Text

2010 Perry Plant Initial License Examination Administered Operating Test
	ML102170206
Person / Time
Site:	Perry
Issue date:	07/18/2010
From:	Mcneil D; NRC/RGN-III/DRS/OLB
To:	;
References
	OT-3701-ADM_NRC10-A1
	Download: ML102170206 (230)
	v • d • e

OT-3701-ADM_NRC10-A1 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO/SRO Safety Function: Conduct of Operations Setting: Simulator Validated: 10 minutes

References:

SOI-E51 ref 25 Tasks: 217-526-02-01 Perform RCIC Valve and Flow Controller Position Verification Task Standard: Perform independent verification of system lineup per SOI-E51 K/A Data: 2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc. 4.1 / 4.0

1. Setup Instructions:

Reset simulator to IC-151 and run schedule file _NRC_JPM-2

Verify RCIC flow control is in MANUAL.

AV02_1E51F0025 to fail the RCIC ST SUPP FIRST DRN SHUTOFF valve closed is entered

1H13P60121AH1 to fail annunciator RCIC St Drn Trap Byp Level High is entered

Fill out form SOI-E51, Attachment 1 as the first verification and provide this form to the candidate.

2. Location / Method: Simulator / Perform

3. Initial Condition: The unit is at 100%. RCIC has been out of service for maintenance.

Last shift, RCIC was returned to standby readiness IAW SOI-E51, Section 4.1, Startup to Standby Readiness.

4. Initiating Cue: The Unit Supervisor directs you to Independently Verify the 1H13-P601 RCIC lineup, IAW SOI-E51, Attachment 1, Verification Checklist Section 4.1, Startup to Standby Readiness.

Start Time: End Time:

Candidate:

OT-3701-ADM_NRC10-A1 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 RCIC PUMP FLOW CONTROL 1E51-R600 700 GPM Standard: Operator observes RCIC PUMP FLOW CONTROL 1E51-R600 set at 700 gpm Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 RCIC PUMP FLOW CONTROL 1E51-R600 AUTO Critical Step: Operator finds controller in MANUAL and places RCIC PUMP FLOW CONTROL 1E51-R600 in AUTO.

Instructor Cue: When the US is informed about the mispositioning, then direct/inform the operator:

Place the controller in AUTO

Two other operators will perform verification / independent verification for that step

Continue on with the independent verification Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A1 Step 3 RCIC ST SUPP WARM-UP ISOL 1E51-F076 Closed.

Standard: Operator initials for RCIC ST SUPP WARM-UP ISOL 1E51-F076 Closed Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 RCIC ST SUPP INBD ISOL 1E51-F063 Open Standard: Operator initials for RCIC ST SUPP INBD ISOL 1E51-F063 Open Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 RCIC ST SUPP OTBD ISOL1E51-F064 Open Standard: Operator initials for RCIC ST SUPP OTBD ISOL1E51-F064 Open.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A1 Step 6 RCIC STEAM SHUTOFF 1E51-F045 Closed Standard: Operator initials for RCIC STEAM SHUTOFF 1E51-F045 Closed.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 7 TRIP THROTTLE VLV POSITION Open Standard: Operator initials for TRIP THROTTLE VLV POSITION Open Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 8 RCIC TURBINE TRIP THRT V LATCH 1E51-F510 Open Standard: Operator initials for RCIC TURBINE TRIP THRT V LATCH 1E51-F510 Open Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 9 OT-3701-ADM_NRC10-A1 Operator initials for RCIC INJECTION VLV 1E51-F013 Closed Standard: Operator initials for RCIC INJECTION VLV 1E51-F013 Closed Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 10 RCIC ST SUPP FIRST DRN SHUTOFF 1E51-F025 OPEN and SW IN AUTO Critical Step: Operator recognizes for RCIC ST SUPP FIRST DRN SHUTOFF 1E51-F025 is closed and informs the US.

Instructor Cue: When the US is informed about the mispositioning, then direct/inform the operator:

There is a report of an air leak on the valve.

When fixed, two other operators will perform verification /

independent verification for that step

Continue on with the independent verification Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A1 Step 11 RCIC ST SUPP SECOND DRN SHUTOFF 1E51-F026 OPEN and SW IN AUTO Standard: Operator initials for RCIC ST SUPP SECOND DRN SHUTOFF 1E51-F026 OPEN and SW IN AUTO Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 12 RCIC PUMP MIN FLOW VALVE 1E51-F019 Closed Standard: Operator initials for RCIC PUMP MIN FLOW VALVE 1E51-F019 Closed Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A1 Step 13 RCIC EXH VAC BRKR SECOND ISOL 1E51-F077 Open Standard: Operator initials for RCIC EXH VAC BRKR SECOND ISOL 1E51-F077 Open Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 14 RCIC EXH VAC BRKR FIRST ISOL 1E51-F078 Open Standard: Operator initials for RCIC EXH VAC BRKR FIRST ISOL 1E51-F078 Open Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A1 Step 15 RCIC TURBINE GLAND SEAL COMP 1E51-C004 SW IN AUTO and GREEN LIGHT ON.

Standard: Operator observes RCIC TURBINE GLAND SEAL COMP 1E51-C004 SW IN AUTO and GREEN LIGHT ON.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 16 RCIC TURB EXH SHUTOFF 1E51-F068 Open Standard: Operator initials for RCIC TURB EXH SHUTOFF 1E51-F068 Open Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 17 RCIC TURB CNDS TO CRW FIRST SHUTOFF 1E51-F004 SW IN AUTO Standard: Operator initials for RCIC TURB CNDS TO CRW FIRST SHUTOFF 1E51-F004 SW IN AUTO Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 18 OT-3701-ADM_NRC10-A1 RCIC PUMP CST SUCTION VALVE 1E51-F010 Open Standard: Operator initials for RCIC PUMP CST SUCTION VALVE 1E51-F010 Open Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 19 RCIC WATER LEG PUMP 1E51-C003 ON Standard: Operator initials for RCIC WATER LEG PUMP 1E51-C003 ON Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A1 Step 20 RCIC PUMP SUPR PL SUCT ISOL 1E51-F031 Closed Standard: Operator initials for RCIC PUMP SUPR PL SUCT ISOL 1E51-F031 Closed Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Instructor Cue: If the operator moves on to the next step, Seal Air Comp Disch Test Conn 1E51-F541, then tell the operator another Operator will independently verify it.

Terminating Cue: RCIC lineup, ATTACHMENT 1 completed.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_NRC10-A1 JPM CUE SHEET INITIAL CONDITIONS:

The unit is at 100%.

RCIC had been out of service for maintenance.

RCIC has been returned to standby readiness IAW SOI-E51, section 4.1, Startup to Standby Readiness.

INITIATING CUE: .

The Unit Supervisor directs you to Independently Verify the 1H13-P601 RCIC lineup, IAW SOI-E51, Attachment 1, Verification Checklist Section 4.1, Startup to Standby Readiness.

OT-3701-ADM_NRC10-A2 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO/SRO Safety Function: Conduct of Operations Setting: Classroom Validated: 20 minutes

References:

TMA-4206, page 18, paragraph 4.9.1.4.b and Attached Work Schedule Tasks: 299-831-03-01 Perform licensed duties only if your license is Current and Active Task Standard: Review proposed work schedules to determine appropriate schedule(s) to reactivate RO license per TMA-4206, Licensed Operator Requalification Programs 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. RO 3.3 SRO 3.8

1. Setup Instructions: N/A

2. Location / Method: Classroom / Perform

3. Initial Condition: It is March 27, 2011 and you have an INACTIVE RO license.

Operations wants you to activate your RO license. The OPS Training Coordinator has developed 6 proposed schedules to re-activate your license.

4. Initiating Cue:

Using the proposed schedules determine if each of the schedules meets TMA-4206, Licensed Operator Requalification Programs required:

o Number of work hours o Position Title to work under the direction of o Completed turnovers

If a schedule does not meet one of these requirements, EXPLAIN why it does not.

STATE which, if any, of the proposed schedules you would work so that your license may be re-activated.

Start Time: End Time:

Candidate:

OT-3701-ADM_NRC10-A2 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 Schedule 1.

Standard: Operator determines Schedule 1 does not meet:

40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months in a quarter

The appropriate watch standing position (NOT Field Supervisor)

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 Evaluate Schedule 2 Critical Step: Operator determines Schedule 2 can be used to reactivate his license.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A2 Step 3 Evaluate Schedule 3 Standard: Operator determines Schedule 3 does not meet the minimum of 1 oncoming turnover requirement.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Evaluate Schedule 4 Standard: Operator determines Schedule 4 does not meet the minimum 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months in a quarter.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A2 Step 5 Evaluate Schedule 5 Standard: Operator determines Schedule 5 does not meet the appropriate watch standing position (NOT Field Supervisor).

Instructor Cue: None Notes: The operator may also state the schedule does not meet the total hours since total hours count only when standing watch in the appropriate position.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 6 Evaluate Schedule 6 Critical Step: Operator determines Schedule 6 can be used to reactivate his license.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A2 Step 7 Critical Step: Operator does NOT select Schedules 1, 3, 4 or 5 as appropriate for reactivation of his license.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Operator 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 reactivate license.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_NRC10-A2 STUDENT HANDOUT Schedules Mar 28 Mar 29 Mar 30 Mar 31 Apr 1 Apr 2 Apr 3 Apr 4 1 Hours 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs Position Field BOP ATC Field ATC Supervisor Supervisor Turnovers On-coming Off-going Off-going 2 Hours 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs Position Field ATC BOP ATC BOP Supervisor Turnovers On-coming Off-going 3 Hours 12 hrs 12 hrs 12 hrs 12 hrs Position BOP BOP BOP ATC Turnovers Off-going Off-going Off-going 4 Hours 8 hrs 8 hrs 8 hrs 8 hrs 8 hrs Position ATC ATC BOP BOP ATC Turnovers On- On- Off-going Off-going coming coming 5 Hours 12 hrs 8 hrs 12 hrs 8 hrs 12 hrs 8 hrs Position BOP ATC ATC ATC Field ATC Supervisor Turnovers Off-going On-coming On-coming 6 Hours 12 hrs 12 hrs 8 hrs 8 hrs 8 hrs Position ATC ATC BOP BOP Field Supervisor Turnovers On- Off-going Off-going coming OT-3701-ADM_NRC10-A2 JPM CUE SHEET INITIAL CONDITIONS:

It is March 27, 2011 and you have an INACTIVE RO license.

Operations wants you to activate your RO license. The OPS Training Coordinator has developed 6 proposed schedules to re-activate your license.

INITIATING CUE: .

Using the proposed schedules determine if each of the schedules meets TMA-4206, Licensed Operator Requalification Programs required:

o Number of work hours o Position Title to work under the direction of o Completed turnovers

If a schedule does not meet one of these requirements, EXPLAIN why it does not.

STATE which, if any, of the proposed schedules you would work so that your license may be re-activated.

OT-3701-ADM_NRC10-A3 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO/SRO Safety Function: Equipment Control Setting: Simulator Validated: 25 minutes

References:

PRI-TSR, SVI-E32-T0374, completed up to/including 5.1.2 Tasks: 035-506-01-01 Determine Identified/Unidentified leakage rates Task Standard: Calculate Drywell Sump in-leakage rate per SVI-E31-T0374 and complete Tech Spec Rounds for Drywell Sump in-leakage K / A Data: 2.2.12 Knowledge of surveillance procedures. 3.7 / 4.1 Materials Needed:

Pictures of current DW FDS level of 11.78 with time (T=0130 hrs). And T=0130 pictures of DW EDS with a leak rate of 1.5 and DW Cnds Flow with 0 gpm.

Calculator.

SVI-E31-T0374 with US signature on the Test Cover Sheet and filled out up to but not including step 5.1.3

1. Setup Instructions: Set Overrides ZA1E31R0618-BLU to 6.0 for DW FDS Level, ZA1E31R0619-RED to 1.5 for DW EDS Rate and ZA1E31R0609 to 0.0 for Upper DW Cooler Drain Flow

2. Location / Method: Simulator / Perform

3. Initial Condition: The plant is at 100% power. It has been determined that DW Floor Drain Sump 1E31-R618 (red indicator) is inoperable. SVI-E31-T0374, Reactor Cooling System Unidentified Leakage Determination has been started. The DW Floor Drain Sump has NOT been recently pumped down (within the last hour). It is Tuesday, 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months and you are the BOP operator.

4. Initiating Cue

Complete SVI-E31-T0374, Reactor Cooling System Unidentified Leakage Determination using the Sump Level Recorder Method.

Perform the Operator Tech Spec Rounds for Drywell Leak Detect, Step 42.

Start Time: End Time:

Candidate:

OT-3701-ADM_NRC10-A3 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 Record DW Floor Drain Sump Level.

Standard: Operator records the 1E31-R618 blue sump level reading of 6.0 on Attachment 5.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 Wait for sump to fill up for second reading.

Standard: Operator waits for sump to fill.

Instructor Cue: After the operator logs the initial 6 sump reading, inform the operator that, using time compression, it is now 01:30 hrs and provide the operator with the 01:30 hour pictures of the sumps/flow.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A3 Step 3 Calculate floor sump level increase.

Critical Step: Operator determines sump level has increased by 5.78 Instructor Cue: None Notes: 5.7 to 5.8 is acceptable.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Calculate elapsed time.

Critical Step: Operator determines 30 minutes have elapsed.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A3 Step 5 Calculate Unidentified Leakage.

Critical Step: Operator determines 90.3414 gallons of unidentified leakage.

Instructor Cue: None Notes: An answer from 89.0 to 90.7 gallons is acceptable (based upon acceptable answers for step 3)

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 6 Calculate Unidentified Leakage Rate.

Critical Step: Operator determines an Unidentified Leakage Rate of 3.01138 Instructor Cue: None Notes: An answer of 2.9 to 3.1 is acceptable (based upon acceptable answers for step 5).

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A3 Step 7 Independently verify calculations Standard: Operator asks for independent verification.

Instructor Cue: When asked, inform the operator that the calculations have been verified.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 8 Record DW FDS rate in PRI-TSR.

Standard: Operator records 3.01 gpm leakage rate on TS Rounds sheet.

Instructor Cue: None Notes: An answer of 2.9 to 3.1 is acceptable (based upon acceptable answers for step 5).

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A3 Step 9 Determine Equipment Drain Sump Rate.

Standard: Operator records 1.5 gpm on TS Rounds Sheet.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 10 Determine total leakage rate.

Standard: Operator records a total leakage rate of 4.51 on TS Rounds Sheet.

Instructor Cue: None Notes: An answer of 4.4 to 4.6 is acceptable. (based upon acceptable answers for step 8).

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A3 Step 11 Determine 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months total leakage average rate Standard: Operator averages the last 3 readings and obtains an average of 3.20.

Instructor Cue: None Notes: An answer of 3.1 to 3.3 is acceptable. (based upon acceptable answers for step 10).

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 12 Record DW CNDS FLOW Standard: Records zero GPM.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_NRC10-A3 Step 13 Verify increase in Unidentified Leakage is < 2 gpm in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Critical Step: Operator notifies US that increase in unidentified leakage is > 2 gpm in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Operator notifies US that increase in Unidentified Leakage is > 2 gpm in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

Evaluation Results: SAT_____ UNSAT_____

End Time:

PRI-TSR Rev 21 Attachment 5 Sheet 17 of 31 Page 34 SHEET 17 MODES 1, 2 & 3 WEEK OF :___________________________

TSR-MODES 1,2&3-17 Rev. Error! Reference TECHNICAL SPECIFICATION ROUNDS source not found.

T R U MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY SATURDAY SUNDAY I E N PANEL OR PARAMETER/ M D A M D A M D A M D A M D A M D A M D A T Q I ORIGIN INSTRUMENT I A F I A F I A F I A F I A F I A F I A F L M T D Y T D Y T D Y T D Y T D Y T D Y T D Y T E T S RCIC AREA T CC 41 P632 °F 78 80 82 79 (1E31-N700A-A6-1) (143)

LEAK DETECTION RCIC RCIC AREA T CC 1H13-P642 °F 78 81 78 80 (1E31-N700B-A6-1) (143)

RHR AREA 1 T CC 1H13-P632 °F 80 82 78 78 (1E31-N700A-A6-4) (157)

RHR AREA 1 T CC

°F ISOLATION <B00139>

1H13-P642 (1E31-N700B-A6-4) (157) 82 82 80 81 RHR AREA 2 T CC 1H13-P632 °F 81 80 79 78 (1E31-N700A-A6-5) (157)

RHR AREA 2 T CC 1H13-P642 °F 83 81 81 79 (1E31-N700B-A6-5) (157)

Reading for 1E31-R618 (red) is only valid if DW Floor Drains Sump Level 1E31-R618 (blue) is < 12.5. If 1E31-R618 (red) is not operable, perform SVI-E31-T0374 to determine DW Floor Drains Rate.

42 Obtain TOTAL LEAKAGE RATE by summing DW FDS RATE and DW EDS RATE. Obtain 24 Hr TOTAL LEAKAGE AVERAGE by averaging the last 3 TOTAL LEAKAGE RATES. Verify 24 Hr TOTAL LEAKAGE AVERAGE 30 gpm.

<F01291> FDS SUMP LEV

<F01332> 1E31-R618 (blue)

< 12.5 INCH 8.00 7.20 6.30

DRYWELL LEAK DETECT DW FDS RATE

<L01448> 1E31-R618 (red) 5 GPM .7 .8 .7 DW EDS RATE 1E31-R619 (red)

GPM 1.8 1.9 1.7 TOTAL SEE 1H13-P642 LEAKAGE RATES NOTE GPM 2.5 2.7 2.4 24 Hr TOTAL SEE LEAKAGE AVG GPM 2.4 2.6 2.5 NOTE DW CNDS FLOW 1H13-P692 1E31-R609 GPM 0 0 0 Required in Mode 1. Verify that the increase in Unidentified Leakage within the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period is 2 gpm.

DW FDS RATE SEE 1H13-P642 INCREASE NOTE INIT AJ BN CC Candidate Handout 1 0130 hrs Upper Drywell Cooler Drain Flow Monitor Candidate Handout 2 0130 hrs DWS & EDS Level/Rate Monitors Candidate Handout 3 JPM CUE SHEET INITIAL CONDITIONS:

The plant is at 100% power.

It has been determined that DW Floor Drain Sump 1E31-R618 (red indicator) is inoperable.

SVI-E31-T0374, Reactor Cooling System Unidentified Leakage Determination has been started.

The DW Floor Drain Sump has NOT been recently pumped down (within the last hour).

It is Tuesday, 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months and you are the BOP operator.

INITIATING CUE: .

Complete SVI-E31-T0374, Reactor Cooling System Unidentified Leakage Determination using the Sump Level Recorder Method

Perform the Operator Tech Spec Rounds for Drywell Leak Detect, Step 42.

OT-3701-ADM NRC10-A4 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO/SRO Safety Function: Radiation Control Setting: Classroom Validated: 15 minutes

References:

OBP-OP-4009 rev 0 (p.12), GE C-RWT200901_PY, Attached: Survey Maps A57042, A57403B; RWPs 100002,100005.

Tasks: 299-502-03-01 Maintain Radiation Exposure as Low as Reasonably Achievable (ALARA) 299-848-01-01 Comply with the Administrative Requirements for the Perry Plant Radiation Dose Control Program Task Standard: Calculate maximum stay-time using conect RWP and Survey Map for RHR A walk-down.

K/ A Data: 2.3.7 Ability to comply with radiation work pem1it requirements during n01111al or abnonnal conditions. 3.5/3.6 Required Materials: Calculator

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1. Setup Instructions: N/A

2. Location / Method: Classroom / Perfonn

3. Initial Condition: The plant is at 100% power. HP reports water leakage in the "A" RHR pump room.

4. Initiating Cue: You are to walk-down and inspect the "A" RHR pump and piping. In preparation for this you are to:

Detennine which, of the two provided survey maps, is the conect survey map to use

Detennine which, of the two provided RWPs, is the conect RWP to use

Assuming you remain on the East Side of the pump casing, calculate the maximum stay time before the MG-DRD alanns on Dose Limit.

State your required actions if the MG-DRD alanns on Dose Limit.

Start Time: _ End Time:

(, Candidate:

OT-3701-ADM NRC10-A4 Rev 0 JPM BODY SHEET

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Standard: Perfo1111er obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc ...

before perfonning task.

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

Step 1 Determine the appropriate survey map.

Critical Step: Operator detem1ines that survey map #57403B is the COlTect map.

Instructor Cue: None Notes: None SAT UNSAT Comment(s): _

(

Step 2 Dete1111ine the appropriate RWP.

Critical Step: Operator detennines that RWP 100002 is the COlTeet RWP.

Instructor Cue: None Notes: RWP 100005 is not for High Rad areas. The survey map shows the RHR room is posted High Rad.

SAT UNSAT Comment(s): _

OT-3701-ADM NRC10-A4 Rev 0 Step 3

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Calculate the maximum stay time before the MG-DRD alarms on Dose Limit.

Critical Step: Operator divides 25 (the dose limit alarm) by 32 (the east side pump dose) and multiples by 60 (minutes/hour) to obtain 46.875 minutes.

Instructor Cue: None Notes: 46 to 47 minutes is acceptable.

SAT UNSAT Comment(s): _

Step 4 Required actions if the MG-DRD alanns on Dose Limit Critical Step: Operator determines that immediate exit and HP notification is required.

( Instructor Cue: None Notes: None SAT UNSAT Comment(s): _

Terminating Cue: Operator has selected an RWP, Survey Map, performed a dose calculation and stated actions on an alarm.

Evaluation Results: SAT UNSAT End Time:

. 1 RADIOLOGICAL SURVEY FORf {SURVEY Nl},.1l8ER-----r, ,.AI-' # - 1 RV,/P' UMBI.i~- --;

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OT-3701-ADM_311_SRO (A5)

JOB PERFORMANCE MEASURE SETUP SHEET System: Admin Time Critical: Yes Alternate Path: No Applicability: SRO only K/A: 295017 - AK3.03 295038 - EK3.01 Safety Function: Emergency Procedures/Plan Validated Time: 20 Minutes

References:

EPI-A1 rev 21, EPI-A2 rev 14, EPI-B1 rev 20, EPI-B8 rev, NORM-LP-5001 rev 1 Task: 344-502-05-03 Determine Protective Action Recommendations (PARs) and Ensure that the State and Counties are Notified 344-532-05-02 Prepare Emergency Plan Initial Notification Form Task Standard: Declare the emergency action level (AG1), complete initial notifications within 15 minutes and ensure communicator has notification form within the following 15 minutes.

Required Material EPI-A1 - Emergency Action Levels EPI-A2 - Emergency Actions Based On Event Classification EPI-B1 - Emergency Notification System EPI-B8 - Protective Actions And Guides NORM-LP-5001 - FENOC Position on Release in Progress for Emergency Response Organization

1. Setup Instructions: Provide EPI-A1 Attachment 1 chart from simulator for candidate use.

2. Location / Method: Admin / Performance

3. Initial Condition: The plant had been operating at 100% power for the last 218 days.

Outside Temperature is 70 °F, with 6 mph winds from the northwest (310°).

A reactor scram has occurred due to a Main Turbine trip caused by a loss of Main Condenser Vacuum. All rods are indicating 00, full-in. Plant is operating in accordance with EOP-01 RPV Control. RPV level is -1 inches and lowering slowly All available injection and injection subsystems are and have been injecting. The MSIVs and Main Steam Stop Valves are open and all attempts to isolate the Main Steam Lines have failed.

Drywell radiation is indicating 140 Rem/hr. The TB/HB Vent Gas Radiation Monitor:

Gas (1D17-K856), Iodine (1D17-K857), and Particulate (1D17-K858), are all in alarm.

4. Initiating Cue: You are the Shift Manager and I am the Control Room Communicator.

You are to: declare the emergency action level, complete initial notifications, provide any required Protective Action Recommendations and fill out associated paperwork.

Task is Time Critical Start Time: End Time: Candidate:

OT-3701-ADM_311_SRO (A5)

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 Event Classification: 15 Minutes to classify (Time Critical)

Classify Event as AG1.

Critical Step: Classifies AG1, 15 minutes to classify.

Instructor Cue: Notify that time critical action starts after first read of initial conditions and he is given initiating cue.

Notes: Containment Barrier Loss, MSIVs do not close as required. Path to the environment loss of condenser vacuum.

RCS Barrier Loss, Drywell Rad > 135 Rem/hr RPV Level < 0 inches Fuel Barrier Challenge, RPV Level < 0 inches.

Start Time ________ Classification Time __________

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_311_SRO (A5)

Step 2 Event Classification Checklist:

Checklist completed through line A.6.

Standard: Uses Event Classification Checklist to assist with required actions.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 Initial Notification:

Initial Notification completed within 15 minutes after classification. (Time Critical)

Critical Step: Initial Notification Completed within 15 minutes of classification.

Block 3.a is checked for General Emergency AG1.

Instructor Cue: None Notes: Time Given to Communicator ______________

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_311_SRO (A5)

Step 4 Protective Action Recommendation:

PAR Decision Flowchart.

Critical Step: Protective action recommendation, evacuate 1, 2, 3, and Lake. Block 5.c and 6.c are checked.

Instructor Cue: No impediment to evacuation, No controlled release. CADAP in progress but not complete.

Notes: Wind Direction 310 degrees = 282° to 11° EVACUATE 1, 2, 3 & Lake*

Table A is used for default PAR.

Block 5.c is checked because TB/HB monitored release info is given.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 Pager Message:

Complete Pager Message for Emergency Facility staffing.

Standard: Pager Message completed, scenario ID No. 4 Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: AG1 Classified within 15 minutes and Initial Notification given to Communicator within 15 minutes.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_311_SRO (A5)

JPM CUE SHEET INITIAL CONDITIONS:

The plant had been operating at 100% power for the last 218 days.

Outside Temperature is 70 °F, with 6 mph winds from the northwest (310°).

A reactor scram has occurred due to a Main Turbine trip caused by a loss of Main Condenser Vacuum.

All rods are indicating 00, full-in.

Plant is operating in accordance with EOP-1 RPV Control.

RPV level is -1 inches and lowering slowly

All available injection and injection subsystems are and have been injecting.

The MSIVs and Main Steam Stop Valves are open and all attempts to isolate the Main Steam Lines have failed.

Drywell radiation is indicating 140 Rem/hr.

The TB/HB Vent Gas Radiation Monitor: Gas (1D17-K856),

Iodine (1D17-K857), and Particulate (1D17-K858), are all in alarm.

INITIATING CUE: You are the Shift Manager and I am the Control Room Communicator. You are to:

Declare the emergency action level

Complete initial notifications

Provide any required Protective Action Recommendations

Fill out associated paperwork.

Task is Time Critical OT-3701-NRC10-S1 JOB PERFORMANCE MEASURE SETUP SHEET System: Reactor Protection System Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 1 - Reactivity Control Setting: Control Room / Plant Validated: 20 minutes

References:

EOP-SPI-1.2 rev 2 Tasks: 212-539-05 Install RPS Jumpers (Scram Cannot be Reset)

Task Standard: Install jumpers and lift leads per EOP-SPI 2.1, Scram and ARI, to reset scram and de-energize ARI solenoids K / A Data: 295015 AK2.04 Knowledge of the interrelations between INCOMPLETE SCRAM and the following: RPS 4.0 / 4.1

1. Setup Instructions: N/A

2. Location / Method: Control Room / Simulate

3. Initial Condition: An ATWS is in progress. The scram fuses are installed. (EOP-SPI 1.1, Pulling Scram Fuses has NOT been performed) EOP-SPI-1.2 SCRAM AND ARI has been completed up to and including step 12. Both Scram and ARI signals remain, and are NOT reset.

4. Initiating Cue: The Unit Supervisor directs you to perform EOP-SPI-1.2 SCRAM AND ARI, steps 13 through 14, to reset the Scram and de-energize ARI solenoid valves.

Start Time: End Time:

Candidate:

OT-3701-NRC10-S1 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-1.2, SCRAM AND ARI 13.0 IF scram signal is NOT reset, THEN RESET the scram as follows:

13.1 IF Pulling Scram Fuses, EOP-SPI 1.1 has been performed, THEN REFER TO Pulling Scram Fuses, EOP-SPI 1.1 and VERIFY that the Scram Fuses are installed.

Standard: Operator moves to step 13.2.

Instructor Cue: None Notes: Initial conditions state fuses are installed.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-NRC10-S1 Step 2 13.2 INSTALL the following RPS jumpers:

Panel From To H13-P694 Bay B Bay B fuse 1C71A-F14D (F21) relay 1C71K19H wire C71A096X1 terminal T1 wire C71A0933W H13-P691 Bay A Bay B fuse 1C71A-F14A (F23) relay 1C71K19E wire C71A09X1 terminal T1 wire C71A0903W H13-P692 Bay A Bay B fuse 1C71A-F14B (F14) relay 1C71K15B wire C71A092X1 terminal M1 wire C71A0913W H13-P693 Bay B Bay B fuse 1C71A-F14C (F14) relay 1C71K15C wire C71A094X1 terminal M1 wire C71A0923W Critical Step: Operator identifies correct terminals, and describes jumper installation.

Instructor Cue: For each jumper, Jumper installed Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-NRC10-S1 Step 3 13.3 DEPRESS the following pushbuttons to reset the scram:

SCRAM RESET CH A C71A-S5A

SCRAM RESET CH C C71A-S5C

SCRAM RESET CH B C71A-S5B

SCRAM RESET CH D C71A-S5D Critical Step: Operator simulates pushing the 4 scram reset pushbuttons.

Instructor Cue: GP1A through GP4A and GP1B through GP4B SCRAM SOL VALVE lights are on.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-NRC10-S1 Step 4 14.0 IF the ARI is NOT reset, THEN AT H13-P703, REMOVE the following wires to de-energize ARI solenoid valves:

Bay Terminal Strip Terminal Wire A TM017 5 C22A032N1 A TM019 5 C22A032N1 A TM020 5 C22A032N1 A TM018 5 C22A032N1 B TM021 5 C22A048N1 B TM022 5 C22A048N1 B TM023 5 C22A048N1 B TM024 5 C22A048N1 Critical Step: Operator identifies correct Bay, Terminals, Strip and Wire.

Instructor Cue: For each identified wire state that the wire is now removed.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: The scram fuses have been pulled and the ARI wires lifted.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-NRC10-S1 JPM CUE SHEET INITIAL CONDITIONS:

An ATWS is in progress.

The scram fuses are installed. (EOP-SPI 1.1, Pulling Scram Fuses has NOT been performed)

EOP-SPI-1.2 SCRAM AND ARI has been completed up to and including step 12.

Both Scram and ARI signals remain and are NOT reset.

INITIATING CUE: .

The Unit Supervisor directs you to perform EOP-SPI-1.2 SCRAM AND ARI, steps 13 through 14, to reset the Scram and de-energize ARI solenoid valves.

OT-3701-E22A_07 (S2)

JOB PERFORMANCE MEASURE SETUP SHEET System: High Pressure Core Spray Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 2 - Reactor Water Inventory Control Setting: Control Room / Plant Validated: 15 minutes

References:

EOP-SPI-2.4 rev 0, EOP-SPI-2.7 rev 0 Tasks: 206-543-05-01 Bypass HPCS L8 259-541-05-01 Bypass MFP L8 Trip Task Standard: Perform bypass of HPCS and Motor Feed Pump level 8 trips per EOP-SPI 2.4 and EOP-SPI 2.7 K / A Data: 295009 AA1.02 Ability to operate and/or monitor the following as they apply to LOW REACTOR WATER LEVEL: Reactor water level control. 4.0 / 4.0

1. Setup Instructions: None

2. Location / Method: Control Room / Simulation

3. Initial Condition: Operating in accordance with EOP 4.4 RPV Flooding. All rods are in.

Core damage is not occurring.

4. Initiating Cue: Unit Supervisor directs you the Reactor Operator to perform EOP-SPI 2.4 Bypass of HPCS L8 Trip and EOP-SPI 2.7 Bypass of MFP L8 Trip.

Start Time: End Time:

Candidate:

OT-3701-E22A_07 (S2)

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 2.4, Bypass of HPCS L8 Trip 1.0 IF HPCS INJECTION VALVE E22-F004 is closed, THEN TAKE HPCS INJECTION VALVE E22-F004 to CLOSE.

Standard: Operator takes HPCS Injection Valve E22-F004 to CLOSE Instructor Cue: Injection valve is closed green light on initially and after.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E22A_07 (S2)

Step 2 2.0 AT H13-P625, DEFEAT HPCS INJECTION VALVE L8 closure as follows:

2.1 UNLOCK the card file. E22A-Z1-1 2.2 REMOVE the following trip units:

RX LEVEL HPCS INJ VALVE CLOSED RX HI-L8 B21-N674L

RX LEVEL HPCS INJ VALVE CLOSED RX HI-L8 B21-N674R Critical Step: Operator simulates unlocking card file and removing the two trip units Instructor Cue: Card File unlocked, Trip units removed Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 3.0 DEPRESS RX WATER LEVEL HIGH SEAL IN RESET. 1E22A-S6 Critical Step: Operator simulates depressing seal in reset (at H13-P601)

Instructor Cue: White light is on initially, light is off after reset Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E22A_07 (S2)

Step 4 EOP-SPI 2.7, Bypass of MFP L8 Trip 1.0 IF the MFP is NOT running, THEN PLACE the MFP control switch in OFF. N27-C004 Standard: Operator simulates placing motor Feed Pump in OFF (at H13-P680)

Instructor Cue: Motor Feed Pump is not Running Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 2.0 AT H13-P866 Bay C relay N27-K42 terminal A, REMOVE AND INSULATE wire.

Wire N272457A Critical Step: Operator simulates removing wire N272457A from terminal A of relay N27-K42.

Instructor Cue: If operator indicates difficulty in reading the relay number, inform the operator that it is the relay and is labeled N27-K42.

Notes: One of the number 2s on the relay is hard to read.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: EOP-SPI 2.4 and EOP-SPI 2.7 complete for Bypass of L8 Trips Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-E22A_07 (S2)

JPM CUE SHEET INITIAL CONDITIONS: Operating in accordance with EOP-4-4 RPV Flooding.

All rods are in.

Core damage is not occurring.

INITIATING CUE: Unit Supervisor directs you the Reactor Operator to perform EOP-SPI 2.4 Bypass of HPCS L8 Trip and EOP-SPI 2.7 Bypass of MFP L8 Trip.

OT-3701-N62_01 (S3)

JOB PERFORMANCE MEASURE SETUP SHEET System: OFF-GAS/CONDENSER AIR REMOVAL SYSTEM Time Critical: No Alternate Path: Yes Applicability: RO/SRO Safety Function: 3 Reactor Pressure Control Setting: Simulator, Bank Validated: 20 minutes

References:

IOI-6, SOI-N64/62 Tasks: 255-501-01-01 Monitor the Condenser Air Removal System 255-506-01-04 Start a Mechanical Vacuum Pump 255-515-01-01 Establish Main Condenser Vacuum Task Standard: Recover main and aux condenser vacuum per IOI-6 and SOI-N64/62 K / A Data: 295002 AK2.04 Knowledge of the interrelations between LOSS OF MAIN CONDENSER VACUUM and the following: Reactor/turbine pressure regulating system 3.2 / 3.3

1. Setup Instructions:

Use IC 166 with Schedule File JPM_4 for a loss of condenser pressure with MSIVs closed

Verify open Vacuum Breakers

Verify Mech Vac Pump A failure to auto trip malfunction is in

Verify the Inop/Failure of A MSL Rad monitor on Trigger 1

2. Location / Method: Simulator / performance

3. Initial Condition: MSIV isolation has occurred. Recovery of the Main Condenser, as a reactor heat sink, is underway in accordance with Attachment 1 of IOI-6, Cooldown Main Condenser Not Available. The following systems are in service to support Mechanical Vacuum Pump startup: TBCCW, Condensate, Condensate Seal and Sealing Steam.

4. Initiating Cue: The Unit Supervisor directs you as the Reactor Operator to reestablish a vacuum in the Main Condenser and Aux Condensers using the Mechanical Vacuum Pumps per SOI-N64/62, section 4.2 Establishing a Vacuum.

Start Time: End Time:

Candidate:

OT-3701-N62_01 (S3)

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-6, Cooldown - Main Condenser Not Available, Attachment 1, Recovery Of Main Condenser For Use As Reactor Heat Sink 15.0 DRAW a vacuum on the main condenser with the Mechanical Vacuum Pumps.

SOIN64/62 SOI-N64/62, Offgas 4.2 Establishing a Vacuum NOTE This Section should be entered from IOI-1, IOI-2, or IOI-6.

4.2.1 VERIFY the Turbine Building Closed Cooling System (P44) is in service supplying cooling water to Mechanical Vacuum Pumps.

4.2.2 VERIFY the Condensate System (N21) is in service supplying makeup water to the mechanical vacuum pumps separator.

4.2.3 VERIFY the Condensate Seal System (P12) is in service.

4.2.4 VERIFY sealing steam is applied in accordance with SOI-N33 for each turbine that will have a vacuum established in its condenser.

Standard: Verifies from initial conditions that conditions are met.

Instructor Cue: If asked, confirm these conditions are met.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-N62_01 (S3)

Step 2 4.2.5 IF vacuum is to be drawn on Auxiliary Condenser A, THEN PERFORM the following:

4.2.5.a VERIFY the AUX CNDR LEVEL CONT A is in AUTO. 1N21-R042 4.2.5.b VERIFY the AUX CNDR LEVEL CONT A is set at 10.75. 1N21-R042 4.2.6 IF vacuum is to be drawn on Auxiliary Condenser B, THEN PERFORM the following:

4.2.6.a VERIFY the AUX CNDR LEVEL CONT B is in AUTO. 1N21-R102 4.2.6.b VERIFY the AUX CNDR LEVEL CONT B is set at 10.75. 1N21-R102 Standard: Verifies controllers in AUTO and set at 10.75 Instructor Cue: None Notes: The next two SOI steps, 4.2.7 and 4.2.8, are N/A SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 4.2.9 IF drawing a vacuum on the Main Condenser, THEN VERIFY the MAIN CONDENSER VENT VALVES control switch is in CLOSE. 1N62-F010A, 1N62-F010B, 1N62-F010C Critical Step: Verifies vent valve switch in close by placing the valve control switches to the CLOSE position.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-N62_01 (S3)

Step 4 4.2.10 REFER TO SOI-P12 and FILL the respective condenser seal troughs to reseal the vent valves.

NOTE Both mechanical vacuum pumps should normally be used to initially draw a vacuum and may be started in parallel.

4.2.11 NOTIFY Chemistry of Mechanical Vacuum Pump startup.

Standard: Contacts NLO to fill seal troughs and contacts chemistry Instructor Cue:

Seal Troughs (HP, IP, LP & Aux Condensers) are filled.

Chemistry is standing by on-station.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 4.2.12 TAKE the MECH VACUUM PUMP to START. 1N62-C001A, 1N62-C001B Critical Step: Starts both Mechanical Vacuum Pumps by taking their control switches to START.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-N62_01 (S3)

Step 6 4.2.13 CONFIRM the following:

Mechanical Vacuum Pump Seal Wtr Pump has started. 1N62-C003A, 1N62-C003B

Mechanical Vac Pmp Clr Auto Isol. has opened. 1P44-F260A, 1P44-F260B

MECH VACUUM PMP SUCT VLV has opened. 1N62-F130A, 1N62-F130B Standard: Contacts NLO to Confirm Instructor Cue: NLO confirms above actions Notes: Simulator Operator wait 60 seconds after Vac pump start then Activate Trigger 1 SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 7 Standard: Acknowledges annunciators:

Mechanical Vacuum Pump A Trip

Mechanical Vacuum Pump B Trip Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-N62_01 (S3)

Step 8 Backup failed automatic action.

Critical Step: Operator trips the A MVP by placing its control switch to STOP.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Mechanical Vacuum Pumps A and B are secured.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-N62_01 (S3)

JPM CUE SHEET INITIAL CONDITIONS: MSIV isolation has occurred. Recovery of the Main Condenser, as a reactor heat sink, is underway in accordance with Attachment 1 of IOI-6, Cooldown Main Condenser Not Available. The following systems are in service to support Mechanical Vacuum Pump startup:

TBCCW

Condensate

Condensate Seal

Sealing Steam.

INITIATING CUE: The Unit Supervisor directs you as the Reactor Operator to reestablish a vacuum in the Main Condenser and Aux Condensers using the Mechanical Vacuum Pumps per SOI-N64/62, Section 4.2 Establishing a Vacuum.

OT-3701-E12_004_RO (S4)

JOB PERFORMANCE MEASURE SETUP SHEET System: E12 - RHR Time Critical: No Alternate Path: No Applicability: RO/SRO K/A: 205000 - A2.10, A4.01, A4.03 & A4.09 Safety Function: 4 - Heat Removal From the Core Validated Time: 25 Minutes

References:

SOI-E12 rev 46 Required Material SOI-E12 - RESIDUAL HEAT REMOVAL SYSTEM Task: 205-535-01-01 Warmup and Initiate Shutdown Cooling from Standby Readiness Task Standard: Establish Shutdown Cooling using RHR A through the normal return path and use RHR A Head Spray per SOI-E12.

1. Setup Instructions:

Reset simulator to IC 166 with schedule file NRC_JPM_3.

Verify reactor pressure is ~ 70 psig and maintained less than the 135 psig SDC isolation.

Verify RHR F006A inadvertent closure malfunction on Trigger 2.

2. Location / Method: Simulator / performance

3. Initial Condition: The Plant is in Mode 3. Plant shutdown for beginning of RFO in progress. Feedwater is in operation on the Low Flow Controller, Unit Supervisor is operating in IOI-4 Shutdown RHR A is ready to be placed in Shutdown Cooling.

SOI-E12 Sections 4.5.1 through 4.5.4 are complete.

4. Initiating Cue: The Unit Supervisor directs you to use SOI-E12, section 4.5.5, Establishing the Shutdown Cooling Return Path

Establish Shutdown Cooling using RHR A through the normal return path

Spray the Vessel Head with RHR A.

Start Time End Time Operator OT-3701-E12_004_RO (S4)

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-E12 - RESIDUAL HEAT REMOVAL SYSTEM 4.5.5 Establishing the Shutdown Cooling Return Path

1. Verify the Subsection 4.5.3, Establishing the Shutdown Cooling Suction Path has been completed.

Standard: Operator verifies section 4.5.3 complete Instructor Cue: None Notes: Section 4.5.3 was completed.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2

2. Hold RHR A HXS OUTLET VALVE, 1E12-F003A, control switch in CLOSE until the valve is closed.

Critical Step: Operator closes 1E12F003A.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_004_RO (S4)

Step 3

3. If it is desired to establish Shutdown Cooling using the normal return path, perform the following:

a. If the Feedwater System is shutdown, confirm closed the FDW HDR A(B)

SHUTOFF, 1B21-FO65A(B) to prevent flow to the feedwater system.

Standard: Feedwater operating, 1B21F065s are open, opearator NAs step.

Instructor Cue: If asked about the status of Feedwater, inform the candidate that another operator will shut down feedwater after Shutdown Cooling is in service and he is to continue.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4

b. Perform the following concurrently:

Hold SHUTDOWN COOLING A TO FDW SHUTOFF, 1E12-F053A, control switch in OPEN until the valve is open.

Take RHR PUMP A, 1E12-C002A(B), control switch to START.

c. Go to Subsection 4.5.6, Initiation of Shutdown Cooling Flow.

Critical Step: Operator opens 1E12F053A and starts RHR A pump. Then refers to Section 4.5.6.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_004_RO (S4)

Step 5 4.5.6 Initiation of Shutdown Cooling Flow CAUTION Shutdown Cooling Flow of 7000-7100 gpm flow is necessary to ensure that valid temperature and flow indications are maintained to preclude vessel repressurization. Flows of > 2575 gpm ensure adequate minimum flow.

NOTE:

Initiation of shutdown cooling flow should be accomplished in 1000-2000 gpm increments.

1. Throttle open RHR A HXS BYPASS VALVE, 1E12-F048A, until Loop A flow is 7000-7100 gpm on RHR A PUMP FLOW, 1E12-R603A.

Critical Step: Operator establishes flow.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-E12_004_RO (S4)

Step 6

2. Throttle open RHR A HXS OUTLET VALVE, 1E12-F003A, while throttling closed on RHR A HXS BYPASS VALVE, 1E12-F048A, to establish a cooldown rate less than 100°F/hr with a loop flow rate of 7000-7100 gpm on RHR A PUMP FLOW, 1E12-R603A.

Critical Step: Establish Cooldown rate Instructor Cue: None Notes: This critical step is accomplished when the candidate first throttles F003A AND F048A and has loop flow within a band of 6,900 - 7,200 gpm.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 7

3. Maintain a cooldown rate of less than 100°F/hr by adjusting the positions of the RHR A HXS OUTLET VALVE, 1E12-F003A, and RHR A HXS BYPASS VALVE, 1E12-F048A.

Critical Step: Maintain a cooldown rate of less than 100°F/hr.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_004_RO (S4)

Step 8

4. If operating RHR A and if it is desired to establish reactor head spray, perform the following:

a. Confirm that RCIC INJECTION VLV, 1E51-F013, is closed.

b. Perform the following simultaneously:

1) Jog open RHR A HEAD SPRAY ISOL, 1E12-F023, as necessary to establish 500 gpm on HD SPRAY FLOW,1E12-R607.

2) Adjust RHR A HXS BYPASS VALVE, 1E12-F048A, and RHR HXS OUTLET VALVE, 1E12-F003A, as required to maintain a RHR A PUMP FLOW, 1E12-R603A, of 7000-7100 gpm.

Critical Step: Vessel head is being sprayed thru 1E12F023.

Instructor Cue: If asked, inform operator that 1E51-F013 was verified closed when RCIC was placed in secured status.

Notes: Simulator Operator: Activate Trigger 2 SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 9 Acknowledge annunciator.

Standard:: Operator acknowledges annunciator RHR A Suction Press Low and refers to the ARI.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_004_RO (S4)

Step 10 Trip running RHR Pump Critical Step: Operator places RHR A Pump control switch to STOP.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: RHR Pump A has been tripped.

Evaluation Results: SAT_____ UNSAT_____

End Time OT-3701-E12_004_RO (S4)

JPM CUE SHEET INITIAL CONDITIONS: The Plant is in Mode 3. Plant shutdown for beginning of RFO in progress. Feedwater is in operation on the Low Flow Controller, Unit Supervisor is operating in IOI-4 Shutdown RHR A is ready to be placed in Shutdown Cooling. SOI-E12 Sections 4.5.1 through 4.5.4 are complete.

INITIATING CUE: The Unit Supervisor directs you to use SOI-E12, section 4.5.5, Establishing the Shutdown Cooling Return Path

Establish Shutdown Cooling using RHR A through the normal return path

Spray the Vessel Head with RHR A.

OT-3701-NRC10-S5 JOB PERFORMANCE MEASURE SETUP SHEET System: Residual Heat Removal Time Critical: No Alternate Path Yes Applicability: RO/SRO Safety Function: 5 - Containment Integrity Setting: Simulator Validated: 10 minutes

References:

EOP-SPI 3.1, Rev 1 Tasks: 205-509-05-01 Manually Initiate Containment Spray 205-540-05-01 Monitor Containment Spray Operation Task Standard: Manually initiate Containment Spray per EOP-SPI-3.1.

K / A Data: 226001 A1.05 Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE controls including: System lineup 3.1 / 3.4

1. Setup Instructions: Reset simulator to IC 162. Insert malfunction mv05-1e12f0024a to prevent E12-F024A from auto closing on Containment Spray initiation. Place both loops of RHR in Suppression Pool Cooling and insure the E12-F048A valve is closed.

2. Location / Method: Simulator / Perform

3. Initial Condition: A small break LOCA has occurred in the drywell. RHR A and B loops are running in suppression pool cooling. EOP 1 and EOP 2 have been entered.

4. Initiating Cue: The Unit Supervisor directs you to Spray Containment IAW EOP-SPI 3.1 Containment Spray and terminate Spray at 0.5 psig in containment.

Start Time: End Time:

Candidate:

OT-3701-NRC10-S5 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 1.0 IF while executing the following steps:

Containment pressure cannot be maintained greater than 0 psig

Directed to terminate Containment Spray operations THEN TERMINATE RHR Containment Spray as follows:

Standard: Operator observes Containment pressure greater than 0 psig.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 2.0 RHR Containment Spray Loop A is NOT lined up to vent Containment and Containment Spray A loop is available THEN INITIATE Containment Spray A Loop as follows:

Standard: Operator recognizes that RHR is NOT lined up to vent.

Instructor Cue: None Notes: Initial conditions stated that RHR A and B are lined up in Suppression Pool Cooling.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-NRC10-S5 Step 3 2.1 IF Drywell Pressure is less than 1.68 psig, THEN AT H13-P629, PLACE CNTMT SPRAY A HI DW PRESS BYP keylock switch in BYPASS.E12A-S75 Standard: Operator observes DW pressure > 1.68 psig & moves to the next step.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 2.2 CONFIRM Containment Pressure is above the Containment Spray Initiation Limit (CSIL) Figure 10.

Standard: Operator confirms pressure is greater than CSIL using Figure 10.

Instructor Cue: None Notes: Figure 10 is the last page of EOP-SPI 3.1 SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-NRC10-S5 Step 5 2.3 ARM AND DEPRESS CNTMT SPRAY A MANUAL INITIATION pushbutton. E12A-S63A Critical Step: Operator Arms and Depresses Cntmt Spray A Manual Initiation pushbutton Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 6 2.4 VERIFY RHR PUMP A is running. 12-C002A Standard: Operator verifies RHR Pump A is running.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-NRC10-S5 Step 7 2.5 IF ESW PUMP A is available, THEN VERIFY ESW PUMP A is running. P45-C001A Standard: Operator verifies ESW Pump A is running.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 8 2.6 IF ECC PUMP A is available, THEN VERIFY ECC PUMP A is running. P42-C001A Standard: Operator verifies ECC Pump A is running.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-NRC10-S5 Step 9 2.7 VERIFY the following valves are OPEN:

CNTMT SPRAY A FIRST SHUTOFF E12-F028A

CNTMT SPRAY A SECOND SHUTOFF E12-F537A Standard: Operator verifies OPEN:

CNTMT SPRAY A FIRST SHUTOFF E12-F028A

CNTMT SPRAY A SECOND SHUTOFF E12-F537A Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 10 2.8 VERIFY the following valves are CLOSED:

LPCI A INJECTION VALVE E12-F042A

SHUTDOWN COOLING A TO FDW SHUTOFF E12-F053A

RHR A HXS BYPASS VALVE (10 minutes) E12-F048A Standard: Operator verifies the following valves are CLOSED:

LPCI A INJECTION VALVE E12-F042A

SHUTDOWN COOLING A TO FDW SHUTOFF E12-F053A

RHR A HXS BYPASS VALVE (10 minutes) E12-F048A Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-NRC10-S5 Step 11 2.8 VERIFY the following valves are CLOSED:

RHR A TEST VALVE TO SUPR POOL E12-F024A Critical Step: Operator manually closes E12-F024A Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 12 3.0 RHR Containment Spray Loop B is NOT lined up to vent Containment AND Additional Containment Spray is Required THEN INITIATE Containment Spray B Loop as follows:

Standard: Operator observes Containment pressure lowering and determines additional Containment Spray is NOT required.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Containment Spray loop A is initiated, E12-F024A is shut, and Containment pressure is lowering.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-NRC10-S5 JPM CUE SHEET INITIAL CONDITIONS:

A small break LOCA has occurred in the drywell.

RHR A and B loops are running in Suppression Pool Cooling.

EOP 1 and EOP 2 have been entered.

INITIATING CUE:

The Unit Supervisor directs you to Spray Containment IAW EOP-SPI 3.1 Containment Spray and terminate Spray at 0.5 psig in containment.

OT-3701-R10_02 (S6)

JOB PERFORMANCE MEASURE SETUP SHEET System: AC Power Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 6 - Electrical Setting: Control Room / Plant Validated: 30 minutes

References:

ONI-SPI F-1 rev 1 Tasks: 066-508-04-01 Respond to a Loss of Off Site Power 066-509-01-01 Place Unit 1 (or Unit 2) SU XFMR in Service 262-539-04-04 Assist in Off Site Power Restoration Task Standard: Energize buses L20 and TH21 per ONI-SPI F-1.

K / A Data: 295003 AA1.01 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: A.C. electrical distribution system 3.7 / 3.8

1. Setup Instructions: None. Operator provided with a copy of ONI-SPI F1 Section 2.0 with Step 2.4 marked up.

2. Location / Method: Control Room / simulation

3. Initial Condition:

Plant is operating in accordance with ONI R10. Loss of AC Power.

ONI-SPI F1 Off-Site Power Restoration Section 2.0 is in progress, Steps 2.1, through 2.4 are complete

Main Bus 2 - West Bus is energized

Main Bus 1 - East Bus is energized.

Disconnect S290 is closed.

Disconnect S180 is open.

Bus L10 is NOT available for energization.

Bus L20 is available for energization

4. Initiating Cue: Unit Supervisor directs you the Reactor Operator to energize Bus L20 and Bus TH21 per ONI-SPI F1 Off-Site Power Restoration.

Start Time: End Time:

Candidate:

OT-3701-R10_02 (S6)

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 F-1, Off-Site Power Restoration Step 2 2.5 Bus L10 is available to be re-energized Main Bus 2 - West Bus is Main Bus 1- East Bus is energized energized Unit One Startup Main Xfmr Unit Two Startup Transformer Disconnect S112 is Transformer Manual Disconnect closed Manual Disconnect S180 is closed Unit One Startup S290 is closed Transformer 100-PY-B is unavailable Unit Two Startup Transformer 200-PY-B is unavailable THEN PERFOM THEN PERFOM THEN PERFOM Step 2.6 to Step 2.8 to Step 2.7 to energize Bus L10 energize Bus L10 energize Bus L10 Standard: N/As Steps 2.5, 2.6, 2.7 and 2.8 Instructor Cue: None Notes: These steps are N/A, initiating cue L10 is Unavailable SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R10_02 (S6)

Step 2 2.9 Bus L10 is energized Bus L10 cannot be energized THEN PERFORM Step 2.10 THEN PROCEED to Step 2.11 Standard: N/As steps 2.10 and proceeds to step 2.11.

Instructor Cue: None Notes: Step 2.10 is N/A, Initiating Cue L10 is Unavailable SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 2.11 Bus L20 is available to be re-energized Main Bus 2 - West Bus is Main Bus 1- East Bus is energized energized Unit Two Startup Transformer Unit One Startup Transformer Manual Disconnect S290 is Manual Disconnect S180 is closed closed THEN PERFORM Step THEN PERFORM Step 2.11.1 to energize Bus L20 2.11.2 to energize Bus L20 Standard: Steps thru matrix and determines that step 2.11.1 is to be performed.

Instructor Cue: None (all information previously provided)

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R10_02 (S6)

Step 4 2.11.1 Energize bus L20 form the Unit 2 Startup transformer as follows:

2.11.1.a VERIFY the START-UP TRANSFORMER 200-PY-B white potential light (secondary windings) is energized.

2.11.1.b CLOSE the MAIN START-UP SUPPLY L2003 BRKR.

2.11.1.c OBSERVE voltage on BUS L20 VOLTS 2R22-R012 indicates 12.5-14.3KV.

Critical Step: Verifies white light on, simulates closing L2003 and verifies voltage on 2R22R12.

Instructor Cue: White light on, Red light on and green light off when closing L2003, voltage indicate as read 13.5 KV Notes: Only the closing of the breaker is critical.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R10_02 (S6)

Step 5 2.11.2 Energize bus L20 form the Unit 1 Startup transformer as follows:

2.11.2.a VERIFY the START-UP TRANSFORMER 100-PY-B white potential light (secondary windings) is energized.

2.11.2.b CLOSE the BUS TIE BRKR. L1001 2.11.2.c CLOSE the BUS TIE BRKR. L2004 2.11.2.d OBSERVE voltage on BUS L20 VOLTS 2R22-R012 indicates 12.5-14.3KV.

Standard: Step is N/A Instructor Cue: None Notes: Step 2.11.2 is NA SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R10_02 (S6)

Step 6 2.11.3 WHEN Bus L20 is energized, THEN PERFORM the following to restore Bus TH21:

2.11.3.a CLOSE the INTERBUS TRANSFORMER L2006 BRKR to energize LH-2-A.

2.11.3.b CLOSE the BUS TIE BRKR. EH2101 2.11.3.c VERIFY BUS TH21 white potential light on 1H13-P877 is energized.

2.11.3.d WHEN time permits, LH-2-A THEN REFER to SOI-2 R10 (4KV) to perform a check of Interbus Transformer.

Critical Step: Operator simulates closing L2006, and EH2101 verifies TH21 light on, directs check of LH2A Instructor Cue: L2006 red light on and green light off, EH2101 red light on and green light off, TH21 light on. Time does not permit for step d.

Notes: Bus TH21 volts R22R020A 4300 volts if read.

Only the closing of the breakers (L2006 and EH2101) is critical.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Bus L20 is energized and TH21 is energized.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-R10_02 (S6)

JPM CUE SHEET INITIAL CONDITIONS: Plant is operating in accordance with ONI R10. Loss of AC Power.

ONI-SPI F1 Off-Site Power Restoration Section 2.0 is in progress, Steps 2.1, through 2.4 are complete Main Bus 2 - West Bus is energized Main Bus 1 - East Bus is energized.

Disconnect S290 is closed.

Disconnect S180 is open.

Bus L10 is NOT available for energization.

Bus L20 is available for energization INITIATING CUE: Unit Supervisor directs you the Reactor operator to energize Bus L20 and Bus TH21 per ONI-SPI F1 Off-Site Power Restoration.

OT-3701-C11_05 (S7)

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 Validated: 25 minutes

References:

SOI-C11 rev 26 Tasks: 214-501-05-01 Bypass a Control Rod in the Rod Action Control Cabinet 214-505-01-01 Respond to RCIS Alarms 214-519-04-01 Respond to an Inability to Move Control Rods Task Standard: Bypass the control rod position in RACCs 1 and 2 per SOI-C11 (RCIS)

K / A Data: 201005 K1.03 Knowledge of the physical connections and/or cause effect relationships between ROD CONTROL AND INFORMATION SYSTEM (RCIS) and the following: Control rod drive system: BWR-6 3.7 / 3.7

1. Setup Instructions: N/A

2. Location / Method: Control Room / Simulation

3. Initial Condition: Rod shuffle is in progress. Data fault on rod 18-47 exists. Reactor Engineer and Unit Supervisor have been informed and concur that 18-47 control rod position must be bypassed to allow movement of control rod.

4. Initiating Cue: The Unit Supervisor directs you as the Reactor Operator to bypass the control rod position in RACCs for control rod 18-47 using SOI-C11 (RCIS) section 7.15 Rod Position Bypass in RACC.

Start Time: End Time:

Candidate:

OT-3701-C11_05 (S7)

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 CAUTION Bypassing the position for a control rod will prohibit a rod withdrawal or insertion inhibit from being actuated for that particular rod, making it possible to move the rod regardless of normal rod pattern controller restrictions.

7.15 Rod Position Bypass in RACC NOTE There are two position bypass channels, one in each RACC. Although each Bypass File has 20 card slots, only 8 will have cards installed. Each card contains 11 toggle switches in a vertical arrangement.

The top switch has the bypass function.

The remaining 10 switches are provided for the binary address of the rod to be bypassed.

Any bypassing operation must be verified by a second licensed operator or other technically qualified member of the Unit Technical Staff. This is documented on Attachment 4, Verification Checklist Section 7.15 and 7.16, Rod Position Bypass in RACC. (SR 3.3.2.1.9) 7.15.1 INFORM the following a rod position requires bypassing:

Unit Supervisor

Reactor Engineer Standard: Condition met from initiating cue Instructor Cue: None Notes: None OT-3701-C11_05 (S7)

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_05 (S7)

Step 2 7.15.2 DETERMINE the binary address of the rod to be bypassed from Attachment 1, Binary Coordinates.

7.15.3 RECORD the following on Attachment 3, Verification Checklist Section 7.15 and 7.16, Rod Position Bypass in RACC.

Binary address of the rod to be bypassed

Rod position of the rod to be bypassed.

Critical Step: Determines binary address and records on attachment 3.

Instructor Cue: Rod position is 00 Notes: Binary address X address 0-0-1-1-0 and Y address 0-1-1-0-1 SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 7.15.4 PERFORM independent verification of the following:

Binary address of the rod to be bypassed.

Rod position of the rod to be bypassed Standard: Requests IV Instructor Cue: IV is complete Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_05 (S7)

Step 4 7.15.5 IF required, THEN UNLOCK the Bypass File in the RACC at 1H13-P651.

Standard: Unlocks 1H13P651 Instructor Cue: Bypass File is unlocked.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 NOTE Position toggle switches to the right for a 1 or to the left for a 0.

7.15.6 POSITION the bottom 10 toggle switches to the binary address for the rod being bypassed on a Bypass Card at 1H13-P651.

Critical Step: Simulates positioning toggle switches to binary address.

Instructor Cue:

If asked, the selected Card/Slot is NOT in use.

As Found or right as needed Notes: Toggle switch position X address L-L-R-R-L and Y address L-R-R-L-R SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_05 (S7)

Step 6 7.15.7 RECORD the 1H13-P651 Bypass Card slot number on Attachment 3, Verification Checklist Section 7.15 and 7.16, Rod Position Bypass in RACC.

Standard: Records slot number on attachment 3 Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 7 7.15.8 PLACE the bypass (top) switch for the card to BYPASS (right) at 1H13-P651.

Critical Step: Simulates placing the top switch to the right.

Instructor Cue: Switch to right, Red light on Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_05 (S7)

Step 8 NOTE The red BYPASS LED will indicate the rod position is bypassed.

7.15.9 IF required, THEN UNLOCK the Bypass File in the RACC at 1H13-P652.

Standard: Unlocks P652 Instructor Cue: Bypass File is unlocked Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 9 7.15.10 POSITION the bottom 10 toggle switches to the binary address for the rod being bypassed on a Bypass Card at 1H13-P652.

NOTE Position toggle switches to the right for a 1 or to the left for a 0.

Critical Step: Simulates positioning toggle switches to binary address.

Instructor Cue:

If asked, the selected Card/Slot is NOT in use.

As Found or right as needed Notes: Toggle switch position X address L-L-R-R-L and Y address L-R-R-L-R SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_05 (S7)

Step 10 7.15.11 RECORD the 1H13-P652 Bypass Card slot number on Attachment 3, Verification Checklist Section 7.15 and 7.16, Rod Position Bypass in RACC.

Standard: Records slot number Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 11 7.15.12 PLACE the bypass (top) switch for the card to BYPASS (right) at 1H13-P652.

Critical Step: Simulates placing the top switch to the right.

Instructor Cue: Switch to right, Red light on Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_05 (S7)

Step 12 7.15.13 PERFORM independent verification of the following:

Bypass Card slot number

Bypass Card toggle switch positions.

7.15.14 IF all bypassing is complete, THEN LOCK the Bypass File.

Standard: Request IV and locks panel Instructor Cue: IV complete Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 13 NOTE POSITION BYPASSED on the OCM will be backlit to indicate a rods position is bypassed.

If both channels of RPIS are NOT bypassed a CHANNEL DISAGREE will occur.

7.15.15 CONFIRM the CHANNEL DISAGREE light is NOT backlit at the OCM, unless backlit for other reasons.

7.15.16 DEPRESS POSITION BYPASSED at the OCM.

7.15.17 CONFIRM the rod to be bypassed is indicated as Bypassed by its green LED at the OCM.

7.15.18 RELEASE POSITION BYPASSED at the OCM.

Standard: Confirms channel disagree light not back lit, confirms rod bypassed indicates bypassed Instructor Cue: Channel disagree off, correct rod bypassed green light for rod 18-47 Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_05 (S7)

Step 14 7.15.19 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 3, Verification Checklist Section 7.15 and 7.16, Rod Position Bypass in RACC is attached to the LCO Tracking Sheet.

Standard: Reports Rod bypassed and simulates initiating log entry and LCO Instructor Cue:

Log Entry has been made by the ATC

IV sheet is attached to the LCO Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Rod 18-47 is bypassed in RACCs Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-C11_05 (S7)

JPM CUE SHEET INITIAL CONDITIONS: Rod shuffle is in progress.

Data fault on rod 18-47 exists.

Reactor Engineer and Unit Supervisor have been informed and concur that 18-47 control rod position must be bypassed to allow movement of control rod.

INITIATING CUE: The Unit Supervisor directs you as the Reactor Operator to bypass the control rod position in RACCs for control rod 18-47 using SOI-C11 (RCIS) section 7.15 Rod Position Bypass in RACC.

OT-3701-P51/52_NRC10-S8 JOB PERFORMANCE MEASURE SETUP SHEET System: Service and Instrument Air Time Critical: No Alternate Path: Yes Applicability: RO/SRO Safety Function: 8 - Plant Service Systems Setting: Simulator Validated: 20 minutes

References:

EOP-SPI-2.8 rev 1. SOI-P51/52 rev25 ARI-H13-P680-07 rev 18 Tasks: 278-506-05-01Bypass Instrument Air Isolation following RHR LOCA Task Standard: Bypass Instrument Air Isolation and start either Unit 1 Service Air or Instrument Compressor per EOP-SPI 2.8.

K / A Data: 300000 K1.03 Knowledge of the connections and / or cause effect relationships between INSTRUMENT AIR SYSTEM and the following:

Containment air 2.8 / 2.9

1. Setup Instructions:

Reset to IC-162 and use schedule file _NRC_JPM-1a

Verify a High DW Pressure LOCA signal is in

Verify Remote Function of U2 Air Compressors is in Man-Modulate

Verify Malfunction is in to prevent Unit 1 Air Compressors from auto starting

Verify NO air compressor is running

Verify annunciator SERV AIR COMP TRBL on Trigger 1

Verify annunciator INST AIR COMP TRBL on Trigger 2

Note: Only ONE of these annunciators will be activated for the FIRST air compressor started.

2. Location / Method: Simulator / Perform

3. Initial Condition: A High DW pressure LOCA signal is in. Bus H22 has tripped.

4. Initiating Cue: Perform EOP-SPI 2.8 Bypass Of Instrument Air Isolation.

Start Time: End Time:

Candidate:

OT-3701-P51/52_NRC10-S8 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 2.8, Bypass Of Instrument Air Isolation 1.0 Instrument Air is isolated to Containment NO known air leak is present in Containment NO known air leak is present in Drywell THEN RESTORE Instrument Air to Containment and Drywell as follows:

1.1 OPEN INST AIR DRYWELL ISOL valve. P52-F646 1.2 OPEN INST AIR CNTMT ISOL valve. P52-F200 Critical Step: Operator opens:

INST AIR DRYWELL ISOL valve. P52-F646

INST AIR CNTMT ISOL valve. P52-F200 Instructor Cue: If asked, tell the operator that there is no known air leak in the Containment or the Drywell.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P51/52_NRC10-S8 Step 2 2.0 PLACE BUS XH11 LOCA BYPASS keylock switch in BYPASS.

Standard: Operator verifies XH11 LOCA BYPASS keylock switch in BYPASS Instructor Cue: None Notes: LOCA BYPASS keylock switch may already be in BYPASS SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 3.0 PLACE BUS XH12 LOCA BYPASS keylock switch in BYPASS.

Standard: Operator verifies XH12 LOCA BYPASS keylock switch in BYPASS Instructor Cue: None Notes: LOCA AYPASS keylock switch may already be in BYPASS SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 4.0 IF Bus EH11 is energized, THEN TAKE ISOLATING BRKR to CLOSED.

Standard: Operator verifies EH1116 Isolating Brkr to CLOSED.

Instructor Cue: None Notes: Breaker EH1116 Isolating Brkr may already be CLOSED SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P51/52_NRC10-S8 Step 5 5.0 IF Bus EH12 is energized, THEN TAKE ISOLATING BRKR to CLOSED.

Standard: Operator verifies EH1214 Isolating Brkr to CLOSED.

Instructor Cue: None Notes: Breaker EH1214 Isolating Brkr may already be CLOSED SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 6 6.0 AT H13 P970, VERIFY only one of the following is running:

NCC PUMP AP43-C001A

NCC PUMP BP43-C001B

NCC PUMP CP43-C001C Critical Step: Operator verifies (starts/stops if necessary) only one NCC pump running Instructor Cue: If the NCC Ht Exch Outlet Temp High alarm comes in, inform the operator that another operator will address that alarm.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P51/52_NRC10-S8 Step 7 7.0 REFER TO SOI-P51/52, Service and Instrument Air System to start an air compressor.

Section 4.2, Unit 1 Serv. Air Comp. Manual Startup from Standby Readiness

Section 4.5, Unit 2 Serv. Air Comp. Manual Startup from Standby Readiness

Section 4.8, Unit 1 Inst. Air Comp. Manual Startup from Standby Readiness

Section 4.11, Unit 2 Inst. Air Comp. Manual Startup from Standby Readiness Standard: Operator refers to SOI-P51/52 section 4.2 (4.8) to start an Air Compressor.

Instructor Cue: None Notes: The operator may start Unit 1 Service Air per section 4.2 or Unit 1 Inst.

Air per section 4.8. The below steps apply to the start of either compressor. (Both Unit 2 compressors are powered from bus H22)

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 8 SOI-P51/52, Service and Instrument Air System 4._.1 VERIFY the oncoming Compressor is in Standby Readiness.

Standard: Operator observes no SERV (INST) AIR COMP TRBL alarm for oncoming compressor.

Instructor Cue: If asked, inform the operator the compressor is in Standby Readiness.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P51/52_NRC10-S8 Step 9 4._.2 ESTABLISH communications between the Control Room and Service (Inst) Air Compressor Control Panel 1H51-P051(P057).

Standard: Operator sends an NLO to the local control panel 1H51-P051 (P057).

Instructor Cue: An NLO is at the control panel Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 10 4._.2 TAKE the SERVICE (INST) AIR COMPRESSOR to START at 1H13-P870.

Critical Step: Operator starts the Service (Inst) Air Compressor at 1H13-P870 Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P51/52_NRC10-S8 Step 11 4._.4 DEPRESS the PRESSURE CONTROL MODULATE at 1H51-P051(P057) 4._.5 DEPRESS the START/STOP MODE MANUAL at 1H51-P051 (P057) 4._.6 VERIFY the Oil Filter Outlet Press indicates > 20 psig locally.

Standard: Operator directs the NLO to:

DEPRESS the PRESSURE CONTROL MODULATE at 1H51-P051(P057)

DEPRESS the START/STOP MODE MANUAL at 1H51-P051(P057)

VERIFY the Oil Filter Outlet Press indicates > 20 psig locally.

Instructor Cue:

Pushbuttons have been depressed.

After simulator instructor activates the below alarm inform the operator:

o As the ATC, an unexpected Serv (Inst) Air Comp Trbl alarm came in o As the NLO, that oil pressure is 10 psig and the local Low Oil Pressure shutdown annunciator is in alarm.

If asked as the NLO, the Aux Oil pump is not running Notes: Simulator Instructor: Activate the alarm for the started compressor For Service Air: Activate SERV AIR COMP TRBL, (Trigger 1)

For Inst Air: Activate INST AIR COMP TRBL , (Trigger 2)

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P51/52_NRC10-S8 Step 12 Stop/Trip the running air compressor.

Critical Step: Operator stops the running air compressor.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 13 7.0 REFER TO SOI-P51/52, Service and Instrument Air System to start an air compressor

Section 4.2, Unit 1 Serv. Air Comp. Manual Startup from Standby Readiness

Section 4.5, Unit 2 Serv. Air Comp. Manual Startup from Standby Readiness

Section 4.8, Unit 1 Inst. Air Comp. Manual Startup from Standby Readiness

Section 4.11, Unit 2 Inst. Air Comp. Manual Startup from Standby Readiness Standard: Operator refers to SOI-P51/52 section 4.8 (4.2) to start an Air Compressor.

Instructor Cue: None Notes: The operator will start the last available compressor: Service Air per section 4.2 or Inst. Air per section 4.8. The below steps apply to the start of either compressor.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P51/52_NRC10-S8 Step 14 4._.1 VERIFY the oncoming Compressor is in Standby Readiness.

Standard: Operator observes no INST (SERV) AIR COMP TRBL alarm for oncoming compressor.

Instructor Cue: If asked, inform the operator the compressor is in Standby Readiness.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 15 4._.2 ESTABLISH communications between the Control Room and Inst (Service) Air Compressor Control Panel 1H51-P057(P051).

Standard: Operator sends an NLO to the local control panel 1H51-P057(P051).

Instructor Cue: An NLO is at the control panel Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P51/52_NRC10-S8 Step 16 4._.2 TAKE the INST (SERVICE) AIR COMPRESSOR to START at 1H13-P870.

Critical Step: Operator starts the Service (Inst) Air Compressor at 1H13-P870 Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P51/52_NRC10-S8 Step 17 4._.4 DEPRESS the PRESSURE CONTROL MODULATE at 1H51-P057(P051) 4._.5 DEPRESS the START/STOP MODE MANUAL at 1H51-P057(P051).

4._.6 VERIFY the Oil Filter Outlet Press indicates > 20 psig locally.

4._.7 VERIFY the oil level is visible within the sightglass locally.

4._.8 ADJUST the Serv Air Comp NCC Oil Cooler Out to maintain lube oil temperature 95-120°F.

Standard: Operator directs the NLO to:

DEPRESS the PRESSURE CONTROL MODULATE at 1H51-P057(P051)

DEPRESS the START/STOP MODE MANUAL at 1H51-P057 (P051).

VERIFY the Oil Filter Outlet Press indicates > 20 psig locally.

VERIFY the oil level is visible within the sightglass locally.

ADJUST the Serv Air Comp NCC Oil Cooler Out to maintain lube oil temperature 95- 120°F.

Instructor Cue: NLO reports all indications are within specifications.

The Unit Supervisor has assigned another operator to complete remainder of this procedure.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: First air compressor is secured and second air compressor is running.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-P51/52_NRC10-S8 JPM CUE SHEET INITIAL CONDITIONS:

High DW pressure LOCA signal is in. Bus H22 has tripped.

INITIATING CUE: .

Perform EOP-SPI 2.8 Bypass Of Instrument Air Isolation.

OT-3701-C41_07 (P1)

JOB PERFORMANCE MEASURE SETUP SHEET System: Standby Liquid Control Time Critical: No Alternate path: No Applicability: RO/SRO Safety Function: 1 - Reactivity Control Setting: Plant Validated: 35 minutes

References:

EOP-SPI 1.8 rev 2 Tasks: Complete the Alternate Boron Injection Flowpath per EOP-SPI 1.8 steps 4 through 8 Task #: 211-523-05-01 Complete the Alternate Boron Injection Flowpath in Preparation for Injection into the RPV 211-546-05-04 Perform Alternate Boron Injection K / A Data: 295037 EA1.10 Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Alternate boron injection methods 3.7 / 3.9

1. Setup Instructions: N/A

2. Location / Method: Plant / Simulation

3. Initial Condition: Plant operating in EOP-1A Level Power Control. EOP-SPI 1.8 Alternate Boron Injection is complete up to step 4.0.

4. Initiating Cue: The Unit Supervisor directs you, a plant operator, to perform Alternate Boron Injection hook up per EOP-SPI 1.8 section 4.0 through 8.0.

Start Time: End Time:

Candidate:

OT-3701-C41_07 (P1)

JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

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

Step 1 4.0 PERFORM the following to connect High Pressure Hose:

CAUTION Prior HPCS operation may result in elevated radiation levels in the HPCS Valve Room.

4.1 AT AX 620 D/02, HPCS Valve Room, VERIFY HPCS Pump Disch Line Flush Conn 1E22-F031 is closed.

Standard: Operator verifies 1E22F031 closed Instructor Cue: Valve closed Notes: When candidate identifies where (Aux-620 EOP Gang Box) he would obtain the necessary tools to perform this task, give him the Handouts.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C41_07 (P1)

Step 2 4.2 AT AX 620 D/02, AX hallway, PERFORM the following to install the High Pressure Hose:

4.2.1 REMOVE Fast Fire Water Connection.

4.2.2 INSTALL ABI Connection Assembly End of High Pressure Hose to the HPCS Discharge Flush Connection.

4.2.3 REMOVE pipe cap from ABI Pump Discharge Piping.

4.2.4 INSTALL free end of the High Pressure Hose to ABI Pump Discharge Piping.

Critical Step: Operator simulates installing high pressure hose.

Instructor Cue: Hose installed Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 5.0 CONNECT the Low Pressure Hose as follows:

5.1 AT AX 620 E/01, at the Intermediate Building entrance, SECURE IB Man-door open using the nylon rope. IB 301 Standard: Operator simulates propping IB301 open Instructor Cue: Door open Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C41_07 (P1)

Step 4 5.2 AT AX 620 D/02, AX hallway, PERFORM the following to install the Low Pressure Hose:

5.2.1 REMOVE pipe cap from ABI Pump suction piping.

5.2.2 INSTALL Low Pressure Hose to ABI Pump suction piping.

Critical Step: Operator simulates installing one end of low pressure hose.

Instructor Cue: Hose installed Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 5.3 AT IB 620 D/02, PERFORM the following to connect the free end of the Low Pressure Hose:

5.3.1 REMOVE pipe cap from UNIT 1 TRSF LN Drain Vlv 1C41-F527.

5.3.2 INSTALL free end of the Low Pressure Hose to UNIT 1TRSF LN Drain Vlv 1C41-F527.

5.3.3 OPEN UNIT 1 TRSF LN Drain Vlv 1C41-F527.

Critical Step: Operator simulates installing other end of low pressure hose and opens 1C41F527.

Instructor Cue: Hose installed and valve 1C41F527 open Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C41_07 (P1)

Step 6 6.0 CONNECT ABI Pump Motor Starter Cable as follows:

6.1 AT AX 620 D/02, ABI Pump Local Starter, 1C41-C0004, INSTALL one end of ABI Pump Local Starter, 1C41-C0004 Cable.

6.2 AT IB 620 D/02, Welding Receptacle 1R25-S230, INSTALL free end of ABI Pump Local Starter, 1C41-C0004 Cable.

6.3 AT IB 620 D/02, Welding Receptacle 1R25-S230, CLOSE local disconnect switch.

6.4 AT AX 620 D/02, ABI Pump Local Starter, 1C41-C0004, CLOSE local disconnect switch.

6.5 AT AX 620 D/02, ABI Pump Local Starter, 1C41-C0004, VERIFY green OFF light illuminates.

Critical Step: Operator simulates connecting electrical cable and closing disconnect switches.

Instructor Cue: Cable installed and disconnect switches closed, green light illuminated Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 7 7.0 AT IB 654 C/04, VERIFY Unit 1 Trsf Line Otbd Cntmt Isol Vlv 1C41-F518 is closed.

Standard: Operator verifies 1C41F518 closed.

Instructor Cue: 1C41F518 Closed Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C41_07 (P1)

Step 8 8.0 AT IB 599 I/05, PERFORM the following to line up seal leak off:

8.1 VERIFY sleeving from Mixing Tk & Pump Drain Isol Valve to pre-staged 55 gallon drum is installed. C41-F512 8.2 OPEN Mixing Tk & Pump Drain Isol Valve. C41-F512 Standard: Operator verifies sleeving and opens C41-F512.

Instructor Cue: Sleeving installed and valve open Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: EOP-SPI 1.8, Alternate Boron Injection steps 4.0 through 8.0 complete.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-C41_07 (P1)

JPM CUE SHEET INITIAL CONDITIONS: Plant operating in EOP-1A Level Power Control. EOP-SPI 1.8 Alternate Boron Injection is complete up to step 4.0.

INITIATING CUE: The Unit Supervisor directs you, a plant operator, to perform Alternate Boron Injection hook up per EOP-SPI 1.8 section 4.0 through 8.0.

Handout 1 Handout 2 Handout 3 Handout 4 Handout 5 Handout 6 OT-3701-P52_01 (P2)

JOB PERFORMANCE MEASURE SETUP SHEET System: Service and Instrument Air Time Critical: No Alternate Path: Yes Applicability: RO/SRO Safety Function: 8 - Plant Service Systems Setting: Plant Validated: 15 minutes

References:

ONI-SPI D-8 Tasks: 279-511-04-01 Respond to a Loss of Service or Instrument Air 278-531-04-04 Isolate an Air Receiver Task Standard: Isolate an air receiver per ONI-SPI-D8 K / A Data: 295019 AA1.02 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Instrument air system valves: Plant-Specific 3.3 / 3.1

1. Setup Instructions: None

2. Location / Method: Plant / Simulation

3. Initial Condition: Plant has experienced a loss of air, due to sabotage to the air system.

Unit Supervisor is operating in ONI-P52 and ONI-P56-2. Currently no air compressors are operating. Security has apprehended the individual responsible for the damage to the air system.

4. Initiating Cue: The Unit Supervisor directs you to perform ONI-SPI-D8, Air Receiver Isolation and isolate one of the Instrument air receivers.

Start Time: End Time:

Candidate:

OT-3701-P52_01 (P2)

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.

EVALUATOR NOTE: The candidate will select either Unit 1 or Unit 2 Air Receiver Tank, find that the tank can not be isolated and then move to the other Unit Air Receiver Tank and isolate it.

Step 1 ONI_PSI D8, Air Receiver Isolation 1.0 ISOLATE one of the Instrument air receivers as follows:

1.(_) IF isolating the Unit 1(2) Instrument Air Receiver Tank (P52-A001), THEN VERIFY CLOSED the following valves:

1.(_).1 INST AIR PREFILTER A INLET ISOLATION (_)P52-F511A 1.(_).2 INST AIR PREFILTER B INLET ISOLATION (_)P52-F511B Standard: Operator simulates closing P52-F511A or B, and verifies closed the other valve.

Instructor Cue: Valves are as found, one should be open and one closed. After operator simulates closing the one valve, inform the operator that both valves are closed.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P52_01 (P2)

Step 2 1.(_).3 INST AIR PREFILTER BYPASS VALVE (_)P52-F515 Standard: Operator verifies P52-F515 closed.

Instructor Cue: Valve is as found, closed.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 1.(_).4 INST AIR RECEIVER TK INLET FROM INST AIR (_)P52-F509 Standard: Operator simulates closing P52-F509.

Instructor Cue: Valve is as found, open. After operator simulates closing the valve, inform the operator the valve is closed.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P52_01 (P2)

Step 4 1.(_).5 INST AIR RECEIVER TK INLET FROM SERV AIR (_)P52-F544 Standard: Operator simulates closing P52-F544.

Instructor Cue: Valve is as found, open. The valve is damaged and will not move. Air can be heard moving through the line.

If the operator asks for direction from the US, repeat the initiating cue The Unit Supervisor directs you to perform ONI-SPI-D8, Air Receiver Isolation and isolate one of the Instrument air receivers.

If the operator wants to return the valves to the as found condition, inform the operator that someone else will be assigned to do this.

Notes: Candidate will move to the other Units Air Receiver Isolation section (1.1 or 1.2) and attempt to isolate that receiver.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P52_01 (P2)

Step 5 1.0 ISOLATE one of the Instrument air receivers as follows:

1.(_).1 IF isolating the Unit 2(1) Instrument Air Receiver Tank (P52-A001), THEN VERIFY CLOSED the following valves:

1.(_).1 INST AIR PREFILTER A INLET ISOLATION (_)P52-F511A 1.(_).2 INST AIR PREFILTER B INLET ISOLATION (_)P52-F511B Critical Step: Operator simulates closing P52-F511A or B, and verifies closed the other valve.

Instructor Cue: Valves are as found, one should be open and one closed. After operator simulates closing the one valve, inform the operator that both valves are closed.

Notes: Only the valve that is found open and subsequently closed is critical.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 6 1.(_).3 INST AIR PREFILTER BYPASS VALVE (_)P52-F515 Standard: Operator verifies P52-F515 closed.

Instructor Cue: Valve is as found, closed.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P52_01 (P2)

Step 7 1.(_).4 INST AIR RECEIVER TK INLET FROM INST AIR (_)P52-F509 Critical Step: Operator simulates closing P52-F509.

Instructor Cue: Valve is as found, open. After operator simulates closing the valve, inform the operator the valve is closed Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 8 1.(_).5 INST AIR RECEIVER TK INLET FROM SERV AIR (_)P52-F544 Critical Step: Operator simulates closing P52-F544.

Instructor Cue: Valve is as found, open. After operator simulates closing the valve, inform the operator the valve is closed.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P52_01 (P2)

Step 9 1.1.6 NOTIFY the control room one Instrument Air Receiver Tank is ISOLATED.

1.1.7 EXIT this instruction.

Standard: Operator notifies Control Room and exits instruction.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: One Instrument Air Receiver Tank is isolated.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-P52_01 (P2)

JPM CUE SHEET INITIAL CONDITIONS: Plant has experienced a loss of air, due to sabotage to the air system.

Unit Supervisor is operating in ONI-P52 and ONI-P56-2.

Currently no air compressors are operating.

Security has apprehended the individual responsible for the damage to the air system.

INITIATING CUE: The Unit Supervisor directs you to perform ONI-SPI-D8, Air Receiver Isolation and isolate one of the Instrument air receivers.

OT-3701-C61_02 (P3)

JOB PERFORMANCE MEASURE SETUP SHEET System: Remote Shutdown Panel Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 7 - Instrumentation Setting: Plant Validated: 15 minutes

References:

IOI-11 rev 19 Tasks: 007-533-04-01 Shutdown LPCI from Remote Shutdown Panel Task Standard: When RPV level reaches 200, shutdown LPCI B from Remote Shutdown Panel per IOI-11, Attachment 10.

K / A Data: 295016 AA1.06 Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: Reactor water level. 4.0 / 4.1

1. Setup Instructions: None

2. Location / Method: Plant / Simulation

3. Initial Condition: Operating in accordance with IOI-11 at Division 2 Remote Shutdown Panel. Level control is on LPCI B, the Unit supervisor is going to transfer level control to LPCI A at the Division 1 Remote Shutdown Panel.

4. Initiating Cue: Unit Supervisor directs you the Reactor Operator to perform IOI-11 Attachment 10 section 6.0 LPCI B Shutdown when vessel level reaches 200 inches.

Start Time: End Time:

Candidate:

1

OT-3701-C61_02 (P3)

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 6.0 LPCI SHUTDOWN 6.1 VERIFY the RHR PUMP B MIN FLOW VALVE is open at EF1D07-CC. 1E12-F064B Critical Step: Operator verifies level on C61R030 and then simulates opening 1E12F064B Instructor Cue: Initially, 1E12F064B switch is in CLOSE position.

Reactor level when checked is as read or 201 inches and rising slowly. If RHR B flow is checked flow is 6000 gpm on C61R025. 1E12F064B when verified is closed green light on. After operator simulates opening 1E12F064B red light on Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

2

OT-3701-C61_02 (P3)

Step 2 6.2 TAKE the LPCI B INJECTION VALVE to CLOSE at EF1D07-X. 1E12-F042B Critical Step: Operator simulates closing 1E12F042B Instructor Cue: Initially, 1E12F042B switch is in OPEN position.

Red light on originally, green light on after closure. If flow checked flow going from 6000 gpm to 0 gpm.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 6.3 WHEN the LPCI B INJECTION VALVE is full closed, 1E12-F042B THEN HOLD RHR B HXS BYPASS VALVE in OPEN at EF1D07-V UNTIL full open. 1E12-F048B Standard: Operator verifies 1E12F042B full closed, then simulates opening 1E12F048B Instructor Cue: Initially, 1E12F048B switch is in NORMAL position.

Green light on for 1E12F042B, 1E12F048B has green light on.

After operator simulates opening 1E12F048B red light on.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

3

OT-3701-C61_02 (P3)

Step 4 6.4 HOLD the RHR B HXS OUTLET VALVE in OPEN at EF1D07-D UNTIL fully open.

1E12-F003B Standard: Operator fully opens 1E12F003B.

Instructor Cue: Initially, 1E12F003B switch is in NORMAL position.

1E12F003B has red and green light on initially, when full open red light on.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 6.5 TAKE the RHR PUMP B to STOP at EH1208. 1E12-C002B Critical Step: Operator simulates stopping 1E12C002B Instructor Cue: Initially, 1E12C002B switch is in NORMAL position.

Red light on originally, green light on after stopping pump.

Flow currently is 0 gpm C61R025.

Reactor level is 205 inches if checked.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: LPCI B shutdown from injecting to RPV, Reactor Level 200 to 205 inches Evaluation Results: SAT_____ UNSAT_____

End Time:

4

OT-3701-C61_02 (P3)

JPM CUE SHEET INITIAL CONDITIONS: Operating in accordance with IOI-11 at Division 2 Remote Shutdown Panel. Level control is on LPCI B, the Unit supervisor is going to transfer level control to LPCI A at the Division 1 Remote Shutdown Panel.

INITIATING CUE: Unit Supervisor directs you the Reactor operator to perform IOI-11 Attachment 10 section 6.0 LPCI B shutdown when vessel level approaches 200 inches.

5

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 1 - 100% Op-Test No.: 2010-01 Examiners: Operators:

Initial Conditions: Reactor Power 100%. BOL Pull Sheets, Rods @ Step 64.

IOI-3 Step 4.5 is complete.

HPCS ESW running to support HPCS run.

RFBP A is OOS for motor replacement. ODMI Actions for RFBP A are in place.

Control Rod 34-55 is inserted.

ESW B is running for vibration testing.

A severe thunderstorm watch has been issued for Lake, Geauga, & Ashtabula counties.

Green Risk.

Turnover: Start HPCS in CST to CST IAW SOI-E22 for a PM run. Personnel have been briefed and are on station to support field activities. When SCC request, lower power to 95% per IOI-3 Power Maneuvering.

Event Malf. No. Event Event No. Type* Description 1 N-BOP/SRO Start HPCS for PM run (CST CST)

SRO Tech Spec 3.5.1 2 mv05_1e22f0012 C-BOP/SRO HPCS Minimum Flow fails to close 3 R-ATC Lower power with flow N-SRO 4 cp01_1p45c0002 C-BOP/SRO ESW C pump trips - secure HPCS & EDG SRO Tech Spec 3.7.2 5 pt01_1c34n0004c ATC/SRO C34N004C fails high SRO ORM 6.2.13 6 pt01_1c34n0004b M-All Loss of feedwater EOP-1 RPV Control & EOP-1A (ATWS) 7 cb03_1b33s101b C-ATC/SRO Reactor Recirc pump B fails to trip from fast speed cb03_1b33s105b cb03_1b33s106b 8 mv04_1e51f0013 C-BOP/SRO RCIC Injection valve fails to auto open, HPCS & RCIC trip (Loss cp02_1e22c0001 of HP Feed) 9 TC04A ATC/SRO Bypass valve #1 fails open 10 M-All Emergency Depressurize EOP-4-2 on inability to maintain > -25

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

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 2 of 25 Event

Description:

Simulator Setup Time Position Applicants Actions or Behavior Driver Driver Simulator Setup:

Reset Simulator to IC 151 Load Schedule _NRC-01-100pct.sch Load Schedule _NRC_Info.sch Load Event _NRC_Exam-1-100.evt Cycle HPCS Minimum Flow valve and ensure it opens closes with the control switch (i.e. ensure contacts are not dirty).

Verify possession of cue card for HPCS trip unit on P625 Driver Driver Verify Initial Conditions:

Reactor Power 100%. BOL Pull Sheets, Rods @ Step 64.

IOI-3 Step 4.5 is complete.

HPCS ESW running to support HPCS run.

Place yellow switch cap on RFBP A & RFBP A discharge valve.

Control Rod 34-55 is inserted.

ESW B running for vibration testing.

Green Risk.

Driver Driver Turnover:

Start HPCS in CST to CST IAW SOI-E22A for a PM run. Personnel have been briefed and are on station to support field activities. When SCC request lower power to 95% per IOI-3 Power Maneuvering SRO Directs BOP to start HPCS IAW SOI-E22A, 7.10 HPCS Full Flow Test to CST Declares HPCS inoperable IAW Tech Spec 3.5.1., Condition B:

Verify RCIC operable in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Restore HPCS to operable in 14 days

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 3 of 25 Event

Description:

Start HPCS for PM Run Time Position Applicants Actions or Behavior BOP 7.10.1 VERIFY HPCS System in Standby Readiness.

7.10.2 RECORD the appropriate Maintenance Rule (HPCS inoperable) status in the Plant Narrative Log.

7.10.3 REFER TO SOI-P45/49 and START the HPCS ESW Loop.

7.10.4 VERIFY the Suppression Pool Cleanup System is shutdown.

7.10.5 VERIFY the HPCS SUPR POOL SUCTION VALVE is closed. 1E22-F015 7.10.6 VERIFY the HPCS CST SUCTION VALVE is open. 1E22-F001 7.10.7 TAKE the HPCS PUMP to START. 1E22-C001 7.10.8 VERIFY the HPCS PUMP MIN FLOW VALVE is open. 1E22-F012 7.10.9 WHILE performing the following step, VERIFY the HPCS PUMP MIN FLOW 1E22-F012 VALVE closes WHEN HPCS PUMP FLOW is >725 gpm. 1E22-R603 BOP Recognizes that the HPCS Min Flow Valve did not auto close and manually closes 1E22-F012.

Reports failure of valve to close to US.

Driver Driver Wait for the operator at the back table. If the operator goes to check the HPCS trip units (pressure, flow - E22N651 & N656) inform him that the readings/indications are normal (the low flow trip light is off with > 725 gpm) or hold up cue card.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 4 of 25 Event

Description:

Start HPCS for PM Run Time Position Applicants Actions or Behavior NRC NRC Note: The US may decide to suspend the PM and return HPCS to standby. The steps to placing HPCS to standby are contained in Event 4, ESW C pump trip.

NOTE: Steps 7.10.10 through 7.10.15 are for Examiners use BOP 7.10.10 SIMULTANEOUSLY JOG open:

HPCS FIRST TEST VALVE TO CST 1E22- F010

HPCS SECOND TEST VALVE TO CST 1E22-F011 UNTIL

HPCS PUMP FLOW indicates approximately 6100 gpm 1C11- R603

Both HPCS TEST VLV POSIT position indicators are relatively equal 1E22-606 1E22-R606 7.10.11 HOLD the HPCS FIRST TEST VALVE TO CST in CLOSE 1E22-F010 UNTIL a decrease in HPCS PUMP FLOW occurs. 1E22-R603 7.10.12 HOLD the HPCS FIRST TEST VALVE TO CST in OPEN 1E22-F010 UNTIL

HPCS PUMP FLOW indicates approximately 6100 gpm 1E22-R603

HPCS FIRST TEST VALVE TO CST is full open 1E22-F010 7.10.13 HOLD the HPCS SECOND TEST VALVE TO CST in CLOSE 1E22-F011 UNTIL a decrease in HPCS PUMP FLOW occurs. 1E22-R603 7.10.14 WHILE performing the following step, VERIFY the HPCS PUMP MIN FLOW VALVE closes 1E22-F012 WHEN HPCS PUMP FLOW is >725 gpm. 1E22-R603 7.10.15 HOLD the HPCS SECOND TEST VALVE TO CST in OPEN 1E22-F011 UNTIL

HPCS PUMP FLOW indicates approximately 6100 gpm 1E22-R603

HPCS SECOND TEST VALVE TO CST is full open 1E22-F011 NRC NRC Note: The SRO will decide to call HPCS inoperable based upon the failure of the minimum flow valve to close.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 5 of 25 Event

Description:

3 - Lower Power with Flow Time Position Applicants Actions or Behavior Driver Driver At predetermined time or when directed by Chief Examiner, call as the SCC and request a power decrease to 95%.

SRO Directs ATC to lower power IAW IOI-3, Section 4.6 Power Decrease to 30%

Reactor Power 4.6.1 IF reducing reactor power within the approximate range of 68% and 100%

using Recirculation flow only AND power is required to be changed for either of the following:

Testing requires placing the plant at reduced power levels.

Plant conditions require placing the plant at reduced power levels.

THEN REFER TO Attachment 3 -POWER MANEUVERING.

SRO 1.1 COMMENCED POWER MANEUVERING at the following time:

Time: __________ Date: ___________

ATC 1.3 ADJUST the setpoint of the RCIRC AUTOMATIC FLOW DEMAND LIMITER B33-K650.

Driver Driver When 95% power is reached, or when directed by Chief Examiner, continue on to the next event.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 6 of 25 Event

Description:

4 - Trip of ESW C Time Position Applicants Actions or Behavior Driver Driver At predetermined time or when directed by Chief Examiner, insert Trigger 3 (Event 4) (cp01_1p45c0002), ESW C pump trip.

BOP

Responds to H13-P601 annunciators:

o HPCS OUT OF SERVICE o ESW TO DIESEL HEAT EXCHANGER FLOW LOW o HPCS ESW PUMP DISCHARGE PRESSURE LOW

Checks which indicator is illuminated on the INOP and Bypass matrix and determines ESW C has tripped.

Refers to Steps 4.9 and 4.10 of the annunciator procedures o 4.9 Adequate core cooling is assured AND loss of ESW cooling occurs THEN SHUTDOWN the HPCS Pump o 4.10 HPCS System operability is affected, HPCS System is in Standby Readiness and the alarm is NOT due to testing or maintenance THEN PERFORM the following:

4.10.1 REFER TO SOI-E22A and PLACE the HPCS System in the Secured Status.

4.10.2 REFER TO SOI-E22B and PLACE the HPCS DG in the Secured Status.

Informs US of ESW C trip and annunciator steps 4.9 & 4.10.

SRO Directs BOP to

Shutdown HPCS and place in secured status IAW SOI-E22A.

Place HPCS EDG in secured status IAW SOI-E22B.

SRO ESW C Inoperable IAW TS 3.7.2 , Condition A

Declares HPCS inoperable

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 7 of 25 Event

Description:

4 - Trip of ESW C Time Position Applicants Actions or Behavior BOP 7.10.16 WHEN desired to shutdown Full Flow Test to the CST, THEN PERFORM the remaining steps of this section.

7.10.17 HOLD the HPCS FIRST TEST VALVE TO CST in CLOSE UNTIL the flow rate is 500-600 gpm. 1E22-F010 1E22-R603 7.10.18 VERIFY the HPCS PUMP MIN FLOW VALVE opens.1E22-F012 7.10.19 HOLD the HPCS FIRST TEST VALVE TO CST in CLOSE UNTIL closed.1E22-F010 7.10.20 HOLD the HPCS SECOND TEST VALVE TO CST in CLOSE UNTIL closed. 1E22-F011 7.10.21 TAKE the HPCS PUMP to STOP. 1E22-C001 7.10.22 VERIFY the HPCS PUMP MIN FLOW VALVE closes. 1E22-F012

Manually closes 1E22-F012

Notifies US that the HPCS Min Flow Valve did not close 7.10.23 RECORD the appropriate Maintenance Rule status in the Plant Narrative Log.

7.10.24 IF the HPCS ESW Loop is NO longer required, THEN REFER TO SOI-P45/49 and SHUTDOWN the HPCS ESW Loop to Standby Readiness.

7.10.25 IF HPCS Pump Room Cooler is NO longer required, THEN REFER TO SOI-M39 and SHUTDOWN to Standby Readiness.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 8 of 25 Event

Description:

4 - Trip of ESW C Time Position Applicants Actions or Behavior Driver Driver For shutting down and securing of HPCS/DG:

If directed to shutdown HPCS Room Cooler, M39 fan, use Remote Function HV28.

If directed to rackout HPCS Breaker or remove fuses, use Remote Function HP03.

If asked to investigate, report you found 3 main line fuses blown.

If directed to open HPCS Injection Valve disconnect, use remote function HP08

If directed to place DG in MAINT, use Remote Function DG03.

BOP Places HPCS DG in Shutdown to Secured Status.

6.3.1 VERIFY Diesel Generator is Shutdown to Standby Readiness.

6.3.2 PLACE the DIESEL GENERATOR in PULL-TO-LOCK at 1H13-P601.

6.3.3 PLACE the DIESEL GENERATOR MODE in MAINT at 1E22-P001 o Dispatches an NLO to place in MAINT BOP Places HPCS in Shutdown from Standby Readiness to Secured Status 6.2.1 RECORD the following in the Plant Narrative Log in accordance with PAP-1125:

Availability management time entries

Unavailable time entries 6.2.2 PERFORM one of the following, as directed by Unit Supervisor for the HPCS PUMP Breaker: EH 1304

REMOVE the control power fuses

REFER TO SOI-R22 and RACK OUT the HPCS PUMP Breaker 6.2.3 OPEN the HPCS INJECTION VALVE Disconnect. 1E22-F004 EF1E-1-F

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 9 of 25 Event

Description:

5 - FW Level Instrument C34N004C Fails Upscale Time Position Applicants Actions or Behavior Driver Driver At predetermined time or when directed by Chief Examiner, insert Trigger 5 (Event 5) (pt01_1c34n0004c) for C34N004C Rx Level C Transmitter Failure.

ATC Responds to H13-P680 alarms

MAIN TURB & FDW TRIP RCIC/L8

RX LEVEL CHANNEL ERROR HI Informs the US that C34N004C has failed upscale SRO Directs ATC to bypass the failed transmitter IAW SOI-C34, Feedwater section 7.12 Bypassing/Unbypassing Transmitters ATC Bypasses C transmitter:

7.12.1 SELECT the transmitter to be bypassed/unbypassed.

7.12.2 SELECT the bypass/online button SRO Declares C34N004C inoperable IAW ORM 6.2.13 Action B

Restore to operable within 7 days or be in at least Mode 2 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 10 of 25 Event Descriptions: 6, 7, 8 - Loss of FW/HP Feed, EOP Entry, Recirc B Trip Failure Time Position Applicants Actions or Behavior Driver Driver At predetermined time or when directed by Chief Examiner, insert Trigger 6 (Event 6) (pt01_1c34n0004b and cp02_1e22c0001) for C34N004B Feedwater Level B Transmitter Failure and HPCS pump trip (trips HPCS if not previously tripped).

All Recognize loss of Feedwater, Turbine Trip and Reactor Scram NRC Performs SCRAM Hardcard actions Verify the following actions completed:

Mode Switch Locked in Shutdown.

RPS Initiated if all control rods are not fully inserted.

ARI Initiated if RPS failed to Scram the reactor.

If Reactor Recirc Pumps are running in fast speed:

Then simultaneously take the following to XFER:

RECIRC PUMP A BRKR 5A

RECIRC PUMP B BRKR 5B NRC NRC Note: The B pump will trip from fast speed when taken to XFER.

If Reactor power is above 4% then start SLC A and SLC B pumps.

Driver Driver When SLC is started, verify Trigger 11 activates.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 11 of 25 Event Descriptions: 6, 7, 8 - Loss of FW/HP Feed, EOP Entry, Recirc B Trip Failure Time Position Applicants Actions or Behavior ATC Perform crew update with the following information:

The Mode Switch is locked in shutdown

RPS was initiated (report failure)

ARI was initiated (report failure)

All Control Rods are not inserted

Reactor Power is _______________

Reactor Pressure is _______________

Reactor Level is _______________

Reactor Recirc Pumps Tripped

EOP-01 entry Reactor Level When generator load less than 90 MWe, then perform the following:

Trip the main turbine

Verify Main Stop valves, Control valves and CIVs are shut

Verify Gen BRKRs S-610-PY-TIE and S-611-PY-TIE are open

Verify Gen Field Breaker open Insert Nuclear Instruments,

SRMs

IRMs

Place recorders in IRM (leave A or E in APRM)

Verify HST Lvl CV Manual Control, N21-S19, in OFF

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 12 of 25 Event Descriptions: 6, 7, 8 - Loss of FW/HP Feed, EOP Entry, Recirc B Trip Failure Time Position Applicants Actions or Behavior ATC STABLIZE reactor water level.

a) Feedwater (REFER TO FEEDWATER HARDCARD) b) RCIC c) HPCS STABLIZE reactor pressure:

a) Turbine / Turbine Bypass valves (REFER TO REACTOR SCRAM PRESSURE CONTROL HARDCARD) b) SRVs

Evacuate Containment

REFER TO PRESSURE CONTROL HARDCARD

Evaluate placing RCIC in pressure Control Mode Verifies RWCU F004 or F001 closes if SLC was initiated SRO Enter EOP-1 RPV Control on Low Level, transitions to EOP-1A Power and Level Control, Power Leg and directs ATC to:

Monitor and Control Reactor Power

Stabilize Reactor Water Level with a level band of +50 to +100

Stabilize Reactor Pressure with a pressure band of 800-1000 psig Direct ATC to insert Rods per EOP-SPI 1.1 to 1.7 (Critical Task 1)

ATC Inserts Control Rods per EOP-SPI 1.3 (Critical Task 1)

Verify open Instrument Air Containment Isolation P52-F200 Verify CRD Hydraulics Flow Control is in MANUAL 1C11-R600 Adjust CRD Hydraulics Flow Control output to 100.

Close CRD Drive Press Control Valve 1C11-F003

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 13 of 25 Event Descriptions: 6, 7, 8 - Loss of FW/HP Feed, EOP Entry, Recirc B Trip Failure Time Position Applicants Actions or Behavior BOP At H13-P629, place Lo Power Set Pt Div 1 Bypass C11A-S4 in BYPASS At H13-P618, place Lo Power Set Pt Div 2 Bypass C11A-S3 in BYPASS Places Bus XH11 and XH12 LOCA Bypass switches to Bypass and verify XH11 &

XH12 buses are energized Verify One NCC Pump Running by stopping an NCC pump ATC Verify a CRD pump is running DEPRESS AND HOLD the IN TIMER SKIP pushbutton SELECT the desired Control Rod SRO Directs BOP to:

Verify Isolations and Actuations

Inhibit ADS (Critical Task 2)

Bypass MSIVs and ECCS Interlocks IAW EOP-SPI-2.3 BOP Inhibit ADS - Place ADS Inhibit switches in INHIBIT (Critical Task 2)

Performs EOP-SPI 2.3 Place keylock switches in BYPASS for:

MSIV ISOL LO LEVEL Bypass CH D, A, C, B - B21H-S76D, A, B, C

HPCS Logic Bypass (E22-F023)

RHR ISOL Bypass (E12-F053B)

LPCI C LOGIC BYP (E12-F021)

LO POWER SET PT DIV 2 Bypass (C11A-S3)

RHR ISOL Bypass (E12-F053A)

LPCS LOGIC BYP (E21-F012)

LO POWER SET PT DIV 1 Bypass (C11A-S4)

Verify Bus XH11 and XH12 LOCA Bypass switches in BYPASS Verify Isolating Breakers EH1116 and EH1214 to close Start/Verify One NCC Pump Running NRC NRC Note: If level is less than 100 OR the APRMs are downscale, then the below order is modified to only Terminate and Prevent ECCS injection and a level band of

+150 to +219

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 14 of 25 Event Descriptions: 6, 7, 8 - Loss of FW/HP Feed, EOP Entry, Recirc B Trip Failure Time Position Applicants Actions or Behavior SRO Directs:

BOP - Terminate and Prevent ECCS Injection IAW EOP-SPI-5.1 ATC -

Terminate and Prevent Feedwater injection IAW EOP-SPI-5.3

ATC - After 100 is reached, maintain Reactor Water Level +50 to +100 BOP Terminate and Prevent all ECCS injection systems

VERIFY BUS XH11 LOCA BYPASS keylock switch in BYPASS.

VERIFY BUS XH12 LOCA BYPASS keylock switch in BYPASS.

HOLD the HPCS INJECTION VALVE in CLOSED E22-F004.

ARM AND DEPRESS HPCS MANUAL INITIATION pushbutton to obtain white HPCS SEAL IN RESET light.

WHEN HPCS INJECTION VALVE E22-F004 is closed, THEN RELEASE the HPCS INJECTION VALVE control switch.

HOLD the following switches in CLOSE:

o LPCS INJECTION VLV E21-F005 o LPCI A INJECTION VALVE E12-F042A

ARM AND DEPRESS LPCS & LPCI A MANUAL INITIATION pushbutton to obtain the white LPCS & LPCI A SEAL IN RESET light.

RELEASE LPCI A INJECTION VALVE control switch E12-F042A.

WHEN LPCS INJECTION VLV E21-F005 is closed, THEN RELEASE LPCS INJECTION VLV.

HOLD the following switches in CLOSE:

o LPCI B INJECTION VALVE E12-F042B o LPCI C INJECTION VALVE E12-F042C

ARM AND DEPRESS LPCI B & C MANUAL INITIATION pushbutton to obtain the white LPCI B & C SEAL IN RESET light

RELEASE LPCI B INJECTION VALVE control switch E12-F042B.

WHEN LPCI C INJECTION VALVE is CLOSED, THEN RELEASE LPCI C INJECTION VALVE E12-F042C.

VERIFY the following valves are CLOSED:

o SHUTDOWN COOLING B TO FDW SHUTOFF E12-F053B o SHUTDOWN COOLING A TO FDW SHUTOFF E12-F053A o RHR A HEAD SPRAY ISOL E12-F023

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 15 of 25 Event Descriptions: 6, 7, 8 - Loss of FW/HP Feed, EOP Entry, Recirc B Trip Failure Time Position Applicants Actions or Behavior ATC Terminate and Prevent Feedwater for RPV Level Control

Verify RFPT A and B tripped

Place Motor Feed Pump Flow Control Valves Controller in Manual and close 1N27-F010 and 1N27-F110.

Verify closed o Bypass Valve 1N27-F200 o Motor Feed Pump Flow Control Valve 1N27-F010 o Motor Feed Pump Flow Control Valve 1N27-F110 o RFPT Discharge Valves 1N27-F100A and B BOP Verifies Isolations and Actuations at 130

RCIC Start

HPCS Start

Div 3 D.G. Start

RWCU Isolation BOP Reports the following:

HPCS tripped

RCIC injection valve did not open BOP Opens RCIC Injection Valve If running, trips Div 3 DG due to lack of ESW flow and puts in PTL.

Driver Driver When RCIC Injection Valve is opened verify Trigger 9 (RCIC Trip) becomes active. (RCIC will trip in 7 minutes)

BOP Reports RCIC has tripped

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 16 of 25 Event Descriptions: 6, 7, 8 - Loss of FW/HP Feed, EOP Entry, Recirc B Trip Failure Time Position Applicants Actions or Behavior NRC NRC Note: With the ATC driving control rods with CRD, CRD Alternate Injection may not be a priority.

SRO Directs ATC to maintain level +50 to +100 with CRD Alternate Injection, EOP-SPI 4.1 NRC Note: CRD Alternate Injection steps 1 to 9.3 have been completed previously when EOP-SPI 1.3 (Control Rod Insertion) and EOP-SPI 2.3 (MSIV/ECCS Interlocks) were completed.

ATC Directs NLO to open the following valves:

CRD pumps Suction Filter Bypasss 1C11-F116/F117

Drive Water Fltr A Inlet Isolations 1C11-F020A/B

Drive Water Fltr A Outlet Isolations 1C11-F021A/B Starts 2nd CRD Pump by:

START CRD AUX OIL PUMP

VERIFY blue PERM light is energized.

START CRD PUMP Directs NLO to close Minimum flow Isolation Valves 1C11-F015A/B SRO Directs BOP to start:

Hydrogen igniters

Hydrogen analyzers BOP Performs the following:

Verifies ESW pump running

Verifies ECC pump running

Verifies Comb Bas H2 Anal Outlet Clg Valve open

Verifies Comb Bas H2 Anal Inlet Clg Valve open

Takes Comb Gas H2 Anal Sample Valve keylock switch to open

Verifies Mode & Function Selector is in Sample

Places the System Function SW in On

Directs field operator to complete H2 Analyzer startup

Takes Div 1 H2 Igniter control switch to On

Takes Div 2 H2 Igniter control switch to On

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 17 of 25 Event

Description:

9 - Bypass #1 Fails Open Time Position Applicants Actions or Behavior NRC NRC Note: If reactor level is near zero inches, and an Emergency Depressurization is expected, the below actions may not be taken.

ATC Reports Reactor Pressure and lowering.

BOP Reports # 1 Bypass Valve has failed open.

SRO Directs BOP to close the MSIVs if Rx pressure is low out of band BOP Closes the MSIVs.

SRO Directs BOP to maintain Reactor Pressure 800-1000 psig using SRVs in sequence listed on P601.

BOP Opens SRVs in tagged numbered sequence (1 to 5) to maintain 800-1000 psig.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 18 of 25 Event

Description:

10 - Emergency Depressurization Time Position Applicants Actions or Behavior SRO At or below 0 determines level can not be restored and maintained above -25 directs BOP:

Terminate and Prevent ECCS and Feedwater for depressurization

Verify Suppression Pool is above 5.25 ft BOP Terminates and Prevents ECCS (Critical Task 3)

Verifies that ECCS is terminated and prevented NRC NRC Note: Terminate and Prevent ECCS (T&P) for depressurization was accomplished during T&P for level reduction.

Note: The critical portion of Terminate and Prevent ECCS is that is was accomplished (not verified) as part of either Level Control or Depressurization.

BOP Terminates and Prevents Feedwater for Depressurization (Critical Task 3)

VERIFY the following valves are CLOSED:

o HEATER 6A and 6B FDW BYPASS VALVE 1N27-F135 o HEATER 6A FDW OUTLET VALVE 1N27-F130A o HEATER 6B FDW OUTLET VALVE 1N27-F130B

VERIFY LOW FLOW CONTROLLER MANUAL/AUTO station in MANUAL 1N27-F175

ADJUST LOW FLOW CONTROLLER MANUAL/AUTO station output to 0% output 1N27-F175

VERIFY LOW FLOW RX LEVEL CONTROL VALVE is CLOSED 1N27-F175 BOP Reports

Feedwater Terminated and Prevented has been completed

ECCS Terminated and Prevented has been verified

Suppression Pool is above 5.25 ft SRO Directs BOP to open 8 ADS valves (Critical Task 4)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 19 of 25 Event

Description:

10 - Emergency Depressurization Time Position Applicants Actions or Behavior BOP Opens and reports 8 ADS valves are open (Critical Task 4)

SRO At 140 psig Reactor Pressure, directs BOP to slowly inject with Reactor Feed Booster Pumps/ECCS restore/maintain level ABOVE -25. (Critical Task 5)

BOP Starts, injects and maintains level ABOVE -25 with Reactor Feed Booster Pumps/ECCS. (Critical Task 5)

NRC NRC Note: If all rods are inserted, the SRO will transition to EOP-1. It that occurs the Emergency Depressurization will still occur because level can not be maintained greater than -25 and Critical Task 5 will become:

With RPV pressure below the Shutoff Head of the available Low Pressure system(s), operate available Low Pressure system(s) to restore RPV water level above T.A.F. (0 inches).

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 20 of 25 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. Reactor depressurized to less than or equal to 140 psig.

2. Injects to maintain level between -25 and +100.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 21 of 25 Event

Description:

Critical Task #1 Time Position Applicants Actions or Behavior With a reactor scram required and the reactor not shutdown, initiate action to reduce power by inserting control rods.

1. Safety Significance:

Shutting down reactor can preclude failure of containment or equipment necessary for the safe shutdown of the plant.

2. Cues:

Procedural compliance.

3. Measured by:

Control Rod insertion commenced in accordance with Section 1.0 of EOP-SPIs.

4. Feedback:

Reactor Power trend.

Control Rod indications.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 22 of 25 Event

Description:

Critical Task #2 Time Position Applicants Actions or Behavior With reactor scram required and the reactor not shutdown, to prevent an uncontrolled RPV depressurization and subsequent power excursion, inhibit ADS.

1. Safety Significance:

Precludes core damage due to an uncontrolled reactivity addition.

2. Cues:

Procedural compliance.

3. Measured by:

ADS logic inhibited prior to an automatic initiation unless all required injection systems are Terminated and Prevented.

4. Feedback:

RPV pressure trend.

RPV level trend.

ADS "ADS OUT OF SERVICE" annunciator status.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 23 of 25 Event

Description:

Critical Task #3 Time Position Applicants Actions or Behavior During an ATWS, when conditions when conditions are met to deliberately lower level: Terminate and Prevent RPV injection from ECCS and Feedwater until conditions are met to reestablish injection.

1. Safety Significance:

Prevention of fuel damage due to uncontrolled feeding.

2. Cues:

Procedural compliance.

3. Measured by:

Observation - With Emergency Depressurization not required and the deliberate lowering level override met (>4% power and >100" RPV level) injection systems are terminated and prevented until < 100" RPV level.

4. Feedback:

Reactor power trend, power spikes, reactor short period alarms.

Injection system flow rates into RPV.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 24 of 25 Event

Description:

Critical Task #4 Time Position Applicants Actions or Behavior After RPV water level drops to 0 inches, when RPV level cannot be restored and maintained above MSCRWL (-25"), RO initiates Emergency Depressurization as directed by US.

1. Safety Significance:

Maintaining adequate core cooling.

2. Cues:

Procedural compliance.

RPV level indication.

3. Measured by:

At least 5 SRV's are opened when RPV level cannot be restored and maintained above -25".

4. Feedback:

RPV pressure trend.

Suppression Pool temperature trend.

SRV open status indication.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 1 - 100% Page 25 of 25 Event

Description:

Critical Task #5 Time Position Applicants Actions or Behavior With RPV pressure <MSCP, slowly increase and control injection into RPV to restore and maintain RPV level above MSCRWL (-25") as directed by US.

1. Safety Significance:

Maintaining adequate core cooling and preclude possibility of large power excursions.

2. Cues:

Procedural compliance.

RPV pressure indication.

3. Measured by:

Observation - Injection not commenced until less than MSCP, and injection controlled such that power spikes are minimized, level restored and maintained greater than or equal to -25".

4. Feedback:

RPV level trend.

RPV pressure trend.

Injection system flow rate into RPV.

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 2 - 92% Op-Test No.: 2010-01 Examiners: Operators:

Initial Conditions: Reactor Power 92%. BOL Pull Sheets, Rods @ Step 64, Gang 48, at Position 48.

Power ascension is in progress. IOI-3 Step 4.5.34.

B CRD pump & C CBP in secured status and tagged out for oil leaks. Main Steam line radiation monitor B, D17-K610B is INOP. I&C has tripped the D17-K601B logic and opened the sliding link inputs into the annunciators. Rod 34-55 is inserted and disarmed.

ESW B running for vibration testing.

Green Risk Turnover: Shift RFBP B to A due to oil leak. The NLO has been briefed and is on station. Tagout is being prepared. When requested by Reactor Engineering, raise Power to 100% with Recirculation Flow.

Event Malf. No. Event Type* Event No. Description 1 N-BOP Shift RFBP BA 2 IN03 R-ATC RFPT A - high vibrations - Lower power 7% with flow 1H13P6803AC6 N-SRO 3 FW66 C-ATC/SRO RFPT A trips - ONI-C34 & ONI-C51 4 bs02_e12n0662a SRO Containment Spray containment pressure transmitter fails up -

Tech Spec 3.3.6.2 5 pt01_1d17n0003b C-BOP/SRO D17-K610C fails causing isolation signal to B33-F019.

pt01_1d17n0003c B33-F019 - fails to auto close av04_1b33f0019 SRO Tech Spec 3.6.1.3 6 Schedule file N/A Earthquake - ONI-D51 7 RD13A BOP /SRO CRD suction filter clogging - shift suction filters or pump trips 8 ZD1E51AS37ARM M-All Inadvertent RCIC initiation RFPTs & MT trip ZD1E51AS37INI 9 cb03_1n5141mcs C-ATC/SRO Gen field breaker fails to auto open on turbine trip 10 Schedule file M-All Loss of level indication - Go to RPV FLOOD ED 11 rv04_1b21f0041e C-BOP/SRO ADS-SRV B21F041E fails closed 12 All Inject to Recover Level Above Main Steam Lines

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

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 2 of 23 Event

Description:

Simulator Setup Time Position Applicants Actions or Behavior Driver Driver Simulator Setup:

Reset Simulator to IC 156 Load Schedule _NRC-02-92pct.sch Load Schedule _NRC_Info.sch Load Event _NRC_Exam-02-92pct.evt Driver Driver Verify Initial Conditions:

Reactor Power 92%. BOL Shutdown Pull Sheets, Rods @ Step 64, Gang 48, at Position 48.

Power ascension is in progress. IOI-3 Step 4.5.34. (Provide marked up copy)

Place yellow switch caps on B CRD pump and CRD Oil Pimp & C CBP (in secured status and tagged out for oil leaks).

Control Rod 34-55 is inserted and disarmed ESW B running for vibration testing.

Green Risk Verify position of cue card for P629 trip unit Driver Driver Turnover:

Shift RFBP B to A due to oil leak. The NLO has been briefed and is on station.

Tagout is being prepared. When requested by Reactor Engineering, raise Power to 100% with Recirculation Flow.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 3 of 23 Event

Description:

1 - RFBP Shift Time Position Applicants Actions or Behavior SRO Directs BOP to shift RFBP B to A IAW SOI-N27, section 7.3, Shifting Reactor Feedwater Booster Pumps BOP 7.3.1 VERIFY seal water flow to the oncoming RFBP is greater than 4 gpm at local flow indicator.

Driver Driver When an NLO is sent to check A RFBP seal water, inform the operator that it is 5 gpm and oil levels are SAT. If asked to do a walkdown, report suction & discharge valves are open and oil level is normal.

BOP 7.3.2 VERIFY the oncoming RFBP DISCH VALVE is open. 1N27-F050A 7.3.3 TAKE the oncoming RFBP to START. 1N27-C001A 7.3.4.a PLACE the offgoing RFBP to OFF. 1N27-C001B 7.3.4.c IF the offgoing pump is to be secured, THEN TAKE the offgoing RFBP DISCH VALVE to CLOSE.1N27-F050B NRC NRC Note: Pump may be left in standby if the crew waits for the tagout to be prepared and delivered.

7.3.8 THROTTLE all un-isolated RFBP Seal Cooling Water Supply Valves as necessary to achieve 4 to 5 gpm flow.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 4 of 23 Event

Description:

1 - RFBP Shift Time Position Applicants Actions or Behavior Driver Driver When an NLO is sent to adjust seal water flows, inform the operator that all pumps are within the 4-5 gpm band.

Driver Driver When RFBP shift is complete or directed by Chief Examiner, proceed to next event (insert Trigger 1, RFT A Pump Vib N27-R421.) (Event 2)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 5 of 23 Event

Description:

2 - RFPT A High Vibrations, Lower Power 7%

Time Position Applicants Actions or Behavior Driver Driver When RFBP shift is complete or directed by Chief Examiner, insert Trigger 1, RFT A Pump Vib N27-R421. (Event 2)

BOP Responds to annunciators

RFPT A VIB/TEMP P823

RFP A VIB HI Performs RFP A VIB HI ARI actions:

4.1 REFER TO SOI-C34 and CHANGE RFPT A speed to reduce vibration.

4.2 MONITOR RFP A vibration.

4.3 IF RFP A vibration increases to >4 mils for >3 minutes, THEN PERFORM the following: Trip RFPT A.

4.4 REFER TO SOI-N27 and VERIFY the following parameters are proper:

Bearing temperature

Bearing oil flows

Seal injection flow

RFP A NPSH

Feedwater flow 4.5 IF vibration persists, THEN PERFORM the following:

4.5.1 DISPATCH an operator to the RFP to evaluate for abnormal conditions.

4.5.2 REDUCE reactor power UNTIL RFP A is NOT required for feedwater.

Driver Driver When an NLO is sent to check on RFPT A inform the operator that you hear a bearing noise but all other parameters are normal (temperatures, flows and NPSH).

You will continue to monitor, but suggest that the control room lowers load on the FP turbine to see of noise goes away. Failure is not eminent.

SRO Directs power reduction to approximately 85% IAW IOI-3, Attachment 3, Power Maneuvering.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 6 of 23 Event

Description:

2 - RFPT A High Vibrations, Lower Power 7%

Time Position Applicants Actions or Behavior NRC NRC Note: If the SRO directs lowering of speed per the SOI, as the Shift Manager, direct the SRO to lower speed through lowering power to 85% per IOI-3.

Note: The lowering of power to 85% puts feedwater within the capability of one RFPT and the MFP.

NRC/ NRC/ NOTE: If the SRO directs tripping the RFPT or the RO trips the RFPT, then request SM SM an additional 5% power reduction after plant stabilizes ATC Reduces power using Recirc A and B FCVs.

NRC NRC Note: SRO may directs entry into ONI-C51, Unplanned Change In Reactor Power Or Reactivity

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 7 of 23 Event

Description:

3 - RFPT A Trip Time Position Applicants Actions or Behavior Driver Driver At approximately 87% power, or when directed by Chief Examiner, insert Trigger 5, RFP A Vibration Increase.

ATC

Acknowledges re-alarm of RFP A VIB HI alarm and notifies US that it is now reading greater than 4 mils.

Informs RFPT that if >4 mils for 3 minutes, the RFPT must be tripped.

Driver Driver After the RFP A VIB HI alarm is acknowledged, call as the local operator and inform the crew that the bearing noise has gotten much worse.

SRO Directs ATC to:

Monitor for 3 minute trip requirement

Continue reducing power to 85%

At 85% power start the MFP IAW SOI-C34.

NRC NRC Note: It is expected that the 3 minutes will elapse and the operator will manually trip the RFPT. However, if not manually tripped it will be tripped by the simulator driver.

Driver Driver If the MFP is manually started OR if RFPT A is manually tripped, insert Trigger 2, RFT A Local Manual Trip (FW66). If operator does not trip the RFPT within 3 minutes, insert Trigger 2.

Note: Besides tripping the RFPT this trigger will return the vibration readings to normal.

ATC Informs the US of:

Trip of RFPT A

Auto (Manual) Start of the MFP

Recirc runback

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 8 of 23 Event

Description:

3 - RFPT A Trip Time Position Applicants Actions or Behavior SRO Directs entry into:

ONI-C34 - Feedwater Flow Malfunction

ONI-C51 - Unplanned Change In Reactor Power Or Reactivity Directs BOP to perform ONI-SPI G4 - Power Verification SRO Directs ATC to monitor for power oscillations and scram the reactor if oscillations are observed.

ATC Monitors neutron monitoring systems: APRMs, LPRMs and SRM period.

SRO IAW ONI-C34 supplemental actions, directs ATC to shutdown RFPT A IAW SOI-C34 Reactor Feed Pump Shutdown from 1100 rpm.

SRO May direct ATC to reset FCV runback.

ATC If directed, resets FCV runback IAW SOI-B33, section 7.22 Resetting RCIRC Flow Control Cavitation Runback

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 9 of 23 Event

Description:

4 - Containment Spray Pressure Transmitter Failure Time Position Applicants Actions or Behavior Driver Driver At predetermined time or when directed by Chief Examiner, insert Trigger 10 (bs02_e12n0662a). (Event 4)

Driver Driver Wait at back table for RO to lead you to P629 then display cue card or give verbal cue E12N0662A, inform him that it is pegged high and the gross fail light is on BOP Responds to H13-P601 alarm:

CONTAINMENT PRESS A HIGH Notifies US, monitors Containment Temperature, checks back-panel indications BOP Informs US that E12-N662A is pegged upscale SRO Refers to Tech Specs and determines instrument E12-N662A is Inop IAW Tech Spec 3.3.6.2 and is a potential LCO.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 10 of 23 Event

Description:

5 - Failure of MSL Rad Monitors and closure of B33-F019 Time Position Applicants Actions or Behavior Driver Driver At predetermined time or when directed by Chief Examiner, insert Trigger 3 (1D17N0003B/C), Main Steam Line Monitor C Failure. (Event 5)

BOP Responds to MAIN STEAM LINE RADIATION HIGH annunciator.

BOP

Attempts to close B33-F019

Reports to US o Failure of B33-F019 to close o MSL Rad Monitor C has failed upscale Driver Driver Wait at back table for RO to lead you to MSL Rad Monitor C, then inform him that MSL Rad Monitor C is upscale HI and the Upscale Alarm Light is ON.

SRO Determines Tech Spec 3.6.1.3, Condition A is met

Isolate the affected penetration flow path by use of at least one closed and deactivated automatic valve within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

NRC NRC Note: The MSL Rad signal is NOT required, per TS and ORM, to shut the F019.

However, when the F019 fails to close by manual closure, the valve/penetration should be declared inoperable IAW TS 3.6.1.3.

SRO Directs BOP to close B33-F020 valve BOP Closes the B33-F020 valve.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 11 of 23 Event

Description:

6 - Earthquake Time Position Applicants Actions or Behavior Driver Driver

At predetermined time or when directed by Chief Examiner, insert Trigger 6 (EarthQuakeAlert.sch) for an Earthquake. (Event 6)

As a field operator, call the Control Room to report you felt and earthquake.

ATC Responds to annunciators:

RFP A VIB HI

RFP B VIB HI

RCIRC A MOTOR VIB HI

RCIRC B MOTOR VIB HI

SEISMIC ALARM P969

SEISMIC MONITOR TRBL Informs US.

SRO Directs the following:

Entry into ONI-D51 EARTHQUAKE

BOP to check 1H13-P969 for seismic indications

Shift Manager to check for EALs

ATC to check for alarms/indications of plant damage BOP Checks 1H13-P969 for indications of seismic event Informs the US that there are amber and red indicator lights on 1H13-P969.

NRC NRC Note: The amber lights indicate a 2/3 OBE and the red lights indicate an OBE or greater.

SRO Directs crew to perform a normal shutdown IAW IOI-3, Power Changes and IOI-4, Shutdown.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 12 of 23 Event

Description:

7 - CRD Suction Filter Clogging Time Position Applicants Actions or Behavior NRC NRC Note: CRD suction filter clogging is determined by simulator computer.

BOP Responds to annunciator CRD PUMP SUCTION FILTER DIFF PRESS HI Informs the US.

SRO Directs BOP to send NLO to investigate and shift CRD pump suction filters IAW SOI-C11 (CRDH).

BOP Sends NLO out to investigate and shift CRD pump suction filters IAW SOI-C11 (CRDH).

Driver Driver When directed to the CRD pumps, inform the RO that P is 8.2 psid and rising.

When directed to shift CRD pump suction filters, delete Malfunction RD13A to indicate filters are shifted. Call the Control Room, report the shift and P is now 2.2 psid.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 13 of 23 Event

Description:

8 & 9 - Inadvertent RCIC Initiation & Gen Field Brk Fails to Open Time Position Applicants Actions or Behavior Driver Driver At predetermined time or when directed by Chief Examiner, insert Trigger 8 (Event 8) (ZD1E51AS37ARM/INI) for inadvertent RCIC initiation.

Crew Recognize Turbine Trip and Reactor Scram ATC Performs SCRAM Hardcard actions Verify the following actions completed:

Mode Switch Locked in Shutdown.

RPS Initiated if all control rods are not fully inserted.

ARI Initiated if RPS failed to Scram the reactor.

If Reactor Recirc Pumps are running in fast speed:

Then simultaneously take the following to XFER:

RECIRC PUMP A BRKR 5A

RECIRC PUMP B BRKR 5B If Reactor power is above 4% then start SLC A and SLC B pumps.

ATC Perform crew update with the following information:

The Mode Switch is locked in shutdown

All Control Rods are inserted

Reactor Power is _______________

Reactor Pressure is _______________

Reactor Level is _______________

Reactor Recirc Pumps are running in slow speed

EOP-01 entry (only if condition met)

NRC NRC Note: EOP-01 entry would be required if the Turbine trip causes a high reactor pressure (1065 psig). The entry into EOP-1 is expected as part of Event 9, Loss of Level Indication.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 14 of 23 Event

Description:

8 & 9 - Inadvertent RCIC Initiation & Gen Field Brk Fails to Open Time Position Applicants Actions or Behavior ATC When generator load less than 90 MWe, then perform the following:

Trip the main turbine

Verify Main Stop valves, Control valves and CIVs are shut

Verify Gen BRKRs S-610-PY-TIE and S-611-PY-TIE are open

Verify Gen Field Breaker open ATC Informs US that Generator Field Breaker had to be manually opened.

ATC Insert Nuclear Instruments,

SRMs

IRMs

Place recorders in IRM (leave A or E in APRM)

ATC VERIFY HST LVL CV MANUAL CONTROL, N21-S19, IN OFF ATC STABLIZE reactor water level.

a) Feedwater (REFER TO FEEDWATER HARDCARD)

When level is > 178

Verify MFP is running

Trip both RFPTs

Verfiy MFP FCV Man/Auto Station in Auto

Reset Setpoint Setdown

Verify Digital Feedwater in Single Element Control b) RCIC c) HPCS

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 15 of 23 Event

Description:

8 & 9 - Inadvertent RCIC Initiation & Gen Field Brk Fails to Open Time Position Applicants Actions or Behavior ATC STABLIZE reactor pressure:

a) Turbine / Turbine Bypass valves (REFER TO REACTOR SCRAM PRESSURE CONTROL HARDCARD)

Verify Turbine Bypass Valves properly adjusted

If RCIC is running and is NOT needed for level control, then trip the RCIC turbine.

b) SRVs

Evacuate Containment

REFER TO PRESSURE CONTROL HARDCARD

Evaluate placing RCIC in pressure Control Mode

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 16 of 23 Event

Description:

10 & 11 - Loss of Level Indication and ED Time Position Applicants Actions or Behavior Driver Driver

If Mode Switch not placed in Shutdown, manually insert Trigger 9

(_NRC_LossLevel.sch) for loss of level indication.

Verify Trigger 9 automatically initiates when RO places the Mode Switch to SHUTDOWN.

NRC NRC Note: All level indications are sequentially lost over several minutes.

Crew Recognize that there is no valid level indication.

SRO Directs entry into EOP-01 and for the:

ATC to stabilize level and pressure with bands of 179-219

ATC to stabilize pressure with bands of 800-1000 psig

BOP to verify isolations and actuations SRO Directs entry and actions of EOP-04-4 Directs BOP to open 8 ADS Valves (Critical Task 1)

BOP Attempts to open 8 ADS Valves, reports 1 valve did not open (Critical Task 1)

SRO Directs BOP to open additional SRVs until 8 SRVs are open BOP Opens an additional SRV and reports 8 SRVs are open.

SRO Directs BOP to isolate: (Critical Task 2)

MSIVs

MS Line Drains

RCIC Steam Isolations

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 17 of 23 Event

Description:

10 & 11 - Loss of Level Indication and ED Time Position Applicants Actions or Behavior BOP Isolates: (Critical Task 2)

MSIVs

MS Line Drains

RCIC Steam Isolations SRO Directs BOP to start:

Hydrogen igniters

Hydrogen analyzers BOP Performs the following:

Verifies ESW pump running

Verifies ECC pump running

Verifies Comb Bas H2 Anal Outlet Clg Valve open

Verifies Comb Bas H2 Anal Inlet Clg Valve open

Takes Comb Gas H2 Anal Sample Valve keylock switch to open

Verifies Mode & Function Selector is in Sample

Places the System Function SW in On

Directs field operator to complete H2 Analyzer startup

Takes Div 1 H2 Igniter control switch to On

Takes Div 2 H2 Igniter control switch to On

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 18 of 23 Event

Description:

12 - Inject to recover level to above MSLs Time Position Applicants Actions or Behavior SRO SRO Directs ATC/BOP to:

Bypass HPCS L8 Trip IAW EP-SPI 2.4

Bypass MFP L8 Trip IAW EP-SPI 2.7 ATC/BOP Calls an operator to bypass HPCS & MFP L8 Trips Driver Driver When called to bypass the L8 trips, acknowledge the call. If called later about it, say you are working on it.

SRO Directs ATC to inject with RFBPs ATC Opens Feedwater Pump Bypass Valve, N27-F200 valve.

SRO Directs BOP/ATC to:

Inject with LPCS IAW EOP-SPI- 6.5

Inject with RHR IAW EOP-SPI-6.1, 6.2, 6.3

Inject with HPCS IAW EOP-SPI 6.4 BOP/ATC Performs the following for LPCS:

Verify LPCS Injection Valve is closed..

Verify ESW pump A is running.

Verify ECC pump A is running.

Verify LPCS pump is running.

Operate LPCS injection Vlv to full open

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 19 of 23 Event

Description:

12 - Inject to recover level to above MSLs Time Position Applicants Actions or Behavior BOP/ATC Performs the following for RHR A (B) (C):

Verify LPCI Injection Valve A (B) (C) is closed

Verify ESW Pump A (B) is running

Verify ECC Pump A (B) is running

Verify LPCI Pump A (B) (C) is running

Opens LPCI Injection Valve A (B) (C)

BOP/ATC Performs the following for HPCS:

IF the HPCS pump is NOT running, THEN VERIFY HPCS INJECTION VALVE is CLOSED. E22-C001 E22-F004

IF HPCS ESW PUMP is available, THEN VERIFY HPCS ESW PUMP is RUNNING. P45-C002

VERIFY HPCS PUMP is RUNNING. E22-C001

WHEN injection into the RPV using HPCS is desired, THEN PERFORM the following:

IF the Reactor is Shutdown, THEN OPERATE HPCS INJECTION VALVE.

All At least one injection system is injecting to recover level to above the MSL (Critical Task 3)

SRO

Enters EOP-2 on Suppression Pool Level or Temperature

Directs BOP to monitor for level above the MSL.

BOP Monitors for Suppression Pool level, with constant or rising RPV pressure:

Without injection from outside Containment level stabilizes

With injection from sources outside Containment Level slowly increases.

Notifies SRO when Suppression Pool level indicates level is above Main Steam Lines.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 20 of 23 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. Emergency Depressurization has been completed

2. At least one ECCS/RFBP is being used to inject and recover reactor water level.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 21 of 23 Event

Description:

Critical Task #1 Time Position Applicants Actions or Behavior With reactor scram required and the reactor not shutdown, to prevent an uncontrolled RPV depressurization and subsequent power excursion, inhibit ADS.

1. Safety Significance:

Precludes core damage due to an uncontrolled reactivity addition.

2. Cues:

Procedural compliance.

3. Measured by:

ADS logic inhibited prior to an automatic initiation unless all required injection systems are Terminated and Prevented.

4. Feedback:

RPV pressure trend.

RPV level trend.

ADS "ADS OUT OF SERVICE" annunciator status.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 22 of 23 Event

Description:

Critical Task #2 Time Position Applicants Actions or Behavior With RPV Flooding required and 2 or more SRV's open, manually isolate the MSIV's, MSL Drains and RCIC steam lines.

1. Safety Significance:

Take action to prevent degradation of barrier to fission product release.

2. Cues:

Procedural compliance.

Valve position indication shows valve open.

3. Measured by:

Observation - Valve 1B21-F016 control switch taken to close prior to completion of scenario.

4. Feedback:

RPV pressure trend.

Valve position indication.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2010-01 Scenario No.: 2 - 92% Page 23 of 23 Event

Description:

Critical Task #3 Time Position Applicants Actions or Behavior With reactor water level unknown, inject into RPV to establish RPV level above the Main steam Lines.

1. Safety Significance:

Prevent fuel damage by establishing and maintaining adequate core cooling.

2. Cues:

RPV water level unknown.

Procedural compliance.

3. Measured by:

Observation - RPV level established and controlled above the MSLs. (10 psig increase in RPV pressure with ADS SRV tailpipe temperatures decreasing).

4. Feedback:

RPV pressure indication.

SRV tail pipe temperature indication.

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 2a - 92% Op-Test No.: 2010-01 Examiners: Operators:

Initial Conditions: Reactor Power 92%. BOL Pull Sheets, Rods @ Step 64, Gang 48, at Position 48.

Power ascension is in progress. IOI-3 Step 4.5.34.

B CRD pump & C CBP in secured status and tagged out for oil leaks. Main Steam line radiation monitor B, D17-K610B is INOP. I&C has tripped the D17-K601B logic and opened the sliding link inputs into the annunciators. Rod 34-55 is inserted and disarmed.

ESW B running for vibration testing.

Green Risk Turnover: Shift RFBP B to A due to oil leak. The NLO has been briefed and is on station. Tagout is being prepared. When requested by Reactor Engineering, raise Power to 100% with Recirculation Flow.

Event Malf. No. Event Type* Event No. Description 1 N-BOP Shift RFBP BA 2 IN03 R-ATC RFPT A - high vibrations - Lower power 7% with flow 1H13P6803AC6 N-SRO 3 FW66 C-ATC/SRO RFPT A trips - ONI-C34 & ONI-C51 4 bs02_e12n0662a SRO Containment Spray containment pressure transmitter fails up -

Tech Spec 3.3.6.2 5 pt01_1d17n0003b C-BOP/SRO D17-K610C fails causing isolation signal to B33-F019. B33-F019 pt01_1d17n0003c - fails to auto close av04_1b33f0019 SRO Tech Spec 3.6.1.3 6 Schedule file N/A Earthquake - ONI-D51 7 RD13A BOP /SRO CRD suction filter clogging - shift suction filters or pump trips 8 ZD1E51AS37AR M-All Inadvertent RCIC initiation RFPTs & MT trip M

ZD1E51AS37INI 9 cb03_1n5141mcs C-ATC/SRO Gen field breaker fails to auto open on turbine trip 10 Schedule file M-All Loss of level indication - Go to RPV FLOOD ED 11 rv04_1b21f0041e C-BOP/SRO ADS-SRV B21F041E fails closed 12 All Inject to Recover Level Above Main Steam Lines

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