ML023510106

Init Exam - August 2002 - Draft Operating Exam

ML023510106
Person / Time
Site:	Cooper
Issue date:	02/25/2002
From:	Gody A Division of Reactor Safety IV
To:	Denise Wilson Nebraska Public Power District (NPPD)
References
50-298/02-301 50-298/02-301
Download: ML023510106 (194)

Text

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Task

Title:

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Directions to Examiner:

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DEMAND A PMIS POINT REVIEW Directions to Trainee:

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General Conditions:

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General

References:

 

General Tools and Equipment:

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ATTACHMENT 1 Directions to Trainee:

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General Conditions:

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Initiating Cues:

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Directions to Trainee:

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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level RO Administrative Topic A.3 Subject

Description:

Radiation Protection Question Number: 1 Question:

You have an accumulated TEDE of 0.5 Rem for the year. Because of dose projections for work in the outage, you are expected to receive an additional TEDE of 0.8 Rem.

What authorization is required for you to receive the expected dose?

Answer:

Individuals Supervisor (SS), and ALARA Supervisor.

Justification:

The total expected dose is 1300 mrem. Approvals for dose above 1000 mrem are required by the ALARA Supervisor.

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Description:

Radiation Protection Question Number: 2 Question:

The scram discharge volume must be drained during an ATWS. Conditions are:

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• Drywell Radiation Monitor RMA-RM-40A reads 8x103 R/hr.

• Drywell Radiation Monitor RMA-RM-40B reads 2x103 R/hr.

• Emergency Director declared a Site Area Emergency five (5) minutes ago.

• The TSC is not operational What radiological requirements are required to drain the scram discharge volume?

Answer:

Must be accompanied by a RP Tech.

Justification:

If either station area radiation monitor is off-scale the SS instructs the SO to meet the RP Technician. If either drywell radiation monitor was above 104 R/hr then the crew must wait of the TSC to be operational.

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Description:

Emergency Facilities / Procedures Question Number: 1 Question:

What emergency facilities are activated for an ALERT emergency classification if this is the INITIAL emergency plan classification?

Answer:

TSC (0.4 pt.), OSC (0.4 pt.), and EOF (0.2 pt.) are activated for an Alert, Site Area Emergency, and General Emergency.

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Description:

Emergency Facilities / Procedures Question Number: 2 Question:

You are a licensed Reactor Operator on day shift assigned to the RELIEF CREW. You are escorting two (2) visitors who are auditing clearances in the Work Control Center. A transient occurs that results in the initial declaration of an ALERT and a site evacuation.

What are your required actions regarding the location that you and the visitors physically report to?

Answer:

Escort the visitors to the exit turnstile and direct them to go to Training Building Classroom J, H or I and then report to the Control Room.

Justification:

Personnel escorting visitors shall take them to the exit turnstile and direct them to report to the Training Building Classroom j, H, or I for assembly. Escorts then report to their own designated assembly area. Operations personnel acting as relief crew shall report to the Control Room.

Technical Reference(s):

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Task

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Task

Title:

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Task Standards:

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Task

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Title:

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Title:

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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level SRO Administrative Topic A.3 Subject

Description:

Radiation Protection Question Number: 1 Question:

To support of an outage, two Station Operators will be assigned outage jobs and two will continue shift duties. Each of the four Station Operators is fully qualified and competent to perform the jobs to be assigned. The accumulated TEDE for the Station Operators and the dose projections for the assignments are:

SO #1 = 100 mrem Shift Duties #1 = 100 mrem SO #2 = 250 mrem Shift Duties #2 = 300 mrem SO #3 = 300 mrem Outage Job #1 = 550 mrem SO #4 = 550 mrem Outage Job #2 = 400 mrem Plant management has indicated that NO dose extensions will be authorized except for contract personnel performing RPV weld inspections.

Considering the guidelines associated with radiological protection at the facility and the directive by Plant Management regarding dose extensions, assign the Station Operators a job.

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Answer:

Note: Only the BOLDED information is required to answer the question. The remaining information is the justification for the appropriate response.

One consideration is a dose extension is required to exceed 1000 mrem. SO #4 cannot perform either outage job since a dose extension is required. Each of the other Station Operators can be assigned to the outage work.

Another consideration is collective dose for the individuals. Each department should levelize dose accumulated by each individual performing similar job functions to maintain individual dose ALARA. To comply with this directive, the two Station Operators with the lowest accumulated TEDE (SO #1 and SO #2) should be assigned the outage jobs since they have the highest projected dose.

SO #1 should perform Outage Job #1 (projected TEDE = 650 mrem) because of the lowest accumulated TEDE of SO #1 and SO #2.

SO#2 should perform Outage Job #2 (projected TEDE = 650 mrem).

SO# 3 should perform the shift duties with the highest projected dose.

SO #3 should perform Shift Duties #2 (projected TEDE = = 600 mrem).

SO #4 should be assigned the job with the lowest dose.

SO #4 should perform Shift Duties #1 (projected TEDE = = 650 mrem).

With these assignments NO doses extensions are required and collective dose is equalized amongst the Station Operators.

Technical Reference(s):

9.ALARA.1: 6.2.1.1, 5.7.1 K/A #: Importance:

2.3.1 3.0 2.3.4 3.1 Comments:

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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level SRO Administrative Topic A.3 Subject

Description:

Radiation Protection Question Number: 2 Question:

During an emergency, it is necessary to enter a Very High Radiation Area to stop a discharge to prevent large release to the general public. The general area dose rate is 156 Rem/hr and time in the area for one worker to stop the discharge is estimated at 10 minutes.

What emergency exposure control requirements must be met for this individual before entering the area to stop the effluent discharge?

Answer:

Note: Only the BOLDED information is required to answer the question. The other information supports the correct answer and justification for the response.

(156r/hr) x (1 hr/60 min) x (10 min) = 26 Rem exposure to the worker. Exposure above 25 Rem is permitted to save a life or to protect the general public. For emergency exposures above 25 Rem, several requirements must be met.

Be a volunteer.

NOT a declared pregnant worker.

NO previous emergency exposure.

Aware of the hazards associated with the emergency exposure.

Technical Reference(s):

5.7.12; Section 2.6, Attachment 1 K/A #: Importance:

2.3.1 3.0 2.3.10 3.3 Comments:

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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level SRO Administrative Topic A.4 Subject

Description:

EAL Classification / Communications Question Number: 1 Question:

The plant is at 100% power:

• At 08:00 on June 1, HPCI is declared inoperable

• At 08:00 on June 5, one (1) ADS valve is declared inoperable

• At 08:55 on June 5, Reactor Recirc flow is reduced Determine the if a 1-hour or 4-hour report is required and the LATEST time to complete it.

Answer:

4-hour report by 12:55.

Justification:

Per 2.0.5, Attachment 2, a 4-hour report is required when a shutdown is required (initiated) by TS. However, the reporting requirement (time to report) the event does not start until initiation of the plant shutdown meaning that reactor power is reduced / negative reactivity is inserted as a direct result of the requirement.

Therefore, the NRC must be notified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of lowering recirc flow (08:55) which is 12:55.

Per 2.0.5, step 2.1.3.1, for events deemed reportable the reporting time is keyed to the occurrence of the event or condition.

Technical Reference(s):

2.0.5, step 2.1.3.1 and attachment 2 NUREG 1022 Rev. 2 K/A #: Importance:

2.4.30 3.6 Comments:

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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level SRO Administrative Topic A.4 Subject

Description:

EAL Classification / Communications Question Number: 1 Question:

The plant is at 100% power:

• At 08:00 on June 1, HPCI is declared inoperable

• At 08:00 on June 5, one (1) ADS valve is declared inoperable

• At 08:55 on June 5, Reactor Recirc flow is reduced Determine the if a 1-hour or 4-hour report is required and the LATEST time to complete it.

Answer:

4-hour report by 12:55.

Justification:

Per 2.0.5, Attachment 2, a 4-hour report is required when a shutdown is required (initiated) by TS. However, the reporting requirement (time to report) the event does not start until initiation of the plant shutdown meaning that reactor power is reduced / negative reactivity is inserted as a direct result of the requirement.

Therefore, the NRC must be notified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of lowering recirc flow (08:55) which is 12:55.

Per 2.0.5, step 2.1.3.1, for events deemed reportable the reporting time is keyed to the occurrence of the event or condition.

Technical Reference(s):

2.0.5, step 2.1.3.1 and attachment 2 NUREG 1022 Rev. 2 K/A #: Importance:

2.4.30 3.6 Comments:

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Cooper Nuclear Station Category A - Examination Outline Cross Reference Operating Test Number Cat A Test: 1 Examination Level SRO Administrative Topic A.4 Subject

Description:

EAL Classification / Communications Question Number: 2 Question:

Based on the current plant conditions for the scenario you just completed, determine the highest emergency classification.

Answer:

Refer to the scenario for the emergency classification and justification.

Technical Reference(s):

5.7.1 K/A #: Importance:

2.4.40 4.0 2.4.41 4.1 Comments:

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Performance Standards Initials Checklist

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ATTACHMENT 1 SIMULATOR SET-UP

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ATTACHMENT 2 Directions to Trainee:

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General Conditions:

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Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 9 of 99 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101

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

Task

Title:

Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)

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

Trainee: Examin er:

Score: Pass Fail Examiner Signature:

Date:

Performed faulted/non-faulted: NON-Faulted Additional Program Information:

3. Appropriate Performance Locations: Perform in the plant only.

4. Appropriate Trainee Levels: RO/SRO

5. Evaluation Method: Perform Simulate

6. Performance Time: 35 minutes

7. NRC K/A: 2.1.30 (3.9/3.4)

Directions to Examiner:

1. This JPM evaluates the trainees ability to transfer H2/O2 monitoring system monitors from Standby to Operation.

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

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

4. Observe the trainee during performance of the JPM for proper performance IAW NTP 5.4 and the procedure.

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

Directions to Trainee:

When I tell you to begin, you are to transfer Division 1 H2/O2 monitors from standby to operation. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

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

Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 10 of 99 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101

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

Task

Title:

Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)

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

as you would have manipulated them to transfer H2/O2 monitoring system monitors from standby to operation.

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

Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 11 of 99 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101

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

Task

Title:

Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)

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

General Conditions:

1. Division II H2/O2 System is scheduled to be removed from service.

2. Division I H2/O2 System is in Standby.

General

References:

1. Procedure 2.2.60.1 General Tools and Equipment:

None Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*".

Task Standards:

1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to transfer H2/O2 monitoring system monitors from Standby to Operation.

2. Accurately locate and identify all the instrumentation required to be monitored to transfer H2/O2 monitoring system monitors from standby to operation.

3. Correctly interpret instrument and system responses and their interrelationships when transferring H2/O2 monitoring system monitors from Standby to Operation.

4. Satisfactory completion of TPE requires a minimum of:

a. 100% of critical elements, as defined in the JPM, successfully completed without error.

b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).

Initiating Cue(s):

The CRS has directed you to place the Division I monitoring system in Operation from standby. You are to notify the CRS when Division I H2/O2 monitoring system has been placed in operation.

NOTE: Tell the trainee to begin.

Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 12 of 99 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101

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

Task

Title:

Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)

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

Note to Examiner: The trainee may perform either Step 1 or Step 2 to satisfy the critical step.

Performance Checklist Standards Initials Performance Checklist Standards Initial s

1. Place DIV I H2/O2 The operator places Div I H2/O2 ANALYZER RESET ANALYZER RESET switch to RESET and switch to RESET and then to ON.

• then to ON.

CUE: Switch is positioned to RESET and then to ON.

2. Place POWER switch The operator places POWER switch to RESET and to RESET and release at PC-CS-release at PC-CS- H2/O2 I (Cable Spreading Room).

• H2/O2 I (Cable Spreading Room) CUE: Switch is positioned toward RESET and RELEASED.

3. Ensure power switch The operator ensures power switch in ON in ON.

CUE: Switch is positioned toward ON.

4. Check pump P-1 is The operator checks pump P-1 is running with PUMP running with PUMP switch in RUN.

switch in RUN.

CUE: Pump switch is in RUN, red light is lit for the P-1 pump.

Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 13 of 99 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101

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

Task

Title:

Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)

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

Performance Checklist Standards Initial s

5. Ensure only one The operator ensures only one sample stream sample stream solenoid valve and solenoid valve and H2/O2 Pump P-1 discharge valve

• H2/O2 Pump P-1 indicates OPEN.

discharge valve indicates OPEN. CUE: One sample stream solenoid valve light is red, the others are green. (Select and indicate one of the valves one away from the Div II monitor current sample point).

6. Advance sample The operator advances the sample stream by pressing stream by pressing Key 7 until Div Key 7 until Div I I and Div II are on different and Div II are on streams with one line between different streams them.

with one line between them. CUE: Provide response to match action taken by operator.

(The sample stream should advance one for each press of Key 7.)

7. Re-initialize the The operator presses Key 1.

monitor by pressing Key 1. CUE: Key 1 has been pressed. *

8. Place Div I H2/O2 The operator places Div I H2/O2 ANALYZER RESET ANALYZER RESET switch to OFF.

switch to OFF.

CUE: Switch is positioned toward OFF.

Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 14 of 99 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101

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

Task

Title:

Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)

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

Performance Checklist Standards Initial s

9. Place PC-R-H2 I, The operator places PC-R-H2 I, CONTAINMENT CONTAINMENT HYDROGEN, PRINT HOLD HYDROGEN, PRINT- switch in PRINT.

• HOLD switch in PRINT. CUE: Switch is positioned toward PRINT.

10. Place PC-R-O2 I, The operator places PC-R-O2 I, CONTAINMENT OXYGEN, CONTAINMENT OXYGEN, PRINT-HOLD PRINT-HOLD switch switch in PRINT.

• in PRINT.

CUE: Switch is positioned toward PRINT.

11. Check PC-R-H2 I and The operator checks that PC-R-O2 I digital PC-R-H2 I and PC-R-O2 I digital displays indicate displays indicator number number associated associated with stream being with stream being sampled as indication on PC-CS-sampled as H2/O2 I.

indicated on PC-CS-H2/O2 I. CUE: Recorders are synchronized CUE: One hour has elapsed after recorders were synchronized.

12. LCD displays H2 and The operator ensures the LCD O2 values with no displays H2 and O2 values with no alarm messages. alarm messages.

CUE: Only H2 and O2 values are indicated.

13. Ensure no alarm The operator ensures no alarm indicating lights indicating lights are on.

are on.

CUE: No red lights are illuminated.

Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 15 of 99 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101

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

Task

Title:

Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)

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

Performance Checklist Standards Initial s

14. Inform CRS Div I is The operator informs the CRS Div I in operation. is in operation.

CUE: The CRS acknowledges the report. This JPM is now complete.

Nebraska Public Power District SKL034-21-01 Cooper Nuclear Station Page 16 of 99 Job Performance Measure Revision 01 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 223070A0101

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

Task

Title:

Transfer H2/O2 Monitoring System Monitors From Standby to Operation (Div. 1)

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

ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to transfer Division 1 H2/O2 monitors from standby to operation. Before you start, I will state the general plant conditions, the Initiating Cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to transfer H2/O2 monitoring system monitors from standby to operation.

General Conditions:

1. Division II H2/O2 System is scheduled to be removed from service.

15. Division I H2/O2 System is in standby.

Initiating Cues:

The CRS has directed you to place the Division I monitoring system in operation from standby. You are to notify the CRS when Division I H2/O2 monitoring system has been placed in operation.

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JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104

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Task

Title:

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JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104

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Task

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JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104

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Task

Title:

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JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104

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Task

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TRANSFER AN MCC TO THE ALTERNATE POWER SUPPLY

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Task

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JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 262018O0104

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

Task

Title:

TRANSFER AN MCC TO THE ALTERNATE POWER SUPPLY

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

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ATTACHMENT 1 Directions to Trainee:

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Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 24 of 99 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104

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

Task

Title:

INSTALL & REMOVE PTMs (PTM #41 & 42)

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

Trainee:

Examiner:

Score: Pass Fail Examiner Signature:

Date:

Additional Program Information:

1. Appropriate Performance Locations: Plant

2. Appropriate Trainee Levels: SO/RO/SRO

3. Evaluation Method: Simulate Perform

4. Performance Time: 20 minutes

5. NRC K/A: 2.1.30 (3.9/3.4); 2.4.34 (3.8/3.6)

Directions to Examiner:

1. This JPM evaluates the trainees ability to defeat RCIC low Reactor pressure isolation using PTM #41 and #42 per 5.8.20.

2. ENSURE THE OPERATOR COMPLIES WITH ALL ELECTRICAL SAFETY PRECAUTIONS.

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

4. Observe the trainee during performance of the JPM for proper performance IAW NTP 5.4 and the procedure.

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

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

Directions to Trainee:

When I tell you to begin, you are to perform the steps necessary to defeat RCIC low Reactor pressure isolation using PTM #41 and #42 per 5.8.20. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to complete EOP PTM #41 and #42.

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

Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 25 of 99 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104

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

Task

Title:

INSTALL & REMOVE PTMs (PTM #41 & 42)

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

Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 26 of 99 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104

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

Task

Title:

INSTALL & REMOVE PTMs (PTM #41 & 42)

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

General Conditions:

1. The plant has scrammed.

2. The MSIVs are closed.

3. HPCI is being used for pressure control.

4. RCIC is being used for level control.

General

References:

5. Emergency Support Procedure 5.8.20, EOP Plant Temporary Modifications General Tools and Equipment:

1. Flat tipped screwdriver.

2. Key for Aux Relay Room (Grand Master will work)

3. Electrical tape.

4. Key for PTM Box in Aux Relay Room (Master Lock J423)

5. Flashlight.

Special Conditions, References, Tools, Equipment:

1. Critical checks denoted by "*".

Task Standards:

1. Accurately locate, identify, operate and/or manipulate all component controls required to be utilized to install EOP PTMs #41 and #42.

2. Accurately locate and identify all instrumentation required to be monitored when installing EOP PTMs #41 and #42.

3. Correctly interpret instrument and system responses and their interrelationships when installing EOP PTMs #41 and #42.

4. Satisfactory completion of TPE requires a minimum of:

a. 100% of critical elements, as defined in the JPM, successfully completed without error.

b. 100% of core work practices (e.g., safety, housekeeping, control of tools, material control, proper use of tools, procedure steps performed in sequence and as written) evaluated as satisfactory (SAT) or not applicable (N/A).

Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 27 of 99 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104

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

Task

Title:

INSTALL & REMOVE PTMs (PTM #41 & 42)

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

Initiating Cue(s):

The Reactor Operator has directed you to defeat RCIC low Reactor pressure isolation by installing EOP PTMs #41 and #42 per ESP 5.8.20. You are to inform the Reactor Operator when the EOP PTMs #41 and #42 have been installed.

NOTE: Tell the trainee to begin.

Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 28 of 99 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104

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

Task

Title:

INSTALL & REMOVE PTMs (PTM #41 & 42)

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

Performance Checklist Standards Initials

1. Obtain flat-tipped The operator obtains flat-tipped screwdriver screwdriver and electrical and electrical tape.

• tape.

NOTE: Procedure 5.8.20 is NOTE: The student must show you a flat-staged in the Relay Room. tipped screwdriver and electrical tape. These are in the PTM box, NOTE: Key J423 is required to but a Master Lock key is required.

open the PTM Box in the Aux Any flat-tipped screwdriver and Relay room. electrical tape will work.

2. Identify Wire RC27-4 on The operator correctly identifies Wire Terminal BB-43 in PNL 9-30 RC27-4 on Terminal BB-43 in PNL 9-30.

(C-903-AUX RELAY RM).

3. Install EOP PTM The operator loosens the screw and removes Number 41 by lifting Wire Wire RC27-4 from Terminal BB-43 in PNL

• RC27-4 from Terminal 9-30.

BB-43, PNL 9-30 (C-903-AUX RELAY RM).

CUE: The lead is lifted.

4. Insulate the lifted lead The operator wraps tape around the end of the wire lifted.

CUE: The end of the wire has electrical tape wrapped around it.

Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 29 of 99 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104

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

Task

Title:

INSTALL & REMOVE PTMs (PTM #41 & 42)

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

Performance Checklist Standards Initials

5. Hang PTM tag. The operator hangs the PTM 41 tag on the lifted lead.

CUE: The PTM 41 tag is attached to the lifted lead.

6. Identify Wire RC-35-3 on The operator correctly identifies Wire Terminal DD-28 in BAY-3 of RC-35-3 on Terminal DD-28 in BAY-3 of PNL 9-33 (C-903-AUX PNL 9-33.

RELAY RM).

NOTE: Panel 9-33 bays are numbered from right to left, bay 3 is the bay farthest to the left.

7. Install EOP PTM The operator loosens the screw and removes Number 42 by lifting Wire Wire RC-35-3 from Terminal DD-28 in

• RC-35-3 from BAY-3 of PNL 9-33.

Terminal DD-28, BAY-3, PNL 9-33 (C-903-AUX RELAY RM). CUE: The lead is lifted.

8. Insulate the lifted lead The operator wraps tape around the end of the wire lifted.

CUE: The end of the wire has electrical tape wrapped around it.

Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 30 of 99 Job Performance Measure Revision 00 JOB PERFORMANCE MEASURE FOR OPERATIONS Task No.: 299051A0104

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

Task

Title:

INSTALL & REMOVE PTMs (PTM #41 & 42)

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

Performance Checklist Standards Initials

9. Hang PTM tag. The operator hangs the PTM 42 tag on the lifted lead.

CUE: The PTM 42 tag is attached to the lifted lead.

10. Inform CRS that RCIC The operator informs the CRS (RO) that low reactor pressure EOP PTM 41 and 42 has been installed.

isolation has been defeated. CUE: The CRS (RO) acknowledges. This JPM is complete.

Nebraska Public Power District SKL034-40-72 Cooper Nuclear Station Page 31 of 99 Job Performance Measure Revision 00 ATTACHMENT 1 Directions to Trainee:

When I tell you to begin, you are to perform the steps necessary to defeat RCIC low Reactor pressure isolation using PTM #41 and #42 per 5.8.20. Before you start, I will state the general plant conditions, the initiating cues, and answer any questions you may have.

When simulating, physically point to any meters, gauges, recorders and controls you would be using. State the position of controls as you would have manipulated them to complete EOP PTM #41 and #42.

General Conditions:

1. The plant has scrammed.

2. The MSIVs are closed.

3. HPCI is being used for pressure control.

4. RCIC is being used for level control.

Initiating Cue(s):

The Reactor Operator has directed you to defeat RCIC low Reactor pressure isolation by installing EOP PTMs #41 and #42 per ESP 5.8.20. You are to inform the Reactor Operator when the EOP PTMs #41 and #42 have been installed.

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JOB PERFORMANCE MEASURE FOR OPERATIONS 7DVN1R

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ATTACHMENT 1 Directions to Trainee:

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Simulation Cooper Nuclear Scenario 1 Op Test No.:

Facility Station No.:

Examin Operat CRS ers: ors:

RO BOP Initial 70% Full Power Operation, (EOC) (IC-20) with all Condition systems operable except the Emergency Transformer and s: A CRD Pump.

Turno See attached turnover sheet ver:

Event Eve Positi Event No. nt on Description Typ e*

Pre- N/A ATWS insert Pre- N/A Group 1 isolation failure insert Pre- N/A Loss of power, Emergency Transformer insert 1 N BOP Shift RB HVAC Fans 2 C CRS/ REC Pump Trip.

BOP Page 36 of 17

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3 R CRS/ Scheduled power increase RO 4 I CRS/ A APRM fails high.

RO 5 C Crew Loss of main condenser vacuum 6 M Crew ATWS (Hydraulic Lock on HCUs).

7 C CRS/ MSIVs fail to close following loss of vacuum.

BOP

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Page 37 of 17

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SCENARIO #1

SUMMARY

The crew assumes the shift with the plant operating at 70% power with all systems operable except the Emergency Transformer and the A CRD Pump. The crew will perform a routine shifting of RBHVAC Fans; shortly after the fan swap, the B REC Pump will trip. This will require entry into 2.4REC and T.S. 3.7.3.

After conditions are stabilized, the load dispatcher will request raising main generator load 100 Mwe which requires raising reactor power with recirc flow. While raising load the A Average Power Range Monitor (APRM) will fail high, initiating a half scram. This will require bypassing the APRM, resetting RPS and checking Technical Specifications (tracking LCO only). Main Condenser vacuum will degrade as air in-leakage rises from a leak in the turbine/condenser boot. This will require a turbine trip and reactor scram. When a reactor scram is attempted, an ATWS requires entry into EOPs 1A, 6A and 7A. ARI will also fail to insert Control Rods. When Vacuum lowers to the MSIV isolation setpoint, the MSIVs will fail to close and must be manually closed.

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Some Control Rods will insert on the first manual scram after the ATWS. A second manual scram will insert more Control Rods, and the third manual scram will insert the remaining Control Rods.

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Scenario 1 Event 1 No: No.

Event Shift Reactor Building H & V Exhaust Fans

==

Description:==

Tim Positi Applicants Actions or Behavior e on CRS Directs Shift Reactor Building H & V Exhaust Fans per Section 5.0 of OP 2.2.47.

BOP Place Controller HV-DPIC-835A, RX BLDG/ATMOS DP, to MANUAL (M) and adjust signal to stabilize Reactor Building pressure at -0.30" to -0.33" wg.

Place control switch for SUPPLY FAN selected to AUTO to RUN.

NOTE - Performance of the next step should be rapid and may result in RX BLDG LOW D/P alarm and entry into EOPs and T.S. if RX BLDG d/p goes above zero.

BOP Place control switch for EXHAUST FAN selected to STBY to RUN.

Place control switch for fan to be removed from service Page 40 of 17

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Tim Positi Applicants Actions or Behavior e on to OFF and back to STBY.

Ensure Reactor Building pressure is being maintained at -

0.30" to -0.33" wg.

Adjust HV-DPIC-835A, to stabilize Reactor Building pressure at -0.30" to -0.33" wg.

Place control switch for SUPPLY FAN selected to RUN to AUTO.

Place control switch for EXHAUST FAN selected to RUN to AUTO.

Place Controller HV-DPIC-835A, RX BLDG/ATMOS DP, in AUTO (A). Ensure Reactor Building pressure continues to be maintained at -0.30" to -0.33" Page 41 of 17

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Tim Positi Applicants Actions or Behavior e on Page 42 of 17

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Scenario 1 Event 2 No: No.

Event REC Pump Trip

==

Description:==

Tim Positi Applicants Actions or Behavior e on BOP Reports Annunciator: M-1/B-2, REC PUMP B FAILURE. and possibly LOW HEADER PRESSURE.

BOP Diagnoses the loss of the B REC Pump CRS Directs the start of necessary REC pumps.

BOP Starts the C REC pump.

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Tim Positi Applicants Actions or Behavior e on BOP Starts the C REC Pump and verifies normal system operation.

Directs an SO to inspect the REC Pump area for unusual conditions and verify the C REC Pump is operating correctly.

Verifies correct valve lineup and monitors REC Pump discharge pressures.

CRS Initiates investigation and repair of REC Pump B Enters T.S. 3.7.3.A1 and declares a 30 day LCO Page 44 of 17

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Tim Positi Applicants Actions or Behavior e on Page 45 of 17

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Scenario 1 Event 3 No: No.

Event Power Increase

==

Description:==

Tim Positi Applicants Actions or Behavior e on CRS Direct the RO to increase station output by 100 MWe by raising recirc flow in accordance with station procedure 2.1.10.

NOTE:

CRS may act as Reactivity Manager.

RO Enters 2.1.10, STATION POWER CHANGES Raises power by increasing RR pump flow, maintaining loop flows balanced. Maintains rate of power change consistent with system capabilities as determined by Load Dispatcher.

Discontinues power rise when directed or station output has risen 100 MWe.

BOP Monitors secondary plant parameters and reports Mwe changes to RO.

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Tim Positi Applicants Actions or Behavior e on Page 47 of 17

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Scenario 1 Event 4 No: No.

Event A APRM Fails High

==

Description:==

Tim Positi Applicants Actions or Behavior e on RO Reports Annunciators 9-5-1/A-4, ROD WITHDRAWAL BLOCK 9-5-1/A-7 APRM RPS CH A UPSCALE TRIP OR INOP 9-5-2/A-1 RX SCRAM CHANNEL A alarm.

Diagnoses half scram and APRM A High CRS Directs BOP to back panels to check APRM drawers for indications and trouble shooting.

BOP Locates APRM A on back panels Reports APRM A failed upscale CRS Directs RO to BYPASS APRM A and reset half scram.

May check T.S. 3.3.1 (Minimum channel requirments are met) and declare a Tracking LCO on the failed APRM.

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Tim Positi Applicants Actions or Behavior e on RO Bpasses APRM A Resets half scram per 2.1.5 Page 49 of 17

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Scenario 1 Event 5 No: No.

Event Loss of Main Condenser vacuum

==

Description:==

Tim Positi Applicants Actions or Behavior e on BOP Operator diagnoses loss of vacuum from Control Room indications or annunciator B-1/A-3, TG LOW VACUUM PRE-TRIP Announces degrading condenser vacuum.

CRS Enters ABNORMAL PROCEDURE 2.4.VAC, LOSS OF CONDENSER VACUUM Directs a reactor power reduction by reducing recirculation flow.

Notifies Load Dispatcher.

Directs BOP operator to keep him informed of vacuum When it is determined that vacuum cannot be recovered to >23" Hg, directs a Reactor Scram and Turbine Trip.

RO Lowers power by lowering RR pump flow. Maintains rate of power change consistent with system capabilities.

When directed, manually scrams the reactor, reports failure to scram.

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Tim Positi Applicants Actions or Behavior e on Page 51 of 17

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Scenario 1 Event 6 No: No.

Event ATWS (Hydraulic Lock)

==

Description:==

Tim Posit Applicants Actions or Behavior e ion CRS Enters EOP-1A and transitions to 6A/7A. Directs:

Place the Mode switch in S/D ARI initiated Manually runback RR pumps to minimum Trip Recirc pumps Insert control rods using 5.8.3 actions.

Verify group isolations.

Inhibit ADS Pressure be maintained 800 to 1000 psig.

RPV Low Water Level Group 1 be defeated. (This step may not be taken if the MSIVs have closed or the CRS anticipates MSIV closure on the loss of vacuum.)

RO Mode switch to SHUTDOWN.

Initiate ARI.

Run Recirc pumps to minimum.

Trip Recirc pumps.

Insert control rods per 5.8.3 Begins actions to reset the scram and re-inserting additional scrams.

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Tim Posit Applicants Actions or Behavior e ion BOP Inhibit ADS.

Verify Group isolations (MSIVs should isolate by 8" Hg vac).

Maintain RPV pressure 800 to 1000 psig with Turbine Bypass Valves and SRVs.

Initiates SLC (If directed at this time) and confirms injection.

Provides initial SLC Tank level to the CRS.

CRS Directs terminating and preventing injection except for RCIC, CRD and Boron injection be terminated and prevented until RPV water level is < +100" (corrected FZ)

Before BIIT, direct SLC be initiated.

When RPV water level reaches +100" (corrected FZ),

direct RPV water level be maintained between -25" and

+100" (corrected FZ) (LL).

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Scenario 1 Event 6 No: No.

Event ATWS (Hydraulic Lock)

==

Description:==

Time Posit Applicants Actions or Behavior ion BOP Lowers RPV water level to +100" and reports to CRS.

When and if directed, maintains RPV water level -25" to

+100".

CRS When torus temperature reaches 95?F, enter and direct the activities of EOP-3A.

Direct torus cooling be placed in service.

When all rods have been inserted or HSBW injected, direct RPV water level be restored and maintained +15" to +40".

RO Direct SO to install EOP PTM 61 & 62.

Install jumpers to defeat RPS.

Reset scram.

Allow SDV to drain.

Insert manual scram, report rod movement.

Reset scram and continue inserting manual scrams.

Report when 26% (HSBW) of the SLC tank has been injected.

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BOP Initiates RHR in Suppression Pool Cooling.

When directed, maximizes Suppression Pool Cooling.

Restore and maintain RPV water level +15" to +40".

CRS Classifies event as a Site Area Emergency (based on EAL 3.3.4) and implements EPIP 5.7.2, Shift Supervisor EPIP.

Page 55 of 17

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Scenario 1 Event 7 No: No.

Event MSIVs failure to automatically isolate

==

Description:==

Time Posit Applicants Actions or Behavior ion BOP Report MSIVs have not isolated on low cond. vacuum (10").

CRS Direct maually closing the MSIVs.

BOP Place all MSIV control switches to CLOSE.

Verify all MSIVs are closed.

Page 56 of 17

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Time Posit Applicants Actions or Behavior ion Critical Tasks Sat Unsat Scenario #1 Page 57 of 17

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The Crew shall stop injection within 5 minutes of directing injection be stopped.

The crew shall insert the control rods.

Page 58 of 17

Instructor Station Instructions 6./

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SIMULATOR SET-UP A.Initialize the simulator in IC 20, Full Power Operation (EOL).

1. Transfer to RUN.

2. Load batch file A:\nrc1

3. Lower Reactor power to 70% using recirc flow

4. Adjust generator to +100 MVARs.

5. Balance voltage regulator.

6. Balance all controllers.

7. Place breakers 1FS and 1GS in PTL

8. Ensure PMIS IDTs are blank

9. Red tag the "A" CRD Pump

10. Red tag breaker C/S for 1FS & 1GS.

11. Clear all annunciators

12. Turn recorder power ON Page 59 of 17

Instructor Station Instructions 6./

Scenario #1 3-

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13. Adjust GAFs B.Verify simulator conditions as follows:

1. Triggers Number File Name Description E1 None Default to False E2 None Default to False E3 None Default to False E4 None Default to False E5 None Default to False

2. Malfunctions Numbe Title Trigg T Severit Ram Initi r er D y p al RP04 Group 1 Isolation Active N/ N/A N/A N/A Failure A RD02 ATWS Active N/ 90% N/A N/A A

Page 60 of 17

Instructor Station Instructions 6./

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Numbe Title Trigg T Severit Ram Initi r er D y p al ED06 Loss of Power Active N/ N/A N/A N/A Emergency A Transformer SW11B Trip of B REC E1 0 N/A N/A N/A Pump NM09A APRM Signal E3 0 100% N/A N/A Failure MC01 Main Condenser E4 0 100% 10:00 N/A Air In-Leakage

3. Remotes Numbe Title Trigg Value Ram r er p RD18 Install ARI PTMs E4 N/A N/A RD04 Manually Close E5 CLOS N/A CRD-29 E Page 61 of 17

Instructor Station Instructions 6./

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4. Overrides Instrument Tag Trigge T Valu Ram r D e p Control Switch zdicrdsws3a[1] A N/ STO N/A for CRD Pump A P A (START, STOP)

Control Switch zdocrdsws3a[1] A N/ OFF N/A for CRD Pump A A green light Page 62 of 17

Instructor Station Instructions 6./

Scenario #1 3-

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Pre Events:

Allow the operators several minutes to review the panels and set up the controls and displays as they desire.

Event #1:Shift Reactor Building H & V Exhaust Fans ROLE PLAY:

None Event #2: REC Pump Trip ACTION:

When the crew has swapped RBHVAC fans and Secondary Containment Parameters are normal and when directed by the lead examiner Activate Trigger E1: REC Pump B Trip ROLE PLAY:

If asked as the Station Operator to investigate wait 1 minute and report that the pump motor is hot and it smells of hot insulation.

ROLE PLAY:

If asked to check the C REC Pump as the SO report that it is Page 63 of 17

Instructor Station Instructions 6./

Scenario #1 3-

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operating normally.

Event #3: Power Increase ROLE PLAY:

Contact the Control Room via extension 5271 as the load dispatcher and direct that net load be raised 100 MWe. In addition direct that MVARs remain at +100 MVARs.

ROLE PLAY:

If contacted as the reactor engineer direct the crew to raise power using recirc flow.

Page 64 of 17

Instructor Station Instructions 6./

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Event #4: A APRM Fails High ACTION:

After the crew has completed the power change and when directed by the lead examiner Activate Trigger E3: APRM Signal Failure.

ROLE PLAY:

If contacted as I & C report that you will get a tech and be up in the control room in about 15 minutes.

Event #5: Loss of Main Condenser vacuum ACTION:

After the crew has reponded to the APRM failure and when directed by the lead examiner Activate Trigger E4:Main Condenser Air In-Leakage.

ROLE PLAY:

If called as the load dispatcher acknowledge the load reduction.

Event #6: ATWS ROLE PLAY:

Page 65 of 17

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If asked as the Station Operator to install ARI PTMs, wait 2 minutes, then Insert REMOTE FUNCTION RD18, EOP PTMs 61 and 62 and inform the Control Room.

ACTION:

One minute after the first manual scram, modify malfunction RD02, ATWS to 80%

After the second scram modify malfunction RD02, ATWS to 60%

After the third scram delete malfunction RD02.

ACTION:

When the following conditions are reached, place the simulator in FREEZE:

1. The MSIVs are closed.

2. Reactor is shutdown under all conditions without boron.

3. When directed by the lead examiner.

Page 66 of 17

Instructor Station Instructions 6./

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Batch File

^NRC Scenario 1 imf rp04 imf rd02 90 imf ed06 ior zdicrdsws3a[1] stop ior zlocrdsws3a[1] off imf sw11b(1) imf nm09a(2) imf mc01(3) 100 10:00 irf rd18(4) remove irf rd04(5) close Page 67 of 17

Turnover Information Scenario #1 Plant Status:

1. The plant is operating at approximately 70% power near the end of the operating cycle.

2. Rod Sequence Step: 1 Information:

Rod: 18-27 Notc 26 h:

3. Tech. Spec. Limitations in effect:

Day 1 of 7 day LCO (3.8.1, condition A) due to Emergency Transformer being OOS for planned maintenance on 69KV line by OPPD. All associated surveillances are current. SR6.EE.610 was performed one hour ago.

Page 68 of 17

Instructor Station Instructions Scenario #1

4. Significant problems/abnormalities:

• "A" CRD Pump is tagged out. The speed increaser gearbox is being replaced after complete failure.

• Emergency Transformer estimated return to service this shift.

• Southeast Nebraska is in a severe thunderstorm warning and flash flood watch.

5. Evolutions/maintenance for the on-coming shift:

• When contacted, raise power level.

• Mechanics working on "A" CRD Pump.

• OPPD expediting return of 69KV line due to weather

• As soon as possible after assuming the shift, shift RBHVAC fans to permit maintenance to lubricate Exhaust Fan EF-R-1A Page 69 of 17

Simulation Cooper Nuclear Scenario 2 Op. Test Facility: Station No. No.

Examine Operator CR rs: s: S R

O B

OP Initial 100% Full Power Operation, (EOC) (IC-20) with all Conditions: systems operable except the Emergency Transformer.

Turnover: See attached turnover sheet.

Event Eve Posit Event Description No. nt ion Typ e

Pre- N/A RRMG A Scoop Tube Lockout P/B failure insert Pre- N/A RRMG B Scoop Tube Lockout P/B failure insert Pre- N/A RCIC system failure to automatically start insert Pre- N/A HPCI Auxiliary Oil Pump failure to start insert Pre- N/A 4160 Bus auto transfer failure insert Page 70 of 18

Pre- N/A Loss of power Emergency Transformer insert 1 N Start the A CRD pump and place it in (CRS/BOP service. Secure the B CRD Pump.

)

2 R Power reduction to lower load on the south (CRS/RO) interface.

3 C DEH Oil System Pressure Oscillations.

(CRS/BOP

)

4 I Recirculation Pump Runback to 20% with (CRS/RO) power oscillations.

5 C (Crew) Loss of all off-site power.

(CRS/BOP

)

6 M Small break LOCA with an HPCI Aux oil (CREW) pump failure 7 C (CRS/BOP) RCIC fails to automatically (CRS/BOP start then trips.

)

• (N)ormal,(R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient Page 71 of 18

SCENARIO # 2

SUMMARY

Page 72 of 18

The crew assumes the shift with the plant operating at 100% power with all systems operable except the Emergency Transformer and A CRD Pump. The crew will start the A CRD Pump and place it in service. After the CRD system is operating normally, Doniphan will notify Cooper that the south interface load has exceeded 1190 MVA and that Cooper must lower load 100 MWe immediately. After a sufficient power change is observed, the DEH oil pressure pilot valve spring will fail, causing DEH pressure oscillation, this will require stopping the power reduction. When conditions have stabilized, a 20% spurious runback signal will force the reactor into the Stability Exclusion Region and eventual power oscillations will occur. Entry into the Stability Exclusion Region will require entry into T.S. 3.4.1.

The power oscillations will become large and may reach the APRM High setpoints with the auto scram function defeated. The crew must manually scram the reactor. When the reactor scrams off-site power will be lost and a small break will start on the B Recirc Loop discharge line. The DGs will start and provide power to emergency buses. A failure of the HPCI Auxiliary Oil Pump will prevent operation of HPCI. RCIC will fail to automatically start and must be manually started. After its started it will trip. It may be restarted, but will continue to trip. When RPV water level cannot be maintained, Page 73 of 18

the crew must Emergency Depressurize and restore RPV water level with low pressure ECCS systems with power supplied by the DGs.

Page 74 of 18

Scenario No: 2 Event No. 1 Event

Description:

Start the A CRD Pump and secure the B CRD Pump Time Position Applicants Actions or Behavior CRS Directs the BOP to establish communication with the CRD Room, then start the A CRD pump and when proper operation is established shutdown the B CRD Pump.

BOP Establish communications between Control Room and CRD pump area.

BOP Check the A CRD pump is lined up for operation.

BOP At Panel 9-5, balance CRD-FIC-301, CRD FLOW CONTROL, and place to MANUAL.

Start standby CRD pump.

BOP Shut down CRD pump to be removed from service.

adjust manual control on CRD-FC-301 to obtain flow of 50 gpm.

Balance CRD-FC-301 and place to BAL.

At Panel 9-5, check charging water pressure and drive water DP and adjust if needed.

Page 75 of 18

Scenario No: 2 Event No. 2 Event

Description:

Power Reduction Time Position Applicants Actions or Behavior The Control Room is contacted by Doniphan and notified that the Cooper south interface load has exceeded 1190 MVA and that an immediate load reduction of 100 Mwe is required.

CRS Enters 5.3GRID.

Direct an immediate power reduction of 100 Mwe using recirculation flow.

Acts as Reactivity Manager.

RO Enters 2.1.10, STATION POWER CHANGES

- Lowers power by lowering RR pump flow. Maintains rate of power change at 10 MWe per minute

- Enters 5.3GRID.

BOP Monitors plant parameters.

Evaluates which plant loads may be secured.

CRS Notifies station management and the system load dispatcher.

Page 76 of 18

Scenario No: 2 Event No. 3 Event

Description:

DEH Oil System Pressure Oscillation requires stopping power reduction.

Time Position Applicants Actions or Behavior Annunciator B-1/A-6 TURB EH FLUID LOW PRESSURE alarms BOP Determines standby pump starts (both pumps are running).

Directs an SO to check the EHC pumps and piping Diagnoses oscillating DEH relief valve from oscillating pressure on DEH pressure indication.

Requests SO to verify proper operation of pumps and check for leaks.

Remove standby pump from service per 2.2.80.

CRS Directs stopping any power changes in progress Directs RO to monitor reactor pressure set Enters 2.4DEH Gives Scram Actions Directs securing one DEH Pump Directs restoring DEH to a normal lineup in accordance with 2.2.80.

Initiates a work order for the oscillating DEH Valve.

Page 77 of 18

Scenario No: 2 Event No. 4 Event

Description:

Recirculation Pump Runback to 20% with power oscillations.

Time Position Applicants Actions or Behavior Annunciators 9-4-3/D-3 RECIRC A FLOW LIMIT alarms 9-4-3/D-7 RECIRC B FLOW LIMIT alarms Followed by:

Annunciators 9-5-1/A-4 ROD WITHDRAWAL BLOCK 9-5-1/B-7 LPRM UPSCALE 9-5-1/C-7 LPRM DOWNSCALE 9-5-1/B-8 APRM UPSCALE and others indicating core power oscillations.

RO Monitors recirculation flow and reactor power.

Attempts to limit the transient by pressing the SCOOPTUBE LOCKOUT buttons.

Press RR PUMP RUNBACK RESET button.

Determines that feedwater flow is > 20% and RR-MO-53A/B are full open.

Monitors for power oscillations.

Informs CRS of entry into stability exclusion region.

Inserts control rods per Attachment 7, Emergency Power Reduction Rods.

When directed by the CRS or the RO determines reactor safety in jeopardy depresses both RX SCRAM buttons (Panel 9-5).

Verifies all rods in Monitors nuclear instrumentation:

- Insert SRM and IRM detectors.

- Change APRM recorders to IRMs.

- Range IRMs on scale.

- Check reactor power is lowering.

Verifies all SDV vent and drain valves are closed.

CRS Directs RO to press SCOOPTUBE LOCKOUT buttons.

Enters 2.4RR, REACTOR RECIRCULATION ABNORMAL Enter Attachment 4 when entry in or near the stability exclusion region is determined.

Enters T.S. 3.4.1 Increase speed of operating recirculation pump(s) per Procedure 2.1.10.

Insert Emergency Power Reduction Rods per Procedure 10.13.

When core power oscillations reach the APRM scram set point directs a MANUAL SCRAM.

Page 78 of 18

Scenario No. 2 Event No. 4 (continued)

Event

Description:

Recirculation Pump Runback to 20% with power oscillations Time Position Applicants Actions or Behavior BOP Monitors secondary plant response.

After the reactor is scrammed:

Trips one reactor feedwater pump Trips all but one condensate booster pump and condensate pump.

Ensure Main turbine automatically trips or manually trip the turbine when main generator output is <

80 Mwe.

Diagnoses Loss of Off-Site Power.

Page 79 of 18

Scenario No: 2 Event No. 5 Event

Description:

Loss of all off-site power.

Time Position Applicants Actions or Behavior The following annunciators alarm:

C-2/D-9 STARTUP XFMR SECONDARY UNDERVOLTAGE C-2/C-9 STARTUP XFMR LOW VOLATAGE C-2/A-1 4160V BUS 1A UNDERVOLTAGE. (and 1B, 1E, 1G, etc.)

CRS Enters EMERGENCY PROCEDURE 5.3EMPWR, EMERGENCY POWER and directs actions for a loss of off-site AC power.

Establishes a pressure band of 800 to 1000 psig using SRVs.

Establishes a RPV level band of 10 to 40.

Enters EOP-5A is the loss of power causes a high temperature in the MS Tunnel.

Verifies:

BOP 4160V Buses 1A, 1B, 1C, 1D, and 1E de-energized.

Both DGs have started and loaded.

4160V Bus 1F/1G energized by emergency source.

Monitors DG load to prevent exceeding maximum load (4000 kW and 694 amps; DG may be overloaded to 4400 kW and 763 amps for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period).

Places DRYWELL REC ISOL VALVE CONTROL switch to OPEN.

Throttles open REC HX outlet valve for a HX that was in service, as necessary, to maintain REC-PI-452, REC HEADER PRESSURE, in green band:

Ensures the emergency DC lube oil pumps have started Places Condensate and Condensate Booster Pump switches to TRIP.

Places Air Compressor A or B switch to RUN.

RO Restores CRD System per Procedure 2.2.8.

Page 80 of 18

Scenario No.: 2 Event No.: 6 Event

Description:

Small break LOCA with inability to restore RPV water level Time Position Applicants Actions or Behavior Monitors RPV water level and Primary Containment parameters.

RO/BOP Diagnose LOCA by lowering RPV water level and rising Drywell pressure.

Diagnoses HPCI Aux Oil Pump failure.

BOP Diagnoses RCIC failure to start.

Initiates torus spray.

Initiates drywell sprays

- Shuts down drywell coolers (if operating)

- Shuts down recirc pumps

- Initiates drywell sprays Throttles drywell spray to prevent torus pressure from dropping to 0 psig.

Controls low pressure ECCS to restore and maintain RPV water level between TAF and MSL.

Monitors DG load to prevent exceeding maximum load (4000 kW and 694 amps; DG may be overloaded to 4400 kW and 763 amps for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.)

RO Inhibits ADS when timer initiates.

Controls low pressure ECCS to restore and maintain RPV water level between 15 and 40.

Restores REC Re-establishes drywell cooling by re-starting FCUs CRS Enters EOP-1A and 3A Directs attempt to maintain RPV water level between 15 and 40.

Directs restoring REC Directs re-establishing Drywell FCUs Directs maximizes CRD flow and initiating SLC pumps.

Directs inhibiting ADS Before Torus pressure reached 10 psig directs initiating torus spray.

When Torus pressure exceeds 10 psig directs initiating drywell spray.

When RPV water level cannot be maintained >-25 enters EOP-2A, EMERGENCY DEPRESSURIZATION.

Directs opening six SRVs and controlling low pressure injection to restore level.

Page 81 of 18

Scenario No: 2 Event No. 7 Event

Description:

RCIC fails to auto start.

Time Position Applicants Actions or Behavior CRS Directs attempting to manually restore RCIC.

BOP Uses RCIC SYSTEM OPERATION HARDCARD to start RCIC.

Open RCIC-MO-132.

Start GLAND SEAL VACUUM PUMP.

Open RCIC-MO-21.

Adjust RCIC-FIC-91, RCIC flow controller, as required, to maintain level.

Diagnoses RCIC trip on high exhaust pressure.

Page 82 of 18

CRITICAL TASKS SAT UNSAT The Crew shall emergency depressurize when RPV water level cannot be restored and maintained >-25.

The Crew shall initiate drywell sprays at >10 psig torus pressure and before PSP is exceeded.

The Crew shall initiate a manual scram when oscillations reach the APRM Scram setpoint.

1983.

Page 83 of 18

Instructor Station Instructions Scenario #2 SIMULATOR SET-UP A. Initialize the simulator in IC 20, Full Power Operation (EOL).

1. Transfer to RUN.

2. Load batch file A:\nrc2.

3. Balance all controllers.

4. Place breakers 1FS and 1GS in PTL

5. Ensure PMIS IDTs are blank

6. Red tag breaker C/S for 1FS & 1GS.

7. Clear all annunciators

8. Turn recorder power ON

9. Adjust GAFs Verify simulator conditions as follows:

B. Triggers Number File Name Description E1 None Default to False E2 None Default to False E3 nrc2 Activates when #1 TSV closes E4 None Default to False E5 None Default to False C. Malfunctions Number Title Trigger TD Severity Ramp Initial RC01 RCIC System Failure to Auto Start A 0 N/A N/A N/A ED06 Loss of Power, Emergency A 0 N/A N/A N/A Transformer HP11 HPCI Aux Oil Pump Failure A 0 N/A N/A N/A ED03B Transfer Failure A 0 N/A N/A N/A TC04 DEH Oil System Pressure Oscillation E1 0 N/A N/A N/A RR12A A RR Pump Runback 20% E2 0 N/A N/A N/A Page 84 of 18

Instructor Station Instructions Scenario #2 Number Title Trigger TD Severity Ramp Initial RR12B B RR Pump Runback 20% E2 0 N/A N/A N/A CR04 Low-Flow Hi-Power Instability E5 0 80% 3 min N/A Loss of Power Startup Transformer E3 0 N/A N/A N/A ED05 ED07 Loss of Power Normal Transformer E3 0 N/A N/A N/A ED15 Loss of 12.5 KV power E3 0 N/A N/A N/A RR20B Coolant Leak inside the PC E3 2 min 70 15 N/A RC02 RCIC Turbine Trip E4 0 N/A N/A N/A D. Remotes None E. Overrides Instrument Tag Trigger TD Value Ramp RRMG A Scoop Tube lockout P/B ZDIRRMGSWS16A A N/A OFF N/A RRMG B Scoop Tube lockout P/B ZDIRRMGSWS16B A N/A OFF N/A PTM #31 RPS Scram Bypass Jumper ZDIRPSSCRM JA1 IN A N/A IN N/A PTM #32 RPS Scram Bypass Jumper ZDIRPSSCRM JA2 IN A N/A IN N/A PTM #33 RPS Scram Bypass Jumper ZDIRPSSCRM JB1 IN A N/A IN N/A PTM #34 RPS Scram Bypass Jumper ZDIRPSSCRM JB2 IN A N/A IN N/A Page 85 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Pre Events Allow the operators three to five minutes to review the panels and set up the controls and displays as they desire.

Event # 1: Start the A CRD Pump and place it in service. Secure the B CRD Pump.

ROLE PLAY:

As the AO in the CRD Room report you and a maintenance mechanic are standing by for the pump start.

ROLE PLAY:

Report the following:

• Suction valve full open.

• Minimum flow valve open.

• Discharge valve open.

Page 86 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient

• Pump and motor oil levels normal.

• Pump casing and suction filter vented.

ROLE PLAY:

From the CRD Pump room report that the A CRD Pump is operating normally.

Event #2: Power Reduction ROLE PLAY:

When the crew has placed the A CRD Pump in service and secured the B CRD Pump contact the Control Room as Doniphan and notify the CRS the Cooper south interface load has exceeded 1190 MVA and that an immediate load reduction of 100 Mwe is required.

Page 87 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Event #3: DEH Oil System Pressure Oscillation requires stopping power reduction.

ACTION: When directed by the Chief Examiner Activate Trigger E1: DEH Oil Pressure Oscillation ROLE PLAY:

Page 88 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient As SO sent to DEH area; report that the discharge relief valve is periodically lifting.

Report that there are no leaks.

When the standby pump has been started and the oscillating pump shutdown, report all conditions are normal.

NOTE:

Delete the malfunction when the B DEH Pump is secured Event #4: Recirculation Pump Runback to 20% with power oscillations.

ACTION: When directed by the Chief Examiner Activate Trigger E2: Recirculation Pump Runback ROLE PLAY:

Page 89 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient If contacted as Reactor Engineering, request the CRS to wait five minutes while you run some computer analysis to determine the correct rod sequence to use for a power reduction.

ACTION: After the CRS has determined the T.S. Entry (3.4.1) Active Trigger E5: Power Oscillations.

NOTE:

The LOOP and small break LOCA (LOCA is on a time delay and ramp) are automatically triggered by the Main Turbine Stop Valves leaving the full open position when the turbine is tripped following the reactor scram.

Event #5: Loss of Off-Site Power.

ROLE PLAY:

If sent to the Diesel Genrators as the SO to check the DGs report that they are operating normally.

Page 90 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Event #6: Small break LOCA resulting in an inability to restore RPV water level requiring Emergency Depressurization.

Event #7: RCIC fails to auto start then (when manually started) trips on high exhaust pressure.

Page 91 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient ACTION:

When the following conditions are reached, place the simulator in FREEZE.

• RPV Water level is being controlled above + 3.

• Drywell pressure is being maintained below 10 psig.

Page 92 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Page 93 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient imf rc01 imf ed06 imf hp11 imf tc04(1) imf rr12a(2) imf rr12b(2) imf cr04(2 2:00)80 3:00 Put this on a separate trigger (E5 and remove the TD) imf ed03b imf ed05(3) imf ed07(3) imf ed15(3) imf rr20b(3 2:00) 70 15:00 imf rc02(4)

Page 94 of 18

Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Operators: CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient IOR ZDIRPSSCRMJA1 IN IOR ZDIRPSSCRMJA2 IN IOR ZDIRPSSCRMJB1 IN IOR ZDIRPSSCRMJB2 IN ior zdirrmgsws16a off ior zdirrmgsws16b off trgset 3 "zlotcltsv1[2] == 1"

^set up trigger 3 to activate when the #1 TSV is closed Page 95 of 18

Turnover information Scenario 2 Plant Status:

1. The plant is operating at 100% power, near the end of the current cycle.

2. Rod Sequence Information: Step: 01 Rod: 26-27 Notch: 36

3. Tech. Spec. Limitations in effect:

Day 1 of 7 day LCO (3.8.1, condition A) due to Emergency Transformer being OOS for planned maintenance on 69KV line by OPPD. All associated surveillances are current.

4. Significant problems/abnormalities:

0.1 "A" CRD Pump was tagged out. The tags (Clearance) have been cleared and maintenance and an AO are standing by for a pump start to verify proper operation.

0.2 Emergency Transformer estimated return to service this shift.

5. Evolutions/maintenance for the on-coming shift:

- Start the A CRD Pump and if it is operating properly, place it in service and secure the B CRD Pump.

- OPPD expediting return of 69KV line due to weather.

Page 96 of 18

Turnover information Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Scenario Operators:

2 CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Page 97 of 18

Turnover information Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Scenario Operators:

2 CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Page 98 of 18

Turnover information Simulation Facility Cooper Nuclear Station Scenario No.: 3 Op Test No.:

Examiners: Scenario Operators:

2 CRS RO BOP Initial 100% Full Power Operation (EOC) (IC-20).

Conditions: Core Spray Pump B is out of service Turnover: See attached turnover sheet Event Event Position Event No. Type* Description Pre-insert N/A Five SRVs will NOT OPEN Pre-insert N/A Turbine Bypass Valves 1-3 will NOT OPEN Pre-insert N/A Failure of Group Six to automatically isolate 1 N CRS/BOP Shutdown SGT B and place it in a standby lineup.

2 C CRS/BOP 125 VDC Panel AA3 failure (Instrument power supplies) 3 R CRS/RO Power reduction for T.S. 3.0.3 required shutdown.

4 I CRS/RO Loss of Feedwater Master Controller, slowly failing low, requiring manual control of feedwater.

5 M Crew HPCI un-isolatable steam line leak (and trip of running feedwater pumps).

6 I Crew Failure of the auto isolation of Group 6.

7 C CRS/BOP Failure of the Turbine Bypass Valves to remain open and/or failure of up to five SRVs to open.

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Page 99 of 18