ML19239A361

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Proposed RO Admin JPMs
ML19239A361
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 08/23/2019
From: Joseph Demarshall
Operations Branch III
To:
FirstEnergy Nuclear Operating Co
demarshall j
Shared Package
ML17215A920 List:
References
Download: ML19239A361 (21)
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Text

OT-3701-ADM_001_RO Rev 0 1

JOB PERFORMANCE MEASURE SETUP SHEET System:

Administrative Time Critical:

No Applicability:

RO Administrative Topic: Conduct of Operations Validated Time:

13 Minutes Setting:

Classroom/Simulator

References:

PDB-I0002 Rev 8, PDB-I0003 Rev 17, PDB-I0018 Rev 3, & SOI-E31 Rev 8 Required Material:

PDB-I0002 - Transmitter To Trip Unit Cross Reference, PDB-I0003 - Trip Unit To Technical Specification Cross Reference PDB-I0018 - E31 Trip Instructions SOI-E31 - Leak Detection System Task:

035-519-04-01 Place a NUMAC Temperature Monitoring Channel in the Tripped/Untripped Condition 299-753-03-01 Determine Affected Trip Units or Indicators Associated with a Transmitter Task Standard:

Determine required actions for placing 1E31-N700A A2-3 in trip and determine components affected by placing unit in trip.

K/A:

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Importance: RO 4.4 / SRO 4.7 1.

Setup Instructions: If done in simulator, insert Malfunction pt01_1e31n0034a to 0.

2.

Location / Method: Classroom/ Simulator / Admin Performance 3.

Initial Condition: I&C personnel have reported that transmitter 1E31-N034A has failed low. The Unit Supervisor has determined that Tech Spec 3.3.6.1 Condition A is not met and the Required Action to place the channel in trip must be performed.

4.

Initiating Cue: Unit Supervisor directs you the Reactor Operator to determine the method for placing the instrument in trip to meet Technical Specification 3.3.6.1 Condition A and determine what components will isolate when channel is tripped.

Start:

Stop:

Candidate:

OT-3701-ADM_001_RO Rev 0 2

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 PDB-I0002 - Transmitter to Trip Unit Cross Reference Or PDB-I0003 - Trip Unit to Technical Specification Cross Reference Or PDB-I0018 - Instrument Failure Response Manual Trip Instructions Operator refers to one or more of the above PDBs to determine that the correct trip unit is NUMAC 1E31-N700A (A2-3)

Critical Step:

Operator determines that the correct trip unit is NUMAC 1E31-N700A (A2-3).

Instructor Cue:

None Notes:

Operator may also refer to a drawing to ascertain the correct trip unit.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_001_RO Rev 0 3

Step 2 PDB-I0018 - Instrument Failure Response Manual Trip Instructions Place TRIP UNIT in trip condition:

1)

Place 1E31-N700A in INOP.

2)

Press ETC to select menu layer containing MANUAL TRIP.

3)

Press MANUAL TRIP.

4)

Select Module/Input A2-3.

5)

Press TRIP.

6)

Press EXIT.

7)

Place 1E31-N700A in OPER.

Critical Step:

Operator determines the required actions to place channel in trip from PDB-I0018 page 65 or SOI-E31 - Leak Detection System, Section 7.4.

Instructor Cue:

None Notes:

PDB-I0018 and SOI-E31, Section 7.4 contain the same information.

However, the PDB is specific for this input module and the SOI is not specific.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_001_RO Rev 0 4

Step 3 PDB-I0018 - Instrument Failure Response Manual Trip Instructions

1)

De-energizes E31-N702A-K12 a)

Closes G33F039, G33F004 b)

Closes G33F034, G33F054 Critical Step:

Operator determines Division 1 RWCU isolation valves, 1G33-F004, 1G33-F034, 1G33-F039, and 1G33-F054 will close.

Instructor Cue:

None Notes:

Terminate the JPM SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue:

Candidate has determined required actions for placing 1E31-N700A (A2-3) in trip and has identified components affected by placing unit in trip.

Evaluation Results: SAT_____

UNSAT_____

End Time:

OT-3701-ADM_001_RO Rev 0 5

JPM CUE SHEET INITIAL CONDITIONS:

  • I&C personnel have reported that transmitter 1E31-N034A has failed low.
  • The Unit Supervisor has determined that Tech Spec 3.3.6.1 Condition A is not met and the Required Action to place the channel in trip must be performed.

INITIATING CUE:

  • Unit Supervisor directs you the Reactor Operator to determine the method for placing the instrument in trip to meet Technical Specification 3.3.6.1 Condition A and;
  • Determine what components will isolate when channel is tripped.

OT-3701-ADM_005-RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:

Administrative Time Critical:

No Alternate Path:

No Applicability:

RO/SRO Admin Topic:

Conduct of Operations Validated Time:

25 Minutes

References:

ONI-E12-2 Rev. 40, PDB-A019 Rev. 8, PDB-A017 Rev. 11, & PDB-A016 Rev. 16 Required Material:

ONI-E12-2, Loss of Decay Heat Removal PDB-A019, Time to Core Uncovery Curves PDB-A017, Pool Heatup Curves PDB-A016, Decay Heat Curve Task:

299-827-01-01 Demonstrate the Use of PDB Entries in Tabs A, B, C, D, E, F, G, H, and T Task Standard:

Determine Time to Boil and Time to Core Uncovery.

K/A:

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. Importance: RO 3.9 SRO 4.2 1.

Setup: Provide color copies of PDB-A016, A017, & A019 and ONI-E12-2 and a ruler.

2.

Location / Method: Class Room / Administrative performance.

3.

Initial Condition: It is day 20 of Refueling Outage 16. Reactor vessel reassembly is in progress after refueling was completed. Current Reactor level is being maintained near the vessel flange for setting the vessel head. RHR B Loop is in Shutdown Cooling maintaining water temperature at 90 °F. The backup decay heat removal system became unavailable. No alternate decay heat removal systems are in service or currently available.

4.

Initiating Cue: The Shift Manager directs you to perform the following in the event of a loss of Shutdown Cooling.:

1) Calculate Time to Boil per ONI-E12-2 Loss OF Decay Heat Removal Step 4.6.7.
2) Determine Time to Core Uncovery.

Start:

Stop:

Candidate:

OT-3701-ADM_005-RO 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 ONI-E12-2, Loss of Decay Heat Removal 4.0 SUPPLEMENTAL ACTIONS 4.6 IF a loss of reactor decay heat removal has occurred, THEN PERFORM the following:

4.6.7 IF in MODE 5 or At All Times, THEN REFER TO the Perry Work Implementation Schedule (PWIS) OR PDB-A0017 and DETERMINE estimated time to boil.

Standard:

Obtains and reviews PDB-A0017.

Instructor Cue:

If asked, the PWIS is not available.

Notes:

When Candidate identifies the correct PDB, provide him with a copy.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 2 Determine PDB-A0016 and PDB-A0019 are also needed.

Standard:

Determines that PDB-A0016 and PDB-A0019 are also needed.

Instructor Cue:

None Notes:

When Candidate identifies the correct PDBs, provide him with a copy.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_005-RO Rev 0 Step 3 Determine Time to Boil.

Critical Step:

Using PDB-A016 p 6 and PDB-A017 p 9 Candidate determines Time To Boil is 7.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.

Instructor Cue:

None Notes:

Candidate should determine approximately 17.0 Mlbm/hr using PDB-A016 Because of graph readability, 7.0 to 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> is acceptable.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 4 Determine Time To Core Uncovery.

Critical Step:

Using PDB-A016 p 6 and PDB-A019 p 9 Candidate determines Time To Core Uncovery is approximately 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br />.

Instructor Cue:

None Notes:

Due to readability of the graph, 37-39 hours is acceptable.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Determines Time to Boil and Time to Core Uncovery.

Evaluation Results:

SAT_____

UNSAT_____

End Time

OT-3701-ADM_005-RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

  • It is day 20 of Refueling Outage 16.
  • Reactor vessel reassembly is in progress after refueling was completed.
  • Current Reactor level is being maintained near the vessel flange for setting the vessel head.

INITIATING CUE:

The Shift Manager directs you to perform the following in the event of a loss of Shutdown Cooling.:

1) Calculate Time to Boil per ONI-E12-2 Loss OF Decay Heat Removal Step 4.6.7.
2) Determine Time to Core Uncovery.

OT-3701-ADM_033-RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:

Administrative Time Critical:

No Alternate Path:

No Applicability:

RO/SRO Admin Topic:

Equipment Control Validated Time:

8 Minutes

References:

DWG 302-243 Rev. HH & DWG 302-081 Rev. NNN Required Material:

DWG 302-243, Instrument Air Task:

398-502-01-05 Interpret System Piping, Physical Layout, and Electrical Drawings (Ability to use drawings to generate tagouts, MFI/LLJ's.)

Task Standard:

Determine isolation boundary for Instrument Air leak.

K/A:

2.2.41 - Ability to obtain and interpret station electrical and mechanical drawings. Importance RO 3.5 SRO 3.9 1.

Setup: Provide package of support drawings and have ONI-P52 available upon request.

2.

Location / Method: Class Room / Administrative performance.

3.

Initial Condition: The Turbine Tour rounds taker reports an Instrument Air leak on the line going in to 1N27-F305, RFBP RCIRC VALVE in the Heater Bay.

4.

Initiating Cue: The Unit Supervisor directs you, a Reactor Operator, to identify the minimum isolation boundary to stop the leak on 1N27-F305 without affecting other components.

Start:

Stop:

Candidate:

OT-3701-ADM_033-RO 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 Evaluate Leak Isolation, Drawing 302-243, Instrument Air.

Critical Step:

Candidate reviews 302-243 and determines that Instrument Air valve P52-F1405 must be closed.

Instructor Cue:

None Notes:

JPM Steps 1 & 2 can be performed in any order.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 2 Evaluate Leak Isolation, Drawing 302-243, Instrument Air.

Critical Step:

Candidate reviews 302-243 and determines that Instrument Air valve P52-F1404 or P52-F1403 must be closed.

Instructor Cue:

None Notes:

JPM Steps 1 & 2 can be performed in any order.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_033-RO Rev 0 Terminating Cue: Determines Instrument Air valves P52-F1405 and either P52-F1404 or P52-F1403 must be closed to isolate air to 1N27-F305.

Evaluation Results:

SAT_____

UNSAT_____

End Time

OT-3701-ADM_033-RO Rev 0 Leaking Valve Drawing 302-043 (partial_

OT-3701-ADM_033-RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

The Turbine Tour rounds taker reports an Instrument Air leak on the line going in to 1N27-F305, RFBP RCIRC VALVE in the Heater Bay.

INITIATING CUE:

The Unit Supervisor directs you, a Reactor Operator, to identify the minimum isolation boundary to stop the leak on 1N27-F305 without affecting other components.

OT-3701-ADM_019_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:

Administrative Time Critical:

No Alternate Path:

No Applicability:

RO/ SRO Safety Function:

Radiation Control Validated Time:

14 Minutes

References:

Dwg 304-625 Rev J VSDS IB-599 Survey Map Required Material:

IB-599 Survey Map, Calculator Task:

299-502-03-01 Maintain Radiation Exposure as Low as Reasonably Achievable (ALARA) 299-848-01-01 Comply with the Administrative Requirements for the Perry Plant Radiation Dose Control Program Task Standard:

Determine radiological conditions and calculate dose.

K/A:

2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. Importance: RO 3.5 SRO 3.6 1.

Simulator Setup: N/A 2.

Location / Method: Class Room / Administrative performance.

3.

Initial Condition: While investigating a leak in the FPCC Heat Exchanger Room, an NLO became incapacitated against the east wall near the A HX. He is unable to move.

Another NLO was unable to move him but stated that he is directly below the P42-F440 valve. The NLO has suffered unknown injuries. You and a Fire Brigade member will stabilize and rescue the NLO.

4.

Initiating Cue: Review the survey map for the FPCC HX Room and determine the following using the most direct route to get to the injured person:

1.

What is the highest contamination level?

2.

What is the highest contact radiation level?

3.

What is the highest general area dose rate level?

4 What is the estimated dose if it takes you 8 minutes to stabilize and prepare to remove the NLO? (Disregard dose for traveling to and from door to the NLO.)

Start:

Stop:

Candidate:

OT-3701-ADM_019_RO 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 highest contamination level on travel route.

Critical Step:

Determines the highest contamination level is 5000 DPM/100 cm2 at smear location 3.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 2 Determine the highest contact radiation level.

Critical Step:

Determines the highest contact radiation level is 80 mr/hr at DR-7.

Instructor Cue:

None Notes:

The contact dose readings are lower than the 30 cm readings due to the 30 cm reading being taken closer to the HX.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_019_RO Rev 0 Step 3 Determine the highest general area dose rate level.

Critical Step:

Determines the highest general area dose rate level is 350 mr/hr at DR-5.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 4 Determine the estimated dose to stabilize and prepare to remove the incapacitated NLO.

Critical Step:

Calculates the dose to stabilize and prepare to remove NLO.

Instructor Cue:

None Notes:

Dose 30 cm from P42-F440 is 100 mr/hr @ 8 min = 13.3 mr each.

(13 to 14 mr is acceptable)

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Determines highest contamination level, contact dose rate, general area dose, and dose received.

Evaluation Results:

SAT_____

UNSAT_____

End Time

OT-3701-ADM_019_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

While investigating a leak in the FPCC Heat Exchanger Room, an NLO became incapacitated against the east wall near the A HX.

He is unable to move.

Another NLO was unable to move him but stated that he is directly below the P42-F440 valve.

The NLO has suffered unknown injuries.

You and a Fire Brigade member will stabilize and rescue the NLO.

INITIATING CUE:

Review the survey map for the FPCC HX Room and determine the following using the most direct route to get to the injured person:

1.

What is the highest contamination level?

2.

What is the highest contact radiation level?

3.

What is the highest general area dose rate level?

4 What is the estimated dose if it takes you 8 minutes to stabilize and prepare to remove the NLO? (Disregard dose for traveling to and from door to the NLO.)

Handout - page 1 of 3

P42-F0440 P42-F0380 Scaffold X Brace directly in front of HX Handout - page 2 of 3

Handout - page 3 of 3

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