Text

Initial License Exam, Proposed Admin JPMs
	ML100601289
Person / Time
Site:	Perry
Issue date:	01/12/2009
From:	Walton R; Operations Branch III
To:	; FirstEnergy Nuclear Operating Co
References
	OT-3701-ADM_02RO, Rev 0
	Download: ML100601289 (47)
	v • d • e

OT-3701-ADM_02RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO Safety Function: Conduct of Operations Setting: Classroom, New Validated: 10 minutes

References:

NOP-LP-1002 Rev 9 Tasks: Evaluate proposed work schedule against established overtime guidelines Task #: 299-893-03-01 K / A Data: 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

1. Instructions: NA

2. Location / Method: Class Room / Administrative performance.

3. Initial Condition: The Plant is operating at 100% power. Operations section shift manning is being severely affected due to a flu outbreak. All healthy Reactor Operators are being scheduled to work extra hours in order to cover the shifts. Listed below is your proposed work schedule for the next ten days.

Note: All Work hours shown excludes turnover time.

Sun Mon Tues Wed Thu Fri Sat Sun Mon Tues 1/11 1/12 1/13 1/14 1/15 1/16 1/18 1/19 1/20 1/21 Off Off 12-24 12-24 12-24 12-24 14-22 07-19 Off 07-19

4. Initiating Cue: As a Reactor Operator, determine if you can work the proposed schedule without any additional authorization.

OT-3701-ADM_02RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: The Plant is operating at 100% power. Operations section shift manning is being severely affected due to a flu outbreak. All healthy Reactor Operators are being scheduled to work extra hours in order to cover the shifts. Listed below is your proposed work schedule for the next ten days.

Note: All Work hours shown excludes turnover time.

Sun Mon Tues Wed Thu Fri Sat Sun Mon Tues 1/11 1/12 1/13 1/14 1/15 1/16 1/18 1/19 1/20 1/21 Off Off 12-24 12-24 12-24 12-24 14-22 7-19 Off 7-19 INITIATING CUE: As a Reactor Operator, determine if you can work the proposed schedule without any additional authorization.

OT-3701-ADM_02RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 4.15.4 The limits and controls placed on working hours are applicable to all plant and contractor personnel with the exception of the FENOC Executive Leadership Team (ELT). Working hours shall be controlled as specified in each plants licensing documents, and may be supplemented as directed by site management.

1. An individual should not work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover or travel time).

2. An individual should not work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, or 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period (excluding shift turnover or travel time).

3. A break of at least eight hours should be allowed between work periods. (Shift turnover time should not be part of the eight hour break period.)

4. Except during extended shutdown periods, the use of excessive working hours should be considered on an individual basis and not for the entire staff or crew on shift.

5. The crew performing fuel loading operations should not normally be expected to work more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months out of each 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period when scheduled for consecutive daily duty.

4.15.5 Deviation from the above guidelines shall normally not be required during times when the plant is operating and adequate shift coverage is available. Exceptions to this policy may include a Limiting Condition for Operation (LCO), Emergency Plan activation or callout, or other significant need to maintain safe plant operation, to maintain shift complement, or maintain production capability.

OT-3701-ADM_02RO Rev 0 Standard: Evaluates the proposed schedule Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 2 Determines he will need a need Technical Specification Working Hour Deviation request.

Critical Step: Determines he will need a need Technical Specification Working Hour Deviation request.

Instructor Cue: Question candidate on which working hour guideline he fails to meet.

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 3 Candidate determines which working hour guideline he fails to meet.

Critical Step: Determines he will exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period. From Friday to Sunday. From Noon on Tuesday until Noon on the next Tuesday will exceed 72 in 7 days.

Instructor Cue: None Notes: From Noon on Friday to Noon on Sunday, or from 1900 on Friday to 1900 on Sunday.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Terminating Cue: Candidate determines that a Technical Specification Overtime Deviation request is required for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period or &2 hours in a 7 Day period.

Evaluation Results: SAT_____ UNSAT_____

OT-3701-ADM_10 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO Safety Function: Conduct of Operations Setting: Control Room or Simulator, New Validated: 15 minutes

References:

SVI-B33-T1160 Revision 5 Tasks: Perform SVI-B33-T1160 Task #: 283-507-01-01 K / A Data: 2.1.19 Ability to use plant computers to evaluate system or component status.

1. Instructions: If performing in the Control Room ensure Reactor Power is greater than 25%. If in simulator any IC with power greater than 25%.

2. Location / Method: Control Room or Simulator / Administrative performance.

3. Initial Condition: Reactor Power has been greater then 25% for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . All other conditions are as found.

4. Initiating Cue: Perform SVI-B33-T1160 for daily surveillance requirement.

OT-3701-ADM_10 Rev 0 JPM CUE SHEET INITIAL CONDITIONS: Reactor Power has been greater then 25% for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . All other conditions are as found.

INITIATING CUE: Perform SVI-B33-T1160 for daily surveillance requirement.

OT-3701-ADM_10 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 4.0 PREREQUISITES

1. Mark the Unit Supervisors Authorization to Start Prerequisites signature N/A on the Data Package Cover Sheet (DPCS) and initial.

2. Confirm that the plant is operating in MODE 1 with THERMAL POWER > 25% RTP.

3. Confirm that the recirculation flow is steady; and indicate the configuration of the recirculation loops:

a. Loop A (only) in operation, with recirculation flow control in loop manual.

b. Loop B (only) in operation, with recirculation flow control in loop manual.

c. Both recirculation loops in fast speed operation, with recirculation loop jet pump flow mismatch within the limits of SR 3.4.1.1.

d. Both recirculation loops in slow speed operation, with recirculation loop jet pump flow mismatch within the limits of SR 3.4.1.1.

4. When using plant computer points or ICS SDS screens, verify no other maintenance or testing is in progress which would affect recirculation flow indication.

Critical Step: Marks the correct Recirculation configuration will be either C or D.

Instructor No other maintenance or testing is in progress which would affect recirculation Cue: flow indication Notes: If in Control Room will have to verify with Reactor Operator that no other testing or maintenance is in progress.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_10 Rev 0 Step 2 5.0 SURVEILLANCE INSTRUCTION 5.1 Surveillance Test

1. Notify the Reactor Operator before starting and write R.O. (operators name) notified in the Authorization to Start Test signature on the DPCS. Record the time and date and initial the line.

5.1.1 Recirculation Loop Drive Flow vs. FCV Position

1. Determine the relationship between each operating recirculation loop drive flow and the corresponding flow control valve position, and indicate the method used.

If using ICS SDS, attach a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., RFPERF for two loop

- fast speed, or RSPERF for two loop - slow speed); otherwise, complete Attachment 1, Manual Recirculation Loop Drive Flow vs. FCV Position.

[ ] SDS Screen [ ] Attachment 1 Critical Step: Prints either RFPERF or RSPERF from SDS Instructor None Cue:

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_10 Rev 0 Step 3

2. Indicate, for each operating loop, whether the relationship determined in Step 5.1.1.1 is within the appropriate established pattern.

-- If using ICS SDS, observe cursor is within limits for the DRIVE FLOW A VS.

FCV A and/or for the DRIVE FLOW B VS. FCV B; otherwise, refer to Step 3 on Attachment 1.

a. Loop A: [ ] YES [ ] NO [ ] N/A

b. Loop B: [ ] YES [ ] NO [ ] N/A Critical Step: Loop A and B checked Yes Instructor None Cue:

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 4 5.1.2 Recirculation Loop Drive Flow vs. Total Core Flow

1. Determine the relationship between recirculation loop drive flow and total core flow, and indicate the method used.

-- If using ICS SDS, attach a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., RFPERF for two loop

- fast speed, or RSPERF for two loop - slow speed); otherwise, complete Attachment 2, Manual Recirculation Loop Drive Flow vs. Total Core Flow.

[ ] SDS Screen [ ] Attachment 2 Standard: SDS Screen Print previously obtained Instructor None Cue:

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_10 Rev 0 Step 5

2. Indicate whether the relationship determined in Step 5.1.2.1 is within the appropriate established pattern.

-- If using ICS SDS, observe cursor is within limits for the DRIVE FLOW VS.

CORE FLOW; otherwise, refer to Step 3 on Attachment 2.

[ ] YES [ ] NO Critical Step: checks Yes Instructor None Cue:

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_10 Rev 0 Step 6 5.1.3 Jet Pump Differential Pressure and Flow NOTE 1: It is not necessary to satisfy both Section 5.1.3.1 and Section 5.1.3.2. The preferred method is contained in Section 5.1.3.1. The unnecessary section may be marked N/A.

1. Jet Pump Differential Pressure

a. Determine each normalized jet pump diffuser to lower plenum differential pressure for each operating recirculation loop, and indicate the method used.

-- If using ICS SDS, attach a copy of the JPDP screen; otherwise, complete Attachment 3, Normalized Jet Pump dPs Data Sheet.

[ ] SDS Screen [ ] Attachment 3

b. Indicate whether the relationship determined in Step 5.1.3.1.a is within the appropriate established pattern.

-- If using ICS SDS, observe NORMAL indication for the JET PUMP DPS; otherwise, refer to Step 6 on Attachment 3.

[ ] YES [ ] NO [ ] N/A Critical Step: Prints copy of JPDP screen and checks Yes Instructor None Cue:

Notes: Should perform this section it is preferred SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_10 Rev 0 Step 7

2. Jet Pump Differential Flow

a. Determine each normalized jet pump flow for each operating recirculation loop, and indicate the method used.

-- If using ICS SDS, attach a copy of the JPFLOW screen; otherwise, complete Attachment 4, Normalized Jet Pump Flows Data Sheet.

[ ] SDS screen [ ] Attachment 4

b. Indicate whether the relationship determined in Step 5.1.3.2.a is within the appropriate established pattern.

-- If using ICS SDS, observe NORMAL indication for the JET PUMP FLOWS; otherwise, refer to Step 7 on Attachment 4.

[ ] YES [ ] NO [ ] N/A Standard: Section is NA, Marks as NA Instructor None Cue:

Notes: Should perform section 1 and skip this section SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_10 Rev 0 Step 8 5.2 Plant/System Restoration None 5.3 Acceptance Criteria NOTE 1: Satisfactory completion of this surveillance shall be based only on Technical Specification items (marked with a $ sign).

$ 1. The jet pumps, in each operating recirculation loop, have been demonstrated OPERABLE by one of the following two methods:

a. At least two of the following three criteria have been satisfied:

1) Recirculation loop drive flow versus flow control valve position differs by 10% from established patterns. (YES in Step 5.1.1.2)

2) Recirculation loop drive flow versus total core flow differs by 10%

from established patterns. (YES in Step 5.1.2.2)

3) Either each jet pump diffuser to lower plenum differential pressure differs by 20% from established patterns, or each jet pump flow differs by 10% from established patterns. (YES in either Step 5.1.3.1.b or Step 5.1.3.2.b)

[ ] YES [ ] NO, U.S. notified [ ] N/A If step 5.3.1.a is marked NO, consider the applicability of step 5.3.1.b; otherwise mark the signature line in step 5.3.1.b N/A.

Critical Step: checks Yes Instructor None Cue:

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_10 Rev 0 Step 9

b. While baselining the new established patterns, the Shift Engineer (SE), or the Responsible System Engineer (RSE), or a Reactor Engineer (RE) has reviewed the surveillance results and has determined, based upon engineering judgment, that no significant abnormality exists that could indicate a jet pump failure.

___________________________________________/________

SE, RSE, or RE Signature Date

2. All other items checked in this surveillance performed satisfactorily.

[ ] YES [ ] NO, applicable Supervisor notified

3. Check the appropriate block on the Data Package Cover Sheet to indicate acceptable or unacceptable test results.

Critical Step: Checks FULL and ACCEPTABLE for Technical Specification Data on the Data Package Cover Sheet to indicate acceptable performance.

Instructor Not baselining new established patterns.

Cue:

Notes: b. is NA, 2. should be checked yes SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Terminating Cue: SVI-B33-T1160 completed satisfactorily.

Evaluation Results: SAT_____ UNSAT_____

OT-3701-ADM_21 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO Safety Function: Equipment Control Setting: Classroom, New Validated: 30 minutes

References:

NOP-OP-1001, 302-0081, and 208-149 Tasks: Determine tagging boundary for RFBP B.

Task #: 299-925-03-01 K / A Data: 2.2.13 Knowledge of tagging and clearance procedures.

1. Instructions: None

2. Location / Method: Class Room / Administrative performance.

3. Initial Condition: Reactor Feed Booster Pump B, 1N27-C001B, experienced a pump seal failure. The pump has been shutdown in accordance with SOI-N27, Section 6.8.

4. Initiating Cue: The Unit Supervisor directs you, as the Reactor Operator, to identify all of the components and tags required, including their required positions, for a Clearance that will isolate Reactor Feed Booster Pump B in preparation to repair the pump seal. The Clearance itself is not required to be generated OT-3701-ADM_21 Rev 0 JPM CUE SHEET INITIAL CONDITIONS: Reactor Feed Booster Pump B, 1N27-C001B, experienced a pump seal failure. The pump has been shutdown in accordance with SOI-N27, Section 6.8.

INITIATING CUE: The Unit Supervisor directs you, as the Reactor Operator, to identify all of the components and tags required, including their required positions, for a Clearance that will isolate Reactor Feed Booster Pump B in preparation to repair the pump seal. The Clearance itself is not required to be generated OT-3701-ADM_21 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Determines isolation boundary Standard: 1N27-F050B RFBP B Discharge Valve, Closed with Yellow Tag on control switch on P680 Instructor Cue: None Notes: Vent and drain boundary valves may be identified but are not critical.

TBCC to RFBP B motor valves may be identified not critical.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 2 Determines isolation boundary Critical Step: 1N27-F050B RFBP B Discharge Valve, Red Tag on handwheel Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_21 Rev 0 Step 3 Determines isolation boundary Critical Step: Open and Red Tag disconnect F1B06-W for 1N27-F050B Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 4 Determines isolation boundary Standard: 1N27-F015B RFBP B Suction Valve, Closed with Yellow Tag on control switch at local control panel Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 5 Determines isolation boundary Critical Step: 1N27-F015B RFBP B Suction Valve, Red Tag on handwheel Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_21 Rev 0 Step 6 Determines isolation boundary Critical Step: Open and Red Tag disconnect F1B06-U for 1N27-F015B Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 7 Determines isolation boundary Critical Step: 1N27-F503B RFBP B Casing Warmup Isolation Valve, Closed with Red Tag on handwheel Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 8 Determines isolation boundary Standard: 1N27-C001B RFBP B, Off with Yellow Tag on control switch on P680.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_21 Rev 0 Step 9 Determines isolation boundary Critical Step: Breaker H1208 Racked Out with Red Tag, 1N27-C001B RFBP B Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 10 Determines isolation boundary Critical Step: 1P12-F606B RFBP B Seal Cooling Water Supply Valve, Closed with Red Tag on handwheel Instructor Cue: None Notes: Vent and drain boundary valves may be identified but are not critical.

TBCC to RFBP B motor valves may be identified not critical.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Terminating Cue: Determines the required components to isolate RFBP B.

Evaluation Results: SAT_____ UNSAT_____

OT-3701-ADM_09RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO Safety Function: Radiation Control Setting: Classroom, New Validated: 20 minutes

References:

HPI-B003 Revision 19 Tasks: Determine if you as an Operator can perform an emergency evolution due to radiation levels.

Task #: 299-848-01-01 K / A Data: 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions.

1. Instructions: NA

2. Location / Method: Class Room / Administrative performance.

3. Initial Condition: The plant is in a General Emergency. No facilities are currently activated and Emergency Coordinator duties remain in the Control Room. You have volunteered to stop a large off-site release, by manually closing 1G33-F004 RWCU SUCT FM CNTMT OTBD ISOL Valve. Radiation Protection Supervision has informed you that travel path dose rates are 10 REM/hr to the valve in question and 50 REM/hr at the valve. It is estimated that you will take 15 minutes of total travel time to and from the valve and take 30 minutes to close the valve. You have been briefed to the radiological hazards.

4. Initiating Cue: As the Operator who has volunteered to close 1G33-F004 RWCU SUCT FM CNTMT OTBD ISOL Valve are you permitted to perform this evolution due to the radiation dose levels and whose authorization is required if you are permitted.

OT-3701-ADM_09RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: The plant is in a General Emergency. No facilities are currently activated and Emergency Coordinator duties remain in the Control Room. You have volunteered to stop a large off-site release, by manually closing 1G33-F004 RWCU SUCT FM CNTMT OTBD ISOL Valve. Radiation Protection Supervision has informed you that travel path dose rates are 10 REM/hr to the valve in question and 50 REM/hr at the valve. It is estimated that you will take 15 minutes of total travel time to and from the valve and take 30 minutes to close the valve. You have been briefed to the radiological hazards.

INITIATING CUE: As the Operator who has volunteered to close 1G33-F004 RWCU SUCT FM CNTMT OTBD ISOL Valve are you permitted to perform this evolution due to the radiation dose levels and whose authorization is required if you are permitted.

OT-3701-ADM_09RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Determine the radiation dose that he will receive.

Critical Step: Determines he will receive 27.5 REM Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 2 Determines that he may receive greater than 25 REM to protect large populations.

Critical Step: Determines that he can receive the estimated 27.5 REM.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_09RO Rev 0 Step 3 Identifies that the Shift Manager may authorize the dose.

Critical Step: Determines that the Shift Manager can authorize the Emergency Dose Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Terminating Cue: Determines he may receive in excess of 25 REM and that the Operations Shift Manager may authorize the Emergency Dose.

Evaluation Results: SAT_____ UNSAT_____

OT-3701-ADM_02SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: SRO Safety Function: Conduct of Operations Setting: Classroom, New Validated: 15 minutes

References:

NOP-LP-1002 Rev 9 Tasks: Evaluate proposed work schedule against established overtime guidelines Task #: 343-710-03-02 K / A Data: 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

1. Instructions: NA

2. Location / Method: Class Room / Administrative performance.

3. Initial Condition: The Plant is operating at 100% power. You are the Unit Supervisor for Crew 2. Two Reactor Operators from your crew are needed to work a 12-hour overtime assignment on Sunday (1/18) from 0800 to 2000, due to a flu outbreak. It is not expected that any of the Reactor Operators who work on Sunday will work the following Monday (1/19). Listed below is the current work schedule for the three Reactor Operators on your crew. Note: All Work hours shown excludes turnover time.

Sun Mon Tues Wed Thu Fri Sat 1/11 1/12 1/13 1/14 1/15 1/16 1/18 Off 08-20 08-20 08-16 08-20 08-20 08-20 Dan Off 08-16 08-20 08-20 08-16 08-16 08-16 Guy Off 08-20 08-16 08-20 08-20 Off 08-24 Tim

4. Initiating Cue: Determine which Reactor Operator(s) can work the proposed overtime without any additional authorization and complete any form(s) required in order to fill the two overtime assignments. Note: No split shifts will be worked OT-3701-ADM_02SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: The Plant is operating at 100% power. You are the Unit Supervisor for Crew 2. Two Reactor Operators from your crew are needed to work a 12-hour overtime assignment on Sunday (1/18) from 0800 to 2000, due to a flu outbreak. It is not expected that any of the Reactor Operators who work on Sunday will work the following Monday (1/19). Listed below is the current work schedule for the three Reactor Operators on your crew.

Note: All Work hours shown excludes turnover time.

Sun Mon Tues Wed Thu Fri Sat 1/11 1/12 1/13 /14 1/15 1/16 1/18 Off 08-20 08-20 08-16 08-20 08-20 08-20 Dan Off 08-16 08-20 08-20 08-16 08-16 08-16 Guy Off 08-20 08-16 08-20 08-20 Off 08-24 Tim INITIATING CUE: Determine which Reactor Operator(s) can work the proposed overtime without any additional authorization and complete any form(s) required in order to fill the two overtime assignments.

Note: No split shifts will be worked OT-3701-ADM_02SRO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.