pool temperature > 92°F, enter the ________*

Conditions and Required Actions of LCO 3.6.2.1 and contact Engineering to determine available instrument margin.

6. Notifies CRS. The trainee informs the CRS that the Div I Average Torus Temperature is above 92°F, and that the ________*

Conditions and Required Actions of LCO 3.6.2.1 needs to be done.

CUE: As the CRS, acknowledge the report.

NOTE: It is not necessary to sign the sign-off and review sheet. Review the completed form and verify it with the KEY provided.

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 8 of 11 Job Performance Measure for Operations Revision 00 Task No.: 299015O0301

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Task

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Perform RO Review of Daily Logs (Alt Path)

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RO DATA SHEET KEY ATTACHMENT 15 TORUS AVERAGE TEMPERATURE AND DRYWELL BULK AVERAGE TEMPERATURE INSTRUMENT 0700-1000 1900-2200 OPERABILITY ATT. 21 LOC NUMBER READING READING LIM IT MAX ) MODES NOTES MCO VBD -J PC-TR-24 POINT 0 95 MCO VBD -J PC-TR-24 POINT 1 90 MCO VBD -J PC-TR-24 POINT 2 94 MCO $ 4 RTDs VBD -J PC-TR-24 POINT 3 95 OPERABLE with no 2 # 6°F (a) 1, 2, 3 27 MCO adjacent RTDs VBD -J PC-TR-24 POINT 4 92 INOP MCO VBD -J PC-TR-24 POINT 5 94 MCO VBD -J PC-TR-24 POINT 6 90 MCO VBD -J PC-TR-24 POINT 7 95 Sum of OPERA BLE points MCO 745 N/A N/A N/A N/A for PC-TR-24 Divide sum of PC-TR-24 MCO by total number of 93.1 # 92°F (b) N/A 1, 2, 3 57 OP ER AB LE points (a) For MAX ) check, compare like points. Examples: Compare PC-TR-24 Point 0 to PC-TR-25 Point 0 or compare PC-TR-24 Point 0 to PMIS Point N031. (PMIS Point to TR-25 point number relationship is available in Surveillance Procedure 6.2PC.303.)

(b) If suppression pool temperature > 92°F during normal operation or > 102°F during testing which adds heat to suppression pool, enter the Conditions and Required Actions of LCO 3.6.2.1, then contact Engineering to determine available instrument margin. If suppression pool temperature >

95°F during normal operation or > 105°F during testing which adds heat to suppression pool, ensure LCO 3.6.2.1 is entered.

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 9 of 11 Job Performance Measure for Operations Revision 00 ATTACHMENT 1 For use in Simulator Directions to Trainee:

When I tell you to begin, you are to enter the data on the appropriate log sheet and complete the RO review of the daily log. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to complete the assigned task.

General Conditions:

1. The plant is operating at 100% power.

2. It is 19:00 and the readings from PC-TR-24 need to be entered into 6.LOG.601 Initiating Cues:

You are to fill out Attachment 15, Torus Average Temperature and Drywell Bulk Average Temperature, for Div I, using the data from the simulator and complete an RO review of the log sheet per 6.LOG.601.

Provide the CRS the log sheet when the review is completed.

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 10 of 11 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 For use in Classroom Directions to Trainee:

When I tell you to begin, you are to enter the data on the appropriate log sheet and complete the RO review of the daily log. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using.

State the position of controls as you would have manipulated them in order to complete the assigned task.

General Conditions:

1. The plant is operating at 100% power.

2. The 19:00 readings from PC-TR-24 are: PC-TR-25 are:

Pt. 0 = 95°F Pt. 0 = 96°F Pt. 1 = 90°F Pt. 1 = 91°F Pt. 2 = 94°F Pt. 2 = 92°F Pt. 3 = 95°F Pt. 3 = 95°F Pt. 4 = 92°F Pt. 4 = 93°F Pt. 5 = 94°F Pt. 5 = 95°F Pt. 6 = 90°F Pt. 6 = 92°F Pt. 7 = 95°F Pt. 7 = 97°F Initiating Cues:

You are to fill out Attachment 15, Torus Average Temperature and Drywell Bulk Average Temperature, for Div I, using the data provided and complete an RO review of the log sheet per 6.LOG.601. Provide the CRS the log sheet when the review is completed.

Nebraska Public Power District SKL034-50-48 (16804)

Cooper Nuclear Station Page 11 of 11 Job Performance Measure for Operations Revision 00 RO DATA SHEET ATTACHMENT 15 TORUS AVERAGE TEMPERATURE AND DRYWELL BULK AVERAGE TEMPERATURE INSTRUMENT 0700-1000 1900-2200 OPERABILITY ATT. 21 LOC NUMBER READING READING LIM IT MAX ) MODES NOTES MCO VBD -J PC-TR-24 POINT 0 MCO VBD -J PC-TR-24 POINT 1 MCO VBD -J PC-TR-24 POINT 2 MCO $ 4 RTDs VBD -J PC-TR-24 POINT 3 OPERABLE with no 2 # 6°F (a) 1, 2, 3 27 MCO adjacent RTDs VBD -J PC-TR-24 POINT 4 INOP MCO VBD -J PC-TR-24 POINT 5 MCO VBD -J PC-TR-24 POINT 6 MCO VBD -J PC-TR-24 POINT 7 Sum of OPERA BLE points MCO N/A N/A N/A N/A for PC-TR-24 Divide sum of PC-TR-24 MCO by total number of # 92°F (b) N/A 1, 2, 3 57 OP ER AB LE points (a) For MAX ) check, compare like points. Examples: Compare PC-TR-24 Point 0 to PC-TR-25 Point 0 or compare PC-TR-24 Point 0 to PMIS Point N031. (PMIS Point to TR-25 point number relationship is available in Surveillance Procedure 6.2PC.303.)

(b) If suppression pool temperature > 92°F during normal operation or > 102°F during testing which adds heat to suppression pool, enter the Conditions and Required Actions of LCO 3.6.2.1, then contact Engineering to determine available instrument margin. If suppression pool temperature >

95°F during normal operation or > 105°F during testing which adds heat to suppression pool, ensure LCO 3.6.2.1 is entered.

Nebraska Public Power District SKL034-20-75 (2152)

Cooper Nuclear Station Page 1 of 7 Job Performance Measure for Operations Revision 06 Task No.: 271-017

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Task

Title:

Respond to Sustained Combustion in Off Gas System

===================================================

Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: CR/SIM

2. Appropriate Trainee level: RO/SRO

3. Evaluation Method: Simulate Perform

4. Performance Time: 10 minutes

5. NRC K/A 271000 A1.08 (3.1/3.1); A2.06 (3.5/3.9)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to respond to sustained combustion in off gas system.

2. If this JPM is performed on the Simulator, only the cues preceded by "#" should be given.

3. Observe the trainee during performance of the JPM for proper use of self-checking methods.

4. All blanks must be filled out with either initials or an NP for not performed; an explanation may also be written in the space if desired by the examiner.

5. Brief the trainee, place the simulator in run, and tell the trainee to begin.

Directions to Trainee:

When I tell you to begin, you are to respond to sustained combustion in off gas system. Before you start, I will state the general plant conditions, the Initiating Cues and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to respond to sustained combustion in off gas system. During performance, state the actions you are taking, e.g.:

repositioning controls and observing instrumentation.

===================================================

General Conditions:

1. The Plant is operating at 100% power.

2. The "Red" set of SJAEs is in-service.

Nebraska Public Power District SKL034-20-75 (2152)

Cooper Nuclear Station Page 2 of 7 Job Performance Measure for Operations Revision 06 Task No.: 271-017

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Task

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Respond to Sustained Combustion in Off Gas System

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3. Off gas flow recorder, FR-47, indicates very low and erratic flow.

4. Condensate System Conductivity has increased markedly.

5. There has not been any indication of an explosion in the off gas system.

General

References:

1. Procedure 2.4OG General Tools and Equipment:

1. None Special Conditions, References, Tools, Equipment:

1. Simulator Setup: See Attachment 1.

2. Critical checks denoted by "*".

3. Simulator cues denoted by "#".

Task Standards:

1. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

You are the BOP operator. You are to monitor panel indications and alarms, and take all appropriate actions to respond to sustained combustion in off gas system. Inform the CRS when combustion has been stopped.

NOTE: Place the Simulator in RUN and tell the trainee to begin.

Nebraska Public Power District SKL034-20-75 (2152)

Cooper Nuclear Station Page 3 of 7 Job Performance Measure for Operations Revision 06 Task No.: 271-017

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Task

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Respond to Sustained Combustion in Off Gas System

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Performance Standards Initials Checklist

1. Obtains Procedure The Operator obtains a current copy of Procedure 2.4OG. _______

2. Check PMIS points The Operator checks PMIS Points F040, STM Jet Air F040 Eject 1A Drain, and F041, STM Jet Air Eject 1B and F041 Drain (PMIS Group BURN).

CUE: F040 temperatures is 175°F.

F041 temperatures is 160°F.

Note: If direction was given to the Station Operator(s) to check temperatures locally or to inspect the system, provide the following CUE(s) as appropriate.

1. CUE: Station Operator reports OG-TIS-45 is 175°F and 160°F.

1. CUE: Station Operator reports visual inspection of the OG system has been performed, nothing unusual found.

4. CLOSE AR-AO- The Operator closes AR-AO-151 on Bd B.

151 CUE: The valves GREEN light is ON. The RED _________*

light is OFF.

5. OPEN CD-545 The Operator directs the Turbine Building SO to OPEN CD-545, SJAE FIRST STAGE 1A1 TEST _________*

CONNECTION.

1. CUE: The Station Operator acknowledges the directions.

1. CUE: (After 1 minute has elapsed) The SO reports that CD-545 is OPEN.

NOTE: Remove malfunction OG-02.

Nebraska Public Power District SKL034-20-75 (2152)

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Task

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Respond to Sustained Combustion in Off Gas System

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Performance Standards Initials Checklist

6. Monitor Check condenser vacuum on MS-PI-72A(B).

Condenser vacuum _________

(PNL B) CUE: Vacuum is 26.5' Hg on both.

1. CUE: (If asked) the RO is prepared to reduce Reactor Power.

NOTE: Indicate that 5 minutes has elapsed

7. CLOSE CD-545 The Operator direct the Turbine Building SO to CLOSE CD-545. _________

1. CUE: The Station Operator acknowledges the directions.

1. CUE: (After 1 minute has elapsed) The SO reports that CD-545.

8. OPEN AR-AO- The Operator opens AR-AO-151, SJAE A SUCT 151 (PNL B) (RED) FM CNDR B VLV. _________*

CUE: The valves RED light is ON. The GREEN light is OFF.

9. Monitor PMIS Using a PMIS terminal, check computer points F040, points F040 and STM JETAIREJECT 1A DRAIN, and F041 ,STM _________

F041 JETAIREJECT 1B DRAIN.

CUE: Both temperatures are 126°F.

10. Inform the CRS Inform the Control Room Supervisor that Combustion that the task is has been stopped. _________

Complete.

1. CUE: The Control Room Supervisor acknowledges the report.

Nebraska Public Power District SKL034-20-75 (2152)

Cooper Nuclear Station Page 5 of 7 Job Performance Measure for Operations Revision 06 Task No.: 271-017

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Task

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Respond to Sustained Combustion in Off Gas System

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ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in a full power IC.

Batch File Name - none.

C. Change the simulator conditions as follows:

1. Triggers None

2. Malfunctions Number Title Trigger TD Severity Ramp Initial OG02 Sustained H2 Burn

3. Remotes None

4. Overrides

a. ZAOMSP172A -26

b. ZAOMSP172B -26

5. Panel Setup

a. Initialize Simulator and place in RUN.

b. Insert malfunction OG02.

c. Place Simulator in FREEZE.

Nebraska Public Power District SKL034-20-75 (2152)

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Task

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Respond to Sustained Combustion in Off Gas System

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d. Ensure the "Red" set of SJAEs is in-service.

Note: If this JPM is to be performed more than once, snap the simulator into a saved IC after the panel setup is complete.

Nebraska Public Power District SKL034-20-75 (2152)

Cooper Nuclear Station Page 7 of 7 Job Performance Measure for Operations Revision 06 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to respond to sustained combustion in the off gas system.

Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to respond to sustained combustion in the off gas system. During performance, state the actions you are taking, e.g.:

repositioning controls and observing instrumentation.

General Conditions:

1. The Plant is operating at 100% power.

2. The "Red" set of SJAEs is in-service.

3. Off gas flow recorder, FR-47, indicates very low and erratic flow.

4. Condensate System Conductivity has increased markedly.

5. There has not been any indication of an explosion in the off gas system.

Initiating Cues:

You are the BOP operator. You are to monitor panel indications and alarms, and take all appropriate actions to respond to sustained combustion in off gas system. Inform the CRS when combustion has been stopped.

OPS Lightning Strike, Failure of a Drywell Pressure Lesson

Title:

Instrument, Loss of MCC F, RFP High Vibs, FW line break Rev. No.: 0 inside DW, Isolation Failure.

Lesson No: SKL052-52-95 SAP BET# 16727 Prerequisite: None Duration (Hours): 1.5 References

1. Technical Specifications

a. Technical Specification 3.3.1.1 RPS Instrumentation

b. Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation

2. Procedures

a. COP 2.0.11, Entering and exiting TS LCO Conditions

b. GOP 2.1.5, Reactor Scram

c. GOP 2.1.22, Recover from Group Isolation

d. AOP 2.4MC-RF, Condensate and Feedwater Abnormal

e. EOP 1A, RPV Control

f. EOP 3A, Primary Containment Control

g. ESP 5.8.20, EOP Plant Temporary Modifications

3. Miscellaneous

a. None.

4. PRA

a. Class of Sequence - Loss of Coolant Accidents with Failure to Inject

b. Key Contributor - HPCI Failure

c. Initiator of Core Damage - LOCA

d. High Fussel-Vesely and Risk Achievement Worth - HPCI Failure to start and failure to run

Page 2 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 Examination Criteria:

Satisfactory completion of this Dynamic Evaluation requires a grade as identified in NUREG 1021, Operator Licensing Examination Standards for Power Reactors COMMITMENT LIST Commitment Rev. Added None Method:

This evaluation scenario is intended to be used as an examination mechanism for evaluating Initial Licensed Operator knowledge in a dynamic plant situation.

Crew configurations shall be consistent with the technical specification crew compliment for operating the plant in Mode 1.

Special Equipment/Materials/Special Instructions:

Validation Load 0505. Compare current simulator load to the validation load. If they are not the same, run the scenario and look for possible changes.

Page 3 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 I. SCENARIO

SUMMARY

The plant is operating at 100% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a normal configuration with Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity.

A failure of a drywell pressure sensor results in a half-scram and an inoperable TS instrument.

The instrument may be bypassed to reset the half-scram. The half-group isolation may also be reset. TS 3.3.1.1 and 3.3.6.1 will need to be assessed.

When the Technical Specification assessment is complete, a bus ground results in a loss of MCC F. The loss of MCC F causes a trip of RFPT A due to low lube oil pressure, A1 pump tagged out, requiring a power reduction to maintain reactor water level and to reduce heat load to the capacity of the remaining pump.

When conditions have stabilized, RFP B vibrations increase to the point that the pump must be tripped. The crew will scram the reactor and trip the last remaining RFP.

When RCIC initiates, a break develops on the "A" feedwater line inside the drywell. HPCI fails to automatically start, but may be manually started. RCIC will not inject due to the location of the leak.

The feedwater line check valve leaks, and the leak continues.

HPCI can maintain RPV water level for the selected leak size. Containment sprays will be required by the EOPs.

Drywell sprays will be initiated. Drywell sprays will fail to isolate on low containment pressure.

The operator must either maintain pressure by controlling spray flowrate or manally isolate drywell sprays when containment becomes negative before air is drawn into the primary containment.

The scenario ends when RPV water level is being restored to the normal band, drywell pressure is being controlled and classifications have been made.

Page 4 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 II. TASKS A. RO 259060O0401 Respond to High Reactor Feed Pump Vibration 259046P0401 Respond To Loss Of Single RFP 259017P0401 Respond To Loss Of Both RFPs 200043C0401 Respond To Small Leak Inside PC 226002O0101 Manually Initiate Drywell Spray 230002O0101 Manually Initiate Torus Spray 206019P0101 Respond To HPCI System Automatic Initiation 213002P0101 Verify and Reset a Group 2 Primary Containment Isolation 213003P0101 Verify and Reset a Group 3 Primary Containment Isolation 213006P0101 Verify and Reset a Group 6 Primary Containment Isolation 299015O0301 Apply Technical Specification Requirements B. SRO 259061G0403 Direct Actions For Loss Of Single feed Pump 259062G0403 Direct Actions For Loss Of Feedwater 245046G0403 Direct Actions For High Vibration 200322G0503 Direct Actions For Small Leak Inside PC 200336G0503 Direct Actions To Control Reactor Pressure 200337G0503 Direct Actions To Control Reactor Level 200340G0503 Direct Actions For Emergency Shutdown From Power 200342G0503 Direct Actions To Control PC Pressure 200344G0503 Direct Actions To Control Drywell Temperature 341030O0303 Evaluate Plant Systems Performance And Coordinate Appropriate Actions Per Technical Specifications In The Event A Limiting Condition For Operation is Entered/Not Satisfied

Page 5 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 III. SIMULATOR SET-UP A. Materials Required None B. Initialize the simulator in IC20, 100% (EOC)

Batch File Name - opexam/525295 C. Change the simulator conditions as follows:

Page 6 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01

1. Triggers Number File Name Description E1 None trg 1 "set zroeerelcrfl(1) = 1" E4 None trgset 4 zaorcicfi91 .ge. 0.2

^RCIC flow > 20% of scale or 100 gpm E9 None trgset 9 "zdipcsw1301mv(1) == 1 .or. zdipcsw1302mv(1) == 1 .or.

zdipcsw1311mv(1) == 1" E10 None trgset 10 "zdipcsw1312mv(1) == 1 .or. zdipcswcs240av == 0 .or.

zdipcswcs241av == 0" E11 None trgset 11 "et_array(9) == 1 .or. et_array(10) == 1"

^cross-connect between torus and drywell isolated trg 11 mmf pc12 0

^remove the downcomer leak

2. Malfunctions Number Title Trigger TD Severity Ramp Initial HP01 HPCI Failure to Auto Start A N/A N/A N/A N/A PC17A Individual Group 2 Valve A N/A N/A N/A N/A Automatic Isolation Failure (1301)

PC17B Individual Group 2 Valve A N/A N/A N/A N/A Automatic Isolation Failure (1302)

PC17I Individual Group 2 Valve A N/A N/A N/A N/A Automatic Isolation Failure (1311)

PC17J Individual Group 2 Valve A N/A N/A N/A N/A Automatic Isolation Failure (1312)

PC12 Primary Containment A N/A 20 N/A N/A Downcomer Leak

Page 7 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01

2. Malfunctions Number Title Trigger TD Severity Ramp Initial RM02L ERP Normal Range Radiation E1 0 100 0 As Is DELETE Monitor Failure (RMP-RM-3A)

RM02M ERP High Range Radiation E1 0 100 0 As Is DELETE Monitor Failure (RMP-RM-3B)

ADD Drywell pressure switch PC- 100 PS-12C Fails UPSC ED10A 480 Volt MCC A Failure E2 0 N/A N/A As Is FW07B B RFP High Vibration E3 0 100 6:00 0 FW18A Feedwater Line Break E4 0 100 5:00 0 RR31A Recirc "A" Suction Line E4 00:30 1.6 10:00 0 Break

3. Remotes Number Title Trigger Value Ramp RH44 EOP PTM 76 & 77 A INSTALL N/A RH45 EOP PTM 78 & 79 A INSTALL N/A

4. Overrides Instrument Tag Trigger TD Value Ramp Rx Feed Pump A LO Pump zlorfloswrfopa1(1) A 0 OFF N/A A1 red light Rx Feed Pump A LO Pump zlorfloswrfopa1(3) A 0 OFF N/A A1 green light Rx Feed Pump A LO Pump zdirfloswrfopa1(1) A 0 PTL N/A A1 control switch

Page 8 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01

4. Overrides Instrument Tag Trigger TD Value Ramp Sump Pump D1 green light zlorwswd1(1) A 0 OFF N/A Sump Pump D1 red light zlorwswd1(2) A 0 OFF N/A Sump Pump D1 control zdirwswd1(1) A 0 OFF N/A switch D. Monitor variable CRTCD(14), Diffused Nodal Clad Temperature. This is necessary for Critical Task performance monitoring.

E. Panel Set-up

1. Ensure PMIS IDTs are blank

2. Ensure A DEH pump is running with switch in AUTO.

3. Ensure preferred tag is on A DEH Pump.

4. Balance Master Feedwater Controller.

5. Balance Main Generator voltage regulator.

6. Ensure Recirc Controllers are selected to S.

7. Hang a red tag on:

a. A1 Feed Pump Lube Oil Pump control switch

b. D1 Sump Pump control switch.

8. Update status lights on panel 9-5 to reflect equipment out of service.

9. Mark up boards and ensure tag reflects CREF is on Division I.

Page 9 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 F. SCENARIO CONDUCT Conditions/Instructor Activities Operator Activities CREW Panel walkdown.

ROLL PLAY CRS After crew has assumed the watch, call the control Directs the RO to reduce Reactor Power to room and request a drop of 100 Mwe Net to support approximately 658 MWe.

some switching activities.

RO Lowers Reactor Recirculation Pump speeds to approximately 66% on each. Turbine load should drop to approximately 658 MW.

ACTION BOP When the crew has lowered power, activate

• Reports alarm 9-5-2/D-3 TRIGGER E1 to initiate a drywell pressure

• instrument failing upscale (PC-PS-12C).

• CREW

• Refer to other indications of drywell pressure and determines an instrument failure has occurred.

• Determine no entry into 2.4PC is required as no high pressure exists.

Page 10 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 ROLE PLAY CRS When the SRO reports the problem with the DW

• Refer to TS 3.3.1.1 and 3.3.6.1, RPS and instrument, have the OPS manager direct the crew to PCIS Instrumentation.

bypass the instrument and reset the scram while the

• Determine Condition 3.3.1.1.A and problem is being assessed. 3.3.6.1.A are applicable.

Note: this is being done so the RO has to reset the RO scram and the BOP has to reset the half-isolation.

• Resets half-scram BOP

• Resets the half-isolation ACTION BOP After the TS assessment and resets are complete,

• Report alarm C-3/E-10, 480V BUS 1B activate TRIGGER E2 to fail MCC B. GROUND

• Report ground is on MCC-B.

NOTE:

• Report alarm C-3/C-10, 480V BUS 1B No entry exists for 5.3AC480. MCC-B BKR TRIP.

ROLE PLAY: RO If asked to investigate, report there is no obvious

• Report trip of A RFP.

cause for the breaker trip.

• Monitor for recirc runback.

BOP

• Report A RFP has no normal lube oil pumps.

• If necessary, control TEC temperature manually with TEC-MO-130, TEC HX BYPASS VALVE, or TEC HX SW outlet valves.

Page 11 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 CRS Enter 2.4MC-RF.

BOP

• Perform 2.4MC-RF.

• Update crew on scram actions.

• Check if operation in or near Stability Exclusion Region of Power to Flow Map.

• Determine need to enter Procedure 2.4RR.

• Determine there are no more applicable actions.

CRS Directs the BOP operator to enter 2.4 RR and carry out the actions.

BOP S Enters 2.4RR as operation is in the stability exclusion region.

S coordinates with the RO the driving of control rods.

RO S Drives the control rods to exit the stability exclusion region of the Power to Flow Map.

ACTION BOP After the actions for the MCC loss are complete, S Report rising vibrations on A RFP.

activate TRIGGER E3 to cause high vibrations on S Report alarm A-1/E-6, RFP TURBINE A A RFP. CONTROL TROUBLE S Terminate any power changes in progress.

S Monitor reactor level, power, steam flow, and feed flow.

S On RFC-M-OITA, determine high vibration caused alarm.

Page 12 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 ACTION: BOP IF the crew is not going to trip the RFP, insert S Report alarm A-1/F-5, RFP TURBINE A malfunction FW01A, Reactor Feedwater Pump Trip. SUPERVISORY TROUBLE.

S Determine cause of alarm on RFC-M-OITA (done).

S Lower RFPT speed until alarm clears (must reduce power to do so).

S When bearing vibration reaches 3.5 mils, trip RFP Turbine A.

ACTION: RO If the crew does not start RCIC to control RPV water S When second RFP is tripped, manually level, manually actuate TRIGGER 4. scrams the reactor.

S Make scram report.

CRS S Enter and direct the activities of EOP-1A.

S Direct group isolations and initiations be verified.

S Direct RPV water level be restored and maintained +15" to +40".

S Direct Reactor pressure be maintained 800 to 1000 psig.

NOTE: CREW The feedwater line leak and suction line leak (to Recognize rapidly rising drywell pressure.

simulate feedwater check valve leakage) go active automatically when RCIC injects. RO S Recognize HPCI failed to automatically start.

S Manually start HPCI.

Page 13 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 CRS S Re-enter EOP-1A.

S Enter and direct the activities of EOP-3A.

S Check PC water level.

S Direct torus sprays be placed in service.

S Direct Drywell FCUs be placed in OVERRIDE.

BOP Place Drywell FCUs in OVERRIDE.

BOP Place torus sprays in service.

CRS When torus pressure reaches 10 psig,:

S Direct Recirc pumps be tripped.

S Direct Drywell FCUs be tripped.

S Check DWSIL.

S Direct Drywell sprays be placed in service.

BOP Trips Drywell FCUs.

RO Trips Reactor Recirc pumps.

NOTE: BOP Drywell sprays will fail to isolate on low containment S Place Drywell sprays in service.

pressure. The operator must either maintain pressure S Maintain Drywell pressure in the ordered by controlling spray flowrate or manally isolate band.

drywell sprays when containment becomes negative before air is drawn into the primary containment.

CRS Classify the event as an ALERT per EAL 2.2.1 VI. SCENARIO TERMINATION When RPV water level is being restored to the normal band, drywell pressure is being controlled and classifications have been made, FREEZE the simulator.

Page 14 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 VII. POST-SCENARIO CRITIQUE If this scenario is not being used for an annual exam, provide a critique in accordance with the general critique guidelines of OTP-806.

Page 15 of 16 Lesson

Title:

OPS Lightning Strike, Failure of a Drywell Pressure Instrument, Loss of MCC F, RFP High Vibs, FW line break inside DW, Isolation Failure.

Lesson No.: SKL052-52-95 Rev. No.: 01 VIII. CRITICAL TASK PERFORMANCE A. Crew Performance CREW CRITICAL TASKS SAT UNSAT The crew will take action to maintain operation within the Pressure Suppression Pressure Limit (PSP).

The crew will take actions to prevent primary containment oxygen level from exceeding 5%.

The crew will control injection to assure fuel temperature remains below 1500/F and not require emergency depressurization.

B. Individual Performance CREW: DATE:

CRS PASS / FAIL RO PASS / FAIL BOP PASS / FAIL

IX. INITIAL CONDITIONS A. Plant Status:

1. 100% power, steady state, near End of Cycle.

2. Rod Sequence Information: Page: 2 Rod: 18-27 Notch: 26 B. Tech. Spec. Limitations in effect:

1. None C. Significant problems/abnormalities:

1. Optimum Water Chemistry is out of service.

2. A1 Reactor Feed Pump Lube Oil Pump tagged out for motor replacement.

3. Sump Pump D1 tagged out due to high motor vibration.

4. The control room was notified by NAWAS that Southeast Nebraska is in a severe thunderstorm warning for the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The off-going shift completed all applicable actions in 5.1WATCH.

D. Sentinal Status: Green E. Evolutions/maintenance for the on-coming shift:

F. Continue full power operation.

Scram Accumulator Low Pressure, Inadvertent HPCI Lesson

Title:

Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, Rev. No.: 0 MSOT 2 Areas, ED Lesson No: SKL052-52-94 SAP BET# 16726 Prerequisite: None Duration (Hours): 1.5 References

1. Technical Specifications/TRM

a. 3.1.3 Scram Accumulators

b. 3.1.5 Control Rods

c. 3.5.1 ECCS - Operating d.

2. Procedures

a. ACP 2.4EXT-STM Loss of Extraction Steam

b. GOP 2.2.29 Feedwater Heaters and Extraction Steam

c. GOP 2.1.5 Reactor Scram

d. ACP 2.4CSCS Inadvertent CSCS Initiation

e. EP 5.1RAD Building Radiation Trouble

f. EPIP 5.7.1 Emergency Classification

g. EPIP 5.7.2 Shift Supervisor EPIP

h. EOP 5.8 RPV Control - 1A

i. EOP 5.8 Primary Containment Control - 3A

j. EOP 5.8 Reactor Pressure/Power Control (ATWS) - 6A

k. EOP 5.8 Reactor Pressure/Power Control (ATWS) - 6B

l. EOP 5.8 Reactor Level Control (ATWS) - 7A

m. EOP 5.8.3 Alternate Rod Insertion Methods

n. EOP 5.8.4 Alternate Injection Subsystems (Table 4)

o. EOP 5.8.13 Outside Shroud Injection Systems (Failure to Scram)

(Table 13)

p. EOP 5.8.20 EOP Plant Temporary Modifications q.

3. Miscellaneous

a. SER 4-00, Continued Operation When Conditions Called for Manually Scramming the Reactor

4. PRA

a. Class of Sequence - ATWS

b. Key Contributor - RPS Failure, HPCI Failure, RCIC Failure

c. Initiator of Core Damage - Loss of Condenser

d. High Fussel-Vesely and Risk Achievement Worth - Mechanical Failure of RPS

e. High Risk Achievement Worth - Mechanical Failure of RPS

Page 2 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 Examination Criteria:

Satisfactory completion of this Dynamic Evaluation requires a grade as identified in OTP-809 COMMITMENT LIST Commitment Rev. Added None Method:

This evaluation scenario is intended to be used as an examination mechanism for evaluating Licensed Operator knowledge in a dynamic plant situation.

Crew configurations shall be consistent with the normal crew compliment used to operate the plant.

Special Equipment/Materials/Special Instructions:

Validation Load 0505. Compare current simulator load to the validation load. If they are not the same, run the scenario and look for possible changes.

Page 3 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 I. SCENARIO

SUMMARY

The plant is operating at 60% power with instructions to continue the power ascension to 100%.

The crew will raise power greater than 70% before the first event is called in. The A1 Feed Pump Lube Oil Pump and Sump Pump D1 are tagged out. After a 10% power increase has been achieved, a scram accumulator fault on low pressure occurs.

Following the Tech Spec assessments, an inadvertent initiation of HPCI occurs. The crew should respond per 2.4CSCS and Technical Specifications.

After the Tech Spec assessment is complete, an unisolable steam line leak will develop on the HPCI steam line. The automatic isolation for the steam supply valves will not function and the valves cannot be closed from the control room. The crew is expected to take action EOP-05, Secondary Containment Control and scram the plant before one area reaches a Maximum Safe Operating Temperature (MSOT).

Due to a hydraulic lock, many control rods will fail to insert. The crew should respond to the ATWS per EOP-06A, 7A and 5.8.3. Power level should be ~ 10% after the Recirculation pump trip, so RPV water level will have to be lowered. Control rods can be inserted via RMCS.

The secondary containment temperatures will continue to rise, resulting in MSOT in 2 areas. The crew is expected to take action iaw EOP-6B and perform an Emergency Depressurization. After the Emergency Depressurization is complete and RPV water level is being controlled, the control rods will insert the next time the scram is reset and scrammed again.

The scenario will terminate when the RPV has been depressurized, control rods have been inserted. and RPV water level has been restored to +15 to +40.

Page 4 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 II. TASKS A. RO 200020O0401 Perform Emergency Shutdown From Power and Scram Response 200174A0501 Conduct Alternate Pressure Control Using Safety Relief Valves 200369A0501 Conduct Alternate Rod Insertion Using Repeat Manual Scrams 200379A0501 Conduct Alternate Rod Insertion Using RMCS 206021P0401 Respond to HPCI Inadvertent Initiation 213002P0101 Verify and Reset a Group 2 Primary Containment Isolation 213003P0101 Verify and Reset a Group 3 Primary Containment Isolation 213006P0101 Verify and Reset a Group 6 Primary Containment Isolation 272005O0401 Respond to High Radiation Level Alarms 218002O0101 Manually Operate SRVs to Control Reactor Pressure B. SRO 200336G0503 Direct Actions To Control Reactor Pressure 200337G0503 Direct Actions To Control Reactor Level 200340G0503 Direct Actions For Emergency Shutdown From Power 200347G0503 Direct Actions To Control Torus Water Temperature 200357G0503 Direct Actions To Shutdown Reactor During Failure To Scram 200358G0503 Direct Actions To Control Reactor Pressure During Failure To Scram 288073G0403 Direct Actions For Loss of Reactor Building Ventilation 200349G0503 Direct Actions To Control Secondary Containment Radiation Levels 341039O0303 Authorize Overriding Automatic Actions of Engineered Safety Systems 200350G0503 Direct Actions To Control Secondary Containment Temperature

Page 5 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 341030O0303 Evaluate Plant Systems Performance And Coordinate Appropriate Actions Per Technical Specifications In The Event A Limiting Condition For Operation is Entered/Not Satisfied 344018O0303 Classify Emergency Events Requiring Emergency Plan Implementation 344022O0303 Direct Emergency Response As Emergency Director (Emergency Plan) 344037O0303 Perform Required Notifications Of On-Site And Off-Site Personnel For Abnormal/Emergency Events III. COMMON OPERATOR ERRORS A. None identified.

Page 6 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 IV. SIMULATOR SET-UP A. Materials Required None B. Initialize the simulator in IC 16, ~60% (MOC)

Batch File Name - OPEXAM/525294 C. Change the simulator conditions as follows:

1. Triggers Number File Name Description E2 None Default to False E4 None Default to False E6 None Default to False E8 None Default to False

2. Malfunctions Number Title Trigger TD Severity Ramp Initial RD02 ATWS A 0 90 0 N/A HP09 HPCI Failure to Auto Isolate A 0 N/A N/A N/A HP05 HPCI Inadvertent Initiation E2 0 N/A N/A N/A HP06 HPCI Steam Line Break E4 0 6 25:00 0.5

Page 7 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00

3. Remotes Number Title Trigger Value Ramp None

4. Overrides Instrument Tag Trigger TD Value Ramp Stm Supp Outbd Isol Vlv zdihpcisws1[2] A 0 Open N/A MO-15 Stm Supp Inbd Isol Vlv MO-16 zdihpcisws2[2] A 0 Open N/A HPCI Manual Isolation PB zdihpcisws32 A 0 Off N/A ASD Room Outer Door RA:MUX15C035 E8 0 ON N/A ASD Switch Position Abnormal RA:MUX15C038 E8 30 ON N/A HPCI MO 16 Red Light zlohpcisws1(2) E8 30 OFF N/A HPCI MO 18 Red Light zlohpcisws2(2) E8 35 OFF N/A Rx Feed Pump A LO Pump A1 red zlorfloswrfopa1(1) A 0 OFF N/A light Rx Feed Pump A LO Pump A1 zlorfloswrfopa1(3) A 0 OFF N/A green light Rx Feed Pump A LO Pump A1 zdirfloswrfopa1(1) A 0 PTL N/A control switch Sump Pump D1 green light zlorwswd1(1) A 0 OFF N/A Sump Pump D1 red light zlorwswd1(2) A 0 OFF N/A Sump Pump D1 control switch zdirwswd1(1) A 0 OFF N/A

Page 8 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00

5. Panel Set-up

a. Ensure PMIS IDTs are blank

b. Ensure A DEH pump is running with its switch in AUTO

b. Place a red tag on A1 FPLO Pump control switch.

c. Place a red tag on D1 Sump Pump control switch.

D. Monitor variable CRTCD(14), Diffused Nodal Clad Temperature. This is necessary for Critical Task performance monitoring.

E. Compare current simulator load to the validation load. If they are not the same, run the scenario and look for possible changes.

Page 9 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 VI. SCENARIO CONDUCT Conditions/Instructor Activities Operator Activities Take the simulator out of FREEZE and allow the CREW crew time to walkdown the panels. Panel walkdown.

ACTION CRS Crew briefs and starts power ascension. S Briefs crew and assigns task for the power ascension to 100% power.

ROLE PLAY If the crew does not start the power ascension shortly RO after assuming the watch, call as the load dispatcher S Reviews procedure and adjust reactor recirc and request at least 150 Mwe Net increase. speeds to raise reactor power greater than 70%.

ACTION RO When the power ascension is complete, activate - Reports the alarm to the SRO and TRIGGER E2 to cause an accumulator low pressure determines which accumulator is alarm on control rod xx-yy (for a rod not fully faulted.

withdrawn).

SRO Directs an equipment operator to recharge the faulted accumulator.

ROLE PLAY After a few minutes, the equipment operator reports back the accumulator cannot be recharged due to a leak on the charging isolation valve.

SRO Refers to TS 3.1.5 and 3.1.3. Declares the ROLE PLAY affected control rod inoperable.

If requested by the SRO, there are no other inoperable or slow control rods.

Page 10 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 Conditions/Instructor Activities Operator Activities ACTION BOP When the Tech Spec assessment is complete, activate S Respond to inadvertent initiation of HPCI TRIGGER E2 to cause HPCI to inadvertently per 2.4CSCS.

initiate. S Verify not a valid signal by 2 independent indications S Trip and lock out HPCI CRS S Directs/ensures HPCI tripped.

S (IF HPCI is not shut down within a minute or so, enter and direct the activities of EOP-5A, Secondary Containment Control due to high area radiation.

RO If necessary, maintain reactor power approximately where it was before the injection with recirculation flow and/or control rods.

CRS S Refer to Technical Specification 3.5.1, determine ACTION C.1 (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) and ACTION C.2 (14 day) apply.

Page 11 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 Conditions/Instructor Activities Operator Activities ACTION BOP When the Tech Spec assessment is complete, activate Announces Heater A5 High Level Alarm TRIGGER E3 to cause a 100% tube rupture in (Alarm clears when the emergency dump valve feedwater heater A5. opens.) Begins diagnosing heater A5 when alarm clears.

Reports to SRO condensate flow has increased.

SRO Directs the equipment operator to check the status of heater A5. Checks with the radwaste operator on the status of ? Enters procedure 2.4EX-STM.

ROLE PLAY The equipment operator reports back the heater level is very high in the band and all three dump valves are open. The radwaste operator reports higher than normal flows in radwaste.

ROLE PLAY SRO If the SRO calls plant management concerning the Directs the crew to commence a normal heater problem and reports the decision to shutdown, shutdown as directed by procedure 2.2.29, acknowledge the report and provide agreement to the Feedwater Heaters and Extraction Steam decision to shutdown. System.

RO Begins power reduction using control rods and reactor recirc flow.

BOP Supports power reduction - secures one RFPT.

Page 12 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 Conditions/Instructor Activities Operator Activities ACTION BOP When the power reduction has exceeded 5%, activate S Reports alarm 9-3-1/E-10: Area High TRIGGER E4 to cause HPCI steam line to begin to Temp.

leak. S Diagnoses HPCI failed to isolate.

S Attempts to isolate HPCI.

ROLE PLAY When the reactor building becomes positive, call the control room as security and report steam blowing out around the railroad airlock doors.

ROLE PLAY CRS IF asked to investigate, report a lot of steam coming Enter and direct the activities of EOP-5A, out of the HPCI quad. Secondary Containment Control.

S Direct the Reactor Building be isolated (if ACTION high radiation signal is present).

If requested to isolate HPCI from the ASD room S Direct all quad coolers be started.

perform the following activate TRIGGER E8. S Direct verification of sump pump operation S Direct HPCI be manually isolated.

ROLL PLAY Call the control room and report the valves will not close from the ASD room.

Page 13 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 Conditions/Instructor Activities Operator Activities NOTE: CRS The crew should attempt to close MO-15 from MCC- S Direct area temperatures be monitored.

R due to the steam leak rather than MO-16 which is S Dispatch personnel to investigate the leak.

in the Quad BOP ROLE PLAY Reports temperatures from Pnl 9-21 or PMIS.

If asked to close HPCI MO-16 manually (local), wait 2 minutes, then report steam in the Rx Bldg prohibits access to the valve.

NOTE: CRS/BOP It takes ~ 8 minutes from the high temperature alarm Monitor for any secondary containment until the first maximum safe temperature is reached parameter reaches its maximum safe operating (if they do not depressurize). value:

• Temperatures (TABLE 9)

• Radiation (TABLE 10)

• Water levels (TABLE 11)

CRS When high area radiation alarms occur, direct 5.1RAD be performed.

BOP Perform actions per 5.1RAD as directed.

CRS S Determine a manual scram is required BEFORE a Maximum Safe Operating Value has been exceeded (already complete).

S Enter EOP-1A

Page 14 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 Conditions/Instructor Activities Operator Activities ACTION CRS After the scram has been inserted, modify S Direct a manual scram be inserted.

malfunction RD02 to 80%.

RO Manually scram the reactor as directed.

RO S Make scram report - ATWS S Report many control rods have not inserted.

CRS Transition to 6A/7A.

• Mode switch in S/D ROLE PLAY

• ARI initiated If requested, as station operator close the CRD-29

• RR pumps to minimum valve 2 minutes after being directed (Remote

• Insert control rods using 5.8.3 actions.

Function RD04).

• Verify group isolations.

• Inhibit ADS ACTION RO If requested to bypass ARI (PTM #61/62), S Inhibit ADS use REMOTE FUNCTION S Verify group isolations RD18, EOP PTMs 61 & 62, REMOVE.

RO Insert control rods per 5.8.3 CRS S Direct RPV pressure be maintained 800 to 1000 psig.

S Direct RPV water level be maintained +15" to +40".

BOP S Maintain RPV pressure 800 to 1000 psig.

S Maintain RPV water level +15" to +40".

Page 15 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 Conditions/Instructor Activities Operator Activities NOTE: CRS The MSIVs will close on low level if the crew does Direct RPV water level be maintained between not get the jumpers in before -95". -25" (FZ) and +40" (WR).

BOP Maintain RPV water level between -25" (FZ) and +40" (WR).

ACTION RO When directed to install ARI PTMs, wait 2 minutes, S Direct SO to install EOP PTM 61 & 62.

then Insert REMOTE FUNCTION RD18, EOP S Install jumpers to defeat RPS.

PTMs 61 and 62 to REMOVE . Inform the Control S Reset scram.

Room. S Allow SDV to drain.

S Insert manual scram, report some rod movement.

RO (5.8.3)

S Insert rods with RMCS as drive pressure allows.

NOTE: CRS Emergency depressurization CANNOT be When 2 areas exceed Maximum Safe Operating anticipated. Values, direct an Emergency Depressurization be performed.

S Exit the pressure leg of 6A, Enter and direct 6B.

S Direct injection be stopped and prevented except RCIC, CRD and boron.

BOP Stop and prevent injection as directed by the CRS.

CRS S Verify PC level is > 6'.

S Direct 6 SRVs be opened.

Page 16 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 Conditions/Instructor Activities Operator Activities BOP When directed to emergency depressurize RPV then open 6 SRVs.

CRS S When torus temperature reaches 95/F, enter and direct the activities of EOP-3A.

S Direct torus cooling be placed in service.

BOP Place maximum torus cooling in service.

CRS Direct pressure be monitored and reported when MSCP is reached (135 psig).

BOP Report when MSCP is reached.

CRS Direct injection be started and slowly increased to restore and maintain RPV water level -25" (FZ) to 40" (WR).

BOP Control injection as directed by the CRS.

ACTION RO When RPV water level has been restored and Report all Control Rods fully inserted.

maintained the scram is reset, delete malfunction RD02. CRS S Enter and direct the activities of EOP-1A.

S Direct RPV water level be restored and maintained +15" to +40".

CRS Classifies event as a Site Area Emergency (based on EAL 3.3.4) and implements EPIP 5.7.2, Shift Supervisor EPIP.

Page 17 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 VII. SCENARIO TERMINATION ACTION:

When all control rods are inserted, RPV water level has been restored +15" to +40", and classifications have been made, FREEZE the simulator.

VIII. POST-SCENARIO CRITIQUE N/A

Page 18 of 19 Scram Accumulator Low Pressure, Inadvertent HPCI Initiation, Heater A5 Tube Rupture, HPCI Leak, and ATWS, MSOT 2 Areas, ED Lesson No.: SKL052-52-94 Rev. No.: 00 VIII. CRITICAL TASK PERFORMANCE A. Crew Performance CREW CRITICAL TASKS SAT UNSAT The crew shall initiate an Emergency Depressurization when 2 areas exceed MSOT.

The Crew shall stop injection within 5 minutes of directing injection be stopped.

The crew shall control injection such that RPV water level is restored and maintained -25(FZ) to +54" The crew shall insert control rods to ensure the reactor will remain shutdown under all conditions without boron prior to scenario termination.

B. Individual Performance CREW: DATE:

CRS PASS / FAIL RO PASS / FAIL BOP PASS / FAIL

V. INITIAL CONDITIONS A. Plant Status:

1. 60% power, near middle of cycle.

2. The plant is being returned to service after a short forced outage.

3. Rod Sequence Information: Page: 24 Rod: 42-11 Notch: 12 B. Tech. Spec. Limitations in effect:

None C. Significant problems/abnormalities:

1. A1 Reactor Feed Pump Lube Oil Pump is tagged out due to a motor failure.

2. D1 Sump Pump tagged out due to a motor failure.

3. I&C are completing 6.2H2O2.302, Div II H2O2 Analyzer Channel Calibration.

D. Sentinal Status: Green E. Evolutions/maintenance for the on-coming shift:

Continue power ascension to 100% power.

Appendix D Required Operator Actions Form ES-D-2 Facility: Cooper Nuclear Station Examination Date: 6/5/2005 Op-Test Number: Scenario: 4 Event No.: 1 Page 1 of 8 Event

Description:

Power Reduction to < 70%

Time Position Applicants Actions or Behavior CRS DIRECTS power reduction to < 70% using control rods (NOTE: use of recirculation flow could place the reactor in the Power-to-Flow Map Stability Exclusion Zone).

ATCO Prior to moving control rods, Operator shall verify rod positions in the Control Rod Sequence and Movement Binder agree with actual rod positions by comparing to RPIS display or 4-Rod/Full Core display.

ATCO Withdraw or insert control rods to required rod pattern using prescribed methods and sequences as designated by a Reactor Engineer and/or Procedure 10.13. Rod Movement: #18-27 (26 to 20), #26-35 (26 to 20), #34-27 (26 to 20), #26-19 (26 to 20), #18-19 (48 to 20), #18-35 (48 to 20), #34-35 (48 to 20), #34-19 (48 to 20),

1. 10-27 (48 to 20) & #26-43 (48 to 20)

BOP All control rod moves performed with REACTOR MODE switch in START & HOT STBY or RUN shall be checked by a second Licensed Operator or an individual certified as an STE.

ATCO Monitor core thermal limits (MFLCPR, MFLPD, and MAPRAT), per Procedure 6.LOG.601, to ensure compliance with Technical Specifications Section 3.2.

CRS CONTACTS or DIRECTS contact to Mechanical Maintenance to begin work on Feed Pump A, Lube Oil Pump A1 following power reduction.

Appendix D Required Operator Actions Form ES-D-2 Facility: Cooper Nuclear Station Examination Date: 6/5/2005 Op-Test Number: Scenario: 4 Event No.: 2 Page 2 of 8 Event

Description:

Surveillance 6.MS.201 Section 5 (Failure of MSIV MOV-80A to open)

Time Position Applicants Actions or Behavior CRS DIRECTS completion of the overdue Surveillance 6.MS.201, Main Steam Isolation Valve Operability Test (IST), Section 5, MSIV Spring Only Closure Tests.

ATCO VERIFY power < 70% AND at least 7% lower than APRM rod block setpoints to compensate for flux spike due to MSIV closure.

BOP At Panel 9-3, press and hold MSIV TEST button for MSIV being tested (MOV-80A) until it indicates closed.

BOP When MSIV being tested is closed, checks at Panel 9-3 that green lights on bench board and PCIS mimic are on, and red lights on bench board and PCIS mimic are off.

BOP At Panel 9-3, release MSIV TEST button for MSIV being tested (MOV-80A). NOTE: valve fails to open.

ATCO MAY DETERMINE that annunciator 9-5-2/B-2, MSIV NOT FULL OPEN TRIP, does not come in as expected when MOV-80A is closed.

IF SO, go to Event 5.

CRS Enters 2.4MSIV and carries out actions CRS Refers to TS 3.6.1.3 PCIVs CRS MAY DIRECT BOP Reactor Operator close MOV-80B.

CRS MAY DIRECT electrical maintenance to de-energize MOV-80A.

Appendix D Required Operator Actions Form ES-D-2 Facility: Cooper Nuclear Station Examination Date: 6/5/2005 Op-Test Number: Scenario: 4 Event No.: 3 Page 3 of 8 Event

Description:

Loss of 69 kV Offsite Power Line (OPPD Nebraska City Line)

Time Position Applicants Actions or Behavior BOP Observe Board C, 345 KV NEB CITY LINE VOLTS, 161 KV LINE VOLTS, and 69 KV LINE VOLTS indication.

BOP Reviews annunciator responses for C-1/G-6, C-2/D-10, C-2/C-10 & C-4/G-1 CRS ENTERS 5.3GRID per annunciator procedure C-2/C-10.

CRS CONTACTS Doniphan Control Center for line status CRS ENTERS 2.2.17, Emergency Station Service Transformer, Section 5, Removing Emergency Transformer from Service. DIRECTS steps 5.3 through 5.9. MAY request a Switching Order from Doniphan Control Center prior to performing steps 5.3 to 5.9.

CRS ENTERS LCO 3.8.1 BOP WHEN DIRECTED, Ensures Breakers 1FS and 1GS are open per Procedures 2.2.17 and 2.2.18.

CRS MAY DIRECT Surveillance 3.8.1.1, Verify correct breaker alignment and indicated power availability for each offsite circuit, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

CRS ENTERS 5.1WATCH after notification of tornado watch for Nemaha County CRS ENSURES the following Air Compressor lineup: Air Compressor A aligned to REC, Air Compressor B aligned to REC & Tendamatic in C-A-B BOP Places Tendamatic in C-A-B.

CRS DIRECTS personnel to close and secure all external doors to all buildings both within and outside Protected Area. MAY DIRECT: (1)

Terminate unnecessary activities, and (2) thoroughly inspect station for loose materials.

Appendix D Required Operator Actions Form ES-D-2 Facility: Cooper Nuclear Station Examination Date: 6/5/2005 Op-Test Number: Scenario: 4 Event No: 4 Page 4 of 8 Event

Description:

Main Steam Line A Radiation Monitor Fails High Time Position Applicants Actions or Behavior BOP Responds to annunciator 9-4-4/A-4, MAIN STM LINE HI HI RAD.

CRS Refers to TS 3.3.6.1 BOP Observes MSL radiation monitors on the backpanel and reports to the CRS the radiation monitor for MSL A has failed high.

CRS Directs the radiation monitor that has failed be placed in the tripped condition.

BOP Places MSL A Radiation Monitor in INOP CRS

Appendix D Required Operator Actions Form ES-D-2 Facility: Cooper Nuclear Station Examination Date: 6/5/2005 Op-Test Number: Scenario: 4 Event No.: 5 Page 5 of 8 Event

Description:

APRM Channel B Failure (INOP)

Time Position Applicants Actions or Behavior ATCO Identifies half-scram condition.

CRS ENTERS 2.1.5, Reactor SCRAM, Section 4, Half Scram Reset.

DIRECTS ATCO to place APRM Channel B in bypass and reset the half-scram ATCO WHEN DIRECTED places place APRM Channel B in bypass ATCO WHEN DIRECTED places REACTOR SCRAM RESET switch to Group 1 and 4, Group 2 and 3, then back to NORM. Ensures eight SCRAM GROUP lights (Panels 9-15 and 9-17) or SCRAM INDICATIONS GROUP A and GROUP B lights are on.

CRS ENTERS LCO 3.3.1.1 (RPS Instrumentation)

CRS ENTERS TLCO 3.3.1 (Rod Block Monitor)

CRS DIRECTS placing the RPS channel in trip ATCO WHEN DIRECTED places RPS channel in trip ATCO WHEN DIRECTED inserts Reactor Manual Control System rod withdrawal block

Appendix D Required Operator Actions Form ES-D-2 Facility: Cooper Nuclear Station Examination Date: 6/5/2005 Op-Test Number: Scenario: 4 Events No.: 6 and 7 Page 7 of 8 Event

Description:

(7) Tornado Warning, Lightning Strike (Loss of Offsite Power),

Reactor SCRAM, and Steam Leak into Primary Containment, (8) Loss of DG-2 after 5 minutes Time Position Applicants Actions or Behavior CRS REENTERS 5.1WATCH following tornado warning for Nemaha County CRS DIRECTS or SOUNDS the emergency alarm for 10 seconds CRS DIRECTS or MAKES GAITRONICS announcement (per 5.1WATCH, Attachment 1, #1.1.2, Attention, a Tornado Warning has been issued for Nemaha County......)

CRS DIRECTS or CALLS Doniphan Control Center CRS ENTERS 5.3EMPWR, Emergency Power, following lightning strike and complete loss of offsite power CRS ENTERS 2.1.5, Reactor SCRAM, following reactor scram.

ATCO Presses both RX SCRAM buttons following reactor scram. Ensures eight SCRAM GROUP lights (Panels 9-15 and 9-17) or SCRAM INDICATIONS GROUP A and GROUP B lights are on.

ATCO Places REACTOR MODE switch to REFUEL. Checks all control rods are inserted by checking REFUEL MODE SELECT PERMISSIVE light is on or all green FULL-IN lights on full core display are on.

ATCO Lowers RFC-LC-83, MASTER LEVEL CONTROLLER, settape setting to 15".

ATCO Places REACTOR MODE switch to SHUTDOWN.

ATCO Places REACTOR SCRAM RESET switch to Group 1 and 4, Group 2 and 3, then back to NORM CRS DIRECTS Doniphan Control Center to initiate Operating Instruction 7 per the Switching Order Book CRS ENTERS EOP 1A, RPV Control (RPV level # +3 inches) & EOP 3A, Primary Containment Control (drywell pressure & torus water level) &

EOP 5A, Secondary Containment Control ($ max normal radiation due to operation of HPCI)

Appendix D Required Operator Actions Form ES-D-2 Facility: Cooper Nuclear Station Examination Date: 6/5/2005 Op-Test Number: Scenario: 4 Events No.: 7 & 8 Page 8 of 8 Event

Description:

(7) Tornado Warning, Lightning Strike (Loss of Offsite Power),

Reactor SCRAM, and Steam Leak into Primary Containment, (8) Loss of DG-2 after 5 minutes Time Position Applicants Actions or Behavior CRS DIRECTS maintaining RPV level between +3" to +54" using ECCS ATCO or AS DIRECTED, maintains RPV level within the target band using BOP HPCI and RCIC CRS DIRECTS Reactor Operators in restoring REC and station Air Compressors using 5.3EMPWR Attachment 2 BOP WHEN DIRECTED, restores REC per 5.3EMPWR, Attachment 2, steps 1.2.1 to 1.2.9 BOP WHEN DIRECTED, restores station air compressors per 5.3EMPWR, Attachment 2, steps 1.6.1 to 1.6.5 CRS DIRECTS Station Operator to close CST valves per 5.3EMPWR, Attachment 2, step 1.7 CRS DIRECTS initiating Torus Sprays when drywell pressure is between 4

- 8 psig ATCO or AS DIRECTED, initiates and operates Torus Sprays BOP CRS DOES NOT DIRECT torus cooling when torus temperature $ 95/F

[torus sprays have higher priority]

CRS DIRECTS initiating Drywell Sprays when torus pressure $10 psig.

DIRECTS maintaining torus pressure in a range 2 to 10 psig using Drywell Sprays.

ATCO or AS DIRECTED, initiate and operate Drywell Sprays BOP BOP WHEN DIRECTED, places condensate pumps, condensate booster pumps and sparger pumps in TRIP BOP WHEN DIRECTED, places breakers 1AS and 1BS in pull-to-lock