Text

2009-09-DRAFT Jpms
	ML100880141
Person / Time
Site:	Cooper
Issue date:	09/21/2009
From:	; NRC Region 4
To:	; Nebraska Public Power District (NPPD)
References
	50-298/09-09
	Download: ML100880141 (149)
	v • d • e

Nebraska Public Power District SKL034-50-58 (36403)

Cooper Nuclear Station Page 1 of 149 Job Performance Measure for Operations Revision: 00 Task No.: 283016S0101 Obtain and Interpret a GARDEL Periodic Report 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

4. Performance Time: 10 minutes

5. NRC K/As 2.1.7 Imp. 3.7/4.4 Directions to Examiner:

1. This JPM evaluates the trainee=s ability to Obtain and Interpret a Gardel Periodic Case.

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 Anot performed@; 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 Obtain and Evaluate a Gardel Official Case by completing attachment 2 of 6.LOG.601. 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.

Nebraska Public Power District SKL034-50-58 (36403)

Cooper Nuclear Station Page 2 of 149 Job Performance Measure for Operations Revision: 00 Task No.: 283016S0101 Obtain and Interpret a GARDEL Periodic Report General Conditions:

1. The Reactor is at approximately 100% power.

General

References:

1. Procedure 6.LOG.601 Daily Surveillance Log.

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 obtain a Gardel Periodic Case and verify that Thermal Limits are within Specification by completing Attachment 2 of 6.LOG.601. Inform the CRS when you have completed you review of the official case.

NOTE: Give the candidate Attachment 2 of 6.LOG.601 and tell the candidate to begin.

Nebraska Public Power District SKL034-50-58 (36403)

Cooper Nuclear Station Page 3 of 149 Job Performance Measure for Operations Revision: 00 Task No.: 283016S0101 Obtain and Interpret a GARDEL Periodic Report Performance Checklist Standards Initials The Operator demands and prints a Periodic Case.

1. Demand a Gardel CUE: Gardel Official Case prints.

Periodic Case _______*

CUE: Remove the periodic case from the printer and give the Candidate the attached Periodic Case

2. Scans the periodic case and records the highest Value for the highest MFLCPR is recorded on value of MFLCPR. Attachment 2. _______*

3. Scans the periodic case and records the highest Value for the highest MFLPD is recorded on value of MFLPD. Attachment 2. _______

4. Scans the periodic case and records the highest Value for the highest MAPRAT is recorded on value of MAPRAT. Attachment 2. _______

5. Scans the periodic case and records reactor Reactor power is recorded on Attachment 2 power. _______

6. Scans the periodic case and records lowest Value for the lowest MCPR is recorded on value of MCPR. Attachment 2. _______

7. Scans the periodic case and records lowest Value for the APRM GAF is recorded on value of APRM GAF Attachment 2.

CRS informed that MFLCPR value is greater

8. Informs the CRS that than 1.

MCPR is out of limits.

CUE: Acknowledge the report. Inform the _______*

candidate that the JPM is complete.

ATTACHMENT 1 Cooper Nuclear Station GARDEL Gardel: Periodic Report Todays Date Current Time A C E B D F Thermal Power 2418.6 MWth 99.98%

APRM 100.1 100.5 100.7 100.6 100.3 100.7 Elect. Power 827.1 MWel APRM GAF 1.006 1.012 1.017 1.017 1.014 1.017 Efficiency 34.18%

APRM -%CTP -0.57 -1.15 -1.70 -1.67 -1.37 -1.70 Coolant Flow 70.5 Mlb/hr 95.95%

LPRM Status Normal APRM ave. 100.53 ADAPT ON TIP+LPRM The 4 most limiting bundles of the core MFLCPR Position MCPR CPRLIM MFLPD Position LHGR LHGRLIM MAPRAT Position APLHGR ALHLIM 1.004 19-32 1.467 1.370 0.800 31-44-04 10.718 13.397 0.887 19-28-05 9.228 10.399 1.004 15-32 1.471 1.370 0.798 35-44-04 10.689 13.397 0.887 21-32-05 9.102 10.257 1.003 23-38 1.532 1.370 0.798 11-38-04 10.686 13.397 0.882 25-34-04 9.289 10.535 1.002 37-24 1.541 1.370 0.794 15-42-04 10.637 13.397 0.805 35-44-04 8.159 10.138 PCIUTL Position 19-28-04 Control Rod Withdrawal Simulator 02 06 10 14 18 22 26 30 34 38 42 46 50 Parameters CR withdrawal 4.81%

51 Ave. Xenon conc. 1593.85E12/cm3 Xenon symmetry -0.03%

47 Core press drop 18.04 psi Average void 47.08%

43 16 Total bypass flow 17.25%

K-effective 1.00159 39 Cycle burnup 2032 GWD/Mt Total pow peaking 2.461 35 Sup plate pres drop 13.19 psi 31 Heat Balance Parameters Feed water flow 9.49 Mlb/hr 27 16 12 16 Feed water temp. 363.66 F Absolute press 1009.78 psi 23 Inlet subcooling 31.33 Btu/lb CR drive temp. 100.00 F 19 CR drive flow 0.02Mlb/hr Cleanup inlet temp. 514.91 F 15 Cleanup system flow 0.11 Mlb/hr Ext. Recirc pump A 2.28 MW 11 16 Ext. Recirc pump B 2.29 MW Steam flow 9.51 Mlb/hr 07 Sup plate pres drop 15.03 psi 03

Nebraska Public Power District SKL034-50-58 (36403)

Cooper Nuclear Station Page 5 of 149 Job Performance Measure for Operations Revision: 00 Task No.: 283016S0101 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to obtain and interpret a Gardel Periodic Case. 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 Reactor is at approximately 100% power.

Initiating Cue(s):

The Control Room Supervisor directs you to obtain a Gardel Periodic Case and to log Official case in 6.LOG.601 Attachment 2 to verify operation is within limits.

Inform the CRS when you have completed you review of the official case.

Nebraska Public Power District SKL034-50-57 (36402)

Cooper Nuclear Station Page 6 of 149 Job Performance Measure for Operations Revision: 00 Task No.: 299012O0301 Determine Isolation Boundaries 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

4. Performance Time: 15 minutes

5. NRC K/As 2.1.24 2.8/3.1 Directions to Examiner:

4. This JPM evaluates the trainees ability to determine appropriate mechanical isolation boundaries.

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

6. 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.

Directions to Trainee:

When I tell you to begin, you are to use station documents to determine the minimum mechanical/piping boundaries required to isolate the RHR 1A pump for removal. RHR 1A Motor has already been tagged and removed. 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.

General Conditions:

N/A

Nebraska Public Power District SKL034-50-57 (36402)

Cooper Nuclear Station Page 7 of 149 Job Performance Measure for Operations Revision: 00 Task No.: 299012O0301 Determine Isolation Boundaries General

References:

1. Procedure 0.49 General Tools and Equipment:

1. Set of Mechanical Prints

2. Copy of 2040 Sheet 1

3. Copy of 2031 Sheet 2 Special Conditions, References, Tools, Equipment:

1. Simulator Setup: N/A.

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 determine the minimum mechanical/piping isolation boundaries required to isolate the RHR 1A pump for removal. RHR 1A Motor has already been tagged and removed. Find and highlight all valves required to be positioned to support this task.

Nebraska Public Power District SKL034-50-57 (36402)

Cooper Nuclear Station Page 8 of 149 Job Performance Measure for Operations Revision: 00 Task No.: 299012O0301 Determine Isolation Boundaries Performance Checklist Standards Initials

9. May reference References procedure 0.49 _______

procedure 0.49.

NOTE: Steps 2 thru 12 can be completed in any order Finds BR 2040 Sheet 1

10. References BR 2040 CUE: When the candidate successfully _______*

Sheet 1 locates 2040 Sheet 1 Provide a copy for the candidate to mark up.

11. Highlights RHR-MO-RHR-MO-15A is highlighted. _______*

15A.

12. Highlights RHR-MO-RHR-MO-13A is highlighted. _______*

13A.

13. Highlights RHR-98. RHR-98 is highlighted. _______*

14. Highlights RHR-58. RHR-58 is highlighted. _______*

15. Highlights RHR-11 RHR-11 is highlighted. _______*

16. Highlights RHR drain RHR-35, RHR 36 and/or RHR 34 are path. _______

highlighted.

17. References BR 2031 Finds BR 2031 Sheet 2.

Sheet 2 to find REC Isolation valves. #CUE: When the candidate successfully _______*

locates 2031 Sheet 2 Provide a copy for the candidate to mark up.

Nebraska Public Power District SKL034-50-57 (36402)

Cooper Nuclear Station Page 9 of 149 Job Performance Measure for Operations Revision: 00 Task No.: 299012O0301 Determine Isolation Boundaries Performance Checklist Standards Initials

18. Highlights REC-75. REC-75 is highlighted. _______*

REC-76 is highlighted.

19. Highlights REC-76. _______*

20. Highlights REC Drain REC-87, 397 and 83 are highlighted. _______

Path.

Gives the highlighted drawings to the examiner.

21. Informs the CRS that the boundaries are _______

identified. #CUE: Acknowledges receipt of the highlighted prints. This JPM is complete.

Nebraska Public Power District SKL034-50-57 (36402)

Cooper Nuclear Station Page 10 of 149 Job Performance Measure for Operations Revision: 00 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to use station documents to determine the minimum mechanical/piping boundaries required to isolate the RHR 1A pump for removal. RHR 1A Motor has already been tagged and removed. 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.

General Conditions:

1. The plant is shutdown in a refueling outage.

2. RHR Loop A is not required to be operable.

Initiating Cue(s):

The Control Room Supervisor directs you to determine the minimum mechanical/piping isolation boundaries required to isolate the RHR 1A pump for removal. RHR 1A Motor has already been tagged and removed. Find and highlight all valves required to be positioned to support this task.

Nebraska Public Power District SKL034-30-52 (16532)

Cooper Nuclear Station Page 11 of 149 Job Performance Measure for Operations Revision 02 Task No.:

Task

Title:

Radiation Protection Table Top Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Time Started: ____________ Time Finished: _____________

Additional Program Information:

1. Appropriate Performance Locations: CR, SIM, Class

2. Appropriate Trainee level: SO, RO, SRO

3. Evaluation Method: Simulate Perform

4. Performance Time: 10 minutes

5. NRC K/A 2.3.1 (4.2)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to determine if certain work can be performed within the confines of the Code of Federal Regulations and CNS procedures.

2. This JPM can be performed any place the operator can access appropriate procedures.

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.

Directions to Trainee:

When I tell you to begin, you are to determine whether you can perform in-vessel work for which you are specially qualified. If you find you cannot perform the work state the reason you cannot. If you can perform the work state what authorization, if any is required prior to performing the work. 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 shutdown to perform in-vessel work.

2. Your on-site exposure is within 10% of the average work group exposure.

General

References:

10CFR20 9.ALARA.1 Personnel dosimetry and Occupational Radiation Exposure program.

Nebraska Public Power District SKL034-30-52 (16532)

Cooper Nuclear Station Page 12 of 149 Job Performance Measure for Operations Revision 02 Task No.:

Task

Title:

Radiation Protection Table Top 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.

Initiating Cue(s):

You have unique skills to perform special in vessel work. Performance of the work is expected to result in a whole body dose of 500 mrem and a shallow dose to the skin of fingers of 7.5 Rem. Your Shift Manager directs you to determine based on your dose history, as provided whether you can perform this work.

Nebraska Public Power District SKL034-30-52 (16532)

Cooper Nuclear Station Page 13 of 149 Job Performance Measure for Operations Revision 02 Task No.:

Task

Title:

Radiation Protection Table Top Performance Checklist Standards Initials

1. Refer to 9.ALARA.1 9.ALARA.1 referenced. ________

2. Pertinent personal Dose Dose History is reviewed. ________

history is reviewed.

3. Pertinent job dose projections for the job are Dose projections are reviewed.

reviewed.

4. Compares the job requirements to the amount Job requirements are reviewed.

of dose that can be ________

received.

SM informed.

5. Informs the SM that he CUE: Acknowledge the report and ask the ________*

cannot perform this job.

operator what impediment exists for performance.

SM informed that the reason is that he/she is limited to 1000 mrem/year because his/her lifetime dose is in excess of the lifetime TEDE

6. Informs the SM why he/she guideline and extensions to this limit cannot cannot perform the job. be granted. ________*

CUE: Acknowledge the report and inform the operator that the JPM is complete.

Nebraska Public Power District SKL034-30-52 (16532)

Cooper Nuclear Station Page 14 of 149 Job Performance Measure for Operations Revision 02 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to determine whether you can perform in-vessel work for which you are specially qualified. If you find you cannot perform the work state the reason you cannot and if you can perform the work state what authorization, if any is required prior to performing the work. 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 shutdown to perform in-vessel work.

2. Your on-site exposure is within 10% of the average work group exposure.

Initiating Cues:

You have unique skills to perform special in vessel work. Performance of the work is expected to result in a whole body dose of 500 mrem and a shallow dose to the skin of fingers of 7.5 Rem. Your Shift Manager directs you to determine based on your dose history, as provided whether you can perform this work.

Nebraska Public Power District SKL034-30-52 (16532)

Cooper Nuclear Station Page 15 of 149 Job Performance Measure for Operations Revision 02 Your Pertinent Statistics Your Age: 32 years Lifetime TEDE: 35 Rem TEDE so far this year: 0.75 Rem Extremities SDE dose so far this year: 35 Rem NCR Form 116 has previously been signed.

Pertinent Job Dose Projections for the one individual performing this job Projected Whole Body Dose: 0.5 Rem Extremities SDE dose: 7.5 Rem

Nebraska Public Power District SKL034-50-56 (36401)

Cooper Nuclear Station Page 16 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259019P0401 Determine RPV Water Level Instrumentation Availability During LOCA Conditions Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: Classroom / Simulator

2. Appropriate Trainee Levels: RO/SRO/STE

3. Evaluation Method: Perform

4. Performance Time: 10 minutes

5. NRC K/A: 295028.EA2.03(CFR: 41.10 / 43.5 / 45.13)(3.7/3.9)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to determine RPV water level instrumentation availability during LOCA conditions.

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 determine RPV water level instrumentation availability during LOCA 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 may ask questions of you if necessary to understand your actions.

Nebraska Public Power District SKL034-50-56 (36401)

Cooper Nuclear Station Page 17 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259019P0401 Determine RPV Water Level Instrumentation Availability During LOCA Conditions General Conditions:

A LOCA has occurred with the following stable plant conditions:

- Narrow range RPV water level + 0" (indicated)

- Shutdown Range + 0 (indicated)

- Steam Nozzle Range + 0 (indicated)

- Wide range RPV water level - 140" (indicated)

- Fuel zone RPV water level - 145 " (indicated)

- RPV pressure 55 psig (6 SRVs open)

- Drywell pressure 53.1 psig (drywell spray unavailable)

- Drywell temp 330 °F (All PC-TI-505's and 510's)

General

References:

1. Procedure 5.8

2. EOP/SAP Graphs General Tools and Equipment:

1. EOP/SAP Graphs Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*".

Nebraska Public Power District SKL034-50-56 (36401)

Cooper Nuclear Station Page 18 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259019P0401 Determine RPV Water Level Instrumentation Availability During LOCA Conditions Task Standards:

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

2. 100% of safety and radiological work practices.

Initiating Cue(s):

You are to determine RPV water level instrumentation availability during LOCA conditions.

Complete the table below with the status of RPV level instruments return this Attachment to the examiner when you have completed this task.

Nebraska Public Power District SKL034-50-56 (36401)

Cooper Nuclear Station Page 19 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259019P0401 Determine RPV Water Level Instrumentation Availability During LOCA Conditions Performance Checklist Standards Initials NOTE: Steps may be performed concurrently or in any order

1. Refer to EOP/SAG The operator refers to EOP/SAG Graphs. _______

Graphs.

The operator refers to EOP/SAG Graphs.

2. Refer to EOP/SAG Determines Narrow range RPV water level is Not _______*

Graphs. Available The operator refers to EOP/SAG Graphs.

3. Refer to EOP/SAG Determines Steam Nozzle Range RPV water level Graphs. is Not Available _______*

The operator refers to EOP/SAG Graphs.

4. Refer to EOP/SAG Determines Shutdown Range RPV water level is Graphs. Not Available _______*

5. Refer to EOP/SAG The operator refers to EOP/SAG Graphs.

Determines Wide range RPV water level is Not _______*

Graphs.

Available The operator refers to EOP/SAG Graphs.

6. Refer to EOP/SAG Determines Fuel Zone RPV water level is Available _______*

Graphs. for Trending

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

paperwork.

Nebraska Public Power District SKL034-50-56 (36401)

Cooper Nuclear Station Page 20 of 149 Job Performance Measure for Operations Revision 00 ATTACHMENT 1 Directions to Trainee:

You are to determine RPV water level instrumentation availability during LOCA conditions.

Complete the table below with the status of RPV level instruments and return this attachment to the examiner when you have completed this task.

General Conditions:

A LOCA has occurred with the following stable plant conditions:

- Narrow range RPV water level + 0" (indicated)

- Shutdown Range RPV water level + 0 (indicated)

- Steam Nozzle Range RPV water level + 0 (indicated)

- Wide range RPV water level - 140" (indicated)

- Fuel zone RPV water level - 145 " (indicated)

- RPV pressure 55 psig (6 SRVs open)

- Drywell pressure 53.1 psig (drywell spray unavailable)

- Drywell temp 330 °F (All PC-TI-505's and 510's)

What is the status of RPV water level instruments?

Level Instrument AFT = Available for Trending, NA = Not Available Narrow range RPV water level Shutdown Range RPV water level Steam Nozzle Range RPV water level Wide range RPV water level Fuel zone RPV water level

Nebraska Public Power District SKL034-30-26 (6253)

Cooper Nuclear Station Page 21 of 149 Job Performance Measure for Operations Revision 07 Task No. 344050O0503 Security Emergency Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Time Started: ____________ Time Finished: _____________

Additional Program Information:

1. Appropriate Performance Locations: SIM / CR

2. Appropriate Trainee Level: SRO / STE

3. Evaluation Method: Perform

4. Performance Time: 25 minutes

5. NRC K/A 2.4.28 (2.3/3.3)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to perform the required actions for a Security Emergency.

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, 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 a Security Emergency as appropriate to the provided 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 in order to complete the assigned task. ALL PLANT ANNOUNCEMENTS WILL BE SIMULATED!

Nebraska Public Power District SKL034-30-26 (6253)

Cooper Nuclear Station Page 22 of 149 Job Performance Measure for Operations Revision 07 Task No. 344050O0503 Security Emergency General Conditions:

1. The plant is operating at 30% power.

2. The Shift Manager has delegated you to direct the plant response.

3. The board operators are available ONLY to support control room actions.

4. You must personally perform any communications required for this situation.

5. The Shift Manager will perform all Emergency Director required actions.

General

References:

1. Emergency Procedure 5.5SECURITY General Tools and Equipment:

1. Site communication System.

2. Emergency Telephone number book.

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):

At 9:35 p.m. you are informed by the Operations Manager that armed intruders have been seen in the protected area. The intruders last known location was the 903 corridor outside the door to the reactor building. The intruders are carrying automatic rifles, pistols and grenades.

You are to perform the required control room actions for this situation until directed to stop by the evaluator.

Nebraska Public Power District SKL034-30-26 (6253)

Cooper Nuclear Station Page 23 of 149 Job Performance Measure for Operations Revision 07 Task No. 344050O0503 Security Emergency Performance Checklist Standards Initials

1. Obtain Procedure Current revision of 5.5SECURITY obtained.

5.5SECURITY. (Note: May be given if the operator goes to ________

procedure rack or lock box in simulator.)

2. Contact the Security Security Shift Supervisor contacted and asked to Shift Supervisor to confirm the threat.

confirm threat.

CUE: As the Security Shift Supervisor, indicate that the intruders posses explosive devices and automatic weapons. An actual Security Threat exists with high potential for significant ________

structural damage and personnel injury. Security is in a Code Red

CUE: Security has just made the following plant announcement, All Station Personnel, Imminent Security Threat exists, seek shelter inside the nearest building. Code Red.

3. Determines that an Enters Attachment 2 Actual Threat exists and enters 5.5Security # CUE: If asked, a credible insider threat ________*

Attachment 2. DOES NOT exist.

CUE: The SM directs you to DIRECT actions per Attachment 2 and he/she will complete remaining actions in Section 4.

Nebraska Public Power District SKL034-30-26 (6253)

Cooper Nuclear Station Page 24 of 149 Job Performance Measure for Operations Revision 07 Task No. 344050O0503 Security Emergency Performance Checklist Standards Initials

4. Directs the reactor be RO directed to scram the reactor.

scrammed.

CUE: As the RO, acknowledge the order ________*

and report that the reactor is scrammed. All control rods are fully inserted. RPV water level and pressure are stable. No EOP entry conditions were met during the scram.

5. Directs level be BOP/RO/WCO directed to maintain level high in maintained high is level the band using RCIC per 2.2.67.1.

band using RCIC ________*

CUE: As the BOP/WCO/RO, acknowledge the order and report that RCIC is running and level is being controlled

+20to +45 using RCIC.

6. Directs Reactor RO/BOP/WCO directed to cooldown reactor not to Cooldown. exceed 90 degrees per hour.

CUE: As the BOP/WCO/RO, acknowledge ________*

the order and report that Reactor pressure is being lowered to 500 psig using Turbine Bypass Valves (or as directed in order by SRO).

7. Directs maximizing RO/BOP/WCO directed to maximize CRD CRD for injection. injection per 5.8.4.

CUE: As the BOP/WCO/RO, acknowledge ________

the order and report that you will review procedure and perform when RB Station Operator is available.

Nebraska Public Power District SKL034-30-26 (6253)

Cooper Nuclear Station Page 25 of 149 Job Performance Measure for Operations Revision 07 Task No. 344050O0503 Security Emergency Performance Checklist Standards Initials

8. Directs the BOP to BOP/WCO directed to ensure that BF-C-1A, ensure that BF-C-1A, EMERGE BSTR FAN is running.

EMERGE BSTR FAN is running. # CUE: As the BOP/WCO, acknowledge the ________*

order and report that BF-C-1A, EMERG BSTR FAN is running.

9. Directs rapid isolation of RO/BOP/WCO directed to remove RWCU from RWCU. service.

CUE: As the BOP/WCO/RO, acknowledge the order and report that RWCU has ________*

been removed from service and isolated. You are following up per 2.2.66.

10. Directs the BOP to BOP/WCO directed to start and run unloaded start and run unloaded both DGs.

both DGs.

CUE: As the BOP/WCO acknowledge the order. (If prestart checks are waived, ________*

report that both DGs are running unloaded.)

NOTE: Controls for the fire pumps do not exist in the simulator.

Nebraska Public Power District SKL034-30-26 (6253)

Cooper Nuclear Station Page 26 of 149 Job Performance Measure for Operations Revision 07 Task No. 344050O0503 Security Emergency Performance Checklist Standards Initials

11. Directs or Starts Electric Directs the BOP/WCO to start the 1E or 1D Fire Fire pump 1E or 1D. Pump or places the 1E or 1D fire pump control switch to start.

CUE: If BOP/WCO directed, then acknowledge the order as the BOP and report that the diesel or motor ________

driven Fire Pump is running. (If the CRS starts the pump the RED light is ON and the GREEN light is OFF for the pump started.)

Nebraska Public Power District SKL034-30-26 (6253)

Cooper Nuclear Station Page 27 of 149 Job Performance Measure for Operations Revision 07 Task No. 344050O0503 Security Emergency Performance Checklist Standards Initials

12. Directs Station Station Operators directed to obtain fire fighting Operators/UT Fire gear and to report to the Control Room.

Brigade to obtain fire fighting gear and report # CUE: Indicate that the Radwaste Station to the Control Room. Operator and UT Fire Brigade personnel have reported to the Control Room.

CUE: The Turbine Building operator contacts the Control Room and reports that he is unable to get to the Control Room at this time. He is just outside the #1 DG room and the 903 area just outside the doors to the control building is blocked by the ________

armed intruders. The intruders are currently unaware of his presence.

The Station Operator requests direction from you.

CUE: The Reactor Building operator contacts the Control Room and reports that he is unable to get out of the Reactor Building at this time. He is in the SE Quad (859 elevation).

The intruders are currently unaware of his presence. The Station Operator requests direction from you.

13. Directs the Duty The Duty Chem/RP Tech is called to the control Chem/RP Tech to room.

report to the control room. # CUE: The Duty Chem/RP Tech reports to ________*

the control room.

Nebraska Public Power District SKL034-30-26 (6253)

Cooper Nuclear Station Page 28 of 149 Job Performance Measure for Operations Revision 07 Task No. 344050O0503 Security Emergency Performance Checklist Standards Initials

14. Directs the TB Station TB Station Operator directed to enter the DG Operator to card into room and RB Station Operator told to stay in Vital the DG room and RB Area.

Station Operator told to ________*

stay in Vital Area. # CUE: TB operator acknowledges the order and reports that he has entered the DG room and RB Station Operator is remaining in current location (or as directed).

PROVIDE THE FOLLOWING CUE:

Annunciators 9-3-3/G-5 ASD Room Door Open and 9-3-3/F-5 ASD Switch Position Abnormal have just alarmed.

15. Responds to ASD Directs RB Station Operator to open EE-DSC-Abnormal indications 125ASD or EE-DSC-125B.

CUE: If asked as RB Station Operator, report that you can get to EE-DSC-125ASD.

CUE: If asked if anyone has been dispatched to CB-903, report that no operator is currently in that area.

CUE: If the SRO directs and operator to ________*

CB-903 to open EE-DSC-125B, report that you have opened EE-DSC-125B

CUE: As RB Station Operator dispatched to open disconnect, report that EE-DSC-125ASD is open.

CUE: The JPM is complete.

Nebraska Public Power District SKL034-30-26 (6253)

Cooper Nuclear Station Page 29 of 149 Job Performance Measure for Operations Revision 07 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to respond to a Security Emergency as appropriate to the provided 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 in order to complete the assigned task. ALL PLANT ANNOUNCEMENTS WILL BE SIMULATED!

General Conditions:

1. The plant is operating at 30% power.

2. The Shift Manager has delegated you to direct the plant response.

3. The board operators are available ONLY to support control room actions.

4. You must personally perform any communications required for this situation.

5. The Shift Manager will perform all Emergency Director required actions.

Initiating Cue(s):

At 9:35 p.m. you are informed by the Security Shift Supervisor that armed intruders have been seen in the protected area. The intruders last known location was the 903 corridor outside the door to the reactor building. The intruders are carrying automatic rifles, pistols and grenades.

You are to perform the required control room actions for this situation until directed to stop by the evaluator.

Nebraska Public Power District SKL034-20-114 (29981)

Cooper Nuclear Station Page 30 of 149 Job Performance Measure for Operations Revision 01 Task No. 341033W0303 Determine Shift Staffing Requirements for Mode Change Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Time Started: ____________ Time Finished: _____________

Additional Program Information:

6. Appropriate Performance Locations: SIM / CR

7. Appropriate Trainee Level: SRO

8. Evaluation Method: Perform

9. Performance Time: N/A

10. NRC K/A 2.1.4 (3.4)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to determine shift staffing requirements for a mode change.

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 evaluate the staff available and determine if a change in Modes can occur without incurring an LCO condition. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

Nebraska Public Power District SKL034-20-114 (29981)

Cooper Nuclear Station Page 31 of 149 Job Performance Measure for Operations Revision 01 Task No. 341033W0303 Determine Shift Staffing Requirements for Mode Change General Conditions:

1. The plant conditions are as follows:

Reactor Pressure is 0 psig

Coolant temperature is 200ºF

Mode Switch is in Shutdown

2. Your Shift complement is comprised of:

One SRO (you)

Two ROs

Three Non-Licensed Nuclear Plant Operators

One RP/Chem Tech General

References:

1. Conduct of Operations Procedure 2.0.3 General Tools and Equipment:

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

1. Critical checks denoted by "*".

Task Standards:

3. 100% of critical elements successfully completed without error.

4. 100% of safety and radiological work practices.

Initiating Cue(s):

During your shift Reactor Coolant temperature is expected to rise to 215ºF as a result of Shutdown Cooling being removed from service. As the Senior Licensed person on your shift, you are to determine two things; 1. Do you have sufficient staff now and 2. will you have sufficient staff to allow you to raise Coolant Temperature to 215ºF during your shift. If not determine how many additional staff types are needed and document your findings on .

Nebraska Public Power District SKL034-20-114 (29981)

Cooper Nuclear Station Page 32 of 149 Job Performance Measure for Operations Revision 01 Task No. 341033W0303 Determine Shift Staffing Requirements for Mode Change

Nebraska Public Power District SKL034-20-114 (29981)

Cooper Nuclear Station Page 33 of 149 Job Performance Measure for Operations Revision 01 Task No. 341033W0303 Determine Shift Staffing Requirements for Mode Change Performance Checklist Standards Initials

16. Obtain ________

Procedure 2.0.3. Current revision of 2.0.3 obtained.

17. Determine section of Procedure The SRO turns to Section 10, Control Room and ________

2.0.3. Shift Staffing Requirements.

18. Determines the The SRO may use Tech Specs to confirm that the ________

current mode. Unit is in MODE 4.

19. Determines the mode to be entered when The SRO may use Tech Specs to confirm that the temperature rises to Unit will be entering Mode 3 within the shift.

215ºF Your Shift complement is comprised of:

20. Determines that the

One SRO (you) current shift staff is

Two ROs ________*

adequate until the

Three Non-Licensed Nuclear Plant Operators mode change.

One RP/Chem Tech For Mode 3 the SRO determines that the following staff types are needed:

Two SRO (so there is a SM and a CRS)

21. Determines which

Three RO (RO, BOP, WCO) staff types are required. ________*

Three Non-Licensed Nuclear Plant Operators

One STE

One RP/Chem Tech The SRO writes the additional needed staff on Attachment 1.

22. Writes the needed

One SRO (so there is a SM and a CRS)

Staff on Attachment 1. ________*

One RO (RO, BOP, WCO)

One STE

Nebraska Public Power District SKL034-20-114 (29981)

Cooper Nuclear Station Page 34 of 149 Job Performance Measure for Operations Revision 01 Task No. 341033W0303 Determine Shift Staffing Requirements for Mode Change Performance Checklist Standards Initials

23. Turns in completed Returns completed Attachment 1 to evaluator. _______

paperwork.

Nebraska Public Power District SKL034-20-114 (29981)

Cooper Nuclear Station Page 35 of 149 Job Performance Measure for Operations Revision 01 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to evaluate the staff available and determine if a change in Modes can occur without incurring an LCO condition. 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 conditions are as follows:

Reactor Pressure is 0 psig

Coolant temperature is 200ºF

Mode Switch is in Shutdown

2. Your Shift complement is comprised of:

One SRO (you)

Two ROs

Three Non-Licensed Nuclear Plant Operators

One RP/Chem Tech Initiating Cue(s):

During your shift Reactor Coolant temperature is expected to rise to 215ºF as a result of Shutdown Cooling being removed from service. As the Senior Licensed person on your shift, you are to determine two things; 1. Do you have sufficient staff now and 2. Will you have sufficient staff to allow you to raise Coolant Temperature to 215ºF during your shift? If not determine how many additional staff types are needed and document your findings on .

Current Staff: Adequate in current mode Inadequate in current mode (Check one)

Additional needed staff:

Staff required at 215ºF: Current staff adequate Additional staff needed.

(Check one)

Nebraska Public Power District SKL034-20-114 (29981)

Cooper Nuclear Station Page 36 of 149 Job Performance Measure for Operations Revision 01 Additional needed staff:

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 37 of 149 Job Performance Measure for Operations Revision 01 Task No.: 202012O0201 PERFORM JET PUMP OPERABILITY CHECK (RO or SRO)

Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: Simulator Only

2. Appropriate Trainee Level: RO / SRO

3. Evaluation Method: Perform in Simulator Only.

4. Performance Time: 18 minutes

5. NRC K/A 202001 K1.06 3.6/3.6 Directions to Examiner:

1. This JPM evaluates the trainee's ability to perform the daily Jet Pump and Recirc Pump Flow Check of the Daily Tech Specs Surveillance Log.

2. Provide the Reactor Recirc and Jet Pump values to the candidate; do not allow them to take the readings form the simulator.

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, 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 activities associated with daily Jet Pump AND Recirc Pump Flow Check. 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.

General Conditions:

1. The plant is operating at rated power with DEH in Mode 4.

2. Both Reactor Recirculation pumps are operating with pump flows balanced.

3. Data is provided for the readings to be taken.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 38 of 149 Job Performance Measure for Operations Revision 01 Task No.: 202012O0201 PERFORM JET PUMP OPERABILITY CHECK (RO or SRO)

General

References:

1. Procedure 6.LOG.601 General Tools and Equipment:

1. Calculator.

2. Jet pump operability curves.

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):

RO.

The Control Room Supervisor directs you to perform the daily Jet Pump (6.LOG.601 Attachment

12) and Recirc Pump Flow Check (6.LOG.601 Attachment 13) as part of the routine shift activities. Notify the CRS when the task is complete.

SRO.

Perform the Control Room Supervisors review of the daily Jet Pump (6.LOG.601 Attachment

12) and Recirc Pump Flow Check (6.LOG.601 Attachment 13) as part of the routine shift activities to ensure that it has been performed correctly. Notify the SM when the task is complete.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 39 of 149 Job Performance Measure for Operations Revision 01 Task No.: 202012O0201 PERFORM JET PUMP OPERABILITY CHECK (RO or SRO)

Performance Checklist Standards Initials NOTE: 1. This is the RO Section.

2. Steps 1 - 5 may be in any order.

Record Core flow from Recorder NBI-FRDPR-95

1. Record indicated core (Green Pen) (+/- 2).

flow (106 lb/hr) _______*

CUE: Core Flow = 62 Record RR pump flow, from RR-FR-163 for Pumps

2. Record RR pump flow A & B (+/- 2).

(103 gpm) _______*

CUE: Pump A = 38.5; Pump B = 38.5 Record RRMG Set speed from the following (+/- 2):

3. Record RRMG Set a. RRFC-SI-1A for RRMG A speed b. RRFC-SI-1B for RRMG B _______*

CUE: RRMG A = 79; RRMG B = 80.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 40 of 149 Job Performance Measure for Operations Revision 01 Task No.: 202012O0201 PERFORM JET PUMP OPERABILITY CHECK (RO or SRO)

Performance Checklist Standards Initials Record Jet Pump Flow from the following (+/- 2):

a. NBI-FI-92A for LOOP A

b. NBI-FI-92B for LOOP B

4. Record Jet Pump Flow CUE: LOOP A = 31; LOOP B = 31 _______*

Record differential pressures from individual jet pump instruments NBI-FI-78A through NBI-FI-78Z on Panel 9-38 in control room (+/- 2).

CUE: 1 = 31 11 = 32 2 = 32 12 = 30 3 = 31 13 = 20

5. Record Jet Pump 4 = 31 14 = 32 Differential Pressure 5 = 36 15 = 34 _______*

6 = 34 16 = 35 7 = 33 17 = 32 8 = 32 18 = 31 9 = 33 19 = 33 10 = 33 20 = 32 Note G, H, I, O, P & Q are not used.

Add JP #1 through 10 and divide by 10 for LOOP B, then add JP #11 through 20 and divide by 10 for

6. Record Loop B and LOOP A (+/- 2).

Loop A Average _______*

CUE: Average 32.6 for LOOP B and 31.1 for LOOP A.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 41 of 149 Job Performance Measure for Operations Revision 01 Task No.: 202012O0201 PERFORM JET PUMP OPERABILITY CHECK (RO or SRO)

Performance Checklist Standards Initials NOTE: Curves are contained in the binder labeled Cooper Nuclear Station Jet Pump Operability Graphs and Instability Noise Level Data.

7. Verify RR pump flow Check 1 Determine that the values recorded in and RRMG set speed Items B and C are within the limits of the curve _______*

within limits. (SAT checked).

8. Verify JP flow and Check 2 Determine that the values recorded in RRMG set speed Items C and D are within or outside the limits of the _______

within limits. curve (SAT checked).

NOTE: Jet Pump 13 is outside the Operability Graphs. The candidate should determine that it falls outside the limit.

9. Jet Pump p differs Check 3 Determine that Jet Pump p differs by by < 20% from 20% from established patterns for (UNSAT _______*

established patterns. checked for Loop A).

10. Verify check 1 and 2 SAT or check 3 SAT. Verify check 1 and check 2 SAT or check 3 is SAT (Check 3 is SAT). _______*

11. Verify operation is not in Stability Exclusion Determines operation is outside Stability Exclusion Region of Power to Region of Power to Flow Map using core flow value recorded in Item A on previous page and 2.1.10 _______*

Flow Map.

Power to Flow Map.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 42 of 149 Job Performance Measure for Operations Revision 01 Task No.: 202012O0201 PERFORM JET PUMP OPERABILITY CHECK (RO or SRO)

Performance Checklist Standards Initials

12. Verify loop flow mismatch is within limit when at < 51.45 Determine Step is N/A.

x106 lbs/hr core flow.

13. Verify loop flow mismatch is within Determine Item D values (previous page of limits when 51.45x106 6.LOG.601) for Loop A and Loop B flow mismatch _______*

lbs/hr core flow. is 3.67x106 lbs/hr (SAT entered into block).

14. Verify Recirc Pump operating or RHR Determine Step is N/A.

Pump operating in _______

SDC.

Inform Control Room Supervisor that the daily Jet Pump and Recirc Pump Flow Check is Complete

15. Inform the CRS that and Jet Pump 13 d/p is low out of spec.

the task is complete. _______

CUE: The CRS Acknowledges the report.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 43 of 149 Job Performance Measure for Operations Revision 01 Task No.: 202012O0201 PERFORM JET PUMP OPERABILITY CHECK (RO or SRO)

SRO Section Performance Checklist Standards Initials NOTE: 1. SRO Section

2. Declares Jet Pump 13 inop.

1. Reviews Attachment Reviews Attachment 12 Jet Pump Operability 12 Jet Pump Items A, B, C and D. Notes that all have been filled _______

Operability Items. out correctly.

2. Reviews Attachment 12 Jet Pump Reviews Attachment 12 Jet Pump Operability Operability Checks 1, Items 1, 2, and 3. Notes that Check 3 should be _______*

2 and 3. checked Unsat and denotes it.

3. Reviews Attachment Reviews Attachment 13 RECIRC Pump Flow 13 RECIRC Pump Checks, NBI-FRDPR-95 is outside of the Exclusion Flow Checks Checks Region. Checks that it is marked SAT correctly. _______*

4. Reviews Attachment Reviews Attachment 13 RECIRC Pump Flow 13 RECIRC Pump Checks, NBI-FI-92A/B Mismatch should be N/Aed Flow Checks Checks for this flow. _______

5. Reviews Attachment Reviews Attachment 13 RECIRC Pump Flow 13 RECIRC Pump Checks, NBI-FI-92A/B Mismatch should be marked Flow Checks Checks SAT. Checks that it is marked SAT correctly. _______*

6. Reviews Attachment 13 RECIRC Pump Reviews Attachment 13 RECIRC Pump Flow Flow Checks Checks Checks, Recirc Pump operating or RHR Pump _______

operating in SDC is marked N/A.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 44 of 149 Job Performance Measure for Operations Revision 01 Task No.: 202012O0201 PERFORM JET PUMP OPERABILITY CHECK (RO or SRO)

Performance Checklist Standards Initials Notifies the Reactor Engineer that Jet Pump 13 d/p is low out of spec.

7. Notifies Reactor Engineer CUE: As reactor engineer respond to the report and tell the CRS that it was not low last time the _______

surveillance was run.

Contacts the Shift Manager and tells him that Jet Pump 13 is low out of spec and that was not that

8. Notifies the Shift way last surveillance.

Manager CUE: Respond as the Shift Manager and tell the _______

CRS that the JPM is completed.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 45 of 149 Job Performance Measure for Operations Revision 01 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to perform the daily Jet Pump and Recirc Pump Flow Check.

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.

General Conditions:

1. The plant is operating at rated power with DEH in Mode 4.

2. Both Reactor Recirculation pumps are operating with pump flows balanced.

Initiating Cues:

RO.

The Control Room Supervisor directs you to perform the daily Jet Pump (6.LOG.601 2) and Recirc Pump Flow Check (6.LOG.601 Attachment 13) as part of the routine shift activities. Notify the CRS when the task is complete.

Jet Pumps 1 = 31 11 = 32 2 = 32 12 = 30 3 = 31 13 = 20 4 = 31 14 = 32 5 = 36 15 = 34 6 = 34 16 = 35 7 = 33 17 = 32 8 = 32 18 = 31 9 = 33 19 = 33 10 = 33 20 = 32 SRO.

Perform the control room supervisors review of the daily jet pump (6.log.601 attachment 12) and recirc pump flow check (6.log.601 attachment 13) as part of the routine shift activities to ensure that it has been performed correctly. Notify the Shift Manager when the task is complete.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 46 of 149 Job Performance Measure for Operations Revision 01 ATTACHMENT 12 JET PUMP OPERABILITY RO SECTION ATTACHMENT 12 JET PUMP OPERABILITY NOTE - If in single loop operation, mark idle loop N/A.

JET PUMP P (%)

LOOP LOOP LOOP ITEMS A B JP # B JP # LOOP A 6

Core Flow (10 lb/hr) NBI-FRDPR-A 1 11 95 RR Pump Flow (103 gpm) RR-FR-B 2 12 163 RRMG Set Speed (%) RRFC-SI-C 3 13 1A/B D JP Flow (106 lb/hr) NBI-FI-92A/B 4 14 5 15 6 16 7 17 8 18 9 19 10 20 LOOP LOOP B Avg A Avg UNSA OPERABILIT APPLICABL ATT. 21 CHECKS SAT T Y LIMIT E MODE NOTE Loop A: 1 (b), 2 (b) 50 Item B and C values 9 1

within curve limits (a) Loop B:

9 Loop A:

Item C and D values 9 2 SAT within curve limits (a) Loop B:

9 Loop A:

Jet Pump P differs by 9 3 20% from established patterns (a, c) Loop B:

9

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 47 of 149 Job Performance Measure for Operations Revision 01 Loop A:

Checks 1 and 2 SAT, or 9 SAT Check 3 SAT Loop B:

9 (a) Refer to Jet Pump Operability Curves maintained in Control Room.

(b) Required to be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 25% RTP and required to be performed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in service.

(c) If any Jet Pump P vs. established pattern is not within curve limits, immediately notify Reactor Engineering.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 48 of 149 Job Performance Measure for Operations Revision 01 3 RECIRC PUMP FLOW CHECKS RO Section ATTACHMENT 13 RECIRC PUMP FLOW CHECKS 0700-1000 1900-2200 OPERABILITY APPLICABLE ATT. 21 CHECKS SAT/UNSAT SAT/UNSAT LIMIT MODES NOTES Core Flow, MCO NBI-DPR/FR-95, value is not in Stability SAT 1, 2 49 Exclusion Region of Power to Flow Map (a)

JP Flow, NBI-FI-92A/B, MCO values for Loop A and Loop B flow mis-match SAT 1 (c), 2 (c) 48, 127 is 7.35x106 lbs/hr at

< 51.45x106 lbs/hr Rated Core Flow (b) (d)

JP Flow, NBI-FI-92A/B, MCO values for Loop A and Loop B flow mis-match SAT 1 (c), 2 (c) 48, 127 is 3.67x106 lbs/hr at 51.45x106 lbs/hr Rated Core Flow (b) (d)

(a) Refer to power to flow map in Procedure 2.1.10.

(b) Per Technical Specification and TRM Bases, a recirculation loop is considered not in operation when the mis-match between total jet pump flows of the two loops is greater than required limits. The loop with the lower flow must be considered not in operation.

(c) Required to be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in service.

(d) If a flow mismatch results in one loop considered not in operation, contact FRED to manually insert single loop operation limits into GARDEL.

0700-1000 1900-2200 READING READING OPERABILITY APPLICABLE ATT. 21 CHECK (9) (e) (9) (e) LIMIT MODES NOTES 3 (when Reactor Verify Recirc Pump RR Pump or Pressure is operating or RHR Pump SDC in 66 less than SDC operating in SDC Operation Pressure Permissive) (f)

(e) 9 indicates at least one RR pump or SDC Subsystem is in service.

(f) Required to be met within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the shutdown cooling permissive pressure.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 49 of 149 Job Performance Measure for Operations Revision 01 Attachment 12 JET PUMP OPERABILITY SRO Section ATTACHMENT 12 JET PUMP OPERABILITY NOTE - If in single loop operation, mark idle loop N/A.

JET PUMP P (%)

LOOP LOOP LOOP ITEMS A B JP # B JP # LOOP A 6

Core Flow (10 lb/hr) NBI-DPR/FR-A 62 1 31 11 32 95 RR Pump Flow (103 gpm) RR-FR- 30 B 38.5 38.5 2 32 12 163 RRMG Set Speed (%) RRFC-SI-C 79 80 3 31 13 20 1A/B D JP Flow (106 lb/hr) NBI-FI-92A/B 31 31 4 31 14 32 5 36 15 34 6 34 16 35 7 33 17 32 8 32 18 31 9 33 19 33 10 33 20 32 LOOP LOOP 32.6 31.1 B Avg A Avg UNSA OPERABILIT APPLICABL ATT. 21 CHECKS SAT T Y LIMIT E MODE NOTE Loop A: 1 (b), 2 (b) 50 9

Item B and C values 9 1

within curve limits (a) Loop B:

9 9

Loop A:

9 Item C and D values 9 2 SAT within curve limits (a) Loop B:

9 9

Loop A:

Jet Pump P differs by 9 9

3 20% from established patterns (a, c) Loop B:

9 9

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 50 of 149 Job Performance Measure for Operations Revision 01 Loop A:

9 Checks 1 and 2 SAT, or 9 SAT Check 3 SAT Loop B:

9 9

(a) Refer to Jet Pump Operability Curves maintained in Control Room.

(b) Required to be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 25% RTP and required to be performed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in service.

(c) If any Jet Pump P vs. established pattern is not within curve limits, immediately notify Reactor Engineering.

Nebraska Public Power District SKL034-20-113 (29979)

Cooper Nuclear Station Page 51 of 149 Job Performance Measure for Operations Revision 01 Attachment 13 RECIRC PUMP FLOW CHECKS SRO Section ATTACHMENT 13 RECIRC PUMP FLOW CHECKS 0700-1000 1900-2200 OPERABILITY APPLICABLE ATT. 21 CHECKS SAT/UNSAT SAT/UNSAT LIMIT MODES NOTES Core Flow, NBI-DPR/FR-95, value is not in Stability SAT MCO SAT 1, 2 49 Exclusion Region of Power to Flow Map (a)

JP Flow, NBI-FI-92A/B, values for Loop A and Loop B flow mis-match N/A MCO SAT 1 (c), 2 (c) 48, 127 is 7.35x106 lbs/hr at

< 51.45x106 lbs/hr Rated Core Flow (b) (d)

JP Flow, NBI-FI-92A/B, values for Loop A and Loop B flow mis-match SAT MCO SAT 1 (c), 2 (c) 48, 127 is 3.67x106 lbs/hr at 51.45x106 lbs/hr Rated Core Flow (b) (d)

(a) Refer to power to flow map in Procedure 2.1.10.

(b) Per Technical Specification and TRM Bases, a recirculation loop is considered not in operation when the mis-match between total jet pump flows of the two loops is greater than required limits. The loop with the lower flow must be considered not in operation.

(c) Required to be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in service.

(d) If a flow mismatch results in one loop considered not in operation, contact FRED to manually insert single loop operation limits into GARDEL.

0700-1000 1900-2200 READING READING OPERABILITY APPLICABLE ATT. 21 CHECK (9) (e) (9) (e) LIMIT MODES NOTES 3 (when Reactor Verify Recirc Pump RR Pump or Pressure is operating or RHR Pump N/A N/A SDC in 66 less than SDC operating in SDC Operation Pressure Permissive) (f)

(e) 9 indicates at least one RR pump or SDC Subsystem is in service.

(f) Required to be met within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the shutdown cooling permissive pressure.

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 52 of 149 Job Performance Measure for Operations Revision 02 Task No. 341013O0303 Approve Radioactive Discharge-Release Permit Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Additional Program Information:

11. Appropriate Performance Locations: SIM / CR

12. Appropriate Trainee Level: SRO

13. 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.

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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 53 of 149 Job Performance Measure for Operations Revision 02 Task No. 341013O0303 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 Manager complete the Liquid Radioactive Waste Discharge Form for the FDST (Attachment 1) and inform me when all required actions are complete.

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 54 of 149 Job Performance Measure for Operations Revision 02 Task No. 341013O0303 Approve Radioactive Discharge-Release Permit Performance Checklist Standards Initials

1. Records Stop Run Data in Operator records Date as 1/6/xx, records time Section 5. as 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: 16360 to 16380 gallons.

4. Records total time of Operator calculates total time of discharge in discharge. 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 56-57 gpm.

6. Records River Level. Operator records river level as 880 ft MSL.

CUE: River level is 880 ft MSL.

7. Removes Discharge In Operator would remove or direct control room Progress Tags from running operator to remove the tags from the running CWPs. CWPs. ________

CUE: Tags are removed.

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Cooper Nuclear Station Page 55 of 149 Job Performance Measure for Operations Revision 02 Task No. 341013O0303 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.

CUE: Chemistry reports total river flow is ________

5.9E7 l/min. (This may be completed by the Chemist after SM signature.)

9. Completes discharge permit. Operator signs form as Shift Manager and forwards to Chemistry for review. ________

CUE: Accept form as Chemist.

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 56 of 8 Job Performance Measure for Operations Revision: 02 Attachment 1LIQUID RADIOACTIVE WASTE DISCHARGE FORM ATTACHMENT 1 LIQUID RADIOACTIVE WASTE DISCHARGE FORM Section 1. REQUEST FOR ANALYSIS OF RADIOACTIVE LIQUID WASTE PRIOR TO DISCHARGE To: Chemistry From: Shift Manager Tank To Be Discharged: FDST Started Recirculation For Sample: Time: 0300 Date: 1/6/xx Recirculation Of Tank Complete: Time: 0500 Date: 1/6/xx Estimated Volume To Be Discharged: 98%-10.5% = 87.5%

Shift Manager: Mark Helen Time: 0555 Date: 1/6/xx Section 2. THIS SECTION TO BE COMPLETED BY PERSON TAKING SAMPLE Monitor Source Check Informed Control Room And Performed Source Check Initials: REW Sample Point: 18 Time: 0635 Date: 1/6/xx Signature: Ray Moname Section 3. AUTHORIZATION TO RELEASE RADIOACTIVE LIQUID WASTE To: Shift Manager From: Chemistry Release Authorization Number:

Total Ci/ml: 3.74E-5 Total Concentration is < 1.0E-02 Ci/ml YES/NO Signature: Ray Moname 31 Day Dose, Percent Of Annual Limit For Each Value Is 2.0E+00 YES/NO Signature: Ray Moname You Are Authorized To Release Subject Tank With 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 Discharge If Above Specifications Cannot Be Maintained. Contents Of This Tank Are Within Chemical Parameters For Discharge.

Chemistry: Ray Moname Time: 0707 Date: 1/6/xx

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 57 of 8 Job Performance Measure for Operations Revision: 02 Section 4. SHIFT MANAGER APPROVAL TO RELEASE 4.1 Circle Appropriate Discharge Canal Flow Rate:

NUMBER OF AVERAGE CW DISCHARGE FLOWRATE (gpm)

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 Manager The Subject Tank Contents Are Approved For Release Subject To The Following Restrictions:

1) Maximum Liquid Disch Rate: 100 gpm (Section 3)

2) Minimum Dilution Flow To Canal Of: 159000 gpm (Section 3)

3) Alarm Limits Specified (Section 3)

4) Tank Volume Verified: 98 (Compare To Section 1)

5) DISCHARGE IN PROGRESS Tags Installed On Running Circ Water Pumps.

Approval To Release:

Shift Manager: Mark Helen Time: 0804 Date: 1/6/xx

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Cooper Nuclear Station Page 58 of 8 Job Performance Measure for Operations Revision: 02 Section 5. To: Chemist From: Shift Manager The Subject Discharge Has Been Completed And The Following Data Obtained During The Discharge:

START STOP RUN % TANK RUN % TANK NUMBER DATE TIME LEVEL NUMBER DATE TIME LEVEL 1 1/6/xx 0905 98 1 2 2 3 3 4 4 Usable Tank Volumes (0% to 100%)

FDST - 18,707 gal WST A - 20,015 gal WST B - 20,015 gal

1) Dilution Flow (Section 4.1): gpm

2) Volume Of Release: gal

3) Total Time Of Discharge: min

4) Discharge Flow: gpm

5) River Level: ft MSL

6) Remove DISCHARGE IN PROGRESS Tags From Running Circ Water Pumps.

7) Total River Flow: l/min (Determined By The Chemist)

Shift Manager: Time: Date:

Chemist Review: Date:

Nebraska Public Power District SKL034-50-29 (8908)

Cooper Nuclear Station Page 59 of 8 Job Performance Measure for Operations Revision: 02 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 SKL034-30-62 (36404)

Cooper Nuclear Station Page 60 of 149 Job Performance Measure for Operations Revision 00 ATWS SCENARIO EAL Trainee: Examiner:

Pass: Fail: Examiner signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: SIM

2. Appropriate Trainee Level: SRO

3. Evaluation Method: Perform

4. Performance Time: 20 minutes

5. NRC K/A 2.4.41 2.3/4.1 Directions to Examiner:

1. This JPM evaluates the trainee's ability to determine the Emergency Action Level from an ATWS Scenario (Scenario 1).

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

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.

General Conditions:

1. As seen during the previous simulator scenario.

General

References:

1. EPIP 5.7.1, Emergency Classification, Revision 33 General Tools and Equipment:

None

Nebraska Public Power District SKL034-30-62 (36404)

Cooper Nuclear Station Page 61 of 149 Job Performance Measure for Operations Revision 00 ATWS SCENARIO EAL Special Conditions, References, Tools, Equipment:

1. Simulator Setup: NA

2. Critical checks denoted by "*".

3. Simulator cues denoted by "#".

Task Standards:

1. Accurately classify the event using the correct plant procedure.

Initiating Cue(s):

The Shift Manager has directed you to determine what the highest Emergency Action Level was during the previous scenario. Notify the Shift Manager when the task is complete.

Nebraska Public Power District SKL034-30-62 (36404)

Cooper Nuclear Station Page 62 of 149 Job Performance Measure for Operations Revision 00 ATWS SCENARIO EAL Performance Checklist Standards Initials

1. Consult EAL. Candidate consults EAL procedure.

Candidate identifies that a Site Area Emergency would have been declared per

2. EAL classification. EAL 3.3.4. This is because boron was injected to shut down the reactor.

Inform Shift Manager that the Emergency Classification is complete.

3. Inform the SM that the task is complete. _______

CUE: The SM Acknowledges that it is complete. This JPM is complete.

Nebraska Public Power District SKL034-30-62 (36404)

Cooper Nuclear Station Page 63 of 149 Job Performance Measure for Operations Revision 00 ATWS SCENARIO EAL

Nebraska Public Power District SKL034-30-62 (36404)

Cooper Nuclear Station Page 64 of 149 Job Performance Measure for Operations Revision 00 ATTACHMENT 1 Directions to Candidate:

When I tell you to begin, you are to determine the Emergency Action Level from the ATWS Scenario you just experienced. Before you start, I will state the general plant conditions, the initiating cues and answer any questions you may have.

General Conditions:

1. As seen during the previous simulator scenario.

Initiating Cues:

The Shift Manager has directed you to determine what the highest Emergency Action Level was during the previous scenario. Notify the Shift Manager when the task is complete.

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Task

Title:

Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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Trainee: Examiner:

Pass [ ]; Fail [ ] Examiner Signature: Date:

Additional Program Information:

NOTE THIS IS AN ALTERNATE PATH JPM.

1. Appropriate Performance Locations: CR/SIM

2. Appropriate Trainee Level: RO/SRO

3. Evaluation Method: Perform Simulate

4. Performance Time: 8 minutes

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

Directions to Examiner:

NOTE THIS IS AN ALTERNATE PATH JPM. The flow subtracting network will fail and require manual input of total core flow.

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

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

7. 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.

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

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

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Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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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:

7. The plant is operating at power.

8. 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

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Task

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Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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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.

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Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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Performance Checklist Standards Initials

1. Assume the watch at panel The operator positions himself in a position to 9-5. 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 Recirc pump. of B Reactor Recirculation pump. *

CUE: Acknowledge the report as CRS.

Directs 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 3 for stability Attachment 3 for stability exclusion region; exclusion region. determines entry is required.

CUE: Acknowledge the report as CRS and another operator will address stability exclusion region.

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Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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Performance Checklist Standards Initials

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

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

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 closed for 5 minutes, open been 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 transferred to Startup the Startup Transformer.

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

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Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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Performance Checklist Standards Initials

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

CUE: Acknowledge/repeat back order as Station Operator.

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

TEMP.

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

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

Loop Operation per Procedure 2.2.68.1.

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

lockout relays and targets for tripped pump. #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 above 20%

concurrently enter rated.

Attachment 2.

CUE: Indicated core flow is 41 Mlbm/hr.

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Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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Performance Checklist Standards Initials

16. Align RRMG H&V System Operator aligns RRMG H&V System per per Procedure 2.2.85. Procedure 2.2.85.

CUE: When operator initiates action to align ventilation, inform him that another operator will perform the ventilation alignment.

17. Raise core flow to Operator determines core flow is >

> 29.5x106 lbs/hr, if possible. 29.5x106 lbs/hr CUE: Indicated core flow is 41 Mlbm/hr.

18. Determine if reverse flow Operator determines reverse flow summer is summer is functioning. NOT functioning as annunciator 9-4-3/E-7 is

NOT in and indicated core flow is NOT approximately equal to difference between NBI-FI-92A and NBI-FI-92B CUE: 9-4-3/E-7 is NOT alarming.

CUE: NBI-FI-92A reads 37 Mlbm/hr.

NBI-FI-92B reads 4 Mlbm/hr.

19. Initiate an emergency Work Operator initiate an emergency Work Order to Order to repair or replace repair or replace reverse flow summer reverse flow summer (NBI-SUM-97).

(NBI-SUM-97).

CUE: Another operator will perform this task.

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Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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Performance Checklist Standards Initials

20. Determine difference Operator determines difference between between NBI-FI-92A and NBI-FI-92A and NBI-FI-92B loop flows is

NBI-FI-92B loop flows. 31x106 lbs/hr.

NOTE: Entering substitute value for point B012 is accomplished using an IDT terminal and pressing the Bogey Value button. On screen prompts will guide the rest of the substitution.

21. Enter substitute value for Operator enters difference between PMIS Point B012. NBI-FI-92A and NBI-FI-92B loop flows as

substitute for PMIS Point B012.

CUE: PMIS Point B012 has been substituted for.

CUE: SIMULATOR ONLY. Ask the candidate to verify that the core flow value has updated on the power to flow map.

22. Verify value substituted for Operator enters turn-on code of PFMAP and PMIS Point B012 (Simulator verifies core flow value matches value ONLY). substituted.

NOTE: As soon as the student attempts to contact the Reactor Engineer, tell them that the JPM is complete.

23. Initiate actions to notify the Initiate actions to notify the Reactor Engineer Reactor Engineer about that MCPR needs to be adjusted for single MCPR. loop operations

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Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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ATTACHMENT 1 SIMULATOR SET-UP A. Materials required None B. Initialize the Simulator in any full power IC (IC-18, 19 or 20 suggested)

Batch File name - none.

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

1. Triggers Number File Name Description E1 None trgset 11 "zlorrmgfbb(1)==1"

^B Recirc MG Field Breaker green light on

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

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Respond to a Trip of a Reactor Recirc Pump (Alternate Path)

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4. Overrides Instrument Tag Trigger TD Value Ramp 9-4-3/E-7, RECIRC LOOP B RA:MUX08C108 A 0 OFF 0 OUT OF SERVICE Total Core Flow ZAONBIDPRFR95[2] E1 0:10 41 0:10 A Loop Flow ZAONBIFI92A E1 0:12 37 0:12 B Loop Flow ZAONBIFI92B E1 0:15 4 1:00

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 SKL034-21-56 (8779)

Cooper Nuclear Station Page 75 of 11 Job Performance Measure for Operations Revision: 02 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:

9. The plant is operating at power.

10. You are the CRO - Reactor Operator (RO) (9-5 PNL).

11. 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 SKL034-22-03 (36408)

Cooper Nuclear Station Page 76 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259058G401 Perform a Quick Restart of RFPT A (Hard Card) (Alternate Path)

Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Additional Program Information:

THIS IS AN ALTERNATE PATH JPM

1. Appropriate Performance Locations: CR / SIM

2. Appropriate Trainee level: RO / SRO

3. Evaluation Method: Simulate Perform

4. Performance Time: 20 minutes

5. NRC K/A 259001 A4.02 (3.9/3.7)

Directions to Examiner:

THIS IS AN ALTERNATE PATH JPM. THE INITIAL ATTEMPT TO RESET THE NOTE: RFPT TRIP WILL FAIL AND REQUIRE USE OF THE ALTERNATIVE METHOD TO RESET THE TRIP.

1. This JPM evaluates the trainee's ability to perform a quick start of a RFPT

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. DO NOT place the simulator in RUN until the student is ready to perform the JPM.

(RFP must be coasting down or on turning gear < 5 minutes to use this procedure section.)

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

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 a quick start of the A RFPT. 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

Nebraska Public Power District SKL034-22-03 (36408)

Cooper Nuclear Station Page 77 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259058G401 Perform a Quick Restart of RFPT A (Hard Card) (Alternate Path) 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.

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General Conditions:

1. The Reactor has scrammed.

2. Both RFPs have tripped on high level.

General

References:

1. Procedure 2.2.28

8. Procedure 2.2.28.1 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 restart A RFP in Reactor Pressure Follow Mode and raise RPV water level to the GREEN Band using the quick restart hard card.

Nebraska Public Power District SKL034-22-03 (36408)

Cooper Nuclear Station Page 78 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259058G401 Perform a Quick Restart of RFPT A (Hard Card) (Alternate Path)

Performance Checklist Standards Initials Ensure RFPT coasting from trip or not on turning

1. Ensure RFPT time gear > 5 minutes after trip.

limit is met. _______

CUE: RFPTs are still coasting down.

NOTE: RFPT Trips are as follows:

1. Low pump suction pressure of 260 psig after a 15 second time delay

2. Exhaust casing high pressure at 7" Hgv

3. Exhaust casing high temperature of 23°F

4. Low lube oil pressure of 10 psig

5. Thrust bearing wear at 10 psig oil pressure

6. High reactor water level of 52.5" (Tech Spec < 54")

7. Electrical overspeed at 5950 rpm

8. Mechanical overspeed at 6050 to 6150 rpm

9. Emergency trip pushbutton operation Ensure RFPT trips (except high water level) are reset. Check the following annunciators are clear:

- A-1/A-6 (Low Suction Pressure),

- A-1/B-4 (Exhaust Hood High Temp),

- A-1/B-5 (Low Vacuum Trip),

- A-1/B-6 (Thrust Bearing Trip),

2. Ensure RFPT trips are - A-1/C-4 (Low Oil Pressure Pre Trip) reset. Ensure reactor water level is < 54 _______

Check RFPT/Main Turbine high RPV water level trip amber lights (panel 9-5)

CUE: All trips (except high RPV water level) are reset.

Nebraska Public Power District SKL034-22-03 (36408)

Cooper Nuclear Station Page 79 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259058G401 Perform a Quick Restart of RFPT A (Hard Card) (Alternate Path)

At Panel 9-5, reset at least 2 of the HIGH WATER

3. Ensure High RPV water LEVEL TRIPS.

level RFPT trips are reset. CUE: All 3 High RPV water level trips were in and now have been reset.

4. Ensure RFP-CS-RFPT- Operator ensures RFP-CS-RFPT-A is in MDVP A RFPT A Control Station is in MDVP CUE: RFP-CS-RFPT-A is in MDVP Operator ensures OUTPUT on RFP-CS-RFPT-A

5. Ensure OUTPUT on is adjusted to minimum.

RFP-CS-RFPT-A is _______

adjusted to minimum. CUE: OUTPUT on RFP-CS-RFPT-A is adjusted to minimum.

Press and hold RFPT A TRIP RESET button.

Note the RFPT A HP and LP STOP valves are

6. Attempt to reset A NOT open.

RFPT _______

CUE: HP and LP STOP valves red light are OFF Green lights are ON.

7. Recognize and report Recognize and report the A RFPT trip reset the trip reset failure. failure. _______

Press and hold RFPT A OVERSPEED TRIP BLOCK and RFPT A OVERSPEED TRIP RESET.

8. Reset A RFPT CUE: HP and LP STOP valves red lights are ON _______*

Green lights are OFF.

Ensure RF-FCV-11A, MIN FLOW VALVE, is

9. Ensure RF-11A is open.

OPEN _______

CUE: RF-FCV-11A Red light is ON and Green light OFF.

Nebraska Public Power District SKL034-22-03 (36408)

Cooper Nuclear Station Page 80 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259058G401 Perform a Quick Restart of RFPT A (Hard Card) (Alternate Path)

At a HMI, select FEEDPUMP A screen for desired RFP to be started.

10. Select RFP CUE: A RFP selected _______

Select QUICK RESTART start type.

11. Select Quick Restart.

CUE: Quick restart selected _______*

If extraction steam is available, select LP START.

Otherwise, select HP START.

12. Select HP Start. _______*

.CUE: HP Start selected Press green START button and confirm start in

13. Press green Start pop-up box button and confirm start _______*

in pop-up box. CUE: Start in Pop-up box.

After RFP A(B) reaches MINIMUM GOVERNOR, depress green CONTINUE button.

14. Continue Button _______*

CUE: green CONTINUE button depressed.

Ensure injection path is aligned to the reactor vessel, as dictated by plant conditions

15. Ensure injection path _______

CUE: Path lined up Use UP arrow to raise RFP speed to raise RFP discharge pressure.

16. Raise speed CUE: RFP speed rising. _______

Nebraska Public Power District SKL034-22-03 (36408)

Cooper Nuclear Station Page 81 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259058G401 Perform a Quick Restart of RFPT A (Hard Card) (Alternate Path)

Place RFP in desired mode (e.g., AUTO or REACTOR PRESSURE FOLLOW).

17. Place In Reactor Pressure Follow CUE: In Reactor pressure follow _______*

If required, adjust STARTUP MASTER controller using UP/DOWN arrows or RAMP FUNCTION, to adjust LEVEL SETPOINT as desired.

18. Raise Level _______*

CUE Level at 35 Inform the Control Room Supervisor that 1A RFP has been restarted and injecting into the RPV

19. Inform the CRS that the task is Complete. _______

CUE: CRS acknowledges the report.

Nebraska Public Power District SKL034-22-03 (36408)

Cooper Nuclear Station Page 82 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259058G401 Perform a Quick Restart of RFPT A (Hard Card) (Alternate Path)

ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator in IC Any IC that will support this JPM C. Run Batch File None D. Change the simulator Number Title Tgr TD Sev Ramp Initial conditions as follows:

1. Triggers None Shutdown

2. Malfunctions RR19 Cooling Loss 100 of Mass N/A N/A

3. Remotes None N/A N/A RFPT-A Trip

4. Overrides ZDIRFSWRFTRA[1] Reset OFF Pushbutton

a. Place the Simulator in run.

b. Use Monitor Parameter RRMRVLOSS to reset malfunction RR19.

c. Place the Mode Switch to Shutdown.

d. Secure two Condensate and Condensate Booster pumps.

e. If water level needs to be lowered insert RR19.

5. Panel Setup

f. Ensure the A RFP is still coasting down or is on the turning gear.

g. Ensure RPV water level is < +50" (narrow range).

h. Insert listed switch override.

i. Place the Simulator in FREEZE until the operator is ready to begin.

Note: If this JPM is to be performed more than once, take a SNAPSHOT after the panel setup is complete.

Nebraska Public Power District SKL034-22-03 (36408)

Cooper Nuclear Station Page 83 of 149 Job Performance Measure for Operations Revision 00 Task No.: 259058G401 Perform a Quick Restart of RFPT A (Hard Card) (Alternate Path)

Nebraska Public Power District SKL034-22-03 (36408)

Cooper Nuclear Station Page 84 of 149 Job Performance Measure for Operations Revision 00 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to perform a quick start of the A RFPT. 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 Reactor has scrammed.

2. Both RFPs have tripped on high level.

Initiating Cues:

The Control Room Supervisor directs you to restart A RFP in Reactor Pressure Follow Mode and raise RPV water level to the GREEN Band using the quick restart hard card.

Nebraska Public Power District SKL034-21-48 (7405)

Cooper Nuclear Station Revision 02 Job Performance Measure Page 85 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:206005O0101

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Task

Title:

Manually Initiate HPCI (Hard Card) (Alternate Path)

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Trainee: Examiner:

Pass [ ]; Fail [ ] Examiner Signature: Date:

Additional Program Information:

NOTE THIS IS AN ALTERNATE PATH JPM.

1. Appropriate Performance Locations: CR/SIM

2. Appropriate Trainee Level: RO/SRO

3. Evaluation Method: Perform Simulate

4. Performance Time: 8 minutes

5. NRC K/As 206000 K3.02 (3.8/3.8) and A4.01 (3.8/3.7)

Directions to Examiner:

NOTE THIS IS AN ALTERNATE PATH JPM. THE FLOW CONTROLLER WILL FAIL TO OPERATE IN AUTOMATIC AND MUST BE PLACED IN MANUAL.

10. This JPM evaluates the trainees ability to perform the injection mode of operation of HPCI per the guidance of procedure 2.2.33.1, High Pressure Coolant Injection System Operations (hard card).

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

12. 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.

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

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

Nebraska Public Power District SKL034-21-48 (7405)

Cooper Nuclear Station Revision 02 Job Performance Measure Page 86 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:206005O0101

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Task

Title:

Manually Initiate HPCI (Hard Card) (Alternate Path)

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Directions to Trainee:

When I tell you to begin, you are to operate HPCI in the injection mode at rated flow using the hard card. 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:

12. The Reactor is shutdown following a scram.

13. Reactor pressure is currently being maintained by another operator.

14. Suppression Pool Cooling will be placed in service by another operator.

15. SBGT and REC have been aligned to support HPCI operation.

General

References:

1. Procedure 2.2.33.1, High Pressure Coolant Injection System Operation.

Nebraska Public Power District SKL034-21-48 (7405)

Cooper Nuclear Station Revision 02 Job Performance Measure Page 87 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:206005O0101

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Task

Title:

Manually Initiate HPCI (Hard Card) (Alternate Path)

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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:

2. 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 place HPCI in the injection mode at rated flow using the hard card. Inform the CRS when HPCI is injecting at rated flow.

Nebraska Public Power District SKL034-21-48 (7405)

Cooper Nuclear Station Revision 02 Job Performance Measure Page 88 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:206005O0101

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Task

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Manually Initiate HPCI (Hard Card) (Alternate Path)

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Performance Checklist Standards Initials

24. Place GLAND SEAL CNDSR The operator places the control switch for the BLOWER control switch in GLAND SEAL CNDSR BLOWER in START.

START.

CUE: The red light for the GLAND SEAL CNDSR BLOWER is lit, the green light is out.

25. Checks High Water Level Checks and Resets REACTOR HI WTR Trip LEVEL TRIP SIGNAL.

CUE: REACTOR HI WTR LEVEL TRIP yellow light is OFF.

26. Open HPCI-MO-14, STM TO The operator places the control switch for the TURB VLV. HPCI-MO-14 in OPEN.

CUE: HPCI-MO-14 red light is on, green light is off.

27. Start AUXILIARY OIL PUMP The operator places the control switch for the by placing control switch in Auxiliary Oil Pump switch to START.

START.

CUE: HPCI Aux Oil pump red light is on, green light is off.

28. Open HPCI-MO-19, The operator places the control switch for the INJECTION VALVE. HPCI-MO-19 in OPEN.

CUE: HPCI-MO-19 red light is on, green light is off.

Nebraska Public Power District SKL034-21-48 (7405)

Cooper Nuclear Station Revision 02 Job Performance Measure Page 89 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:206005O0101

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Task

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Manually Initiate HPCI (Hard Card) (Alternate Path)

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Performance Checklist Standards Initials

29. Adjust FLOW Operator attempts to control HPCI flow with CONTROLLER the Set Tape.

HPCI-FIC-108 setpoint to maintain desired HPCI flow, CUE: HPCI flow remains almost zero, as necessary. irrespective of Set Tape setting.

30. Operator recognizes and Operator reports to CRS that HPCI controller reports failed controller has failed in automatic.

CUE: CRS acknowledges, directs operator to continue with HPCI injection

31. Operator places HPCI Operator turns HPCI controller controller in manual. AUTO/BAL/MAN switch to MAN.

CUE: HPCI controller AUTO/BAL/MAN switch is in MAN.

32. Operator adjusts HPCI Operator turns HPCI controller manual knob controller in manual to clockwise to raise flow, counter-clockwise to

control flow.` lower flow until flow is 4250 gpm.

CUE: HPCI flow responds to manual control knob adjustment as appropriate.

33. Operator reports HPCI is in Operator reports HPCI is in injection mode at injection mode at rated flow. rated flow per the hard card.

CUE: CRS acknowledges report.

Nebraska Public Power District SKL034-21-48 (7405)

Cooper Nuclear Station Revision 02 Job Performance Measure Page 90 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:206005O0101

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Task

Title:

Manually Initiate HPCI (Hard Card) (Alternate Path)

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ATTACHMENT 1 SIMULATOR SET-UP A. Materials required None C. Initialize the Simulator in any IC that will support HPCI injection mode after a scram (IC-18, 19 or 20 suggested)

Batch File name - none.

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 RC01 RCIC System Failure to A N/A N/A N/A N/A Auto Start HP01 HPCI System Failure to A N/A N/A N/A N/A Auto Start

3. Remotes Number Title Trigger TD Value Ramp None

Nebraska Public Power District SKL034-21-48 (7405)

Cooper Nuclear Station Revision 02 Job Performance Measure Page 91 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:206005O0101

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Task

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Manually Initiate HPCI (Hard Card) (Alternate Path)

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4. Overrides Instrument Tag Trigger TD Value Ramp HPCI Set Tape ZAIHPCIFIC108[2] A 0 200 0

5. Panel Set-up (suggested. Any setup is allowed that supports performance of the HPCI injection mode)

a. Insert listed overrides and malfunctions.

b. Place the Simulator in RUN.

c. Trip both RFPs.

d. Trip the CRD pump.

e. Reset HPCI high level trip signal (if present).

f. 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 SKL034-21-48(7405)

Cooper Nuclear Station Page 92 of 8 Job Performance Measure for Operations Revision: 02 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to operate HPCI in the injection mode at rated flow using the hard card. 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:

16. The Reactor is shutdown following a scram.

17. Reactor pressure is being maintained by another operator.

18. Suppression Pool Cooling will be placed in service by another operator.

19. SBGT and REC have been aligned to support HPCI operation.

Initiating Cue(s):

The Control Room Supervisor directs you to place HPCI in the injection mode at rated flow using the hard card. Inform the CRS when HPCI is injecting at rated flow.

Nebraska Public Power District SKL034-21-60(8901)

Cooper Nuclear Station Page 93 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 213003P0101

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Task

Title:

Verify a Group 3 Primary Containment Isolation (Alternate 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 Locations: CR / SIM

2. Appropriate Trainee level: RO / SRO / STE

3. Evaluation Method: Perform Simulate

4. Performance Time: 8 minutes

5. NRC K/As 2.1.31 (4.2/3.9) and 223002 A4.01 (3.6/3.5)

Directions to Examiner:

NOTE:THIS IS AN ALTERNATE PATH JPM. THE RWCU-MO-15 and RWCU-MO-18 WILL FAIL TO AUTOMATICALLY CLOSE AND MUST BE MANUALLY CLOSED.

15. This JPM evaluates the trainee=s ability to verify a Group 3 Primary Containment Isolation per the hard card in procedure 2.1.22, Recovering from a Group Isolation.

16. This JPM is an alternate path, it evaluates the trainee=s ability to identify a failure of Group 3 Primary Containment Isolation valves to close and to take action to ensure the Primary Containment Isolation occurs.

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

18. All blanks must be filled out with either initials or an ANP@ for Anot performed@; an explanation may also be written in the space, if desired, by the examiner.

19. IF asked, it is acceptable to use the hard card to perform the isolation verification.

Nebraska Public Power District SKL034-21-60(8901)

Cooper Nuclear Station Page 94 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 213003P0101

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Task

Title:

Verify a Group 3 Primary Containment Isolation (Alternate Path)

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

21. 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 verify a Group 3 Primary Containment Isolation using the hard card. 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:

20. The Reactor is shutdown following a transient and scram.

21. EOP 1A has been entered.

General

References:

1. Procedure 2.1.22, Recovering from a Group Isolation.

General Tools and Equipment:

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

Nebraska Public Power District SKL034-21-60(8901)

Cooper Nuclear Station Page 95 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 213003P0101

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Task

Title:

Verify a Group 3 Primary Containment Isolation (Alternate Path)

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

1. Simulator Setup: See Attachment 1.

2. Critical steps denoted by A*@.

3. Simulator cues denoted by A#@.

Task Standards:

3. 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 verify a Group 3 Primary Containment Isolation. Inform the CRS when you have completed the verification.

Nebraska Public Power District SKL034-21-60(8901)

Cooper Nuclear Station Page 96 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 213003P0101

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Task

Title:

Verify a Group 3 Primary Containment Isolation (Alternate Path)

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Performance Checklist Standards Initials

34. Obtains 2.1.22 Hard Card (or procedure 2.1.22)

Attachment 1 Hard Card obtained (or 2.1.22).

35. Verifies Group 3 Observes the four Group 3 isolation signal is Isolation Indicating lights on present. panel 9-5 are OFF.

CUE: Channel A and B (4) White indicating lights are OFF.

36. Verifies RWCU-MO-15 Operator observes indicating is closed. lights for RWCU-MO-15 on panel 9-3 and determines valve failed to close.

CUE: The green light is OFF and the Red light is ON.

37. Manually closes Operator places the control RWCU-MO-15. switch for RWCU-MO-15 in CLOSE and observes the green light ON and the red light OFF.

CUE: When control switch is

placed to CLOSE then green light is ON and red light is OFF.

38. Verifies RWCU-MO-18 Operator observes indicating is closed. lights for RWCU-MO-18 on panel 9-3 and determines valve failed to close.

Nebraska Public Power District SKL034-21-60(8901)

Cooper Nuclear Station Page 97 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 213003P0101

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Task

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Verify a Group 3 Primary Containment Isolation (Alternate Path)

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Performance Checklist Standards Initials CUE: The green light is OFF and the Red light is ON.

39. Manually closes Operator places the control RWCU-MO-18. switch for RWCU-MO-18 in CLOSE and observes the green light ON and the red light OFF.

CUE: When control switch is placed to CLOSE then green light is ON and red light is OFF.

40. Crack open RWCU-MO- Operator places the control 74, Demin Suction switch for RWCU-MO-74 in OPEN Bypass Valve. position until dual valve position indication is observed.

CUE: Both green light and red light are ON.

41. Informs CRS that the CRS informed that the Group 3 group 3 isolation isolation is verified and that has been verified. RWCU-MO-15 and 18 failed to isolate and were manually closed.

CUE: As the CRS acknowledge the report.

Nebraska Public Power District SKL034-21-60(8901)

Cooper Nuclear Station Page 98 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 213003P0101

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Task

Title:

Verify a Group 3 Primary Containment Isolation (Alternate Path)

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ATTACHMENT 1 SIMULATOR SET-UP A. Materials required None B. Initialize the Simulator in any IC with the reactor at 100%

power.(IC-18, 19 or 20 suggested)

Batch File name - none.

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

1. Triggers Number File Name Description E8 Group 2 isolation zlopcisrelk5ac[1]==0

2. Malfunctions Number Title Trigger TD Severit Ramp Initi y al RP12 Group 3 Isolation A 0 NA NA NA Failure

3. Remotes Number Title Trigger TD Value Ramp None

Nebraska Public Power District SKL034-21-60(8901)

Cooper Nuclear Station Page 99 of 8 Job Performance Measure for Operations Revision: 01 Task No.: 213003P0101

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Task

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Verify a Group 3 Primary Containment Isolation (Alternate Path)

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4. Overrides Instrument Tag Trigge TD Value Ramp r

Group 3 ISOL IND zlopcisrelk26(1) 8 0 OFF 0 LIGHT Group 3 ISOL IND zlopcisrelk26(2) 8 0 OFF 0 LIGHT Group 3 ISOL IND zlopcisrelk27(1) 8 0 OFF 0 LIGHT Group 3 ISOL IND zlopcisrelk27(2) 8 0 OFF 0 LIGHT

5. Panel Set-up (suggested. Any setup that results in a Group 3 isolation signal.)

a. Place the Simulator in RUN.

Insert a scram.

c. Verify a Group 3 isolation signal is present (low reactor water level).

i. 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 SKL034-21-60(8901)

Cooper Nuclear Station Page 100 of 8 Job Performance Measure for Operations Revision: 1 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to Verify a Group 3 Primary Containment Isolation per the hard card. 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:

b. The Reactor is shutdown following a transient and scram.

c. EOP 1A has been entered.

Initiating Cue(s):

The Control Room Supervisor directs you to verify a Group 3 Primary Containment Isolation. Inform the CRS when you have completed the verification.

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 101 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer 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: 20 minutes

5. NRC K/A:262001 A4.04 (3.6/3.7)

Directions to Examiner:

22. This JPM evaluates the trainee's ability to perform transfer of 4160 bus 1G from DG2 to the Emergency Transformer.

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

24. All blanks must be filled out with either initials or an ANP@ for Anot performed@; an explanation may also be written in the space, if desired, by the examiner.

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

26. 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 required actions to transfer 4160V bus 1G from DG2 to the Emergency Transformer. 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.

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 102 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer

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General Conditions:

1. DG2 is supplying 4160 VAC bus 1G.

2. The Emergency Transformer is available.

3. Breaker 1GB has failed.

General

References:

1. Procedure 2.2.18, 4160V Auxiliary Power Distribution System

2. Procedure 2.2.20.1, Diesel Generator Operations General Tools and Equipment:

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

1. Simulator Setup: See Attachment 1.

2. Critical steps denoted by A*@.

3. Simulator cues denoted by A#@.

Task Standards:

22. 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 transfer of 4160V bus 1G from DG2 to the Emergency Transformer. Inform Control Room Supervisor when 4160V bus 1G is being carried by the Emergency Transformer.

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 103 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer Performance Checklist Standards Initials

1. Obtain copy of 2.2.18 and Operator obtains a copy of procedure 2.2.18 2.2.20.1. and 2.2.20.1. _________

2. Ensure risk has been The operator determines that risk need not be assessed, per Procedure assessed as breaker is already open due to a _________

0.49, for placing Breaker failure.

1FS, EMERGENCY XFMR BKR, for Bus 1F in #CUE: IF asked as CRS, inform the PULL-TO-LOCK operator that risk has been evaluated.

3. Ensure the Emergency The operator verifies voltage available from Transformer is energized the Emergency Transformer. _________

CUE: Emergency Transformer secondary voltage is 4440VAC.

4. Inform Shift Manager both Inform Shift Manager to declare both off-site off-site circuits are circuits inoperable and to enter the _________

inoperable. appropriate Condition and Required Action of LCO 3.8.1, AC Sources - Operating.

CUE: SM acknowledges the information.

5. Verify 1GS racked in. Ensure Breaker 1GS, EMERGENCY TRANSFORMER FEED TO 4160V BUS 1G, _________

is racked in.

CUE: 1GS Breaker RED light OFF, GREEN light ON.

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 104 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer Performance Checklist Standards Initials

6. Start signals clear Ensure DG2 auto start signals clear.

CUE: Drywell pressure is .5 pig and steady Reactor water level being controlled 15" to 40".

CUE: 4160V Bus 1F/1G are energized

7. Depress local RESET Direct SO to locally at DG2 Control Panel, button press and release EMERGENCY to NORMAL ________*

RESET button

CUE: Station Operator reports EMERGENCY to NORMAL RESET button has been depressed and released

8. Place into Droop Parallel Direct SO to locally at DG2 Control Panel, to Parallel. ensure DROOP PARALLEL switch is in ________*

PARALLEL.

CUE: Station Operator reports DROOP PARALLEL switch is in PARALLEL.

9. Speed control check Adjust speed of DG2 by placing DIESEL GEN 2 GOVERNOR SWITCH to RAISE or LOWER _________

to verify DG2 frequency control.

CUE: DG2 frequency is 59.6 Hz CUE: DG2 frequency rises to 60.0 Hz

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 105 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer Performance Checklist Standards Initials

10. Voltage control check Adjust voltage of DG2 by placing DIESEL GEN 2 VOLTAGE REGULATOR switch RAISE or LOWER to maintain DG2 voltage at _________

4160 volts.

CUE: DG voltage is 4050 volts.

CUE: DG voltage rises to 4160 volts.

11. Synch switch to 1GS Place SYNCH SWITCH 1GS to 1GS.

CUE: SYNCH SWITCH is in 1GS position ________ *

12. Adjust speed Using DIESEL GEN 2 GOVERNOR switch, adjust engine speed so SYNCHROSCOPE is rotating very slowly in counter-clockwise _________

(slow) direction.

CUE: If the operator indicates that he is placing the governor switch to raise indicate that the SYNCHROSCOPE is speeding up in the clockwise (fast) direction.

CUE: If the operator indicates that he is placing the governor switch to lower indicate that the SYNCHROSCOPE starting to rotate in the counter-clockwise (slow) direction.

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 106 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer Performance Checklist Standards Initials

13. Adjust voltage Using DIESEL GEN 2 VOLTAGE REGULATOR switch, adjust Bus 1G voltage to slightly lower than EMERGENCY XFMR ________

VOLTAGE CUE: (Before adjustment) DG2 Voltage reads 4160 volts.

CUE: XFMR Transformer voltage is 4449 volts.

CUE: (after adjustment) DG2 voltage reads 4430 volts.

14. Close 1GS When SYNCHROSCOPE is at 1 o=clock, the operator closes Breaker 1GS and check switch spring returns to NORMAL AFTER ________*

CLOSE (red flagged)

CUE: Switch returns to center position (red flagged). 1GS Breaker , GREEN light is OFF, RED light is ON.

15. Adjust kVARS The Operator adjust DG2 kVARS so that they are slightly positive (~200 kVARS) using DIESEL GEN 2 VOLTAGE REGULATOR _________

switch. (100 - 300 KVARs)

CUE: DG2 kVARS reads 40 kVARS CUE: DG2 kVARS reads 200 kVARS

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 107 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer Performance Checklist Standards Initials

16. Bkr 1FS Pull-To-Lock. Verify switch for 1FS in PULL-TO-LOCK (PTL)

CUE: 1FS Breaker is still tagged _________

17. Lower DG2 Load Reduce load on DG2 to 1000 KW using DIESEL GEN 2 GOVERNOR switch. _________

CUE: DG2 load is 2200 KW CUE: DG2 load is 1000 KW

18. Place SYNCH SWITCH to Place SYNCH SWITCH 1GS to OFF OFF _________

CUE: SYNCH SWITCH is in OFF

19. DG2 Cooldown After engine has cooled and cylinder exhaust temperature have dropped (~5 minutes),

remove DG2 from services per 2.2.20.1. _________

CUE: Five minutes have elapsed.

CUE: Station Operator reports engine temperatures are cooling down.

20. Lower DG2 load Lower DG2 load to 400 kW and 1000 kW (2.2.20.1) _________

CUE: DG2 load is 600 kW

CUE: 15 minutes have elapsed.

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 108 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer Performance Checklist Standards Initials

21. Lower to 400 KW Lower DG2 load to 400 KW CUE: DG2 load is 400 kW

22. Lower kVARs Reduce DG2 kVARs as low as possible.

CUE: DG2 kVARs is 50 KVA

23. Open EG2 Open DIESEL GEN 2 BKR EG2 CUE: BKR EG2 is NORMAL AFTER TRIP (green flagged). Green light is ON. Red light is OFF.

24. Inform CRS Inform CRS that the Emergency Transformer is carrying 4160 V Bus 1G.

CUE: CRS acknowledges. This JPM is complete. (Stop JPM at this point even if candidate continues.)

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 109 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer ATTACHMENT 1 SIMULATOR SET-UP A. Materials required None B. Initialize the Simulator in any at power IC (IC-18, 19 or 20 suggested)

Batch File name - none.

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

3. Remotes Number Title Trigger TD Value Ramp None

4. Overrides Instrument Tag Trigger TD Value Ramp None

Nebraska Public Power District SKL034-21-31 (2641)

Cooper Nuclear Station Page 110 of 149 Job Performance Measure for Operations Revision 05 Task Number: 245056G0101 Transfer of 4160V Bus 1G from DG2 to Emergency Transformer

5. Panel Set-up (suggested. Any setup is allowed that supports performance of the bus transfer)

a. Place Bkr 1FS & 1GB in PTL and place Danger Tag on C/S

b. Place 2nd SW pump B in service

c. Place B RHR loop in Suppression Pool Cooling using Div 2 power sources

d. Place Bkr 1GS to NORMAL AFTER TRIP

e. At DG2 local panel, depress & release EMERGENCY to NORMAL RESET pushbutton.

f. At DG2 local panel, place DROOP PARALLEL switch in PARALLEL.

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 SKL034-21-31 (2641)

Cooper Nuclear Station Page 111 of 12 Job Performance Measure for Operations Revision 05 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to perform the required actions to transfer 4160V bus 1G from DG2 to the Emergency Transformer. 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. DG2 is supplying 4160 VAC bus 1G.

2. The Emergency Transformer is available.

3. Breaker 1GB has failed.

Initiating Cues:

The Control Room Supervisor directs you to perform transfer of 4160V bus 1G from DG2 to the Emergency Transformer. Inform Control Room Supervisor when 4160V bus 1G is being carried by the Emergency Transformer.

Nebraska Public Power District SKL034-30-51 (16531)

Cooper Nuclear Station Page 112 of 5 Job Performance Measure for Operations Revision 01 Task Number: 200363G0501 Install EOP PTMs 57, 58, 59 and 60 Trainee: Examiner:

Pass: Fail: Examiner Signature: Date:

Additional Program Information:

1) Appropriate Performance Locations: Simulator

2) Appropriate Trainee Level: SO / RO / SRO

3. Evaluation Method: Simulate Perform

4. Performance Time: 10 minutes

5. NRC K/A 295037 EA1.11 (3.5/3.6),

Directions to Examiner:

1. This JPM evaluates the trainee's ability to Install the EOP PTMs that bypass the low level group 1 isolation during an ATWAS.

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 install EOP PTMs 57, 58, 59 and 60 to bypass the low level group 1 isolation. 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 SKL034-30-51 (16531)

Cooper Nuclear Station Page 113 of 5 Job Performance Measure for Operations Revision 01 Task Number: 200363G0501 Install EOP PTMs 57, 58, 59 and 60 General Conditions:

23. An ATWAS has occurred.

2. The MSIVs are open.

General

References:

1. EMERGENCY OPERATING PROCEDURE 5.8.20.

General Tools and Equipment:

1. Safety Glasses

2. Electrical Safety Equipment Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*.

Task Standards:

4. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

The CRS directs you to bypass the low level MSIV isolation per 5.8.20 and to inform him when it is complete.

Nebraska Public Power District SKL034-30-51 (16531)

Cooper Nuclear Station Page 114 of 5 Job Performance Measure for Operations Revision 01 Task Number: 200363G0501 Install EOP PTMs 57, 58, 59 and 60 Performance Checklist Standards Initials

3. Obtain a copy of EOP 5.8.20. Current revision of EOP 5.8.20 is obtained.

4. Verifies the MSIVs are MSIV position is verified.

OPEN.

CUE: All MSIV red position indicating lights are lit and the green lights are extinguished.

5. Ensure following RR sample Ensure following valves closed (PNL 9-4) :

valves CLOSED. RR-AO-740, OUTBD ISOL VLV and RR-AO-741, IND ISOL VLV .

CUE:RR-AO-740, OUTBD ISOL VLV and RR-AO-741, IND ISOL VLV GREEN lights ON RED lights OFF.

Caution: If the student fails to put on safety glasses prior to installing the PTMs the JPM cannot proceed. If the JPM is being used for evaluation purposes the JPM is concluded at that point and marked unsat.

6. Puts on required safety As a minimum safety glass are worn during equipment. the performance of this task. *

7. Install EOP PTM Number 57 EOP PTM Number 57 installed.

by jumpering between

Terminals DD1 and DD2 CUE: Jumper is installed.

(BAY-1, PNL 9-15).

8. Install EOP PTM Number 58 EOP PTM Number 58 installed.

by jumpering between

Terminals BB1 and BB2 CUE: Jumper is installed.

(BAY-3, PNL 9-15).

9. Install EOP PTM Number 59 EOP PTM Number 59 installed.

by jumpering between

Terminals DD1 and DD2 CUE: Jumper is installed.

(BAY-1, PNL 9-17).

10. Install EOP PTM Number 60 EOP PTM Number 60 installed.

by jumpering between Terminals BB1 and BB2 CUE: Jumper is installed. *

(BAY-3, PNL 9-17).

Nebraska Public Power District SKL034-30-51 (16531)

Cooper Nuclear Station Page 115 of 5 Job Performance Measure for Operations Revision 01 Task Number: 200363G0501 Install EOP PTMs 57, 58, 59 and 60 Performance Checklist Standards Initials

11. Informs the CRS that the low CRS is informed.

level MSIV isolation is bypassed per 5.8.20. CUE: As the Control Room Supervisor acknowledge the report.

Nebraska Public Power District SKL034-30-51(16531)

Cooper Nuclear Station Page 116 of 4 Job Performance Measure for Operations Revision 01 ATTACHMENT 1 When I tell you to begin, you are to install EOP PTMs 57, 58, 59 and 60 to bypass the low level group 1 isolation. 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. An ATWAS has occurred.

2. The MSIVs are open.

Initiating Cues:

The CRS directs you to bypass the low level MSIV isolation per 5.8.20 and to inform him when it is complete.

Nebraska Public Power District SKL034-22-02 (36407)

Cooper Nuclear Station Revision 00 Job Performance Measure Page 117 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:208018C0101

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=

Task

Title:

Align REC after REC isolation on Low Pressure

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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: 10 minutes

5. NRC K/A 295018; AA1.03 (3.3/3.4)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to Restore REC after REC isolation on Low Pressure.

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.

Directions to Trainee:

When I tell you to begin, you are to restore REC flow for Drywell Cooling after REC isolation on Low Pressure, per the Hardcard.

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 restore REC flow for Drywell Cooling after REC isolation on Low Pressure.

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

=

General Conditions:

1. The Reactor was scrammed due to loss of REC per 5.2REC.

2. REC Isolation was due to REC Augmented Radwaste Supply pipe break down stream of REC-MO-1329, AUGMENTED RADWASTE SUPPLY

3. The REC pipe break has been isolated.

Nebraska Public Power District SKL034-22-02 (36407)

Cooper Nuclear Station Revision 00 Job Performance Measure Page 118 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:208018C0101

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=

Task

Title:

Align REC after REC isolation on Low Pressure

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

=

Nebraska Public Power District SKL034-22-02 (36407)

Cooper Nuclear Station Revision 00 Job Performance Measure Page 119 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:208018C0101

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=

Task

Title:

Align REC after REC isolation on Low Pressure

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=

General

References:

SOP 2.2.65.1 General Tools and Equipment:

None 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:

5. 100% of critical elements successfully completed without error.

2. 100% of safety and radiological work practices.

Initiating Cue(s):

You are the Balance of Plant Operator. The CRS has directed you restore REC after REC isolation on Low Pressure Inform the CRS when REC is restored for Drywell Cooling NOTE: Tell Trainee to begin. Place Simulator in RUN

Nebraska Public Power District SKL034-22-02 (36407)

Cooper Nuclear Station Revision 00 Job Performance Measure Page 120 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:208018C0101

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Task

Title:

Align REC after REC isolation on Low Pressure

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

=

Performance Standards Initials Checklist

1. Obtain copy of The operator obtains a copy of SOP 2.2.65.1 or SOP 2.2.65.1 Hard Card. _______

CUE: None.

2. Determine Ensure low pressure isolation not due to leakage cause of REC or leak isolated. _______*

isolation CUE: REC piping break has been repaired.

3. Verify two REC Ensure two REC pumps are running.

pumps in Operation CUE: REC Pumps B and D are in service. ________*

4. Verify REC Ensure one of following valves are OPEN:

critical loop REC-MO-711, NORTH CRITICAL LOOP _______*

supplied. SUPPLY.

Or REC-MO-714, SOUTH CRITICAL LOOP SUPPLY.

CUE: REC-MO-711, NORTH CRITICAL LOOP SUPPLY and REC-MO-714, SOUTH CRITICAL LOOP SUPPLY are OPEN

Nebraska Public Power District SKL034-22-02 (36407)

Cooper Nuclear Station Revision 00 Job Performance Measure Page 121 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:208018C0101

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=

Task

Title:

Align REC after REC isolation on Low Pressure

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

=

Performance Standards Initials Checklist

5. Checking If drywell temperature 260°F on PC-TI-505A Drywell through PC-TI-505E, place DRYWELL REC ISOL Temperature VALVE CONTROL switch to OPEN.

CUE: PC-TI-505A through PC-TI-505E reading 253°F.

6. Throttle open Throttle open REC HX outlet valve for a HX that REC HX outlet was in service, as necessary, while maintaining _______

valve REC CRIT LOOP SUPPLY PRESS in green band.

REC-MO-712, HX A OUTLET VLV.

REC-MO-713, HX B OUTLET VLV.

CUE: REC-MO-712, HX A OUTLET VLV is open.

7. Start third REC Start third REC pump. _______*

pump CUE: REC Pump C is in service

8. Throttle open Throttle open REC HX outlet valve, as necessary, _______*

REC HX outlet to obtain following conditions:

valve REC CRIT LOOP SUPPLY PRESS 62 psig.

REC HEADER PRESSURE in top of green band.

CUE: REC-MO-712, HX A OUTLET VLV is open.

Nebraska Public Power District SKL034-22-02 (36407)

Cooper Nuclear Station Revision 00 Job Performance Measure Page 122 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:208018C0101

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=

Task

Title:

Align REC after REC isolation on Low Pressure

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

=

Performance Standards Initials Checklist

9. Open REC- Perform following simultaneously: _______*

MO-700, NON- Open REC-MO-700, NON-CRITICAL HEADER CRITICAL SUPPLY.

HEADER Continue throttling open REC HX outlet valve, as SUPPLY. necessary, to maintain REC HEADER PRESSURE in green band.

CUE: REC-MO-700, NON-CRITICAL HEADER SUPPLY is open.

10. Ensure REC Ensure REC HX outlet valve full open. _______*

HX outlet valve full open CUE: REC-MO-712, HX A OUTLET VLV is open.

11. Open REC- If REC-AO-710, RWCU NON-REGEN HX INLET, _______*

AO-710, not closed for leak isolation, open REC-AO-710.

RWCU NON-REGEN HX CUE: REC-MO-712, HX A OUTLET VLV is INLET open.

12. Verify REC- If REC-MO-1329, AUGMENTED RADWASTE _______*

MO-1329, SUPPLY, not closed for leak isolation and cooling AUGMENTED desired, open REC-MO-1329.

RADWASTE SUPPLY is CUE: REC-MO-1329, AUGMENTED closed. RADWASTE SUPPLY, is closed.

13. DRYWELL Place DRYWELL REC ISOL VALVE CONTROL _______*

REC ISOL switch to AUTO.

VALVE CONTROL CUE: REC-MO-712, HX A OUTLET VLV is switch to open.

AUTO

Nebraska Public Power District SKL034-22-02 (36407)

Cooper Nuclear Station Revision 00 Job Performance Measure Page 123 of 149 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.:208018C0101

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Task

Title:

Align REC after REC isolation on Low Pressure

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Performance Standards Initials Checklist Notify CRS that REC is restored for Drywell

14. Notify CRS. Cooling

CUE: Respond as the CRS and acknowledge the report.

SKL034-22-02 (36407)

Page 124 of 149 Revision 00 ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required SOP 2.2.65.1 B. Initialize the Simulator in IC-20 or any IC that will support REC isolation.

C. Change the simulator conditions as follows:

1. Perform Mitigating Scram Actions.

2. Close the in service heat exchanger outlet valve until the REC system isolates on low pressure. Close REC-MO-1329, AUGMENTED RADWASTE SUPPLY

3. Place simulator in freeze.

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

SKL034-22-02 (36407)

Page 125 of 149 Revision 00 ATTACHMENT 2 Directions to Trainee:

When I tell you to begin, you are to restore REC flow for Drywell Cooling after REC isolation on Low Pressure, per the Hardcard.

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 restore REC flow for Drywell Cooling after REC isolation on Low Pressure.

General Conditions:

1. The Reactor was scrammed due to loss of REC per 5.2REC.

2. REC Isolation was due to REC Augmented Radwaste Supply pipe break down stream of REC-MO-1329, AUGMENTED RADWASTE SUPPLY

3. The REC pipe break has been isolated.

Initiating Cues:

You are the Balance of Plant Operator. The CRS has directed you restore REC after REC isolation on Low Pressure Inform the CRS when REC is restored for Drywell Cooling.

Nebraska Public Power District SKL034-22-01(36406)

Cooper Nuclear Station Page 126 of 12 Job Performance Measure for Operations Revision 00 Task No.: 261003O0101 Task

Title:

SGT SYSTEM SUPPORT FOR HPCI OPERATIONS (Alternate Path)

Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Time Started: ____________ Time Finished: _____________

THIS IS AN ALTERNATE PATH JPM Additional Program Information:

1. Appropriate Performance Locations: CR / SIM

2. Appropriate Trainee level: RO / SRO

3. Evaluation Method: Simulate Perform

4. Performance Time: 15 minutes

5. NRC K/A 261000 A4.03 (3.0/3.0)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to manipulate the SGT controls in order to start SGT in support of HPCI operation.

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.

Directions to Trainee:

When I tell you to begin, you are to start the SGT system to support HPCI operation. 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.

Nebraska Public Power District SKL034-22-01(36406)

Cooper Nuclear Station Page 127 of 12 Job Performance Measure for Operations Revision 00 Task No.: 261003O0101 Task

Title:

SGT SYSTEM SUPPORT FOR HPCI OPERATIONS (Alternate Path)

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 Standby Gas Treatment System is required to support HPCI operation.

General

References:

1. Procedure 2.2.73.

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 start SGT to support HPCI operation. Inform the CRS when SGT is running to support HPCI.

Nebraska Public Power District SKL034-22-01(36406)

Cooper Nuclear Station Page 128 of 12 Job Performance Measure for Operations Revision 00 Task No.: 261003O0101 Task

Title:

SGT SYSTEM SUPPORT FOR HPCI OPERATIONS (Alternate Path)

Performance Checklist Standards Initials

1. Obtains the current revision of Procedure Current revision of 2.2.73 is obtained. _______

2.2.73.

2. Determine the SGT train 1A is determined to be the preferred train. _______

preferred SGT train.

EF-R-1E, SGT A EXHAUST FAN switch is placed to RUN.

3. Start EF-R-1E, SGT A EXHAUST FAN.

CUE: SGT Fan Red running light is ON and the Green light is OFF Position of SGT-AO-249, SGT A INLET and SGT-AO-251, SGT A DISCHARGE are checked.

4. Verifies the inlet and CUE: SGT-AO-249, SGT A INLET RED light is On discharge valves _______

and the GREEN light is OFF.

OPEN.

SGT-AO-251, SGT A DISCHARGE red light is ON and the GREEN light is OFF.

SGT-DPIC-546 is verified in Manual.

5. Verifies SGT-DPIC-546 is in Manual.

CUE: SGT-DPIC-546 is in Manual.

D pushbutton is depressed until parameter V is

6. Toggles SGT-DPIC-displayed.

546 until Parameter V _______*

is displayed.

CUE: Parameter V is displayed.

Nebraska Public Power District SKL034-22-01(36406)

Cooper Nuclear Station Page 129 of 12 Job Performance Measure for Operations Revision 00 Task No.: 261003O0101 Task

Title:

SGT SYSTEM SUPPORT FOR HPCI OPERATIONS (Alternate Path)

Performance Checklist Standards Initials SGT-DPIC-546 is adjusted to obtain 800 scfm on

7. Adjusts SGT-DPIC-SGT-FI-545, SGT DISCHARGE HEADER FLOW.

546 to ensure 800 _______*

CFM CUE: SGT-FI-545 indicates 900 CFM.

Checks that Annunciator K-1/A-2 SGT A HI Moisture.

8. Checks High Moisture is clear.

CUE: Annunciator is in alarm.

Checks Annunciator K-1/A-2 SGT A HI Moisture and informs CRS of Alarm

9. Checks Annunciator K-1/A-2 SGT A HI #CUE: CRS acknowledges the report and directs A _______

Moisture SBGT be secured and B SBGT train started to support HPCI operation, alarm card actions will not be performed due to not emergency condition.

Ensure Reactor Building H&V System running and

10. Determines Reactor maintaining Reactor Building pressure at -0.25" wg.

Building HV System _______

Operation CUE: Reactor Building pressure at -0.3" wg..

SGT-DPIC-546 is verified in Manual.

11. Verifies SGT-DPIC-546 is in Manual.

CUE: SGT-DPIC-546 is in Manual.

Nebraska Public Power District SKL034-22-01(36406)

Cooper Nuclear Station Page 130 of 12 Job Performance Measure for Operations Revision 00 Task No.: 261003O0101 Task

Title:

SGT SYSTEM SUPPORT FOR HPCI OPERATIONS (Alternate Path)

Performance Checklist Standards Initials D pushbutton is depressed until parameter V is

12. Toggles SGT-DPIC-displayed.

546 until Parameter V _______

is displayed.

CUE: Parameter V is displayed.

SGT-DPIC-546 is adjusted to obtain ~ 100 scfm on

13. Adjusts SGT-DPIC-SGT-FI-545, SGT DISCHARGE HEADER FLOW.

546 to ensure ~ 100 _______*

CFM CUE: SGT-FI-545 indicates 100 CFM.

Verifies SGT heaters are off.

14. Check SGT heaters _______

CUE: SGT heaters GREEN lights ON, RED light OFF EF-R-1E, SGT A EXHAUST FAN switch is placed to AUTO.

15. Stop EF-R-1E, SGT A EXHAUST FAN.

CUE: SGT Fan Red running light is OFF and the Green light is ON Position of SGT-AO-249, SGT A INLET and SGT-AO-251, SGT A DISCHARGE are checked.

16. Verifies the inlet and CUE: SGT-AO-249, SGT A INLET RED light is OFF discharge valves and the GREEN light is ON. _______

CLOSED.

SGT-AO-251, SGT A DISCHARGE red light is OFF and the GREEN light is ON.

Nebraska Public Power District SKL034-22-01(36406)

Cooper Nuclear Station Page 131 of 12 Job Performance Measure for Operations Revision 00 Task No.: 261003O0101 Task

Title:

SGT SYSTEM SUPPORT FOR HPCI OPERATIONS (Alternate Path)

Performance Checklist Standards Initials Ensure SGT-AO-271, SGT B DILUTION AIR, in AUTO and valve closed.

17. Verifies SGT-AO-271, SGT B DILUTION CUE: SGT-AO-271, SGT B DILUTION AIR, in AUTO _______

AIR, in AUTO and valve RED light is OFF and the GREEN light is ON.

EF-R-1F, SGT B EXHAUST FAN switch is placed to RUN.

18. Start EF-R-1F, SGT B EXHAUST FAN.

CUE: SGT Fan Red running light is ON and the Green light is OFF Position of SGT-AO-250, SGT B INLET and SGT-AO-252, SGT B DISCHARGE are checked.

19. Verifies the inlet and CUE: SGT-AO-250, SGT A INLET RED light is On discharge valves _______

and the GREEN light is OFF.

OPEN.

SGT-AO-252, SGT A DISCHARGE red light is ON and the GREEN light is OFF.

SGT-DPIC-546 is verified in Manual.

20. Verifies SGT-DPIC-546 is in Manual.

CUE: SGT-DPIC-546 is in Manual.

D pushbutton is depressed until parameter V is

21. Toggles SGT-DPIC-displayed.

546 until Parameter V _______*

is displayed.

CUE: Parameter V is displayed.

Nebraska Public Power District SKL034-22-01(36406)

Cooper Nuclear Station Page 132 of 12 Job Performance Measure for Operations Revision 00 Task No.: 261003O0101 Task

Title:

SGT SYSTEM SUPPORT FOR HPCI OPERATIONS (Alternate Path)

Performance Checklist Standards Initials SGT-DPIC-546 is adjusted to obtain 800 scfm on

22. Adjusts SGT-DPIC-SGT-FI-545, SGT DISCHARGE HEADER FLOW.

546 to ensure 800 _______*

CFM CUE: SGT-FI-545 indicates 900 CFM.

Ensures that Annunciator K-2/A-2 SGT B HI

23. Ensures High Moisture is clear.

Moisture is clear.

CUE: Annunciator is clear.

CRS is informed.

24. Informs CRS that the task is complete. #CUE: Acknowledge the report and inform the candidate that the JPM is complete.

Nebraska Public Power District SKL034-22-01(36406)

Cooper Nuclear Station Page 133 of 12 Job Performance Measure for Operations Revision 00 Task No.: 261003O0101 Task

Title:

SGT SYSTEM SUPPORT FOR HPCI OPERATIONS (Alternate Path)

ATTACHMENT 1 SIMULATOR SET-UP A. Materials Required None B. Initialize the Simulator to a full power IC.

Batch File Name - none.

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

1. Triggers Number Description 1 ZAOSGTFI545 >0.13 Ramps moisture reading when SBGT flow greater than 500 cfm

2. Malfunctions Number Title Trigger TD Severity Ramp Initial none

3. Remotes Number Title Trigger Value Ramp None

4. Overrides Instrument Tag Trigger TD Value Ramp 18A2M04 0 TO 100% SGT A 1 30 sec 53.3358 30 sec CARBON FILTER INLET RH 18A2M05 0 TO 100% SGT A HI- 1 30 sec 53.3358 30 sec EFF FILTER RH INDICATOR

Nebraska Public Power District SKL034-22-01(36406)

Cooper Nuclear Station Page 134 of 12 Job Performance Measure for Operations Revision 00 Task No.: 261003O0101 Task

Title:

SGT SYSTEM SUPPORT FOR HPCI OPERATIONS (Alternate Path)

Instrument Tag Trigger TD Value Ramp K-1 A-02 SGT A MOISTURE HIGH 1 58 sec OFF

5. Panel Setup

a. Ensure that SGT train 1A is the preferred SGT train.

Setup for the Exam:

a) Initialize the simulator in any power IC.

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 SKL034-22-01 (36406)

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 start the SGT system to support HCI operation.

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 Standby Gas Treatment System is required to support HPCI operation.

Initiating Cues:

The Control Room Supervisor directs you to start SGT to support HPCI operation. Inform the CRS when SGT is running to support HPCI.

Nebraska Public Power District SKL034-10-95 Cooper Nuclear Station Course Type 7456 Job Performance Measure for Operations Revision 03 Task No.: 200134I0504

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

Task

Title:

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

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

=

Trainee: Examiner:

Pass Fail Examiner Date:

Signature:

THIS IS AN ALTERNATE PATH JPM Additional Program Information:

27. Appropriate Performance Locations: Plant

28. Appropriate Trainee Level: SO / RO / SRO

29. Evaluation Method: Simulate

30. Performance Time: 25 minutes

31. 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.

24. 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 ANP@ for Anot 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.

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Task

Title:

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

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

=

Directions to Trainee:

When I tell you to begin you are to perform the assigned Control Building Operator=s 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 4.3.11 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:

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Nebraska Public Power District SKL034-10-95 Cooper Nuclear Station Course Type 7456 Job Performance Measure for Operations Revision 03 Task No.: 200134I0504

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Task

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

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=

2. 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 Operator=s actions for restoring power from the Alternate Supply (MCC-R). Notify the CRS when the NBPP is energized.

138 of 149

Nebraska Public Power District SKL034-10-95 Cooper Nuclear Station Course Type 7456 Job Performance Measure for Operations Revision 03 Task No.: 200134I0504

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Task

Title:

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

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

=

Performance Standard Initials Checklist

3. Obtain a copy of Obtain a copy of 5.3NBPP, NO BREAK 5.3NBPP POWER FAILURE _________

d. Ensure MCC-R FEED Ensure EE-DSC-NBPP(AC), MCC-R FEED TO NBPP is in ON. TO NBPP TRANSFMR (Cable Spreading _________

near NBPP), is in ON. _*

CUE: Indicate the handle is in the UP position.

e. Contact the Rx Contacts the Reactor Building Building Operator to ensure that MCC-R, _________

Operator. 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.

f. Open breaker At Inverter A, open INVERTER OUTPUT breaker. _________

CUE: Indicate the handle is in the DOWN position.

1. Ensure breaker is At Inverter A, ensure SUPPLY TO closed. NBPP breaker is closed. _________

CUE: Indicate the handle is in the UP position.

139 of 149

Nebraska Public Power District SKL034-10-95 Cooper Nuclear Station Course Type 7456 Job Performance Measure for Operations Revision 03 Task No.: 200134I0504

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Task

Title:

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

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

=

Performance Standard Initials Checklist

2. Ensure breaker is At Inverter A, ensure ALTERNATE AC closed. INPUT TO STATIC SWITCH breaker is closed. _________

CUE: Indicate the handle is in the UP position.

3. Depress button. At Inverter A, depress ALTERNATE SOURCE SUPPLYING LOAD button. _________

CUE: The red ALT SOURCE SUPPLYING LOAD light is off. (NBPP is still de-energized)

g. Place MAN BP SW Place MANUAL BYPASS SWITCH to to ALT SOURCE TO ALTERNATE SOURCE TO LOAD. _________

LOAD. _*

CUE: Point to ALTERNATE SOURCE TO LOAD position.

h. Depress ALT Depress ALTERNATE SOURCE SUPPLYING SOURCE SUPPLYING LOAD button. _________

LOAD button. _*

CUE: The red ALT SOURCE SUPPLYING LOAD light is on. (NBPP is energized)

NOTE: The Gaitronics do not need to be transferred

i. Notifies CRS. Notifies CRS that NBPP is 140 of 149

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Task

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

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=

Performance Standard Initials Checklist energized. _________

CUE: As the CRS respond to the report.

141 of 149

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

Cooper Nuclear Station Page 142 of 6 Job Performance Measure for Operations Revision 03 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin you are to perform the assigned Control Building Operator=s 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 4.3.11 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 Operator=s actions for restoring power from the Alternate Supply (MCC-R). Notify the CRS when the NBPP is energized.

142 of 149

Nebraska Public Power District SKL034-40-84 (18851)

Cooper Nuclear Station Page 143 of 149 Job Performance Measure for Operations Revision 03 Task Number: 200390A0501 5.3ALT-STRATEGY, Inject Fire Protection Water to RHR Trainee: Examiner:

Pass Fail Examiner Signature: Date:

Additional Program Information:

1. Appropriate Performance Locations: In Plant

2. Appropriate Trainee Levels: RO / SRO

3. Evaluation Method: Simulate

4. Performance Time: 15 minutes

5. NRC K/A 295003.AA1.03 (4.4 / 4.4)

Directions to Examiner:

1. This JPM evaluates the trainee's ability to inject fire protection water into the RHR System during a complete loss of AC and DC power.

2. If this JPM is to be 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, and 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 perform the actions to align Fire Protection to RHR Subsystem A, using SWBP A in accordance with Procedure 5.3ALT-STRATEGY. 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.

During task performance, state the actions you are taking, e.g.: repositioning controls and observing instrumentation. ALL PLANT ANNOUNCEMENTS WILL BE SIMULATED!

Nebraska Public Power District SKL034-40-84 (18851)

Cooper Nuclear Station Page 144 of 149 Job Performance Measure for Operations Revision 03 Task Number: 200390A0501 5.3ALT-STRATEGY, Inject Fire Protection Water to RHR General Conditions:

1. The Plant has experience a total loss of A/C and D/C power.

2. Reactor Pressure is 600 psig.

3. Procedure 5.3ALT-STRATEGY, Alternate Core Cooling Mitigating Strategies, has been entered.

4. Another SO has completed the breaker alignments per step 1.1 Attachment 1 of 5.3ALT-STRATEGY.

5. Fire Protection header is intact.

General

References:

1. Procedure 5.3ALT-STRATEGY General Tools and Equipment:

1. 3 Fire Hose

2. Fire hose Wrench 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):

The CRS has directed you to align Fire Protection Water to RHR Subsystem A using SWBP A in accordance with 5.3ALT-STRATEGY, Attachment 1. You are to inform the CRS when Fire Protection Water is aligned to RHR.

Nebraska Public Power District SKL034-40-84 (18851)

Cooper Nuclear Station Page 145 of 149 Job Performance Measure for Operations Revision 03 Task Number: 200390A0501 5.3ALT-STRATEGY, Inject Fire Protection Water to RHR Performance Checklist Standards Initials The Operator obtains a copy of the current

32. Obtain procedure revision of procedure 5.3ALT-STRATEGY _______

NOTE - Equipment is stored C-882-N by MCC-T.

NOTE - The Operator must show that they are capable of obtaining the required equipment, but does not have to take them to the specified locations, to get credit for the task element.

The Operator obtains the 3 hose.

25. C-882 N, gets hose.

CUE: Hose is obtained.

3. Remove existing 21/2 The Operator removes the 21/2 hose hose at Hose Station No.

16 CUE: The hose is removed.

The Operator attaches the 3 hose to FP-315,

j. 4. C-882 N, attaches Hose Station No. 16.

hose.

CUE: The hose is attached.

The Operator removes the pipe cap from SW-641, GW System Supply from SWB Pump A. (Outlet

k. 5. C-882 N, removes of SWBP A Pump Inlet Strainer)

pipe cap.

CUE: The pipe cap is removed.

The Operator attaches the 3 hose to SW-641 connection.

l. 6. C-882 N, attaches

hose.

CUE: The hose is attached.

Nebraska Public Power District SKL034-40-84 (18851)

Cooper Nuclear Station Page 146 of 149 Job Performance Measure for Operations Revision 03 Task Number: 200390A0501 5.3ALT-STRATEGY, Inject Fire Protection Water to RHR Performance Checklist Standards Initials The Operator ensures that the SW-77, SWBP A

m. 7. C-882 N, ensures Suction valve is closed.

SW-84 is CLOSED. CUE: The hand wheel has stopped moving in the _______

clockwise direction.

The Operator ensures that the SW-121, Emergency Core Flooding Tell-Tale Drain valve is CLOSED. (SW-121 is in a contaminated area.

He can call for RP support or obtain PCs, or since

n. 8. C-882 N, ensures the this is an Emergency Procedure, he can complete SW-121 is CLOSED.

the task and then ask for RP support.) _______

CUE: The hand wheel has stopped moving in the clockwise direction.

The Operator ensures that the SW-119 Emergency Core Flooding Supply Root valve is

o. 9. C-882 N, ensures OPEN.

valve is OPEN.

CUE: The hand wheel has stopped moving in the counter-clockwise direction.

The Operator ensures that the SW-120, Emergency Core Flooding Supply Shutoff valve is

p. 10. C-882 N, ensures OPEN.

valve is OPEN.

CUE: The hand wheel has stopped moving in the counter-clockwise direction.

The Operator ensures that the SW-641, GW System Supply from SWBP A is OPEN.

q. 11. C-882 N, ensures valve is OPEN. CUE: The valve Operator has been turned Counter Clockwise now is pointing straight up.

Nebraska Public Power District SKL034-40-84 (18851)

Cooper Nuclear Station Page 147 of 149 Job Performance Measure for Operations Revision 03 Task Number: 200390A0501 5.3ALT-STRATEGY, Inject Fire Protection Water to RHR Performance Checklist Standards Initials The Operator slowly opens FP-315.

r. 12. Slowly opens FP-CUE: The hand wheel has stopped moving in the 315.

counter-clockwise direction and the hose is _______*

charged.

The operator informs the CRS that Fire Water is aligned to the RHR System via SWBP A.

s. 13. Notifies CRS that task is completed.

CUE: The CRS acknowledges the report.

Nebraska Public Power District SKL034-40-84 (18851)

Cooper Nuclear Station Page 148 of 149 Job Performance Measure for Operations Revision 03 Task Number: None ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to perform the actions to align Fire Protection to RHR Subsystem A, using SWBP A in accordance with Procedure 5.3ALT-STRATEGY. 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. ALL PLANT ANNOUNCEMENTS WILL BE SIMULATED!

General Conditions:

1. The Plant has experience a total loss of A/C and D/C power.

2. Reactor Pressure is 600 psig.

3. Procedure 5.3ALT-STRATEGY, Alternate Core Cooling Mitigating Strategies, has been entered

4. Another SO has completed the breaker alignments per step 1.1 Attachment 1 of 5.3ALT-STRATEGY.

5. Fire Protection header is intact.

Initiating Cues:

The CRS has directed you to align Fire Protection Water to RHR Subsystem A using SWBP A in accordance with 5.3ALT-STRATEGY, Attachment 1. You are to inform the CRS when Fire Protection Water is aligned to RHR.

Nebraska Public Power District SKL034-40-84 (18851)

Cooper Nuclear Station Page 149 of 149 Job Performance Measure for Operations Revision 03 Task Number: None

ML100880141

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