ML110200260

Final Operating Exam (Sections a, B, and C) (Folder 3)

ML110200260
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	11/01/2010
From:	Entergy Nuclear Operations
To:	D'Antonio J Operations Branch I
Hansell S
Shared Package
ML102070016	List: IR 05000271/2010301 ML102110017 ML103280164 ML110110502 ML110110512 ML110110519 ML110110525 ML110200243 ML110200247 ML110200254 ML110200260 ML110620439
References
TAC U01769, 50-271/10-301
Download: ML110200260 (245)

Text

NRC ..IPM-A1a RO Rev. FINAL Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Perform Control Room Panel Walkdowns (weekly surveillance)

Failure Mode: Incorrect switch positions

Reference:

OP 0150. "Conduct of Operations and Operator Rounds" Task Number: 2997230301 (Complete CRO Round Sheet)

Task Performance: AO/RO/SRO _ RO/SRO L SRO Only_

Sequence Critical: Yes Time Critical: Yes No X Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:----------------------------------

Date of Evaluation:

Activity Code: _______________________

Method of Testing: Simulation,____ Performance X Discuss.____

Setting: Classroom _ _ _ Simulator X Plant_ _

Performance Expected Completion Time: 15 minutes Evaluation Results:

Performance: PASS - - FAIL ---- Time Required: _ _ __

Prepared by: ____________________________________

NRC Exam Lead Developer Date Reviewed by:____________________________________

Operations Representative Date Approved by: ____________________________________

Facility Reviewer Date NRC JPM-Ala RO

NRC JPM-A1a RO Rev. FINAL Page 2 of 6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance ofthat step by circling either "SAT" or "UNSAT". Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant is operating at 100% RTP

• Surveillances have just been completed on "A" ECCS systems.

• "A" Core Spray System has been declared INOP for corrective maintenance following the surveillance.

Initiating Cues:

• You have been directed by the Control Room Supervisor to perform the applicable portions of VYOPF 0150.10 (Operations Department Control Room Panel Walkdown Checklist) lAW OP 0150, "Conduct of Operations and Operator Rounds". Section "F",

steps 1-3 and 5-8 will be used for the guidance to conduct the walkdowns.

Task Standards:

• VYOPF 0150.10 completed for the applicable portions on CRP 9-3; identification of 4 deficiencies noted and CRS informed.

NRC JPM-Ala RO

NRC JPM-A1a RO Rev. FINAL Page 3 of 6 Required Materials:

• OP 0150, "Conduct of Operations and Operator Rounds" section "F" placekept.

• VYOPF 0150.10 (CRP 9-3) with the non applicable portions annotated Simulator Set-Up:

• IC: 814

• RUN on scenario file NRC ..IPM RO a1 a

• Simulator setup with the following discrepancies:

o CRP 9-3, Danger tag hanging on CS pump "A" with the switch in PTL o CRP 9-3, MCC-89A Source Transfer switch not in NORM/UPS-1A position o CRP 9-3, RHR-25A (Inboard injection valve not open) o CRP 9-3, RHR-27A (Inboard injection valve not closed)

NRC lPM-Ala RO

NRC ...IPM-A1a RO Rev. FINAL Page 4 of 6 Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ __

Evaluation Performance Steps EVALUATOR NOTES:

SAT/UNSAT Step 1: Obtain OP 0150, "Conduct of Operations and Operator Rounds". and review section "F".

Standard: OP 0150 obtained and Section "F" reviewed.

SAT/UNSAT Step 2: Obtain copy of VYOPF 0150.10 and identifies the portions of the form that need to be walked down.

Standard: Operator obtains copy of form, identifies the applicable portions of 9-3 that are required to be walked down lAW section "F", step 9.

SAT/UNSAT *Step 3: Completes VYOPF 0150.10 for panel 9-3 Standard: Operator identifies the following abnormality/deficiencies:

o Operator identifies a danger tag on CS Pump "Au and documents the reason in the remarks section. This is done lAW OP 0150, Section "F", step 6.

EVALUATOR CUE: Inform the operator that the HPCI valves were incorrectly repositioned following the last HPCI surveillance. A CR has been written.

EVALUATOR CUE: Inform the operator that the HPCI valves will be swapped back after the walkdown is complete lAW OP 2120,Section I.

NRC JPM-Al a RO

NRC JPM-A1a RO Rev. FINAL Page 5 of 6 Evaluation Performance Steps SAT/UNSAT *Step 4: Completes VYOPF 0150.10 for panel 9-3 Standard: Operator identifies the following abnormality/deficiency:

o Operator identifies a danger tag on CS Pump itA" and documents the reason in the remarks section. This is done lAW OP 0150, Section "F", step 6.

SAT/UNSAT *Step 5: Completes VYOPF 0150.10 for panel 9-3 Standard: Operator identifies the following abnormality/deficiency:

o Operator identifies that the MCC-89A source transfer switch is not in the NORM/UPS-1A position and informs the CRS.

EVALUATOR CUE: When informed as the CRS, acknowledge and inform the operator that the discrepancy will be addressed and corrected for at the completion of the walkdown.

SAT/UNSAT *Step 6: Completes VYOPF 0150.10 for panel 9-3 Standard: Operator identifies the following abnormalities/deficiencies:

o Operator identifies that the RHR injection valves are incorrectly positioned. RHR-25A should be open and RHR-27A should be closed. Informs the CRS of the discrepancies.

EVALUATOR CUE: When informed as the CRS, acknowledge and inform the operator that the discrepancies will be addressed and corrected for at the completion of the walkdown.

NRC lPM-AlaRO

NRC "IPM-A 1a RO Rev. FINAL Page 6 of 6 Evaluation Performance Steps SAT/LINSAT *Step 5: VYOPF 0150.10 is completed in accordance with the standards outlined in section "F".

Standards:

• Switch positions that differ from the normal position identified on VYOPF 0150.10 due to Tagouts should be noted in the remarks section.

• If abnormal switch and/or indications are detected which are not expected the CR8 / 8M shall be immediately notified.

• No attempt shall be made to correct the condition prior to obtaining permission from the CRS/SM and the expected response from such actions is completely understood.

• Critical Step TIME FINISH: _ _ __

Terminating Cue: Once the operator completes the applicable panel walkdowns defined on VYOPF 0150.10 for CRP 9-3, the JPM can be terminated.

NRC lPM-Ala RO

NRC ..IPM-A 1a RO Rev. FINAL Page 7 of6 Evaluator Comments:

System Generic KlA's: 2.1.31 Ability to locate control room switches, controls, and indications and to determine that they correctly reflect the desired plant lineup (RO 4.6, SRO 4.3)

NRC JPM-Ala RO

EXAMINEE HANDOUT Initial Conditions:

• The plant is operating at 100% RTP

• Surveillances have just been completed on "A" ECCS systems.

• "A" Core Spray System has been declared INOP for corrective maintenance following the surveillance.

Initiating Cues:

• You have been directed by the Control Room Supervisor to perform the applicable portions of VYOPF 0150.10 (Operations Department Control Room Panel Walkdown Checklist) lAW OP 0150, "Conduct of Operations and Operator Rounds". Section "F",

steps 1-3 and 5-8 will be used for the guidance to conduct the walkdowns.

NRC JPM-A1b RO Rev. FINAL Page 1 of 8 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Record Critical Data Failure Mode: Not applicable

Reference:

OP 0105, "Reactor Operations" Task Number: 2987240201 (Startup Reactor to Criticality)

Task Performance: AO/RO/SRO _ RO/SRO l SRO Only Sequence Critical: Yes No -1S Time Critical: Yes Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date of Evaluation: _ _ _ _ _ _ _ _ _ __

Activity Code: _ _ _ _ _ _ _ _ _ _ __

Method of Testing: Simulation___ Performance X Discuss_ _

Setting: Classroom _ _ _ Simulator X Plant,_ _

Performance Expected Completion Time: 10 minutes Evaluation Results:

Performance: PASS - - FAIL - - - Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Alb RO

NRC ..IPM-A1b RO Rev. FINAL Page 2 of 8 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "SAT" or "UNSAT".

Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk through" the JPM, stating the indications/parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• A reactor Startup and rod withdraw to criticality is in progress lAW OP 0105, Phase 1A, "Reactor Operations" Initiating Cues:

• The Operator at the Controls has just reported to the Control Room Supervisor (CRS) that the reactor is critical.

• The CRS directs you to record the parameters on VYOPF 0105.03 and calculate the stable period lAW OP 0105 Phase 1A, step 28.

• An additional operator is provided to range IRMs as necessary.

• Complete the VYOPF 0105.03 form and forward it to the SM for review.

Task Standards:

VYOPF 0105.03 data collected and documented satisfactorily, form initialed/dated and forwarded to the Shift Manager for review.

NRC lPM-Alb RO

NRC JPM-A1b RO Rev. FINAL Page 3 of 8 Required Materials:

• OP 0105, "Reactor Operations", placekept through Phase 1A, step 27.

• VYOPF 0105.03 completed through "Doubling Count Rates"

• Stop watch

• Calculator Simulator Set-Up:

• Simulator setup with a critical reactor. Simulator is taken to freeze until the operator to take critical data lAW OP 0105, Phase 1A, step 28.

• Audio alarms silenced

• An additional Simulator operator responsible for ranging IRMs to maintain 25/75 scale.

• Ie: 815 NRC JPM-AI b RO

NRC JPM-A1b RO Rev. FINAL Page 4 of 8 Provide operator with Initial Conditions/Cue (Last Page of this ..tPM).

TIME START: _ _ __

Evaluation Performance Steps EVALUATOR NOTES:

• If asked, inform the operator that their sole function is to record data. The other responsibilities of OP 0105 will be addressed by the rest of the crew.

• There is no particular order to the data taken on VYOPF 0105.03. The sequence provided on this JPM worksheet is the layout as it exists on the form. They can be done in any order.

SAT/UNSAT Step 1: Obtain VYOPF 0105.03. "Reactor Criticality Check Sheet, Regular and In-Sequence".

Standard: Obtains VYOPF 0105.03 from the Operator at the Controls.

SAT/U NSAT *Step 2: Records Time at criticality Standard: Documents current time on VYOPF 0105.03.

SAT/UNSAT *Step 3: Records Rod Sequence from the Rod Worth Minimizer at criticality.

Standard: Documents "A2" Rod Sequence on VYOPF 0105.03.

, SAT/UNSAT *Step 4: Records Rod Group from the Rod Worth Minimizer at criticality Standard: Documents Rod Group 2 on VYOPF 0105.03.

NRC JPM-Alb RO

NRC JPM-A1b RO Rev. FINAL Page 5 of 8 Evaluation Performance Steps SAT/UNSAT *Step 5: Records Rod Number from the Rod Worth Minimizer. ERFIS screen. or CRP 9-5 full core display at criticality Standard: Documents Rod Number 18-23 on VYOPF 0105.03.

SAT/UNSAT *Step 6: Records Rod Position from the Rod Worth Minimizer, ERFIS screen, or CRP 9-5 full core display at criticality Standard: Documents Rod Position 24 on VYOPF 0105.03.

SAT/UNSAT *Step 7: Records B023 "Temperature" from ERFIS screen Standard: Documents B023 Temperature 151°F on VYOPF 0105.03.

SAT/UNSAT *Step 8: Records B025 "Reactor Pressure" from ERFIS screen Standard: Documents B025 Pressure 0 psig on VYOPF 0105.03.

SAT/LINSAT *Step 9: Records "A" loop Temperature from TR 2-165 (Red) on CRP Standard: Documents TR 2-165 (Red) Temperature -155°F on VYOPF 0105.03.

SAT/LI NSAT *Step 10: Records "B" Loop Temperature from TR 2-165 (Blue) on CRP 9-4.

Standard: Documents TR 2-165 (Blue) Temperature -152°F on VYOPF 0105.03.

NRC JPM-Alb RO

NRC JPM-A1b RO Rev. FINAL Page 6 of 8 Evaluation Performance Steps SAT/UNSAT *Step 11: Records Reactor Vessel Flange Temperature from TR 2-3-90 (Red) on CRP 9-4.

Standard: Documents TR 2-3-90 (Red) Temperature -155°F on VYOPF 0105.03.

SAT/UNSAT *Step 12: Records Reactor Water Cleanup Inlet Temperature from TI 12-137 on CRP 9-4.

Standard: Documents T112-137 Temperature -145°F on VYOPF 0105.03.

SAT/UNSAT *Step 13: Calculates Stable Period by applying Note 1 on VYOPF 0105.03.

Standard: Documents Stable Period by multiplying time for power to double by 1.445. (based on the time of their calculation and when count rates have doubled)

EVALUATOR NOTE: The candidate may use a couple methods to determine the SRM count rate (ERFIS display, SRM recorder)

EVALUATOR NOTE: Evaluator documents SRM count rate and time to determine if candidates calculation was perfomrd satisfactorily.

Initial SRM count/time: _ _ _ _/:...._ __

Final SRM count/time: 1 SAT/U NSAT *Step 14: Records C121 ERFIS Period from ERFIS screen.

Standard: Documents C121 ERFIS Period on VYOPF 0105.03. (as indicated based on when they observe the period)

NRC JPM-Alb RO

NRC ..IPM-A1b RO Rev. FINAL Page 7 of 8 Evaluation Performance Steps SAT/UNSAT *Step 15: Records Reactor Pressure from PR-6-96 on CRP 9-5.

Standard: Documents PR-6-96 pressure 0 psig on VYOPF 0105.03.

SAT/UNSAT Step 16: Initials and Dates the completed VYOPF 0105.03.

Standard: Records his/her initials and current date on VYOPF 0105.03.

• Critical Step TIME FINISH: _ _ __

Terminating Cue: Operator completes and looks to forward the completed VYOPF 0105.03 form to the S~lift Manager.

NRC JPM-Alb RO

NRC JPM-A1b RO Rev. FINAL Page 8 of 8 Evaluator Comments:

System Generic KIA's: 2.1.20 Ability to interpret and execute procedure steps (RO 4.6, SRO 4.6)

NRC JPM-Alb RO

EXAMINEE HANDOUT Initial Conditions:

• A reactor Startup and rod withdraw to criticality is in progress lAW OP 0105, Phase 1A, "Reactor Operations" Initiating Cues:

• The Operator at the Controls has just reported to the Control Room Supervisor (CRS) that the reactor is critical.

• The CRS directs you to record the parameters on VYOPF 0105.03 and calculate the stable period lAW OP 0105 Phase 1A, step 28.

• An additional operator is provided to range IRMs as necessary

• Complete the VYOPF 0105.03 form and forward it to the SM for review NRC JPM-Alb RO

NRCJPM-A2 RO Rev. FINAL Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Interpret station Electrical/Mechanical Drawings Failure Mode: Not applicable

Reference:

EN-OP-102, Attachment 9.2 Task Number: FQC-OPS-TOPOSIT (Knowledge of Work Boundaries)

Task Performance: AO/RO/SRO _ RO/SRO l SRO Only_

Sequence Critical: Yes l No Time Critical: Yes No X Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:

Date of Evaluation:

Activity Code: _ _ _ _ _ _ _ _ _ _ __

Method of Testing: Simulation______ Performance X Discuss_ _

Setting: Classroom X Simulator- - - Plant- - -

Performance Expected Completion Time: 22 minutes Evaluation Results:

Performance: PASS _ _ FAIL _ __ Time Required: _____

Prepared by: _______________________________

NRC Exam Lead Developer Date Reviewed by:_______________________________________

Operations Representative Date Approved by: _________________________

Facility Reviewer Date NRC JPM-A2 RO

NRCJPM-A2 RO Rev. FINAL Page 2 of 7 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "SAT" or "UNSAT".

Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the classroom and you are to perform the actions.

You are requested to "talk through" the JPM, stating the indications/parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant is operating at 100% RTP.

• The Control Room has removed the "A" RBCCW pump from service due to a seal failure.

Initiating Cues:

• Using Station mechanical and/or electric drawings, to determine which components are required to be danger tagged for the seal replacement.

• List ALL required components in the correct sequence AND in the correct position as required by EN-OP-102, "Protective and Caution Tagging", Attachment 9.2

• Fill in the table on Examinee handout Task Standards:

• The operator determines the following components are required to be danger tagged and lists them in the required tagging sequence. (critical steps and sequence is BOLDED)

• "A" RBCCW pump control switch on CRP 9-6 (SW-9-6-19) PTL

• Bus 9, cubicle 5B (P59-1A pump breaker) OPEN

• V70-94A (pump discharge valve) CLOSED

• V70-96A (pump suction valve) CLOSED

• V70-923 (PI-2A isolation valve on pump discharge line) OPEN

• V70-600 (pump casing vent valve) OPEN

• V70-924 (PI-2A drain valve on pump discharge line) OPEN NRC JPM-A2 RO

NRCJPM-A2 RO Rev. FINAL Page 3 of 7 Required Materials:

• EN-OP-102, "Protective and Caution Tagging", Attachment 9.2

• P&ID G-191159 Sheet 3 (mechanical)

• P&ID G-191301 Sheet 1 (electrical)

• CWD Sheet 442 Simulator Set-Up:

• N/A NRC JPM-A2 RO

NRCJPM-A2 RO Rev. FINAL Page 4 of 7 Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ __

Evaluation Performance Steps EVALUATOR NOTE: The operator may elect to review the CWO for the "A" RWCU first prior to looking at the other electrical drawings.

SAT/UNSAT Step 1: Obtain EN-OP-102. "Protective and Caution Tagging" and reviews Attachment 9.2. "General Tagout Standards" Standard: Obtains a copy of EN-OP-102, Attachment 9.2. When asked, provide a copy of EN-OP-1 02, "Protective and Caution Tagging.

The operator then reviews the procedure and Attachment 9.2.

EVALUATOR NOTE: When asked, provide the candidate with a copy of EN-OP-1 02 SAT/UNSAT Step 2: Operator identifies the tagging sequence outlined in EN-OP-Standard: Operator identifies the recommended tagging sequence for pumps as follows:

• Control switch

• Breaker for main power

• Breakers for auxiliary power (motor heater, oil pumps, etc.)

• Discharge valve

• Suction valve SAT/UNSAT *Step 3: Operator identifies the control switch for the "A" RBCCW pump on CWO Sheet 442 Standard: Operator identifies P59-1A control switch (SW-9-6-19) as the control switch for the "A" RBCCW pump on CWO 442.

Operator identifies the position that the switch will be tagged in (Pull to lock).

NRC JPM-A2 RO

NRCJPM-A2 RO Rev. FINAL Page 5 of 7 Evaluation Performance Steps SAT/UNSAT *Step 4: Operator identifies the breaker cubicle for the "A" RBCCW pump Standard: Operator identifies Bus 9, breaker cubicle 5B as the power supply for the "An RBCCW pump using CWO 442 and/or P&IO G-191301 Sheet 1.

Operator identifies the position that the breaker will be tagged (open/racked out)

SAT/UNSAT *Step 5: Operator identifies the discharge valve for the RBCCW pump Standard: Operator identifies valve V70-94A as the "A" RBCCW pump discharge valve using P&IO G-191159 Sheet 3.

Operator identifies the position that the valve will be tagged (closed)

SAT/UNSAT *Step 6: Operator identifies the suction valve for the RBCCW pump Standard: Operator identifies valve V70-96A as the "An RBCCW pump suction valve using P&IO G- G-191159 Sheet 3.

Operator identifies the position that the valve will be tagged (closed)

SAT/LINSAT Step 7: Operator identifies the PI isolation valve on the discharge of the "An RBCCW pump.

Standard: Operator identifies valve V70-923 as the PI-2A isolation valve on pump discharge line using P&IO G-191159 Sheet 3.

Operator identifies the position that the valve will be tagged (open)

NRC JPM-A2 RO

NRCJPM-A2 RO Rev. FINAL Page 6 of 7 Evaluation Performance Steps SAT/UNSAT Step 8: Operator identifies the pump casing vent valve for the "A" RBCCW pump.

Standard: Operator identifies valve V70-600 as the pump casing vent valve using P&ID G-191159 Sheet 3.

Operator identifies the position that the valve will be tagged (open)

SAT/UNSAT Step 9: Operator identifies the PI-2A drain valve on the pump discharge line pump casing vent valve for the "A" RBCCW pump.

Standard: Operator identifies valve V70-924 as the PI-2A drain valve on the pump discharge line using P&ID G-191159 Sheet 3.

Operator identifies the position that the valve will be tagged (open)

EVALUATOR CUE: Once the table is filled in, inform the Operator no additional tasks are needed for this JPM.

• Critical Step Terminating Cue: The JPM is complete TIME FINISH: _ _ __

NRC JPM-A2 RO

NRCJPM-A2 RO Rev. FINAL Page 7 of 7 Evaluator Comments:

System Generic KIA's: 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings (RO 3.5, SRO 3.9)

NRC JPM-A2 RO

EXAMINEE HANDOUT Initial Conditions:

• The plant is operating at 100% RTP.

• The Control Room has removed the "A" RBCCW pump from service due to a seal failure.

Initiating Cues:

• Using Station mechanical and/or electric drawings, to determine which components are required to be danger tagged for the seal replacement.

• List ALL required components in the correct sequence AND in the correct position as required by EN-OP-102, "Protective and Caution Tagging", Attachment 9.2

• Fill in the table on Examinee handout

NRC ..IPM-A4 RO Rev. FINAL Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Activate the Fire Brigade and Make Reguired Plant Announcements Failure Mode: N/A

Reference:

OP 3020, "Fire Emergency Response Procedure" Task Number: 2867290401,2850110101 Task Performance: AO/RO/SRO _ _ _ RO/SRO _ __ SRO Only X Sequence Critical: Yes No X Time Critical: Yes No X Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date of Evaluation: _ _ _ _ _ _ _ _ _ __

Activity Code: _ _ _ _ _ _ _ _ _ _ __

Method of Testing: Simulation___ Performance X Discuss_ _

Setting: Classroom X Simulator___ Plant:...-__

Performance Expected Completion Time: 6 minutes Evaluation Results:

Performance: PASS - - FAIL - - - Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-A4 RO

NRC ...IPM-A4 RO Rev. FINAL Page 2 of 7 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "SAT" or "UNSAT".

Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk through" the JPM, stating the indications/parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant is operating at 100% RTP Initiating Cues:

• The Control Room has just received Fire Alarms on Control Room Panel CP-115-3. The CRS has entered OP 3020, Fire Emergency Response Procedure, Figure 1 and has directed you to make ALL required announcements lAW Figure 1 based on the location of the fire.

Task Standards:

• Plant Announcement made in accordance with OP 3020 Figure 1 (Table A) and PSB/PUB announcement made in accordance with OP 3020 Figure 1 (Table B).

NRC JPM-A4 RO

NRC JPM-A4 RO Rev. FINAL Page 3 of 7 Required Materials:

• OP 3020 Figure 1; Figure 1 is placekept up to the plant announcement.

Simulator Set-Up:

• IC: 810 (100% power Ie)

• RUN on scenario file NRC JPM RO A4 o mfFP_01c "Active" (Fire in the East Switchgear Room). Also, ensure that Zone 27 indicating light is in alarm using soft panel if necessary)

NRC JPM-A4 RO

NRC ..IPM-A4 RO Rev. FINAL Page 4 of 7 Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ __

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain a copy of OP 3020, Figure 1 Standard: Operator obtains a copy of OP 3020 Figure 1.

EVALUATOR CUE: Provide the operator the flow chart that is placekept up to the point where a plant announcement is required to be made.

SAT/UNSAT Step 2: Recognizes that Zone 27, 28, 29 and 30 fire alarms are in the East Switchgear Room Standard: Operator recognizes that the Control Room Fire Protection Panel has Zone 27-30 alarms which correspond to a C02 discharge and detector fire alarm in the East Switchgear Room.

SAT/UNSAT *Step 3: Activates the paging system in preparation for plant announcement per Table "A" Standard: Operator places page system "Volume and Alarm Tone" select switch to "Alert" NRC lPM-A4 RO

NRC JPM-A4 RO Rev. FINAL Page 5 of 7 Evaluation Performance Steps SAT/UNSAT *Step 4: Make Plant Announcement Per Table "A" Standard: Operator makes the following announcement:

"Attention! Attention! Attention!"

"Fire! Fire! Fire!"

"There is a fire in the East Switchgear Room."

"Fire Brigade respond and assemble on the North Side of the Admin Building" "Medical Response Team report to the West side of the Admin Building" "All personnel evacuate the Switchgear Rooms, the Admin Building lower level, and Lobby due to a C02 discharge and report to the West side of the Admin Building."

EVALUATOR CUE: After the Table "A" announcement, inform the candidate that time progression has been used and the 5 man fire brigade team is assembled.

SAT/UNSAT Step 5: Deactivates the paging system Standard: Operator places page system "Volume and Alarm Tone" select switch to "Off' EVALUATOR NOTE: The following call will be simulated SAT/UNSAT *Step 6: Activate the PSB/PUB Office Paging System per Table "B" Standard: Operator dials x3999 and makes the following announcement on the office paging system.

NRC JPM-A4 RO

NRC JPM-A4 RO Rev. FINAL Page 6 of 7 Evaluation Performance Steps SAT/UNSAT *Step 7: Make PSB/PUB Announcement Per Table "B" Standard: Operator makes the following announcement:

"Attention! Attention! Attention!"

"Fire Emergency! Fire Emergency!"

"Medical Response Team report to the West side of the Admin Building" "Fire Emergency! Fire Emergency!"

"Medical Response Team report to the West side of the Admin Building"

• Critical Step TIME FINISH: _ _ __

Terminating Cue: Plant Announcement made in accordance with OP 3020 Figure 1 (Table A) and PSB/PUB announcement made in accordance with OP 3020 Figure 1 (Table B)

NRC lPM-A4 RO

NRC JPM-A4 RO Rev. FINAL Page 7 of 7 Evaluator Comments:

System Generic KIA's: 2.4.27 Knowledge of the "Fire in the Plant" procedures (RO 3.4, SRO 3.9)

NRC lPM-A4 RO

EXAMINEE HANDOUT Initial Conditions:

• The plant is operating at 100% RTP Initiating Cues:

• The Control Room has just received Fire Alarms on Control Room Panel CP-115-3. The CRS has entered OP 3020, Fire Emergency Response Procedure, Figure 1 and has directed you to make ALL required announcements lAW Figure 1 based on the location of the fire.

NRC .JPM-A1a SRO Rev. FINAL Page 1 of 8 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Determine License Reactivation Requirements Failure Mode: N/A

Reference:

AP 0151! "Responsibilities and Authorities of Operations Department Personnel" Task Number: 34103703 (Maintain a valid SRO license)

Task Performance: AO/RO/SRO _ _ _ RO/SRO _...:....:X~ SROOnly_ _

Sequence Critical: Yes No X Time Critical: Yes No X Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:

Date of Evaluation:

Activity Code: _ _ _ _ _ _ _ _ _ _ __

Method of Testing: Simulation- - - Performance X Discuss- - -

Setting: Classroom X Simulator- - - Plant Performance Expected Completion Time: 15 minutes Evaluation Results:

Performance: PASS ___ FAIL _ __ Time Required: _ _ __

Preparedby: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____

NRC Exam Lead Developer Date Reviewed by:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____

Facility Reviewer Date NRC JPM-Ala SRO

NRC JPM*A1a SRO Rev. FINAL Page 2 of 8 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "SAT" or "UNSAT".

Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the classroom and you are to perform the actions.

You are requested to "talk through" the JPM, stating the indications/parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• Three Senior Reactor Operators are reactivating their licenses in preparation for becoming part of the crew rotation.

• A portion of VYOPF 0151.02, "Watch Standing License Reactivation Form", has been completed.

• Under instruction watches for the Control Room Supervisor position (CRS) occurred on the following dates and times (Attachment 1). These dates and times are from the "Credit for Position Report" that the Operation Department Admin Specialist printed out on ESOMS.

NRC JPM-Ala SRO

NRC ...IPM-A1a SRO Rev. FINAL Page 3 of 8 Initiating Cues:

• In accordance with AP 0151, "Responsibilities and Authorities of Operations Department Personnel", determine if the REACTIVATION requirements are met for Hobbs, Wilson, and Fox to resume duties on shift as a Control Room Supervisor and complete ALL associated paperwork.

• Route associated paperwork to the Operations Manager for review.

Task Standards:

• The operator determines that 2/3 SROs (Hobbs and Fox) have met the requirements requirements to activate the SRO license and that 1/3 SROs (Wilson) has not met the requirements due to not having the minimum number of 8 or 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> watches; Completes VYAPF 0151.01/02 and forwards the forms to the Operations Manager for review.

Required Materials:

• AP 0151, "Responsibilities and Authorities of Operations Department Personnel"

• Handout: VYAPF 0151.01

• Handout: VYAPF 0151.02 (3- partially completed)

Simulator Set-Up:

• N/A NRC JPM-Ala SRO

NRC JPM-A1a SRO Rev. FINAL Page 4 of 8 Provide operator with Initial Conditions/Cue and Attachment 1 (Last 2 pages of this JPM).

TIME START: _ _ __

Evaluation Performance Steps SAT/liNSAT Step 1: Obtain AP 0151, "Responsibilities and Authorities of Operations Department Personnel" and review section 4.11, Standard: Obtains AP 0151.

EVALUATOR CUE: When asked, provide a copy of AP 0151.

SAT/UNSAT *Step 2: lAW AP 0151! section 4.11.1.5.1.1 verify the individual is currently enrolled and participating in the Vermont Yankee Licensed Operator Regualification (LOR) Program or SRO Upgrade Program.

Standard: Upon reviewing VYAPF 0151.02, the operator determines that the signatures and dates for Hobbs, Wilson, and Fox satisfy the requirements of being up to date in the License Operator Requalification Program.

EVALUATOR CUE: When asked, provide the three VYAPF0151.02 forms for Hobbs, Wilson, and Fox.

NRC JPM-Ala SRO

NRC JPM-A1a SRO Rev. FINAL Page 5 of 8 Evaluation Performance Steps SAT/UNSAT *Step 3: lAW AP 0151. section 4.11.1.5.1.2. verify the individual has stood 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of parallel watches under the direct supervision of an operator or senior operator Standard: From the initial conditions, the operator determines that Hobbs (44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />) and Fox (42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />) stood at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of under instruction watches at the CRS position. The operator determines that Wilson (38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br />) did NOT stand at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of under instruction watches at the CRS position.

EVALUATOR NOTE: The operator may incorrectly determine that 5-12 hour watches are required. This is the requirement for maintaining a license in a calendar quarter.

EVALUATOR CUE: If asked, inform the operator that the individual was logged in to ESOMS Narrative Log Shift Roster.

SAT/UNSAT *Step 4: lAW AP 0151, section 4.11.1.5.1.2, verify the individual has completed a plant tour from an active license holder while standing the 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of under instruction watches.

Standard: From the initial conditions, the operator determines that a plant tour was conducted by the Field Support Supervisor (FSS) for Hobbs, Wilson and Fox.

SAT/UNSAT *Step 5: lAW AP 0151. section 4.11.1.5.1.2. verify the individual has completed a review of all required shift turnover procedures while standing the 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of under instruction watches.

Standard: From the initial conditions, the operator determines that a review of the procedures was conducted for Hobbs, Wilson, and Fox.

NRC lPM-Ala SRO

NRC JPM-A1a SRO Rev. FINAL Page 6 of 8 Evaluation Performance Steps SAT/UNSAT Step 6: lAW AP 0151. section 4.11.1.5.1.2. the 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> will be documented on NRC License Maintenance Quarterly Summary. VYAPF 0151.01 Standard: The operator documents the watches stood on VYOPF0151.01 for Hobbs (44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />) and Fox (42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />).

EVALUATOR CUE: If the operator just states the number of hours stood without filling in the form, inform the operator to complete all paperwork associated with the SRO reactivation.

SAT/UNSAT *Step 9: lAW AP 0151. section 4.11.2.3.2. verify and/or record the reactivation information on VYOPF 0151.01.

Standard: Operator verifies and or records the following information for Hobbs and Fox:

o Reactivation is checked o Calendar quarter is checked (Oct. 1-Dec.31) o Individual's name recorded o Individual's position recorded (CRS) o Number of hours stood as CRS and!or number of full 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> watches watches stood.

o Initial for verification after ensuring the acceptance criteria (b) is met for reactivation: 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of under instruction watches.

EVALUATOR NOTE/CUE: The blank on VYAPF0151.01 says number of watches!8 or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the operator states that there are watches not 8 or 12 in length, then inform the operator to document the number of total hours stood.

EVALUATOR CUE: If not available, inform the operator that the "Credit for Position Report" is being printed by the Operations Department Administrative Specialist and will be forwarded to the Operations Manager.

NRC IPM-Ala SRO

NRC JPM-A1a SRO Rev. FINAL Page 7 of 8 Evaluation Performance Steps SAT/UNSAT Step 10: Route the VYAPF 0151.01 and VYAPF 0151.02 forms to the Operations Manager or Designee for review Standard: Operator routes form VYAPF 0151.01/.02 to the Operations Manager for review.

• Critical Step TIME FINISH: _ _ __

Terminating Cue: The operator informs the evaluator that the reactivation requirements are satisfied for Hobbs and Fox and that Wilson does not meet the reactivation requirements. The form is routed to the Operations Manager for review.

NRC lPM-Ala SRO

NRC ..IPM-A1a SRO Rev. FINAL Page 8 of 8 Evaluator Comments:

System Generic KIA's: 2.1.1 Knowledge of conduct of operations requirements. (RO 3.8, SRO 4.2)

NRC JPM-Ala SRO

EXAMINEE HANDOUT Initial Conditions:

• Three Senior Reactor Operators are reactivating their licenses in preparation for becoming part of the crew rotation.

• A portion of VYOPF 0151.02, "Watch Standing License Reactivation Form", has been completed.

• Under instruction watches for the Control Room Supervisor position (CRS) occurred on the following dates and times (Attachment 1). These dates and times are from the "Credit for Position Report" that the Operation Department Admin Specialist printed out on ESOMS.

Initiating Cues:

• In accordance with AP 0151, "Responsibilities and Authorities of Operations Department Personnel", determine if the REACTIVATION requirements are met for Hobbs, Wilson, and Fox to resume duties on shift as a Control Room Supervisor and complete ALL associated paperwork.

• Route associated paperwork to the Operations Manager for review.

NRC JPM-Ala SRO

Attachment 1 The information provided is the watchstanding dates and times that were carried over from the "Credit for Position Report" that the Operation Department Admin Specialist printed out on ESOMS.

Brian Hobbs: Senior Reactor Operator watches stood as CRS o October 7th , 2010 from 0600-1800 (This watch included a review of all shift turnover procedures) o October 8 th , 2010 from 0600-1400 th o November 16 , 2010 from 1800-0600 (this watch included a plant tour from the Shift Manager) o November 1ih , 2010 from 1800-0600 Frank Wilson: Senior Reactor Operator watches stood as CRS o October 10th , 2010 from 0600-1800 (This watch included a review of all shift turnover procedures) th o October 11 , 2010 from 0600-1200 (this watch included a plant tour from the Shift Manager) o November 21s~ 2010 from 1800-0400 n

o November 22 , 2010 from 1800-0400 Carey Fox: Senior Reactor Operator watches stood as CRS o October 3rd, 2010 from 0600-1200 (This watch included a review of all shift turnover procedures) o October 4 th , 2010 from 0600-1800 th o November 19 , 2010 from 1800-0600 (this watch included a plant tour from the Shift Manager) th o November 20 , 2010 from 1800-0600 NRC JPM-Ala SRO

NRC JPM-A1b SRO Rev. FINAL Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Determine Containment Venting Strategy while Implementing the Severe Accident Guidelines.

Failure Mode: N/A

Reference:

Severe Accident Guidelines (SAGs)

Task Number: 31071403 (Direct Primary Containment Venting)

Task Performance: AO/RO/SRO _ _ _ RO/SRO _ __ SRO Only X Sequence Critical: Yes No X Time Critical: Yes No X Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:

Date of Evaluation: - - - - - - - - - - -

Activity Code: _ _ _ _ _ _ _ _ _ _ __

Method of Testing: Simulation___ Performance X Discuss_ _

Setting: Classroom X Simulator_ _ _ Plant'--__

Performance Expected Completion Time: 10 minutes Evaluation Results:

Performance: PASS _ _ FAIL _ __ Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Alb SRO

NRC ..IPM-A1b SRO Rev. FINAL Page 2 of 6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "SAT" or "UNSAT".

Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the classroom and you are to perform the actions.

You are requested to "talk through" the ..IPM, stating the indications/parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant automatically scrammed from normal full power operations due to a large break loss of coolant accident (LOCA).

• Equipment malfunctions have resulted in the inability to maintain Adequate Core Cooling (ACC) and Severe Accident Guideline-2 (SAG-2) has been entered.

• Containment conditions are as follows:

o Torus water level is 20 feet and slowly rising o Torus 02: 4% and steady o Torus H2 : 5% and steady o Drywell O2 : 6% and steady o Drywell H2 : 5% and steady

• Radiological conditions are as follows:

o Stack High Range Monitor (Gas 3 [RM-17-155]) is reading 175 mRlhr and slowly rising o Dose assessment using actual meteorology indicates doses of 105 mRem/hr and steady at the Site boundary o Field surveys are in progress

• The Emergency Plan organization is NOT yet manned NRC JPM-Alb SRO

NRC JPM-A1b SRO Rev. FINAL Page 3 of 6 Initiating Cues:

• In accordance with the SAG-2, determine the following for each the Torus and Drywell independent of one another:(FiII in chart on handout) o Can high radiation isolations be defeated?

o What is/are the procedures(s) that can be used to vent containment?

o What is the criterion for securing venting?

o Can release rate limits be exceeded?

Task Standards:

• The correct SAG-2 thresholds for H2/02 and the subsequent containment venting actions have been determined and all questions from the initiating cue answered.

Required Materials:

• Severe Accident Guideline (SAG)-2, "RPV, Containment, and Radioactivity Release Control"

• AP 3125, "Emergency Plan Classification and Action Level Scheme", Appendix "A" (Hot)

• EAL Bases document

• Technical Specifications Simulator Set-Up:

• N/A NRC JPM-Alb SRO

NRC ..IPM-A1b SRO Rev. FINAL Page 4 of 6 Provide operator with Initial Conditions/Cue and handout (Last 2 pages of this ..IPM).

TIME START: _ _ __

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain SAG*2 flowchart and reviews the flowpath for Hydrogen and Oxygen concentration.

Standard: Obtains SAG-2 Flowchart.

SAT/UNSAT *Step 2: From the given Hydrogen and Oxygen concentrations, the operator determines the required action levels for containment venting/purge operations in the Drywell and Torus:

Standard: From the given Hydrogen and Oxygen concentrations, the operator determines the following:

• Action level 2 for the Drywell

• Action level 4 for the Torus SAT/UNSAT Step 3: Obtains and reviews AP 3125, Appendix "A" (Hot) to review the Emergency Action Level thresholds for current radiological conditions.

Standard: Some action levels have criteria for securing venting operations based on reaching General Emergency levels for effluent releases. Based on the initial conditions, the operator determines that the plant is at Site Area Emergency levels for effluent releases with plenty of margin to the General Emergency levels.

NRC JPM-Al b SRO

NRC ,..IPM-A1 b SRO Rev. FINAL Page 5 of 6 Evaluation Performance Steps SAT/UNSAT *Step 4: Based on the action level for the Drywell, the operator answers the given questions Standard: The operator answers the Orywell questions as follows (Action level 2):

o Can high radiation isolations be defeated? YES o What is/are the procedures(s) that can be used to vent containment? The Drywell is vented using OP 2115, OP 2125, or OE 3107.

o What is the criterion for securing venting?

• Hydrogen no longer detected in the Drywell AND EITHER Drywell Oxygen is <5% OR Hydrogen no longer detected in the Torus -or

• RPV water level maintained above TAF AND off site release rates reach General Emergency level.

o Can release rate limits be exceeded? NO (below the limit already)

SAT/UNSAT *Step 5: Based on the action level for the Torus, the operator answers the given questions Standard: The operator answers the Torus questions as follows (Action level 4):

o Can high radiation isolations be defeated? NO o What is/are the procedures(s) that can be used to vent containment? With Torus level at 18.5 feet, the Torus is vented using OP 2115 or OP 2125 o What is the criterion for securing venting?

• Hydrogen no longer detected in the Torus OR Off Site release rate reaches the LCO.

o Can release rate limits be exceeded? NO (below the limit already)

NRC JPM-Alb SRO

NRC JPM-A1b SRO Rev. FINAL Page 6 of6

• Critical Step TIME FINISH: _ _ __

Terminating Cue: The operator informs the evaluator that all the questions asked in the initiating cue have been answered.

Evaluator Comments:

System Generic KIA's: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (RO 3.9, SRO 4.2)

NRC lPM-Alb SRO

EXAMINEE HANDOUT Initial Conditions:

• The plant automatically scrammed from normal full power operations due to a large break loss of coolant accident (LOCA).

• Equipment malfunctions have resulted in the inability to maintain Adequate Core Cooling (ACC) and Severe Accident Guideline-2 (SAG-2) has been entered.

• Containment conditions are as follows:

o Torus water level is 20 feet and slowly rising o Torus 02: 4% and steady o Torus H2: 5% and steady o Drywell 02: 6% and steady o Drywell H2 : 5% and steady

• Radiological conditions are as follows:

o Stack High Range Monitor (Gas 3 [RM-17-155]) is reading 175 mRlhr and slowly rising o Dose assessment using actual meteorology indicates doses of 105 mRem/hr and steady at the Site boundary o Field surveys are in progress

• The Emergency Plan organization is NOT yet manned Initiating Cues:

• In accordance with the SAG-2, determine the following for each the Torus and Drywell independent of one another:(Fili in chart on handout) o Can high radiation isolations be defeated?

o What is/are the procedures(s) that can be used to vent containment?

o What is the criterion for securing venting?

o Can release rate limits be exceeded?

NRC lPM-Alb SRO

EXAMINEE HANDOUT Quesmi.t;.Is. ... . . . . . . . . ;'/ DRYWELL . TORUS Can high radiation isolations be defeated?

What isfare the procedures(s) that can be used to vent containment?

What is the criterion for securing venting?

Can release rate limits be exceeded?

NRC JPM-Alb SRO

NRC ...IPM-A2 SRO Rev. FINAL Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASLIRE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Administrative Review of OPST-CS-4123-02A, "Core Spray 'A' MOV/lnjection Valve Operability Test", Surveillance.

Failure Mode: Administrative deficiencies and out of spec 1ST value associated with paperwork

Reference:

OPST-CS-4123-02A. "Core Spray 'A' MOV/lnjection Valve Operability Test" Task Number: 34202603 (Review Results of Surveillance Test)

Task Performance: AO/RO/SRO _ _ _ RO/SRO _ __ SRO Only X Sequence Critical: Yes No~

Time Critical: Yes No~

Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date of Evaluation: _ _ _ _ _ _ _ _ _ __

Activity Code: _ _ _ _ _ _ _ _ _ _ __

Method of Testing: Simulation___ Performance X Discuss_ _

Setting: Classroom _=-=--_ Simulator___ Plant,_ __

Performance Expected Completion Time: 8 minutes Evaluation Results:

Performance: PASS _ _ FAIL _ __ Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC lPM-A2 SRO

NRC ...IPM-A2 SRO Rev. FINAL Page 2 of 7 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "SAT" or "UNSAT".

Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the classroom and you are to perform the actions.

You are requested to "talk through" the ...IPM, stating the indications/parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant is operating at 100% RTP

• OPST-CS-4123-02A, Core Spray 'A' MOVllnjection Valve Operability Test", surveillance was just completed to satisfy the monthly requirement.

• Core Spray "A" is administratively inoperable lAW OPST-CS-4123-02A, step 9.2. (T.S.

3.5.A).

Initiating Cues:

• In accordance with OPST-CS-4123-02A, Core Spray 'A' MOVllnjection Valve Operability Test", perform section 12.4, "SRO Review".

• Step 9.13 will not be signed until the CRS has performed the review of the surveillance.

Task Standards:

Section 12.4 complete and signed off to be forwarded to the Shift Manger for review.

NRC JPM-A2 SRO

NRC ..IPM-A2 SRO Rev. FINAL Page 3 of 7 Required Materials:

• OPST-CS-4123-02A, Core Spray 'A' MOV/lnjection Valve Operability Test"

• Step 8 prerequisites are completed .

• Step 9 provided (placekept) to the candidate completed with the following discrepancies:

o Step 9.6.3 missing final Torus volume o Step 9.7.2.A missing an initial

• Step 9.13 not filled in until after the CRS review is complete

• Step 12.1.1 table filled in with RO and IV names/signatures

• Step 12.2 completed

• Attachment 1 completed with open time for CS-12A UNSAT at 7.70 seconds Simulator SetwUp:

• N/A NRC JPM-A2 SRO

NRC JPM-A2 SRO Rev. FINAL Page 4 of 7 Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ __

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain the completed OPST*CS~4123-02A for review.

Standard: Obtains OPST-CS-4123-02A and reviews section 12.4 EVALUATOR NOTE: When the operator asks, provide a copy of the completed surveillance.

SAT/UNSAT *Step 2: lAW step 12.4.1, VERIFY all data. initial AND signature blocks are complete.

Standard: The operator notices the following deficiencies with the surveillance paperwork:

• final torus water volume missing for step 9.6.3

• missing initial for step 9.7.2.A The operator does NOT initial the review for this step until the paperwork is fixed.

EVALUATOR CUE: Inform the operator that the missing initial and data has been 'filled in by the operators that performed the surveillance. This step can now be initialed for and the review continued.

SAT/UNSAT Step 3: lAW step 12.4.2, VERIFY personnel performing activities are recorded in Step 12.1.1.

Standard: The operator verifies personnel performing activities are recorded in step 12.1.1 AND initials this review as complete.

NRC JPM-A2 SRO

NRC JPM-A2 SRO Rev. FINAL Page 5 of 7 Evaluation Performance Steps SAT/UNSAT *Step 4: lAW step 12.4.3, VERIFY Acceptance Criteria met in Section 11.0.

Standard: The operator verifies not ALL acceptance criterion is met for section 11.0 on Attachment 1. The following deficiency is noted:

• 11.4 PUMP DISCHARGE CS-12A does NOT stroke open within 1ST Acceptable as recorded on Attachment 1.

• Notes that the 1ST Review for CS-12A in section 12.2 is subsequently incorrect.

The operator does NOT initial the review for this step and continues with step 12.4.4.

SAT/UNSAT *Step 5: lAW step 12.4.4, takes action if acceptance criterion was not Standard: The operator performs the following:

• Informs the Shift Manger

• Ensure CR and WR have been initiated

• Record CR and WR in the "Remarks" section 12.3 AND initials this review as complete EVALUATOR NOTE/CUE: If asked, inform the operator that the Shift Technical Advisor has written a CR and initiated a WR. Provide the numbers to the operator to fill in on section 12.4.4:

• CR-VTY-2010-5000

• WR Number: 10-2000 SAT/UNSAT Step 6: lAW step 12.4.5. RECORD any additional required corrective OR compensatory actions in remarks section.

Standard: The operator notes the unsat timing on CS-12A. The operator may document the CR and WR number as well.

NRC JPM-A2 SRO

NRC JPM-A2 SRO Rev. FINAL Page 6 of 7 Evaluation Performance Steps SAT/UNSAT Step 7: lAW step 12.4.6, IF reactor pressure is LESS THAN 400 psis in Step. then reschedule ...

Standard: The operator verifies step 9.7.1 was done at a pressure >400 psig and marks step 12.4.6 as "N/A" SAT/UNSAT Step 8: lAW step 12.4.7, ENSURE results are entered in Control Room Log Book.

Standard: The operator verifies entry in the Control Room Log Book and initials this review as complete.

EVALUATOR CUE: If asked, inform the operator that the Shift Manager made an entry in the Control Room Log Book (including the updating results of the surveillance).

SAT/UNSAT Step 9: lAW step 12.4.8, RECORD date AND time SRO Review complete.

Standard: The operator signs and records the date and time the SRO Review is complete: Signature, printed name, current date and time.

• Critical Step TIME FINISH: _ _ __

Terminating Cue: Section 12.4 of OPST-CS-4123-02A is complete and routed to the Shift Manager for review (step 12.5).

NRC JPM-A2 SRO

NRC JPM-A2 SRO Rev. FINAL Page 7 of 7 Evaluator Comments:

System Generic KIA's: 2.2.12 Knowledge of surveillance procedures (RO 3.7, SRO 4.1)

NRC JPM-A2 SRO

EXAMINEE HANDOUT Initial Conditions:

• The plant is operating at 100% RTP

• OPST-CS-4123-02A, Core Spray 'A' MOV/lnjection Valve Operability Test", surveillance was just completed to satisfy the monthly requirement.

• Core Spray "A" is administratively inoperable lAW OPST-CS-4123-02A, step 9.2. (T.S.

3.5.A).

Initiating Cues:

• In accordance with OPST-CS-4123-02A, Core Spray 'A' MOVllnjection Valve Operability Test", perform section 12.4, "SRO Review",

• Step 9.13 will not be signed until the CRS has performed the review of the surveillance.

NRC JPM-A2 SRO

NRC JPM-A3 SRO Rev. FINAL Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Determine the Radiological Protection Requirements for Entering a Locked High Radiation Area.

Failure Mode: N/A

Reference:

EN-RP-101! "Access Control for Radiologically Controlled Areas" Task Number: 2990100301 (Apply Radiological and Contamination Safety Procedures)

Task Performance: AO/RO/SRO _ _ _ RO/SRO _--'X"""""----_ SROOnly_ _

Sequence Critical: Yes No X Time Critical: Yes No~

Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date of Evaluation: _ _ _ _ _ _ _ _ _ __

Activity Code: _ _ _ _ _ _ _ _ _ _ __

Method of Testing: Simulation___ Performance X Discuss_ _

Setting: Classroom _~_ Simulator___ Plant,-__

Performance Expected Completion Time: 9 minutes Evaluation Results:

Performance: PASS _ _ FAIL _ __ Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-A3 SRO

NRC JPM-A3 SRO Rev. FINAL Page 2 of 7 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "SAT" or "UNSAT".

Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the classroom and you are to perform the actions.

You are requested to "talk through" the ..IPM, stating the indications/parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant is shutdown for a refueling outage.

• Fuel moves from the Spent Fuel Pool to and from the RPV are in progress

• A leak develops resulting in the loss of Fuel Pool level. The Control Room enters and directs actions of ON 3157, "Loss of Fuel Pool Level".

• The source of the leak has been found and secured.

• Radiation levels in the Reactor Building DO NOT permit access on the refuel floor.

• The Service Water system is unavailable.

• The required valve manipulations will take a total of 20 minutes in the area to restore fuel pool level to normal.

o NOTE 1: For the purpose of this scenario, the operator is at the location of the valves in communication with the Refuel Floor SRO for the entire 20 minutes o NOTE 2: assume a total exposure of 5 mrem is collected by the AO transitioning to and from the valve locations.

NRC JPM-A3 SRO

NRC JPM-A3 SRO Rev. FINAL Page 3 of 7 Initiating Cues:

• For the given scenario and RWP Index provided, determine the following:

o Which valves are operated?

o Which type of radiologically controlled area the valves are located in?

o Which RWP and task to enter under?

o Will the dose alarm be received by the individual performing the valve manipulations?

Task Standards:

• The answers to the initiating cues have been provided.

Required Materials:

• OP 3157, "Loss of Fuel Pool Level"

• OP 2184, Normal Fuel Pool Cooling System", Appendix "A"

• RWP Index

• RWP 2010-0053, task #7

• ESOMS Equipment Manager program available

• Survey map of the Fuel Pool Heat Exchanger Room with valve locations identified by Operations and RP.

Simulator Set-Up:

• N/A NRC lPM-A3 SRO

NRC JPM-A3 SRO Rev. FINAL Page 4 of 7 Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ __

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain ON 3157. "Loss of Fuel Pool Level" to determine which valves are required to be operated.

Standard: Obtains ON 3157, and from operator action 10a determines that with the fuel moves in progress, the fuel pool gates are removed.

FPC-28, Reactor Well Fill from Condensate Transfer, and FPC 53, Reactor Well Recirculation Valve, are required to be operated to provide makeup flow.

EVALUATOR CUE: Provide the Operator with a copy of ON 3157.

EVALUATOR NOTE: Based on the initial conditions, the operator determines that ON 3157 steps 10.a.2 (gates are removed), 10.b (Refuel Floor inaccessible), 10.c (Refuel Floor inaccessible), and 10.d (SW system is unavailable) are all unavailable. The only means of adding to the Fuel Pool are CST lAW step 10.a.1.

SAT/UNSAT *Step 2: Operator determines where these valves are located Standard: The operator can use a variety of references to determine the location of the valves.

• OP 2184 Appendix "A" lists FPC -28 and FPC in the "Reactor Building (Fuel Pool Pump Area)"

• ESOMS Equipment Manager lists these valves in the "RB 303/Fuel Pool HX Room"

• Operator knowledge (see Evaluator Note)

EVALUATOR NOTE: If the operator just states where the valves are located based on prior knowledge, the evaluator may elect to ask a follow-up to have the operator prove it.

NRC JPM-A3 SRO

NRC ...IPM-A3 SRO Rev. FINAL Page 5 of 7 Evaluation Performance Steps EVALUATOR NOTE: ESOMS Equipment Manager is a program that can be accessed from the START menu:

Programs/Nuclear ESOMS/Equipment Database. From here, each operator has their own login.

SAT/UNSAT

• Step 3: Operator reviews RWP Index to determine the required RWP and the type of radiologically controlled area.

Standard: The operator reviews the index and determines that the Fuel Pool Heat Exchanger Room is listed under RWP 2010-0053 and that the RWP controls entry in the Locked High Radiation Area (LHRA).

EVALUATOR CUE: When asked, provide the Operator with a copy the RWP Index.

SAT/U NSAT *Step 4: Operator reviews the RWP and determines the task number for which he/she will enter under.

Standard: The operator reviews the RWP and determines that task number seven applies to the Fuel Pool Cooling Heat Exchanger Room.

EVALUATOR CUE: When asked, provide the Operator with a copy RWP 2010-0053.

NRC JPM-A3 SRO

NRC JPM-A3 SRO Rev. FINAL Page 6 of 7 Evaluation Performance Steps SAT/UNSAT *Step 5: Operator reviews the survey map to determine how much dose would be received for the required time to perform the valve operations Standard: The operator predetermines that he/she will receive 25 mrem in the twenty minutes it takes to perform the valve operations.

This dose for the valve operations (20 mrem) plus the 5mrem accumulated transitioning to and from the HX room are added and compared to the ED alarm setpoint (40 mrem).

The operator determines that the total dose accumulated for the Fuel Pool makeup water transfer operation will NOT result in an ED alarm for total dose.

EVALUATOR NOTE: If the operator operator chose the wrong valves, it would result in an ED alarm for total dose (40 mrem

+ 5mrem = 45 mrem which exceeds dose alarm of 40 merem.

• Critical Step TIME FINISH: _ _ __

Terminating Cue: Answers to the questions have been provided to the evaluator NRC lPM-A3 SRO

NRC JPM-A3 SRO Rev. FINAL Page 7 of 7 Evaluator Comments:

System Generic KIA's: 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions (RO 3.5, SRO 3.6)

NRC JPM-A3 SRO

EXAMINEE HANDOUT Initial Conditions:

• The plant is shutdown for a refueling outage.

• Fuel moves from the Spent Fuel Pool to and from the RPV are in progress

• A leak develops resulting in the loss of Fuel Pool leveL The Control Room enters and directs actions of ON 3157, "Loss of Fuel Pool Level".

• The source of the leak has been found and secured.

• Radiation levels in the Reactor Building DO NOT permit access on the refuel floor.

• The Service Water system is unavailable.

• The required valve manipulations will take a total of 20 minutes in the area to restore fuel pool level to normal.

o NOTE 1: For the purpose of this scenario, the operator is at the location of the valves in communication with the Refuel Floor SRO for the entire 20 minutes o NOTE 2: assume a total exposure of 5 mrem is collected by the AO transitioning to and from the valve locations.

Initiating Cues:

• For the given scenario and RWP Index provided, determine the following:

o Which valves are operated?

o Which type of radiologically controlled area the valves are located in?

o Which RWP and task to enter under?

o Will the dose alarm be received by the individual performing the valve manipulations?

1. Which valves are operated? _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

2. What type of radiologically controlled area are the valves located in? _ _ _ _ _ __

3. Which RWP and task number is the operator entering under? .;.,;R=W.:...;P:.......;,;#..;,.:_ _ _ _ __

Task #:

4. Will the Electronic Dosimeter (ED) dose alarm be received by the individual performing the valve manipulations? Circle answer YES I NO NRC JPM-A3 SRO

NRC JPM-A4 SRO Rev. FINAL Page 1 of 8 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Emergency Action Level Classification and PAR Failure Mode: NIA

Reference:

AP 3125. "Emergency Plan Classification" Task Number: 34401703 (Analyze Indications to Determine if an Emergency Plan Event is in Progress)

Task Performance: AO/RO/SRO RO/SRO SRO Only X Sequence Critical: Yes No X Time Critical: Yes X No Operator Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation Performance X Discuss Setting: Classroom X Simulator___ Plant._ __

Performance Expected Completion Time: 5/7 minutes Evaluation Results:

Performance: PASS _ _ FAIL _ __ Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-A4 SRO

NRC JPM-A4 SRO Rev. FINAL Page 2 ofS Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "SAT" or "UNSAT".

Comments are required for any "UNSAT" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the classroom and you are to perform the actions.

You are requested to "talk through" the JPM, stating the indications/parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• With the plant operating at 100% RTP and end of cycle, a steam leak in the steam tunnel resulted in a PCIS Group 1 isolation and automatic closure of 3 of 4 Main Steam Lines.

MS-SOD and MS-S6D failed to auto isolate and could not be manually shut. Partial rod insertion had resulted in power remaining at 60%.

• The applicable Emergency Operating Procedures have been entered and current plant conditions are as follows:

o RPV water level is being controlled in the -19 inches to +90 inches and power is now 14%.

o RPV water level is at +50 inches and steady o Pressure is cycling near the SRV setpoints o SLC failed to inject and rod insertion appendices are being performed o Drywell pressure is 9.S psig and steady o Drywell radiation levels as read on the Drywell Hi Range Radiation Monitors (RM 16/19-1A1B) are 1100 Rlhour and slowly rising o Reactor Building radiation levels are -100 times normal o Chemistry samples revealed primary coolant activity of 320 jJCilgrn 1-131 dose equivalent o Torus level is 11.5 feet and rising slow o Torus temperature is 104°F and steady o Steam Tunnel temperatures are at 1S0°F and rising slow o There is no off-site radiological data at this time NRC JPM-A4 SRO

NRC JPM-A4 SRO Rev. FINAL Page 3 of 8 Initiating Cues (2):

• As the Shift Manager, in accordance AP 3125, "Emergency Plan Classification and Action Level Scheme", step 4.2, to make the highest Emergency Action Level (EAL) classification required for the current plant conditions

• You have 15 minutes to make the classification.

EVALUATOR NOTE: Hand out second initiating cue AFTER the classification is made and read the following cue:

• After the classification, make a Protective Action Recommendation based on plant conditions lAW OP OP 3511.

• Route completed paperwork to the Shift Manager for review.

• You have 15 minutes to make the PAR.

Task Standards:

• The correct EAL classification has been made and justification for the criteria used explained to the evaluator.

• The correct PAR made for the given plant conditions.

Required Materials:

• AP 3125, "Emergency Plan Classification and Action Level Scheme"

• EAL Bases document

• EOP-2, "RPV ATWS Control"

• P &ID G-191167, "Flow Diagram Nuclear Boiler"

• OP 3511, "Off-Site Protective Action Recommendations"

• OP 3513, Attachment 9.7, 'Manual Meteorological Data Acquisition"

• METPAC data dated 11/10/10 @1529 Simulator Set-Up:

• NIA NRC JPM-A4 SRO

NRC JPM-A4 SRO Rev. FINAL Page 4 of 8 Evaluation Performance Steps Provide operator with Initial Conditions/Cue (First handout- DO NOT provide second handout until the first portion has been completed).

TIME START: _ _ _ __ (15 minutes from the start of JPM to doc'ument the highest EAL classification for current plant conditions)

EVALUATOR NOTES: Based on the thought process used by the operator in determining the highest EAL classification, a review of other EALs while determining the highest may be captured in the remarks section.

If at any time throughout this JPM the Operator wishes to review the EAL Bases document, provide this to the Operator.

There is ONLY one EAL classification for a General Emergency associated with this "IPM.

SAT/UNSAT Step 1: Obtain AP 3125, "Notification of Significant Events" and review steps 4.1 and 4.2 Standard: Obtains AP 3125 and reviews steps 4.1 and 4.2 EVALUATOR CUE: Provide a copy of AP 3125 to the operator when asked.

SAT/UNSAT Step 2: Obtains and reviews AP 3125, Appendix "A" (Hot) to review the Emergency Action Level thresholds for current plant conditions.

Standard: Operator determines that plant conditions warrant the use of AP 3125, Appendix "An (HOT) and EVALUATOR CUE: Provide a copy of AP 3125 and/or AP 3125 Appendix "A" (Hot) to the operator when asked.

NRC JPM-A4 SRO

NRC JPM-A4 SRO Rev. FINAL Page 5 of 8 Evaluation Performance Steps SAT/UNSAT *Step 3: Operator determines that there is a Loss of the Primary Containment barrier lAW AP 3125, Appendix A, Table F-1.

Standard: The operator determines that an open Main Steam Line that cannot be shut manually following a failure to auto close constitutes" Failure of all valves in anyone line to close AND Direct downstream pathway to the environment exists after PC isolation signal" (steam leak in the steam tunnel).

SAT/UNSAT *Step 4: Operator determines that there is a Loss of the Reactor Coolant System barrier lAW AP 3125, Appendix A, Table F-1.

Standard: Operator determines that there is a loss based on any ONE of the following:

• DW High Rad Monitor (RM-16-19-1A1B) > 10 Rlhr OR

• Release pathway exists ouside Pcresulting from isolation failure in the Main Steam system.

SAT/UNSAT *Step 5: Operator determines that there is a Loss of the Fuel Clad barrier lAW AP 3125, Appendix A, Table F-1.

Standard: There is a loss of Fuel Clad barrier based on Primary Coolant Activity.

NRC JPM-A4 SRO

NRC "IPM-A4 SRO Rev. FINAL Page 6 of 8 Evaluation Performance Steps SAT/UNSAT *Step 6: Operator determines that the criteria has been satisfied for Emergency Action level (EAl) classification FG1.1.

Standard: The operator declares EAL FG1.1.

EVALUATOR NOTES: Ensure the Operator explains the criteria used in determining that FG1.1 applies: Loss of Reactor Coolant System and Primary Containment barriers with the Loss of the Fuel Clad barrier.

Verifying this with the Operator does not have to be within the 15 minutes to declare the correct EAL.

EVALUATOR CUE: Inform the Operator that the STA will backup the classification. This portion of the JPM is complete.

Time complete: ____ (calssification declared)

TOTAL TIME to declare EAl: _ _ _ _ _ (Criteria: S 15 minutes)

Provide operator with Initial Conditions/Cue (Second handout).

TIME START: _ _ _ __ (15 minutes from the initiating cue provided to the time that OP 3511 Attachment 9.5 has been routed)

SAT/UNSAT Step 7: Obtain OP 3511. "Off-Site Protective Action Recommendations" Standard: Obtains OP 3511 and reviews section 5.6 EVALUATOR CUE: Provide a copy of AP OP 3511 to the operator when asked.

NRC JPM-A4 SRO

NRC JPM-A4 SRO Rev. FINAL Page 7 of 8 Evaluation Performance Steps SAT/UNSAT *Step 8: Use Attachment 9.4 and Attachment 9.1 to determine the appropriate PAR based on plant conditions:

Standard: Determines wind direction of 6.3 degrees from Meterological data using OP 3513, Attachment 9.7 Uses upper wind direction for a Stack release along with the 15 minute AVERAGE data and NOT the instantaneous data.

Standard: Determines that there is no substantial core damage in progress or projected.

Standard: Determines that there is no significant release underway.

Standard: Recommends the towns of Vernon, Hinsdale, and town within 5 miles downwind (Sector "A" towns of Bernardston, Northfield, Winchester, Vernon, and Hinsdale) using OP 3511, Attachment 9.1.

SAT/UNSAT *Step 9: Complete OP 3511! Attachment 9.5 Section 1 for plant conditions.

Standard: Fills in date and time; fills in the towns that are recommended to be sheltered (Sector "A" towns of Vernon, Hinsdale, Bernardston, Northfield, and Winchester) by placing an "S" in the space provided; lines out section II as not applicable (not critical); signs the "Preformed by" space and routes to the Shift Manager for verification.

EVALUATOR Cue: Inform the operator that the STA will complete the remainder of the required paperork and notifications.

No additional action is required for this JPM.

Time complete: ____ (paperwork routed to SM for review)

TOTAL TIME to complete PAR: _ _ _ _ _ (Criteria: S 15 minutes)

• Critical Step NRC JPM-A4 SRO

I\IRC JPM-A4 SRO Rev. FINAL Page 8 of 8 Evaluator Comments:

System Generic KIA's: 2.4.41 Knowledge of the emergency action level thresholds and classifications (RO 2.9/SRO 4.6) 2.4.44 Knowledge of the emergency plan protective action recommendations. (RO 2.4, SRO 4.4)

NRC JPM-A4 SRO

EXAMINEE HANDOUT Initial Conditions:

• With the plant operating at 100% RTP and end of cycle, a steam leak in the steam tunnel resulted in a PCIS Group 1 isolation and automatic closure of 3 of 4 Main Steam Lines.

MS-80D and MS-86D failed to auto isolate and could not be manually shut. Partial rod insertion had resulted in power remaining at 60%.

• The applicable Emergency Operating Procedures have been entered and current plant conditions are as follows:

o RPV water level is being controlled in the -19 inches to +90 inches and power is now 14%.

o RPV water level is at +50 inches and steady o Pressure is cycling near the SRV setpoints o SLC failed to inject and rod insertion appendices are being performed o Drywell pressure is 9.8 psig and steady o Drywell radiation levels as read on the Drywell Hi Range Radiation Monitors (RM 16/19-1NB) are 1100 Rlhour and slowly rising o Reactor Building radiation levels are -100 times normal o Chemistry samples revealed primary coolant activity of 320 tJCi/gm 1-131 dose equivalent o Torus level is 11.5 feet and rising slow o Torus temperature is 104°F and steady o Steam Tunnel temperatures are at 180°F and rising slow o There is no off-site radiological data at this time Initiating Cue:

• As the Shift Manager, in accordance AP 3125, "Emergency Plan Classification and Action Level Scheme", step 4.2, to make the highest Emergency Action Level (EAL) classification required for the current plant conditions

• You have 15 minutes to make the classification.

EAL Classification:

NRC JPM-A4 SRO

EXAMINEE HANDOUT Initiating Cue:

• After the classification, make a Protective Action Recommendation based on plant conditions lAW OP OP 3511.

• Route completed paperwork to the Shift Manager for review.

• You have 15 minutes to make the PAR NRC JPM-A4 SRO

NRC JPM S-1 Rev. FINAL Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORA"nON JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Transfer the Mode Switch to Run Failure Mode: N/A

Reference:

OP 0105. "Reactor Operations" Task Number: 2017400201 (Perform Heating and Pressurization of the Reactor)

Task Performance: AO/RO/SRO _ RO/SRO Only ~ SE Only_

Sequence Critical: Yes X No Time Critical: Yes No X Individual Performing Task:

Examiner:

Date of Evaluation: _ _ _ _ _ __

Activity Code:

Method of Testing: Simulation Performance ~ Discuss Setting: Classroom _ Simulator ~ Plant, Performance Expected Completion Time: 15 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Simulator 1 (S-l)

NRC "IPM S-1 Rev. FINAL Page 2 of6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

After providing the initiating cue, ask the individual "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• A plant startup is in progress with reactor power just below 2% on the APRMs. The crew is currently performing actions as directed IA OP 0105, Phase 2D.

• The Mechanical Vacuum Pump (~ogger) has been secured Initiating Cues:

• You have been directed by the CRS to transfer the Mode Switch to RUN lAW OP 0105, "Reactor Operations", phase 2D, step 10a -7 10g.

• Phase 2D, step 10e, is in progress and is being performed by other operators.

• OP 2111, CRD Hydraulic System, section "AA" placekeeping for rod movement has been suspended by the CRS.

Task Standards:

• Mode switch has been transferred to RUN Required Materials:

• OP 0105, placekept up to Phase 2D, step 10a.

• A2 rod sequence placekept up to rod group 26, control rod 18-27 NRC JPM-Simulator 1 (S-l)

NRC JPM S-1 Rev. FINAL Page 3 of 6 Simulator Set-Up:

• IC- 811

• Ensure CRD parameters are in band

• Remove caution tag on IRM "A" detector

• Ensure process computer printer is on Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ _ _ __

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain OP 0105 and review procedure Standard: Operator obtains procedure and reviews requirements EVALUATOR CUE: When the operator asks, provide a copy of the procedure and inform him/her all prerequisites are met.

SAT/UNSAT *Step 2: lAW OP 0105, Phase 2D, step 10a, pull control rods until all APRMs are indicating onscale.

Standard: lAW the A2 rod with draw sequence, the operator withdraws control rods to bring all APRMs indicating onscale EVALUATOR NOTE: The goal is to not only bring onscale but to also clear the downscale alarms. Based on how the operator reads the APRM recorders, this may vary from 2 control rods to several (operator dependent).

SAT/UNSAT Step 3: lAW OP 0105, Phase 2D, step 10b, Check that the APRMs are reading above 2% power by shifting the recorder select switches one at a time to APRM and returning them to the IRM positions.

Standard: Operator verifies that all APRMs are reading above 2% power by operating the 6 APRMIIRM shared recorders one at a time. After the operation of each one, the recorder is returned to the IRM position.

NRC JPM-Simulator 1 (S-l)

NRC JPM S-1 Rev. FINAL Page 4 of 6 Evaluation Performance Steps SAT/UNSAT *Step 4: lAW OP 0105, Phase 20, step 10c. check that all APRM downscale alarms are clear Standard: Operator verifies all downscale alarms are clear on the bench board for each APRM AND annunciator 5-M-4, "APRM DWNSCL" clears SAT/UNSAT *Step 5: lAW OP 0105. Phase 20, step 10d, smartly transfer Reactor Mode Switch to RUN Standard: Operator rotates the Mode switch clockwise to the RUN position EVALUATOR NOTE: Failure to ensure APRM downscale alarms have cleared prior to this step will result in an IRM HI-Hi signal. (lRM high flux trip and inoperative trip are bypassed in the RUI\I mode only if the APRM downscale trips have cleared)

SAT/UNSAT Step 6: lAW OP 0105, Phase 20, step 10e, ensure actions to inert the containment and establish Orywell to Torus.1P per OP 2115 are in progress or initiated.

EVALUATOR CUE: If asked, remind the operator that this step is being performed by other operators and he/she shall continue with Phase 2D, step 1Of.

SAT/UNSAT *Step 7: lAW OP 0105, Phase 20. step 10f, transfer recorder switches to APRM channels.

Standard: Operator rotates each IRM/APRM recorder clockwise to the APRM position to allow APRM monitoring on each recorder.

NRC JPM-8imulator 1 (8-1)

NRC JPM S-1 Rev. FINAL Page 5 of 6 Evaluation Performance Steps SAT/UNSAT *Step 8: lAW OP 0105, Phase 2D. step 10g. fully withdraw alllRM detectors Standard: Operator performs the following actions to withdraw IRM detectors:

• Depresses "SRM/IRM Detector Position" pushbutton on CRP 9-5

• Depresses "Channel A through F IRM/Select" pushbutton on CRP 9-5

• Depresses "Drive Out" pushbutton on CRP 9-5 EVALUATOR NOTE: The operator may chose to ensure IRM withdraw by observing IRM recorders. Proper IRM withdrawal may be determined by selecting each IRM channel for recording as its respective chamber is withdrawn and verify that indicated level is decreasing EVALUATOR NOTE: The operator may reference OP 2131, step A.11 for withdrawing IRMs however this is not required since it is skill of the craft lAW EN-OP-115.

EVALUATOR TERMINATING CUE: The IRMs will take some time to drive out. It is at the discretion of the evaluator to inform the operator that no other actions are required for this JPM.

• Critical Step TIME FINISH: _ _ __

NRC JPM-Simulator 1 (S-l)

NRC JPM S-1 Rev. FINAL Page 6 of 6 Evaluator Comments:

System KIA: Average Power Range Monitor System (215005) A4.01 (Ability to manually operate and/or monitor in the Control Room: IRM/APRM recorder.

R03.2/SR03.1 )

NRC JPM-Simulator 1 (S-I)

EXAMINEE HANDOUT Initial Conditions:

• A plant startup is in progress with reactor power just below 2% on the APRMs. The crew is currently performing actions as directed IA OP 0105, Phase 20.

• The Mechanical Vacuum Pump (Hogger) has been secured Initiating Cues:

• You have been directed by the CRS to transfer the Mode Switch to RUN lAW OP 0105, "Reactor Operations", phase 20, step 10a ~ 10g.

• Phase 20, step 10e, is in progress and is being performed by other operators.

• OP 2111, CRO Hydraulic System, section "AA" placekeeping for rod movement has been suspended by the CRS.

NRC IPM-8irnulator 1 (8-1)

NRC JPM S-2 Rev. FINAL Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Respond to a failed EPR and MPR Failure Mode: Pressure Oscillations on MPRIBoth regulators have failed

Reference:

OT 3115, "Reactor Pressure Transients" Task Number: 2000180501 (Respond to High Reactor Pressure)

Task Performance: AO/RO/SRO _ RO/SRO Only ~ SE Only Sequence Critical: Yes X No Time Critical: Yes No..L.

Individual Performing Task:

Examiner:

Date of Evaluation: _ _ _ _ _ __

Activity Code:

Method of Testing: Simulation Performance ~ Discuss Setting: Classroom _ Simulator ~ Plant, Performance Expected Completion Time: 6 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Simulator 2 (S-2)

NRC JPM S-2 Rev. FINAL Page 2 of 6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

After providing the initiating cue, ask the individual "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant was operating at 82% RTP and 976 psig when a failed EPR has resulted in high reactor pressure

• The CRS has entered OT 3115, "Reactor Pressure Transients" Initiating Cues:

• You have been directed as the OATC by the CRS to perform OT 3115, step 2.

Task Standards:

• Manual scram inserted for failed EPR and MPR Required Materials:

• OT 3115, "Reactor Pressure Transients" placekept up to step 2 NRC JPM-Simulator 2 (S-2)

NRC JPM S-2 Rev. FINAL Page 3 of 6 Simulator Set-Up:

• IC- 812

• Run on Scenario file NRC JPM S-2

• MPR stroke set at 68%

• OT 3115 placekept Lip to step 2 Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ _ _ __

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain OT 3115 and review procedure Standard: Operator obtains procedure and reviews requirements EVALUATOR CUE: When the operator asks, provide a copy of the procedure.

SAT/UNSAT Step 2: lAW OT 3115, step 2a1 , verify the MPR has taken control Standard: Operator verifies the white light above the MPR control switch is illuminated and that pressure is being controlled at a higher pressure on the MPR.

SAT/UNSAT *Step 3: lAW OT 3115, step 2a2, place the EPR CUTOUT SWITCH on CRP 9-7 to CUTOUT Standard: Operator places the EPR CUTOUT SWITCH to CUTOUT.

Annunciator 7-G-2, "EPR CONTROL POWER LOSSITROUBLE" is an expected alarm.

NRC JPM-Simulator 2 (S-2)

NRC JPM S-2 Rev. FINAL Page 4 of 6 Evaluation Performance Steps SAT/UNSAT *Step 4: lAW OT 3115, step 2a3, lower the MPR setpoint to return reactor pressure to pre-transient pressure Standard: Operator turns the MPR control switch counter clockwise incrementally to lower reactor pressure to its pre-transient pressure (976 psig). The indications the operator should use are the ERFIS display (8025) on CRP 9-5 and/or the pressure recorder on CRP 9-5 (PR 2-3-56).

SIM OPERATOR CUE: When pressure is -985 psig, insert KEY 1 (MPR failure resulting in high reactor pressure)

. SAT/UNSAT Step 5: Operator observes rising Reactor pressure and abnormal response to operation of the MPR.

Standard: Operator informs the CRS of rising reactor pressure and a failed MPR.

EVALUATOR NOTE: The ramp time of the MPR malfunction is such that an automatic reactor scram will occur in 70 seconds when initiated from 985 psig.

EVALUATOR CUE: If recommended to the CRS to manually scram the reactor, inform the operator to take the appropriate actions for the indications observed.

SAT/UNSAT *Step 6: lAW OT 3115. IMMEDIATE OPERATOR ACTIONS, operator manually scrams the reactor Standard: Operator depresses the manual scram pushbuttons on CRP 9-5 to scram the reactor.

EVALUATOR CUE: If asked as the CRS, inform the operator to take the appropriate actions for the indications observed.

EVALUATOR TERMINATING CUE: Inform the operator there are no additional actions required for this JPM.

NRC JPM-Simulator 2 (8-2)

NRC JPM S-2 Rev. FINAL Page 5 of 6

• Critical Step TIME FINISH: _ _ __

Terminating Cue: A manual scram has been inserted following realization that both EPR and MPR have failed.

NRC JPM-Sirnulator 2 (S-2)

NRC JPM S-2 Rev. FINAL Page 6 of 6 Evaluator Comments:

System KIA: Reactor/Turbine Pressure Regulating System (241000) A2.02 (Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations RO 3.7/SRO 3.7).

NRC JPM-Sirnulator 2 (S-2)

EXAMINEE HANDOUT Initial Conditions:

• The plant was operating at 82% RTP and 976 psig when a failed EPR has resulted in high reactor pressure

• The CRS has entered OT 3115, "Reactor Pressure Transients" Initiating Cues:

• You have been directed as the OATC by the CRS to perform OT 3115, step 2.

NRC lPM-Simulator 2 (8-2)

NRC JPM S-3 Rev. FINAL Page 1 of 8 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Main Steam Isolation Valve Full Closure Time Test Failure Mode: MS-86A fails the timing test

Reference:

OP 0105, "Reactor Operations" Task Number: 2390010201 (Perform Main Steam Valve Full Closure and Timing at Power)

Task Performance: AO/RO/SRO _ RO/SRO Only ~ SE Only_

Sequence Critical: Yes ~ No Time Critical: Yes No X Individual Performing Task:

Examiner:

Date of Evaluation: _ _ _ _ _ __

Activity Code:

Method of Testing: Simulation Performance --L Discuss Setting: Classroom _ Simulator ~ Plant Performance Expected Completion Time: 15 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Simulator 3 (S-3)

NRC JPM S-3 Rev. FINAL Page 2 of 8 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

After providing the initiating cue, ask the individual "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• A plant startup is in progress with reactor power at 55% RTP. The crew is performing steps within OP 0105, "Reactor Operations", Phase 48.

Initiating Cues:

• You have been directed by the CRS perform MSIV Full Closure and Timing Test lAW OP 4113, "Main Steam System Surveillance", Section "A".

• Steps A 1 ~ 5 are complete nd

• A 2 licensed operator is standing by to verify RPS relay actuation upon cycling MSIVs.

Task Standards:

• Identifies the out of spec MS-86A MSIV and takes the action of informing the CRS and shutting MS-80A.

Required Materials:

• OP 0105, placekept up to Phase 4B step 12.

• OP 4113

• VYOPF 4113.02 with header information filled in NRC JPM-Simulator 3 (S-3)

NRC JPM S-3 Rev. FINAL Page 3 of 8 Simulator Set-Up:

• IC- 813

• RUN on Scenario file NRC JPM S-3 Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ _ _ __

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain OP 0105 and OP 4113 and review procedure Standard: Operator obtains procedures and reviews requirements EVALUATOR CUE: When the operator asks, provide a copy of the surveillance and inform him/her all prerequisites are met.

SAT/UNSAT Step 2: lAW OP 4113. step A6. check steam flow in all 4 steam lines on CRP 9-5 and verify that they indicate approximately the same value.

Standard: Operator observes all four Main Steam flow indicators are reading approximately the same value on CRP 9-5 (FI 6-88A1B/C/D)

SAT/UNSAT Step 3: lAW OP 4113. step A7. determine which valve will be tested and notify the operator at the RPS Panel and at CRP 9-5.

Standard: Operator determines that the first valve to be tested will be MS 80A. This information is conveyed to the Operator at the Controls and the operator standing by at CRP 9-15 and 9-17 to observe RPS relay actuation.

EVALUATOR CUE: Acknowledge the operator and inform him/her that you are standing by to cycle the first MSIV (MS-80A)

NRC JPM-Simulator 3 (S-3)

NRC JPM 8-3 Rev. FINAL Page 4 of 8 Evaluation Performance Steps SAT/UNSAT *Step 4: lAW OP 4113, step A8a, close and time STEAM ISOLATION MS-80A as follows:

• Place STEAM ISOLATION MS-80A control switch to the CLOSE position

• Observe valve closure by Green indicating light illuminates when the valve starts to close AND

• Red open light extinguishes within the limits of 3 to 5 seconds

• On CRP 9-5, observe steam flow decreases to approximately zero as indicated on FI 6-88A, STEAM FLOW A

• On CRP 9-5, observe steam flow increases on FI 6-888 eC t D) STEAM FLOW 8 eC t D)

Standard: Operator places the MS-80A control switch to close and times the valve closure with a stop watch. The watch is started when the switch is repositioned and stopped when the red light extinguishes. Additionally, the operator observes steam flow indications on CRP 9-5.

EVALUATOR CUE: If asked as the OATC to mark steam flow indication for the MS-80A MSIV, inform him/her, flow indications on CRP 9-5 were SAT.

EVALUATOR NOTES: If the operator wishes to have a second operator provide a redundant timing of the valve, inform him/her that a second operator is timing the valve.

Any information asked for concerning the valve closure time will be identical to the operator's time.

Observing the steam flow indications is not critical to this step. Closing the valve and timing the valve closure is.

NRC JPM-Simulator 3 (S-3)

NRC .JPM S-3 Rev. FINAL Page 5 of 8 Evaluation Performance Steps SAT/UNSAT *Step 5: lAW OP 4113, step A8a2, record STEAM ISOLATION MS-80A closure time to the nearest 1/100 of a second.

Standard: Operator records the closing time for MS-80A on VYOPF 4113.02 SAT/UNSAT Step 6: lAW OP 4113, step A8a3, if STEAM ISOLATION MS-80A does not satisfy the closure time criteria of 3-5 seconds, perform the following ...

Standard: Operator identifies that the closure time for MS-80A was SAT and this step is N/A SAT/UNSAT Step 7: lAW OP 4113, step A8a4, verify that RPS recognizes STEAM ISOLATION MS-80A closure by observing that the following relays have de-energized (contacts open).

EVALUATOR CUE: When asked, inform the operator that 5A-K3A and 5A-K3B are de-energized on CRP 9-15 and CRP 9 17.

SAT/UNSAT *Step 8: lAW OP 4113, step A8b, return STEAM ISOLATION MS-80A control switch to the AUTO OPEN position.

Standard: Operator returns the MS-80A control switch to the AUTO OPEN position and observes.

• On CRP 9-5, observe steam flow increases on FI 6-88A STEAM FLOW A.

• Observe that STEAM ISOLATION MS-80A indicates full open.

EVALUATOR NOTE: Observing steam flow and indication is NOT critical for this step. Placing the control switch to open is critical.

NRC JPM-8imulator 3 (8-3)

NRC ,JPM S-3 Rev. FINAL Page 6 of 8 Evaluation Performance Steps SAT/UNSAT *Step 9: lAW OP 4113, step ASc, verify RPS recognizes STEAM ISOLATION MS-SOA is open by observing that the following relays have re-energized (contacts closed).

EVALUATOR CUE: When asked, inform the operator that 5A-K3A and 5A-K3B are energized on CRP 9-15 and CRP 9-17.

EVALUATOR NOTE: Based on the relays being re-energized, the operator determines that step A8d is not applicable SAT/UNSAT *Step 10: lAW OP 4113, step ASe, record results on VYOPF 4113.02 Standard: Operator documents that the relays have energized as expected on VYOPF 4113.02 under "SAT" column" Results of RPS Relay Actuation".

SAT/UNSAT *Step 11: lAW OP 4113, step A9a, close and time STEAM ISOLATION MS-S6A as follows:

• Place STEAM ISOLATION MS-S6A control switch to the CLOSE position

• Observe valve closure by Green indicating light illuminates when the valve starts to close AND

• Red open light extinguishes within the limits of 3 to 5 seconds

• On CRP 9-5, observe steam flow decreases to approximately zero as indicated on FI 6-SSA, STEAM FLOW A

• On CRP 9-5, observe steam flow increases on FI 6-SS8 (C, D) STEAM FLOW 8 (C, D)

Standard: Operator places the MS-86A control switch to close and times the valve closure with a stop watch. The watch is started when the switch is repositioned and stopped when the red light extinguishes. Additionally, the operator observes steam flow indications on CRP 9-5.

EVALUATOR ClIE: If asked as the OATC to mark steam flow indication for the MS-80A MSIV, inform him/her, flow indications on CRP 9-5 were SAT.

NRC JPM-Simulator 3 (S-3)

NRC JPM S-3 Rev. FINAL Page 7 of 8 Evaluation Performance Steps EVALUATOR NOTES: If the operator wishes to have a second operator provide a redundant timing of the valve, inform him/her that a second operator is timing the valve.

Any information asked for concerning the valve closure time will be identical to the operator's time.

Observing the steam flow indications is not critical to this step. Closing the valve and timing the valve closure is.

SATIUNSAT *Step 12: lAW OP 4113, step A9a2. record STEAM ISOLATION MS-86A closure time to the nearest 1/100 of a second.

Standard: Operator records the closing time for MS-86A on VYOPF 4113.02 SAT/UNSAT *Step 13: lAW OP 4113. step A9a3, if STEAM ISOLATION MS-80A does not satisfy the closure time criteria of 3-5 seconds, perform the following ...

• Suspend any further MSIV testing

• Close STEAM ISOLATION MS-80A

• Notify the Operations Manager

• Refer to Technical Specification 3.7 Standard: Operator informs the CRS of the UNSAT closure time and that TS 3.7 applies. Operator takes the control switch for MS-80A to the closed position.

EVALUATOR NOTE: The malfunction results in an UNSAT closure time of approximately 7 seconds.

EVALUATOR NOTE: Informing the CRS about the UNSAT closure time and TS application is not critical. Shutting MS-80A is a critical step.

EVALUATOR TERMINATING ClIE: Inform the operator as the CRS that additional MSIV testing is suspended. No additional actions are required for this JPM.

NRC lPM-Simulator 3 (S-3)

NRC JPM S-3 Rev. FINAL Page 8 of 8

• Critical Step TIME FINISH: _ _ __

Terminating Cue: MSIV testing through MS-86A is complete. MS-80A and 86A are in the closed position. VYOPF 4113.02 is documented through the UNSAT closure time for MS-86A.

Evaluator Comments:

System KIA: Primary Containment Isolation System (Main Steam 223002) A2.08 (Ability to predict the impacts on the PRIMARY CONTAINMENT ISOLATION (a)

SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and (b) based on those (b) predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: surveillance testing RO 2.7/SRO 3.1)

NRC JPM-Simulator 3 (S-3)

EXAMINEE HANDOUT Initial Conditions:

• A plant startup is in progress with reactor power at 55% RTP. The crew is performing steps within OP 0105, "Reactor Operations", Phase 4B.

Initiating Cues:

• You have been directed by the CRS perform MSIV FIJII Closure and Timing Test lAW OP 4113, "Main Steam System Surveillance", Section "A".

• Steps A 1 ~ 5 are complete

• A 2 nd licensed operator is standing by to verify RPS relay actuation upon cycling MSIVs.

NRC JPM-Simulator 3 (S-3)

NRC JPM S-4 Rev. FINAL Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Respond to a trip of a CRD Pump Failure Mode: N/A

Reference:

OPON-3145-01! "Loss of CRD Regulating Function" Task Number: 2007280501 (Respond to a loss of CRD Regulating Function)

Task Performance: AO/RO/SRO _ RO/SRO Only...x.- STA Only_

Sequence Critical: Yes -2L No Time Critical: Yes No-L Individual Performing Task:

Examiner:

Date of Evaluation: -------

Activity Code:

Method of Testing: Simulation Performance - L Discuss Setting: Classroom _ Simulator...x.- Plant, Performance Expected Completion Time: 9 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Simulator 4 (S-4)

NRC JPM S-4 Rev. FINAL Page 2 of 7 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*),

it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

After providing the initiating cue, ask the individual "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to ""talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant was operating at 100% RTP when the "B" CRD Pump tripped due to an electrical fault

• The CRS has entered OPON-3145-01, "Loss of CRD Regulating Function"

• Recirculation pump seal purge has been secured Initiating Cues:

• The pump tripped 5 minutes ago.

• You have been directed by the CRS to perform OPON-3145-01, step 3.5 to start the "A" CRD pump.

Task Standards:

• The operator starts the "A" CRD pump lAW OPON-3145-01, step 3.5 Required Materials:

• OPON-3145-01 is placekept up to step 3.4.

NRC lPM-Simulator 4 (S-4)

NRC JPM S-4 Rev. FINAL Page 3 of 7 Simulator Set-Up:

• IC- 810 (NOTE: there will be 2 other JPMs done in parallel with this from the same IC setup)

• Remove recirculation seal pump purge from service.

• Secure the "B" RWCU pump

• RUN on Scenario file NRC JPM 8-4, S-5, AND 8-6

• When each candidate has completed this JPM, reset for the next evalaution on this JPM as follows:

o Delete malfunction on KEY 2 o Restart the "B" CRD Pump o Secure the "A" CRD Pump o INSERT KEY 2 just prior to the evaluation start Provide operator with Initial Conditions/Cue (Last Page of this JPM).

EVALUATOR NOTE: In the event the operator takes an unanticipated long time such that pressure has not been restored within 20 minutes from receiving a second accumulator alarm, the operator will be expected to insert all control rods lAW step 3.1.2.

TIME START: _ _ _ _ (15 minute clock to restore CRD charging pressure to ~940 psig)

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain OPON-3145-01 and review procedure Standard: Operator obtains procedures and reviews requirements EVALUATOR CUE: When the operator asks, provide a copy of the procedure.

SAT/UNSAT Step 2: lAW OPON-3145-01. step 3.5.1.A. on CRD SYSTEM FLOW CONTROL FIC 3-301, use the display pushbutton to observe the value of the following: CRD.S and CRD.P Standard: Operator depresses the "D" pushbutton to observe the "CRD.P" value and the "CRD.S" value.

NRC lPM-Simulator 4 (S-4)

NRC ..IPM S-4 Rev. FINAL Page 4 of 7 Evaluation Performance Steps SAT/UNSAT *Step 3: lAW OPON-3145-01. step 3.5.1.B. verify CRD.S and CRD.P indicate the same value. THEN on CRD SYSTEM FLOW CONTROL FIC 3-301 depress the AIM pushbutton.

Standard: Operator adjusts setpoint signal (CRD.S) to 0.0 to match CRD.P by turning controller potentiometer counterclockwise to 0.0.

Standard: Operator depresses NM pushbutton on CRD SYSTEM FLOW CONTROL FIC 3-301 and verifies the green auto LED extinguishes and the red manual LED illuminates.

EVALUATOR NOTE: Observing the light indications is not a critical part of this step.

EVALUATOR NOTE: If the operator would need to make adjustments while in manual, step 3.5.1.C would be followed which has the operator select the CRD.v parameter and make adjustments as necessary.

SAT/UNSAT *Step 4: lAW OPON-3145-01. step 3.5.2. ADJUST the flow controller to zero to close CRD FCV-19A(Bl.

Standard: Operator rotates the potentiometer on FIC 3-301 counterclockwise to close CRD FCV-19A (CRD.V parameter). Indication of the valve closing is on CRP 9-5 bench board.

SAT/UNSAT *Step 5: lAW OPON-3145-01. step 3.5.3. START the alternate CRD pump. P-8-1A(Bl.

Standard: Operator turns the P-38-1A pump control switch to the START position and observes pumps running indications (amps, annunciators, etc.). Annunciators 5-C-5 and 5-8-8 are expected to clear.

EVALUATOR NOTE: While not procedurally required when starting a 480Vac load, a plant announcement may be made as a good practice.

NRC lPM-Simulator 4 (S-4)

NRCJPM S-4 Rev. FINAL Page 5 of7 Evaluation Performance Steps SAT/UNSAT *Step 6: lAW OPON-3145-01, step 3.5.4, slowly ADJUST the CRD flow controller to establish 48-52 gpm.

Standard: Operator rotates the potentiometer on FIG 3-301 clockwise to raise flow up to 48-52 gpm. Operator observes GRO-FCV-19A opening and CRO parameters returning to normal operational bands.

EVALUATOR NOTE: It was provided in the initial conditions that Recirculation pump seal purge was removed from service.

SAT/UNSAT Step 7: lAW OPON-3145-01. step 3.5.5.A. on CRD SYSTEM FLOW CONTROL FIC 3-301, use the display pushbutton to observe the value of the following: CRD.S and CRD.P Standard: Operator depresses the "0" pushbutton to observe the "CRO.P" value and the "GRO.S" value. The operator may write these numbers down for use in the next step.

EVALUATOR NOTE: GRD.P -56.0, CRO.S -0.0 SAT/UNSAT Step 8: lAW OPON-3145-01, step 3.5.5.B. using one or both of the following steps as plant conditions dictate. adjust the CRD system flow controller so that CRD.S and CRD.P indicate the same value.

Standard: Operator adjusts the CRD.S parameter to match the GRD.S parameter to the CRD.P parameter from step 3.5.5.A.

SAT/UNSAT Step 9: lAW OPON-3145-01. step 3.5.5.C, when CRD.S and CRD.P indicate the same value, on CRD SYSTEM FLOW CONTROL FIC 3-301 depress the AIM pushbutton.

• On GRO SYSTEM FLOW CONTROL FIG 3-301 verify the green auto LED illuminates and the red manual LED extinguishes.

Standard: Operator depresses the AIM pushbutton on FIG 3-301 and observes the light indications.

EVALUATOR NOTE: Observing the light indications is not a critical part of this step.

NRC IPM-8imulator 4 (8-4)

NRC JPM S-4 Rev. FINAL Page 6 of 7 Evaluation Performance Steps SAT/UNSAT Step 10: lAW OPON-3145-01 , step 3.5.6, IF required, THROTTLE CRD 36A(B) Pump ACB) Discharge Stop Check. to maintain charging header pressure at the flow control station at 1420-1470 psig (PI-3-34).

Standard: Operator contacts the RBAO to mark charging pressure as read on PI-3-34 and throttle CRD-36A as necessary.

EVALUATOR NOTE: When asked what pressure is on PI-3-34, inform the operator that pressure is 1450 psig and steady.

SAT/UNSAT Step 10: lAW OPON-3145-01, step 3.5.7, IF recirc pump seal purge was isolated, THEN RESTORE recirc pump seal purge to service.

Standard: Operator contacts the RBAO to place Recirculation pump seal purge in service.

EVALUATOR NOTE: When asked, acknowledge the order to place Recirculation seal purge in service. Inform the operator that the JPM is complete.

TIME FINISH: _ _ __

Terminating Cue: OPON-3145-01 has been completed with the exception of placing Recirculation pump seal purge in service. The "A" CRD pump is running.

NRC IPM-8imulator 4 (8-4)

NRC JPM S-4 Rev. FINAL Page 7 of 7 Evaluator Comments:

System KIA: Control Rod Drive Hydraulic System (201001) (A2.01 Ability to (a) predict the impacts of the following on the CONTROL ROD DRIVE HYDRAULIC SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations RO 3.2/SRO 3.3)

NRC lPM-Simulator 4 (S-4)

EXAMINEE HANDOUT Initial Conditions:

• The plant was operating at 100% RTP when the "8" CRD Pump tripped due to an electrical fault

• The CRS has entered OPON-3145-01, "Loss of CRD Regulating Function"

• Recirculation pump seal purge has been secured Initiating Cues:

• The pump tripped 5 minutes ago.

• You have been directed by the CRS to perform OPON-3145-01, step 3.5 to start the "A" CRD pump.

NRC lPM-Simulator 4 (S-4)

NRC JPM S-5 Rev. FINAL Page 1 of 10 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Testing Of Emergency Governor Failure Mode Governor Will Not RESET

Reference:

OP 4160, "Turbine Generator Surveillance" Task Number: 2457120201 Task Performance: AO/RO/SRO RO/SRO ~ SRO Only _

Sequence Critical: Yes l No Time Critical: Yes No~

Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:

Date of Evaluation: _ _ _ _ _ _ _ __

Activity Code:

Method of Testing: Simulation Performance --X. Discuss Setting: Classroom _ Simulator ~ Plant_

Performance Expected Completion Time: 9 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by:._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-8imulator 5 (8-5)

NRC JPM S-5 Rev. FINAL Page 2 of 10 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*),

it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant is at 100% power.

Initiating Cues:

• The CRS directs you to perform the once/month Emergency Governor Test from CRP 9-7 lAW OP 4160, section G.1. The test from the front standard is not required.

• A second licensed operator will monitor panel CRP 9-5 and the alarm typer as necessary.

Task Standards:

• The Oil Trip Test on the Emergency Governor is complete.

Required Materials:

• OP 4160, Turbine Generator Surveillance

• VYOPF 4160.16 with header information filled in NRC JPM-8imulator 5 (8-5)

NRC JPM S-5 Rev. FINAL Page 3 of 10 Simulator Setup:

• IC- 810 (NOTE: there will be 2 other JPMs done in parallel with this from the same IC setup)

• Run on Scenario file NRC JPM S-4, S-5 and S-6.

• INSERT KEY 1

• When each candidate has completed this JPM, reset for the next evalaution on this JPM as follows:

o Place the Emergency Governor Trip Test switch back to the normal position o Ensure KEY 1 is still active Provide operator with Initial Conditions/Cue (Last Page of this JPM).

Evaluation Performance Steps TIME START: _ _ _ _ __

SAT/UNSAT Step 1: Obtain Procedure OP 4160 and review admin limits precautions, and prerequisites.

Standard: Operator obtains the OP procedure and reviews admin limits, precautions and prerequisites.

EVALUATOR CUE: When the operator asks, provide a copy of the procedure and inform him/her that all prerequisites are satisfied.

SAT/UNSAT Step 2: Station an operator at the front standard to observe local indications.

Standard: Dispatch an AO to the front standard to observe the local indications.

EVALUATOR CUE: When asked as the AO, inform the Control Room that you are stationed at the front standard and in communication with the Control Room.

SAT/UNSAT *Step 3: Place in LOCKOUT as follows:

1) Pull EMER GOVERNOR TRIP & TEST switch handle out.

Standard: Operator pulls Emergency Governor Trip Test handle out straight out on CRP 9-7.

NRC JPM-8imulator 5 (8-5)

NRC JPM S-5 Rev. FINAL Page 4 of 10 Evaluation Performance Steps SAT/UNSAT Step 4: 2) Verify emergency governor lockout valve red LOCKOUT light (to left and above switch) illuminates and stays on.

Standard: Operator checks that RED light above and to left of switch is ON.

SAT/UNSAT Step 5: 3) Have operator at the front standard verify (lockout indication) amber EMERGENCY TRIP VALVE LOCKED OUT light is illuminated.

Standard: Direct AO at the front standard to verify amber LOCKED OUT indication is illuminated.

EVALUATOR CUE: When asked as the AO, report that the amber LOCKED OUT indication is illuminated.

SAT/UNSAT *Step 6: Place in TRIP as follows:

1)Turn the EMER GOVERNOR TRIP & TEST switch fully clockwise through RESET to the TRIP position and hold it there Standard: Operator turns the switch fully clockwise to the 3 o'clock position and holds it there.

SIM OPERATOR: Insert KEY 1 to override the switch in the TRIP position.

SAT/UNSAT Step 7: 2) Verify green TRIP light (directly above switch) illuminates and stays on while the switch is held in TRIP position.

Standard: Operator checks that GREEN light above the switch is ON.

SAT/UNSAT Step 8: 3) Verify red trip RESET light (above switch to right) extinguishes and stays out while the switch is held in TRIP position.

Standard: Operator checks that red RESET light above and to the right of the switch is NOT on.

NRC JPM-Simulator 5 (S-5)

NRC ..IPM S-5 Rev. FINAL Page 5 of 10 Evaluation Performance Steps SAT/UNSAT Step 9: 4) Verify computer alarm tvper prints TURBINE TRIP - EMERG TRIP VALVE.

Standard: Operator asks that eRO verify alarm typer prints TURBINE TRIP EMERG TRIP VALVE.

EVALUATOR CUE: When asked as the additional Control Room operator, report that the typer has printed "TURBINE TRIP EMERG TRIP VALVE",

SAT/UNSAT *Step 10: Reset the trip as follows:

1)Turn the EMER GOVERNOR TRIP & TEST switch counter-clockwise to the RESET position and hold it there Standard: Operator turns the switch counter-clockwise to the -1 :30 position and holds it there.

SAT/UNSAT *Step 11: 2) Verify green TRIP light extinguishes and stays out.

Standard: Operator observes that GREEN light above the switch is still ON.

SAT/UNSAT *Step 12: 3) Verify red trip RESET light illuminates and stays on.

Standard: Operator observes that red RESET light above and to the right of the switch is still NOT on.

SAT/UNSAT *Step 13: 4) Verify alarm typer prints TURBINE EMERG TRIP VALVE NORM.

Standard: Operator asks that additional operator in the Control Room to verify alarm typer prints "TURBINE EMERG TRIP VALVE NORM".

EVALUATOR CUE: When asked as the additional Control Room operator, report that the typer has NOT printed "TURBINE TRIP EMERG TRIP VALVE NORM" NRC lPM-Simulator 5 (S-5)

NRC JPM S-5 Rev. FINAL Page 6 of 10 Evaluation Performance Steps SAT/U NSAT *Step 14: 5) Turn the switch counter-clockwise to vertical position. but do not push in at this time.

Standard: Operator turns switch to 12 o'clock position and releases switch.

SAT/UNSAT *Step 15: 6) Observe green TRIP light stays out.

Standard: Operator observes that green TRIP light is still on.

SAT/UNSAT *Step 16: 7) Observe red trip RESET light stays on.

Standard: Operator observes that red RESET light above and to the right of the switch is still NOT on.

SAT/UNSAT *Step 17: 8) Verify alarm typer still indicates TURBINE EMERG TRIP VALVE NORM.

Standard: Operator asks that CRO verify alarm typer prints TURBINE EMERG TRIP VALVE NORM.

EVALUATOR CUE: When asked as the additional Control Room operator, report that the typer has still NOT printed "TURBINE TRIP EMERG TRIP VALVE NORM" SAT/UNSAT Step 18: 9) Have operator at the front standard verify (reset indication) red EMERGENCY TRIP VALVE RESET light is lit.

Standard: Operator directs the AO at the front standard to verify red RESET indication is illuminated.

EVALUATOR CUE: When asked as the AO at the front standard, report that the amber LOCKED OUT indication is still illuminated and the red RESET indication is NOT illuminated.

NRC JPM-Simulator 5 (8-5)

NRC ..IPM S-5 Rev. FINAL Page 7 of 10 Evaluation Performance Steps SAT/UNSAT Step 19: 10) If 6). 7). 8) or 9) above are not satisfied. return the switch to the TRIP position and repeat reset Steps G.1.d.1) through G.1.d.9).

Standard: informs the CRS that the trip failed to reset and the procedure directs to make another attempt at resetting.

SAT/UNSAT *Step 20: Reset the trip as follows:

1)Turn the EMER GOVERNOR TRIP & TEST switch counter-clockwise to the RESET position and hold it there Standard: Operator turns the switch counter-clockwise to the -1 :30 position and holds it there.

SAT/UNSAT *Step 21: 2) Verify green TRIP light extinguishes and stays out.

Standard: Operator observes that GREEN light above the switch is still ON.

SAT/UNSAT *Step 22: 3) Verify red trip RESET light illuminates and stays on.

Standard: Operator observes that red RESET light above and to the right of the switch is still NOT on.

SAT/LiNSAT *Step 23: 4) Verify alarm typer prints TURBINE EMERG TRIP VALVE NORM.

Standard: Operator asks that additional operator in the Control Room to verify alarm typer prints "TURBINE EMERG TRIP VALVE NORM".

EVALUATOR CUE: When asked as the additional Control Room operator, report that the typer has NOT printed "TURBINE TRIP EMERG TRIP VALVE NORM" NRC JPM-Simulator 5 (S-5)

NRC JPM S-5 Rev. FINAL Page 8 of 10 Evaluation Performance Steps SAT/UNSAT *Step 24: 5) Turn the switch counter-clockwise to vertical position, but do not push in at this time.

Standard: Operator turns switch to 12 o'clock position and releases switch.

SAT/UNSAT *Step 25: 6) Observe green TRIP light stays out.

Standard: Operator observes that green TRIP light is still on.

SAT/UNSAT *Step 26: 7) Observe red trip RESET light stays on.

Standard: Operator observes that red RESET light above and to the right of the switch is still NOT on.

SAT/U NSAT *Step 27: 8) Verify alarm typer still indicates TURBINE EMERG TRIP VALVE NORM.

Standard: Operator asks that CRO verify alarm typer prints TURBINE EMERG TRIP VALVE NORM.

EVALUATOR ClIE: When asked as the additional Control Room operator, report that the typer has still NOT printed "TURBINE TRIP EMERG TRIP VALVE NORM" SAT/UNSAT Step 28: 9) Have operator at the front standard verify (reset indication) red EMERGENCY TRIP VALVE RESET light is lit.

Standard: Operator directs the AO at the front standard to verify red RESET indication is illuminated.

EVALUATOR CUE: When asked as the AO at the front standard, report that the amber LOCKED OUT indication is still illuminated and the red RESET indication is NOT illuminated.

NRC JPM-Simulator 5 (S-5)

NRC JPM S-5 Rev. FINAL Page 9 of 10 Evaluation Performance Steps SAT/U NSAT *Step 29: 11) If test indications are not normal at this time, perform the following:

a) Leave the emergency governor trip/test switch in the LOCKOUT position.

Standard: Operator informs CRS that the reset is still not successful and leaves switch pulled out.

SAT/UNSAT Step 30: b) Contact the Maintenance Department.

Standard: Contacts the maintenance department. Based on the recommendation the Maintenance Department provides, step G.1.e is not performed.

EVALUATOR CUE: When asked as Maintenance, inform the Control Room the switch should be left as is and they will commence troubleshooting.

SAT/UNSAT Step 31: lAW step G.1.f. document remote test performance on VYOPF 4160.16.

Standard: Operator checks "REMOTE" and "UNSAT" EVALUATOR CUE: Inform the operator there is nothing else required for this JPM.

• Critical Step TIME FINISH: _ _ _ _ __

Terminating Cue: The Oil Trip Test on the Emergency Governor is complete.

NRC lPM-Simulator 5 (S-5)

NRC JPM S-5 Rev. FINAL Page 10 of 10 System: KIA: Main Turbine Generator and Auxiliary Systems (245000) A4.08 (Ability to manually operate and/or monitor in the Control Room: Turbine Oil Pressure RO 2.7/SRO 2.7)

NRC JPM-Simulator 5 (S-5)

EXAMINEE HANDOUT Initial Conditions:

• The plant is at 100% power.

Initiating Cues:

• The CRS directs you to perform the once/month Emergency Governor Test from CRP 9-7 lAW OP 4160, section G.1. The test from the front standard is not required.

• A second licensed operator will monitor panel CRP 9-5 and the alarm typer as necessary.

NRC JPM-Simulator 5 (S-5)

NRC JPM S-6 Rev. FINAL Page 1 of 8 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Respond to high Reactor Building Ventilation alarm Failure Mode: Reactor Building Ventilation failed to isolate

Reference:

ARS 9-5-H-1 Task Number: 2727150401 (Respond to ARM Alarms)

Task Performance: AO/RO/SRO _ RO/SRO Only ~ SE Only_

Sequence Critical: Yes No :...:.X_ _

Time Critical: Yes No X Individual Performing Task:

Examiner:

Date of Evaluation: _ _ _ _ _ __

Activity Code:

Method of Testing: Simulation Performance X Discuss Setting: Classroom _ Simulator ~ Plant.

Performance Expected Completion Time: 9 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Simulator 6 (S-6)

NRC JPM S-6 Rev. FINAL Page 2 of 8 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

After providing the initiating cue, ask the individual "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant was operating at 100% RTP when the Control Room received annunciator 9-5-H-1, "RX BLDG/REFUEL FLR CH A RAD HI

• Radiological conditions appear to be normal for current plant operations Initiating Cues:

• You have been directed by the CRS to perform the following:

o Determine the cause for the annunciator and THEN ...

o Based on the cause Confirm and backup all APPLICABLE automatic actions lAW ARS 9-5-H-1 .

Task Standards:

• Cause has been determined to be a failed upscale ARM

• PCIS Group 3 backed up, SBGT initiation backed up, RB ventilation secured backed up.

Required Materials:

• ARS 9-5-H-1, CRP 9-5 operator aid NRC JPM-Simulator 6 (S-6)

NRC JPM S-6 Rev. FINAL Page 3 of 8 Simulator Set-Up:

• IC- 810 (NOTE: there will be 2 other JPMs done in parallel with this from the same IC setup)

• Run on Scenario file NRC JPM S-4, S-5 and S-6.

• INSERT KEY 3

• When each candidate has completed this JPM, reset for the next evalaution on this JPM as follows:

o Remove Event trigger for HVAC-9, 10, 11, and 12 valves o Place control switches to their normal operational lineup (reverse backing up the valves) Refer to OP 2115 Section "L" o Ensure KEY 3 and HVAC 9, 10, 11, and 12 malfunctions are inserted and event trigger is active.

Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ _ _ __

Evaluation Performance Steps SAT/UNSAT Step 1: Obtain ARS 9-5-H-1 and review Standard: Operator obtains ARS and reviews requirements EVALUATOR CUE: When the operator asks, provide a copy of ARS 9-5-H-1.

SAT/UNSAT Step 2: Operator reviews the ARS to determine the cause and informs the CRS Standard: Operator confirms validity of the alarm by observing the failed upscale PRM on CRP 9-10 (RM 17-452A, "Rx Bldg Vent Exh South Rad Mon"). Additionally, the operator observes the note in the ARS and realizes that a failed upscale detector will result in ALL automatic actions. An additional indication used may be ERFIS to observe the high radiation alarm and indication.

EVALUATOR CUE: When informed of the cause, acknowledge as the CRS NRC JPM-8imulator 6 (8-6)

NRC ..IPM S-6 Rev. FINAL Page 4 of 8 Evaluation Performance Steps SAT/UNSAT Step 3: Operator reviews automatic actions and references CRP 9-5 operator aid to assist in confirming and back up expected automatic actions.

Standard: Operator reviews ARS and determines SBGT initiation, isolation of RB ventilation, and a PCIS Group 3 isolation should have occurred.

EVALUATOR NOTE: The operator may use OP 2115, "Primary Containment" to reference the PCIS Group 3 expected actions in place of or in addition to the CRP 9-5 operator aid.

EVALUATOR NOTE: Confirming and backing up the following automatic actions is not sequence critical and may be done in any order. They are outlined here as they are on the CRP 9-5 operator aid.

SAT/UNSAT Step 4: Operator verifies the following valves are closed:

• AC-23

• AC-8

• AC-10

• AC-9

• AC-7

• AC-7A

• AC-7B Standard: Operator observes the control switches on CRP 9-3 are in the closed position and the green indicating light above the control switch for each valve is illuminated.

SAT/UNSAT *Step 5: Operator initiates back up for valve position on AC-22B.

Standard: Operator places the control switch for AC-22B on CRP 9-3 to "CLOSE".

NRC lPM-Simulator 6 (S-6)

NRC JPM S-6 Rev. FINAL Page 5 of 8 Evaluation Performance Steps SAT/UNSAT Step 6: Operator verifies the following valves are closed:

• AC-22A

• AC-6A Standard: Operator observes the control switches on CRP 9-3 are in the closed position and the green indicating light above the control switch for each valve is illuminated.

SAT/UNSAT *Step 7: Operator initiates back up for valve position on AC-6B, SGT 6, CA-38. and AC-20.

Standard: Operator places the control switch for AC-6B, SGT-6, CA-38, and AC-20 on CRP 9-3 to "CLOSE".

SAT/UNSAT Step 8: Operator verifies the following valves are closed:

• AC-11A

• AC-11B Standard: Operator observes the control switches on CRP 9-3 are in the closed position and the green indicating light above the control switch for each valve is illuminated.

SAT/UNSAT *Step 9: Operator initiates back up for valve position on CA-38B.

Standard: Operator places the control switch for CA-38B on CRP 9-3 to "CLOSE".

SAT/LINSAT Step 10: Operator backs up SBGT auto initiation by operating the following valve control switches on CRP 9-26:

• SGT-1A

• SGT-1B

• SGT-2B

• SGT-3B Standard: Operator places the control switch for SGT-1A. SGT-1 B, SGT-2B, and SGT-3B on CRP 9-26 to the "CLOSE AUTO-OP" position NRC JPM-Simulator 6 (S-6)

NRC JPM S-6 Rev. FINAL Page 6 of 8.

Evaluation Performance Steps SAT/UNSAT *Step 11: Operator observes that R8 ventilation did NOT auto isolate.

Operator then initiates an isolation by operating the following control switches on CRP 9-26:

• HVAC-9

• HVAC-12

• HVAC-10

• HVAC-11 Standard: Operator places the control switch for HVAC-9, HVAC-12, HVAC 10, and HVAC-11 on CRP 9-26 to the "CLOSE" position.

SAT/UNSAT *Step 12: Operator initiates back up for valve position on VG-76A. VG 768. VG-26. and VG-23.

Standard: Operator places the control switch for VG-76A, VG-268, VG-26, and VG-23 on CRP 9-47 to "CLOSE".

SAT/UNSAT Step 13: Operator verifies the following valves are closed:

• NG-11A

• NG-12A

• NG-13A

• VG-22A

• VG-9A Standard: Operator observes the control switches on CAD Panel "An are in the closed position and the green indicating light above the control switch for each valve is illuminated.

EVALUATOR CUE: If asked about CAD Panel "8", inform the operator that valves on CAD panel "8" have been verified and no abnormalities were found (Simulator not modeled for CAD Panel "8".)

NRC JPM-Simulator 6 (S-6)

NRC JPM S-6 Rev. FINAL Page 7 of 8 Evaluation Performance Steps SAT/UNSAT Step 14: Operator verifies all PCIS Group 3 have been backed up completely.

Standard: Operator observes the red "SYS 1 RESET PERMISSIVE GRP3" and "SYS 2 RESET PERMISSIVE GRP3" on CRP 9-5 are illuminated.

SAT/UNSAT Step 15: Operator informs the CRS that PCIS Group 3 has been backed up. SBGT auto initiated, and RB ventilation failed to isolate and had to be manually isolated.

Standard: Operator makes report to the CRS

• Critical Step TIME FINISH: _ _ __

Terminating Cue: PCIS Group 3 has been backed up, SBGT verified running, and RB ventilation manually isolated due to failure to auto isolate.

NRC JPM-Simulator 6 (S-6)

NRC ..IPM S-6 Rev. FINAL Page 8 of 8 Evaluator Comments:

System KIA: Radiation Monitoring System (272000) A3.06 (Ability to monitor automatic operations of the RADIATION MONITORING SYSTEM including Ventilation system isolation indications RO 3.4/SRO 3.4).

NRC JPM-Simulator 6 (S-6)

EXAMINEE HANDOUT Initial Conditions:

• The plant was operating at 100% RTP when the Control Room received annunciator 9-5-H-1, "RX BLDG/REFUEL FLR CH A RAD HI

• Radiological conditions appear to be normal for current plant operations Initiating Cues:

• You have been directed by the CRS to perform the following:

o Determine the cause for the annunciator and THEN ...

o Based on the cause Confirm and backup all APPLICABLE automatic actions lAW ARS 9-5-H-1 .

NRC IPM-Simulator 6 (S-6)

NRC JPM S-7 Rev. FINAL Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Start a Reactor Feedwater Pump during Startup Failure Mode: Pump discharge valve fails to remain open

Reference:

OP 2172. Feedwater System Task Number: 2597150101 Task Performance: AO/RO/SRO RO/SRO l SRO Only Sequence Critical: Yes No X Time Critical: Yes No X Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:

Date of Evaluation: _ _ _ _ _ __

Activity Code:

Method of Testing: Simulation l Performance Discuss Setting: Classroom _ Simulator l Plant_

Performance Expected Completion Time: 8 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ _ _ _ _ _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Simulator 7 (S-7)

NRC JPM S-7 Rev. FINAL Page 2 of 6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant is operating at - 84% power with a plant startup is in progress lAW OP 0105, Phase 4B.

Initiating Cues:

• The CRS directs you to start the 'B' Feedwater pump using OP 0105, Phase 4B, step 22.

• The TBAO has walked down the RFP Room in preparation for pump start and all personnel are cleared of the area.

Task Standards:

• The 'B' feedwater pump tripped due to discharge valve failing to remain open (within 5 seconds of receiving the "FW Pump B Trip Flow Lo" alarm (6-E-5>>.

Required Materials:

• OP 0105, "Reactor Operations, Phase 4B, placekept up to step 22 NRC JPM-Simulator 7 (S-7)

NRC JPM S-7 Rev. FINAL Page 3 of6 Simulator Setup:

• IC-812

• Run on Scenario file NRC JPM S-7 Provide operator with Initial Conditions/Cue (Last Page of this JPM).

Evaluation Performance Steps TIME START: _ _ __

SAT/UNSAT Step 1: Operator obtains the procedure and reviews the step for starting a 3rd RFP and the precautions associated with OP 0105, Phase 4.

rd Standard: OP 0105 is obtained and the procedure reviewed for starting a 3 RFP.

EVALUATOR CUE: When the operator asks, provide a copy of the procedure and inform him/her that all prerequisites are satisfied.

SAT/U NSAT Step 2: On CRP 9-6 verify COND PUMP A, B, and C are running Standard: The operator observes the pump running indications for the "A",

"S", and "c" Condensate pumps (light indications, current indications, and RFP suction pressure indication)

SAT/UNSAT *Step 4: Verify Standby Lube Oil pump in service Standard: Operator verifies the Standby Lube Oil pump is in service for the "S"RFP.

NRC JPM-Simulator 7 (8-7)

NRC JPM S-7 Rev. FINAL Page 4 of 6 Evaluation Performance Steps SAT/UNSAT Step 5: On CRP 9-6. close feed pump discharge valve (FWD-4A, B, or C) for the oncoming pumps Standard: Operator closes feed pump discharge valve FWD-4B.

SAT/UNSAT Step 5: Operator makes a Gaitronics announcement for starting the "B" RFP and calls the TBAO to stand by for start of the "B" RFP Standard: Operator makes Gaitronics announcement and calls the TBAO to standby to monitor the "B" RFP after it ahs been started.

EVALUATOR CUE: When asked, inform the operator as the TBAO that you are standing by for the start of the "B" RFP.

SAT/UNSAT *Step 6: Position the feed pump control switch to START and verify the following:

• Pump breaker closes.

• Pump discharge valve opens.

• Auxiliary lube oil pump stops Standard: Operator verifies pump current rises after the pump control switch is taken to normal after start, pump discharge valve (FDW-4B) opens by observing red light ON and green light OFF above valve control switch, and the auxiliary lube oil pump stops by observing green light ON and red light OFF. Additionally, the minimum flow recirculation valve (FDW-2B) will close as adequate flow exists through the open discharge valve.

SIM OPERATORCUE: When the FDW-4B indicates full open, enter KEY 1 (CLOSE FDW-4B and indicate CLOSE on FDW 2B).

NRC JPM-Simulator 7 (S-7)

NRC JPM S-7 Rev. FINAL Page 50f6 Evaluation Performance Steps SAT/UNSAT *Step 10: Operator recognize that FDW*4B strokes closed and that FDW*2B (minimum flow recirculation valve) remains closed Standard: Operator recognizes that the pump discharge valve strokes closed and that the minimum flow recirculation valve remains closed.

SIM OPERATOR CUE: When the FDW-48 indicates full closed, enter KEY 2 (Maintains indication that FDW-48 is closed even if operator attempts to reopen the valve and gives annunciator 6-E-5 13 seconds after the discharge valve closes).

EVALUATOR CUE: If asked as the CRS for concurrence or permission to secure the RFP, then inform the operator to continue with OP 0105 for RFP start.

SAT/UNSAT *Step 11: Immediately following pump startup, ensure that the discharge valve and minimum flow valve open. If minimum flow path or normal flow cannot be established, the pump shall be immediately secured.

Standard: Operator takes the "8" RFP control switch to stop.

EVALUATOR NOTE: The operator may attempt to re-open the discharge valve EVALUATOR NOTE: If the operator does not recognize there is no minimum or normal flow path, annunciator 6-E-5 will alarm. The operator must trip the pump within 10 seconds of receiving this alarm to meet the prescribed task standard.

EVALUATOR CUE: After the "8" RFP trips, inform the operator that there are no further actions required for this JPM.

NRC JPM-Simulator 7 (S-7)

NRC JPM S-7 Rev. FINAL Page 6 of6

• CriticaI Step TIME FINISH: _ _ __

Terminating Cue: The '8' Feedwater pump tripped.

Evaluator Comments:

System: KIA: Reactor Feedwater System (259001) A4.02 Ability to manually operate and/or monitor in the Control Room: Manually start/control a RFPITDRFP RO 3.9/SRO 3.7).

NRC JPM-Sirnulator 7 (S-7)

EXAMINEE HANDOUT Initial Conditions:

• The plant is operating at,." 84% power with a plant startup is in progress lAW OP 0105, Phase 4B.

Initiating Cues:

• The CRS directs you to start the "B' Feedwater pump using OP 0105, Phase 4B, step 22.

• The TBAO has walked down the RFP Room in preparation for pump start and all personnel are cleared of the area.

NRC JPM-Simulator 7 (S-7)

NRC JPM S-8 Rev. FINAL Page 1 of 5 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Energize Bus 8 from Bus 9 Failure Mode: N/A

Reference:

OP 2143, "480 and Lower Voltage AC System" Task Number: 2620060101 Task Performance: AO/RO/SRO RO/SRO X SRO Only Sequence Critical: Yes L No_

Time Critical: Yes No~

Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:

Date of Evaluation: _ _ _ _ _ __

Activity Code: _ _ _ _ _ _ _ __

Method of Testing: Simulation Performance X Discuss Setting: Classroom _ Simulator L Plant _

Performance Expected Completion Time: 4 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by:._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Simulator 8 (S-8)

NRC "IPM S-8 Rev. FINAL Page 2 of 5 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by Circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• While operating at 100% RTP the plant experiences a loss of 4 KV Bus 3.

• The CRS has entered ON 3171, "Loss of Bus 3".

Initiating Cues:

• As directed in ON 3171, the CRS directs you to energize bus 8 from bus 9 lAW OP 2143, Appendix "C".

Task Standards:

• Bus 8 is re-energized from Bus 9 Required Materials:

• OP 2143, "480 And Lower Voltage AC System", Appendix "c" Simulator Setup:

• IC- 810

• RUN on Scenario file NRC JPM S-8 NRC JPM-Simulator 8 (S-8)

NRC JPM S-8 Rev. FINAL Page 3 of 5

• Start all available drywell RRUs

• Silence annunciators on panels other than CRP 9-8 when Bus 8 power is restored.

Provide operator with Initial Conditions/Cue (Last Page of this JPM).

Evaluation Performance Steps TIME START: _ _ __

SAT/UNSAT Step 1: Obtain Procedure, review administrative limits, precautions and prerequisites Standard: Operator obtains OP 2143 and reviews administrative limits, precautions, and prerequisite.

EVALUATOR CUE: When the operator asks, provide a copy of the procedure and inform him/her that all prerequisites are satisfied.

SAT/UNSAT Step 2: Ensure that Bus 9 is energized Standard: Checks Bus 9 energized using voltage indication on CRP 9-8 (EI 9-8-28) (or via appropriate breaker line-up)

SAT/UNSAT Step 3: Inform the CRS the need to enter the following LCOs and to declare the following equipment inoperable:

• 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cold shutdown LCO 3.10.B.1 while Bus 8 is powered from Bus 9.

• Declare both diesel generators A and B inoperable.

• Declare Buses 8 and 9 inoperable Standard: Informs CRS to enter LCO 3.1 0.B.1 , and to declare both diesel generators and buses 8 & 9 inoperable lAW OP 2143.

NRC JPM-Simulator 8 (S-8)

NRC JPM S-8 Rev. FINAL Page 4 of 5 EVALUATOR CUE: Inform the operator that TS 3.1 0.B.1 has been entered.

Evaluation Performance Steps SAT/UNSAT *Step 4: Open/confirm open breaker 88 Standard: Places control switch for Breaker 88 to OPEN. On CRP 9-8, observes green light ON, red light OFF SAT/UNSAT Step 5: Verify zero voltage on Bus 8 Standard: Checks Bus 8 voltage reading zero SAT/UNSAT *Step 6: Close Breaker 9T8 from CRP 9-8.

Standard: Places control switch for Breaker 9T8 to CLOSE and releases. Verifies Breaker 9T8 CLOSED by red light ON and green light OFF.

EVALUATOR NOTE: Operator may make a plant announcement informing the station that buses 8 and 9 are being cross tied, This announcement is not a critical portion of this step.

SAT/UNSAT *Step 7: Close Breaker 8T9 from CRP 9-8.

Standard: Places control switch for Breaker 8T9 to CLOSE and releases. Verifies Breaker 8T9 CLOSED by red light ON and green light OFF.

SAT/UNSAT Step 8: Observe Bus 8 voltage approximately 435 to 506 VAC Standard: Observes Bus 8 volts approximately 480 volts on CRP 9-8 vertical panel (EI 9-8-27)

SAT/UNSAT Step 9: Verify XFMR T-9 amps less than or equal to 160 amps on NRC JPM-Simulator 8 (S-8)

NRC JPM S-8 Rev. FINAL Page 5 of 5 EI-9-8-11.

Standard: Verifies and notes that T-9 amps are less than 160 amps on EI-9-8-11.

• Critical Step TIME FINISH: _ _ __

Terminating Cue: Bus 8 is re-energized from Bus 9 System KIA: AC Electrical Distribution (262001) (A4.01 Ability to manually operate NRC JPM-Simulator 8 (8-8)

NRC JPM S-8 Rev. FINAL Page 6 of 5 and/or monitor in the Control Room: All breakers and disconnects (including available switchyard) RO 3.4/SRO 3.7)

NRC JPM-8imulator 8 (8-8)

EXAMINEE HANDOUT Initial Conditions:

• While operating at 100% RTP the plant experiences a loss of 4 KV Bus 3,

• The CRS has entered ON 3171, "Loss of Bus 3",

Initiating Cues:

• As directed in ON 3171, the CRS directs you to energize bus 8 from bus 9 lAW OP 2143, Appendix "C",

NRC JPM-Simulator 8 (S-8)

NRC JPM P-1 Rev. FINAL Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Shutdown the nAn Diesel Generator Locally Failure Mode: N/A

Reference:

OP 2126. "Diesel Generators" Task Number: 2647230101. Shutdown the Diesel Generator Locally Task Performance: AO/RO/SRO l RO/SRO _ SRO Only_ _ AOOnly _ __

Sequence Critical: Yes X No _ _

Time Critical: Yes No X Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation X Performance Discuss Setting: Classroom _ Simulator _ Plant ~

Performance Expected Completion Time: 12 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC lPM-Plant 1 (P-l)

NRC ..IPM P-1 Rev. FINAL Page 2 of 6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the plant and you are to simulate the actions.

You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The "A" EDG has been running for 60 minutes, paralleled to the bus, loaded to 2500 KW and 500 KVAR (out) for post maintenance testing of the local control panel.

• All Operator rounds have been completed satisfactorily, and the EDG is ready to be secured.

Initiating Cues:

• You have been directed by the CRS to shutdown the EDG locally, per OP 2126, "Diesel Generators", Section "0".

Task Standards:

• The local shutdown of the diesel generator is complete and satisfactory.

Required Materials:

• OP 2126, "Diesel Generators" Simulator Setup:

N/A NRC lPM-Plant 1 (P-l)

NRC JPM P-1 Rev. FINAL Page 3 of 6 Evaluation Performance Steps Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ __

SAT/UNSAT Step 1: Obtain Procedure OP 2126 and review Precautions/Limitations.

Standard: OP 2126 obtained, reviewed the Precautions/Limitations EVALUATOR CUE: Inform operator the Precautions/Limitations are SAT.

EVALUATOR NOTE: All steps are performed in the DG A Room.

SAT/UNSAT *Step 2: On generator panel DG-1-1A, using the GOVERNOR control switch. gradually reduce load to approximately 50%.

Standard: On DG A, the operator intermittently positions diesel governor control switch to LOWER until generator unloads to 50% on Diesel Control Panel.

EVALUATOR CUE: Inform the Operator that the EDG is unloaded to 1250 KW SAT/UNSAT Step 3: Using the AUTO VOLTAGE REG ADJUST switch. adjust reactive load to as close to zero KVARs as possible Standard: Reactive load reads approximately zero KVARs.

EVALUATOR CUE: When asked, inform the Operator that KVARs are reading approximately zero SAT/UNSAT Step 4: Run unit at 50% load for 5 minutes.

Standard: Operator allows unit to run for 5 minutes at 50% load.

EVALUATOR CUE: Inform the Operator that using time-compression, The EDG has been running at 50% load for 5 minutes.

NRC JPM-Plant 1 (P-l)

NRC JPM P-1 Rev. FINAL Page 4 of 6 Evaluation Performance Steps SAT/UNSAT *Step 4: On generator panel DG-1-1A, using the GOVERNOR control switch, unload unit to < 200 kw.

Standard: Operator intermittently positions diesel governor control switch to LOWER until generator unloads to < 200KW, as indicated on the Diesel Control Panel.

EVALUATOR CUE: Inform the Operator that the EDG is unloaded to 180 KW SAT/UNSAT Step 5: On CRP 9-8 open diesel output breaker 4KV BREAKER DIESEL GENERATOR 1A.

Standard: Operator directs another operator to open the DG A output breaker from CRP 9-8.

EVALUATOR CUE: Inform the Operator that the output breaker has been Opened and EDG KW is zero; green light lit and red light out.

SAT/UNSAT Step 6: Run unloaded for approximately 1 minute.

Standard: Operator allows diesel to run unloaded for approximately one minute.

EVALUATOR CUE: Inform the Operator that using time-compression, the EDG has been running for one minute.

SAT/UNSAT *Step 7: Reset the SPEED DROOP to "Zero" Standard: Operator resets the speed droop to zero at the Diesel Governor.

(Top left knob on governor.)

EVALUATOR CUE: Inform the Operator that the speed droop is at zero.

NRC JPM-Plant 1 (P-I)

NRC JPM P-1 Rev. FINAL Page 5 of 6 Evaluation Performance Steps SAT/UNSAT Step 8: Check the voltage regulator maintaining approximately 4160V and the governor maintaining 60 Hz.

Standard: Operator observes voltage and adjusts voltage regulator as necessary to maintain 4160V, and observes frequency meter and adjusts governor as necessary to maintain 60 HZ.

EVALUATOR CUE: Inform the Operator that Voltage indicates 4160V and Frequency indicates 60 Hz.

SAT/UNSAT Step 9: Have a second operator independently verify the governor is maintaining diesel generator frequency at 60 Hz.

Standard: Operator contacts another operator to perform independent verification of EDG frequency.

EVALUATOR CUE: Inform the Operator that a second operator has performed independent verification.

SAT/UNSAT *Step 10: Stop the diesel from the DG-1-1A(B) GENERATOR panel by depressing the MANUAL ENG. STOP pushbutton.

Standard: Operator depresses the MANUAL ENG. STOP pushbutton on the Diesel Generator Control panel.

EVALUATOR CUE: Inform the Operator that the EDG slows, noise level is reduced to normal background.

EVALUATOR TERMINATING CUE: Inform the Operator that the JPM is complete.

• Critical Step TIME FINISH: _ _ __

NRC JPM-Plant 1 (P-l)

NRC JPM P-1 Rev. FINAL Page 6 of6 Evaluators Comments: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

System KIA: Emergency Generators (Diesel/Jet) (264000) (A2.02 Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/JET) ;

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Unloading prior to securing emergency generator RO 3.1/SRO 3.1).

NRC JPM-Plant 1 (P-I)

EXAMINEE HANDOUT Initial Conditions:

• The "A" EDG has been running for 60 minutes, paralleled to the bus, loaded to 2500 KW and 500 KVAR (out) for post maintenance testing of the local control panel.

• All Operator rounds have been completed satisfactorily, and the EDG is ready to be secured.

Initiating Cues:

• You have been directed by the CRS to shutdown the EDG locally, per OP 2126, "Diesel Generators" Section "0".

I NRC JPM-Plant 1 (P-l)

NRC .JPM P-2 Rev. FINAL Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Task Identification:

Title:

Isolate and Vent the Scram Air Header Failure Mode: N/A

Reference:

OE 3107. <lEOP/SAG Appendices". Appendix D Task Number: 2007550501. Perform Manual Isolation and Venting of the Scram Air Header Task Performance: AO/RO/SRO X RO/SRO SRO Only _ _ AO Only_

Sequence Critical: Yes No~

Time Critical: Yes No X Operator Performing Task: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Examiner: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date of Evaluation: _ _ _ _ _ __

Activity Code:

Method of Testing: Simulation L Performance Discuss Setting: Classroom _ Simulator _ Plant ~

Performance Expected Completion Time: 5 minutes Evaluation Results:

Performance: PASS FAIL Time Required: _ _ _ _ __

Prepared by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Exam Lead Developer Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Facility Reviewer Date NRC JPM-Plant 2 (P-2)

NRC JPM P-2 Rev. FINAL Page 2 of 6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat".

Comments are required for any "Unsat" classification. If a step is preceded by an asterisk

(*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Plant and you are to simulate all actions.

You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• Actions are being carried out lAW EOP-2, "RPV ATWS Control". The reactor is at 1000 psig and all control rods have failed to insert.

Initiating Cues:

• CRS directs you to isolate and vent the Scram Air Header per OE 3107, "EOP/SAG Appendices", Appendix D Task Standards:

• Scram Air Header isolated and vented in accordance with OE 3107, "EOP/SAG Appendices", Appendix D Required Materials:

• OE 3107, "EOP/SAG Appendices", Appendix D NRC IPM-Plant 2 (P-2)

NRC JPM P-2 Rev. FINAL Page 30f6 Evaluation Performance Steps Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ __

SAT/UNSAT Step 1: Obtain Procedure Standard: OE 3107 Appendix D obtained EVALUATOR CUE: When the operator asks, provide a copy of the procedure.

SAT/UNSAT Step 2: If reactor pressure is < 500 psi .* THEN OPEN/confirm OPEN CRD*56 Charging Water Header Supply Standard; Determines reactor pressure is >500 psig based on initial conditions or calls the control room to confirm reactor pressure.

EVALUATOR CUE: If requested inform the operator that reactor pressure is at 1000 psig (This pressure was provided as an initial condition).

SAT/UNSAT *Step 3: CLOSE/check CLOSED the following:

a.

• CRD-A1 Air filter inlet valve

b.

• CRD-A4 Air filter inlet valve Standard: CRD-A 1 and CRD-A4, Air filter inlet valve handwheels are taken to the clockwise direction until valve resistance is felt.

EVALUATOR CUE: CRD-A 1 and CRD-A4 valve handwheels rotate freely in the clockwise direction and the valve stem lowers until resistance is felt.

NRC JPM-Plant 2 (P-2)

NRC "IPM P-2 Rev. FINAL Page 4 of 6 Evaluation Performance Steps SAT/LiNSAT *Step 4: OPEN/check OPEN the following:

a.

• CRD-A2 Air filter outlet valve

b.

• CRD-A3 Air filter outlet valve Standard: CRD-A2 and CRD-A3 Air filter outlet valve are open, handwheel taken to the clockwise direction, then counter-clockwise until full open.

EVALUATOR CUE: CRD-A2 and CRD-A3 valve handwheels rotate freely in the clockwise direction, then counterclockwise until resistance is felt and the handwheel stops moving. The valve stem moves first inward then outward while the valve is moving.

EVALUATOR NOTE: One valve is already aligned in the OPEN position for normal plant operations.

SAT/UNSAT *Step 5: Open the air filter cartridge drains to vent the scram air header

a.

• Open CRD-A12 Air Filter Drain Valve

b.

• Open CRD-A13 Air Filter Drain Valve Standard: CRD-A12 and CRD-A13 Air Filter Cartridge drain valves are petcocks located on the underside of the air filters, are rotated counterclockwise.

EVALUATOR CUE: CRD-A 12 and CRD-A 13 valves rotated counterclockwise to a position parallel to the vent/drain line. The sound of air rushing out is heard.

SAT/liNSAT Step 6: Verify the scram air header is depressurized by observing decreasing pressure on scram valve pilot air pressure gayge PI-3-229 Standard: Air pressure decreasing on PI-3-229, located on the wall above the air filter.

EVALUATOR CUE: When the operator locates PI-3-229 inform him that the air pressure is decreasing.

NRC JPM-Plant 2 (P-2)

NRC JPM P-2 Rev. FINAL Page 50f6 Evaluation Performance Steps SAT/UNSAT Step 7: Inform the CRS that the scram air header has been isolated and vented Standard: The operator informs the CRS that the scram air header has been isolated and vented EVALUATOR CUE: Acknowledge the report to the CRS that the scram air header is isolated and vented. No additional actions will be required.

• Critical Step TIME FINISH: _ _ __

Terminating Cue: Scram air header isolated and vented lAW OE 3107 Appendix D.

NRC JPM-Plant 2 (P-2)

NRC JPM P-2 Rev. FINAL Page 6 of 6 Evaluators Comments:

System KIA: Control Rod Drive Hydraulics (201001) and SCRAM present and Reactor power above APRM downscale or unknown (295037) (EA 1.05 Ability to monitor and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: CRD hydraulics system RO 3.9/SRO 4.0)

NRC JPM-Plant 2 (P-2)

EXAMINEE HANDOUT Initial Conditions:

• Actions are being carried out lAW EOP-2, "RPV ATWS Control". The reactor is at 1000 psig and all control rods have failed to insert.

Initiating Cues:

• CRS directs you to isolate and vent the Scram Air Header per OE 3107, "EOP/SAG Appendices", Appendix D NRC JPM-Plant 2 (P-2)

NRC JPM P-3 Rev. FINAL Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET 2010 ILO NRC EXAM Taskldenuficauon:

Title:

Respond to RPS Power Protection Panel Trip Failure Mode: N/A

Reference:

OP 2134, "Reactor Protection System" Task !\lumber: 2127070401! Respond to RPS Power Protection Panel Trip Task Performance: AO/RO/SRO X RO/SRO SRO Only Sequence Critical: Yes X No Time Critical: Yes No X Individual Performing Task:

Examiner:

Date of Evaluation: _ _ _ _ _ _ __

Activity Code:

lVIethod of Testing: Simulation X Performance Discuss Setting: Classroom _ Simulator _ Plant 1 Performance Expected Completion Time: 15 minutes Evaluation Results:

Performance: PASS FAIL Time Required: - - - - -

Preparedby: ______________________________________

NRC Exam Lead Developer Date Reviewed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Operations Representative Date Approved by: ______________________________________

Facility Reviewer Date NRC IPM-Plant 3 (P-3)

NRC JPM P-3 Rev. FINAL Page 2 of 7 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

After providing the initiating cue, ask the individual "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Plant and you are to simulate the actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

• The plant is operating normally at full power. RPS Power Protection Panels PPP-A-1 and PPP-A-2 have tripped. In addition, the associated MG set Generator Output breaker has tripped. The trips have been determined to be spurious.

Initiating Cues:

• The CRS directs you to perform OP 2134, "Reactor Protection System", Section "F".

Maintenance is NOT available to assist in setting RPS MG Set voltage at this time.

Task Standards:

• RPS Power Protection Panels PPP-A-1 and PPP-A-2 are reset and re-powered.

Required Materials:

• OP 2134 Reactor Protection System Simulator Setup:

N/A NRC IPM-Plant 3 (P-3)

NRC JPM P-3 Rev. FINAL Page 3 of 7 Evaluation Performance Steps Provide operator with Initial Conditions/Cue (Last Page of this JPM).

TIME START: _ _ __

SATIUNSAT Step 1: Obtain Procedure OP 2134 and review precautions and prerequisites.

Standard: OP 2134 obtained, precautions and prerequisites reviewed.

EVALUATOR CUE: When the operator asks, provide a copy of the procedure and inform him/her all prerequisites are met.

SATIUNSAT Step 2: Check the status lights on the tripped RPS power protection panels to determine the cause of the trip.

Standard: Operator checks the status lights on panels PPP-A-1 and PPP A-2.

EVALUATOR CUE: Inform the operator Panels PPP-A-1 and PPP-A-2 status lights for undervoltage and underfrequency are lit.

SATIUNSAT Step 3: If the cause of the trip is the MG set then: Check the MIG set generator output voltage and adjust voltage to 118 + 1 volt.

Standard: Operator checks MG3-1 A output voltage meter.

EVALUATOR CUE: Inform the operator that the MG3-1 A output voltage meter indicates 118 volts (or As-Isft if II operating) .

SA TIUNSA T *Step 4: Position the MG3-1A output breaker to OFF.

Standard: Operator places MG3-1A output breaker to OFF.

EVALUATOR CUE: Inform Operator that breaker is tripped free NRC JPM-Plant 3 (P-3)

NRC JPM P-3 Rev. FINAL Page 4 of 7 (slightly lower than the liON" position.

Evaluation Performance Steps ISATIUNSAT *Step 5: Position the MG3-1A output breaker in ON.

Standard: Operator places MG3-1 A output breaker to ON.

EVALUATOR CUE: Inform Operator that breaker is in ON.

EVALUATOR CUE: Inform Operator that the Control Room will initiate a WR due to Maintenance not being available (step 4b).

SATIUNSAT Step 6: RESET the affected RPS Power Protection Panel as follows:

Verify Power In lamp is On.

Standard: Operator verifies that PPP-A-l POWER IN lamp is On.

EVALUATOR CUE: Inform Operator that PPP-A-l POWER IN lamp is On.

SATIUNSAT *Step 7: Place panel output breaker to OFF to reset.

Standard: Operator positions PPP-A-1 output breaker to OFF.

EVALUATOR CUE: Inform Operator that breaker is OFF.

SA TIUNSAT *Step 8: Place panel output breaker to ON.

Standard: Operator positions PPP-A-l output breaker is placed in ON.

EVALUATOR CUE: Inform Operator that breaker is ON.

SA TIUNSAT Step 9: Verify the Power Out light on the affected RPS Power Protection Panel is On.

Standard: Operator verifies that PPP-A-1 Power Out light is lit.

EVALUATOR CUE: Inform Operator that light is lit.

NRC lPM-Plant 3 (P-3)

NRC JPM P-3 Rev. FINAL Page 5 of7 Evaluation Performance Steps SA TIUNSA T Step 10: RESET the affected RPS Power Protection Panel as follows:

Verify Power In lamp is On.

Standard: Operator verifies that PPP-A-2 POWER IN lamp is On.

EVALUATOR CUE: Inform Operator that PPP-A-2 POWER IN lamp is On.

SA TIUNSA T

• Step 11: Place panel output breaker to OFF to reset.

Standard: Operator positions PPP-A-2 output breaker to OFF.

EVALUATOR CUE: Inform Operator that breaker is OFF.

SATIUNSAT

• Step 12: Place panel output breaker to ON.

Standard: Operator positions PPP-A-2 output breaker is placed in ON.

EVALUATOR CUE: Inform Operator that breaker is ON.

SA TIUNSA T Step 13: Verify the Power Out light on the affected RPS Power Protection Panel is On.

Standard: Operator verifies that PPP-A-2 Power Out light is lit.

EVALUATOR CUE: Inform Operator that light is lit.

SA TIUNSA T Step 14: Verify that the AEOG radiation monitor is indicating correctly.

Standard: Operator directs control room operator to check the indications on the AEOG radiation monitor.

EVALUATOR CUE: Inform the Operator that the AEOG radiation monitor indicates correctly.

NRC JPM-Plant 3 (P-3)

NRCJPM P-3 Rev. FINAL Page 6 of 7 Evaluation Performance Steps SATIUNSAT Step 15: At east wall of Cable Vault, Box B1024, check that RPS A VAILABLE white lamp is On.

Standard: Operator verifies that RPS AVAILABLE white lamp on Box B1024 is On.

EVALUATOR CUE: If asked, inform Operator that lamp is lit.

SATIUNSAT

• Step 16: Turn the APRM Bus A Reset selector switch to RESET and return it to NORMAL.

Standard: Operator turns the APRM Bus A Reset selector switch to RESET and returned to NORMAL on Box B1024.

EVALUATOR CUE: Inform the Operator that the switch has been rotated to RESET and returned to NORMAL SATIUNSAT Step 17: Ensure that red lamp for RPS A is On Standard: Operator verifies that the RPS A red lamp is lit.

EVALUATOR CUE: Inform the Operator the red lamp is lit.

SATIUNSAT Step 18: Contact the Control Room and request that the following actions be performed:

a) Reset of the half scram.

b) Reset of the Group 3 isolation per OP 2115 Standard: Operator contacts the Control Room and requests the following actions be performed:

a) Reset of the half scram b) Reset of the Group 3 isolation per OP 2115 EVALUATOR TERMINATING CUE: Inform Operator that the JPM is complete.

NRC JPM-Plant 3 (P-3)

NRC JPM P-3 Rev. FINAL Page 7 of 7

• Time Critical TIME FINISH: _ _ __

Evaluator Comments:

System KIA: Reactor Protection System (212000) (A2.02 Ability to (a) predict the impacts of The following on the REACTOR PROTECTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: RPS Bus power supply failure RO 3.7/SR03.9).

NRC JPM-Plant 3 (P-3)

EXAMINEE HANDOUT Initial Conditions:

• The plant is operating normally at full power. RPS Power Protection Panels PPP-A-1 and PPP-A-2 have tripped. In addition, the associated MG set Generator Output breaker has tripped. The trips have been determined to be spurious.

Initiating Cues:

• The CRS directs you to perform OP 2134, "Reactor Protection System", Section "F".

Maintenance is NOT available to assist in setting RPS MG Set voltage at this time.

NRC JPM-Plant 3 (P-3)

VY 2010 NRC Scenario 1 Page 4 of 23 SIMULATOR EVALUATION GUIDE 2010 NRC Examination NRC Evaluators: ILO Candidates CRS OATC BOP Critical Task Performance: SAT UNSAT (Circle One)

Date Administered:

Prepared by: Date:

Lead Exam Developer Reviewed by: Date:

Operations Representative Approved by: Date:

Facility Reviewer

VY 2010 NRC Scenario 1 Page 5 of 23 CREW BRIEF:

-Power level: 90% RTP

-Rod Sequence: Rapid Shutdown Sequence Latched -Rod Group: 52 with rod 14-23 the next rod

-Equipment out of service and/or tagged or abnormalities:

1. Minor seal leakage on the "C" Reactor Feedwater Pump.

2. Scheduled ISO-NE electrical grid maintenance

3. IRM"A"

-Reason For Equipment out of Service or tagged:

1. IRM "A" Detector sticking

-Applicable Tech Spec LCOs:

1. N/A EOOS Color:

Green

-Plant evolutions in progress/Scheduled Shift Evolutions:

1. A power reduction to 90% was commenced last shift.

2. Continue with a power reduction to 80% RTP lAW OP 0105, "Reactor Operations", step 5.c.2.b to support planned maintenance on the electrical grid as well as, the "C" Reactor Feedwater Pump seal. The seal has minor leakage and there are no operational restrictions on operating with the current leakage.

3. RE instruction consists of inserting the last rod in group 52 and then lower core flow to reduce reactor power to 80% RTP.

4. The plant is expected to remain at 80% RTP for -48 hours to support maintenance activities.

5. From there, maintain 80% RTP until the maintenance is complete and RFP restored to service. To support the evolution, Hydrogen Water Chemistry has been aligned to the "A" and "8" Reactor Feedwater pumps.

6. The "C" RFP discharge valve (FDW-4C) is to remain shut in preparation for the tagging order.

VY 2010 NRC Scenario 1 Page 6 of 23 SCENARIO

SUMMARY

See ES-D-1 for summary TERMINATING CONDITION(S):

1. The Drywell sprayed to lower Drywell pressure 2.5-3.5 psig and RPV water level and pressure being controlled in EOP-1 bands.

REFERENCES:

1. OP 0105, "Reactor Operations"

2. EN-OP-115, "Conduct of Operations"

3. DP 0166, "Operations Department Standards"

4. OP 2111, "CRD Hydraulic System"

5. OP 2121, "RCIC System"

6. OT 3110, "Positive Reactivity Insertion"

7. OT 3113, "Reactor Low Level"

8. Alarm Response Sheet 3-J-9

9. OT 3111, "High Drywell Pressure"

10. OT 3169, "Loss of Bus 1"

11. ON 3171, "Loss of Bus 3"

12. OT 3100, "Reactor Scram"

13. EOP-1, "RPV Control"

14. EOP-3, "Primary Containment Control"

15. Technical Specifications

VY 2010 NRC Scenario 1 Page 7 of 23 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set Up: 90% RTP

1. IC-S01 on LOI Exam Load; RUN on Scenario List NRC Scenario 1 (included are event triggers ET AC6 and ET AC6S)

2. Master FWLC setpoint set for 160 inches and displaying the "S" parameter

3. Individual FWLC controllers are displaying the "V" parameter

4. Master Recirculation Flow Controller selected for FINE adjust

5. Individual Recirculation controllers are displaying the "P" parameter

6. Rapid Shutdown Sequence available

7. Turnover checklist and TS tracking sheet filled out (VYAPF 0152.01 and 0152.02)

S. OP 0105 placekept through Phase 5A, step 5.c.2.a Discretionary Distracter Malfunctions/RFs/lOs:

1. mfDG_05B Active Preinsert Failure of the "B" EDG to start

2. mfPC_1SB06 Active Preinsert PCIS Group 3 failure (AC-6 mfPC_1 SB06B and AC-6B fail to close)

3. mfRH_03A Active Preinsert RHR-26A (Drywell Spray) fails to open

4. lOR Test 1 After"C" 3-J-9 (RHRlCS A RHdi3210AS34A RFP BUS/LOGIC FAIL) removed

5. mfAN03M8 Failure Failure of 3-M-8 annunciator from service

6. mfRC_04 Active 2 After Inadvertent initiation of RHRlCS Reactor Core Isolation TScall Cooling (RCIC) made

7. mfFW_14 0% 120 3 After RCIC Steam Flow summer fails TScall downscale made

VY 2010 NRC Scenario 1 Page 8 of 23

8. mfMS_06 .1 300 4 After Main Steam Leak in the FWLCS Drywell restored to automatic

9. mfED_03A Active 5 3 minutes Loss of 4KV Bus 1 after the scram

10. mfMS_06 1.5 120 6 6 minutes Main Steam Leak in the after the Drywell scram

11. rfFW_04 BYPASS 7 Feedwater Pump "B" condensate pump trip bypass switch.

VY 2010 NRC Scenario 1 Page 9 of 23 SIMULATOR OPERATOR INSTRUCTIONS (Continued)

Additional Instructions:

1. When asked as the FSSfTBAO to place the P-1-'IB TRIP on COND PUMP TRIP control switch to BYPASS. insert key 7.

2. When asked as the TBAO to mark the status of DC-2C, circuit 2, report that the breaker is tripped free.

3. When asked as the WWM/FSS to investigate the cause for DC-2C, circuit 2 being tripped, provide a time compressed report (when prompted by the lead evaluator) that the cause is unknown and troubleshooting is in progress.

4. When asked as the WMM/FSS to investigate the cause of RCIC inadvertently injecting.

acknowledge and make a time compressed report that the cause was due to a failed low level sensing circuit. The recommendation will be to remove the LT-2-3-72A input to the sensing circuit from service. The input from this LT to all other functions is operational.

This report will be made at the discretion of the Lead Evaluator.

NOTE (2): PRIOR to the scram, ensure you call the Control Room as I&C and inform them that the LT input to the sensing circuit was removed from service. (DELETE malfunction on KEY 2)

5. When called as the FSS/RBAO to fill and vent the RCIC system, inform the crew that time compression has been used and the RCIC system is filled and vented lAW OP 4121.

6. When asked as the WWM/FSS to investigate the cause of the failed Steam Flow Summer, acknowledge and make a time compressed report that the failure was due to an output signal failure. Additional time will be needed to troubleshoot and determine the extent of the failure. This report will be made at the discretion of the Lead Evaluator.

7. When asked as the WWM/FSS to investigate the failure of the "B" EDG to start, provide a time compressed report (when prompted by the lead evaluator) that there is an air start solenoid failure. Troubleshooting is in progress to determine the cause.

8. When asked as the WWM/FSS/RBAO to manually open RHR-26A, report that the valve is binding and cannot be opened manually.

VY 2010 NRC Scenario 1 Page 10 of 23 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Down power reduction from 90% ~ 80% RTP to support removing the "e" Reactor Feedwater Pump from Service

1. CRS Directs the OATC to commence a power reduction to BO% RTP lAW OP 0105, Phase 5, step 5.c.2.b and Recirculation flow lAW RE guidance.

2. OATC Using the rapid shutdown sequence and OP 2111, Section "AN', inserts control rods in reverse order and lower Recirculation flow until power is

-BO% RTP as outlined in the given RE guidance.

3. CRS Directs the BOP to perform VYOPF 0105.07 Decreasing power IShutdown Check Sheet

4. BOP Performs VYOPF 0105.07 consistent with down power reduction

5. CRS Directs the BOP to remove the "cn Reactor Feedwater Pump (RFP) from service lAW OP 0105, Phase 5, step B.

BOP Removes the "cn RFP from service

7. CREW Human Performance Tools consistently utilized throughout event number 1.

VY 2010 NRC Scenario 1 Page 11 of 23 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

Respond to Annunciator 3-J-9 RHRlCS A BUS/LOGIC FAIL BOP Acknowledges annunciator 3-J- ENTER KEY 1 9 and refers to appropriate Alarm Response Sheet

2. CREW Contacts the WWM/FSSrrBAO to investigate the cause of the alarm

3. BOP Informs the CRS that T.S. 3.5 applies

4. BOP After receiving the report from the WWM/FSSrrBAO that DC 2C circuit 2 was found tripped, informs the CRS.

5. CRS Enters T.S. LCO 3.5.A.6 for one CS and 1 RHR subsystem being INOPERABLE. (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cold shutdown)

EVALUATOR NOTE: Based on the pace of the scenario and direction provided from the CRS, the CREW may elect to commence a normal reactor shutdown lAW OP 0105, "Reactor Operations".

6. CREW Human Performance Tools consistently utilized throughout event number 2.

VY 2010 NRC Scenario 1 Page 12 of 23 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

Respond to an Inadvertent Initiation of Reactor Core Isolation Cooling (RCIC)

1. CREW Recognizes that RCIC has ENTER KEY 2 inadvertently initiated by either CRP 9-4 indications, water level change, or the plant computer

. typer.

2. CRS Enters and directs actions of OT 3110, "Positive Reactivity Insertion".

3. CRS After confirming that adequate feedwater exists and level is adequate, directs that RCIC be tripped lAW EN-OP-115 guidance and OT 3110.

4. BOP Trips RCIC as directed

5. CREW The crew may elect to perform OP 2121, "RCIC System",

section G, and respond to a RCIC Turbine Trip. This involves fill and vent the system and swap RCIC suction.

6. CRS Makes a power, pressure, and level report to the CRS when conditions stabilize (management expectation)

7. CREW Contact WWM/FSS to investigate the cause for the inadvertent start of RCIC

8. CRS Enters TS LCO 3.5.G.2 for RCIC being INOPERABLE.

RCIC is still available if needed as a source of high pressure injection (14 day).

9. CRS Brief the crew

VY 2010 NRC Scenario 1 Page 13 of 23

10. CREW Human Performance Tools consistently utilized throughout 1 event number 3.

VY 2010 NRC Scenario 1 Page 14 of 23 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

Respond to Reactor Low Level due to a failed steam flow summer

1. CREW Recognizes that the feedwater ENTER KEY 3 regulating valves are closing resulting in a lowering RPV water level.

2. OATC Shifts the RX VESSEL MASTER CONTROLLER to manual by depressing the AIM pushbutton (Immediate action)

3. CRS Confirms/directs as necessary that the RX VESSEL MASTER CONTROLLER is in manual.

4. CRS Enters and directs actions of OT 3113, "Reactor Low Level"

5. CREW Recognizes that the Steam Flow Summer has failed downscale and is the cause of the lowering RPV water level.

6. BOP Responds to a trip of Hydrogen Water Chemistry (failed steam flow input)

7. CREW Contacts WWM/FSS to determine the cause of the failed Steam Flow Summer.

8. CRS Directs OATC to place VESSEL LEVEL CONTROL MODE switch to the 1 ELEM position.

9. OATC Places the VESSEL LEVEL CONTROL MODE switch to the 1 ELEM position.

VY 2010 NRC Scenario 1 Page 15 of 23

10. OATC Makes a power, pressure, and level report to the CRS when conditions stabilize (management expectation)

11. CRS Directs the OATC to place the RX VESSEL MASTER CONTROLLER to automatic once conditions have stabilized.

12. OATC Places the RX VESSEL MASTER CONTROLLER to automatic.

CRS Brief the crew

14. CREW Human Performance Tools consistently utilized throughout event number 4.

VY 2010 NRC Scenario 1 Page 16 of 23 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

Respond to a small steam leak in the drywell and Reactor Scram

1. CREW Recognizes and reports rising DELETE KEY 2 along with Drywell pressure making report annotated by Note {2} on page 9.

ENTER KEY 4

2. CRS Enters and directs actions of OT 3111, "High Drywell Pressure"

• Start all available Drywell RRUs

4.

• Close AC-20

5.

• Commence a power reduction to 28.5-29.5 Mlbm/hour (if time permits)

6.

• Provide an action level to manually scram the reactor PRIOR to reaching the automatic scram setpoint

7.

• IF TIME PERMITS, may direct transferring house loads to the Startup Transformers.

8. BOP When directed perform actions of OT 3111

9.

• Start all available drywell RRUs

• Close AC-20

• Transfers house loads to the Startup Transformers

VY 2010 NRC Scenario 1 Page 17 of 23 OATC When directed, commence a power reduction to 28.5-29.5 Mlbm/hour.

Insert a manual scram at the action level provided by the CRS.

14. CRS Confirms/directs the insertion of a manual scram

15. CRS Recognizes entry condition for EOP-1 and EOP-3. Enters and directs actions of EOP-1, "RPV Control" and EOP-3, "Primary Containment Control", and OT 3100, "Reactor Scram".

16. OATC Performs and reports the following scram actions:

• Mode switch to shutdown

• Power <2%

• All control rods are inserted

• PB-1 on RX VESSEL MASTER CONTROLLER depressed

17. BOP Reports the turbine has tripped and power exists to all AC buses.

18. CRS Directs level control 127-177 inches and RPV pressure control 800-1000 psig lAW EOP-1

19. OATC Controls RPV water level 127 177 inches and RPV pressure 800-1000 psig as directed.

VY 2010 NRC Scenario 1 Page 18 of 23

20. CRS With adequate high pressure injection source and water level in band, direct HPCI inhibited once auto start at 2.3 psig.

NOTE: The crew may anticipate the automatic start of HPCI and dial the setpoint down to prevent water level from going

>177 inches.

21. CRS Verify automatic actions for EOP-1 Table "A" setpoints as necessary (127 inches)

22. CRS Brief the crew

23. CREW Human Performance Tools consistently utilized throughout event number 5.

VY 2010 NRC Scenario 1 Page 19 of 23 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Respond to a Loss of 4KV Bus 1 with failure of "B" EDG to start and a larger steam leak in the dryweU with a failure of the "A" loop RHR Drywell spray valve to open RHR-26A.

2. CREW Recognizes and reports the ENTER KEY 5 (3 MINUTES after Loss of 4KV Bus 1 the scram)

3. CRS Enters and directs actions of OPOT-3169-01, "Loss of Bus 1".

4. BOP Performs and reports the following BOP operations:

• The "6" EDG failed to start.

• Power to all AC buses except buses 1. 3. and 8

5. CREW Contacts WWM/FSS and directs them to investigate the loss of Bus 1 and the failure of the "B" EDG to start.

OATC Reports the loss of all running Feedwater Pumps.

7. CRS Directs the use of HPCI (un- ENTER KEY 6 (6 minutes after inhibit). RCIC (reset the turbine the scram) trip), "C" RFP re-started. or maximize CRD to restore and maintain RPV water level 127 177 inches.

8. OATC Maintains RPV water level 127 177 inches as directed.

VY 2010 NRC Scenario 1 Page 20 of 23

9. OATCI Continue to maintain RPV BOP pressure 800-1000 psig as directed.

NOTE: With the loss of Bus 1, the Auxiliary Oil pump is lost and eventually, the use of bypass valves will not be an option. Pressure control will need to be shifted to an alternate source (SRVs/HPCI/RCIC).

1 . CRS If time exists and resources are available. The CRS may direct Buses 6 and 7 cross ties lAW OPOT-3169-01, "Loss of Bus 1" to allow use of the MHC system for pressure control.

11. CRS Directs BOP to start all available drywell RRUs defeating interlocks as necessary

12. BOP Starts all available Drywell RRUs as necessary

13. CREW When PCIS Group 1, 2, 3, 5, or 6 fails (GROUP 3 for this CCT-1 scenario) to isolate with a leak present, initiate PCIS Group manually (SGT-6 and AC-6B). STANDARD: Leak or release terminated within 10 minutes of receipt of the auto isolation signal.

TIME of isolation (RPV level at 127 inches or Drywell pressure at 2.5 psig):

TIME SGT-6 and AC-6B are shut:

14. CRS Direct the BOP spray the Torus using the "A" Loop of RHR

15. BOP Sprays the Torus as directed

VY 2010 NRC Scenario 1 Page 21 of 23

16. CREW When torus pressure exceeds the suppression chamber CCT-2 spray initiation pressure, initiate drywell containment spray while in the safe region of the drywell spray initiation limit. STANDARD: Spray the drywell within 10 minutes of exceeding a Torus pressure of 10 psig AFTER power has been restored to Bus 3.

TIME Torus pressure at 10 psig AND means are available to spray:

"IME of the drywell is sprayed (RHR-26B open):

17. CRS Direct the Recirculation pumps and Drywell RRUs secured if running.

18. BOP If running, secure the Recirculation pumps and Drywell RRUs.

19. BOP Recognize and report that RHR 26A will not open and that the drywell can be sprayed remotely using the "A" Loop of RHR

20. CREW Contact the WWM/FSS to investigate the cause for the failure of RHR-26A to open AND manually open RHR-26A locally.

NOTE: Efforts to manually open RHR-26A will fail requiring the crew to bring the Vernon Tie on to Bus 3 and spray using the "B" Loop of RHR.

VY 2010 NRC Scenario 1 Page 22 of 23

21. CRS Direct power to be restored to Bus 3 via the Vernon Tie.

This will power Loop "B" valves from Bus 8 and power the RHRSW pumps from Bus 3.

NOTE: power will have to be restored to Bus 3 from the Vernon Tie for the "B"rD" RHRSW pumps OR manual operation of RHR-26A.

22. BOP Restore power to Bus 3 via the Vernon Tie Spray the Drywell as directed Classify the event lAW AP 3125, EAL FS1.1 RS Brief the crew

26. CREW Human Performance Tools consistently utilized throughout event number 6.

VY 2010 NRC Scenario 1 Page 23 of 23 SCENARIO 1 EVALUATOR NOTES:

VY 2010 NRC Scenario 2 Page 4 of 23 SIMULATOR EVALUATION GUIDE 2010 NRC Examination NRC Evaluators: ILO Candidates CRS OATC BOP Critical Task Performance: SAT UNSAT (Circle One)

Date Administered:

Prepared by: Date:

Lead Exam Developer Reviewed by: Date:

Operations Representative Approved by: Date:

Facility Reviewer

VY 2010 NRC Scenario 2 Page 5 of 23 CREW BRIEF:

-Power level: 100% RTP

-Rod Sequence: Rapid Shutdown Sequence Latched -Rod Group: 53

-Equipment out of service and/or tagged or abnormalities:

1. RHR-39A (TORUS SPRAY/CLG RHR)

2. IRM"A"

-Reason For Equipment out of Service or tagged:

1. RHR-39A (TORUS SPRAY/CLG RHR) valve motor actuator is being repaired (30 day LCO entered 1 day ago per TS 3.5.B.1). Repairs will take a total of 2-3 days.

2. IRM "A" Detector sticking

-Applicable Tech Spec LCOs:

1. 3.5.B.1 EOOS Color:

Green

-Plant evolutions in progress/Scheduled Shift Evolutions:

1. Maintain 100% RTP

2. Complete "OncelWeek Pump Performance Testing" lAW OP 4160, "Turbine Generator Surveillance", section B.1.c ~ B.1.f. B1.a and B1.b are complete and local testing is not desired.

VY 2010 NRC Scenario 2 Page 6 of 23 SCENARIO

SUMMARY

See ES-D-1 for summary TERMINATING CONDITION(S):

1. All Control Rods inserted, EOP-2 exited and EOP-1 re-entered with appropriate level and pressure bands directed to crew.

REFERENCES:

1. OP 0105, "Reactor Operations"

2. EN-OP-115, "Conduct of Operations"

3. DP 0166, "Operations Department Standards"

4. OP 4160, Turbine Generator Surveillance"

5. ON 3163, "Loss of DC-2AS"

6. OT 3114, "Reactor High Level"

7. OT 3110, "Positive Reactivity Insertion"

8. OT 3120, "Condenser High Back Pressure"

9. OT 3100, "Reactor Scram"

10. EOP-1, "RPV Control"

11. EOP-2, "RPV ATWS Control"

12. Technical Specifications

13. Technical Requirements Manual

VY 2010 NRC Scenario 2 Page 7 of 23 SIMULATOR OPERA TOR INSTRUCTIONS Simulator Set Up: 100% RTP

1. IC-802 on LOI Exam Load; RUN on Scenario File "NRC Scenario 2"

2. Master FWLC setpoint set for 160 inches and displaying the "S" parameter

3. Individual FWLC controllers are displaying the "V" parameter

4. Master Recirculation Flow Controller selected for FINE adjust and set at 81.00 (Ensure CTP is s1 00%.)

5. Individual Recirculation controllers are displaying the lip" parameter

6. EOOS updated for RHR-39A being INOPERABLE; DT on RHR-39A control switch

7. Rapid Shutdown Sequence available

8. Turnover checklist and TS tracking sheet filled out (VYAPF 0152.01 and 0152.02)

9. OP 4160 placekeptthrough section B.1.b

10. VYOPF 4160.01 form filled out through 'Turning Gear Oil Pump" Discretionary Distracter Malfunctions/RFs/lOs:

1. mfPC_11A Active Preinsert Failure of SBGT "A" to auto start

2. mfRD_12A 40% Preinsert Hydraulic ATWS mfRD 12B 35%

3. mfRP_01B Active Preinsert Failure of Manual Scram

4. mfED_06E Active 1 After OP Loss of DC-2AS 4160 surveillance

5. mfFW_10A 100% 120 2 AfterTS Failure of the "A" Feedwater call for control level signal Loss of DC-2AS

6. mfMC_08 .1 (1110) 300 3 After Loss of Main Condenser FWLCS is vacuum (air in leakage) restored to automatic

7. mfED_05C Active 4 After back Loss of Bus 8 pressure is stabilized

VY 2010 NRC Scenario 2 Page 8 of 23

8. mfRP_01A Active 4 30 second Failure of Automatic Scram time delay

9. mfRP 09A Failure of RWCU to mfRP_09B completely isolate

10. MfNM_05D 100% 5 After "D" APRM fails upscale power reduction of OT 3120

11. mfSL_01A Active 6 Insert key Trip of "A" SLC pump 830 seconds after the "An pump has been running

12. rfED_45 Close 7 When "N EDG Alternate Control asked by Power crew

13. rfDG_07A Reset 8 When "An EDG Annunciator Panel asked by crew

14. rfRD 02 0 9 When Close CRD-56 asked by crew

15. rfRD_20 0 10 When Close PCV-CRD-22 directed by lead evaluator

16. rfCU_06 0 11 When RWCU annunciator panel asked by crew

VY 2010 NRC Scenario 2 Page 9 of 23 SIMULATOR OPERATOR INSTRUCTIONS (Continued)

Additional Instructions:

1. When asked as the WWM/FSS to investigate the loss of DC-2AS, provide a time compressed report (when prompted by the lead evaluator) that there is a ground fault condition on DC-2AS. Extensive troubleshooting will be required to determine the location and repair. Anticipated time without DC-2AS will be 1 shift. Additionally if asked concerning concurrence to transfer control power, provide report that Electrical Maintenance gives concurrence to transfer control power.

2. When asked as the TBAO to transfer "A" EDG control power to DC-2, INSERT KEY 7

3. When asked as the WWM/FSS, acknowledge the request to station a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fire watch for the Cable Vault and provide a time compressed report that a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fire watch has been established.

4. When asked as the TBAO to acknowledge "A" EDG Control Panel annunciators, insert key 10.

5. When asked as the WWM/FSS to investigate the failure of the "A" FWLC, provide a time compressed report (when prompted by the lead evaluator) that there is a failure of the automatic output Signal in the controller. The FWLC should remain in manual control until troubleshooting, repairs, and retests are completed.

6. When asked as the WWM/FSS to investigate the high Main Condenser backpressure, provide a time compressed report (when prompted by the lead evaluator), that there is a crack in the "A" condenser casing which is allowing some air in-leakage. A work package will be generated to provide a temporary modification to repair the casing until the plant can be shutdown.

7. When asked as the WWM/FSS to investigate the loss of Bus 8, provide a time compressed report (when prompted by the lead evaluator) that there is a ground fault condition on Bus 8. Extensive troubleshooting will be required to determine the location and repair. Anticipated time without Bus 8 will be 2 shifts. Additionally if asked, inform the Control Room that they should NOT cross tie buses 8 and 9 with a fault on Bus 8.

8. When asked as the WWM/FSS to investigate the failure of the "AI! train of SBGT to auto start, provide a time compressed report (when prompted by the lead evaluator) that a lose wire was found between the auto start and "42" relay.

9. When asked as the RBAO to close CRD-56. INSERT KEY 9

10. When asked as the RBAO to close PCV-CRD-22 report that the valve is stuck in mid position and efforts are in progress to free the valve. At the discretion of the lead evaluator, the valve can be closed eventually. At this pOint. INSERT KEY 10. The local operation of this valve will insert all control rods.

VY 2010 NRC Scenario 2 Page 10 of 23 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Complete "OncelWeek Pump Performance Testing" lAW OP 4160, "Turbine Generator Surveillance", section B.i.c ~ B.1.f. Bi.a and B1.b are complete and local testing is not desired.

1. CRS Directs BOP to complete Once/Week Pump Performance Testingn lAW OP 4160, 'Turbine n

Generator Surveillance , section B.1.c~B.1.f

2. BOP Completes Once/Week Pump Performance Testing" lAW OP 4160, "Turbine Generator Surveillance", section B.1.c ~

B.1.f

3.

• Tests the emergency bearing oil pump

4.

• Tests the turbine lift pumps

• Verify pumps are available for automatic operation

• Record required data on VYOPF 4160.01

7. CREW Human Performance Tools consistently utilized throughout event number 1.

VY 2010 NRC Scenario 2 Page 11 of 23 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

Respond to a Loss of DC-2AS CREW Recognizes and reports the loss ENTER KEY 1 of DC-2AS CRS Enters and directs actions of ON 3163, "Loss of DC-2AS"

3. CREW Contacts the WWM/FSS to investigate the loss of DC-2AS

4. CRS Established a fire watch to inspect the Cable Vault every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

5. CREW With Electrical Maintenance concurrence, directs the "A" EDG control power be switched to its alternate source CREW Directs all breakers opened on DC-2AS

7. CRS Enters TS LCO for the loss of "A" EDG control power and the establishment of a Cable Vault fire watch.

• TS 3.10.6.1 (7 day)

EVALUATOR NOTE: 7 day will exist for as long as it takes to swap control power.

• TRM 3.10.6.2 (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fire watch)

8. CREW Human Performance Tools consistently utilized throughout event number 2.

VY 2010 NRC Scenario 2 Page 12 of 23 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

Respond to an upscale failure of the 'A' Feedwater Regulating valve controller

1. CREW Recognizes and reports rising ENTER KEY 2 RPV water level

2. OATC Shift RX VESSEL LEVEL MASTER CONTROLLER to manual by depressing the AIM pushbutton (immediate action)

3. OATC Shift FEEDWATER REG VLV FDW-12A CONTROLLER to manual by depressing the AIM pushbutton (immediate action)

4. CRS Verifies the Master controller and "A" FRV controllers are in manual

5. CRS Enters and directs actions lAW OT 3114, "Reactor High level"

6. CREW Diagnoses that the "A" FRV Controller is failing upscale resulting in the "An FRV fully opening resulting in a rise in water level

7. CREW Contacts the WWM/FSS to investigate the cause of the "A" FRV controller failure.

8. OATC Reports power, pressure, and level to the CRS once plant conditions stabilize.

9. OATC Reports that a positive reactivity insertion resulted in a power rise above 100% RTP.

10. CRS Enters and directs actions of OT 3110, "Positive Reactivity Insertion"

VY 2010 NRC Scenario 2 Page 13 of 23

11. CRS Direct the OATC to shift RX VESSEL MASTER CONTROLLER to automatic

12. OATC Shifts the RX VESSEL MASTER CONTROLLER to automatic as directed.

13. CRS Brief the crew

14. CREW Human Performance Tools consistently utilized throughout event number 3.

VY 2010 NRC Scenario 2 Page 14 of 23 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

Respond to High Condenser Backpressure

1. CREW Recognizes and reports rising ENTER KEY 3 Condenser backpressure EVALUATOR NOTE: If the crew doesn't recognize the rising backpressure from ERFIS point F014, then other alarms which may key the crew in would be High Dissolved O 2 , Air Ejector Off Gas flow High, or High Condenser Backpressure (5.5 in HgA)

2. CRS Enters and directs action lAW OT 3120, "Condenser High Back Pressure" Provides the crew with an action level to Scram based on rate of backpressure rise.

3. CREW Contacts WWM/FSS to investigate the loss of Main Condenser vacuum.

4. CRS Directs the OATC to reduce reactor power at 10%RTP/minute using recirculation flow until Condenser backpressure remains less than 5.OinHgA OR core flow is reduced to 28.5 29.5 Mlbm/hour.

5. OATC Reduces reactor power with recirculation flow as directed.

EVALUATOR NOTE: The intent of this event is to get a reactivity manipulation for the OATC. The power reduction will negate the adverse affect of the condenser air in-leakage, allowing it to stabilize. Once the evaluator is satisfied with the reactivity manipulation and/or implementation of OT 3120, the scenario can progress with event number 6.

VY 2010 NRC Scenario 2 Page 15 of 23

6. CREW Performs actions to support the down power reduction lAW OP 0105, "Reactor Operations" CRS Brief the crew CREW Human Performance Tools consistently utilized throughout event number 4.

VY 2010 NRC Scenario 2 Page 16 of 23 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

Respond to the loss of Bus 8 and"A" SBGT failing to start

1. CREW Recognize and report the loss ENTER KEY 4 (The failure of of 480V Bus 8 auto Scram and failure of RWCU to isolate are on a 30 second time delay to allow the Bus 8 system response to occur first).

2. OATC Reports to the CRS a half scram on RPS channel" A" along with a power, pressure, and level report (management expectation)

3. CRS Enters and directs actions lAW ON 3180, "Loss of Bus 8"

4.

• Start all available drywell RRUs

5.

• Respond to loss of RWCU

6.

• Contact Chemistry concerning Stack Gas instrumentation lost and notify the ODCM compensatory actions.

7. CREW Contacts the WWM/FSS to investigate the loss of Bus 8

8. BOP Reports a PCIS Group 3 Isolation

9. BOP Recognizes and reports that the liN train of SBGT failed to auto start as expected. Confirms and initiates the automatic response by manually starting the "A" train of SBGT (EN-OP-115)

VY 2010 NRC Scenario 2 Page 17 of 23

10. CREW Contacts WWM/FSS to investigate the cause for ION SBGT failing to auto start.

BOP Performs ON 3180 actions as directed

• Starts all available drywell RRUs

13.

• Responds to a trip of RWCU

14.

• Contacts Chemistry regarding trip of RWCU and ODCM compensatory actions for Stack Gas instrumentation being lost

15. CRS Enters a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TS LCO for various equipment lost (3.5.A.6, 3.5.B.2, 3.10.A.3).

• "B"CS

• "B" Loop RHR

• "B" loop of containment cooling with RHR-39A INOP Enter applicable LCOs for:

• "A" SBGT failure

• PCIS loss of power for RCIC-15 EVALUATOR NOTE: Any TS LCO entered which leads to a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cold shutdown is acceptable for evaluation purposes. Other LCOs are less limiting on plant operations.

16. CRS Brief the crew

17. CREW Human Performance Tools consistently utilized throughout event number 5.

VY 2010 NRC Scenario 2 Page 18 of 23 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Respond to a Hydraulic ATWS, failed Group 5 isolation, and failure of SLC pump

1. CREW Recognize and respond to "0" ENTER KEY 5 APRM failure

2. CREW Recognize the failure of RPS Channel "B" to auto scram combined with a half scram on RPS Channel "Alt.

3. OATC Depresses the manual scram pushbuttons. Recognizes and reports a failure of the manual scram pushbuttons.

4. OATC Depresses ARI/RPT pushbuttons. Recognizes and reports only partial rod insertion via ARI/RPT. Additionally, makes ATWS report to the CRS:

• ALL Rods failed to insert

• Power is >2% (give exact power when

• PB-1 depressed on RX VESSEL MASTER CONTROLLER

5. OATC Injects SLC with reactor power remaining above 2%.

Recognizes and reports that CU-18 and CU-68 did not isolate as expected. Manually shuts CU-18 and 68.

Recognizes and reports that the "A" SLC pump tripped moments after starting.

CREW Contacts WWM/FSS to investigate the cause of the "A" SLC pump tripping.

VY 2010 NRC Scenario 2 Page 19 of 23

7. CRS Confirms ARIIRPT and SLC injection as directed by EOP-2.

"RPV ATWS Control" B. CRS Enters and directs action from EOP-1, "RPV Control" and EOP-2, "RPV ATWS Control"

• 9.

• Inhibit ADS

10.

• Implement OE 3107, Appendix P

11.

• Direct implementation of OE 3107, Rod Insertion appendices

12.

• Terminate and prevent per OE 3107, Appendix GG as follows:

13.

• Maintain RPV water level

-19 ~90 inches using Feed and Condensate lAW OE 3107 Appendix GG.

14.

• Maintain RPV pressure BOO ~1000 psig using MHC/Bypass valves.

15. BOP Perform EOP-2 actions as directed

16.

• Inhibit ADS

17.

• Perform OE 3107, Appendix P

VY 2010 NRC Scenario 2 Page 20 of 23

18.

• Terminate and Prevent lAW OE 3107, Appendix GG.

o Inhibit HPIC o Place CS/RHR pumps in Pull to Lock o Take FRV controllers (4) to manual and close all the valves.

CCT-1 During an ATWS with conditions met to perform power/level control TERMINATE AND PREVENT INJECTION into the RPV using appendix GG, until conditions are met to re-establish injection. STANDARD:

completion of Terminate and prevent injection lAW OE 3107 Appendix GG within 7 minutes of loss of forced circulation.

Time ARI/RPT initiated:

Time Appendix "GG" completed: _ _ _ _ __

19. OATC Perform EOP-2 actions as directed

20.

• Control water level -19

~90 inches using feed and condensate NOTE: RCIC may be injecting at 82.5 inches. It is the discretion of the CREW to leave RCIC running or tripping it.

VY 2010 NRC Scenario 2 Page 21 of 23

21.

• Implement control rod SIMULATOR OPERATOR insertion Appendices lAW NOTES:

OE 3107 (Appendix F. G.

H.88).

CRD-56 operation on KEY 9 CCT-2: With a reactor scram PCV-CRD-22 operation on KEY 10 (directed by lead evaluator) required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to prevent exceeding the primary containment design limits. STANDARD: Actions taken within 15 minutes of the scram failure to implement appropriate appendices and/or inject SLC (Implement Appendix "G" in this scenario). Only one method needs to be used. The method must result in successful control rod insertion or SLC injection (Control rod insertion in this scenario).

Time of scram failure (APRM failed upscale): _ _ _ __

Time to control rod insertion with Appendix "Gil:

Evaluator Note: Additional time from original critical task based on failures of SLC and CRD-PCV-22.

• Report that PCV-CRD-22 is stuck in mid position and cannot be opened.

Efforts are in progress to close the valve.

VY 2010 NRC Scenario 2 Page 22 of 23

22. Control RPV pressure 800~ 1000 psig using MHC/Bypass valves.

EVALUATOR NOTES:

The success path will be to have the RBAO manually open FCV-CRO-22 due to not having power. When this valve is open, control rods will insert assuming pressure is high enough in band with Appendix "BB".

Allow several control rods to be inserted via Appendix "G" then allow CRO-22 to be opened. This will insert the remaining control rods.

23. OATC Inform CRS when control rod insertion is successful

24. CRS When all control rods are inserted and SLC verified secured, exit EOP-2 and re enter EOP-2. Direct water level band of 127~ 177 inches and pressure band 800 ~

1000 psig.

25. CRS Controls water level 127 ~ 177 inches and pressure 800~1000 psig.

26. CRS Classifies the event lAW AP 3125:

• EAL SS2.1 EAVALUATOR NOTE: This EAL classification may be evaluated is desired at the completion of the scenario.

CRS Brief the crew CREW Human Performance Tools consistently utilized throughout event number 6.

VY 2010 NRC Scenario 2 Page 23 of 23 SCENARIO 2 EVALUATOR NOTES:

VY 2010 NRC Scenario 3 Page 4 of 23 SIMULATOR EVALUATION GUIDE 2010 NRC Examination NRC Evaluators: ILO Candidates CRS OATC BOP Critical Task Performance: SAT UNSAT (Circle One)

Date Administered:

Prepared by: Date:

Lead Exam Developer Reviewed by: Date:

Operations Representative Approved by: Date:

Facility Reviewer

VY 2010 NRC Scenario 3 Page 5 of 23 CREW BRIEF:

-Power level: 100% RTP

-Rod Sequence: Rapid Shutdown Sequence Latched -Rod Group: 53

-Equipment out of service and/or tagged or abnormalities:

1. "B" train of Standby Gas Treatment INOPERABLE

-Reason For Equipment out of Service or tagged:

1. "B" train of Standby Gas Treatment INOPERABLE due to failed fan motor. The fan is placed in Pull to Lock for Tagout.

-Applicable Tech Spec LCOs:

1. 3.7.6.3.a EOOS Color:

Green

-Plant evolutions in progress/Scheduled Shift Evolutions:

1. Maintain 100% RTP

2. Perform the OP 0150, Section E, "Operations Department Weekly and Monthly Task Performance Listing" surveillances of

• swap TBCCW and lAW RP 4183

• swap RBCCW pumps lAW OP 2182

3. VYOPF 0150.08 will be documented when the surveillances are completed.

4. The swap of the TBCCW heat exchangers has been completed and all temperatures have stabilized.

5. Auto start test of the RBCCW pumps is NOT required.

VY 2010 NRC Scenario 3 Page 6 of 23 SCENARIO

SUMMARY

See ES-D-1 for summary TERMINATING CONDITION(S):

1. RPV-ED has been performed and water level is being controlled lAW EOP-1.

REFERENCES:

1. OP 0105, "Reactor Operations"

2. EN-OP-115, "Conduct of Operations"

3. DP 0166, "Operations Department Standards"

4. OP 2182, "RBCCW System"

5. RP 4183, "TBCCW System Surveillance"

6. ARS 4-M-3, "DWL SUMP VLV CLOSED"

7. OP 2143, 480V Electrical Distribution System"

8. OPON-3142-01, "Recirculation Pump Seal Failure"

9. OT 3118, "Recirculation Pump Trip"

10. OT 3119, "Loss of Stator Water Cooling"

11. ON 3158, "High Reactor Building Temperatures/Levels"

12. OT 3100 "Reactor Scram"

13. EOP-1, "RPV Control"

14. EOP-4, "Secondary Containment Control"

15. EOP-5, "RPV Emergency Depressurization"

16. Technical Specifications

VY 2010 NRC Scenario 3 Page 7 of 23 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set Up: 100% RTP

1. IC-803 on LOI Exam Load; RUN on scenario file "NRC Scenario 3"

2. Master FWLC setpoint set for 160 inches and displaying the "S" parameter

3. Individual FWLC controllers are displaying the "V" parameter

4. Master Recirculation Flow Controller selected for FINE adjust and set at 81.00 (Ensure CTP verified :5100%.)

5. Individual Recirculation controllers are displaying the "P" parameter

6. Rapid Shutdown Sequence available

7. Turnover checklist and TS tracking sheet filled out (VYAPF 0152.01 and 0152.02)

8. "8" S8GT fan is in Pull to lock Discretionary Distracter Malfunctions/RFs/lOs:

2. - 1HP16 Failure of HPCI-16 to close

3. mfRP_01A Active Preinsert Failure of automatic scram

4. mfRP_01B Active Preinsert Failure of manual scram pushbuttons

5. mfPC_2LR8294 Active 1 After weekly blown fuses for LRW-82 and surveillances LRW-94 are complete

6. mfRR_07A 100% 60 2 AfterTS call Inboard "A" Recirculation Pump for LRW Seal Failure PCIS valves

7. mfED_OSB Active 3 After ON Loss of Bus 7 3142 actions

8. mfEG_05A Active 4 After OT Trip of the "A" Stator Water 3118 Cooling pump actions

VY 2010 NRC Scenario 3 Page 8of23

9. mfHP_09 10% 240 5 l.:';rOdS In HPCI Steam leak upstream of HPCI-14

10. mfHP_09 50% 30 6 After 1 area HPCI Steam leak upstream of reached HPCI-14 (larger)

Max Safe Operating Limit

11. rfEG_06 Ack 7 When Local Stator water cooling requested annunciator panel by crew

12. mfTC_12 I Active 8 At 600 psig Bypass Valves fail to open

13. rfCD_08 OUT 9 Condensate Demineralizer "An taken out of service during downpower

14. rfCD_20 RESET 10 Condensate Demineralizer annunciator panel reset

15. rfFW_04 BYPASS 11 RFP trip on condens",to p switch

VY 2010 NRC Scenario 3 Page 9 of 23 SIMULATOR OPERATOR INSTRUCTIONS (Continued)

Additional Instructions:

1. When asked as the WWM/FSS to investigate the cause for the blown fuse provide a time compressed report (when prompted by the lead evaluator) that fuse F-21 was blown and a work package is being written to replace the fuse (CWD 1114)

2. When asked as the WWM/FSS to investigate the inboard seal failure, acknowledge the request. No additional reports will be made concerning the failure

3. When asked as the RBAO to verify seal purge flow to the "A" Recirculation pump, report that seal purge flow is normal and there are no abnormalities.

4. When the TBAO is contacted during the downpower to perform the following, insert the given key and make follow-up report:

• Take Condensate Demineralizers out of service (INSERT KEY 9 for the "A" Condensate Demineralizer)

• Acknowledge Condensate Demineralizer annunciator panel INSERT KEY 10

• Place "B" RFP trip on Condensate pump switch to bypass INSERT KEY 11

5. When asked as the WWM/FSS to investigate the loss of Bus 7, provide a time compressed report (when prompted by the lead evaluator) that there is a ground fault condition on Bus 7. Extensive troubleshooting will be required to determine the location and repair. Anticipated time without Bus 7 will be 2 shifts.

6. When asked as the WWM/FSS to investigate the failure of the "A" Stator Water Cooling pump, acknowledge and provide a time compressed report that the pump tripped on an overload condition. Troubleshooting will be required to determine the cause.

7. When asked as the TBAO acknowledge local annunciators at Stator Cooling alarm panel, INSERT KEY 7.

8. When asked as the WWM/FSS/FB Leader to investigate the Fire Alarm location, acknowledge and make a time compressed report that there is a large amount of steam coming from the HPCI Room and the environment should not be entered without appropriate Personal Protective equipment. Additionally, report there is no visual indication of a fire in the area.

9. When asked as the WWM/FSS to close HPCI-15 and HPCI-16, report that efforts are being made to coordinate with RP. The valves will remain open for the remainder of the scenario until AFTER the RPV-ED is performed and at the discretion of the lead evaluator.

Additionally, steam was observed coming from the HPCI room by the RBAO.

VY 2010 NRC Scenario 3 Page 10 of 23 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Transfer running TBCCW and RBCCW pumps

1. CRS Directs swapping the TBCCW and RBCCW pumps lAW RP 4183 and OP 2182

2. BOP Swaps the TBCCW and RBCCW pumps lAW RP 2183 and OP 2182

3.

• Transfers RBCCW pumps lAW OP 2182, Section "0"

4.

• Transfers TBCCW pumps lAW RP 2183, Section "H"

5. CRS Documents VYOPF 0150.08 will be documented after the pumps are swapped

6. CREW Human Performance Tools consistently utilized throughout event number 1.

VY 2010 NRC Scenario 3 Page 11 of 23 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

Respond to a Blown fuses for LRW-82 and LRW-94

1. CREW Recognizes and reports ENTER KEY 1 annunciator 4-M-3, "OWL SUMP VLV CLOSED"

2. BOP Informs the CRS that valve position indication is lost for LRW-82 and LRW-94

3. CREW Contacts WWM/FSS to investigate the cause of the loss of valve position indication

4. BOP Once the crew is informed the valves have lost solenoid power and subsequently shut due to a blown fuse, positions the control switch for LRW-82 and LRW-94 to shut to backup indications.

(This shuts LRW-83 and LRW 95).

The crew may observe that the IOPL Group 2 Sys 1 red indicating light will not be lit on CRP 9-5 due to blown fuse.

NOTE: This is not procedurally driven however it's a basic operator fundamental of understanding the system.

5. CRS Enters TS LCO loss of sampling capability and failed PCIS valves.

• TS 3.6.C.2 (7 day)

• TS 3.7.0.2 and 4.7.0.2

6. CREW Human Performance Tools consistently utilized throughout event number 2.

VY 2010 NRC Scenario 3 Page 12 of 23 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

Respond to a failure of the "A" Recirculation pump inboard seal

1. CREW Recognizes and responds to ENTER KEY 2 Annunciator 4-C-2, "PUMP A INNER SEAL LKG HI/LO"

2. CREW Contact the WWM/FSS to investigate the failure of the inboard Recirculation pump seal on the "A" Recirculation pump.

3. CREW Observes CRP 9-4 indications to support an inboard seal failure on the "A" Recirculation Pump:

• No.2 (OUTBD) seal pressure approaching No.1 (lNBD) seal pressure

• Seal leakage through No.

2 orifice increasing to

-1.1 gpm giving a PUMP A(B) INNER SEAL LKG HIILO alarm (4-C-2)

• With the increase in leakage, seal cavity temperatures may decrease

4. CRS Enters and directs action of OPON-3142-01, "Recirculation Pump Seal Failure

• Monitor seal temperatures for the"A" Recirculation pump.

S. CREW Monitors for potential outboard seal failure. Recognizes that if the outboard seal fails, they will not be able to monitor leakage with the sumps isolated.

VY 2010 NRC Scenario 3 Page 13 of 23 CREW Contacts RBAO to verify A" U Recirculation pump seal purge and check for any abnormalities.

7. BOP Monitors seal temperatures closely at an interval identified by the CRS (Allen Bradley Temperature Monitoring)

CRS Brief the crew

9. CREW Human Performance Tools conSistently utilized throughout event number 3.

VY 2010 NRC Scenario 3 Page 14 of 23 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

Respond to a loss of Bus 7, "B" Recirculation Pump trip

1. CREW Recognizes and reports the loss ENTER KEY 3 of Bus 7 CREW Recognizes and reports the trip of the "B" Recirculation Pump OATC Monitor and reports power, pressure, level following the Recirculation Pump trip transient.

NOTE: Water level will rise and approach the high level turbine trip setpoint. As long as water level is 160 inches at start of transient, the plant will stay online with no operator action.

CREW Contacts WWM/FSS to investigate the cause of the loss of Bus 7

5. CREW Recognizes the plant is outside the MELLLA region on the Power to Flow map.

6. CRS Enters and supervises/directs actions of OT 3118, "Recirculation Pump Trip".

7.

• Shut "B" Recirculation pump discharge valve RV-53B

8.

• Down power reduction to 40-45% RTP using the rapid shutdown sequence.

9.

• Secure a RFP lAW OP 0105

VY 2010 NRC Scenario 3 Page 15 of 23

10.

• Reduce "N Recirculation pump speed to 65-70%.

11.

• After 5 minutes re-open discharge valve

12. OATC Reduces reactor power using the rapid shutdown sequence to 40-45% RTP as directed.

NOTE: This will be approximately rod 22-07 on rod group 49.

BOP Performs actions of OT 3118 as directed

14.

• Closes discharge valve RV-53B

15.

• Secures RFP

16.

• Re-opens discharge valve

17. OATC Reduces speed of "A" Recirculation pump to 65-70%

as directed.

BOP Performs required actions and notifications lAW OP 0105 down power check list.

19. BOP lAW ARS 7-D-7 and 7-D-8.

places Generator Leads fan to the correct operatin9 condition.

NOTE: If this is not done. the alarms will cycle in and out based on being near the low flow setpoint.

20. CRS Enters TS LCO for single loop operations.

• TS 3.6.G.1

VY 2010 NRC Scenario 3 Page 16 of 23 21 CREW Refers to OP 2143, "480V Electrical Distribution System",

ARSs, and P&IDs to address the other Bus 7 loads lost.

22. CRS Brief the crew

23. CREW Human Performance Tools consistently utilized throughout event number 4.

VY 2010 NRC Scenario 3 Page 17 of 23 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

Respond to a trip of the "A" Stator Water Cooling pump and a subsequent loss of all Stator Water Cooling (Scram lAW OT-3100 and control the reactor plant lAW EOP-1) .

Recognizes and report CREW annunciator 7-B-5, and 7-C-5. ENTER KEY 4 CREW Recognizes a trip of the "A" Stator Water Cooling pump and a complete loss of Stator Water Cooling with the potential for a subsequent automatic turbine trip and reactor scram within 1 minute.

EVALUATOR NOTE: The CRS may direct an attempt to restart the "A" Stator Water Cooling pump.

CRS Enters and directs/verifies action of OT 3119, "Loss of Stator Water Cooling"

• Directs the OATC to manually scram the reactor

• Directs the BOP to manually trip the turbine

4. BOP Depresses the MTS-1/MTS-3 pushbutton OATC Reports that the manual scram pushbuttons failed and an ARIIRPT was initiated to insert all control rods.

VY 2010 NRC Scenario 3 Page 18 of 23

6. CRS Enter and direct actions of OT 3100, "Reactor Scram" and EOP-1, "RPV Control"

• Direct RPV water level band of 127-177 inches with Feed and Condensate

• Direct RPV pressure band of 800-1000 psig with MHC

7. OATC When directed, insert a manual scram and take actions lAW OT 3100, "Reactor Scram". Make scram report to the CRS:

• Mode Switch is in SHUTDOWN

• Power <2%

• All control rods are inserted

• PB-1 depressed on MASTERFWLC

• Manual scram push buttons failed and ARI/RPT inserted

8. CRS Directs EOP-1, Table "A" automatic actions to be confirmed.

9. BOP Report Power available to all AC buses

10. OATC Inserts SRMs and IRMs to monitor Nuclear Instrumentation during the shutdown.

crew

1. CRS

12. CREW Human Performance Tools consistently utilized throughout event number 5.

VY 2010 NRC Scenario 3 Page 19 of 23 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Respond to HPCI Steam Line Leak and Failure of PCIS Group VI; Perform an RPV-ED

1. CREW Recognize and respond to the ENTER KEY 5 After Control following annunciators/alarms: Rods are inserted.

• CP 115-3 Control Room Fire Protection Panel ZONE 11 fire alarm (RB Panel)

• 4-H-1, "STEAM LEAK DET PANEL TEMP HI" EVALUATOR NOTE: The crew may elect to NOT respond to the CP 115-3, Zone 11 alarm lAW OP 3020, "Fire Emergency Response Procedure" and OP-2186, "Fire Suppression Systems" once it becomes evident that the cause for the alarm is a steam leak.

2. CREW Directs WWM/FSS/FB Leader to coordinate with RP to investigate fire and/or leak location and extent.

BOP Recognize a steam leak in the HPCI System and that HPCI-15, HPCI-16 failed to isolate.

Attem pts to close HPCI by:

• taking control switches on CRP 9-3 to close

• taking the manual isolation control switch on CRP-9-3 to isolate Reports to the CRS that HPCI 15 and HPCI-16 failed to isolate automatically and manually from the Control Room.

4. CRS Enters ON 3158, "High Reactor Building Temperatures/Levels"

VY 2010 NRC Scenario 3 Page 20 of 23

5. CREW When a leak is present, CCT-1 dispatch personnel to manually isolate associated PCIS valves that have failed to isolate automatically and manually from the Control Room. STANDARD: Direct Maintenance to manually isolate PCIS valves within 15 minutes of receipt of the isolation signal.

Time leak is initiated:

Time maintenance is contacted to shut the valves:

EVALUATOR NOTE: The critical aspect of this will be to contact maintenance to get the valves manually shut.

The lead evaluator will not allow the valves to be shut until the RPV-ED but after the RPV-ED, the valves can be shut.

6. CREW Recognizes rising temperatures INSERT KEY 6 after one area in the Reactor Building exceeds Max Safe Operating (Channels 6, 8, 9, 12, 15, and Limit.

16).

7. CRS Directs that RB HVAC trips be bypassed lAW EOP-4, OE 3107, Appendix "AA".

8. BOP When directed bypass RB HVAC trips lAW OE 3107, Appendix "AA"

• Install jumper on CRP 9-15 EE6-7EE9

• Install jumper on CRP 9-17 BB10-7BB11

VY 2010 NRC Scenario 3 Page 21 of 23

9. OATCI When directed, Anticipate and INSERT KEY 8 if pressure RPV-ED lAW EOP-1, override reached 600 psig during the BOP RC/OR-4 by rapidly cooldownlanticipate RPV-ED.

depressurizing the RPV using bypass valves (Bypass Opening Jack) irrespective of the cool down rate

10. CRS Verifies a reactor scram and entry into EOP-1 BEFORE any parameter reaches its MAX SAFE OPERATING LIMIT.

NOTE: Channels 12 and 15 are the two areas that rise the quickest. See above for EOP-1 actions.

11. CREW With a Primary system discharging into Secondary CCT-2 Containment and area radiation/temperature/water levels exceed Maximum Safe Operating Levels in more than one area, initiate an RPV-ED. STANDARD: Initiate RPV-ED within 5 minutes of area radiation, temperature, or water level exceeding Maximum Safe Operating Levels in more than one area.

Time the second area temperature exceeds the Maximum Safe Operating Limit: _ _ _ _ __

Time SRVs are opened:

12. CRS Enters and directs actions of EOP-5, "RPV Emergency Depressurization". (Channels 12 and 15 exceed Max Safe Operating Limit)

VY 2010 NRC Scenario 3 Page 22 of 23 CRS Directs action lAW DP 0166 once WR level reaches 82.5 inches SRVs

15. OATC Restores and maintains RPV level>T AF using low pressure injection or condensate systems during the RPV-ED (Table "C")

16. CRS Make E-Plan classification, EAL FS1.1

17. CREW Human Performance Tools consistently utilized throughout event number 6.

VY 2010 NRC Scenario 3 Page 23 of 23 SCENARIO 3 EVALUATOR NOTES:

VY 2010 NRC Scenario 4 Page 4of24 SIMULATOR EVALUATION GUIDE 2010 NRC Examination NRC Evaluators: ILO Candidates CRS OATC BOP Critical Task Performance: SAT UNSAT (Circle One)

Date Administered:

Prepared by: Date:

Lead Exam Developer Reviewed by: Date:

Operations Representative Approved by: Date:

Facility Reviewer

VY 2010 NRC Scenario 4 Page 5 of 24 CREW BRIEF:

-Power level: -1 % RTP, Summer operations

-Rod Sequence: A2 -Rod Group: 23

-Equipment out of service and/or tagged or abnormalities:

1.

-Reason For Equipment out of Service or tagged:

1.

-Applicable Tech Spec LCOs:

1. N/A EOOS Color:

Green

-Plant evolutions in progress/Scheduled Shift Evolutions:

1. A plant startup and heat up are in progress. The goal for the remainder of the shift is to continue the startup lAW OP 0105, "Reactor Operations", Phase 2D, step 1 by performing the following CONCURRENTLY:

• commence a steam chest warm up (Phase 20, step 1)

• continue rod withdrawals to establish MPR operability (Phase 20, step 2a ~2b)

VY 2010 NRC Scenario 4 Page 6 of 24 SCENARIO

SUMMARY

See ES-D-1 for summary TERMINATING CONDITION(S):

1. RPV-ED has been performed and water level is being controlled lAW EOP-2.

REFERENCES:

1. OP 0105, "Reactor Operations"

2. EN-OP-115, "Conduct of Operations"

3. DP 0166, "Operations Department Standards"

4. OP 2134, "Reactor Protections System"

5. ARS 5-N-2, "IRM CH B HI-HI/INOP"

6. OP 2131, "Intermediate Range Monitor Channels"

7. OP 3127, "Natural Phenomena"

8. OT 3165, "Loss ofTBCCW"

9. ARS 7-K-9, "STM SEAL HDR PRESS LO"

10. AP 3125, "Emergency Plan Classification and Action Level Scheme"

11. OT 3122, "Loss of Normal Power"

12. OT 3100 "Reactor Scram"

13. EOP-1, "RPV Control"

14. EOP-2 "ATWS RPV Control"

15. EOP-3. "Primary Containment Control"

16. EOP-4, "Secondary Containment Control"

17. EOP-5, "RPV Emergency Depressurization"

18. ON 3158, "Reactor Building High Area TemperaturelWater Level"

19. Technical Specifications

20. Technical Requirements Manual

VY 2010 NRC Scenario 4 Page 7 of 24 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set Up:

1. IC-804 on LOI Exam Load; RUN on Scenario File "NRC Scenario 4"

2. Auxiliary FWLC setpoint set for 160 inches and displaying the "S" parameter

3. Master Recirculation Flow Controller selected for FINE adjust

4. Individual Recirculation controllers are displaying the "P" parameter (0.00)

5. A2 Rod Sequence available and mark up through Group 23 for the next control rod to be withdrawn

6. VYOPF 0105.05 filled out up to Phase 2D; OP 0105, Appendix "E" placekept up to Phase 2D.

7. Turnover checklist and TS tracking sheet filled out (VYAPF 0152.01 and 0152.02)

8. If applicable, remove the IRM "An caution tag for this scenario Discretionary Distracter Malfunctions/RFs/lOs:

1. mfRP_01B Active Preinsert Failure to manual scram

2. mfDG_09B Active Preinsert Failure of the DBn EDG breaker from Auto closing

3. mfNM_03F 100% 1 After IRM "F" fails upscale reactivity manipulatio n and steam chest warmup

4. rfPP_06 EVNT 2 AfterTS call Seismic Event for failed IRM

5. SL_03 15% 2 SLC Tank Leak

6. mfSW_14A Active 2 10 second "N TBCCW pump Trip delay

7. mfSW_21B Active 2 10 second Failure of "B" TBCCW pump to delay Auto start

8. mfMS_09 Active 2 20 s Failure of the Gland Seal time delay Regulator

9. rfPP _06 EVNT 3 After OP Seismic Event aftershock 3127 has been addressed first time

VY 2010 NRC Scenario 4 Page 8 of 24

10. mfED_17 Active 3 5 second Loss of Off Site Power time delay

11. mfPC 10 65% 750 3 Torus leak

12. mfRD_022227 Active 3 Stuck control rod 22-27

13. mfRD_021 035 Active 3 Stuck control rod 10-35

14. mfRD_023011 Active 3 Stuck control rod 30-11

15. mfRD_021 019 Active 3 Stuck control rod 10-19

16. rfCS_01 100 30 4 -BA CST suction valve

17. rfCS_02 100~0 5 CS-BB CST suction valve

18. mfSL 03 0% 6 Prior to SLC tank leak malfunction calling the removed Control Room to inform them SLC-11 is closed

VY 2010 NRC Scenario 4 Page 9 of 24 SIMULATOR OPERATOR INSTRUCTIONS (Continued)

Additional Instructions:

1. When asked as the WWM/FSS to investigate the failed IRM "F", acknowledge and make a follow-up time compresses report that the failed IRM was due to a failure of the output amplifier. A Work Order is being generated to make repairs on IRM "F".

2. One minute after the first seismic event, call the Control Room as the TBAO on the Turbine Deck and report that you felt seismic activity on the Turbine Deck

3. When contacted as The Wilder Dam. maker a time compressed report that walkdowns of the Dams are in progress and there are no reports of structural damage associated with the seismic event.

4. When asked as the WWM/FSS to investigate the following. acknowledge and make a report that troubleshooting efforts are in progress. No additional information will be provided for these two equipment failures:

• Failure of standby TBCCW pump to auto start

• Failure of Gland Seal Regulator

5. After the order to perform OP 3127. Appendix "A" walkdowns is given to the AOs. make a time compressed report 5 minutes later from the FSS that there is a leak in the common SLC pump suction header. Additionally report that is can be isolated by shutting locked open valve SLC-11. "Standby Liquid Control Tank Outlet". When ordered to shut SLC-11.

report that SLC-11 is shut and the leak has stopped (INSERT KEY 6).

6. When asked as the WWM/FSS to investigate the failure of the "B" EDG breaker to close, acknowledge and make a report that troubleshooting efforts are in progress. No additional information will be provided for this failure.

7. When asked as the WWM/FSS to investigate the Torus leak, acknowledge and make a report that there is a break in the 24inch weld on the "A" RHR Torus suction line and there is about 1 inch of water on the Torus basement floor and rising. Continue to make follow up reports as requested concerning the rising water level on the Torus basement floor.

S.. When asked as the FSS/RBAO to open CS-SA and CS-SB lAW OE 3107, Appendix "W",

make a time compressed report 2 minutes (CS-SA) and 5 minutes (CS-SB) later that each of the valves are open (INSERT KEYS 4 and/or 5).

VY 2010 NRC Scenario 4 Page 10 of 24 OPERATOR ACTIONS EVENT NUMBER 1,2 Crew Task

Description:

Perform a Turbine Chest Warm up and continued power ascension

1. CRS Directs BOP to perform Turbine Chest Warmup OP 0105, Phase 2D, step 1.

2. BOP Performs Turbine Chest Warmup as directed

3. Reset the Emergency Governor

4. Reset turbine Vacuum Trip MTS-1

5. Verify load limiter is latched

6. Check the No.2 stop valve bypass is fully closed.

7. Partially open the No.2 stop valve bypass control switch while the control valves are closed to equalize pressure across the turbine stop valves B. After it is determined that the 60°F L\T will not be exceeded, continue opening No.2 stop valve bypass until all stop valves ramp open (T017 and T018 ERFIS points)

9. CRS Initials and dates/time on VYOPF 0105.05 Phase 2D, step 1

VY 2010 NRC Scenario 4 Page 11 of 24 CRS Directs continued power ascension using control rod withdrawal lAW A2 Rod Sequence OATC Withdraws control rods as directed lAW A2 rod sequence BOP Continues to monitor turbine chest warmup parameters.

EVALUATOR NOTE: Once the required reactivity manipulation and normal evolution is observed, the scenario can move forward with event number 2.

13. CREW Human Performance Tools consistently utilized throughout event number 1.

VY 2010 NRC Scenario 4 Page 12 of 24 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

Respond to a failure of the IRM channel "F" upscale

1. OATC Recognize and respond to the INSERT KEY 1 following annunciators:

• 5-0-3, "ROD WITHDRW BLOCK"

• 5-L-1, "AUTO SCRAM CHB"

• 5-L-2, "NEUTRON MON POWER HI"

• 5-N-2, "IRM CH B HI HI/INOP"

• 5-N-3, "IRM HI"

2. OATC Reports to the CRS that there is a half scram on Reactor Protection System (RPS) channel "B" due to the "F" Intermediate Range Monitor (IRM) failing upscale

3. CREW Contact WWM/FSS to investigate the failure of IRM channel "F"

4. BOP Observes local indications on CRP 9-12 and reports that IRM "F" is reading Hi and Hi-Hi.

5. CRS Directs the "F" IRM be bypassed lAW ARS 5-N-2 OR OP 2131, section "C",

Inoperable IRM.

6. OATC Bypasses IRM channel "F" as directed (annunciators 5-0-3, 5 N-2, and 5-N-3 clear as expected)

VY 2010 NRC Scenario 4 Page 13 of 24

7. CRS Directs the half scram on RPS channel "B" be reset lAW ARS 5-N-2 and OP 2134, section "H".

8. OATC Resets the half scam on RPS "B" as directed.

Annunciators 5-L-1 and 5-L-2 will clear as expected.

9.

• PLACE the SCRAM RESET switch to the "Group 2 and 3" position

10.

• PLACE the SCRAM RESET switch to the "Group 1 and 4" position

11.

• PLACE the SCRAM RESET switch back to the Group 2 and 3 position

12.

• Directs BOP to verify the following relays are Energized on CRP 9-15 and CRP 9-17 CRS Consults Technical Specifications (TS) and Technical Requirements Manual (TRM).

Enters TS LCO for tracking the "F" IRM channel lAW Table 3.1.1 and TRM Table 3.2.5.

14. CREW Human Performance Tools consistently utilized throughout event number 2.

VY 2010 NRC Scenario 4 Page 14 of 24 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

Respond to a Seismic event, failure of the Gland Seal Regulator, Trip of the "A" TSCCW Pump and Failure of the "S" TSCCW pump to auto start

1. CREW Recognizes and reports INSERT KEY 2 annunciator 7-M-7, "SEISMIC MONITOR ALERT"

2. BOP Acknowledges annunciator and confirms an actual seismic event has occurred at the AR 117-1 reflash unit (inside CRP 9-8).

3. OATC Responds to Annunciators 6-J

7. "TBCCW PUMP AlB TRIP' and 6-J-8, "TBCCW HDR PRESS LO".

4. OATC Recognizes and report the trip of the "A" TBCCW pump and the failure of the "B" TBCCW pump to auto start.

Performs immediate actions of OT 3165, "Loss of TBCCCW" and manually starts the "B" TBCCW pump.

5. CRS Verifies/Directs immediate action of OT 3165 to manually start the "B" TBCCW pump.

6. BOP Responds to annunciator 7-K-9, "STM SEAL HDR PRESS LO".

VY 2010 NRC Scenario 4 Page 15 of 24

7. BOP Reports that seal steam pressure is low due to a suspected Gland Seal Regulator Failure.

Recommends taking action lAW ARS 7-K-9 to throttle open MS 10, Steam Seal Regulator Bypass valve.

EVALUATOR NOTE: In the event the crew fails to respond to the loss of seal steam lAW the ARS, they may diagnose this as High Condenser backpressure and thus respond lAW OT 3120, "Condenser High Backpressure". If this is the case, follow-up action step 4 will address MS-10.

EVALUATOR NOTE: The longer it takes to address this issue, the more impact it will have on Advanced Off Gas (AOG) and the OG-516A, Ejector Suction Pressure Control valve, closing. This can also be addressed in OT 3120.

8. CRS Directs BOP to throttle open MS-10.

9. BOP Throttles open MS-10 to raise seal steam pressure to above the alarm setpoint.

10. CREW Contacts WWM/FSS to investigate the trip of the"A" TBCCW pump, failure of the "B" TBCCW pump to auto start, and the failure of the Gland Seal Regulator.

11. CRS Enters and directs actions of OP 3127, "Natural Phenomena", step 6.

VY 2010 NRC Scenario 4 Page 16 of 24

12. Classify the event lAW AP 3125:

• EAL HA1.1 EVALUATOR NOTE: This EAL classification may be evaluated if desired after the scenario is complete.

13. CREW Performs actions of OP 3127 as directed:

14.

• Checks for control rod drifts

15.

• Checks instrument air pressure

16.

• Checks tank level indications

17.

• Calls Wilder Dam

18.

• Direct plant walkdowns using Appendix "Aft EVALAUTOR NOTE: When asked as the STA to check Seismic Monitor Workstation to see if OBE was exceeded, inform the CRS that OBE was exceeded.

EVALAUTOR NOTE: 5 minutes after Appendix "Aft walkdowns have been directed, direct booth operator to call the Control Room, informing the CRS that there is a small leak in the SLC Tank (instruction number 5 on page 9)

CRS Directs the FSS/RBAO to shut SLC-11 to isolate SLC tank leak.

20. CRS Consults Technical Specifications (TS).

Enters TS LCO 3.4.D and directs WWM/FSS to investigate the leak and make repairs. With SLC-11 shut, both SLC pumps are out of service (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO)

21. CR:S I Brief the crew

VY 2010 NRC Scenario 4 Page 17 of 24

22. CREW Human Performance Tools consistently utilized throughout event number 3.

VY 2010 NRC Scenario 4 Page 18 of 24 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

Respond to a Seismic Event aftershock, Loss of Normal Power, failure of the "8" EDG breaker to auto close, Torus leak, ATWS (4 control rods out)

1. CREW Recognizes and reports ENTER KEY 3 annunciator 7-M-7. "SEISMIC MONITOR ALERT". shortly thereafter a Loss of Normal Power.

EVALUATOR NOTE: Based on the plant transient. the CRS may not re-enter and direct actions of OP 3127.

2. CRS CRS Enters and directs actions from OT 3122. "Loss of Normal Power"

3. OATC Reports that a reactor scram has occurred. manual scram failed, and ARI/RPT failed to insert four control rods Performs post scram actions

• Reports loss of Feed and Condensate

• Places Mode Switch in Shutdown

6.

• Reports power <2%

7. CREW Recognizes and/or reports the MSIVs are closed

8. CRS Enters and directs actions from EOP-1. RPV Control" and EOP

2. RPV ATWS Control":

9.

• Direct ADS Inhibited

VY 2010 NRC Scenario 4 Page 19 of 24

10.

• Directs the OATC to maintain RPV water level -19" to 177" using RCIC or HPCI.

EVALUATOR NOTE: Based on low power history, RCIC should be directed and even at that, CRD should be enough to maintain RPV water level.

1.

• Directs the OATC to maintain RPV pressure 800-1000 psig using SRVs/HPCI/RCIC.

12.

• Directs Hydraulic ATWS Rod Appendices to be performed based on available resources EVALUATOR NOTE: Based on available resources and the fact the reactor is "shutdown" despite having four control rods not fully inserted, the CRS may not give this order at this time.

13. OATC Controls RPV water level-19" 177 inches and RPV pressure 800-1000 psig as directed.

14. BOP Performs immediate actions of OT 3122, Loss of Normal Power"

15. Reports the status of the electric plant:

• "A" EDG is carrying buses 4 and 9.

• "B" has started but breaker has failed to close.

• Performs OT 3122, step 3.c.1 to close the "B" EDG output breaker

VY 2010 NRC Scenario 4 Page 20 of 24

16.

• Start or verify operation of 2 SW pumps

17.

• Restart station air compressors A & B.

18. CREW Recognize and report EOP-4, "Secondary Containment Control", entry condition based on annunciators for high sump levels (4-L-4, 4-L-6, 4-M-4, and 4-M-6)

19. CREW Recognize and report EOP-3, "Primary Containment Control",

entry condition for lowering Torus water level.

Additionally, report and respond to annunciator 5-F-5, "TORUS TROUBLE".

20. CREW Contacts WWM/FSS to investigate the loss of Torus water level and rising sump levels in the Reactor Building

21. CRS Enters and directs actions of EOP-3:

22.

• Direct EOP-3 Table "N" systems be lined up to maintain Torus water level using Appendix "W" preferably based on quick to lineup with high capacity.

23. BOP Lines up Core Spray to fill the Torus using OE 3107, Appendix "W".

24. CRS Enters and directs actions of EOP-4 and ON 3158, "Reactor Building High Area TemperaturelWater Level"

VY 2010 NRC Scenario 4 Page 21 of 24

25.

• Operates/verifies operating all sump pumps as required

26. CREW Reports that the loss rate from the Torus exceeds the makeup rate with Core Spray and based on the leak location, will not be able to maintain Torus level above 7 feet.

27. CRS Directs the crew to Terminate and Prevent injection lAW OE 3107, Appendix "GG"

28. BOPI When directed Terminate and Prevent injetion lAW OE 3107, OATC Appendix "GG" as follows:

• Inhibit HPCI

• Place CS/RHR pumps in Pull to Lock

• Place all 4 FRV Controllers in manual and close all valves.

29. CREW During an ATWS with CCT-1 Emergency Depressurization required, terminate and prevent injection into the RPV (using OE 3107, "EOP/SAG Appendices", Appendix GG) until conditions are met to re establish injection.

STANDARD: Terminate and prevent injection lAW Appendix GG such that no system other than SLC, CRD, and/or RCIC is/are injecting during the RPV-ED.

Time Terminate and Prevent is complete: _ _ _ __

Time all SRVs are opened:

VY 2010 NRC Scenario 4 Page 22 of 24

30. BOP Open all SRVs

31. CREW When torus level cannot be maintained above 7 ft, CCT-2 perform RPV emergency depressurization.

STANDARD: Initiate RPV-ED such that RPV pressure is <

50 psig when Torus level reaches 5.5 ft.

Torus level at time the SRVs were opened: _ _ _ __

Time all SRVs are opened:

32. CREW Monitors RPV water level as follows:

• ERFIS point WIDEM071, COMPENSATED RX LEVEL WIDE 70 down to 350 psig

• From 350 psig down, ERFIS point SHDBB045, COMPENSATED RX LEVEL SHRD 73B, or ERFIS point SHDAB046, COMPENSATED RX LEVEL SHRD 73A

33. CRS When RPV pressure drops

<MSCP for 4 open SRVs (160 psig), using Table "H" systems.

Control water level using Table "H" systems -19"-177 inches EVALUATOR NOTE: Based on low power history, CRD should be enough to maintain level.

VY 2010 NRC Scenario 4 Page 23 of 24

34. GATC Control RPV water level-19" 177" as directed.

35. CREW Human Performance Tools consistently utilized throughout event number 3.

VY 2010 NRC Scenario 4 Page 24 of 24 SCENARIO 4 EVALUATOR NOTES: