Text

2021 Perry Ile Administered Walkthrough JPMs-Final
	ML22165A325
Person / Time
Site:	Perry
Issue date:	02/19/2021
From:	Randy Baker; NRC/RGN-III/DRS/OLB
To:	;
	Baker R
Shared Package
ML20136A294	List: ML22165A325; ML22165A326; ML22165A327;
References
	Download: ML22165A325 (242)
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OT-3701-ADM_034_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Setting: Classroom Applicability: RO/SRO Admin Topic: Conduct of Operations Validated Time: 10 Minutes

References:

PRI-TSR Rev. 44 Required Material: PRI-TSR, Technical Specification Rounds Task: 299-584-03-01 Comply with the Requirements of Shift Round Sheets, Logs, and Records Task Standard: Calculate DW Average Temperature IAW TS Rounds and identify any required actions.

K/A: 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. Importance RO 3.6 SRO 3.8

1. Setup Instructions: Provide Candidate completed PRI-TSR page 37 and blank page 57.

2. Location / Method: Classroom / Administrative Performance

3. Initial Condition: Plant is operating at power. NCC was isolated to the Drywell and has not been able to be restored. Annunciator DW RECORDER TEMPERATURE HIGH/LOW has alarmed. Drywell temperatures have been recorded IAW PRI-TSR, Tech Spec Rounds.

4. Initiating Cue: Unit Supervisor directs you, the Balance of Plant Operator, to calculate and record Average DW temperature, IAW PRI-TSR, and identify any required actions.

Start: Stop:

Candidate:

OT-3701-ADM_034_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 PRI-TSR, Technical Specification Rounds Review Tech Spec Rounds Sheet 11 of 42 Standard: Candidate reviews recorded DW temperatures and determines Item 78 (Sheet 31 of 42) must be filled in to calculate Average DW temp.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 2 Calculate Upper DW temperature.

Critical Step Standard: Candidate calculates Upper DW temperature to be 161 °F.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_034_RO Rev 0 Step 3 Calculate Middle DW temperature.

Critical Step Standard: Candidate calculates Middle DW temperature to be 149 °F.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 4 Calculate Lower DW temperature.

Critical Step Standard: Candidate calculates Lower DW temperature to be 127 °F.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_034_RO Rev 0 Step 5 Calculate Average DW temperature.

Critical Step Standard: Candidate calculates Average DW temperature to be >145 °F and informs US of entry condition to EOP-02, Primary Containment Control.

Instructor Cue: None Notes: The Average temperatures of each of the 3 levels of the DW must be calculated first then the average of the averages is calculated.

If all temperatures are averaged together, the result will be 143 °F and Candidate will miss the EOP-02 entry condition.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Average Drywell temperature was calculated and entry condition to EOP-02 was identified.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_034_RO Rev 0 JPM CUE SHEET INITIAL

Plant is operating at power.

CONDITIONS:

NCC was isolated to the Drywell and has not been able to be restored.

Annunciator DW RECORDER TEMPERATURE HIGH/LOW has alarmed.

Drywell temperatures have been recorded IAW PRI-TSR, Tech Spec Rounds.

INITIATING CUE: Unit Supervisor directs you, the Balance of Plant Operator, to calculate and record Average DW temperature, IAW PRI-TSR, and identify any required actions.

PRI-TSR Rev. 44 Attachment 5 Sheet 11 of 42 Page: 37 MODES 1, 2 & 3 SHEET 11 WEEK OF :___________________________ TSR-MODES 1,2&3-11 TECHNICAL SPECIFICATION ROUNDS Rev. 1-20-2020 R U MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY SATURDAY SUNDAY I

E N T PANEL OR PARAMETER/

Q I D M D M D M D M D M D M D M E ORIGIN INSTRUMENT M T A I A I A I A I A I A I A I M

T S Y D Y D Y D Y D Y D Y D Y D DRYWELL TEMPERATURE Containment Upper Pool level is used in Item 78.

1D23-R090A-16 ITEM F 155 (ELEV (1D23-N100A) #78 653) 1D23-R090B-16 ITEM F 161 (1D23-N100B) #78 1H13-P883 1M13-R110-2 ITEM F 175 (1M13-N041) #78 1H13-P800 1M13-R110-16 ITEM F 153 (1M13-N083) #78 1D23-R090A-17 ITEM (1D23-N110A) #78 F 144 1D23-R090B-17 ITEM (1D23-N110B) #78 F 143 (ELEV 634 to 640) 1M13-R110-3 ITEM (1M13-N042) #78 F 154 1H13-P883 1M13-R110-4 ITEM (1M13-N043) #78 F 145 23 1H13-P800 1M13-R110-14 ITEM F 148 (1M13-N081) #78 1M13-R110-15 ITEM F 158 (1M13-N082) #78 1D23-R090A-18 ITEM F 135 (1D23-N120A) #78 1D23-R090B-18 ITEM F 135 (1D23-N120B) #78 (ELEV 604 1M13-R110-5 ITEM F 109 to 609) (1M13-N044) #78 1M13-R110-7 ITEM F 133 1H13-P883 (1M13-N051) #78 1M13-R110-8 ITEM 1H13-P800 F 132 (1M13-N052) #78 1M13-R110-11 ITEM F 113 (1M13-N070) #78 1M13-R110-12 ITEM F 133 (1M13-N071) #78

PRI-TSR Rev. 44 Attachment 5 Sheet 31 of 42 Page: 57 MODES 1, 2 & 3 SHEET 31 WEEK OF :___________________________ TSR-MODES 1,2&3-31 TECHNICAL SPECIFICATION ROUNDS Rev. 1-20-2020 R U MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY SATURDAY SUNDAY I

E N T PANEL OR PARAMETER/

Q I D M D M D M D M D M D M D M E ORIGIN INSTRUMENT M T A I A I A I A I A I A I A I M

T S Y D Y D Y D Y D Y D Y D Y D Average the Suppression Pool Level using the suppression pool level readings from Item 16.

SUPP POOL LEVEL NOTE: The normally required frequency of daily is changed to shifty in Mode 3 when Upper Containment Pools are drained.

SUPR POOL LVL CALCULATE FT.

AVERAGED Average the DW/CNTMT differential pressure readings from Item 17 & obtain the Supr Pl Correction Factor from the Suppression Pool Level Correction chart (Figure 3).

Note: The normally required frequency of daily is changed to shifty in Mode 3 when Upper Containment Pools are drained.

SUPR PL CALCULATE CORRECTION FT.

77 FACTOR Subtract the Supr Pl Correction Factor from the Supr Pool Lvl Averaged reading to obtain the Supp Pool Avg Level Corrected.

Verify that the corrected Supp Pool Level is one of the following:

- Between 17.8 and 18.5, Dryer Storage / Reactor Well Gate Removed

- 18.3, Dryer Storage / Reactor Well Gate Installed

- Mode 3 within the limits of Figure 4, Upper Containment And Suppression Pool Levels NOTE: The normally required frequency of daily is changed to shifty in Mode 3 when Upper Containment Pools are drained.

SUPR POOL SEE CALCULATE AVG LVL FT.

NOTE CORRECTED Using the readings from Item 23, calculate the arithmetical average temperature for each elevation and then compute Drywell DRYWELL TEMP Average Air Temp by averaging the 3 Elevation Averages.

At Least one temp instrument for each elevation must be available for the arithmetic average.

DW 653 F

AVERAGE 78 634 to 640 F

AVERAGE CALCULATE 604 to 609 F

AVERAGE DW AVERAGE 145 F AIR TEMP DRYER STORAGE / Have the Nuclear Island Operator report the position of the Dryer Storage/Reactor Well Pool, Fuel Transfer Pool Gates.

REACTOR WELL GATE Gate information is used in Item 80 and 81.

79 Fuel Transfer Pool I/R REPORTED Gate DATA Dryer Storage /

I/R Reactor Well Gate

OT-3701-ADM_035_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Setting: Classroom Applicability: RO Admin Topic: Conduct of Operations Validated Time: 15 Minutes

References:

PDB-A0016 Rev. 17 & PDB-A0018 Rev. 2 Required Material: PDB-A0016 Decay Heat Curve PDB-A0018 System Decay Heat Removal Capabilities Task: 299-827-01-01 Demonstrate the Use of PDB Entries in Tabs A, B, C, D, E, F, G, and H Task Standard: Calculate decay heat load following shutdown and determine if Alternate Decay Heat Removal System (ADHR) may be placed in service as scheduled.

K/A: 2.1.20 Ability to interpret and execute procedure steps. Importance RO 4.6

1. Setup Instructions: None

2. Location / Method: Classroom / Administrative Performance

3. Initial Condition: The next refuel outage is scheduled for next week. However, the Plant is shutting down for a forced shutdown at noon today. Lake temperature is 79 °F. The ADHR system has been filled and vented. The ADHR pump can supply up to 2000 gpm flow. The Outage Plan calls for placing the ADHR system in service tomorrow at noon, just after Cold Shutdown is achieved.

4. Initiating Cue: Unit Supervisor directs you, an Extra Reactor Operator, to calculate decay heat load following shutdown and determine if the ADHR system may be placed in service as scheduled. Assume lake water temperature will remain stable.

Start: Stop:

Candidate:

OT-3701-ADM_035_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 PDB-A0016 Decay Heat Curve PDB-A0018 System Decay Heat Removal Capabilities Standard: Candidate determines PDB-A016 and PDB-A018 are needed.

Instructor Cue: None Notes: When Candidate identifies correct PDB, provide the Candidate with Individual copies.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 2 Determine decay heat load Critical Step Standard: Using PDB-A016, 1R17 In-Vessel Decay Heat Before Fuel Discharge curve, Candidate determines decay heat load will be 73 MBTUs/hour 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown.

Instructor Cue: None Notes: Due to readability of the graph, acceptable decay heat load is 72-75 MBTUs/hour SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_035_RO Rev 0 Step 3 Determine if ADHR system can remove the decay heat load Critical Step Standard: Using PDB-A018, ADHR Decay Heat Removal Capacity (Reactor Vessel) graph, Candidate determines that based on Lake temperature of 79 °F and Decay Heat load of 73 MBTUs/hour and ADHR pump capability of only 2000 gpm, the ADHR system cannot remove all decay heat generated and the Plant may not remain in Cold Shutdown.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Determines that ADHR system not capable of removing all decay heat generated 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_035_RO Rev 0 JPM CUE SHEET INITIAL

The next refuel outage is scheduled for next week.

CONDITIONS:

However, the Plant is shutting down for a forced shutdown at noon today.

Lake temperature is 79 °F.

The ADHR system has been filled and vented.

The ADHR pump can supply up to 2000 gpm flow.

The Outage Plan calls for placing the ADHR system in service tomorrow at noon, just after Cold Shutdown is achieved.

INITIATING CUE: Unit Supervisor directs you, an Extra Reactor Operator, to calculate decay heat load following shutdown and determine if the ADHR system may be placed in service as scheduled.

Assume lake water temperature will remain stable.

Procedure Number:

PERRY NUCLEAR POWER PLANT PDB-A0016

Title:

Use Category:

Decay Heat Curve In-Field Reference Revision: Page:

17 1 of 9 DECAY HEAT CURVE Functional Location (1J11)

Plant Data Book Effective Date: 12-6-18 Preparer: Pat Curran / 10-19-18 Date Approver: Larry Francis / 11-26-18 Date

Procedure Number:

PERRY NUCLEAR POWER PLANT PDB-A0016

Title:

Use Category:

Decay Heat Curve In-Field Reference Revision: Page:

17 2 of 9

Use Category:

Decay Heat Curve In-Field Reference Revision: Page:

17 9 of 9

PDB-A0018 Page: i Rev.: 2 PERRY OPERATIONS MANUAL Plant Data Book Entry TITLE: SYSTEM DECAY HEAT REMOVAL CAPABILITIES PDB - A0018/Rev. 2 MPL: J11 EFFECTIVE DATE: 3-9-15

SUMMARY

OF LAST CHANGE: Added curves for Alternate Decay Heat Removal Heat Exchanger capacity.

REFERENCES:

Calculations G33-12, Rev. 1; E12-29, Rev. 0; G41-37, Rev. 0; G4O-010, Rev. 0 COMMITMENTS:

PREPARED BY: Rick Carothers 2-16-15 Date

PDB-A0018 Page: ii Rev.: 2 Change History Summary of Changes:

Rev.2. Added Alternate Decay Heat Removal Heat Exchanger curves.

PDB-A0018 Page: 1 Rev.: 2 G33 Flow = 140 gpm (RX Drain)

NOTES: The above curves apply to the heat removal capacity of the G33 Non-Regenerative heat exchangers during refuel, to be used for alternate decay heat removal.

The above curves are based on a maximum bulk fuel pool temperature of 127F and contain a 5% margin for plugged tubes in the heat exchangers.

Nuclear Closed Cooling (NCC - P43) temperature range of 65F to 95F is used for the above curves. The Legend shows the NCC (shell side) flow rates.

It is assumed that the Regenerative heat exchangers will be bypassed after RWCU discharge from the Non-regenerative heat exchangers. The G33 flow rate of 140 gpm for one pump is based on suction from the reactor vessel drain.

PDB-A0018 Page: 2 Rev.: 2 G33 Flow = 204 gpm NOTES: The above curves apply to the heat removal capacity of the G33 Non-Regenerative heat exchangers w/Rx head removed during refuel, to be used for alternate decay heat removal.

The above curves are based on a maximum bulk fuel pool temperature of 127F and contain a 5% margin for plugged tubes in the heat exchangers.

Nuclear Closed Cooling (NCC - P43) temperature range of 65F to 95F is used for the above curves. The Legend shows the NCC (shell side) flow rates.

It is assumed that the Regenerative heat exchangers will be bypassed after RWCU discharge from the Non-Regenerative heat exchangers. The G33 flow rate of 204 gpm is based on operation of one G33 pump.

PDB-A0018 Page: 3 Rev.: 2 RHR Decay Heat Removal Capacity NOTES: The above curves apply to the heat removal capacity of one E12 division. To determine the heat removal rate of both trains of heat exchangers, add the individual rates from these curves based on the observed heat exchanger inlet conditions. RHR Flow Rate is shell side, i.e., from fuel pools.

The above curves are based on a maximum bulk fuel pool temperature of 127F and contain a 5% margin for plugged tubes in the heat exchanger.

Service water (SW) temperature is seasonal. Range of 33F to 85F is used for the above curves. The curves assume a tube side (SW) flow of 7300 gpm.

PDB-A0018 Page: 4 Rev.: 2 G41 Ht. Exchanger Heat Removal Capacity With P43/P45 Flow of 2000 gpm NOTES: The above curves apply to the heat removal capacity of a single G41 heat exchanger. To determine the heat removal rate of both, add the individual rates from these curves based on the observed heat exchanger inlet conditions.

The above curves are based on maximum bulk fuel pool temperatures of 127F and assume a maximum of 20 tubes plugged per heat exchanger.

G41 total system flow is 1500 gpm for single G41 pump operation.

Above curves span the expected range of flows for one G41 loop per SOI-G41.

P43 (NCC) is temperature-controlled, with P43 temperature normally maintained between 70F to 89F. NCC winter minimum is 55 with P47 Chillers operating. With Reactor Recirc. Pumps operating, NCC minimum allowable temperature is 70F to protect bearings. See SOI-P43. Use above curves based on actual P43 flow to G41.

P45 (ESW) temperature is seasonal but must not exceed 85F. The required ESW flow to G41 will vary according to G41 heat load and ESW temperature. Use the appropriate set of curves on pages 4-7 based on actual ESW flow.

Measurement of actual P43/P45 flows through the heat exchanger shall be taken using the P42-N0265A/B orifice using portable M&TE.

Conversion of orifice differential pressure (h, inches of water) for heat exchanger shell side flow in GPM shall be per the equation:

GPM=45.54(h)0.5.

PDB-A0018 Page: 5 Rev.: 2 G41 Ht. Exchanger Heat Removal Capacity With P43/P45 Flow of 1500 gpm NOTES: The above curves apply to the heat removal capacity of a single G41 heat exchanger. To determine the heat removal rate of both, add the individual rates from these curves based on the observed heat exchanger inlet conditions.

The above curves are based on maximum bulk fuel pool temperatures of 127F and assume a maximum of 20 tubes plugged per heat exchanger.

G41 total system flow is 1500 gpm for single G41 pump operation.

Above curves span the expected range of flows for one G41 loop per SOI-G41.

P43 (NCC) is temperature-controlled, with P43 temperature normally maintained between 70F to 89F. NCC winter minimum is 55 with P47 Chillers operating. With Reactor Recirc. Pumps operating, NCC minimum allowable temperature is 70F to protect bearings. See SOI-P43. Use above curves based on actual P43 flow to G41.

P45 (ESW) temperature is seasonal but must not exceed 85F. The required ESW flow to G41 will vary according to G41 heat load and ESW temperature. Use the appropriate set of curves on pages 4-7 based on actual ESW flow.

Measurement of actual P43/P45 flows through the heat exchanger shall be taken using the P42-N0265A/B orifice using portable M&TE.

Conversion of orifice differential pressure (h, inches of water) for heat exchanger shell side flow in GPM shall be per the equation:

GPM=45.54(h)0.5.

PDB-A0018 Page: 6 Rev.: 2 G41 Ht. Exchanger Heat Removal Capacity With P43/P45 Flow of 1000 gpm NOTES: The above curves apply to the heat removal capacity of a single G41 heat exchanger. To determine the heat removal rate of both, add the individual rates from these curves based on the observed heat exchanger inlet conditions.

The above curves are based on maximum bulk fuel pool temperatures of 127F and assume a maximum of 20 tubes plugged per heat exchanger.

G41 total system flow is 1500 gpm for single G41 pump operation.

Above curves span the expected range of flows for one G41 loop per SOI-G41.

P43 (NCC) is temperature-controlled, with P43 temperature normally maintained between 70F to 89F. NCC winter minimum is 55 with P47 Chillers operating. With Reactor Recirc. Pumps operating, NCC minimum allowable temperature is 70F to protect bearings. See SOI-P43. Use above curves based on actual P43 flow to G41.

P45 (ESW) temperature is seasonal but must not exceed 85F. The required ESW flow to G41 will vary according to G41 heat load and ESW temperature. Use the appropriate set of curves on pages 4-7 based on actual ESW flow.

Measurement of actual P43/P45 flows through the heat exchanger shall be taken using the P42-N0265A/B orifice using portable M&TE.

Conversion of orifice differential pressure (h, inches of water) for heat exchanger shell side flow in GPM shall be per the equation:

GPM=45.54(h)0.5.

PDB-A0018 Page: 7 Rev.: 2 G41 Ht. Exchanger Heat Removal Capacity With P43/P45 Flow of 500 gpm NOTES: The above curves apply to the heat removal capacity of a single G41 heat exchanger. To determine the heat removal rate of both, add the individual rates from these curves based on the observed heat exchanger inlet conditions.

The above curves are based on maximum bulk fuel pool temperatures of 127F and assume a maximum of 20 tubes plugged per heat exchanger.

G41 total system flow is 1500 gpm for single G41 pump operation.

Above curves span the expected range of flows for one G41 loop per SOI-G41.

P43 (NCC) is temperature-controlled, with P43 temperature normally maintained between 70F to 89F. NCC winter minimum is 55 with P47 Chillers operating. With Reactor Recirc. Pumps operating, NCC minimum allowable temperature is 70F to protect bearings. See SOI-P43. Use above curves based on actual P43 flow to G41.

P45 (ESW) temperature is seasonal but must not exceed 85F. The required ESW flow to G41 will vary according to G41 heat load and ESW temperature. Use the appropriate set of curves on pages 4-7 based on actual ESW flow.

Measurement of actual P43/P45 flows through the heat exchanger shall be taken using the P42-N0265A/B orifice using portable M&TE.

Conversion of orifice differential pressure (h, inches of water) for heat exchanger shell side flow in GPM shall be per the equation:

GPM=45.54(h)0.5.

PDB-A0018 Page: 8 Rev.: 2 ADHR Decay Heat Removal Capacity (Fuel Pool)

NOTES: The above curves apply to the heat removal capacity of the G40, Alternate Decay Heat Removal Heat Exchanger, PY-1G40B0005.

The above curves are based on a maximum bulk fuel pool temperature of 127F and design fouling (0.0007 hr-ft2-F/Btu) of the heat exchanger.

Service Water (P41) temperature is seasonal. The range of 33F to 85F is used for the above curves. The curves assume a Service Water flow of 3700 gpm.

PDB-A0018 Page: 9 - LAST Rev.: 2 ADHR Decay Heat Removal Capacity (Reactor Vessel)

NOTES: The above curves apply to the heat removal capacity of the G40, Alternate Decay Heat Removal Heat Exchanger, PY-1G40B0005.

The above curves are based on a maximum reactor vessel temperature of 200F and design fouling (0.0007 hr-ft2-F/Btu) of the heat exchanger.

Service Water (P41) temperature is seasonal. The range of 33F to 85F is used for the above curves. The curves assume a Service Water flow of 3700 gpm.

OT-3701-ADM_026_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: P54, Fire Protection System - Water Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: Administrative Validated Time: 10 Minutes

References:

SOI-P54 (WTR) Rev 30, PAP-1910 Rev 43, & Dwg 914-001 Rev VV Required Material: SOI-P54 & Dwg 914-001 Drawing Index Task: 286-505-01-01 Analyze System Problems 286-506-03-01 Inform Unit Supervisor of Inoperable Fire Protection Task Standard: Identify minimum isolation boundary for the designated leaking fire protection system component to permit restoration of the Fire Pumps K/A Data: 2.2.41 - Ability to obtain and interpret station electrical and mechanical drawings. Importance: RO 3.5 2.2.15 - Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. Importance: RO 3.9

1. Setup Instructions: If administered in classroom, have package of all 914 drawings available.

2. Location / Method: Simulator / Classroom - Administrative Performance

3. Initial Condition: Reports from the field indicate that P54-F3554, Motor to Diesel Fire Pump Xconn Supply to Ring has a thru wall pipe rupture. All Fire Pumps were shutdown to secured status per SOI-P54 Water per the Unit Supervisors direction.

4. Initiating Cue: The Unit Supervisor directs you to determine the minimum isolation boundary for P54-F3554 to permit restoration of the Fire Pumps.

Start: Stop:

Candidate:

OT-3701-ADM_026_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 914-0001-0000, Fire Service Yard Area Critical Step Standard: Candidate obtains drawing and determines that closing P54-F3552 is necessary to isolate P54F3554.

Instructor Cue: When the Candidate determines the correct 914 drawing to use, then provide the drawing to the Candidate if required.

Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F3552 coordinates are H-2.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_026_RO Rev 0 Step 2 Evaluate Leak Isolation, Drawing 914-0001-0000, Fire Service Yard Area Critical Step Standard: Candidate obtains drawing and determines that closing P54-F6371 is necessary to isolate P54F3554.

Instructor Cue: None Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F6371 coordinates are C-3.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 Evaluate Leak Isolation, Drawing 914-0001-0000, Fire Service Yard Area Critical Step Standard: Candidate obtains drawing and determines that closing P54-F3555 is necessary to isolate P54F3554.

Instructor Cue: None Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F3555 coordinates are F-4.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: The valves needed to isolate the leak have been correctly identified.

Evaluation Results: SAT_____ UNSAT_____

End Time OT-3701-ADM_026_RO x Rev 0 Answer Key Isolation valve Leaking valve Isolation valve Drawing 914-0001 Rev VV OT-3701-ADM_026_RO Rev 0 JPM CUE SHEET INITIAL

Reports from the field indicate that P54-F3554, Motor to Diesel Fire CONDITIONS: Pump Xconn Supply to Ring has a thru wall pipe rupture.

All Fire Pumps were shutdown to secured status per SOI-P54 Water per the Unit Supervisors direction.

INITIATING CUE: The Unit Supervisor directs you to determine the minimum isolation boundary for P54-F3554 to permit restoration of the Fire Pumps.

OT-3701-ADM_004_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO/SRO Administrative Topic: Radiation Control Validated Time: 23 Minutes

References:

NOP-OP-4201 Rev 5 & NOP-OP-4202 Rev 2 Required Material: NOP-OP-4201, Routine External Exposure Monitoring NOP-OP-4202, Declared Pregnant Workers Task: 299-656-03-01 Direct Non-Licensed Personnel in the Performance of their Duties 299-691-03-01 Properly Use the Exposure Reduction Tools and Methods Available 299-502-03-01 Maintain Radiation Exposure as Low as Reasonably Achievable (ALARA)

Task Standard: Calculate total amount of dose to perform a valve manipulation and select an eligible NLO with the lowest dose to perform this task.

K/A Data: 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. Importance: RO 3.2 SRO 3.7

1. Setup Instructions: Provide NOP-OP-4201 & NOP-OP-4202 and Survey Map

2. Location / Method: Simulator Classroom / Administrative Performance

3. Initial Condition: Todays date is October 1st. Plant is operating at power. A PMT on RCIC requires the performance of PTI-E51-P0003, RCIC Terry Turbine Overspeed Trip Test. Valve 1P61-F586, Aux. Steam To RCIC Turbine must be opened to perform the overspeed test.

RP estimates travel dose to and from the valve is 33 mrem each way.

It is expected to take five minutes to operate the valve.

4. Initiating Cue: Determine dose to be received for the job. Using ALARA principals, select one NLO from the list provided, and determine if an Administrative Control Level Extension form is necessary. Explain rationale for selecting the NLO. These are the only NLOs qualified and available to perform this task.

Start: Stop:

Candidate:

OT-3701-ADM_004_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 Survey Map Candidate reviews survey map and calculates dose to operate valve 1P86-F586.

Critical Step Standard: Candidate determines dose for operating 1P86-F586 is 15.4 mrem.

Instructor Cue: Provide survey map to applicant.

Notes: Dose rate at valve P61-F586 is 185 mrem for 15.4 mrem.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_004_RO Rev 0 Step 2 Calculate dose for entire job.

Candidate calculates total dose to perform task using data provided from RP and calculated dose for operatin.

Critical Step Standard: Candidate calculates total dose to perform task using data provided from RP and calculated dose for operating the valve is 81 mrem.

Instructor Cue: None Notes: Travel dose is 33 mrem x 2 = 66 mrem.

Dose rate at valve P61-F586 is 185 mrem for 15.4 mrem.

Total job dose is 81.4 mrem.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-ADM_004_RO Rev 0 Step 3 NOP-OP-4202, Declared Pregnant Workers 4.0 Limits and Precautions 4.5 The Federal EFDE occupational dose limit is 500 mrem for the entire gestation period or period of declared pregnancy. FENOC utilizes administrative limits of 450 mrem for the entire gestation period and 50 mrem per month. In addition, substantial variation above a monthly uniform dose rate (e.g., no greater than 100 mrem per month) shall be avoided.

4.6 When a worker declares pregnancy and the EFED dose has already exceeded 450 mrem, an additional dose of 50 mrem is permitted for the duration of the pregnancy through the use of form NOP-OP-4201-02, administrative control level extension authorization.

Critical Step Standard: The Candidate reviews NOP-OP-4202 and determines that NLO Sarah Jones is not permitted to perform the task since the task dose will exceed 50 mrem.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_004_RO Rev 0 Step 3 NOP-OP-4201, Routine External Exposure Monitoring Critical Step Standard: The Candidate reviews NOP-OP-4201 and determines that NLO Amanda Smith should perform the task based on YTD dose.

Instructor Cue: If Candidate reports that an ACL Extension is required, acknowledge report.

Notes: Selecting Amanda Smith is appropriate since she has a YTD lower dose than Bill Jones.

ACL will be required since estimated dose + margin (100 mr) + YTD dose will cause worker to exceed 1900 mrem. See below for supporting documentation.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

NOP-OP-4201, Routine External Exposure Monitoring 2.2 Exceptions

2. This procedure does not provide dose limitation for Declared Pregnant Workers. Refer to NOP-OP-4202 for this class of workers.

3.0 DEFINITIONS 3.1 Administrative Control Level (ACL) - A company imposed dose guideline used for the purpose of maintaining doses below the dose limits established in 10 CFR 20.

6.0 PROCEDURE DETAILS 6.1.7 Sum the workers current year DDE/EDE listed in NOP-OP-4201-01 Section 1, and/or attachments, and record on NOP-OP-4201-01 Section 2.

1. If TEDE exceeds 1500 mrem, then notify RP Supervision. An ACL extension may be necessary dependent upon the nature of the expected work.

6.1.9 Determine the workers ACL values:

1. Refer to Attachment A for the standard list of ACLs.

6.5 ACL Extension Authorization Excluding PSE OT-3701-ADM_004_RO Rev 0 NOTES

HIS-20 implements ACL dose limitation. Typically, the TEDE ACL is limiting. HIS-20 limits the EAD dose alarm set point use the minimum of the following:

Allowable set point = ANNUAL ACL - 100 mrem - TOTAL YTD TEDE

For TEDE, the initial ANNUAL ACL is 2000 mrem. If the dose alarm set point is less than needed to perform work, an ACL extension may be requested to increase the ACL.

For example: if an individual is attempting to enter the RCA and their YTD dose plus the RWP dose limit plus 100 mrem margin exceeds 1900 mrem, an ACL extension would be required due to the allowable setpoint not being high enough.

In summary, HIS-20 will not allow you to sign onto a RWP when your YTD TEDE + RWP dose limit +100 mrem exceeds 1900 mrem.

6.5.1 The work group supervisor initiates the ACL extension authorization by completing Section 1 of NOP-OP-4201-02. After Section 1 is completed, forward the form to Radiation Protection/Dosimetry.

Table 2 - HIS-20 Options - ACL Limits for Annual Dose Limit Type TEDE SDE_SK SDE_EX LDE TDE DAC_HR FRAC_ALI PUBLIC *200 1000 1000 300 1000 20 0.01 ACL 500 500 5000 5000 1500 5000 20 0.01 ACL 1000 1000 10000 10000 3000 10000 20 0.01 ACL 1500 1500 15000 15000 4500 15000 50 0.018

- - ACL 2000 2000 40000 40000 12000 40000 80 0.036 ACL 3000 3000 30000 30000 9000 30000 100 0.06 ACL 4000 4000 40000 40000 12000 40000 200 0.1

Includes 100 mrem buffer. Actual limit is 100 mrem.

- Default values ACL.

OT-3701-ADM_004_RO Rev 0 Step 4 Explain rationale for NLO selection.

Standard: The Candidate explains rationale for NLO selection:

Instructor Cue: None Notes: NLO Sarah Jones is not permitted to perform the task since the task dose will exceed 50 mrem and she is only allowed to receive 50 more mrem for the duration of her gestation.

Selecting Amanda Smith would be in line with ALARA principals since she has an initial lower dose than Bill Jones.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Candidate determines total dose to perform task, selects an operator using ALARA principals and completes a dose extension form.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_004_RO Rev 0 JPM CUE SHEET INITIAL

Todays date is October 1st.

CONDITIONS:

Plant is operating at power.

A PMT on RCIC requires the performance of PTI-E51-P0003, RCIC Terry Turbine Overspeed Trip Test. Valve 1P61-F586, Aux. Steam To RCIC Turbine must be opened to perform the overspeed test.

RP estimates travel dose to and from the valve is 33 mrem each way.

It is expected to take five minutes to operate the valve.

INITIATING CUE:

Determine dose to be received for the job.

Using ALARA principals, select one NLO from the list provided, and determine if an Administrative Control Level Extension form is necessary.

Explain rationale for selecting the NLO.

These are the only NLOs qualified and available to perform this task.

OT-3701-ADM_004_RO Rev 0 NLO YTD Dose Comments Bill Johnson 1855 mrem Received dose only at Perry YTD Sarah Jones 1826 mrem Received dose only at Perry YTD Declared Pregnant Worker (as of today)

Amanda Smith 1837 mrem Received dose only at Perry YTD VSDS Standard Map Survey Report Survey PY-M-20120202-4 General Information

Title:

Open valve and remove tag on 1P61F0568 for the RCIC work Survey Date/Time: 2/2/2012 09:00 Lead Surveyor: Tina Mettler Survey Type: Job Coverage Work Order/Task #: n/a Counted By: Rx % Pwr: 100%

RWP #: 120120 SAP/Contract ID: 18396 Status: Approved by: Joe Spahr, 2/3/2012 06:08:08 SAP/Contract ID: 17460 Ready for Review by: Tina Mettler, 2/2/2012 00:00:00 SAP/Contract ID: 18396 Dose Rate (DR) Object Prefixes/Suffixes Dose Rates with Prefixes: Dose Rates with No Prefixes: Default Prefixes: Default Suffixes:

= Contact Gen Area HS = Hot Spot "n" = Neutron

+ = 30cm "b" = Beta "c" = Corrected Postings Legend CA=Contaminated Area LHRA=Locked High Radiation Area Map Locations

File Name Image Description Location Code Bldg/Area Name Location Description 1 ST\ST620 ST620 AX Steam Tunnel 620 Eleva Steam Tunnel ST620 Steam Tunnel 2 ST\ST630 ST630 AX Steam Tunnel - MSIV PlaSteam Tunnel ST630 Steam Tunnel 3 TB\T620E T620E Stop/Control/Bypass Valve Turbine Building 1TB620 Stop/Control/Bypass Valv Instruments Used Instrument Instrument Calibration

Model Serial # Date/Time 1 RM-25 021U 9/15/2011 2 MODEL 451 033B 11/15/2011 Survey #: PY-M-20120202 PDF Generated On: 2/3/2012 06:08 Page 1 of 7

VSDS Standard Map Survey Report Map: 1 ST620 AX Steam Tunnel 620 Elevation Survey #: PY-M-20120202-4 Date/Time: 2/2/2012 09:00 Comments: Summary of Highest Readings (All available values may not be listed)

Smears Air Samples & Wipes

1) 2000 DPM/100 cm2 Type: Job Coverage Symbol Legend (for example only) RWP #: 120120 Reactor Power = 100%

Unless otherwise noted, dose rates in mrem/hr.

Lead Surveyor: Tina Mettler Status: Approved by: Joe Spahr, 2/3/2012 06:08:08 Location Code: Steam Tunnel Bldg/Area Name: ST620 Location

Description:

Steam Tunnel Image File: ST\ST620 Survey #: PY-M-20120202 PDF Generated On: 2/3/2012 06:08 Page 2 of 7

VSDS Standard Map Survey Report Data Point Details Survey #: PY-M-20120202-4 Map: 1 - ST\ST620

Type Inst. Value Units Position Notes 1 DR N/A 300 mrem/hr 2 DR N/A 320 mrem/hr 3 DR N/A 550 mrem/hr 4 DR N/A 1350 mrem/hr 5 DR N/A 850 mrem/hr 6 DR N/A 720 mrem/hr 7 DR N/A 500 mrem/hr 8 DR N/A 350 mrem/hr 1 Smear N/A 2000 DPM/100 cm2 Posting LHRA LHRA and CA at the door to the Steam Tunnel CA Text used this ladder Image File: ST\ST620 Survey #: PY-M-20120202 PDF Generated On: 2/3/2012 06:08 Page 3 of 7

VSDS Standard Map Survey Report Map: 2 ST630 AX Steam Tunnel - MSIV Platform Survey #: PY-M-20120202-4 Date/Time: 2/2/2012 09:00 Comments: Summary of Highest Readings (All available values may not be listed)

Smears Air Samples & Wipes

1) 3000 DPM/100 cm2 Type: Job Coverage Symbol Legend (for example only) RWP #: 120120 Reactor Power = 100%

Unless otherwise noted, dose rates in mrem/hr.

Lead Surveyor: Tina Mettler Status: Approved by: Joe Spahr, 2/3/2012 06:08:08 Location Code: Steam Tunnel Bldg/Area Name: ST630 Location

Description:

Steam Tunnel Image File: ST\ST630 Survey #: PY-M-20120202 PDF Generated On: 2/3/2012 06:08 Page 4 of 7

VSDS Standard Map Survey Report Data Point Details Survey #: PY-M-20120202-4 Map: 2 - ST\ST630

Type Inst. Value Units Position Notes 1 DR N/A 320 mrem/hr 2 DR N/A 375 mrem/hr 3 DR N/A 185 mrem/hr this is where the operator was standing 1 Smear N/A 3000 DPM/100 cm2 2 Smear N/A 2000 DPM/100 cm2 Posting LHRA CA Text 1P61F0568 Image File: ST\ST630 Survey #: PY-M-20120202 PDF Generated On: 2/3/2012 06:08 Page 5 of 7

VSDS Standard Map Survey Report Map: 3 T620E Stop/Control/Bypass Valve Survey #: PY-M-20120202-4 Date/Time: 2/2/2012 09:00 Comments: Summary of Highest Readings (All available values may not be listed)

Smears Air Samples & Wipes

1) 1000 DPM/100 cm2 Type: Job Coverage Symbol Legend (for example only) RWP #: 120120 Reactor Power = 100%

Unless otherwise noted, dose rates in mrem/hr.

Lead Surveyor: Tina Mettler Status: Approved by: Joe Spahr, 2/3/2012 06:08:08 Location Code: Turbine Building Bldg/Area Name: 1TB620 Location

Description:

Stop/Control/Bypass Valve Image File: TB\T620E Survey #: PY-M-20120202 PDF Generated On: 2/3/2012 06:08 Page 6 of 7

VSDS Standard Map Survey Report Data Point Details Survey #: PY-M-20120202-4 Map: 3 - TB\T620E

Type Inst. Value Units Position Notes 1 DR N/A 34 mrem/hr outside door 2 DR N/A 145 mrem/hr 3 DR N/A 420 mrem/hr 1 Smear N/A 1000 DPM/100 cm2 Posting LHRA CA Image File: TB\T620E Survey #: PY-M-20120202 PDF Generated On: 2/3/2012 06:08 Page 7 of 7

ADMINISTRATIVE CONTROL LEVEL EXTENSION AUTHORIZATION NOP-OP-4201-02 Rev. 02 SECTION 1 - REQUEST NAME PLANT ID DEPT/SECT/UNIT PHONE EXT.

INCREASED DOSE LEVEL REQUESTED

>2000 mrem/yr TEDE current year TOTAL dose. Request increase to TOTAL dose of mrem

>450 mrem/gestation period TOTAL dose. Request increase of 50 mrem total for the remainder of the pregnancy.

REASON FOR INCREASE:

WERE OTHER SIMILARLY QUALIFIED PERSONNEL CONSIDERED? YES NO N/A IF NO, WHY NOT?

WORKER: FENOC MANAGER:

Signature Date Signature Date SUPERVISOR:

NOTE: It is the responsibility of the Supervisor to inform the affected Signature Date individual when the Authorization is approved.

SECTION 2 - EXPOSURE HISTORY RECORD ESTIMATE TOTAL COMPLETED BY RADIATION PROTECTION (mrem) (mrem) (mrem)

TEDE CURRENT YEAR SITE TEDE CURRENT YEAR OFFSITE YEAR TO DATE TOTAL Dosimetry Initials/Date /

Comments:_____________________________________________________________________________________

SECTION 3 - APPROVAL APPROVED TEDE DOSE EXTENSION TO ____________ mrem TOTAL APPROVED ADDITIONAL 50 MREM FOR DURATION OF PREGNANCY Manager, Radiation Protection Required for any ACL extension Signature Date Director, Site Operations Required for TOTAL > 3000 mrem Signature Date Site Vice-President Required for TOTAL > 4000 mrem Signature Date SECTION 4 - IMPLEMENTATION New authorized dose value entered into HIS-20 by: _________ , ___________/___________

Initials Date/Time Dosimetry Supervision review & extension verification by: ___________________________ ________________

Signature Date

OT-3701-ADM_028SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: SRO Administrative Topic: Conduct of Operations Validated Time: 15 minutes Setting: Classroom

References:

PYBP-POS 1-5, Rev 3, NOBP-TR-1271 Rev. 11, & NOP-LP-4011 Rev.

14 Required Material: Attached Work Schedule PYBY-POS 1-5, Operations Training Guidelines NOBP-TR-1271, Operator License Administration NOP-LP-4011, FENOC Work Hour Control Tasks: 299-831-03-01 Perform licensed duties only if your license is Current and Active Task Standard: Review proposed work schedules to determine if the schedule(s) is/are appropriate to maintain an Active NRC SRO license per NOBP-TR-1271, Operator License Administration K / A Data: 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. SRO 3.8 2.1.5 / 3 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. SRO 3.9

1. Setup Instructions: N/A

2. Location / Method: Classroom / Perform

3. Initial Condition: You are a Staff SRO who maintains your license Active. Today is March 9th of this year and you have not stood any proficiency watches since December 20th of last year. You have been directed to maintain your SRO license active this year. The OPS Training Coordinator has developed 6 proposed schedules based on filling existing holes in the schedule.

4. Initiating Cue:

Evaluate the proposed schedules to determine which, if any, of the schedules meet the requirements to maintain your SRO license active.

If a schedule does not meet the requirements, EXPLAIN why it does not.

Start Time: End Time:

Candidate:

OT-3701-ADM_028SRO 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 NOBP-TR-1271, Operator License Administration 4.5 Maintaining an Active NRC License In order for a Licensed Operator to maintain an active NRC License, he/she must actively perform the functions of a Reactor Operator or Senior Reactor Operator for a minimum of:

Seven 8-hour shifts per calendar quarter

Five 12-hour shifts per calendar quarter

This requirement may be completed with a combination of COMPLETE 8-hour and COMPLETE 12-hour shifts (in a position appropriately credited for watchstanding proficiency) when working a mixed shift schedule.

Watches shall not be truncated when the operator satisfies the minimum quarterly requirement of 56 total hours.

The 8-hour or 12-hour shift must include a shift turnover meeting at the beginning and end of the Operator Shift to get credit for the watch.

PYBP-POS-1-5, Operations Training Guidelines 4.1 Tracking Of Proficiency Watches

. . . To receive credit for the position the operator must stand one of the Technical Specification required license positions (i.e. SM, US, RO-ATC, or RO BOP). . .

. . . Additionally, on-shift personnel maintaining qualifications for shift positions, other than what they are normally assigned (i.e. SE maintaining RO, SE maintaining US, etc.)

also need to document proficiency completion for each position. An SRO must stand at least one complete watch (8 or 12 hr. shift) per calendar quarter in a SRO only supervisory position. The remainder of complete watches in a calendar quarter may be performed in either a credited SRO or RO position. For Shift Manager qualified personnel, at least one complete watch will be in the Shift Manager position. . .

Step 1 continued on next page OT-3701-ADM_028SRO Rev 0 Step 1 continued Standard: Candidate reviews the following for proficiency requirements:

NOBP-TR-1271, Operator License Administration

PYBP-POS-1-5, Operations Training Guidelines Instructor Cue: None Notes: Candidate may want to review NOP-LP-4011 for Fatigue Rule.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 Evaluate Schedule 1.

Critical Step Standard: Candidate determines Schedule 1 does not meet:

The five 12-hour shifts per calendar quarter in a Qualifying Licensed Position.

The appropriate watch standing position (NOT Shift Engineer)

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_028SRO Rev 0 Step 3 Evaluate Schedule 2 Critical Step Standard: Candidate determines Schedule 2 can be used to maintain his/her SRO license ACTIVE.

Instructor Cue: None Notes: Schedule 2 can be used to maintain the SRO License but will not maintain Shift Manager qualifications.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Evaluate Schedule 3 Critical Step Standard: Candidate determines Schedule 3 does not meet:

The five 12-hour shifts per calendar quarter in a Qualifying Licensed Position.

The appropriate watch standing position (NOT Shift Engineer nor Field Supervisor).

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_028SRO Rev 0 Step 5 Evaluate Schedule 4 Critical Step Standard: Candidate determines Schedule 4 does NOT meet the five 12-hour shifts per calendar quarter in a Qualifying Licensed Position.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 6 Evaluate Schedule 5 Critical Step Standard: Candidate determines Schedule 5 does NOT meet the five 12-hour shifts per calendar quarter in a Qualifying Licensed Position.

Instructor Cue: None Notes: None.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_028SRO Rev 0 Step 7 Evaluate Schedule 6 Critical Step Standard: Candidate determines Schedule 6 can be used to maintain his/her SRO license ACTIVE.

Instructor Cue: None Notes: Schedule 6 is the only schedule that will allow the SRO to maintain his/her Shift Manager qualification active.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Candidate has determined that schedules 1, 3, 4, & 5 do not meet the requirements for license reactivation and has selected either schedule 2 or 6 to maintain his license.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_028SRO Rev 0 STUDENT HANDOUT Schedules Mar 10 Mar 11 Mar 13 Mar 15 Mar 19 Mar 21 Mar 27 Apr 1 Apr 2 Apr 3 Apr 4 1 Shift Days Days Nights Days Days Nights Nights Position US SE US ATC ATC FS BOP 2 Shift Nights Nights Nights Days Nights Nights Nights Nights Position BOP US ATC ATC BOP SE ATC US 3 Shift Days Days Nights Nights Days Nights Position US BOP ATC SE SE FS 4 Shift Days Days Days Days Nights Days Position SM US SM BOP US US 5 Shift Days Days Nights Nights Nights Nights Position SM US US ATC SE ATC 6 Shift Days Days Nights Nights Days Nights Days Position US SM FS US ATC ATC SE SM = Shift Manager US = Unit Supervisor SE = Shift Engineer ATC = At the Controls BOP = Balance of Plant FS = Field Supervisor OT-3701-ADM_028SRO Rev 0 JPM CUE SHEET INITIAL

You are a Staff SRO who maintains your license Active.

CONDITIONS:

Today is March 9th of this year and you have not stood any proficiency watches since December 20th of last year.

You have been directed to maintain your SRO license active.

The OPS Training Coordinator has developed 6 proposed schedules based on existing holes in the schedule.

INITIATING CUE:

Evaluate the proposed schedules to determine which, if any, of the schedules meet the requirements to maintain your SRO license active.

If a schedule does not meet the requirements, EXPLAIN why it does not.

OT-3701-ADM_017SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: SRO Safety Function: 8 - Plant Service Systems Setting: Classroom / Simulator Validated: 10 minutes

References:

SOI-F15 Rev. 25 Required Material SOI-F15 - Refueling And 360 Platforms Tasks: 234-521-04-02 Operate The Refueling Platform In Interlock Override 046-550-04-04 Respond to Alarms Associated With the Refuel Bridge and Fuel Handling Bridge Task Standard: Determine actions required for Refuel Bridge PLC failure with fuel suspended and identify the safe location for the fuel and identify any required actions.

K/A Data: 2.1.36 Knowledge of procedures and limitations involved in core alterations.

Importance Rating: RO 3.0 SRO 4.1 2.1.42 Knowledge of new and spent fuel movement procedures.

Importance Rating: RO 2.5 SRO 3.4

1. Instructions: None

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

3. Initial Condition: Plant is in Mode 5 with refueling operations in progress. A new fuel bundle is being moved from IFTS to Reactor location 17-38. IFTS carriage is now located in the FHB. A Refuel Platform PLC failure occurs, and the Refuel Platform has stopped in the Cattle Chute.

4. Initiating Cue: As the Refueling Supervisor, determine/identify the required response actions to mitigate the Refuel Platform PLC failure. Identify Tech Spec and/or ORM actions if any.

Start Time End Time Candidate OT-3701-ADM_017SRO 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 actions required to move the Refuel Platform and who may authorize the actions.

SOI-F15, Refueling And 360 Platforms 7.15 Operating The Refueling Platform In Interlock Override NOTE

Except for testing, the Interlock Override Key Switch shall only be used in the event of a PLC failure to move the bridge and grappled components. The Interlock Override Key Switch shall only be used as directed by the Refueling Supervisor or Control Room Supervisor.

When Interlock Override Key Switch is taken to override, all interlocks controlled by the PLC are bypassed. The Refueling Platform and Associated Refueling Interlocks are inoperable for Technical Specifications 3.9.1and ORM 6.5.4.

Critical Step Standard: Candidate determines that operating the Refueling Platform in Interlock Override is appropriate.

Candidate determines the Refueling Supervisor or the Unit Supervisor must authorize override.

Instructor Cue: Whose authorization is required to operate the Refueling Platform In Interlock Override?

Notes: The Refueling Supervisor or the Unit Supervisor must authorize use of the Interlock Override Key Switch.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_017SRO Rev 0 Step 2 Determine where the new fuel bundle can be placed.

7.15 Operating The Refueling Platform In Interlock Override NOTE The following conditions of the Fuel or Core Components are defined as safe for the purposes of this instruction:

Properly seated in the reactor vessel (only if all refueling interlocks are available).

Properly seated in a designated storage location.

Properly seated in the IFTS carriage with the carriage at the AT CONTAINMENT position with the Upender inclined.

Properly seated in the IFTS carriage with the carriage at the AT FUEL BUILDING position with the Upender inclined.

Fuel bundles in the Fuel Preparation Machines to their full down position.

7.15.3 IF a fuel bundle OR any other core component is hoisted, THEN PLACE the hoisted component to a safe condition as directed by the Refueling Supervisor.

Critical Step Standard: Candidate determines that the fuel bundle must be properly seated in a designated storage location.

Instructor Cue: None Notes: RP-1 is the Upper Containment Pool designation for the designated storage location.

Per the Initial Conditions, the IFTS carriage is at the Fuel Handling Building.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_017SRO Rev 0 Step 3 Determine where the refueling platform can be placed.

7.15.4 MOVE the refueling platform to a location as directed by the Refueling Supervisor OR the Control Room Unit Supervisor.

Standard: Candidate determines that the refueling platform may be placed at a location to expedite repair of the Refuel Platform PLC.

Instructor Cue: Determine where the Refuel Platform can be placed.

Notes: The Candidate may choose to not reposition the refueling platform once the new fuel bundle is in a safe condition.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Identify Technical Specification and/or Operation Requirements Manual Required Action(s).

Tech Specs:

3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

Actions CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with equipment interlocks inoperable associated with the inoperable interlock (s).

Or A2.1 Insert a control rod Immediately withdrawal block.

Or A.2.2 Verify all control rods are Immediately fully inserted.

OT-3701-ADM_017SRO Rev 0 ORM:

6.5.4 Refueling Platform OPERATIONAL REQUIREMENT:

The refueling platform shall be OPERABLE and used for handling fuel assemblies or control rods within the reactor pressure vessel.

APPLICABILITY:

During handling of fuel assemblies or control rods within the reactor pressure vessel.

ACTION:

With the requirements for refueling platform OPERABILITY not satisfied, suspend use of any inoperable refueling platform equipment from operations involving the handling of control rods and fuel assemblies within the reactor pressure vessel after placing the load in a safe condition.

Critical Step Standard: Candidate identifies TS 3.9.1 RA A.1 OR A.2.1 OR A.2.2 & ORM 6.5.4 Actions for INOP Refuel Platform PLC.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Candidate determines that SOI-F15 section 7.15 has the steps to perform the movement, the Refueling Supervisor or Control Room Unit Supervisor can authorize the override, and the bundle should be placed in a designated storage location, RP-1 and identifies TS & ORM Required Actions..

Evaluation Results: SAT_____ UNSAT_____

End Time OT-3701-ADM_017SRO Rev 0 JPM CUE SHEET INITIAL

Plant is in Mode 5, refueling operations are in progress.

CONDITIONS:

A new fuel bundle is being moved from IFTS to Reactor location 17-38.

IFTS carriage is now located in the FHB.

A Refuel Platform PLC failure occurs, and the Refuel Platform has stopped in the Cattle Chute.

As the Refueling Supervisor, determine/identify the required response INITIATING CUE:

actions to mitigate the Refuel Platform PLC failure.

OT-3701-ADM_026SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: P54, Fire Protection System - Water Time Critical: No Alternate Path: No Setting: Classroom Applicability: SRO only Admin Topic: Equipment Control Validated Time: 22 Minutes

References:

SOI-P54(WTR) Rev 30, PAP-1910 Rev 43, & Dwg 914-001 Rev VV Required Material: PAP-1910, & Dwg 914-001 Task: 286-505-01-01 Analyze System Problems 286-506-03-01 Inform Unit Supervisor of Inoperable Fire Protection Systems 343-684-03-02 Determine Required Actions for an Unplanned Fire Impairment / Barrier Removal When the P54 RSE is not Available Task Standard: Identify minimum isolation boundary for the designated leaking fire protection system component to permit restoration of the Fire Pumps and determine time sensitive Required Actions for the Unplanned Fire Impairment.

K/A Data: 2.2.41 - Ability to obtain and interpret station electrical and mechanical drawings. Importance SRO 3.9 2.2.38 - Knowledge of conditions and limitations in the facility license.

Importance SRO 4.5

1. Setup Instructions: If administered in classroom, have package of all 914 drawings available.

2. Location / Method: Simulator / Classroom - Administrative Performance

3. Initial Condition: The Plant is at rated power. Reports from the field indicate that P54-F3554, Motor to Diesel Fire Pump Xconn Supply to Ring has a thru wall pipe rupture.

The Unit Supervisor has ordered all Fire Pumps shutdown to secured status per SOI-P54(WTR).

4. Initiating Cue: As the Unit Supervisor, determine:

1) The minimum isolation boundary for P54-F3554 to permit restoration of the Fire Pumps.

2) What Fire Protection Functional Specification(s) is the plant currently in due to the isolation of P54-F3554, prior to restoring the Fire Pumps?

Start: Stop:

Candidate:

OT-3701-ADM_026SRO 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 914-0001-0000, Fire Service Yard Area Critical Step Standard: Candidate obtains drawing and determines that closing P54-F3552 is necessary to isolate P54F3554.

Instructor Cue: When the Candidate determines the correct 914 drawing to use, then provide the drawing to the Candidate if required Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F3552 coordinates are H-2.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_026SRO Rev 0 Step 2 Evaluate Leak Isolation, Drawing 914-0001-0000, Fire Service Yard Area Critical Step Standard: Candidate obtains drawing and determines that closing P54-F6371 is necessary to isolate P54F3554.

Instructor Cue: None Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F6371 coordinates are C-3.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 3 Evaluate Leak Isolation, Drawing 914-0001-0000, Fire Service Yard Area Critical Step Standard: Candidate obtains drawing and determines that closing P54-F3555 is necessary to isolate P54F3554.

Instructor Cue: None Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F3555 coordinates are F-4.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_026SRO Rev 0 Step 4 PAP-1910 Fire Protection Program , FIRE PROTECTION FUNCTIONAL SPECIFICATIONS Section 3 FIRE SUPPRESSION EQUIPMENT A. SYSTEMS: Fire Suppression Water Supply (Motor/Diesel Pumps)

D. ACTIONS FOR NOT FUNCTIONAL:

IF 2) Both Fire Pumps are not functional, THEN:

24 HOURS 2) a.(1) Establish a backup fire suppression water system.

OR 1 HOUR 2) a.(2) If a backup system cannot be established, implement the requirements of LCO 3.0.3. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in: MODE 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months , MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months . Where corrective measures are completed that permit operation, LCO 3.0.3 is not required. LCO 3.0.3 is only applicable in MODES 1, 2, and 3.

Determine Fire Protection Functional Specifications: Current Specification, prior to isolation and restoration:

Critical Step Standard: Candidate determines that both fire pumps are not functional and determines Actions for Not Functional are:

2) a.(1) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to establish backup system or

2) a.(2) Enter LCO 3.0.3.

Instructor Cue: None Notes: PAP 1910 pages 66-67, with both pumps in secured status, pumps are not capable of auto starting, therefore, not functional.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_026SRO Rev 0 Step 5 Section 4. FIRE SUPPRESSION EQUIPMENT A. SYSTEMS: Fire Mains and Headers D. ACTIONS FOR NOT FUNCTIONAL:

IF: 1) Any portion of the fire main distribution piping is out of service, THEN:

24 HRS 1) b. Establish back-up fire suppression water supply to the affected system/areas through temporary jumpers.

NOTE During the time period between the determination of loss of fire suppression water supply to a system/area and the establishment of a temporary supply, or if a temporary supply cannot be provided, all impaired systems shall be properly compensated for per the individual systems requirements of this attachment.

Determine Fire Protection Functional Specifications: Current Specification, prior to isolation and restoration:

Candidate determines that the Fire Header located between isolation Standard:

valves P54-F3552, P54-F3555, and P54-F6371 is not functional.

Candidate applies NOTE above Action 4.D.1)b. which states, During the time period between the determination of loss of fire suppression water supply to a system/area and the establishment of a temporary supply, or if a temporary supply cannot be provided, all impaired systems shall be properly compensated for per the individual systems requirements of this attachment. Candidate determines that a temporary supply cannot be provided to the isolated piping due to the pipe rupture.

Candidate refers to PAP-1910, Attachment 3, Section 6.A, Yard Fire Hydrants and Hydrant Hose Houses to determine required actions.

Instructor Cue: None Notes: PAP-1910, Attachment 3, Section 6.A, Yard Fire Hydrants and Hydrant Hose Houses required actions are covered under Step 6.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_026SRO Rev 0 Step 6 Section 6. FIRE SUPPRESSION EQUIPMENT A. SYSTEMS: Yard Fire Hydrants and Hydrants Hose Houses D. ACTIONS FOR NOT FUNCTIONAL:

IF: 2) Any other hydrant or hose house is not functional [per 1) above],

THEN:

NONE 2) a. Ensure that the fire brigade is aware of the status.

Determine Fire Protection Functional Specifications: Current Specification, prior to isolation and restoration:

Standard: Candidate determines that Yard Hydrant # 25 is not functional and determines Actions for Not Functional are:

2) a. Ensure that the fire brigade is aware of the status.

Instructor Cue: Understand Fire Brigade is aware of the status.

Notes: The required completion time for this action is NONE.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: The valves needed to isolate the leak have been correctly identified and the correct Functional Specifications for the loss of Fire Suppression Equipment have been identified.

Evaluation Results: SAT_____ UNSAT_____

End Time OT-3701-ADM_026_SRO Rev 0 Answer Key Isolation valve Leaking valve Isolation valve Drawing 914-0001 Rev VV OT-3701-ADM_026_SRO Rev 0 JPM CUE SHEET INITIAL

The Plant is at rated power.

CONDITIONS:

Reports from the field indicate that P54-F3554, Motor to Diesel Fire Pump Xconn Supply to Ring has a thru wall pipe rupture.

The Unit Supervisor has ordered all Fire Pumps shutdown to secured status per SOI-P54 Water.

INITIATING CUE: As the Unit Supervisor, determine:

1) The minimum isolation boundary for P54-F3554 to permit restoration of the Fire Pumps.

2) What Fire Protection Functional Specification(s) is the plant currently in due to the isolation of P54-F3554 and, to restoring the Fire Pumps?

OT-3701-ADM_034SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Setting: Classroom Applicability: SRO only Admin Topic: Radiation Control Validated Time: 9 Minutes

References:

CHI-ODMC Rev. 23 Required Material: CHI-ODMC, Offsite Dose Calculation Manual Task: 341-591-01-02 Apply Technical Specifications, ORM, ODCM, the Operating License, Holtec Hi Storm Technical Specifications, and FLEX Specifications as required, during all Modes of plant operation.

Task Standard: Determine required actions for the designated non-functional radiation monitor per ODCM K/A: 2.3.15, Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. Importance SRO 3.1

1. Setup Instructions: None

2. Location / Method: Simulator or Classroom / Administrative Performance

3. Initial Condition: A radwaste discharge is in progress. An extent of condition investigation determines that the Radwaste Discharge to ESW Radiation Monitor (0D17-K606) is presently Non-Functional due to its setpoint being non-conservative.

4. Initiating Cue: As the Unit Supervisor, what action(s), if any, is (are) required in response to this event.

Start: Stop:

Candidate:

OT-3701-ADM_034SRO 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 CHI-ODCM Offsite Dose Calculation manual Radioactive Liquid Effluent Monitoring Instrumentation Controls ODCM 3.3.7.9 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.9-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

Standard: Candidate reviews ODCM reference and determines 3.3.7.9 is the correct section and that Radioactive Liquid Effluent Monitoring instrumentation is required at all times.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_034SRO Rev 0 Step 2 ODCM 3.3.7.9 ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

Critical Step Standard: Determines that the radwaste discharge should be immediately suspended (stopped).

Instructor Cue: If stated/directed, acknowledge the discharge should be stopped.

Notes: May direct Radwaste Operator to secure the discharge.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 3 ODCM 3.3.7.9 ACTION:

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.9-1.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.

Standard: Refers to Table 3.3.7.9-1 and determines ACTION 110 is required for the Liquid Radwaste Discharge Radiation Monitor (0D17-K606).

Instructor Cue: After Candidate has stated that the RW Discharge should be stopped; ask candidate the following:

Question: Assuming no change to the status of radiation monitor 0D17-K606, under what conditions if any can the Radwaste discharge be restarted?

Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_034SRO Rev 0 Step 4 Table 3.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation Action Statements ACTION 110 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from this pathway may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Control 4.11.1.1.1, and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

Critical Step Standard: Candidate determines that the Radwaste Discharge can be restarted provided that prior to initiating the discharge the following actions are completed:

At least two independent samples are analyzed in accordance with Control 4.11.1.1.1 and

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valve lineup Instructor Cue: None Notes: JPM can be terminated after Candidate completes ODCM evaluation.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Candidate determines that the radwaste discharge should be immediately suspended; but can be restarted if requirements of Table 3.3.7.9-1 ACTION 110 are completed prior to initiating the release.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_034SRO Rev 0 JPM CUE SHEET INITIAL

A Radwaste discharge is in progress.

CONDITIONS:

An extent of condition investigation determines that the Radwaste Discharge to ESW Radiation Monitor (0D17-K606) is presently Non-Functional due to its setpoint being non-conservative.

INITIATING CUE: As the Unit Supervisor, what action(s), if any, is (are) required in response to this event.

OT-3701-ADM_323SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: Yes Alternate Path: No Setting: Classroom Applicability: SRO only Admin Topic: Emergency Procedures / Plan Validated Time: 8 Minutes

References:

EPI-A1 Rev. 30 Required Material: EPI-A1 Emergency Action Levels Form PNPP 7794 Form PNPP 7983A Form PNPP 9100 Task: 344-532-05-02 Prepare emergency plan initial notification form.

451-654-05-50 Upon declaration of any Emergency Action Level, notify offsite authorities of the event.

Task Standard: Perform a peer check of E-plan forms and make communications to the state and local counties.

K/A: 2.4.43 Knowledge of emergency communications systems and techniques. Importance SRO 3.8

1. Setup Instructions: Simulator Driver may act as State and Counties on 5-way. Make simulator 5-way phone marking match control room. Use analog clock for JPM administration.

2. Location / Method: Simulator / Administrative Performance

3. Initial Condition: A transient occurred. The Emergency Plan has been entered. You as the Shift Engineer have already peer checked the Shift Managers EAL classification of FS1.1 with a non-routine release in progress. The time of the Emergency Declaration was 3 minutes ago. The Notification Messages form has been broadcast; The Shift Manager completed the Initial Notification Form. (Maybe reverse these two I/Cs.)

4. Initiating Cue: Shift Manager directs you the Shift Engineer to perform a peer check of the Initial Notification Form. This JPM is Time Critical.

Start: Stop:

Candidate:

NOTE: Record Start Time once Candidate Acknowledges the I/Cs are understood.

OT-3701-ADM_323SRO 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 Perform a peer check of the Emergency Plan paperwork.

Critical Step Standard: Candidate Reviews the Initial Notification Form and determines an EAL of FG1.1 was recorded vs. FS1.1.

Instructor Cue: I will correct the EAL Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 2 Perform a peer check of the Emergency Plan paperwork.

Critical Step Standard: Candidate Reviews the Initial Notification Form and determines a PAR was incorrectly included on form.

Instructor Cue: I will delete the PAR Notes: After Candidate identifies EAL & PAR errors, hand him a corrected Initial Notification Form.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_323SRO Rev 0 Step 3 Perform a peer check of the Emergency Plan paperwork.

Standard: Candidate Reviews the corrected Initial Notification Form and determines it is completed correctly.

Instructor Cue: After the corrected form is reviewed, hand Candidate Event Classification Envelope with partially completed Event Classification Checklist and inform Candidate that he has now been directed by the Shift Manager to continue with E-plan duties.

Notes: Candidate may review the Event Notification Checklist to determine remaining actions.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-ADM_323SRO Rev 0 Step 4 Make notification to the state and local counties.

Critical Step Standard: Candidate pickups the 5-way and communicates the content of the Initial Notification Form to the State of Ohio and Lake, Geauga, & Ashtabula counties.

Instructor Cue: If Candidate pages the I&C Communicator, inform him the Communicator is stuck in the plant and unable to come to the Control Room When Candidate picks up the Training 5-way phone and presses the red bar (on the lower part of the phone), inform him that State of Ohio and Lake, Geauga, & Ashtabula counties are all on the line.

NOTE:

Once Candidate Acknowledges the cue that all parties are on the line mark the End Time below for completion of the Time Critical portion of the JPM. [End Time - Start Time < or = 12 min; SAT]

The following is from the Initial Notification Cover Sheet:

4. Direct parties to obtain Initial Notification Form. - Respond all parties have the form.

5. Pause 10 seconds.

6. Transmit Notification Data - Respond all parties have the data.

(The State of Ohio phone is answered by the Ohio Highway Patrol office in Columbus.)

Notes: After Candidate makes notifications, terminate the JPM.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Initial Notification Form has been corrected and notification to the state and local counties is complete.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_323SRO Rev 0 JPM CUE SHEET INITIAL

A transient occurred.

CONDITIONS:

The Emergency Plan has been entered.

You as the Shift Engineer have already peer checked the Shift Managers EAL classification of FS1.1 with a non-routine release in progress.

The time of the Emergency Declaration was 3 minutes ago.

The Notification Messages form has been broadcast.

The Shift Manager completed the Initial Notification Form.

(Maybe reverse these last two I/Cs.)

INITIATING CUE: Shift Manager directs you the Shift Engineer to perform a peer check of the Initial Notification Form.

This JPM is Time Critical.

PERRY NUCLEAR POWER PLANT USE FOR: STATE / COUNTY USE ONLY INITIAL CLASSIFICATIONS, INITIAL NOTIFICATION FORM CHANGES IN CLASSIFICATIONS, DATE: TIME:

CHANGES IN PROTECTIVE ACTION RECOMMENDATIONS. MESSAGE NO:

PNPP No. 7794 Rev. 6/5/2020 EPI-B1 EVENT TERMINATION

1. This is the: Perry Nuclear Power Plant

2. This is: An Actual Emergency A Drill

3. a. A(n) GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT was declared at: Now on Today based on EAL: FG1.1 (TIME) (DATE)

b. The Emergency situation has been terminated at: _ on ___

(TIME) (DATE)

c. The Protective Action Recommendation is being changed at: ____ on _

(TIME) (DATE)

4. The radiological conditions are:

a. A non-routine release of radioactive material, as a result of this event, is in progress.

b. The release of radioactive material associated with this event has been terminated.

c. NO Radiological Release in progress as a result of this event.

5. Utility Protective Action Recommendations (PARs):

a. Evacuation:

(check applicable subareas) 1 2 3 4 5 6 7 LAKE AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

b. Sheltering:

(check applicable subareas) 1 2 3 AND Evacuate the Lake AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

c. None For Utility Use Only Approved: Shiff T. Major .

PERRY NUCLEAR POWER PLANT USE FOR: STATE / COUNTY USE ONLY INITIAL CLASSIFICATIONS, INITIAL NOTIFICATION FORM CHANGES IN CLASSIFICATIONS, DATE: TIME:

CHANGES IN PROTECTIVE ACTION RECOMMENDATIONS. MESSAGE NO:

PNPP No. 7794 Rev. 6/5/2020 EPI-B1 EVENT TERMINATION

1. This is the: Perry Nuclear Power Plant

2. This is: An Actual Emergency A Drill

3. a. A(n) GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT was declared at: Now on Today based on EAL: FS1.1 (TIME) (DATE)

b. The Emergency situation has been terminated at: _ on ___

(TIME) (DATE)

c. The Protective Action Recommendation is being changed at: ____ on _

(TIME) (DATE)

4. The radiological conditions are:

a. A non-routine release of radioactive material, as a result of this event, is in progress.

b. The release of radioactive material associated with this event has been terminated.

c. NO Radiological Release in progress as a result of this event.

5. Utility Protective Action Recommendations (PARs):

a. Evacuation:

(check applicable subareas) 1 2 3 4 5 6 7 LAKE AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

b. Sheltering:

(check applicable subareas) 1 2 3 AND Evacuate the Lake AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.

The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.

c. None For Utility Use Only Approved: Shiff T. Major .

OT-3701-B33_504_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: B33, Reactor Recirculation Time Critical: No Alternate Path: Yes Setting: Simulator Applicability: RO/SRO Safety Function: 1 - Reactivity Control Validated Time: 21 Minutes

References:

SOI-B33 Rev. 43 and ARI-H13-P680-04 Rev. 26 Required Material: SOI-B33, Reactor Recirculation System SOI-B33, Attachment 38 ARI-H13-P680-04, Recirc Flow Control Task: 202-504-04-01 Recover a Reactor Recirc Loop Task Standard: Perform Startup of idle Recirc Pump (Mode 1) and upon receipt of High Vibration alarm, secure the pump IAW ARI-H13-P680-0004-E11, RCIRC B MOTOR VIB HI K/A: 202001, Recirculation System - A2.03, Ability to (a) predict the impacts of the following on the Recirculation System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Single recirculation pump trip.

Importance RO 3.6

1. Setup Instructions: Reset simulator to IC-112 for 2021 ILO NRC Exam. Run Schedule file JPM B33-504_RO.sch, Ensure Event file JPM B33-504_RO.evt loads. Verify ARI-H13-P680-04-E11 is clean. Provide Candidate with marked up copy of SOI-B33 Section 7.12. -

Prebriefing JPM recommended.

2. Location / Method: Simulator / Performance

3. Initial Condition: The plant was operating with both Recirc Pumps in fast speed. ONI-C51 was entered due to a Rx Recirc Pump B trip caused by an optical isolater problem. The optical isolater has been repaired. IAW ONI-C51, Recirc Pump B will be restarted. An I&C Tech is standing by to assist. SVI-B33-T1168 is in progress.

4. Initiating Cue: Unit Supervisor directs you the Reactor Operator to continue with restart the B Recirc Pump IAW SOI-B33 Section 7.12.2.

Start: Stop:

Candidate:

OT-3701-B33_504_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 SOI-B33, Reactor Recirculation System 7.12 Rcirc Pump Startup To Fast Speed NOTES

This section is used to restart a Recirc Pump that tripped from fast speed.

ONI-C51 requires performance of SVI-B33-T1170 when the running pumps JP LOOP TOT FLOW, 1B33-R612A(B), is 52 Mlbm/hr.

CAUTION Reducing the running loops flow while operating at less than the 61.9 % load line may result in a Reactor Recirculation Pump downshift to slow speed due to the feedwater flow interlock.

7.12.1 Verify restart of Recirculation Pump is directed by ONI-C51.

7.12.2 Verify the following for the oncoming RCIRC Pump:

The RCIRC Pump LOCKOUT RELAY 86 is reset at the breaker cubicle. BRKR 5B

The GENERATOR LOCKOUT RELAY 86G is reset at the Auxiliary Relay Panel.

1B33-P001B

The POWER INTERLOCK is in NORMAL on the Auxiliary Relay Panel.

1B33-S126B

The TOTAL FEEDWATER LOW FLOW INTERLOCK is in NORMAL at the Auxiliary Relay Panel. 1B33-S127B

The RCIRC PUMP DISCHARGE VALVE is open. 1B33-F067B

The RCIRC PUMP SUCTION VALVE is open. 1B33-F023B

The Reactor Recirculation Flow Control Valve Runback has been restored in accordance with Reactor Recirculation Flow Control Valve Runback Restoration.

Step 1 (continued next page)

OT-3701-B33_504_RO Rev 0 Step 1 (continued)

Standard: Candidate directs NLO to verify LO relays reset and switch positions.

Candidate verifies Suction and Discharge valves are open.

Candidate verifies no FCV Runback annunciator.

Instructor Cue: If asked, SVI-B33-T1170 is complete.

Notes: All in-plant items in Step 7.12.2 have been verified.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 2

BRKR 3 is closed. BRKR 3B

BRKR 4 is closed. BRKR 4B Critical Step Standard: Candidate closes the 3B and 4B breakers.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-B33_504_RO Rev 0 Step 3 7.12.2 Adjust the RCIRC LOOP FLOW CONTROL as follows: 1B33-K603B 7.12.3.a While monitoring the voltages in the following step, adjust the RCIRC LOOP FLOW CONTROL to between 8% and 10% VALVE TRAVEL.

7.12.3.b Confirm the voltage changes from 0 to ~ 68vdc at 1H13-P634 on Rack 2:

Between Terminal Pt 103 and ground. B Critical Step Standard: Candidate closes FCB B to 8-10% open.

Instructor Cue: An I&C Tech is standing by P634 to assist you.

When asked, Voltage is 68 VDC.

Notes: Driver - Event 1 will activate when FCV B <10% open. Alternatively, monitor FCV B position in INSIGHT using ZA1B33R0621B (0.1 to0.01).

When FCV B between 8-10% give a MARK SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-B33_504_RO Rev 0 Step 4 7.12.4 If the FCV does not open from 8%, then refer to Recovery From Failure To Open Flow Control Valve From Minimum Position.

7.12.5 Take RX LEVEL LOW L3 RCIRC PUMP RESET to the applicable position. 1B33-S113B 7.12.6 If necessary, then refer to IOI-3 to raise Reactor Power prior to performing the following step.

7.12.7 Verify the Total Rx Feedwater Flow (venturi) ICS Computer point consistently indicates >

3.43 Mlbm/hr.

7.12.8 Verify the RCIRC Flow Control Cavitation Runback is reset.

7.12.9 Within 15 minutes of idle pump startup, Perform SVI-B33-T1168, Idle Recirculation Loop Temperature and Flow.

7.12.10 If a FCV runback occurs during the following steps, then refer to Resetting RCIRC Flow Control Cavitation Runback.

Standard: The candidate reviews or performs actions for Steps 7.12.4 - 7.12.10.

Instructor Cue: For Step 7.12.6:

If asked if necessary to raise power, refer Candidate to Initial Conditions.

For Step 7.12.9:

If >15 minutes from JPM start, reply the SVI was reperformed and completed 3 minutes ago.

If <15 minutes from JPM start, inform Candidate that SVI-B33-T1168 was completed 7 minutes ago Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-B33_504_RO Rev 0 Step 5 7.12.11 Take the oncoming RCIRC PUMP BRKR to START. BRKR 5B Critical Step Standard: Candidate closes the 5B breaker control switch.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 6 7.12.13 Confirm the oncoming pump speed increases to approximately 1800 rpm as indicated on RCIRC PUMP SPEED.

7.12.14 If the flow control valve will not open from 8% while in fast speed, then refer to Recovery From Failure to Open Flow Control Valve From Minimum Position.

Standard: The candidate confirms pump speed increases and reviews Step 7.12.14.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-B33_504_RO Rev 0 Step 7 7.12.15 While maintaining total core flow approximately constant, match RCIRC Loop Flows Critical Step Standard: Candidate opens FCV B and closes FCV A to match loop flows.

Instructor Cue: None Notes: About 1 minute after Candidate starts opening FCV B, the B FCV vibration annunciator will alarm.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 8 ARI-H13-P680-0004-E11, RCIRC B MOTOR VIB HI 4.0 SUBSEQUENT OPERATOR ACTION 4.1 Attempt to reset the alarm by taking RCIRC MOTOR VIB HI ALARM RESET to the B position at 1H13-P680. 1B33A-S110.

4.2 If the alarm does NOT reset, then refer to IOI-3 and SOI-B33 and shift both Recirculation Pumps to slow speed.

Standard: The candidate responds to RCIRC B MOTOR VIB HI Annunciator and reviews ARI.

Candidate attempts to reset the vibration alarm.

Candidate determines both Recirc pumps need to be shifted to SLOW speed.

Instructor Cue: Inform Candidate you will take care of the Steps in IOI-3 and for him/her to proceed with the down shift IAW SOI-B33.

If candidate reviews IOI-3 and wants APRM gains adjusted, inform him/her I&C will adjust gains and Driver insert Event 30.

Notes: None, SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-B33_504_RO Rev 0 Step 9 SOI-B33, REACTOR RECIRCULATION SYSTEM 7.6 Transferring Rcirc Pumps from Fast to Slow Speed 7.6.1 If While executing this section, a FCV runback occurs, then refer to Section 7.22, Resetting RCIRC Flow Control Cavitation Runback and perform the actions.

7.6.2 If time permits, then perform the following:

7.6.2.a Refer to ATTACHMENT 38 and CONFIRM the Control Closing Circuit is functional. BRKR 2A BRKR 2B 7.6.2.b Take the LFMG A SUPPLY BRKR to CLOSE. BRKR 1A 7.6.2.c Confirm LFMG A supply voltage is 1190 - 1310 vac. (Check one or both indications)

Computer Point (on SPDS screen RPMPR) B33EA093

LFMG Panel Voltmeter 7.6.2.d Take the LFMG B SUPPLY BRKR to CLOSE. BRKR 1B 7.6.2.e Confirm LFMG B supply voltage is 1190 - 1310 vac. (Check one or both indications)

Computer Point (on SPDS screen RPMPR) B33EA094/094

LFMG Panel Voltmeter B33Q5002A/B Standard: The Candidate contacts Maintenance to perform Attachment 38.

Candidate closes both LFMG supply breakers.

Candidate confirms voltages are sat.

Instructor Cue: If asked, inform Candidate that Maintenance has completed Att. 38 and provide a copy.

If asked, local voltmeters B33Q5002A and B read 1250 VAC.

Notes: Candidate may determine insufficient time to perform Step 7.6.2.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-B33_504_RO Rev 0 Step 10 7.6.3 Simultaneously perform the following:

TAKE the RCIRC PUMP A BRKR 5 to XFER. BRKR 5A

TAKE the RCIRC PUMP B BRKR 5 to XFER. BRKR 5B Critical Step Standard: Candidate simultaneously transfers pumps to SLOW.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 11 7.6.4 Verify the RCIRC PUMP A BRKR opens. BRKR 5A 7.6.5 Verify the RCIRC PUMP B BRKR opens. BRKR 5B 7.6.7 When RCIRC PUMP SPEED indicates approximately 450 rpm, then verify the following breakers close:

LFMG OUTPUT BRKR BRKR 2A

LFMG OUTPUT BRKR BRKR 2B Standard: The Candidate verifies the 5A & B breakers open and the 2A &B breakers close and returns to the ARI for high vibrations Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-B33_504_RO Rev 0 Step 12 ARI-H13-P680-0004-E11, RCIRC B MOTOR VIB HI 4.0 SUBSEQUENT OPERATOR ACTION 4.3 Attempt to reset the alarm by taking RCIRC MOTOR VIB HI ALARM RESET to the B position at 1H13-P680. 1B33A-S110.

4.4 If the alarm does NOT reset, then PERFORM the following:

4.4.1 Trip RCIRC PUMP B.

Critical Step Standard: The Candidate attempts to reset the vibration alarm. [Non-Critical]

The Candidate trips Recirc Pump B. [Critical]

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Recirc Pump B was restarted, was downshifted when vibration annunciator alarmed and tripped when vibration alarm would not reset.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-B33_504_RO Rev 0 JPM CUE SHEET INITIAL

The plant was operating with both Recirc Pumps in fast speed.

CONDITIONS:

ONI-C51 was entered due to a Rx Recirc Pump B trip caused by an optical isolater problem.

The optical isolater has been repaired.

IAW ONI-C51, Recirc Pump B will be restarted.

An I&C Tech is standing by to assist.

SVI-B33-T1168 is in progress INITIATING CUE: Unit Supervisor directs you the Reactor Operator to continue with restart the B Recirc Pump IAW SOI-B33, Section 7.12.2.

OT-3701-E21_001_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: E21, Low Pressure Core Spray Time Critical: No Alternate Path: No Setting: Simulator Applicability: RO/SRO Safety Function: 2 - Reactor Water Inventory Control Validated Time: 19 Minutes

References:

SVI-E21-T2001 Rev. 34 Required Material: SVI-E21-T2001, Low Pressure Core Spray Pump And Valve Operability Test Task: 209-505-02-01 Perform LPCS Pump and Valve Operability Test Task Standard: Perform SVI-E21-T2001 to stroke test E21-F001 K/A: 209001 - A4.02, Ability to manually operate and/or monitor in the control room: Suction valves, Importance RO 3.5

1. Setup Instructions: Reset simulator to IC-111 Insert Schedule file JPM E21-001.sch. /

Driver needed for NLO communications and field actions. Verify stopwatch hanging on Key Box. Prebriefing JPM recommended.

2. Location / Method: Simulator / Performance

3. Initial Condition: Plant operating at power. Low Pressure Core Spray is in Standby.

SVI-E21-T2001, LPCS Pump and Valve Operability Test Prereqs and Step 5.1.1 are complete. NLOs are available to support in-field steps.

4. Initiating Cue: Unit Supervisor directs you as the Balance of Plant Operator to perform Step 5.1.2.1 of SVI-E21-T2001, LPCS Pump and Valve Operability Test.

Start: Stop:

Candidate:

OT-3701-E21_001_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 SVI-E21-T2001 Low Pressure Core Spray Pump and Valve Operability Test 5.0 SURVEILLANCE INSTRUCTION 5.1 Surveillance Test 5.1.2 Valve Operability Tests

1. 1E21-F001, LPCS SUPR POOL SUCTION VALVE (PI)

a. System Inoperable/ Available with Operator Action Tracking.

1) Inform US that LPCS system will be inoperable during performance of Step 5.1.2.1.b through Step 5.1.2.1.f:

2) If required, then record in the Narrative Log that 1E21C0001, LPCS PUMP, is inoperable but Available with Operator Action or if Operator Action to Restore Availability is not desired then 1E21C0001 is inoperable and unavailable.

3) Update the System Status Board to indicate the status of LPCS PUMP.

Standard: The Candidate reviews the SVI and determines that a PI needs to be performed, obtains the US signature, and updates the System Status Board.

Instructor Cue: When given the SVI for INOP signature, mark time & date and sign the SVI.

Inform Candidate that another Operator will make Narrative Log entry and update System Status Board.

Notes: The Prereqs section indicates a PI is required.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E21_001_RO Rev 0 Step 2

b. Perform the following:

1) Remove control power fuses for breaker EH1111.

a) CONTROL FUSE - CLOSE.

b) CONTROL FUSE - OPEN Standard: The Candidate contacts the NLO to remove control power fuses.

Instructor Cue: None Notes: Driver: When directed to remove control power fuses, initiate Event 4 and report fuses removed.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 3

c. Close 1E21-F001, LPCS SUPR POOL SUCTION VALVE, and record the following:

1) PI Verification - Closed direction:

Critical Step Standard: Candidate takes 1E21-F001 control switch to Close.

Instructor Cue: None Notes: Driver: Monitor 1E21-F001 travel in INSIGHT using lpvp1e21f0001.

(1= full open & 0=full closed) When valve is closed, report that Position Indication closed is SAT.

It takes about 1 minute 56 seconds for valve to stroke.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E21_001_RO Rev 0 Step 4

d. Open 1E21-F001, LPCS SUPR POOL SUCTION VALVE, and record the following:

1) PI Verification - Open direction:

Critical Step Standard: Candidate takes 1E21-F001 control switch to Open.

Instructor Cue: None Notes: Driver: Monitor 1E21-F001 travel in INSIGHT using lpvp1e21f0001.

(1= full open & 0=full closed. When valve is open, report that Position Indication open is SAT.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E21_001_RO Rev 0 Step 5

e. Independently verify open 1E21-F001, LPCS SUPR POOL SUCTION VALVE.

f. Perform the following:

1) Install control power fuses for breaker EH1111.

a) CONTROL FUSE - CLOSE.

b) CONTROL FUSE - OPEN

g. Complete SOI-R22 Attachment 3 - Verification Checklist Section 7.7, Racking in Switchgear Breakers to CONNECTED for EH1111.

h. Inform US that 1E21C0001 is operable and available with respect to this surveillance and to RECORD in the Narrative Log that 1E21C0001, LPCS PUMP is operable and available (if applicable).

Standard: Candidate asks for IV of 1E21-F001 position, directs NLO to install control power fuses and portion of verification checklist, and gives SVI to US for Operability signature.

Instructor Cue: If asked for Verification Checklist Section 7.7, inform Candidate that an NLO has completed the IV Checklist.

When handed the SVI for Operability signature, inform Candidate that the JPM is complete.

Notes: Driver: When directed to install control power fuses, Insert Event 5 and report fuses are installed.

Driver: When directed to complete Verification Checklist, respond that you will.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: The LPCS Suction valve, 1E21-F001 has been cycled closed and open.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-E21_001_RO Rev 0 JPM CUE SHEET INITIAL

Plant operating at power. Low Pressure Core Spray is in Standby.

CONDITIONS:

SVI-E21-T2001, LPCS Pump and Valve Operability Test Prereqs and Step 5.1.1 are complete.

NLOs are available to support in-field steps.

INITIATING CUE: Unit Supervisor directs you as the Balance of Plant Operator to perform Step 5.1.2.1 of SVI-E21-T2001, LPCS Pump and Valve Operability Test.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 1 of 43 LOW PRESSURE CORE SPRAY PUMP AND VALVE OPERABILITY TEST Surveillance Instruction Effective Date: 3-19-2020 Preparer: Kurt Jones / 3-6-2020 Date Approver: E. P. Condo / 3-10-2020 Date

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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34 2 of 43

1.0 DESCRIPTION

1.1 Scope Successful completion of this instruction will verify that the Low Pressure Core Spray (LPCS) PUMP, 1E21-C001, is OPERABLE at least once every 92 days by measuring pump parameters (i.e., differential pressure, flowrate, and vibration velocity) and verifying that the parameters are within acceptable or alert limits. This will satisfy the 1E21-C001, LPCS PUMP operability requirements of Inservice Testing Program and Technical Specification, SR 3.5.1.4, SR 3.5.2.6 and SR 3.5.2.8.

Successful completion of this instruction will satisfy the requirements of Exercise Open (EO), Exercise Closed (EC), Stroke Time (ST) and Position Indication (PI) as identified for the below listed valves. This will satisfy the valve operability requirements of Inservice Testing Program.

1E21-F001, LPCS SUPR POOL SUCTION VALVE (PI) 1E21-F003, LPCS Pump Disch Check (EC, EO) 1E21-F011, LPCS PUMP MIN FLOW VALVE (EC/EO, ST) 1E21-F012, LPCS TEST VALVE TO SUPR POOL (EC/EO) 1E21-F033, LPCS Wtr Leg Pump Disch Check (EC) 1E21-F034, LPCS Wtr Leg Pump Disch Vlv (EC) 1E21-F501, LPCS To Supr Pool Check (EO)

Successful completion of this instruction satisfies Technical Specification SR 3.6.1.3.5 to verify the isolation time for Primary Containment Isolation Valve (PCIV) 1E21-F011. It also partially satisfies Technical Specification SR 3.6.1.3.8 for 1E21-F011 and 1E21-F012.

Successful completion of this instruction satisfies the Channel Calibration requirement of Technical Specification 3.3.3.1-1.9 and SR 3.3.3.1.3 for 1E21-F011 and 1E21-F012.

1.2 Frequency Section 5.1.2: At least once every 24 months/2 years as noted below.

Section 5.1.3: At least once per 92 days, unless noted below.

Position Indication Channel Calibration required at least once every 24 months for 1E21-F011 and 1E21-F012.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 3 of 43 Position Indication (PI) Verification required at least once every 2 years (731 days) for 1E21-F001.

As required for post-maintenance testing, repair or replacement.

1.3 Technical Specification Applicable MODES Mode 1, Modes 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure d150 psig, Mode 4, Mode 5 except with the reactor vessel head and steam dryer storage/reactor well gate removed and water level t22 ft 9 inches over the top of the reactor pressure vessel flange, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation.

2.0 PRECAUTIONS AND LIMITATIONS

1. Step numbers marked with a dollar sign ($) immediately to the left are required by Technical Specifications. Such items, if found to exceed their Allowable Values, may be NRC reportable and shall be brought to the attention of the Unit Supervisor immediately.

2. Observe the appropriate operating precautions for LPCS from SOI-E21.

3. Verifying that remote position indication accurately reflects actual valve stem travel direction as observed locally performs a Position Indication (PI) Verification. In some cases indications such as system flow during pump testing should be used as supplemental verifications of valve position. Supplemental verifications do not satisfy performance of Position Indication (PI) Verifications.

4. Discontinue testing in the event of a LOCA or LOOP signal. Contact the Unit Supervisor for disposition of the instruction and restoration of the affected systems.

5. Valve stroke time is measured from initiation of the control signal to receipt of desired position indication and recorded to the nearest tenth of a second.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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34 4 of 43

6. When taking vibration data, place the accelerometer probe on the V1, H1 or A1 to localize placement on the upper motor bearing housing.

The accelerometer probe should be perpendicular to the equipment surface when taking a reading and the accelerometer extension probe should not be used. Vibration readings will be taken on the lowest possible range.

7. Performance of ISI-E21-T1100-2, Low Pressure Core Spray (E21)

Functional Pressure Test Class 2 shall be in conjunction with this instruction when required to be performed per the ISI Unit.

8. If measured pump values fall within the required action range, the pump shall immediately be declared inoperable. Notify the ISI Unit.

9. All steps are to be performed in sequence in each section, unless otherwise stated, however each section may be performed in any order per Unit Supervisor direction.

10. LCPS shall not be run in Test Mode when SPCU is in operation through the Suppression Pool Return Line Bypassing RHR A. Operation in this condition could result in loss of flow to the SPCU pump.

11. Care must be taken when performing the Exercise Closed (EC) verification for 1E21-F033. If valve degradation has occurred, a forceful stream of water may be present.

12. If a valve fails to stroke or does not meet its stroke time acceptance criteria, it shall be immediately declared inoperable.

13. Prior to performing oil sampling, contact the Chemistry Unit to determine the required oil sample volume and obtain sample bottles. If this SVI is being performed for any reason other than normal performance (i.e., W.O. retest), DO NOT take a lube oil sample and N/A all applicable steps.

14. Prior to removal of control power fuses for 1E21-C001, LPCS PUMP, (Section 5.1.2), Attachment 5, Section A must be completed to take credit for Operator Action to Restore Availability.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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34 5 of 43

15. Operating the LPCS system in any secondary mode of operation (e.g., Test Return mode) will potentially inhibit the LPCS system from meeting the Technical Specification response time requirements.

Therefore, LPCS shall be declared inoperable whenever it is in a secondary mode of operation or a valve in a secondary path is opened for stroke time testing.

16. ICS point E21EE001 is a 1-minute smoothed average of point E21EA001. Allow sufficient time (approximately 2 to 3 minutes) for stabilization. ICS point E21EA001 may be used in lieu of point E21EE001 at any time. ICS point E21EA001 is preferred when making flow adjustments due to faster update time.

17. If ICS is not available, flow rates will be measured with the digital multimeter (DMM) installed at 1E21-R600. Where a specific flow rate is referenced, a corresponding voltage will be identified in parentheses next to the ICS value [e.g., Verify Exercise Open by obtaining at least 6.110 kGPM as read on E21EA001 (3.444 VDC)]. When flow rate readings are required, the voltage reading on the DMM will be recorded and converted to kGPM using Attachment 4, VDC to kGPM Conversion Table. If ICS is available, N/A recording blocks for VDC unless specifically noted.

18. Snubbers may be used with test gauges to dampen fluctuations.

Throttling of instrument valves may also be used to dampen fluctuations if the correct position of the throttled valve is verified later in the instruction (e.g., test gauge is removed).

19. Operating a motor driven ECCS pump with an open test valve to the suppression pool will make 1E21C0001, LPCS Pump, inoperable in Section 5.1.3.

20. LPCS PUMP is required to be started prior to being declared operable if pump breaker is racked out.

21. When directed to log equipment operable/inoperable or available/unavailable in the Narrative Log, the entry only needs to be made if it reflects a change in the true status of the equipment.

22. ADHR System will not be available during performance of this test.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

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34 6 of 43 3.0 MANPOWER AND EQUIPMENT 3.1 Manpower/Location/Communication

1. Control Room operator to collect data and perform switch manipulations for testing.

2. Two (2) operators in the Auxiliary Building (with communications) to operate manual valves, exercise check valve, monitor operation of LPCS pump, collect data, and obtain oil samples.

3. Technician or operator to take vibration measurements.

4. An assigned operator in the vicinity of 4.16kv Bus EH11 (CC-620) during the time LPCS PUMP breaker EH1111 is in disconnect position.

5. If a PI is being performed, operator(s) (with communications) to observe the below listed valves:

1E21-F001 Location AXD/08-574 1E21-F011 Location AXC/07-599 1E21-F012 Location AXC/07-599

6. I&C Technician(s) to connect DMM to 1E21-R600 (if required) and install test gauges (LPCS INSTRUMENT RACK, 1H22-P001).

7. Chemistry Unit to evaluate lube oil sample volume.

(INTENTIONALLY BLANK)

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

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34 7 of 43 3.2 Required Measuring and Test Equipment (M&TE)

1. Calibrated stopwatch, Robics SC-700 or equivalent.

2. CSI 2130 or equivalent.

NOTE Most digital gauges are calibrated to % of full scale. The 0-500 psig, r0.10%

gauge is calibrated to r0.5 psig at any reading obtained. The OM Code requires an accuracy of 0.5% of reading. The reference value for the 0-500 psig gauge use is 310 psig. This equates to 0.17% at 310 psig for a 0.1% accurate gauge. If an equivalent (analog or digital) gauge is used, it must be accurate to 0.5% or better at 310 psig. For digital gauges the 310 psig reference value cannot exceed 90%

of full scale and analog gauges full scale range must be less than 3 times the 310 psig reference value.

3. 1 - Calibrated test pressure gauge, 0-500 psig, accuracy r 0.10% or equivalent.

NOTE Most digital gauges are calibrated to % of full scale. The 0-15 psig, r0.10% gauge is calibrated to r0.015 psig at any reading obtained. The OM Code requires an accuracy of 0.5% of reading. The reference value for the 0-15 psig gauge use is 7.5 psig. This equates to 0.2% at 7.5 psig for a 0.1% accurate gauge. If an equivalent (analog or digital) gauge is used, it must be accurate to 0.5% or better at 7.5 psig. For digital gauges the 7.5 psig reference value cannot exceed 90% of full scale and analog gauges full scale range must be less than 3 times the 7.5 psig reference value.

4. 1 - Calibrated test pressure gauge, 0-15 psig, accuracy r 0.10% or equivalent.

5. 1 - Calibrated test pressure gauge, 0-150 psig, accuracy r 2.0% or equivalent.

6. Fluke 8050 DMM or equivalent (if required).

7. Tape measure or ruler.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

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34 8 of 43 3.3 Additional Tools and Equipment

1. SVI-E21-T1181, Low Pressure Core Spray Venting and Valve Lineup Verification.

2. SOI-E21, Low Pressure Core Spray System.

3. At least 2 Lube Oil Sample Bottles (volume determined by Chemistry).

4. Valve locking devices (1) - green and (1) - tan.

5. 3/4 fill hose with manifold (reference Attachment 3) for Exercise Closed of 1E21-F033 (manifold should consist of isolation valve(s), 0-150 psig pressure gauge, vent path to fill and vent the pressure gauge, and fittings). Contact I&C for test manifold.

6. Test manifolds for venting 0-15 and 0-500 psig test gauges.

7. Flashlight for Position Indication (PI) Verification.

(INTENTIONALLY BLANK)

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

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34 9 of 43 4.0 PREREQUISITES Initials NOTES x 1E21-F001, LPCS SUPR POOL SUCTION VALVE, PI required once every 2 years for ISTP.

x 1E21-F0011, LPCS PUMP MIN FLOW VALVE and 1E21-F012, LPCS TEST VALVE TO SUPR POOL, PI required once every 24 months for Channel Calibration.

x 1E21-F0011 and 1E21-F012, EC/EO required once every 24 months for ISTP.

1. OBTAIN USs Work Start Approval signature on the Test Cover Sheet/Surveillance Order. ICR

2. HAVE US determine EC/EO requirements for 1E21-F011 and 1E21-F012 and PI verification requirements from the Equipment ID associated with this instruction and check appropriately:

1E21-F001 YES NO 1E21-F011 YES NO 1E21-F012 YES NO ICR

3. IF EC/EO and PI Verification is checked NO, THEN mark Section 5.1.2 as N/A. ICR

4. The plant is in any Mode with LPCS system in Standby Readiness in accordance with SOI-E21. ICR

5. CONFIRM ADHR is not in operation using the common Shutdown Cooling suction header, RHR A Shutdown Cooling return, LPCS Suppression Pool suction or LPCS Suppression Pool return. (i.e., 1G40-F018, 1G40-F053, 1G40-F019 and 1G40-F051 are closed). ICR

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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34 10 of 43 SECTION 4.0 Initials NOTE Step 4.0.6 through Step 4.0.13 may be performed in any order.

6. RECORD M&TE and VERIFY the calibration current on all M&TE.

IF a partial surveillance is to be performed, THEN only the appropriate data must be recorded. ICR EQUIPMENT FLoc CAL DATE DUE DATE CSI 2130 STOPWATCH GAUGE (0-15)

GAUGE (0-500)

GAUGE (0-150)

DMM *

if used NOTE If credit for operator action to restore availability is not desired, N/A Step 4.0.7.

7. COMPLETE Attachment 5, Operator Action to Restore Availability Checklist, Section A, TASK ASSIGNMENT. N/A NOTE Step 4.0.8 through Step 4.0.13 may be marked N/A if Section 5.1.3 is not to be performed.

8. VERIFY SPCU is not in operation through the Suppression Pool Return Line Bypassing RHR A. ICR

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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34 11 of 43 SECTION 4.0 Initials

9. IF ICS is out-of-service, THEN I&C connect Fluke 8050 DMM to 1E21-R600 as follows:

OTHERWISE N/A this Step:

x CONNECT the DMM to 1E21-R600 (+) and (-) terminals (meter will range between 1 and 5 VDC).

N/A Independent Verifier:

10. CONTACT Chemistry Unit to determine the required lube oil sample volumes needed and to obtain sample bottles. ICR NOTE N/A Step 4.0.11 if performing the pump test only (i.e., not performing Step 5.1.3.21, 1E21-F033 Exercise Closed (EC) verification).

11. A Fire Impairment/Barrier Removal Permit, in accordance with FPI-A-C01, Section 6.2.6, will be required for Door No. AX208 or AX209. ICR NOTE Pressure dampening devices may be installed, in test gauge lines only, to ensure stable pressure readings.

CAUTION Following steps may release potentially contaminated water. Observe proper radiological precautions to contain liquid and limit spread of contamination.

12. INSTALL 0-500 psig test gauge in parallel with pressure indicator 1E21-R002 at 1E21-R002-D as follows (Panel 1H22-P001):

a. VERIFY closed 1E21-R002-C. TNO

b. DISCONNECT calibration tubing from HOKE vlv 1E21-R002-D. TNO Independent Verifier: IVR

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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34 12 of 43 SECTION 4.0 Initials

c. INSTALL test manifold and test gauge (0-500 PSIG).

Position gauge at same elevation as 1E21-R002. TNO

d. VERIFY instrumentation is filled and vented by opening 1E21R002-D and 1E21R002-C. TNO

e. VERIFY closed 1E21-R002-C. TNO Independent Verifier: IVR

f. VERIFY closed HOKE valve 1E21-R002-D. TNO Independent Verifier: IVR

13. INSTALL 0-15 psig test gauge in parallel with pressure transmitter 1E21-N071 at 1E21-N071-D as follows (Panel 1H22-P001):

a. VERIFY closed test valve 1E21-N071-C. TNO

b. DISCONNECT calibration tubing from HOKE vlv 1E21-N071-D. TNO Independent Verifier: IVR

c. INSTALL test manifold and test gauge (0-15 PSIG).

POSITION the gauge at same elevation as 1E21-N071. TNO

d. VERIFY instrumentation is filled and vented by opening 1E21-N071-D and 1E21-N071-C. TNO

e. VERIFY closed test valve 1E21-N071-C. TNO Independent Verifier: IVR

f. VERIFY closed HOKE vlv 1E21-N071-D. TNO Independent Verifier: IVR

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

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34 13 of 43 5.0 SURVEILLANCE INSTRUCTION Initials 5.1 Surveillance Test 5.1.1 Test Authorization

1. OBTAIN the Reactor Operators Test Start Approval signature on the Test Cover Sheet/Surveillance Order.

2. PRINT LEAD TEST PERFORMERS name on Attachment 6.

DETACH list and GIVE to Reactor Operator.

NOTE Controls and indicators used in this section are located on 1H13-P601, EMERGENCY CORE COOLING SYSTEMS BENCHBOARD unless otherwise indicated.

5.1.2 Valve Operability Tests

1. 1E21-F001, LPCS SUPR POOL SUCTION VALVE (PI)

a. System Inoperable/ Available with Operator Action Tracking.

1) INFORM US that LPCS system will be inoperable during performance of Step 5.1.2.1.b through Step 5.1.2.1.f:

/

Time Date U.S. Signature

2) IF required, THEN RECORD in the Narrative Log that 1E21C0001, LPCS PUMP, is inoperable but Available with Operator Action or if Operator Action to Restore Availability is not desired then 1E21C0001 is inoperable and unavailable.

3) UPDATE the System Status Board to indicate the status of LPCS PUMP.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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34 14 of 43 SECTION 5.1.2 Initials

b. PERFORM the following:

1) REMOVE control power fuses for breaker EH1111.

a) CONTROL FUSE - CLOSE b) CONTROL FUSE - OPEN

$ c. CLOSE 1E21-F001, LPCS SUPR POOL SUCTION VALVE, and RECORD the following:

1) PI Verification - Closed direction:

SAT UNSAT N/A

d. OPEN 1E21-F001, LPCS SUPR POOL SUCTION VALVE and RECORD the following:

$ 1) PI Verification - Open direction.

SAT UNSAT N/A

e. INDEPENDENTLY VERIFY open 1E21-F001, LPCS SUPR POOL SUCTION VALVE.

f. PERFORM the following:

1) INSTALL control power fuses for breaker EH1111:

a) CONTROL FUSE - OPEN b) CONTROL FUSE - CLOSE

g. COMPLETE SOI-R22 Attachment 3 - Verification Checklist Section 7.7, Racking In Switchgear Breakers to CONNECTED for EH1111.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 15 of 43 SECTION 5.1.2 Initials

h. INFORM US that 1E21C0001 is operable and available with respect to this surveillance and to RECORD in the Narrative Log that 1E21C0001, LPCS PUMP is operable and available (if applicable).

/

Time Date US Signature

2. 1E21-F011, LPCS PUMP MIN FLOW VALVE (EC/EO, PI (SR 3.3.3.1.3), ST)

NOTE Steps 5.1.2.2.a and 5.1.2.2.b may be performed in any order.

$ a. CLOSE 1E21-F011, LPCS PUMP MIN FLOW VALVE, MEASURE stroke time, and RECORD the following:

1) Exercise Closed Results:

SAT UNSAT

2) PI Verification - Closed direction:

SAT UNSAT N/A

3) Stroke Time - Closed direction.

__________ seconds Acceptable Value = d 23.5 seconds SAT UNSAT

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 16 of 43 SECTION 5.1.2 Initials

$ b. OPEN 1E21-F011, LPCS PUMP MIN FLOW VALVE, and RECORD the following:

1) Exercise Open Results:

SAT UNSAT

2) PI Verification - Open direction:

SAT UNSAT N/A

$ c. VERIFY Open 1E21-F011, LPCS PUMP MIN FLOW VALVE.

5.1.3 LPCS Pump and Valve Operability

1. PERFORM the following prior to starting LPCS Pump:

a. VERIFY SPCU is not in service returning to RHR A.

b. CHECK LPCS PUMP bearing oil levels are at the standstill level r 1/8 inch.

2. PERFORM the following to place the 0-15 psig test gauge (1H22-P001) in service:

a. Open HOKE valve 1E21-N071-D.

b. Open test valve 1E21-N071-C.

3. OBSERVE and RECORD 1E21-C001, LPCS PUMP Stopped-Suction pressure (suction pressure reference value approximately 9 psig) from test gauge at 1E21-N071:

_________ psig SAT (t 5.0 psig) UNSAT

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 17 of 43 SECTION 5.1.3 Initials NOTE M&TE installed at 1E21-R002 is removed from service because the test gauge may experience an over ranged condition. Closing 1E21-F012 will cause a high pump discharge pressure (i.e., t 390.0 psig).

4. VERIFY removed from service 0-500 psig test gauge (i.e., parallel with 1E21-R002) at 1E21-R002-D:

a. CLOSE test valve 1E21-R002-C.

b. CLOSE HOKE vlv 1E21-R002-D.

5. OBTAIN ICS traces or screen prints of the following points and LABEL, SIGN and ATTACH them to this SVI.

IF ICS is not available, THEN RECORD data from the listed instruments, OTHERWISE N/A data blocks.

a. Suppression Pool level (At 1H13-P625)

G43EA003 E22N655C ________

G43EA006 or E22N655G ________

b. Containment Pressure D23EA003 D23R024A ________

D23EA017 or D23R024B ________

c. Suppression Pool Temp. D23R220A ________

D23EA010 or D23R220B ________

NOTE Confirming annunciator LPCS PUMP DISCH PRESS LO reset verifies 1E21-F003, LPCS Pump Disch Check closed.

$ 6. CONFIRM that annunciator LPCS PUMP DISCH PRESS LO, 1H13-P601-21A-G6 reset:

SAT (alarm reset) UNSAT

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 18 of 43 SECTION 5.1.3 Initials

7. System Inoperable

a. INFORM US that LPCS System is inoperable during the performance of Step 5.1.3.9 through Step 5.1.3.26:

/

Time Date US Signature

b. IF required, THEN RECORD in the Narrative Log that 1E21C0001, LPCS PUMP, is inoperable while in the secondary mode of operation.

c. UPDATE the System Status Board to show that LPCS PUMP is inoperable while in the secondary mode of operation.

NOTE The following Step 5.1.3.8 will make annunciator ADS A PERMISSIVE LPCS/RHR A RUN, 1H13-P601-19A-F9 come on.

8. START 1E21-C001, LPCS PUMP in accordance with SOI-E21 Section 7.3, LPCS Test Mode Startup.

CAUTION 1E21-C001, LPCS PUMP flow rate shall not exceed 8.05 kGPM (4.22 VDC), as read on 1E21-R600. With 1E21-F012, LPCS TEST VALVE TO SUPR POOL fully open, pump flow rate will be approximately 8.00 kGPM.

$ 9. FULLY OPEN 1E21-F012, LPCS TEST VALVE TO SUPR POOL and RECORD the following:

a. Open Results: SAT UNSAT

b. PI Open Results: SAT UNSAT N/A

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 19 of 43 SECTION 5.1.3 Initials

10. RECORD unthrottled flow rate from E21EA001 (or record VDC and CONVERT to kGPM): ________ VDC ________ kGPM NOTE ICS point E21EA001 may be used in lieu of point E21EE001 at any time. Ref.

P&L 16.

11. VERIFY 1E21-F003, LPCS Pump Disch Check, and 1E21-F501, LPCS To Supr Pool Check Vlv exercise open (EO) by obtaining at least 6.110 kGPM (3.444 VDC) as read from E21EE001.

$ a. 1E21-F003, LPCS Pump Disch Check exercise open:

SAT (t 6.110 kGPM/3.444 VDC) UNSAT

$ b. 1E21-F501, LPCS to Supr Pool Check Vlv exercise open:

SAT (t 6.110 kGPM/3.444 VDC) UNSAT

12. IF Step 4.0.2 was marked YES for 1E21-F012, THEN CONFIRM supplemental PI verification by obtaining an open indication with a flow rate of t 6.110 kGPM (t 3.444 VDC) for the following valves.

a. 1E21-F001, LPCS SUPR POOL SUCTION VALVE:

SAT (Red Energized/t 6.110 kGPM) UNSAT

b. 1E21-F012, LPCS TEST VALVE TO SUPR POOL:

SAT (Red Energized/t 6.110 kGPM) UNSAT

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 20 of 43 SECTION 5.1.3 Initials NOTE 1E21-F011, LPCS PUMP MIN FLOW VALVE should start to open when 1E21-C001, flow rate decreases below 1.350 kGPM (1.54 VDC).

$ 13. CLOSE 1E21-F012, LPCS TEST VALVE TO SUPR POOL, and RECORD the following:

a. Exercise Closed Results:

SAT UNSAT

b. PI Closed Results:

SAT UNSAT N/A

14. VERIFY open 1E21-F011, LPCS PUMP MIN FLOW VALVE.

NOTE A differential pressure of 311.0 r 1.0 psid should be achieved at approximately 6.305 kGPM (3.522 VDC) flow rate.

15. THROTTLE open 1E21-F012, LPCS TEST VALVE TO SUPR POOL until E21EA001 indicates a flow rate of approximately 6.305 kGPM (3.522 VDC).

NOTE 1E21-F011, LPCS PUMP MIN FLOW VALVE should start to close when 1E21-C001, LPCS PUMP flowrate increases above 1.350 kGPM (1.54 VDC).

16. VERIFY 1E21-F011, LPCS PUMP MIN FLOW VALVE closes, when E21EA001 indicates ! 1.350 kGPM (1.54 VDC).

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 21 of 43 SECTION 5.1.3 Initials CAUTION M&TE installed at 1E21-R002 may be over-ranged if 1E21-R002 t 390.0 psig.

17. PLACE in-service 0-500 psig test gauge in parallel with pressure indicator 1E21-R002 at 1E21-R002-D:

a. VERIFY pump discharge pressure is 390.0 psig, as read on 1E21-R002 (1H22-P001).

b. OPEN HOKE vlv 1E21-R002-D.

c. OPEN test valve 1E21-R002-C.

NOTE When performing ISI-E21-T1100-2, verification that the LPCS system is in operation for ten (10) minutes shall commence once a differential pressure t 310.0 psid is established.

18. THROTTLE 1E21-F012, LPCS TEST VALVE TO SUPR POOL until a 1E21-C001 differential pressure of as close as practical to 310.0 psid and within the range of 310.0 to 313.0 psid as calculated below, verification not required:

(suction pressure reference value approximately 9 psig)

Discharge pressure from test gauge at 1E21-R002: _________ psig

- Suction pressure from test gauge at 1E21-N071: - psig

= Differential pressure = psid

19. VERIFY 1M39-B006, LPCS PMP RM CLG FAN automatically starts by indication on 1H13-P800, HVAC CONTROL PANEL:

SAT (Fan Auto Started) UNSAT

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 22 of 43 SECTION 5.1.3 Initials

20. PERFORM 1E21-F034, LPCS Wtr Leg Pump Disch Vlv (AXC/07-568), exercise closed (EC) as follows:

a. UNLOCK and CLOSE 1E21-F034 using the handwheel.

$ b. 1E21-F034, LPCS Wtr Leg Pump Disch Vlv exercise closed (EC) as demonstrated by free movement of handwheel to the Closed position:

SAT (free movement) UNSAT

21. PERFORM 1E21-F033, LPCS Wtr Leg Pump Disch Check (AXC/07-568) exercise closed (EC) as follows:

a. CONNECT 3/4 supply hose to 1P21 or 1P22 water source.

b. CONTACT Shift Engineer and REQUEST permission to impair fire Door No. AX208 or AX209.

c. UNCAP and CONNECT the test manifold (with pressure gauge) to 1E21-F530, LPCS Wtr Leg Pump Disch Vent (AXC/07-574) (refer to Attachment 3).

d. CONNECT supply hose to test manifold.

e. OPEN 1P21 or 1P22 Supply Valve and RECORD initial pressure on test manifold gauge: _______ psig.

(INTENTIONALLY BLANK)

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 23 of 43 SECTION 5.1.3 Initials NOTE Observing a pressure drop of 5.0 psi with 1E21-F530 open satisfies 1E21-F033 exercise closed (EC).

CAUTION Care must be taken when opening 1E21-F530 since 1E21-C001 running discharge pressure is greater than 1P21 or 1P22 operating pressure.

f. UNLOCK and THROTTLE open 1E21-F530.

g. RECORD final test manifold pressure: _______ psig.

h. CALCULATE pressure drop:

_______ psig - _______ psig = _______ psi (Initial) (Final) (Pressure Drop)

Independent Verifier:

i. CLOSE and LOCK 1E21-F530.

Independent Verifier:

$ j. VERIFY 1E21-F033, LPCS Wtr Leg Pump Disch Check exercise closed (EC) of was satisfied by obtaining less than a 5.0 psig pressure drop:

SAT (< 5.0 psig) UNSAT (t 5.0 psig)

k. CLOSE 1P21 or 1P22 water supply valve.

l. DISCONNECT test manifold and INSTALL pipe cap at test connection 1E21-F530.

Independent Verifier:

m. DISCONNECT supply hose from 1P21 or 1P22 water source.

n. CONTACT Shift Engineer to deactivate Fire Impairment/

Barrier Removal Permit for Door No. AX208 or AX209.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 24 of 43 SECTION 5.1.3 Initials

o. REMOVE all test equipment.

Independent Verifier:

22. ALLOW differential pressure to stabilize between 310.0 to 313.0 psid for at least five minutes.

23. MEASURE, RECORD and/or CALCULATE the following for 1E21-C001, LPCS PUMP, as applicable:

a. RECORD discharge and suction pressures, and CALCULATE pump differential pressure as follows:

(suction pressure reference value approximately 9 psig)

Discharge pressure from test gauge at 1E21-R002: _________ psig

- Suction pressure from test gauge at 1E21-N071: - psig

= LPCS Pump, 1E21-C001, Differential pressure = psid Independent Verifier:

$ b. VERIFY proper pump differential pressure of 310.0 to 313.0 psid:

SAT (of 310.0 to 313.0 psid) UNSAT

$ c. RECORD flow rate from E21EE001 (or record VDC, see Narrow Range table on Attachment 4 for conversion):

_______ VDC ______ kGPM Reference Value = 6.305 Acceptable Range = 6.110 to 6.683 Alert Range = N/A Req Act Range Low = < 6.110 Req Act Range High = > 6.683 SAT (6.110 to 6.683kGPM) UNSAT

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 25 of 43 SECTION 5.1.3 Initials

d. VERIFY H1, V1, and A1 Vibration Data Points are visible (reference Attachment 2 for locations):

H1: YES (visible) NO (not visible)

V1: YES (visible) NO (not visible)

A1: YES (visible) NO (not visible)

$ e. MEASURE and RECORD Vibration Velocity data for the following upper motor bearing housing data points:

ITEM HORZ (H1) in/sec VERT (V1) in/sec AXIAL (A1) in/sec Reading in/sec in/sec in/sec Ref Value 0.120 0.210 0.045 Accept Range d0.300 d0.325 d0.112 Alert Range >0.300 to d0.700 >0.325 to d0.700 >0.112 to d0.270 Req Act Range >0.700 >0.700 >0.270 Horz (H1): SAT (d0.700) UNSAT (>0.700)

Vert (V1): SAT (d0.700) UNSAT (>0.700)

Axial (A1): SAT (d0.270) UNSAT (>0.270)

f. RECORD flow rate from 1E21-R600: ________ kGPM.

24. IF desired to obtain pump data at different values of flow rate and differential pressure, THEN PERFORM FTI-F0039 at the direction of the RSE or IST Engineer with concurrence of the US.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 26 of 43 SECTION 5.1.3 Initials NOTE M&TE installed at 1E21-R002 is removed from service because the test gauge may experience an over ranged condition. Closing 1E21-F012 will cause a high pump discharge pressure (i.e., t 390.0 psig).

25. REMOVE 0-500 psig test gauge (i.e., parallel with 1E21-R002) at 1E21-R002-D from service:

a. CLOSE test valve 1E21-R002-C.

Independent Verifier:

b. CLOSE HOKE vlv 1E21-R002-D.

Independent Verifier:

NOTE The following step ensures that LPCS has been operated for at least ten (10) minutes with flow through the Test Return Line. [SR 3.5.2.6].

$ 26. VERIFY that 1E21-F012, LPCS TEST VALVE TO SUPR POOL has been open for at least ten (10) minutes.

$ 27. CLOSE 1E21-F012, LPCS TEST VALVE TO SUPR POOL.

28. VERIFY open 1E21-F011, LPCS PUMP MIN FLOW VALVE.

29. PERFORM the following:

a. INFORM the US that LPCS has been restored.

/

Time Date U.S. Signature

b. IF required, THEN RECORD in the Narrative Log that 1E21C0001, LPCS PUMP, is operable and available with respect to this surveillance.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 27 of 43 SECTION 5.1.3 Initials NOTE N/A Step 5.1.3.30, if Step 5.1.3.20 was not performed.

30. THROTTLE open 1E21-F034, LPCS Wtr Leg Pump Disch Vlv (AXC/07-574) as follows:

a. PERFORM dual concurrent verification to throttle 1E21-F034 one (1) turn open.

Concurrent Verifier:

b. LOCK 1E21-F034 in the throttled position.

31. STOP 1E21-C001, LPCS PUMP in accordance with SOI-E21 Section 7.4, LPCS Test Mode Shutdown.

32. STOP 1M39-B006, LPCS PUMP ROOM COOLER, at 1H51-P037, Pump Room Clg HVAC Cont Pnl Division 1 & 3(AXB/03-599).

NOTE Step 5.1.3.33 through Step 5.1.3.37 may be performed in any order or in parallel as directed by the Unit Supervisor.

$ 33. VERIFY 1E21-F003, LPCS Pump Disch Check exercise closed (EC) by confirming annunciator LPCS PUMP DISCH PRESS LO, 1H13-P601-21A-G6, reset:

SAT (Reset) UNSAT

34. IF DMM was not installed, THEN N/A this Step 5.1.3.34.

IF installed, THEN REMOVE DMM installed at 1E21-R600 (+) and (-)

terminals.

Independent Verifier:

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 28 of 43 SECTION 5.1.3 Initials

35. OBTAIN ICS traces or screen prints of the following points and LABEL, SIGN and ATTACH them to this SVI.

IF ICS is not available, THEN RECORD data from the listed instruments, OTHERWISE N/A data blocks.

a. Suppression Pool level (At 1H13-P625)

G43EA003 E22N655C ________

G43EA006 or E22N655G ________

b. Containment Pressure D23EA003 D23R024A ________

D23EA017 or D23R024B ________

c. Suppression Pool Temp. D23R220A ________

D23EA010 or D23R220B ________

NOTE Oil samples must be taken as soon as possible following 1E21-C001 shutdown to ensure a representative sample is obtained.

36. OBTAIN the LPCS PUMP oil samples from the pump Upper and Lower reservoirs as follows (EQ requirement):

a. REMOVE plug and OPEN 1E21-F616A, LPCS Pmp Upper Oil Sample Drain Valve (AXC/08-568).

b. DRAW the required oil sample from the Upper Oil Reservoir. LABEL the sample with equipment name, equipment ID, sample point and date.

c. CLOSE 1E21-F616A, LPCS Pmp Upper Oil Sample Drain Valve and REINSTALL plug.

Independent Verifier:

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 29 of 43 SECTION 5.1.3 Initials NOTE Step 5.1.3.36.d may be N/A if reservoir level is within the standstill level r 1/8 inch.

d. FILL Upper Oil Reservoir to the standstill level r 1/8 inch and INSTALL fill plug.

Independent Verifier:

e. REMOVE plug and OPEN 1E21-F616B, LPCS Pump Lower Oil Sample Drain Valve (AXC/08-568).

f. DRAW the required oil sample from Lower Oil Reservoir.

LABEL the sample with the equipment name, FLoc, sample point and date.

g. CLOSE 1E21-F616B, LPCS Pump Lower Oil Sample Drain Valve and REINSTALL plug.

Independent Verifier:

NOTE Step 5.1.3.36.h may be N/A if reservoir level is within the standstill level r 1/8 inch.

h. FILL Lower Oil Reservoir to the standstill level r 1/8 inch and INSTALL fill plug.

Independent Verifier:

37. At 1H22-P001, PERFORM the following:

a. CLOSE test valve 1E21-N0071-C.

Independent Verifier:

b. CLOSE HOKE vlv 1E21-N0071-D.

Independent Verifier:

c. DISCONNECT test gauge from HOKE vlv 1E21-N0071-D.

Independent Verifier:

d. INSTALL calibration tubing at HOKE vlv 1E21-N0071-D.

Independent Verifier:

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 30 of 43 SECTION 5.1.3 Initials

e. DISCONNECT test gage from HOKE vlv 1E21-R002-D.

Independent Verifier:

f. CONNECT calibration tubing at HOKE vlv 1E21-R002-D.

Independent Verifier:

38. Initiate a Condition Report if Vibration data is outside of the Acceptable Range.

5.2 Plant/System Restoration NOTE Section 5.2 steps may be performed in any order or in parallel, at Unit Supervisor discretion.

1. VERIFY LPCS full of water in accordance with SVI-E21-T1181, Low Pressure Core Spray Venting and Valve Lineup Verification, at US discretion. At a minimum PERFORM System Venting in accordance with SVI-E21-T1181.

2. COMPLETE Attachment 1, System Restoration Checklist using the methods of Independent Verification.

3. DELIVER the 1E21-C001, LPCS PUMP oil samples to Chemistry.

4. COMPLETE Attachment 5, Operator Action to Restore Availability Checklist, if used.

OTHERWISE MARK this step and Section B of Attachment 5 N/A.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 31 of 43 5.3 Acceptance Criteria Initials NOTE Initialing Acceptance Criteria ensures that the criteria has been reviewed and dispositioned on the Test Cover Sheet/Surveillance Order.

$ 1. The measured values for the test parameters of the 1E21-C001, LPCS PUMP shall be within the acceptable or alert ranges listed [Inservice Testing Program, T/S, SR 3.5.1.4, SR 3.5.2.6 &

SR 3.5.2.8].

$ 2. All power-operated valves tested in this instruction shall operate normally through their complete stroke, and their stroke times shall be d the Tech Spec criteria listed.

$ 3. 1E21-F003, LPCS Pump Disch Check and 1E21-F501, LPCS To Supr Pool Check shall have an exercise open (EO) demonstrated by obtaining at least 6.11 kGPM (3.444 VDC) as indicated on E21EE001 [Inservice Testing Program].

$ 4. 1E21-F003, LPCS Pump Disch Check shall have an exercise closed (EC) by verifying LPCS Discharge Header remains pressurized after securing LPCS PUMP (Annunciator LPCS PUMP DISCH PRESS LO, 1H13-P601-21A-G6 reset)

[Inservice Testing Program].

$ 5. 1E21-F033, LPCS Wtr Leg Pump Disch Check shall have an exercise closed (EC) measuring a pressure drop of less than 5.0 psig during testing [Inservice Testing Program].

$ 6. 1E21-F034, LPCS Wtr Leg Pump Disch Vlv shall have an exercise closed (EC) by verifying free movement of the handwheel to the closed position [Inservice Testing Program].

$ 7. When a PI is performed as part of this instruction, the remote position indications shall agree with actual valve stem travel direction [Inservice Testing Program, T/S SR 3.3.3.1.3].

$ 8. The LPCS system has been operated for at least ten (10) minutes with flow through the Test Return Line.

[SR 3.5.2.6].

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 32 of 43 Comments:

Performed By: Ivan C. Taster / ICT /Today Tigh N Opter / TNO / Today Indo V. Rifer / IVR / Today

/ /

Name (Print) Initials Date

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 33 of 43 6.0 RECORDS 6.1 Records Handling Records completed/generated by this document shall be handled in accordance with the established records management program.

6.2 Records Capture The following documents are completed/generated by this instruction:

Quality Records Test Cover Sheet/Surveillance Order SVI-E21-T2001, pages 9 through 32, and:

Attachment 1, System Restoration Checklist Attachment 5, Operator Action to Restore Availability Checklist, (if used)

ICS Traces and/or print outs Non-Quality Records None

7.0 REFERENCES

7.1 Discretionary D-302-705 B-208-060, Sh. 08, 09, 10, 12, 13 B-208-222, Sh. 400, 402 8020 VMT, Byron Jackson Vertical LPCS Pump Technical Manual, Rev. 3 FTI-F0039, Pump Performance Data Collection ISI-E21-T1100-2, Low Pressure Core Spray (LPCS) Functional Pressure Test Class 2

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 34 of 43 SOI-E21, Low Pressure Core Spray System SVI-E21-T1181, LPCS Venting and Valve Lineup Verification 7.2 Obligations ISTP, Pump and Valve Inservice Testing Program Plan ASME OM Code of Record Technical Specifications: SR 3.3.3.1.3, SR 3.5.1.4, SR 3.5.2.5, SR 3.6.1.3.5, and SR 3.6.1.3.8 USAR, Sections 3.9.6, 5.4 and 6.3 Calculation E21-14, LPCS Pump Performance Acceptance Criteria CRCA 01-3740-007 CR 02-01891 CR 10-71532 CRCA 02-02730-002 CRCA 04-01549-003 TAI-1101-1, Inservice Testing of ASME OM Code Pumps TAI-1101-2, Inservice Testing of ASME OM Code Valves Commitments addressed in this document:

L02330

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 35 of 43 8.0 SCOPE OF REVISION Rev. 34 1. Step 4.0.1 split into two separate steps and clarifying information added for EC/EO and PI verifications and updated step references to match new step numbers. (2018-1290-159, 2018-1290-115)

2. Steps 5.1.3.9.b and 5.1.3.13.b, added N/A blocks for 1E21-F012 PI verification. (2018-1290-159)

3. Steps 5.1.3.12.a and 5.1.3.13.a, added initial lines. (2018-1290-159)

4. Deleted note at Step 5.1.3.20 regarding the N/A of 1E21-F033 and F034 EC testing as this is required quarterly by the ISTP.

(2018-1290-159) 9.0 ATTACHMENTS Attachment 1 - System Restoration Checklist Attachment 2 - Sample Pump Drawing Attachment 3 - Sample Test Manifold Drawing Attachment 4 - VDC to kGPM Conversion Table Attachment 5 - Operator Action to Restore Availability Checklist Attachment 6 - Alarm, Status/Indication Light, and General Information List

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 36 of 43 ATTACHMENT 1: SYSTEM RESTORATION CHECKLIST Page 1 of 1

Title:

Low Pressure Core Spray Pump and Valve Operability Test Verified By:

Signature/Initials Date INITIALS EQUIPMENT ID REQUIRED LOCATION FIRST SECOND REMARKS OR NAME POSITION VERIF VERIF 1H13-P601 1E21-F001 OPEN 1H13-P601 1E21-F011 OPEN 1H13-P601 1E21-F012 CLOSED 1H13-P601 1E21-C001

PUMP OFF AND BREAKER RACKED IN 1H13-P601 1E21-C002 ON 1H51-P037 1M39-B006 OFF SWITCH IN AUTO

Required position at the discretion of the Unit Supervisor.

Comments:

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 37 of 43 ATTACHMENT 2: SAMPLE PUMP DRAWING Page 1 of 1 NOTE Pump Test Data vibration measurement locations for this instruction are identified by a painted H1, V1 or A1. If these markings are no longer visible the horizontal H, vertical V, and axial A positions are identified above on the Sample Pump Drawing. The measurement points are on the pumps upper motor bearing housing in the horizontal, vertical and axial directions.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 38 of 43 ATTACHMENT 3: SAMPLE TEST MANIFOLD DRAWING Page 1 of 1

1. 1E21-F530

2. Fittings

3. Isolation Valve

4. 0-150 psig Test Gauge

5. Vent Path

6. P21/P22 Isolation Valve

7. Test Manifold

8. 3/4 Hose

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 39 of 43 ATTACHMENT 4: VDC TO kGPM CONVERSION TABLE Page 1 of 2 A: Wide Range VDC kGPM VDC kGPM VDC kGPM VDC kGPM 3.00 5.000 3.40 6.000 3.80 7.000 4.20 8.000 3.01 5.025 3.41 6.025 3.81 7.025 4.21 8.025 3.02 5.050 3.42 6.050 3.82 7.050 4.22 8.050 3.03 5.075 3.43 6.075 3.83 7.075 4.23 8.075 3.04 5.100 3.44 6.100 3.84 7.100 4.24 8.100 3.05 5.125 3.45 6.125 3.85 7.125 4.25 8.125 3.06 5.150 3.46 6.150 3.86 7.150 4.26 8.150 3.07 5.175 3.47 6.175 3.87 7.175 4.27 8.175 3.08 5.200 3.48 6.200 3.88 7.200 4.28 8.200 3.09 5.225 3.49 6.225 3.89 7.225 4.29 8.225 3.10 5.250 3.50 6.250 3.90 7.250 4.30 8.250 3.11 5.275 3.51 6.275 3.91 7.275 4.31 8.275 3.12 5.300 3.52 6.300 3.92 7.300 4.32 8.300 3.13 5.325 3.53 6.325 3.93 7.325 4.33 8.325 3.14 5.350 3.54 6.350 3.94 7.350 4.34 8.350 3.15 5.375 3.55 6.375 3.95 7.375 4.35 8.375 3.16 5.400 3.56 6.400 3.96 7.400 4.36 8.400 3.17 5.425 3.57 6.425 3.97 7.425 4.37 8.425 3.18 5.450 3.58 6.450 3.98 7.450 4.38 8.450 3.19 5.475 3.59 6.475 3.99 7.475 4.39 8.475 3.20 5.500 3.60 6.500 4.00 7.500 4.40 8.500 3.21 5.525 3.61 6.525 4.01 7.525 4.41 8.525 3.22 5.550 3.62 6.550 4.02 7.550 4.42 8.550 3.23 5.575 3.63 6.575 4.03 7.575 4.43 8.575 3.24 5.600 3.64 6.600 4.04 7.600 4.44 8.600 3.25 5.625 3.65 6.625 4.05 7.625 4.45 8.625 3.26 5.650 3.66 6.650 4.06 7.650 4.46 8.650 3.27 5.675 3.67 6.675 4.07 7.675 4.47 8.675 3.28 5.700 3.68 6.700 4.08 7.700 4.48 8.700 3.29 5.725 3.69 6.725 4.09 7.725 4.49 8.725 3.30 5.750 3.70 6.750 4.10 7.750 4.50 8.750 3.31 5.775 3.71 6.775 4.11 7.775 4.51 8.775 3.32 5.800 3.72 6.800 4.12 7.800 4.52 8.800 3.33 5.825 3.73 6.825 4.13 7.825 4.53 8.825 3.34 5.850 3.74 6.850 4.14 7.850 4.54 8.850 3.35 5.875 3.75 6.875 4.15 7.875 4.55 8.875 3.36 5.900 3.76 6.900 4.16 7.900 4.56 8.900 3.37 5.925 3.77 6.925 4.17 7.925 4.57 8.925 3.38 5.950 3.78 6.950 4.18 7.950 4.58 8.950 3.39 5.975 3.79 6.975 4.19 7.975 4.59 8.975

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

Use Category:

Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 40 of 43 ATTACHMENT 4: VDC TO kGPM CONVERSION TABLE Page 2 of 2 B: Narrow Range (3.440 to 3.459 VDC / 6.000 to 6.1475 kGPM)

VDC kGPM VDC kGPM VDC kGPM VDC kGPM 3.440 6.100 3.445 6.1125 3.450 6.125 4.455 6.1375 3.441 6.1025 3.446 6.115 3.451 6.1275 4.456 6.140 3.442 6.105 3.447 6.1175 3.452 6.130 4.457 6.1425 3.443 6.1075 3.448 6.120 3.453 6.1325 4.458 6.145 3.444 6.110 3.449 6.1225 3.454 6.135 4.459 6.1475

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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34 41 of 43 ATTACHMENT 5: OPERATOR ACTION TO RESTORE AVAILABILITY CHECKLIST Page 1 of 2 This Attachment is provided for the emergent condition that requires the restoration of LPCS during the performance of this Surveillance Instruction while LPCS pump control power fuses are removed.

For this instruction one person is required to restore the system to an operable status.

This person shall be the control room operator performing the surveillance. This person is responsible for restoring the system should an emergent condition occur that results in the Unit Supervisor ordering the restoration.

This attachment may be left blank if operator action to restore availability was not desired.

SECTION A, TASK ASSIGNMENTS Assigned Control Room Operator: /

(PRINT) Date Assigned Operator in vicinity of 4.16kv Bus EH11 (CC 620):

/

(Print) Date Reactor Operator Notified: /

(Print) Date SECTION B, VALVE OPERABILITY TESTING Initials NOTE If a valid demand for LPCS is received after performing Step 5.1.2.1.b.1 (control power fuses pulled) but prior to performing Step 5.1.2.1.f.1, restore LPCS to an Operable status by performing Steps 1-12.

1. DOCUMENT the Date and Time this Section commenced.

/

2. VERIFY open 1E21-F001, LPCS SUPR POOL SUCTION VALVE.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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34 42 of 43 ATTACHMENT 5: OPERATOR ACTION TO RESTORE AVAILABILITY CHECKLIST Page 2 of 2 Initials

3. VERIFY open 1E21-C001, LPCS PUMP Breaker EH1111 located CC-620, 4.16kV Bus EH11.

4. OPEN the cubicle door.

CAUTION Control Room Operator must HOLD LPCS PUMP 1E21-C001 control switch in the STOP position while installing Control Power fuses to prevent inadvertent pump start. Ensure communications are established between the control room operator and the operator installing fuses at 4.16kv Bus EH11.

5. HOLD LPCS PUMP, 1E21-C001 Control Switch in STOP.

6. REINSTALL the following control power fuses:

a. CONTROL FUSE - OPEN

b. CONTROL FUSE - CLOSE

7. VERIFY fuse continuity by testing for control voltage on the load side of the control power fuses:

a. CONTROL FUSE - OPEN

b. CONTROL FUSE - CLOSE

8. VERIFY Spring Charging Motor Toggle ON, if installed.

9. VERIFY yellow SPRINGS CHARGED indicator is visible.

10. CLOSE and FASTEN cubicle door.

11. After control power fuses have been installed and cubicle door secured, RELEASE 1E21-C001, LPCS PUMP control switch.

12. VERIFY 1E21-C001, LPCS PUMP operating.

13. RECORD Date________ and Time________ this Section was completed.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E21-T2001

Title:

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Low Pressure Core Spray Pump and Valve Step-by-Step Operability Test Revision: Page:

34 43 of 43 ATTACHMENT 6: ALARM, STATUS/INDICATION LIGHT, AND GENERAL INFORMATION LIST Page 1 of 1 SVI

Title:

LOW PRESSURE CORE SPRAY PUMP AND VALVE OPERABILITY TEST NOTE This attachment is for information only and provided as an aid to Reactor Operator.

Additional alarms and/or plant impact may occur due to specific operational conditions at the time of performance. Desired changes to this attachment should be documented in COMMENTS Section on Test Cover Sheet/Surveillance Order.

The following alarms may be received intermittently:

ALARMS LOCATION Annunciator ADS A PERMISSIVE LPCS/RHR A RUN 1H13-P601-19A-F9 Annunciator LPCS PUMP DISCH PRESS LO 1H13-P601-21A-G6 The following status and indication lights may come on or go off intermittently:

STATUS/INDICATION LIGHTS LOCATION None PLANT IMPACT:

SECTION DESCRIPTION 5.1.2 VALVE OPERABILITY TESTS - this section verifies operability of numerous E21 valves, in accordance with the ISTP, by obtaining test data following a valves exercise, stroke time and position indication verification. The testing effects on a system or a component (i.e., operable and/or available) are uniquely identified.

5.1.3 PUMP AND VALVE OPERABILITY TEST - This section verifies operability of 1E21-C001, LPCS PUMP and numerous other LPCS valves, in accordance with the ISTP, by obtaining test data. Since the LPCS system is in a secondary mode of operation that inhibits the system from meeting the Tech. Spec.

response time requirement the LPCS system is declared inoperable but available throughout most of the section.

LEAD TEST PERFORMER:

(PRINT)

OT-3701-C85_501_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: C85, Steam Bypass And Pressure Regulating System Time Critical: No Alternate Path: Yes Setting: Simulator Applicability: RO/SRO Safety Function: 3 - Reactor Pressure Control Validated Time: 14 Minutes

References:

SVI-C85-T1314 Rev.9 Required Material: SVI-C85-T1314, Turbine Bypass Valve Operability Test Task: 248-540-02-01 Perform Steam Bypass Valve Operability Test Task Standard: While performing the monthly SVI to cycle Main Turbine Bypass Valves, respond to a failure of both pressure regulators.

K/A: 241000, Reactor/Turbine Pressure Regulating System - A4.06, Ability to manually operate and/or monitor in the control room: Bypass valves (operation), Importance RO 3.9

1. Setup Instructions: Reset simulator to IC-111 for the 2021 ILO NRC Exam. Load schedule file JPM C85-501_RO and verify event file JPM C85-501_RO loads.

Prebriefing JPM recommended.

2. Location / Method: Simulator / Performance

3. Initial Condition: Plant operating at power. SVI-C85-T1314, Turbine Bypass Valve Operability Test Prerequisites have been completed.

4. Initiating Cue: Unit Supervisor directs you as the Balance of Plant Operator to perform SVI-C85-T1314, Turbine Bypass Valve Operability Test Start: Stop:

Candidate:

OT-3701-C85_501_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 SVI-C85-T1314 Turbine Bypass Valve Operability Test 5.0 SURVEILLANCE INSTRUCTION 5.1 Surveillance Test

1. OBTAIN the Reactor Operators Test Start Approval signature on the Test Cover Sheet/Surveillance Order.

2. DEPRESS TESTING pushbutton for Bypass Valve Test Status.

3. VERIFY the following:

TESTING pushbutton light on

OFF light is extinguished

READY light is on Critical Step Standard: Candidate initials Step 5.1.1 and verifies items in Step 5.1.3. [Non-Critical]

Candidate depresses Testing pushbutton. [Critical]

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-C85_501_RO Rev 0 Step 2 5.1.1 BPV 1 Cycle Test

2. Depress and hold pushbutton TEST BPV 1 and confirm the following:

a. TEST BPV 1 pushbutton illuminates.

b. BPV Test Status READY light goes off.

c. BPV SERVO CURRENT meter 1, 1C85-R718A, shows small positive current.

d. BPV POSITION indicator 1, 1C85-R719A, traveling from 0%

toward 100%.

e. BPV 1 CLOSED light goes off and OPEN light comes on.

f. STEAM BYPASS VLV OPEN annunciator (P680-7A-A1) alarms.

g. BPV 1 OPEN light goes off and FULL OPEN light comes on with an increased rate of travel from 90% - 100% as a result of the fast-acting solenoid.

Critical Step:

Standard: Candidate depresses and holds TEST BPV 1 pushbutton.

Candidate verifies items a thru g before releasing the pushbutton.

Instructor Cue: None Notes: Step 5.1.1.1 should be N/A.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-C85_501_RO Rev 0 Step 3

3. Release pushbutton TEST BPV 1 and confirm the following:

a. BPV 1 FULL OPEN light goes off and OPEN light comes on.

b. STEAM BYPASS VLV OPEN annunciator clears.

c. BPV 1 Position indicator, 1C85-R719A, traveling from 100%

to approximately 0%.

d. BPV 1 OPEN light goes off and CLOSED light comes on. (IF indications show BPV 1 OPEN or indeterminate, then Confirm BPV 1 CLOSED by ICS point C85EA012).

e. BPV 1 servo current meter, 1C85-R718A, indicates negative current.

f. BPV test status READY light comes on.

g. TEST BPV 1 pushbutton light extinguishes.

4. Ensure plant parameters stabilize.

Critical Step Standard: Candidate releases TEST BPV 1 pushbutton and confirms items a thru g and allows plant parameters to stabilize.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-C85_501_RO Rev 0 Step 4 5.1.2 BPV 2 Cycle Test

2. Depress and hold pushbutton TEST BPV 2 and confirm the following:

a. TEST BPV 2 pushbutton illuminates.

b. BPV Test Status READY light goes off.

c. BPV SERVO CURRENT meter 2, 1C85-R718B, shows small positive current.

d. BPV POSITION indicator 2, 1C85-R719B, traveling from 0%

toward 100%.

e. BPV 2 CLOSED light goes off and OPEN light comes on.

f. BPV 2 OPEN light goes off and FULL OPEN light comes on with an increased rate of travel from 90% - 100% as a result of the fast-acting solenoid.

Critical Step:

Standard: Candidate depresses and holds TEST BPV 2 pushbutton.

Candidate verifies items a thru f before releasing the pushbutton.

Instructor Cue: None Notes: Step 5.1.2.1 should be N/A.

One minute after the TEST BPV 2 pushbutton is depressed, pressure regulator A will fail.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-C85_501_RO Rev 0 Step 5

3. Release pushbutton TEST BPV 2 and confirm the following:

a. BPV 2 FULL OPEN light goes off and OPEN light comes on.

b. BPV 2 Position indicator, 1C85-R719B, traveling from 100%

to approximately 0%.

c. BPV 2 OPEN light goes off and CLOSED light comes on. (IF indications show BPV 2 OPEN or indeterminate, then Confirm BPV 2 CLOSED by ICS point C85EA013).

d. BPV 2 servo current meter, 1C85-R718B, indicates negative current.

e. BPV test status READY light comes on.

f. TEST BPV 2 pushbutton light extinguishes.

4. Ensure plant parameters stabilize.

Critical Step Standard: Candidate releases TEST BPV 2 pushbutton and confirms items a thru f and allows plant parameters to stabilize.

Instructor Cue: When Candidate identifies the pressure regulator failure, acknowledge the Candidates report.

After 1 minute - (Booth Operator) initiate Event 3 to initiate the failure of the 2nd regulator.

Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-C85_501_RO Rev 0 Step 6 ONI-C85 PRESSURE REGULATOR FAILURE 3.0 IMMEDIATE ACTIONS 3.1 IF both Pressure Regulators have failed, THEN PERFORM the following:

3.1.1 SCRAM the reactor.

3.1.2 TRIP the main turbine by depressing the TURBINE TRIP push-button Critical Step:

Standard: Candidate scrams the reactor. [Critical]

Candidate trips the main turbine. [Non-Critical]

Instructor Cue: None Notes: Main turbine may trip on reverse power.

Candidate may perform Reactor Scram Hardcard.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-C85_501_RO Rev 0 Step 7 NOTE It is not necessary to wait for a 3rd Turbine Bypass Valve to be fully open in the following step. , Discussion provides guidance on determining bypass valve failure indications.

3.1.1 IF more than 2 Turbine Bypass Valves are failed open, THEN CLOSE the MSIVs.

Critical Step Standard: Candidate identifies bypass valves continue to open, reactor pressure is lowering, and closes the MSIVs.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Main Turbine Bypass Valves 1 &2 tested satisfactorily and reactor scrammed and MSIVs shut.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-C85_501_RO Rev 0 JPM CUE SHEET INITIAL

Plant operating at power.

CONDITIONS:

SVI-C85-T1314, Turbine Bypass Valve Operability Test Prerequisites have been completed.

INITIATING CUE: Unit Supervisor directs you as the Balance of Plant Operator to perform SVI-C85-T1314, Turbine Bypass Valve Operability Test.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 1 of 19 TURBINE BYPASS VALVE OPERABILITY TEST Surveillance Instruction Effective Date: 6-4-2020 Preparer: Dan Roniger / 5-1-2020 Date Approver: Ed Condo / 5-27-2020 Date

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 2 of 19

1.0 DESCRIPTION

1.1 Scope This instruction demonstrates the operational readiness of the main turbine bypass valves (BPV) by cycling each valve through one complete cycle of full travel. This is performed by placing the valves in a test mode and using individual valve test buttons and indicators on the Unit Control Console, 1H13-P680-7, to operate the valves.

This instruction fully satisfies the surveillance requirement of Technical Specification SR 3.7.6.1 for the below listed valves.

The following valves are tested by this instruction:

x BPV-1, 1C85-F002-1 x BPV-2, 1C85-F002-2 x BPV-3, 1C85-F002-3 x BPV-4, 1C85-F001-4 x BPV-5, 1C85-F001-3 x BPV-6, 1C85-F001-2 x BPV-7, 1C85-F001-1 This instruction and SVI-N31-T1153 should be performed sequentially.

1.2 Frequency At least once per 31 days.

1.3 Technical Specification Applicable MODES Mode 1, when THERMAL POWER is greater than or equal to 23.8% of RATED THERMAL POWER.

2.0 PRECAUTIONS AND LIMITATIONS

1. Step numbers marked with a dollar sign ($) immediately to the left are required by Technical Specifications. Such items, if found to exceed their Allowable Values, may be NRC reportable and shall be brought to the attention of the Unit Supervisor immediately.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 3 of 19

2. All steps in each section are to be performed in sequence and the instruction carried through to completion, unless otherwise indicated.

3. The bypass valves may be tested in any order but only one at a time.

Each successive valve should be tested only after the previous valve has returned to its normal operating position and plant conditions have stabilized.

4. Ensure during testing that main turbine control valves respond to maintain reactor pressure. Extraction steam flow is reduced by bypass flow, and results in lower feedwater temperature and increased neutron flux.

5. During performance of BPV-1 cycling, annunciator STEAM BYPASS VLV OPEN (1H13-P680-7A-A1) will come ON.

6. The following channels will be inoperable anytime the trip function is bypassed at t 38% RTP:

x RPS Instrumentation Channels A, B, C, D, E, F, G, and H for Turbine Stop Valve Closure, T.S. 3.3.1.1, Table 3.3.1.1-1, Function 9 x RPS Instrumentation Channels A, B, C, and D for Turbine Control Valve Fast Closure, Trip Oil Pressure - Low. T.S. 3.3.1.1, Table 3.3.1.1-1, Function 10 x End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation, T.S. 3.3.4.1 Main turbine bypass steam flow can affect LPSP non-conservatively for the RWL; therefore, opening the turbine bypass valve may affect the Control Rod Block Instrumentation, T.S. 3.3.2.1.

7. Due to computer point tolerances ICS Data points may not read 0.0% with BPV closed.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

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Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 4 of 19 3.0 MANPOWER AND EQUIPMENT 3.1 Manpower/Location/Communication

1. Control Room operator to cycle BPVs and collect data at UNIT CONTROL CONSOLE, 1H13-P680.

3.2 Required Measuring and Test Equipment (M&TE)

None 3.3 Additional Tools and Equipment None 4.0 PREREQUISITES Initials

1. OBTAIN the Unit Supervisors Work Start (Prerequisites)

Approval signature on the Test Cover Sheet/Surveillance Order. BRO

2. CONFIRM the plant is in one of the following (circle plant condition):

Mode 1 - (generator synchronized to the grid, Rx power d 99%, and no control rods being withdrawn)

Mode 2 - (in Hot Standby with no Start-up in progress)

Mode 3, 4 or 5 BRO

3. VERIFY lamp indications are working as follows:

a. AT 1H13-P680-7, PERFORM a Lamp Test on Steam Bypass. BRO

b. IF lamps are burnt out, THEN REPLACE lamps as necessary.

OTHERWISE MARK this Step as N/A. N/A

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

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Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 5 of 19 SECTION 4.0 Initials

4. At 1H13-P680, VERIFY the following:

a. BPV#1 Position Green CLOSED indicating light ON OR ICS Data point C85EA012 indicates ~ 0.0% and GOOD. BRO

b. BPV#2 Position Green CLOSED indicating light ON OR ICS Data point C85EA013 indicates ~ 0.0% and GOOD. BRO

c. BPV#3 Position Green CLOSED indicating light ON OR ICS Data point C85EA014 indicates ~ 0.0% and GOOD. BRO

d. BPV#4 Position Green CLOSED indicating light ON OR ICS Data point C85EA015 indicates ~ 0.0% and GOOD. BRO

e. BPV#5 Position Green CLOSED indicating light ON OR ICS Data point C85EA016 indicates ~ 0.0% and GOOD. BRO

f. BPV#6 Position Green CLOSED indicating light ON OR ICS Data point C85EA017 indicates ~ 0.0% and GOOD. BRO

g. BPV#7 Position Green CLOSED indicating light ON OR ICS Data point C85EA018 indicates ~ 0.0% and GOOD. BRO

h. Bypass Valve Opening Jack CLOSED light ON. BRO

i. OBSERVE the BPV JACK POSITION, indicator 1C85-R717, reads zero (NOP to 2%). BRO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

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Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 6 of 19 5.0 SURVEILLANCE INSTRUCTION Initials NOTES x All valve controls and indications used in this instruction are located on Control Room panel 1H13-P680.

x Opening bypass valves will cause first stage Turbine Pressure to drop. This will result in sensed power being below actual power and may impact:

o High power setpoint o Low power setpoint o RCIC initiation turbine trip bypass logic 5.1 Surveillance Test

1. OBTAIN the Reactor Operators Test Start Approval signature on the Test Cover Sheet/Surveillance Order.

2. DEPRESS TESTING pushbutton for Bypass Valve Test Status.

3. VERIFY the following:

TESTING pushbutton light on OFF light is extinguished READY light is on 5.1.1 BPV 1 Cycle Test

1. IF initial indications show BPV 1 OPEN or indeterminate, THEN CONFIRM BPV 1 CLOSED by ICS point C85EA012, AND DOCUMENT the indication discrepancy in Section 5.3 comments.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 7 of 19 SECTION 5.1.1 Initials

$ 2. DEPRESS and HOLD pushbutton TEST BPV 1 AND CONFIRM the following:

a. TEST BPV 1 pushbutton illuminates.

b. BPV Test Status READY light goes off.

c. BPV SERVO CURRENT meter 1, 1C85-R718A, shows small positive current.

d. BPV POSITION indicator 1, 1C85-R719A, traveling from 0% toward 100%.

e. BPV 1 CLOSED light goes off and OPEN light comes on.

f. STEAM BYPASS VLV OPEN annunciator (P680-7A-A1) alarms.

g. BPV 1 OPEN light goes off and FULL OPEN light comes on with an increased rate of travel from 90% - 100% as a result of the fast-acting solenoid.

$ 3. RELEASE pushbutton TEST BPV 1 AND CONFIRM the following:

a. BPV 1 FULL OPEN light goes off and OPEN light comes on.

b. STEAM BYPASS VLV OPEN annunciator clears.

NOTE Due to meter calibration tolerances, the valve position meter may not indicate 0%

with the valve closed.

c. BPV 1 Position indicator, 1C85-R719A, traveling from 100% to approximately 0%.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 8 of 19 SECTION 5.1.1 Initials

d. BPV 1 OPEN light goes off and CLOSED light comes on.

(IF indications show BPV 1 OPEN or indeterminate, THEN Confirm BPV 1 CLOSED by ICS point C85EA012).

e. BPV 1 servo current meter, 1C85-R718A, indicates negative current.

f. BPV test status READY light comes on.

g. TEST BPV 1 pushbutton light extinguishes.

4. ENSURE plant parameters stabilize.

5.1.2 BPV 2 Cycle Test

1. IF initial indications show BPV 2 OPEN OR indeterminate, THEN CONFIRM BPV 2 CLOSED by ICS point C85EA013, AND DOCUMENT the indication discrepancy in Section 5.3 comments.

$ 2. DEPRESS and HOLD pushbutton TEST BPV 2 AND CONFIRM the following:

a. TEST BPV 2 pushbutton illuminates.

b. BPV Test Status READY light goes off.

c. BPV SERVO CURRENT meter 2, 1C85-R718B, shows small positive current.

d. BPV POSITION indicator 2, 1C85-R719B, traveling from 0% toward 100%.

e. BPV 2 CLOSED light goes off and OPEN light comes on.

f. BPV 2 OPEN light goes off and FULL OPEN light comes on with an increased rate of travel from 90% - 100% as a result of the fast-acting solenoid.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

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Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 9 of 19 SECTION 5.1.2 Initials

$ 3. RELEASE pushbutton TEST BPV 2 AND CONFIRM the following:

a. BPV 2 FULL OPEN light goes off and OPEN light comes on.

NOTE Due to meter calibration tolerances, the valve position meter may not indicate 0%

with the valve closed.

b. BPV 2 Position indicator, 1C85-R719B, traveling from 100% to approximately 0%.

c. BPV 2 OPEN light goes off and CLOSED light comes on.

(IF indications show BPV 2 OPEN or indeterminate, THEN Confirm BPV 2 CLOSED by ICS point C85EA013).

d. BPV 2 servo current meter, 1C85-R718B, indicates negative current.

e. BPV test status READY light comes on.

f. TEST BPV 2 pushbutton light extinguishes.

4. ENSURE plant parameters stabilize.

5.1.3 BPV 3 Cycle Test

1. IF initial indications show BPV 3 OPEN OR indeterminate, THEN CONFIRM BPV 3 CLOSED by ICS point C85EA014, AND DOCUMENT the indication discrepancy in Section 5.3 comments.

$ 2. DEPRESS and HOLD pushbutton TEST BPV 3 AND CONFIRM the following:

a. TEST BPV 3 pushbutton illuminates.

b. BPV Test Status READY light goes off.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

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9 10 of 19 SECTION 5.1.3 Initials

b. BPV Test Status READY light goes off.

c. BPV SERVO CURRENT meter 3, 1C85-R718C, shows small positive current.

d. BPV POSITION indicator 3, 1C85-R719C, traveling from 0% toward 100%.

e. BPV 3 CLOSED light goes off and OPEN light comes on.

f. BPV 3 OPEN light goes off and FULL OPEN light comes on with an increased rate of travel from 90% - 100% as a result of the fast-acting solenoid.

$ 3. RELEASE pushbutton TEST BPV 3 AND CONFIRM the following:

a. BPV 3 FULL OPEN light goes off and OPEN light comes on.

NOTE Due to meter calibration tolerances, the valve position meter may not indicate 0%

with the valve closed.

b. BPV 3 Position indicator, 1C85-R719C, traveling from 100% to approximately 0%.

c. BPV 3 OPEN light goes off and CLOSED light comes on.

(IF indications show BPV 3 OPEN or indeterminate, THEN Confirm BPV 3 CLOSED by ICS point C85EA014).

d. BPV 3 servo current meter, 1C85-R718C, indicates negative current.

e. BPV test status READY light comes on.

f. TEST BPV 3 pushbutton light extinguishes.

4. ENSURE plant parameters stabilize.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 11 of 19 5.1.4 BPV 4 Cycle Test Initials

1. IF initial indications show BPV 4 OPEN OR indeterminate, THEN CONFIRM BPV 4 CLOSED by ICS point C85EA015, AND DOCUMENT the indication discrepancy in Section 5.3 comments.

$ 2. DEPRESS and HOLD pushbutton TEST BPV 4 AND CONFIRM the following:

a. TEST BPV 4 pushbutton illuminates.

b. BPV Test Status READY light goes off.

c. BPV SERVO CURRENT meter 4, 1C85-R718D, shows small positive current.

d. BPV POSITION indicator 4, 1C85-R719D, traveling from 0% toward 100%.

e. BPV 4 CLOSED light goes off and OPEN light comes on.

f. BPV 4 OPEN light goes off and FULL OPEN light comes on with an increased rate of travel from 90% - 100% as a result of the fast-acting solenoid.

$ 3. RELEASE pushbutton TEST BPV 4 AND CONFIRM the following:

a. BPV 4 FULL OPEN light goes off and OPEN light comes on.

NOTE Due to meter calibration tolerances, the valve position meter may not indicate 0%

with the valve closed.

b. BPV 4 Position indicator, 1C85-R719D, traveling from 100% to approximately 0%.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 12 of 19 SECTION 5.1.4 Initials

c. BPV 4 OPEN light goes off and CLOSED light comes on.

(IF indications show BPV 4 OPEN or indeterminate, THEN Confirm BPV 4 CLOSED by ICS point C85EA015).

d. BPV 4 servo current meter, 1C85-R718D, indicates negative current.

e. BPV test status READY light comes on.

f. TEST BPV 4 pushbutton light extinguishes.

4. ENSURE plant parameters stabilize.

5.1.5 BPV 5 Cycle Test

1. IF initial indications show BPV 5 OPEN OR indeterminate, THEN CONFIRM BPV 5 CLOSED by ICS point C85EA016, AND DOCUMENT the indication discrepancy in Sect. 5.3 comments.

$ 2. DEPRESS and HOLD pushbutton TEST BPV 5 AND CONFIRM the following:

a. TEST BPV 5 pushbutton illuminates.

b. BPV Test Status READY light goes off.

c. BPV SERVO CURRENT meter 5, 1C85-R718E, shows small positive current.

d. BPV POSITION indicator 5, 1C85-R719E, traveling from 0% toward 100%.

e. BPV 5 CLOSED light goes off and OPEN light comes on.

f. BPV 5 OPEN light goes off and FULL OPEN light comes on with an increased rate of travel from 90% - 100% as a result of the fast-acting solenoid.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

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9 13 of 19 SECTION 5.1.5 Initials

$ 3. RELEASE pushbutton TEST BPV 5 AND Confirm the following:

a. BPV 5 FULL OPEN light goes off and OPEN light comes on.

NOTE Due to meter calibration tolerances, the valve position meter may not indicate 0%

with the valve closed.

b. BPV 5 Position indicator, 1C85-R719E, traveling from 100% to approximately 0%.

c. BPV 5 OPEN light goes off and CLOSED light comes on.

(IF indications show BPV 5 OPEN or indeterminate, THEN Confirm BPV 5 CLOSED by ICS point C85EA016).

d. BPV 5 servo current meter, 1C85-R718E, indicates negative current.

e. BPV test status READY light comes on.

f. TEST BPV 5 pushbutton light extinguishes.

4. ENSURE plant parameters stabilize.

5.1.6 BPV 6 Cycle Test

1. IF initial indications show BPV 6 OPEN OR indeterminate, THEN CONFIRM BPV 6 CLOSED by ICS point C85EA017, AND DOCUMENT the indication discrepancy in Section 5.3 comments.

$ 2. DEPRESS and HOLD pushbutton TEST BPV 6 AND CONFIRM the following:

a. TEST BPV 6 pushbutton illuminates.

b. BPV Test Status READY light goes off.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

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9 14 of 19 SECTION 5.1.6 Initials

c. BPV SERVO CURRENT meter 6, 1C85-R718F, shows small positive current.

d. BPV POSITION indicator 6, 1C85-R719F, traveling from 0% toward 100%.

e. BPV 6 CLOSED light goes off and OPEN light comes on.

f. BPV 6 OPEN light goes off and FULL OPEN light comes on with an increased rate of travel from 90% - 100% as a result of the fast-acting solenoid.

$ 3. RELEASE pushbutton TEST BPV 6 AND CONFIRM the following:

a. BPV 6 FULL OPEN light goes off and OPEN light comes on.

NOTE Due to meter calibration tolerances, the valve position meter may not indicate 0%

with the valve closed.

b. BPV 6 Position indicator, 1C85-R719F, traveling from 100% to approximately 0%.

c. BPV 6 OPEN light goes off and CLOSED light comes on.

(IF indications show BPV 6 OPEN or indeterminate, THEN CONFIRM BPV 6 CLOSED by ICS point C85EA017).

d. BPV 6 servo current meter, 1C85-R718F, indicates negative current.

e. BPV test status READY light comes on.

f. TEST BPV 6 pushbutton light extinguishes.

4. ENSURE plant parameters stabilize.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 15 of 19 5.1.7 BPV 7 Cycle Test Initials

1. IF initial indications show BPV 7 OPEN OR indeterminate, THEN CONFIRM BPV 7 CLOSED by ICS point C85EA018, AND DOCUMENT the indication discrepancy in Section 5.3 comments.

$ 2. DEPRESS and HOLD pushbutton TEST BPV 7 AND CONFIRM the following:

a. TEST BPV 7 pushbutton illuminates.

b. BPV Test Status READY light goes off.

c. BPV SERVO CURRENT meter 7, 1C85-R718G, shows small positive current.

d. BPV POSITION indicator 7, 1C85-R719G, traveling from 0% toward 100%.

e. BPV 7 CLOSED light goes off and OPEN light comes on.

f. BPV 7 OPEN light goes off and FULL OPEN light comes on with an increased rate of travel from 90% - 100% as a result of the fast-acting solenoid.

$ 3. RELEASE pushbutton TEST BPV 7 AND CONFIRM the following:

a. BPV 7 FULL OPEN light goes off and OPEN light comes on.

NOTE Due to meter calibration tolerances, the valve position meter may not indicate 0%

with the valve closed.

b. BPV 7 Position indicator, 1C85-R719G, traveling from 100% to approximately 0%.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 16 of 19 SECTION 5.1.7 Initials

c. BPV 7 OPEN light goes off and CLOSED light comes on.

(IF indications show BPV 7 OPEN or indeterminate, THEN CONFIRM BPV 7 CLOSED by ICS point C85EA018).

d. BPV 7 servo current meter, 1C85-R718G, indicates negative current.

e. BPV test status READY light comes on.

f. TEST BPV 7 pushbutton light extinguishes.

4. ENSURE plant parameters stabilize.

5.2 Plant/System Restoration

1. DEPRESS Bypass Valve Test Status OFF pushbutton,

2. VERIFY the following:

OFF pushbutton light on.

TESTING pushbutton light off.

READY light off.

3. COMPLETE System Restoration Checklist, Attachment 1, using the methods of Independent Verification.

5.3 Acceptance Criteria

1. Each BPV tested strokes full open and back to full closed normally as indicated by the respective BPV position status lights sequencing from CLOSED to FULL OPEN and back to CLOSED. (ICS Data points may be used for CLOSED indication)

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

Title:

Use Category:

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9 17 of 19 SECTION 5.3 Initials

2. Satisfactory completion of this surveillance will be based on Technical Specification items (marked with a $ sign) only. If any other items observed during this surveillance did not perform satisfactorily, NOTIFY the Unit Supervisor.

Comments:

Performed By: / /

/ /

Name (Print) Initials Date 6.0 RECORDS 6.1 Records Handling Records completed/generated by this document shall be handled in accordance with the established records management program.

6.2 Records Capture The following documents are completed/generated by this instruction:

Quality Records Test Cover Sheet/Surveillance Order SVI-C85-T1314, pages 4 through 17, and Attachment 1, System Restoration Checklist

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PERRY NUCLEAR POWER PLANT SVI-C85-T1314

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9 18 of 19 Non-Quality Records None

7.0 REFERENCES

7.1 Discretionary Technical Specifications USAR, Section 10.4.4 D-302-021 B-208-045 SIL No. 413, Oct. 4, 1984, Main Steam Bypass Valve Testing GEK-75603A,Section IV. 4-9, Bypass Valve Testing, Dec. 1983 SOI-C85, Steam Bypass and Pressure Regulator System 7.2 Obligations Commitments addressed in this document:

None 8.0 SCOPE OF REVISION Rev. 9 1. Minor Formatting Changes to meet the writers guide (no rev bars used).

2. Updated guidance to reflect Tech Spec Bases Change Notice 20-042.

9.0 ATTACHMENTS Attachment 1 - System Restoration Checklist

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-C85-T1314

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Turbine Bypass Valve Operability Test Step-by-Step Revision: Page:

9 19 of 19 ATTACHMENT 1: SYSTEM RESTORATION CHECKLIST Page 1 of 1 Verified By:

Signature/Initials Date INITIALS EQUIPMENT ID OR REQUIRED LOCATION FIRST SECOND REMARKS NAME POSITION VERIF VERIF 1H13-P680-7 TEST BPV 1 Light Off 1H13-P680-7 TEST BPV 2 Light Off 1H13-P680-7 TEST BPV 3 Light Off 1H13-P680-7 TEST BPV 4 Light Off 1H13-P680-7 TEST BPV 5 Light Off 1H13-P680-7 TEST BPV 6 Light Off 1H13-P680-7 TEST BPV 7 Light Off 1H13-P680-7 BPV TEST Light On STATUS OFF 1H13-P680-7 BPV TEST Light Off STATUS TESTING 1H13-P680-7 BPV TEST Light Off STATUS READY Comments:

OT-3701-G33_003_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: G33 Reactor Water Cleanup System Time Critical: No Alternate Path: No Setting: RRA/Simulator/Non-RRA/Classroom/Control Room Applicability: RO/SRO Safety Function: 4 - Heat Removal From the Core Validated Time: 10 Minutes

References:

SOI-G33 Rev. 50 Required Material: SOI-G33, Reactor Water Cleanup System Task: 204-511-04-01 Recover RWCU Pump after Pump Trip Task Standard: Restart a RWCU Pump following a RWCU Pump trip.

K/A: 204000 Reactor Water Cleanup System - A4.01, Ability to manually operate and/or monitor in the control room: System pumps, Importance RO 3.1

1. Setup Instructions: Reset simulator to IC-111. Take RWCU Pump A to STOP.

2. Location / Method: Simulator / Performance

3. Initial Condition: The Plant is in Mode 1. RWCU Pump A tripped 20 minutes ago due to a human performance error. RWCU FD A is being backwashed. Its been determined that fill and vent of the RWCU system is not required.

4. Initiating Cue: Unit Supervisor directs you, the Balance of Plant Operator, to recover RWCU Pump A. An NLO is in the plant to assist you.

Start: Stop:

Candidate:

OT-3701-G33_003_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 SOI-G33 Reactor Water Cleanup System 7.10 RWCU Pump Trip Recovery 7.10.2 If 15 minutes from the trip have elapsed, then refer to Startup of an Idle RWCU Pump to start the pump.

Standard: The Candidate reviews SOI-G33 to determine correct section to use.

Candidate determines Section 4.3, Starting an Idle RWCU Pump is the correct procedure.

Instructor Cue: None Notes: Since the RWCU pump tripped 20 minutes ago (Initial Conditions), the candidate will use SOI-G33 Section 4.3 to start an idle pump.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-G33_003_RO Rev 0 Step 2 4.3 Starting an Idle RWCU Pump 4.3.1 If fill and vent of the Idle Pump is required, then refer to Restoring an Isolated RWCU Pump to fill the pump.

4.3.2 If Rx Water Temp <190 °F, THEN PERFORM the following:

Standard: The candidate determines Steps 4.3.1 and 4.3.2 are N/A.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-G33_003_RO Rev 0 Step 3 4.3.3 If the Rx Water Temp is 250 °F, then perform the following:

4.3.3.a Verify the oncoming RWCU Pump Warm Up Isolation Valve is closed.

1G33-F045A/B 4.3.3.b Verify the following valves are open for the oncoming pump:

RWCU Pump Suction Shutoff Valve 1G33-F005A/B

RWCU Pump Suction Man Isolation Valve 1G33-F043A/B

RWCU Pump Disch Man Isolation Vlv 1G33-F013A/B 4.3.3.c Monitor the pump casing warm up rate using a Digital Thermometer with a surface contact probe (located on the suction side of the pump casing midway between the suction and discharge flanges) AND extension leads (or equivalent M&TE).

4.3.3.d Perform Steps 4.3.3.e AND 4.3.3.f until the oncoming RWCU pump casing temp is within 100 °F of PT 1(2) RCIRC SUCTION at 1H13-P614 on REACTOR RCIRC TEMP MONITORING recorder 4.3.3.e Crack open the oncoming RWCU Pump Warm Up Isolation Valve.

1G33-F045A/B 4.3.3.f Immediately close the oncoming RWCU Pump Warm Up Isolation Valve.

1G33-F045A/B Standard: The candidate determines Rx water temperature is >250 °F and directs NLO to perform Steps 4.3.3.a through 4.3.3.f.

Instructor Cue: Driver: Inform Candidate that Steps 4.3.3.a through 4.3.3.f. are complete.

Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-G33_003_RO Rev 0 Step 4 4.3.3.g Perform the following for the oncoming RWCU PUMP: 1G33-C001A/B 4.3.3.g.1 Take the oncoming RWCU PUMP to START.

Critical Step Standard: Candidate takes 1G33-C001A/B to START.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 5 4.3.3.g.2 Verify the oncoming RWCU Pump Warm Up Isolation Valve.

1G33-F045A/B Standard: Candidate directs NLO to perform Step 4.3.3.g.2.

Instructor Cue: Driver: Inform Candidate that Step 4.3.3.g.2 is complete Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-G33_003_RO Rev 0 Step 6 4.3.3.h Throttle the RWCU FILTER/DEMIN BYPASS VALVE to establish normal RWCU INLET FLOW in accordance with Normal Operation/Data.

1G33-F0044 Critical Step Standard: Candidate throttles 1G33-F044 open to establish 350 to 450 gpm.

Instructor Cue: None Notes: If the Candidate starts RWCU Pump A, Step 4.3.4 is N/A SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: RWCU pump A has been restarted and Inlet Flow is controlled between 350 and 450 gpm.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-G33_003_RO Rev 0 JPM CUE SHEET INITIAL

The Plant is in Mode 1.

CONDITIONS:

RWCU Pump A tripped 20 minutes ago due to a human performance error.

RWCU FD A is being backwashed.

Its been determined that fill and vent of the RWCU system is not required.

INITIATING CUE: Unit Supervisor directs you, the Balance of Plant Operator, to recover RWCU pump A.

An NLO is in the plant to assist you.

OT-3701-E12_507_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: E12 Residual Heat Removal Time Critical: No Alternate Path: Yes Setting: Simulator Applicability: RO/SRO Safety Function: 5 - Containment Integrity Validated Time: 8 Minutes

References:

EOP-SPI 3.1 Rev. 5 & EOP-SPI-6.1 Rev. 4 Required Material: EOP-SPI 3.1 Containment Spray Operation EOP-SPI 6.1 RHR A Injection EOP-SPI 6.2 RHR B Injection Task: 205-541-05-01 Realign Containment Spray to LPCI Task Standard: Shift RHR Loop A from Containment Spray to Supp Pool Cooling; realign RHR Loop A to LPCI Injection upon trip of RHR Loop B.

K/A: 226001 RHR/LPCI: Containment Spray System Mode - A2.20, & Ability to (a) predict the impacts of the following on the RHR/LPCI: Containment Spray System Mode; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accident IR 3.7.

1. Setup Instructions: Reset simulator to IC-115. Keep simulator in FREEZE and insert Schedule file JPM E12-507.sch. Verify Event file JPM E12-507.evt loads. Place yellow switch cap on HPCS pump and Injection valve. When SPDS comes back, place simulator in RUN, acknowledge alarms, when SPDS updates, rescale screens if necessary, and place simulator in FREEZE. After Evaluator reads Initiating Cue and directs placing simulator in run, place simulator in RUN. Provide marked up copies of EOP-SPI 3.2 & EOP-SPI 6.1

& 6.2. Instructor to act as ATC to silence all alarms not on P601.

2. Location / Method: Simulator - Performance

3. Initial Condition: HPCS was tagged out for maintenance. A loss of all high-pressure injection occurred causing entry into the EOPs. LPCS and RHR loops were lined up for injection IAW EOP-SPIs 6.1, 6.2, 6.3, & 6.5. LPCS tripped on overcurrent. RHR C injection valve lost power. Emergency Depressurization was performed. Containment Spray Loop A was initiated due to rising Containment temperature. Currently, RHR B is only source of injection to control RPV level.

4. Initiating Cue: Unit Supervisor directs you, the Balance of Plant Operator, to terminate Containment Spray Loop A then align RHR A in Suppression Pool Cooling.

Start: Stop:

Candidate:

OT-3701-E12_507_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 EOP-SPI 3.1 CONTAINMENT SPRAY OPERATION 1.0 IF Containment Spray(s) have been initiated:

Containment pressure cannot be maintained greater than 0 psig

Directed to terminate Containment Spray operations THEN TERMINATE RHR Containment Spray as follows:

1.1 IF Containment Spray A Loop is in service, then TERMINATE Containment Spray A Loop as follows:

NOTE LPCI A INJECTION VALVE E12-F042A control switch is overridden closed before resetting Containment Spray logic with a LPCI initiation signal present to prevent uncontrolled LPCI injection into the RPV.

1.1.1 Take LPCI A INJECTION VALVE control switch to CLOSE. E12-F042A Critical Step Standard: Candidate takes 1E12-F042A to close.

Instructor Cue: None Notes: Containment Spray must be terminated prior to negative pressure in containment as indicated by a containment vacuum breaker opening.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_507_RO Rev 0 Step 2 1.1.2 Verify CNTMT SPRAY A MANUAL INITIATION pushbutton collar in DISARM. E12A-S63A Standard: Candidate rotates Initiation pushbutton collar to DISARM.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 3 1.1.3 Depress CNTMT SPRAY A SEAL IN RESET pushbutton to reset the Containment Spray initiation logic. E12A-S64A Critical Step Standard: Candidate depresses the Seal In Reset pushbutton.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_507_RO Rev 0 Step 4 1.1.4 Close CNTMT SPRAY A SECOND SHUTOFF. E12-F537A 1.1.5 If Combustible Gas Mixing System A is not running, then close CNTMT SPRAY A FIRST SHUTOFF. E12-F028A Critical Step Standard: Candidate closes 1st and 2nd spray shutoff valves before a containment vacuum breaker opens.

Instructor Cue: When Candidate reports RHR B pump trip or following your RHR B Pump trip update, direct them to establish RPV level band of 150 to 219 inches.

Notes: When E12-F537A is taken to CLOSE, RHR B pump will trip and RPV level will start to lower.

EOP-SPI 6.1, RHR A Injection contains instructions for shifting from Containment Spray to LPCI injection.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_507_RO Rev 0 Step 5 EOP-SPI 6.1 RHR A INJECTION ENTRY CONDITIONS This instruction is entered when directed to inject or prepare to inject into the RPV inside or outside the shroud with LPCI A. Injection with this instruction secures Containment Spray A operation and the A Loop of Suppression Pool Cooling if in service.

4.2 Verify RHR A Test Valve to Suppression Pool is closed 1E12-F024A 4.3 IF RHR A is in-service providing Containment Spray, THEN TERMINATE Containment Spray as follows:

Standard: Candidate determines EOP-SPI 6.1 contains the steps to shift from Containment Spray to LPCI injection and verifies Steps 4.2 and 4.3 are complete.

Instructor Cue: None Notes: Because of the timing of RHR B trip, Step 4.1 need not be performed.

Steps 4.3.14.3.5 were completed in EOP-SPI 3.1.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 6 4.4 Verify RHR A HXS OUTLET VALVE is OPEN. 1E12-F003A 4.5 Verify RHR A HXS BYPASS VALVE is OPEN. 1E12-F048A Standards: Candidate verifies E12-F003A & E12-F048A valves are open.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_507_RO Rev 0 Step 7 5.0 Perform the following as needed, while injecting into the RPV:

5.1 WHEN desired to inject inside the shroud, THEN PERFORM the following:

5.1.1 VERIFY the SHUTDOWN COOLING A TO FDW SHUTOFF valve is FULLY CLOSED. E12-F053A 5.1.2 OPERATE LPCI A INJECTION VALVE. E12-F042A 5.2 When desired to inject outside the shroud, then perform the following:

5.2.1 At 1H13-P629, verify RHR ISOL BYPASS E12-F053A keylock switch is in BYPASS. E12AS74 5.2.2 Verify LPCI A INJECTION VALVE is CLOSED. E12-F042A 5.2.3 Throttle SHUTDOWN COOLING A TO FDW SHUTOFF to the desired flowrate. E12-F053A Critical Step Standard: Candidate opens E12-F042A or throttles E12-F053A valve to stabilize and recover RPV level.

Instructor Cue: None Notes: In the Initial Conditions, it was given that RHR A was prepared for injection, which means E12-F053A throttle capability was enabled.

Injection outside the shroud is preferred. The Candidate may use Step 5.1, which opens the Injection valve, E12-F042A. However, they should transition to the E12-F053A valve.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Containment Spray A loop has been terminated and LPCI injection using the RHR A is restoring/maintaining RPV level 150 - 219.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-E12_507_RO Rev 0 JPM CUE SHEET INITIAL

HPCS was tagged out for maintenance.

CONDITIONS:

A loss of all high-pressure injection occurred causing entry into the EOPs.

LPCS and RHR loops were lined up for injection IAW EOP-SPIs 6.1, 6.2, 6.3, & 6.5.

LPCS tripped on overcurrent.

RHR C injection valve lost power.

Emergency Depressurization was performed.

Containment Spray Loop A was initiated due to rising Containment temperature.

Currently, RHR B is only source of injection to control RPV level INITIATING CUE: Unit Supervisor directs you, the Balance of Plant Operator, to terminate Containment Spray Loop A then align RHR A in Suppression Pool Cooling.

OT-3701-C11_010_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Rod Control and Information System Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 7 - Instrumentation Setting: Control Room / Plant or Simulator Validated: 11 minutes

References:

SOI-C11 (RCIS) Rev 32 Required Material: SOI-C11 (RCIS) - Rod Control And Information System SOI-C11 (RCIS) - Attachments 1 & 4 Tasks: 214-512-04-01 Bypass a Control Rod in the RGDS Task Standard: Bypass the control rod drive transponder in RGDS per SOI-C11 (RCIS)

K / A Data: 201005 - Ability to monitor automatic operations of the Rod Control And Information System (RCIS) including: A3.03 Verification of proper functioning/ operability: BWR-6. Importance: RO 3.4 SRO 3.3

1. Setup Instructions: Reset simulator to IC-111 for the 2021 ILO NRC Exam. Ensure Control Rod 26-55 is at position 00. Provide yellow copy of SOI-C11(RC&IS)

2. Location / Method: Control Room / Simulation or Simulator / Performance

3. Initial Condition: Rod Drive Gang System has been experiencing spurious shutdowns.

I&C has determined that HCU 26-55 Transponder is the problem. Currently Rod 26-55 is at position 00

4. Initiating Cue: The Unit Supervisor directs you as an Extra Reactor Operator to Rod Drive Bypass HCU 26-55 in RGDS.

Start Time: End Time:

Candidate OT-3701-C11_010_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 SOI-C11 (RCIS) - Rod Control And Information System 7.17 Rod Drive Bypass in RGDS CAUTIONS

Bypassing a rod drive transponder does not always block the drive signal to the rod.

Selecting the affected rods gang and using the gang mode can result in rod movement for the bypassed rod. When moving rods in a gang containing a bypassed rod drive transponder, gang mode should not be used unless the bypassed rod has had its drive solenoids electrically disconnected.

NOTES

The rod drive bypass function is located in the RGDC 1H13-P653, on the ANALYZER II card. The Drive Bypass Register is comprised of 16 toggle switches in a horizontal row.

- The left most switch has the bypass function.

- The 10 right most switches are provided for the binary address of the affected rod.

- The remaining 5 toggle switches are not used and should remain in the down position.

A second licensed Operator or other technically qualified member of the Unit Technical Staff must verify any bypassing operation. This is documented on Attachment 4, Verification Checklist Sections 7.17 and 7.18, Rod Drive Bypass/Restoration in RGDC.

Step 1 (continued on next page)

OT-3701-C11_010_RO Rev 0 Step 1 (continued) 7.17.1 INFORM the following a rod drive requires bypassing:

Unit Supervisor

Reactor Engineer Standard: Candidate informs the Unit Supervisor and Reactor Engineer.

Instructor Cue: Acknowledge the bypassing of a Rod Drive in RGDS.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 7.17.2 DETERMINE the binary address of the rod to be bypassed from Attachment 1, Binary Coordinates.

Critical Step Standard: Candidate determines binary address of Rod 26-55.

Instructor Cue: None Notes: Address for 26 = X4 to X0 = 01000, address for 55 = Y4 to Y0 = 01111 SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_010_RO Rev 0 Step 3 7.17.3 RECORD the following on Attachment 4, Verification Checklist Sections 7.17 and 7.18, Rod Drive Bypass/Restoration in RGDC.

Binary address of the rod to be bypassed.

Rod position of the rod to be bypassed.

Standard: Candidate records the above address and the position.

Instructor Cue: Acknowledge the bypassing of a Rod Drive in RGDS.

Notes: Rod position given in Initial Conditions - 00 SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 7.17.4 PERFORM Independent Verification of the following:

Binary address of the rod to be bypassed.

Rod position of the rod to be bypassed.

Standard: Candidate asks for independent verification.

Instructor Cue: Independent Verification complete.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_010_RO Rev 0 Step 5 NOTES

Position toggle switches up for a 1 and down for a 0.

DRIVE BYPASSED on the OCM will be backlit to indicate a drive has been bypassed.

7.17.5 POSITION the 10 BYPASSED ROD IDENTITY switches (right most) on the Bypass Register to the binary address for the affected rod.

Critical Step Standard: Candidate positions the 10 rod identity switches.

Instructor Cue: None Notes:

Control Rod to Binary Address Rod be Bypassed X4 X3 X2 X1 X0 Y4 Y3 Y2 Y1 Y0 Position 26-55 0 1 0 0 0 0 1 1 1 1 00 SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 6 7.17.6 PLACE the bypass switch (left most) in the BYPASSED position (up) at the RGDC.

Critical Step Standard: Candidate places the bypass switch UP.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_010_RO Rev 0 Step 7 7.17.7 PERFORM independent verification of the following:

Bypassed Rod Identity

Bypass Switch Position 7.17.8 VERIFY the following:

The Control Rod Position Bypass is recorded in the Plant Narrative Log.

The bypass condition is recorded in accordance with OAI-1701.

A copy of Attachment 4, Verification Checklist Sections 7.17 and 7.18, Rod Drive Bypass/Restoration in RGDC, is attached to the LCO Tracking Sheet.

Standard: The Candidate asks for independent verification, request Narrative Log entry, and Bypass Position is recorded per OAI-1701 Instructor Cue:

Independent Verification complete.

Log entry complete

Working on LCO paperwork Notes: Terminate the JPM.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Rod Drive Bypass complete for rod 26-55 in RGDC.

Evaluation Results: SAT_____ UNSAT_____

End Time OT-3701-C11_010_RO Rev 0 JPM CUE SHEET INITIAL

Rod Gang Drive System has been experiencing spurious shutdowns.

CONDITIONS:

I&C has determined that HCU 26-55 Transponder is the problem.

Currently Rod 26-55 is at position 00.

INITIATING CUE: The Unit Supervisor directs you as an Extra Reactor Operator to Rod Drive Bypass HCU 26-55 in RGDS.

OT-3701-P43_502_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: P43 Nuclear Closed Cooling System Time Critical: No Alternate Path: Yes Setting: Simulator Applicability: RO/SRO Safety Function: 8 - Plant Service Systems Validated Time: 15 Minutes

References:

SOI-P43 Rev. 20 Required Material: SOI-P43 NUCLEAR CLOSED COOLING SYSTEM Task: 208-515-02-01 Shift NCC Pumps 208-518-04-01 Respond to a Loss of Nuclear Closed Cooling System Task Standard: Shift NCC pumps and respond to trip of a running NCC pump by starting standby pump K/A: 400000 Component Cooling Water System (CCWS) - A2.01, Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Loss of CCW pump, Importance RO 3.3

1. Setup Instructions: Reset simulator to IC-111. Insert Schedule file JPM P43-502_RO.sch. Stage ONI-P43 book in SAS. Driver required for field communications and Event insertion.

2. Location / Method: Simulator / Performance

3. Initial Condition: Plant operating at power. NCC A & B pumps are running. NCC B pump will be tagged out tonight for scheduled maintenance.

4. Initiating Cue: Unit Supervisor directs you as the Balance of Plant Operator to shift off of NCC B pump in preparation for tagging it out.

Start: Stop:

Candidate:

OT-3701-P43_502_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 SOI-P43 Nuclear Closed Cooling System 7.1 Shifting NCC Pumps 7.1.1 Refer to Additional NCC Pump Startup and START the standby pump.

7.1.2 Refer to NCC Pump Shutdown and stop one of the running pumps.

4.2 Additional NCC Pump Startup 4.2.1 Throttle the oncoming NCC Pump Disch 10% open. P43-F513C Standard: Candidate Reviews SOI-P43 to determine correct procedure sections to use.

Candidate directs NLO to close P43-F513C to 10% open.

Instructor Cue: None Notes: Driver: IC has P43-F513C at 10% open. As NLO, when directed to throttle P43-F513C, wait 30 seconds and inform them that the valve is throttled.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P43_502_RO Rev 0 Step 2 4.2.2 Take the oncoming NCC PUMP control switch on Common Long Response Control Panel H13-P970 to START. P43-C001C Critical Step Standard: Candidate takes P43-C001C to START.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 3 4.2.3 Open the oncoming NCC Pump Disch. P43-F513C 4.2.4 Verify NCC HDR PRESSURE on P970 stabilizes between 94 - 123 psig.

P43-R221 4.2.5 If NCC HDR PRESSURE on P970 is > 125 psig with two pumps operating, then perform the following:

Standard: Candidate directs NLO to open P43-F513C and verifies NCC header pressure in correct range and proceeds to shutdown of NCC B pump.

Instructor Cue: None Notes: Driver: When directed to open P43-F513C, initiate Event 11 and after 45 seconds, report the valve open.

Step 4.2.5 will be N/A.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P43_502_RO Rev 0 Step 4 6.1 NCC Pump Shutdown 6.1.1 Slowly CLOSE the desired NCC Pump Disch. P43-F513B Standard: Candidate directs NLO to slowly close P43-F513B.

Instructor Cue: None Notes: Driver: As NLO, when directed to close P43-F513B, monitor valve position in Insight (ypxrsw015) or Xtreme View and initiate Event 12.

Give candidate a mark when valve almost closed.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 5 6.1.2 Immediately take the offgoing NCC PUMP control switch on H13-P970 to STOP. P43-C001B Critical Step Standard: Candidate takes P43-C001B to STOP when given mark by NLO.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P43_502_RO Rev 0 Step 6 6.1.3 Open the offgoing NCC Pump Disch. P43-F513B Standard: Candidate directs NLO to open P43-F513B.

Instructor Cue: None Notes: Driver: As NLO, when directed to open P43-F513B, initiate Event 13, wait 30 seconds and report valve is open.

NCC C pump will start to degrade shortly after P43-F513B is open.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 7 NCC C pump coupling breaks Standard: Candidate identifies degradation of NCC C pump and entry condition into ONI-P43.

Instructor Cue: Entering ONI-P43, Loss Of Nuclear Closed Cooling.

Inform the Candidate that they own ONI-P43 actions.

Notes: Driver: As NLO, if asked, It looks like the coupling broke.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P43_502_RO Rev 0 Step 8 ONI-P43 Loss Of Nuclear Closed Cooling 4.0 SUPPLEMENTAL ACTIONS 4.1 Loss of Nuclear Closed Cooling 4.1.1 Only one NCC Pump is running A Standby NCC Pump is available START a standby NCC Pump.

Critical Step Standard: Candidate takes P43-C001B to START.

Instructor Cue: None Notes: ONI-P43 allows starting a standby pump with the discharge valve fully open.

Driver: If directed to throttle P43-F513B to 10%, initiate Event 14, wait 30 seconds and report valve is throttled.

Driver: If directed to open P43-F513B following pump start, initiate Event 15, wait 45 seconds and report valve is open.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P43_502_RO Rev 0 Step 7 NCC C pump is stopped Standard: Candidate stops NCC C pump.

Instructor Cue: None Notes: Driver: If directed to throttle P43-F513C, initiate Event 17, wait 30 seconds and report valve is throttled.

Terminate the JPM SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: NCC B pump restarted after degradation of NCC C pump flow.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-P43_502_RO Rev 0 JPM CUE SHEET INITIAL

Plant operating at power. NCC A & B pumps are running.

CONDITIONS:

NCC B pump will be tagged out tonight for scheduled maintenance.

INITIATING CUE: Unit Supervisor directs you as the Balance of Plant Operator to shift off of NCC B pump in preparation for tagging it out.

OT-3701-M13_501_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: M13, Drywell Cooling System Time Critical: No Alternate Path: Yes Setting: Simulator Applicability: RO/SRO Safety Function: 9 - Radioactivity Release Validated Time: 10 Minutes

References:

SOI-M13 Rev. 7 and ARI-H13-P800-03 Rev. 13 Required Material: SOI-M13, Drywell Cooling System ARI-H13-P800-03, Heating Ventilation And Air Conditioning Control Panel (Unit 1)

Task: 314-501-02-01 Shift Drywell Cooling Fans Task Standard: Perform shift of DW fans and respond to high vibration K/A: 288000 Plant Ventilation Systems - A4.01, Ability to manually operate and/or monitor in the control room: Start and stop fans, Importance RO 3.1

1. Setup Instructions: Reset simulator to IC-111. Insert Schedule file JPM M13-501_RO.sch and verify Event file JPM M13-501_RO.evt loads. Put up DW Temperature Validation Screen.

2. Location / Method: Simulator Classroom Plant Control Room / Performance /

Administrative Performance

3. Initial Condition: Plant operating at power.

4. Initiating Cue: Unit Supervisor directs you as the Balance of Plant Operator to shift Lower, Middle, and Upper Drywell Cooling Fans to equalize run time. The ATC will monitor DW temperatures.

Start: Stop:

Candidate:

OT-3701-M13_501_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 Drywell Cooling System 7.1 Shifting Lower Drywell Cooling Fans 7.1.1 Place the oncoming LW DW CLG FAN in ON. 1M13-C001B Critical Step Standard: Candidate places control switch for 1M13-C001B to ON.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 2 7.1.2 Place the offgoing LW DW CLG FAN in STBY. 1M13-C001A Critical Step Standard: Candidate places control switch for 1M13-C001A to STBY.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-M13_501_RO Rev 0 Step 3 7.1.3 Confirm the green status light energized on the standby fan.

Standard: Candidate confirms green light illuminates for 1M13-C001A fan.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 4 7.2 Shifting Middle Drywell Cooling Fans 7.2.1 Place the oncoming MID DW CLG FAN in ON. 1M13-C002B Critical Step Standard: Candidate places control switch for 1M13-C002B to ON.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-M13_501_RO Rev 0 Step 5 7.2.2 Place the offgoing MID DW CLG FAN in STBY. 1M13-C002A Critical Step Standard: Candidate places control switch for 1M13-C002A to STBY.

Instructor Cue: None Notes: Shortly after 1M13-C002A is placed in STBY, the DW COOLING FAN 2B VIBRATION HIGH annunciator will alarm SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 6 7.2.3 Confirm the green status light energized on the standby fan.

Standard: Candidate confirms green light illuminates for 1M13-C002A fan.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-M13_501_RO Rev 0 Step 7 7.3 Shifting Upper Drywell Cooling Fans 7.3.1 Place the oncoming UP DW CLG FAN in ON. 1M13-C003B Critical Step Standard: Candidate places control switch for 1M13-C003B to ON.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 8 7.3.2 Place the offgoing UP DW CLG FAN in STBY. 1M13-C003A Critical Step Standard: Candidate places control switch for 1M13-C003A to STBY.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-M13_501_RO Rev 0 Step 9 7.1.3 Confirm the green status light energized on the standby fan.

Standard: Candidate confirms green light illuminates for 1M13-C003A fan.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 10 ARI-H13-P800-03 Heating Ventilation And Air Conditioning Control Panel (Unit 1)

E6 DW COOLING FAN 2B VIBRATION HIGH.

1.0 CAUSE OF ALARM 1.1 High vibration on Mid Drywell Cooling Fan 2B as sensed by 1M13-N110B.

1.2 Alarm could be caused by a fan malfunction.

4.0 SUBSEQUENT OPERATOR ACTION 4.1 Refer TO SOI-M13 and shift from Mid Drywell Cooling Fan 2B to Mid Drywell Cooling Fan 2A.

4.2 At IB-620, A/02, MOMENTARILY DEPRESS the reset pushbutton on the vibration relay.

Standard: Candidate reviews ARI-H13-P800-03-E6 and determines that middle DW fans need to be shifted from B to A and reset the vibration alarm locally.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-M13_501_RO Rev 0 Step 11 7.2 Shifting Middle Drywell Cooling Fans 7.2.1 Place the oncoming MID DW CLG FAN in ON. 1M13-C002A Critical Step Standard: Candidate places control switch for 1M13-C002A to ON.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 12 7.2.2 Place the offgoing MID DW CLG FAN in STBY. 1M13-C002B Critical Step Standard: Candidate places control switch for 1M13-C002B to STBY.

Instructor Cue: Driver: If directed to reset vibration alarm, wait 30 seconds then delete Malfunction 1H13P8003EA6.

Notes: Candidate may place the control switch for 1M13-C002B to OFF.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-M13_501_RO Rev 0 Step 13 7.2.3 Confirm the green status light energized on the standby fan.

Standard: Candidate confirms green light illuminates for 1M13-C002B fan.

Candidate directs NLO to reset M13-C002A vibration alarm locally.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Upper and Lower B DW Cooling Fans are running and Middle A DW Cooling Fan is running.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-M13_501_RO Rev 0 JPM CUE SHEET INITIAL The plant is operating at power.

CONDITIONS:

INITIATING CUE: Unit Supervisor directs you as the Balance of Plant Operator, to shift Lower, Middle, and Upper Drywell Cooling Fans to equalize run time.

The ATC will monitor DW temperatures.

OT-3701-C61_110_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: C61 RSD Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 2 - Reactor Water Inventory Control Setting: Plant (Non-RRA)

Validated Time: 13 Minutes

References:

IOI-11 Rev 38 Required Material IOI Shutdown From Outside Control Room Task: 007-505-04-01 Startup RCIC from RSP to Maintain Reactor Water Level Task Standard: Start RCIC and control RPV Water level from Division 1 Remote Shutdown Panel per IOI-0011 Attachment 17.

K/A Data: 295016 - AA1.06 Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: Reactor water level RO 4.0 SRO 4.1, AA1.08 Reactor pressure RO 4.0 SRO 4.0, AA2.02 Reactor water level RO 4.2* SRO 4.3*, & AA2.03 Reactor pressure RO 4.3* SRO 4.4*

1. Setup Instructions: Obtain yellow copies of IOI-0011 Attachment 17.

2. Location / Method: Plant / Simulation

3. Initial Condition: The Control Room was evacuated due to a fire. The actions of ONI-C61 are complete. IOI-0011 Attachment 19, Transfer to Division 1 Remote Shutdown Panel is complete. Reactor level is 180 and slowly lowering.

4. Initiating Cue: Unit Supervisor directs you the Reactor Operator to establish and maintain Reactor Level 185 - 215 using RCIC per IOI-0011 Attachment 17.

Start Time End Time Operator 1

OT-3701-C61_110_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 IOI Shutdown From Outside Control Room ATTACHMENT 17 - Level Control Using RCIC 4.0 RCIC STARTUP 4.1 EVACUATE any personnel in the Reactor Building Annulus.

4.2 PREVENT access to the Reactor Building Annulus.

4.3 VERIFY Attachment 19, Control Transfer to Division 1 Remote Shutdown Panel has been completed.

Standard: Candidate uses Plant page to evacuate annulus and contacts Security or Radiation Protection to prevent access to annulus.

Instructor Cue: Act as Radiation Protection or Security no personnel are in the annulus and will not allow entry.

Notes: Attachment 19 completion given in Initial Condition.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

2

OT-3701-C61_110_RO Rev 0 Step 2 NOTE The RCIC Turbine Gland Seal Compressor 1E51-C004 is NOT required for RCIC System operation.

4.4 TAKE the RCIC TURBINE GLAND SEAL COMP to START. 1E51-C004 Standard: Candidate simulates start of Gland Seal Compressor 1E51-C004.

Instructor Cue: Initially: Green light on and Red light off After start: Red light on and green light off Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 4.5 VERIFY the RCIC PUMP FLOW CONTROLLER is in automatic. 1C61-R001 4.6 VERIFY the RCIC PUMP FLOW CONTROLLER is set for 700 gpm flow. 1C61-R001 Critical Step Standard: Candidate simulates placing 1C61-R001 in Auto and adjusts to 700 gpm.

Instructor Cue: Initially: Controller is in Manual at minimum.

After: 1C61R001 is in Auto at 700 gpm Notes: Initially controller will be in manual (M) and Operator will need to place it in auto (A); then adjust flow to ~ 700 gpm SAT ___ UNSAT ___

Comment(s):________________________________________________________________

3

OT-3701-C61_110_RO Rev 0 Step 4 4.7 PLACE the RCIC TURBINE REMOTE TRIP in NORM.

4.8 HOLD the RCIC TURBINE TRIP THRT VLV LATCH in OPEN UNTIL the valve is full open. 1E51-F510 4.9 IF the RCIC Turbine Trip light does NOT extinguish while resetting the RCIC trip, THEN RESET the RCIC turbine locally.

Critical Step Standard: Candidate simulates RCIC turbine remote trip to NORM, holds 1E51-F510 open until valve full open, and verifies RCIC turbine trip light extinguished.

Instructor Cue: RCIC remote trip in NORM.

1E51-F510 - at start, green light on and red light off, then dual indication, then red light on and green light off.

RCIC turbine trip light is OFF.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 4.10 TAKE the RCIC STEAM SHUTOFF to OPEN. 1E51-F045 4.11 CONFIRM the RCIC turbine starts.

Critical Step Standard: Candidate simulates opening 1E51-F045 and confirms indications of RCIC start.

Instructor Cue: At start - Green light on and red light off, then dual indication, then red light on and green light off.

Normal indications for RCIC start RPM increasing.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

4

OT-3701-C61_110_RO Rev 0 Step 6 4.12 TAKE the RCIC PUMP MIN FLOW VALVE to OPEN. 1E51-F019 4.13 TAKE the RCIC INJECTION VLV to OPEN. 1E51-F013 Critical Step Standard: Candidate opens 1E51-F019 and 1E51-F013 Instructor Cue: Valves are opening - green light on and red light off, then dual indication, then red light on and green light off Notes: Operator checks turbine speed, speed increasing, and flow is indicated and increasing.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 7 4.14 WHEN flow to the reactor vessel has been established, THEN TAKE the RCIC PUMP MIN FLOW VALVE to CLOSE. 1E51-F019 4.15 ADJUST flow controller to maintain desired Reactor Vessel level 1C61-R001 Critical Step Standard: Candidate closes 1E51-F019 and adjust flow controller to maintain level.

Instructor Cue: E51-F019 red light on and green light off, then dual indication, then green light on and red light off.

Reactor level has stopped lowering at 175, Reactor level is 180 and rising steadily.

Notes: Operator shall explain operation of flow controller to maintain reactor level.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

5

OT-3701-C61_110_RO Rev 0 Terminating Cue: RCIC maintaining reactor level 185 - 215 inches.

Evaluation Results: SAT_____ UNSAT_____

End Time 6

OT-3701-C61_110_RO Rev 0 JPM CUE SHEET INITIAL

The Control Room was evacuated due to a fire.

CONDITIONS:

The actions of ONI-C61 are complete.

IOI-0011 Attachment 19, Transfer to Division 1 Remote Shutdown Panel, is complete.

Reactor level is 180 and slowly lowering.

INITIATING CUE: Unit Supervisor directs you the Reactor Operator to establish and maintain Reactor Level 185 - 215 using RCIC per IOI-0011 Attachment 17.

7

OT-3701-R14_501_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: R14 - 120 V AC Vital Inverters Time Critical: No Alternate Path: Yes Safety Function: 6 - Electrical Applicability: RO/SRO Setting: Plant (non-RRA) Validated Time: 24 Minutes

References:

SOI-R14 Rev 20 Required Material: SOI-R14 - 120 V AC Vital Inverters, Pictures of INPUT POWER breaker and TRANSFER SWITCH Task: 082-502-01-04 Start Up the Divisional ATWS UPS Inverter 082-505-01-04 Shift ATWS UPS Power Supplies Task Standard: Startup the Div. 1 ATWS Inverter and transfers the UPS to the inverter.

K/A Data: 262002, Uninterruptable Power Supply (A.C./D.C.) - K4.01 Knowledge of Uninterruptable Power Supply (A.C./D.C.) design feature(s) and/or interlocks which provide for the following: Transfer from preferred power to alternate power supplies Importance: RO 3.4 / SRO 3.7

1. Setup Instructions: Place Picture 5 in package backwards. If Inverter is shutdown Pictures 1, 2, & 5 are not necessary.

2. Location / Method: Plant / Simulation

3. Initial Condition: Plant is shutdown. Division 1 ATWS UPS is on the Alternate Source

4. Initiating Cue: Unit Supervisor directs you the Plant Operator to shift Division 1 ATWS UPS to the inverter in accordance with SOI-R14.

Start: Stop:

Candidate:

1

OT-3701-R14_501_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 Review SOI-R14 Standard: Operator reviews SOI-R14 and determines that a key is required for an inverter shift.

Instructor Cue: None Notes: The key can be obtained from the CRA (Control Room Assistant).

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

2

OT-3701-R14_501_RO Rev 0 Step 2 SOI-R14 - 120 V AC Vital Inverters 7.4 Shifting Divisional ATWS UPS to the Inverter NOTE Performance of this section requires the transfer switch key.

7.4.1 IF the inverter is NOT in service, THEN REFER TO Section 4.3, Divisional ATWS UPS Inverter Startup, and ALIGN the system. 1R14-S012 Critical Step: Operator determines that the Div 1 ATWS inverter is not in service and will refer to section 4.3 to startup the inverter.

Instructor Cue:

When arriving at Div 1 ATWS UPS show operator Picture #1 &

Picture #2.

If asked, inform Operator that if voltmeter switch moved to INV, voltage will be reading zero (0).

Notes: Picture #1 shows the INPUT POWER breaker (CB1) on the static transfer switch panel is in the OFF position.

Picture #2 shows right side of panel with appropriate lights illuminated and 0 input volts.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

3

OT-3701-R14_501_RO Rev 0 Step 3 4.3 Divisional ATWS UPS Inverter Startup NOTE This section assumes that the Div 1(2) ATWS UPS distribution system is being supplied from the Alternate Source. If the distribution system has been de-energized completely or a system casualty has occurred, the Recovery of Div 1(2) ATWS UPS, After Complete Shutdown section should be used.

4.3.1 CONFIRM the TRANSFER SWITCH in BYPASS at Div ATWS UPS to be started. 1R14-S012 Standard: Operator confirm the Transfer Switch in BYPASS.

Instructor Cue: Show operator Picture #3.

Notes: Picture #3 shows Transfer Switch in BYPASS position.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 4 4.3.2 CLOSE the DIV ATWS UPS disconnect at Dist Panel for the UPS to be started.

1R14-S012 ED1A 06-22 Critical Step: Operator simulates closing breaker 06-22 on EDIA.

Instructor Cue: Initially: Disconnect 06-22 handle is pointing down to the right (OPEN)

After simulating closing breaker: Breaker 06-22 is as you see it.

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

4

OT-3701-R14_501_RO Rev 0 Step 5 4.3.3 PERFORM the following at the Divisional ATWS UPS to be started:

1R14-S012 4.3.3.a MOMENTARILY DEPRESS the PRE-CHARGE button.

4.3.3.b WAIT 10 seconds.

4.3.3.c CLOSE the INPUT POWER breaker. CB1 Critical Step: Operator depresses the PRE-CHARGE button waits 10 seconds and closes CB1 Instructor Cue:

PRE-CHARGE button is depressed.

CB1 is closed

60 hz hum is heard Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 6 4.3.4 PLACE the Voltmeter Selector Switch in the INV position.

4.3.5 CONFIRM 117.5 to 122.5 VAC as indicated on AC OUTPUT VOLTAGE.

Standard: Operator simulates placing the Voltmeter Selector Switch in the INV position and checks voltage.

Instructor Cue: 1. Voltmeter Selector Switch in the INV position.

2. Voltage is as is (or 120 VAC*).

Notes:

It is anticipated that the Inverter will be in service during performance of this JPM. If not, inform operator voltage is 120 VAC.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

5

OT-3701-R14_501_RO Rev 0 Step 7 4.3.6 CONFIRM the following lights are lit.

SYNC LOSS

REV. XFER

ALT SOURCE NOT AVAIL 4.3.7 PLACE the Voltmeter Selector Switch in the A.C. output position 4.3.8 PERFORM Independent Verification of required components.

Standard: Operator confirms lights are lit, Simulates placing Voltmeter Selector Switch in the A.C. output position, and requests an IV Instructor Cue:

Lights are lit*.

Another operator will perform IV.

When Voltmeter placed in the A.C. output position, Voltage is as is (or 120 VAC*).

Notes:

It is anticipated that the Inverter will be in service during performance of this JPM. If so, the lights will be off.

Same lights as shown on Picture #2 are still on.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

6

OT-3701-R14_501_RO Rev 0 Step 8 4.3.9 Loads are supplied from the Alternate Source.

It is desired to supply the loads from the inverter.

THEN REFER TO Section 7.4, Shifting Divisional ATWS UPS to the Inverter, and ALIGN the system.

Standard: Operator returns to Section 7.4 to finish shift.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

7

OT-3701-R14_501_RO Rev 0 Step 9 7.4 Shifting Divisional ATWS UPS to the Inverter 7.4.2 CONFIRM the following:

Alternate Source Not Available lamp is on. (Indicates the alternate supply is not available to the static switch.)

Synch Loss lamp is on. (With the static switch bypassed, the inverter synch sensing circuit is isolated form the alternate source.) System AC loading can be verified by observation of the AC Ammeter at the static switch compartment.

7.4.3 REMOVE the TRANSFER SWITCH locking device.

7.4.4 PLACE the Voltmeter Selector Switch to INV position.

7.4.5 CONFIRM 118 to 127 VAC.

7.4.6 PLACE Voltmeter Selector Switch to the AC output position.

Standard: Operator confirms Alternate Source Not Available and Synch Loss lamps are ON and simulates moving Voltmeter Selector Switch to check voltage.

Instructor Cue:

TRANSFER SWITCH locking device is removed.

Voltmeter Selector Switch in INV position

Voltage is 124 VAC or as is.

Voltmeter Selector Switch in the AC output position.

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

8

OT-3701-R14_501_RO Rev 0 Step 10 7.4.7 IF the REV XFER light is off, THEN PERFORM the following:

7.4.7.a MOMENTARILY DEPRESS REV XFER. S102 7.4.7.b CONFIRM REV XFER light comes on.

Standard: Operator observes REV XFER light.

Instructor Cue: REV XFER light is ON.

Notes: REV XFER light was previously identified as ON. Steps 7.4.7.a & .b are N/A.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 11 7.4.8 PLACE the TRANSFER SWITCH in INVERTER.

Critical Step: Operator simulates placing TRANSFER SWITCH in INVERTER.

Instructor Cue: Switch in INVERTER.

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

9

OT-3701-R14_501_RO Rev 0 Step 12 7.4.9 CONFIRM the SYNC LOSS light is off.

7.4.10 CONFIRM the ALT SOURCE NOT AVAIL is off.

Standard: Operator confirms SYNC LOSS light and ALT SOURCE NOT AVAIL lights are off.

Instructor Cue: Show operator Picture #4.

Notes: Lights are OFF.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 13 7.4.11 MOMENTARILY DEPRESS the FWD XFER to transfer Loads to the Inverter through the Static Transfer Switch. S101 Critical Step: Operator simulates depressing the FWD XFER button.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

10

OT-3701-R14_501_RO Rev 0 Step 14 7.4.12 CONFIRM the REV. XFER S102 light goes out.

7.4.13 CONFIRM all control panel lights off with the exception of FWD XFER.

7.4.14 INSTALL the TRANSFER SWITCH locking device.

7.4.15 PERFORM Independent Verification of the required components.

Standard: Operator confirms lights and simulates installing locking device.

Instructor Cue: Lights are as is.

Locking device is installed.

IV will be done by another operator.

Notes: If inverter is shutdown at time of JPM, show picture #5 Terminate the JPM SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Terminating Cue: Candidate starts up the Division 1 ATWS Inverter and transfers the UPS to the inverter.

Evaluation Results: SAT_____ UNSAT_____

End Time:

11

OT-3701-R14_501_RO Rev 0 Picture 1 12

OT-3701-R14_501_RO Rev 0 Picture 2 13

OT-3701-R14_501_RO Rev 0 Picture 3 14

OT-3701-R14_501_RO Rev 0 Picture 4 15

OT-3701-R14_501_RO Rev 0 Picture 5 16

OT-3701-R14_501_RO Rev 0 JPM CUE SHEET INITIAL Plant is shutdown. Division 1 ATWS UPS is on the Alternate Source.

CONDITIONS:

INITIATING CUE: Unit Supervisor directs you the Plant Operator to shift Division 1 ATWS UPS to the inverter in accordance with SOI-R14.

17

OT-3701-P54_004_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Fire Protection via Low Pressure Core Spray Time Critical: No Alternate Path: No Setting: RRA Applicability: RO/SRO Safety Function: 8 - Plant Service Systems Validated Time: 20 Minutes

References:

ONI-SPI A-8 Rev. 5 Required Material: ONI-SPI A-8, LPCS FIRE WATER Task: 209-519-05-04 Assist With LPCS Fire Water Operation Task Standard: Align LPCS fast firewater for RPV level control, IAW ONI-SPI-A8.

K/A: 286000 Fire Protection System - A1.05, Ability to predict and/or monitor changes in parameters associated with operating the Fire Protection System controls including: System lineups Importance RO 3.2 SRO 3.2

1. Setup Instructions: None

2. Location / Method: Plant / Simulation

3. Initial Condition: The LPCS pump was tagged out for motor replacement when a transient occurred. Plant is operating in the EOPs. Current RPV level control sources ae not providing adequate injection.

4. Initiating Cue: Unit Supervisor directs you, an Extra Reactor Operator to align LPCS Fire Water IAW ONI-SPI-A8. Contact the Control Room when ready to inject.

Start: Stop:

Candidate:

OT-3701-P54_004_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-SPI A-8, LPCS FIRE WATER 1.0 ALIGN fast firewater as follows:

CAUTION Halligan tools will be required to open the radiation gates when operating valves if this procedure is entered from Emergency Management Overview, OAI-1901 (B.5.b).

1.1 AT AX 620 D/07, CONNECT a 5 hose to the Storz connection on the designated LPCS flange assembly.

1.2 ROUTE the hose to a source of water (e.g., hydrant, portable fire pump, or pumper).

1.3 VERIFY LPCS Pump 1E21-C001, breaker is OPEN. EH1111 NOTE Breakers are disabled if one of the following conditions are met:

Breaker is Racked To Disconnect / Removed From Pocket.

Breaker is Open with Lockout Hasp blocked in the extended position.

WARNING Operations within Bus EH11 cubicles, in the Unit 1 Division 1 Switchgear Room require 100 Cal Arc Flash Protection when Bus EH11 has been energized.

1.4 AT CC 620 (Division 1 Switchgear Room), VERIFY the LPCS Pump 1E21-C001, breaker is DISABLED.

Step 1 (continued next page)

OT-3701-P54_004_RO Rev 0 Step 1 (continued)

Critical Step Standard: Candidate simulates connecting the 5 hose to the Storz connection.

Candidate discusses routing the hose and disabling LPCS breaker.

Instructor Cue: 1. After Candidate describes where to obtain the hose, inform them that Maintenance Services has placed one end of the hose inside the roll-up door at Aux 620.

2. Inform Candidate that an NLO has connected the other end of the hose to a fire hydrant.

3. LPCS pump was tagged out in the Initial Conditions. If candidate checks LPCS pump breaker, inform them the breaker is removed from pocket.

Notes:

Candidate should describe where to obtain the 5 hose - from the B.5.b building between the cooling towers.

Steps 1.3 and 1.4 are performed outside the RRA SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 2 1.5 AT AX 620 D/07, OPEN FLEX Isol Vlv From LPCS Flush Line. 1X11-F018 Critical Step Standard: Candidate simulates opening 1X11-F018.

Instructor Cue: After describing opening the valve, 1X11-F018 is open.

Notes: Candidate should describe turning the handwheel counterclockwise and watching the indicating arrow on top of the valve rotate to the open direction. (geared ball valve)

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P54_004_RO Rev 0 Step 3 1.6 AT AX 620 D/07, OPEN Flush Wtr To LPCS Pump Disch Line. 1E21-F025 Critical Step Standard: Candidate describes/simulates opening 1E21-F025.

Instructor Cue: After describing opening the valve, 1E21-F025 is open.

Notes: A reach-rod handwheel for 1E21-F025 is located about 6 to the right and about 2 above 1X11-F018 (in clean area). 1E21-F025 is inside the LPCS Valve room on Aux 620 which is contaminated. It can be seen from the Step-Off-Pad. It is about 8 feet to the left of the Step-Off-Pad.

Candidate should describe turning the handwheel counterclockwise and watching the position indicator on the side of the valve.

SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Step 4 Contact the Control Room Standard: Candidate contacts the Control Room to report firewater aligned for RPV injection via LPCS.

Instructor Cue: None Notes: Terminate the JPM SAT ___ UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Firewater is aligned via LPCS piping for injection to the RPV.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-P54_004_RO Rev 0 JPM CUE SHEET INITIAL

The LPCS pump was tagged out for motor replacement when a CONDITIONS: transient occurred.

Plant is operating in the EOPs.

Current RPV level control sources are not providing adequate injection.

INITIATING CUE:

Unit Supervisor directs you, an Extra Reactor Operator to align LPCS Fire Water IAW ONI-SPI-A8.

Contact the Control Room when ready to inject.

ML22165A325

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