Revision as of 04:02, 7 December 2019

Text

Draft - Operating Exam (Sections a, B, and C) (Folder 2)
	ML090420123
Person / Time
Site:	Vermont Yankee
Issue date:	01/08/2009
From:	Romeo M; Entergy Nuclear Vermont Yankee
To:	Todd Fish; Operations Branch I
	Hansell S
Shared Package
ML082600332	List: IR 05000271/2009301; ML083090073; ML090360210; ML090420110; ML090420115; ML090420119; ML090420123; ML090760092; ML090790217; ML090790241; ML090790243; ML090790246; ML090960141; ML090960153;
References
	50-271/09-301, TAC U01743
	Download: ML090420123 (273)
	v • d • e

JPM-Ala RO Rev. 111108 Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Perform the RHR Svstem Valve Lineup Failure Mode: Two mispositioned valves.

References:

OP 2124, Residual Heat Removal Svstem, (Rev. 113)

AP 0155, Current Svstem Valve And Breaker Lineup and Idenl 75)

Task Number: 1-Task Performance: AOROISRO _. ROISRO X SRO Only -

Sequence Critical: Yes - No Time Critical: Yes - No 3 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: 13 minutes Evaluation Results:

Performance: PASS FAIL Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedICertified Reviewer Date

'pproved by:

Operations Training Manager Date JPM-A1a RO

JPM-Ala RO Rev. 111108 Page 2 of 6 9irections:

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 f -)r 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.

'nitial Conditions:

The plant is preparing for startup following a Refueling Outage.

Shutdown Cooling has been secured.

0 Appendix B, Containment Remote Operated Valve Checklist, of OP 21 15, Primary Containment, is completed.

Initiating Cues:

The CRS directs you to perform pages 1 and 2 of Appendix A, RHR System Valve Lineup, of OP 2124, Residual Heat Removal System using the guidance found in AP 0155, Current System Valve and Breaker Lineup and Identification.

Task Standards:

The operator performs the Valve Lineup in accordance with OP 2124, using the guidance provided within AP 0155, Current System Valve and Breaker Lineup and Identification, recording all tracking information on the appropriate documentation, discovering and notifying supervision of the two mispositioned valves, and re-positioning the valves as needed.

JPM-A 1a RO

JPM-A1a RO Rev. 111108 Page 3 of 6 Peauired Materials:

Handout 1- OP2124, Appendix A (Rev. 113)

Handout 2 - AP 0155, Current System Valve And Breaker Lineup and Identification, (Rev. 75)

A Danger Tag with a Tag Number on it.

Simulator Set-Ue:

Reset to IC-106.

Remove SDC from service in accordance with OP 2124.

Open RHR-57.

Throttle RHR-65B so that it is NOT fully OPEN, Start Recirc Pump A in accordance with OP2110.

Lined up SBGT on Containment Air Purge in accordance with OP 21 15 Reset to IC-824 Place a Danger Tag with a Tag Number on it on RHR-57.

Examiner Notes:

Since the JPM task is focused on the RHR System Valve/Switch positions ONLY, the Simulator does not reflect the initial conditions specified in the JPM. If the operator questions the Simulator alignment, the Examiner should inform the operator that the Simulator alignment is acceptable for the task to be evaluated.

This JPM should be conducted simultaneously with A4 SRO.

JPM-A 1a RO

JPM-Ala RO Rev. 111108 Page 4 of 6

.'rovide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1.

Evaluation Performance Steps TIME START:

SATAJNSAT *Step 1: Perform Valve Lineue Standard: The operator completes the valve lineup and places their initials in the appropriate space on OP 2 124 Appendix A.

The operator discovers RHR-57 OPEN, when it should be CLOSED, with a Danger Tag requiring it to be OPEN.

Interim Cues: If asked, as the Shift Manager, Examiner direct the operator to leave the valve in its present position and annotate this as required by the procedure.

The operator addresses AP 0155, Current System Valve And Breaker Lineup and Identification, (Rev. 75).

Interim Cue: When it is apparent that the operator is seeking to find AP 0155, Examiner provides copy (Handout 2).

The operator indicates the tag number (i.e., 1RFO-24-xxxx) on the lineup form next to its required position, and leaves the "Initials" column blank at this time.

The operator discovers RHR-65B NOT fully OPEN, when it should be fully OPEN, and reports this to the CRS.

Interim Cues: If asked, as the Shift Manager, Examiner direct the operator to place the valve in the position required by the Valve Lineup.

The operator places the RHR-65B control switch to OPEN, and observe J Red light ON, Green light OFF.

The operator initials the appropriate space on OP 2124, Appendix A, and places a note at the bottom of the page indicating that RHR-65B was found out of position.

JPM-Ala RO

JPM-A 1a RO Rev. 111108 Page 5 of 6 Lvaluation Performance Steps SATIUNSAT *Stew 2: Track valve position on OP 2124, Awwendix A:

Standard: The operator completes the valve lineup and places their initials in tf:e appropriate space on OP 2124 Appendix A for the following valves:

RHR-20 RHR-66 RHR-57 (indicates the tag number on the lineup form next to its required position, and leaves the "Initials" column blank)

RHR-89B RHR 89B Test Switch RHR-65B (with Note and bottom of Page indicating that Valve was found out of position)

RHR-65A RHR-89A RHR 89A Test Switch RHR- 184 RHR- 183 VOTE: The Examiner should review the Valve Lineup paperwork when completed and check to see that the operator hasoplaced their initials, and made one Note, as required on OP 2124, Appendix A.

Critical Step TIME FINISH:

Terminating Cue: The JPM is complete.

Evaluator Comments:

Cystem Generic WA: 2.1.29 (4.U4.0)

JPM-A 1a RO

EXAMINEE HANDOUT Initial Conditions:

0 The plant is preparing for startup following a Refueling Outage.

s Shutdown Cooling has been secured.

0 Appendix B, Containment Remote Operated Valve Checklist, of OP 21 15, Primary Containment, is completed.

Initiatiw Cues:

The CRS directs you to perform pages 1 and 2 of Appendix A, RHR System Valve Lineup, of OP 2124, Residual Heat Removal System using the guidance found in AP 0155, Current System Valve and Breaker Lineup and Identification.

JPM-Ala SRO Rev. 111108 Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Perform the CSIHPCI Svstem Valve LineuD Failure Mode: Two mispositioned valves.

References : OP 21 15, Residual Heat Removal System, (Rev. 113)

AP 0155, Current System Valve And Breaker Lineup and Identification, (Re 1 75)

Task Number: -I-Task Performance: AOIROISRO - ROISRO X SRO Only __

Sequence Critical: Yes __ No Time Critical: Yes _. No 3 Operator Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation - Performance_ZL Discuss __

Setting: Classroom - S i m u l a t o r x Plant -

Performance Expected Completion Time: 10 minutes Evaluation Results:

Performance: PASS FAIL, Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedCertified Reviewer Date Zpproved by:

Operations Training Manager Date JPM-A 1a SRO

JPM-Ala SRO Rev. 111108 Page 2 of 7 Xrections:

Discuss the information given on this page with the operator being evaluated. Allow time for him t 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 fc 2-any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical st :p 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.

'nitial Conditions:

The plant is preparing to enter the Startup mode.

Appendix B, Containment Remote Operated Valve Checklist, of OP 2115, Primary Containmen;, is in progress.

Initiating Cues:

The CRS directs you to complete pages 3-5 of Appendix B, Containment Remote Operated Valve Checklist, of OP 21 15, Primary Containment, using the guidance found in AP 0155, Current System Valve and Breaker Lineup and Identification.

Task Standards:

The operator performs the valve lineup in accordance with OP 21 15, using the guidance provided within AP 0155, Current System Valve and Breaker Lineup and Identification, recording all tracking information on the appropriate documentation, discovering and determining the final disposition of the two mispositioned valves, and identifying Technical Specification limitations.

JPM-Ala SRO

JPM-Ala SRO Rev. 111108 Page 3 of 7 Peuuired Materials:

Handout 1- OP2115, Appendix B (Rev. 75) Pages 3 , 4 and 5 with all valves initialed except:

Page 3 - CS-7A, CS-SA, and CS-11A Page 4 - CS- 12A and CS- 14A Page 5 - CS-7B, CS-5B, CS-11B, CS-l2B, CS-l4B, HPCI-25, HPCI-16, HPCI-15, HPCI-58, and HPCI-57 Handout 2 - AP 0155, Current System Valve And Breaker Lineup and Identification, (Rev. 75)

Simulator Set-Up:

Reset to IC- 106.

Remove SDC from service in accordance with OP 2124.

CLOSE CS-1 1A (mispositioned).

CLOSE CS-1 1B (mispositioned) and use Soft Patch override CSdi0314AS2B to prevent valve from moving.

Start Recirc Pump A in accordance with OP2110.

Lined up SBGT on Containment Air Purge in accordance with OP 2 115 Reset to IC-820 Examiner Notes:

Since the JPM task is focused on the CS/HPCI System Valve/Switch positions ONLY, the Simulator does not reflect the initial conditions specified in the JPM. If the operator questions the Simulator alignment, the Examiner should inform the operator that the Simulator alignment is acceptable for the task to be evaluated.

This JPM should be conducted simultaneously with A4 RO.

JPM-Ala SRO

JPM-Ala SRO Rev. 111108 Page 4 of 7

,'rovide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1.

Evaluation Performance Steps TIME START:

SATRJNSAT *Step 1: Perform Valve Lineup Standard: The operator completes the valve lineup and places their initials in thi appropriate space on OP 2 115 Appendix B.

The operator discovers CS-1 1A CLOSED, when it should be OPEN.

The operator addresses AP 0155, Current System Valve And Breaker Lineup and Identification, (Rev. 75).

Interim Cue: When it is apparent that the operator is seeking to find AP 0155, Examiner provides copy (Handout 2).

Interim Cues: If the operator asks for SM assistance, Examiner inform the operator to act as the Shift Manager.

The operator places the CS-1 1A control switch to OPEN and observes the Red status light ON and the Green status light OFF.

The operator places their initials in the appropriate space on OP 21 15 Appendix B for CS-11A, and places a Note at the bottom of page 3 identifying that CS-1 1A was discovered to be in the CLOSED position.

The operator discovers CS-11B CLOSED, when it should be OPEN.

Interim Cues: If the operator asks for SM assistance, Examiner inform the operator to act as the Shitt Manager.

The operator places the CS-1lB control switch to OPEN and observes the Green status light ON and the Red status light OFF, and identifies that CS-11B will NOT Open.

The operator DOES NOT place their initials in the appropriate space on JPM-Ala SRO

JPM-Ala SRO Rev. 111108 Page 5 of 7 OP 21 15 Appendix B for CS-1 lB, and places a Note at the bottom of page 5 identifying that CS-11B was discovered to be in the CLOSED position, and will NOT OPEN.

Interim Cues: Examiner ask If you were the CRS, what are the operational implications of CS-111il failing closed?

SATNNSAT *Step 2: Evaluate Technical Specifications Standard: The operator addresses LCO 3.5.A.1 and determines that the valve mkist be correctly positioned prior to entering the Startup mode.

SATLJNSAT *Step 3: Track valve position on OP 2115, Appendix B:

Standard: The operator completes the valve lineup and places their initials in the appropriate space on OP 21 15 Appendix B for the following valves:

CS-7A CS-SA CS-1lA (Found Closed, Note on bottom of page 3)

CS-12A CS- 14A CS-7B CS-5B CS-1 1B (Found Closed, Note on the bottom of page 5 to identify that the valve was found out of position, No initials)

CS-12B CS-14B HPCI-25 HPCI- 16 HPCI- 15 HPCI-58 HPCI-57 NOTE: The Examiner should review the Valve Lineup paperwork when completed and check to see that the operator has placed their initials, and made one Note, as required on OP 21 15, Appendix B.

TIME FINISH:

Terminating Cue: The JPM is complete.

JPM-Ala SRO

JPM-Ala SRO Rev. 111108 Page 6 of 7 Yvaluator Comments:

~~ ~ ~ ~~

System Generic WA: 2.1.29 (4. U4.0)

JPM-Ala SRO

EXAMINEE HANDOUT Initial Conditions:

The plant is preparing to enter the Startup mode.

Appendix B, Containment Remote Operated Valve Checklist, of OP 21 15, Primary Containmer,It,is in progress.

Initiating Cues:

The CRS directs you to complete pages 3-5 of Appendix B, Containment Remote Operated Valve Checklist, of OP 21 15, Primary Containment, using the guidance found in AP 0155, Current Systen Valve and Breaker Lineup and Identification.

JPM-Alb S RO Rev. 111;708 Page 1 bf 8 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Perform a Core Thermal Hvdraulics Limits Evaluation Failure Mode: One of the Thermal Limits is Out of Spec

Reference:

OP 4401, Core Thermal Hydraulics Limits Evaluation, (Rev. 34)

Task Number:

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

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation - Performance Discuss -

Setting: Classroom X Simulator - Plant __

Performance Expected Completion Time: 10 minutes Evaluation Results:

Performance: PASS - FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedKertified Reviewer Date Approved by:

Operations Training Supervisor Date JPM-Alb SRO

JPM-A 1b ,".RO Rev. 111708 Page 2 if 8 qirections:

Discuss the information given on this page with the operator being evaluated. Allow time for him tr )

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 fo any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical stbhp is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measurt I.

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 Classroom and you are to perform 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.

TnitialConditions:

0 The plant is at 100% power.

0 A power change from 90% to 100%occurred one hour ago.

The 3D Monicore case is available.

Initiating Cues:

You are required to perform the Daily Core Thermal Hydraulics Limit Evaluation in accordance with OP 4401, Core Thermal Hydraulics Limit Evaluation.

Task Standards:

The Daily Core Thermal Hydraulics Limit Evaluation is performed in accordance with OP 4401, MFIXPR is identified as being out of spec, LCO 3.1 l.C and determines that MCPR must be returnel to within the prescribed limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months otherwise the reactor power shall be brought to less th2-n 23% RTP within four (4) hours.

Required Materials:

Handout 1 - 3D Monicore Case # FMLS 1810319125947 (Modified so that MFLCPR is 00s high:{.

Handout 2 - Thermal Limit Status Board (Copy)

Handout 3 - OP 4401, Core Thermal Hydraulics Limit Evaluation (Rev. 34)

Handout 4 - Printout of the computer screen showing control rod oppositions and APRM GAFs.

JPM-Alb SRO

JPM-Alb RO Rev. 111 708 Page 3 ,if 8 Amulator Setup:

NA JPM-Alb SRO

JPM-Alb ! RO Rev. 111708 Page 4 J f 8

-rovide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout #l.

Evaluation Performance Steps TIME START:

SATKJNSAT Step 1: Obtains and reviews procedure OP 4401 Standard: Procedure obtained and reviewed.

Interim Cue: When it is apparent that the operator is seeking to find OP 4401, Examiner provides copy (Handout 3).

SATNNSAT Step 2: (NOTE prior to Step 1)The time and date that a thermal limits evaluation is completed to meet a surveillance requirement is the time and date the 3D Monicore case was calculated (Le., From case ID).

Standard: The operator reads the Note and proceeds to Step 1.

SATAJNSAT Step 3: (Step 1) If performing daily surveillance, data from an automatic case may be used.

Standard: The operator recognizes that the daily surveillance is being performed and that the automatic case has been provided.

JPM-Alb SRO

JPM-Alb RO Rev. 11 1708 Page5 ,f 8

",valuation Performance Steps SATKJNSAT *Step 4: (Step 2) Complete VYOPF 4401.01 Standard: The operator evaluates 3D Monicore Case # FMLS 1810319125947 i nd completes steps 1-6 of VYOPF 4401.01 as follows:

The operator records 3D Monicore Official Monitoring Case ID FML.S 1810319125947 in Step 1.

The operator compares the control rod positions of the Official Monitoring case to the full core displayRWM.

Interim Cues: When it is apparent that the operator is seeking to locate the full core display or the RWM, provide the operator with the printout of the control rod positions and APRM GAFs (Handout 4).

After cue, the operator determines that the rod positions are correct and enters their name and date in Step 2.

The operator records the core thermal power (in MWth) as 1910.6 in Step 3.

The operator records the highest MFLCPR as 1.022, and its core locat :on as 25-26 in Step 4.

The operator records the highest MFLPD as .796, and its core locatiori as 21-36-4 in Step 5.

The operator records the highest MAPRAT as ,712, and its core locatiJm as 21-36-4 in Step 6.

JPM-A 1b SRO

JPM-Alb SRO Rev. 11; 708 Page 6 of 8 Yvaluation Performance Steps SATAJNSAT Step 5: (NOTE prior to VYOPF 4401.01 Step 7) Any APRM found to be non-conservative shall be corrected as soon as possible. An APRMA considered inoperable if the AGAF is not restored within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the time of discoverv.

Standard: The operator reads the Note and proceeds to Step 7.

SAT/UNS AT Step 6: (Step 7)Check the APRM system gains using the REO display OD ERFIS.

Standard: The operator calls up the REO display on ERFIS and observes ARPM System gains.

After cue, the operator proceeds to Step 8.

Interim Cue: When asked, Examiner inform operator Item #7, APRM gains, has been verified SAI'.

_tAT/UNSAT "Step 7: (Step 8) Verifv MFLCPR, MFLPD and MAPRAT from Steps 4 tr -

are less than or eaual to Administrative Limits posted on Thermal Limit Status Board. If not, contact Reactor Engineering.

Standard: The operator compares the values recorded on VYOPF 4401.01 Steps 4-6 to the associated Administrative Limits listed on the Thermal Limit Status Board, and identifies that the MFLCPR is out of specification.

The operator notifies RE of the out of spec situation.

Interim Cues: When it is apparent that the operator is seeking the Thermal Limit Status Board, Examiner provide a copy of the Thermal Limit Status Board (Handout).

When RE is notified, Examiner acknowledge as RE.

JPM-A 1b SRO

JPM-Alb RO Rev. 111708 Page 7 ,if 8 Svaluation Performance Steps SAT/UNSAT *Step 8: (Step 9) Verify the Acceptance Criteria below are satisfied. If A, &

C or D below are not satisfied, enter applicable Tech. Spec. LCO.

Standard: The operator recognizes that Acceptance Criteria C is NOT satisfied.

The operator enters LCO 3.1 1.C and determines that MCPR must be returned to within the prescribed limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months otherwise the reactor power shall be brought to less than 23% RTP within four (4) hours.

The operator does NOT sign Step 10 of VYOPF 4401.01 indicating that the surveillance has been performed and that the Acceptance Criteria :tre satisfied.

The operator notifies the SM of the results of the surveillance.

TIME FINISH:

Terminating Cue: This JPM is complete.

valuator Comments

WA: Generic 2.1.7 (4.4/4.7)

JPM-Alb SRO

EXAMINEE HANDOUT d i a l Conditions:

The plant is at 100% power.

A power change from 90% to 100% occurred one hour ago.

The 3D Monicore case is available.

Initiating Cues:

You are required to perform the Daily Core Thermal Hydraulics Limit Evaluation in accordance wirh OP 4401, Core Thermal Hydraulics Limit Evaluation.

JPM-A2 RO Rev. 111708 Page 1 of 9 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Perform a Drvwell Temperature Profile Failure Mode: High Temperature in the Drywell

Reference:

OP 41 15, Primary Containment Surveillance, (Rev. 60)

Task Number: 2997170301 Task Performance: AOROISRO - ROISRO X SRO Only __

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

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation - Performance Discuss __

Setting: Classroom - Simulator X Plant -

Performance Expected Completion Time: 15 minutes Evaluation Results:

Performance: PASS FAIL Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedICertifiedReviewer Date

\pproved by:

Operations Training Manager Date JPM-A2 RO

JPM-A2 RO Rev. 111708 Page 2 of 9 Arections:

Discuss the information given on this page with the operator being evaluated. Allow time for him tt R 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 fo any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical st1.p 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.

lnitial Conditions:

0 The plant is operating at 100% power.

0 MCB Annunciator 9-5/F-2, DRYWELL TROUBLE has alarmed.

0 RBCCW HX A is in service.

Initiating Cues:

The CRS directs you to perform the Drywell Temperature Profile in accordance with Section F of OP 41 15, Primary Containment Surveillance.

Task Standards:

The Drywell Temperature Check is completed in accordance with OP4115 (Rev 60), Section F, VYOPF 41 15.05 is filled in, the operator identifies that the Drywell Temperature for Elevation 250' in vicinity of the Recirculation Pumps, and Drywell Temperature below Elevation 270' do NOT meet the identified acceptance criteria, and the operator identifies that ( 1) the Duty Officer/Operations managc*r must be notified, (2) a CR must be written to identify a possible EQ concern, (3) the Drywell Temperature Profile must be performed once per shift, and (4)the completed form VYOPF 41 15.05 must be routed to the EQ Coordinator.

JPM-A2 RO

JPM-A2 RO Rev. 111708 Page 3 of 9 Required Materials:

Handout 1 - OP 41 15, Primary Containment Surveillance, (Rev. 60)

Simulator Set-Up:

Reset to any 100% power IC Insert mfMS-06 at .07% and allow to run until the MCB Annunciator 9-5/F-2alarms.

Remove malfunction and allow plant to stabilize.

Freeze the Simulator Reset to IC# 821 Go to RUN Remove Malfunction MS-06 JPM-A2 RO

JPM-A2 RO Rev. 111708 Page 4 of 9 rovide Candidate with Initial Conditions/Cue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATRJNSAT Step 1: Obtain Procedure.

Standard: OP 41 15, Rev 60, obtained, prerequisites reviewed.

Place keeps on the procedure during performance of the task Interim Cue: When it is apparent that the operator is seeking to find OP 41 15, Examiner provide cipy (Handout 1).

SATAJNSAT Step 2: (CAUTION prior to Step 1) If temperatures below 320 foot elevation exceed 215OF, reactor water level instrumentation errors can occur.

Standard: The operator reads the Caution, and proceeds to Step 1.

SATRJNSAT Step 3: (Step 1) If necessary, refer to Figure 2 for temperature probe locations.

Standard: The operator may or may not refer to Figure 2, and proceeds to Step 2, SATAJNSAT Step 4: (Steps 2/2.a) If a high Drvwell temperature alarm is received:

Calculate the average Drywell temperature for the various elevations using VYOPF 4115.05.

Standard: The operator recognizes that MCB Annunciator 9-5/F-2,DRYWELL TROUBLE, is LIT, and proceeds to VYOPF.05.

JPM-A2 RO

JPM-A2 RO Rev. 111708 Page 5 of 9 Avaluation Performance Steps SATAJNSAT Step 5: (VYOPF 4115.05/NOTE prior to CRP 9-25 data) Identifv anv ouiAf service temperature probe with INOP and ensure a WR is submitted.

Standard: The operator reads the Note and proceeds to record raw data.

SATKJNSAT Step 6: (CRP 9-25 Data) CRP 9-25 TR 1-149, Place a d Mark If RRU In Operation.

Standard: The operator observes the RRU 1through 4 Return and RRU 1througl 4 Disch Temperatures, and records on VYOPF 41 15.05.

The operator places a d Mark in space for RRU 1A, lB, 2A, 2B, 3A 2nd 4A on VYOPF 41 15.05.

The operator records RBCCW HX in service as A on VYOPF 41 15.05 (Initial Conditions).

The operator observes MOOS and records RBCCW HX Outlet Temperature on VYOPF 41 15.05.

SATAJNSAT *Step 7: (Step A.l) Calculate the average temperature for each Drvwell elevation: Drvwell Temperature for Elev. 250' in Vicinitv of Recirculation Pumps(DBD-OIHVAC-041 01).

Standard: The operator calls up ERFIS computer points (or a User Defined Group) as required and records the data on VYOPF 41 15.05.

The operator completes the calculation (2 total sensors/2) on VYOPF 41 15.05 and determines that the calculated Drywell Temperature does NOT meet the Acceptance Criteria.

JPM-A2 RO

JPM-A2 RO Rev. 1 11708 Page 6 of 9 haluation Performance Steps SATAJNSAT *Step 8: (Step A.2) Calculate the average temperature for each Drvwell elevation: Drvwell Temperature for Elev. Below 270'.

Standard: The operator calls up ERFIS computer points (or a User Defined Gro,rp) as required and records the data on VYOPF 41 15.05.

The operator observes temperature points on the Steam Leak Detection Touchscreen Monitor and records the data on VYOPF 41 15.05.

The operator observes TI- 16-19-30B (DW) and records the data on VYOPF 41 15.05.

The operator observes TR-16-19-45 (DW) and records the data on VYOPF 41 15.05.

The operator completes the calculation (1 1 total sensors/l 1) on VYOBF 4 115.05 and determines that the calculated Drywell Temperature does NOT meet the Acceptance Criteria.

VOTE: The operator may record data required in Steps A.3 and A.4 while performing this Step.

SATAJNSAT Step 9: (Step A.3) Calculate the average temperature for each Drvwell elevation: Drvwell Temperature for Elev. 270' to 315'.

Standard: The operator calls up ERFIS computer points (or a User Defined Group) as required and records the data on VYOPF 41 15.05.

The operator observes temperature points on the Steam Leak Detection Touchscreen Monitor and records the data on VYOPF 41 15.05.

The operator completes the calculation (7 total sensors/7) on VYOPF 41 15.05 and determines that the calculated Drywell Temperature meets the Acceptance Criteria.

JPM-A2 RO

JPM-A2 RO Rev. 111708 Page 7 of 9

,valuation Performance Steps SATLJNSAT Step 10: (Step A.4) Calculate the average temperature for each Drvwell elevation: Drvwell Temperatures Above Elev. 315'.

Standard: The operator calls up ERFIS computer points (or a User Defined Group) as required and records the data on VYOPF 41 15.05.

The operator observes temperature points on the Steam leak Detectiori Touchscreen Monitor and records the data on VYOPF 4115.05.

The operator completes the calculation ( 5 total sensors/5) on VYOPF 41 15.05 and determines that the calculated Drywell Temperature meeis the Acceptance Criteria.

SAT/UNSA4T "Step 11: (Section F/Steps 2.b.l-4) If the average temperature of an area exceeds the recommended temperature.

Notify the Dutv on Call Officer and the Operations ManaPer.

Generate a Condition Report for possible EO concern due to exceeding the a v e r a e recommended temperature.

Calculate and document the average temperature once per shift while this condition exists or until an evaluation deems this action is not needed.

Route a COPY of the completed form to the E O Coordinator.

Standard: The operator notifies the Duty On call Officer.

The operator notifies the Operations Manager.

The operator identifies that a CR must be written to identify a possible EQ concern.

The operator notifies the CRS that this surveillance must be performed once per shift.

The operator forwards a copy of the completed VYOPF 41 15.05 to the EQ Coordinator.

Critical Step TIME FINISH:

Terminating Cue: The JPM is complete.

JPM-A2 RO

JPM-A2 RO Rev. 111708 Page 8 of 9

&valuatorComments:

System Generic WA's: 2.2.12 (3.7/4.1)

JPM-A2 RO

EXAMINEE HANDOUT Initial Conditions:

0 The plant is operating at 100%power.

0 MCB Annunciator 9-5/F-2, DRYWELL TROUBLE has alarmed.

0 RBCCW HX A is in service.

Initiating Cues:

The CRS directs you to perform the Drywell Temperature Profile in accordance with Section F of OP 41 15, Primary Containment Surveillance.

JPM-A2 SRO Rev. 111708 Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Review a Surveillance Failure Mode: Error carried forward interpreting Steam Tables.

References:

OP 41 10, Reactor Recirculation System Surveillance, (Rev. 41)

Steam Tables Task Number: -~ I Task Performance: AO/RO/SRO __ RO/SRO X SRO Only __

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 X Simulator - Plant -

Performance Expected Completion Time: 10 minutes Evaluation Results:

Performance: PASS FAIL Time R e p i e d :

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedCertified Reviewer Date Approved by:

Operations Training Manager Date JPM-A2 SRO

JPM-A2 SRO Rev. 111708 Page 2 of 6 3irections::

Discuss the information given on this page with the operator being evaluated. Allow time for him tc 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 foi 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 procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

'nitial Conditions:

The plant is 50% power with Recirc Pump B shutdown for corrective maintenance on its associared MG Set.

ERFIS is NOT available, and attempts to restore it have been unsuccessful for the last hour.

The MG Set maintenance has been completed, and Recirc Pump restart is in progress in accordaiice with OP 21 10, Reactor Recirculation System.

The Reactor Operator has just indicated that while performing the Reactor Coolant Temperature Check Data Sheet of OP 41 10, Reactor Recirculation System Surveillance, he has determined th,it the criteria necessary to start Recirc Pump B is NOT met.

Initiatiw Cues:

As the CRS, evaluate the surveillance and determine if the RO is correct.

Task Standards:

The operator evaluates the Reactor Coolant Temperature Check Data Sheet and determines that a mistake has been made in evaluating the Steam Tables. The operator will correct the mistake, and tk en direct that the RO continue the process of starting Recirc Pump B in accordance with OP 21 10.

JPM-A2 SRO

JPM-A2 SRO Rev. 111708 Page 3 of 6 Qequired Materials:

Handout 1 - VYOPF 41 10.05, Reactor Coolant Temperature Check Data Sheet, (Rev. 41), filled ir as follows:

Temperature (OF)

Recirc Loop B 368 I3 I ;ink Temperature ( O F )

Reactor Pressure 942 Blank (Pa9 Bottom Head Drain 445.9 H kin k Temp ( O F )

(PLC-2-166, RPV/SV/RV Screen, Ch. 4 (ERFIS Pt S026)

Saturation temperature corresponding to above reactor pressure from 603 O F (In Errorxhozd be saturated steam tables 539.3)

Xfference between saturation temperature and bottom head drain 148.1 O F

, cemDerature Handout 2 - Steam Tables Calculator Simulator Set-Up:

NA JPM-A2 SRO

JPM-A2 SRO Rev. 111708 Page 4 of 6

-'rovide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1.

Evaluation Performance Steps TIME START:

SATAJNSAT *Step 1: Review Reactor Coolant Temperature Check Data Sheet alreadv promess.

Standard: The operator observes the partially completed VYOPF 41 10.05.

The operator calculates the differential temperature between Loop A and B to be 42"F, and determines that this differential temperature will support Recirc Pump B start.

The operator observes that the AT between the saturation temperature and the bottom head drain temperature will NOT support Recirc Pump B start.

YATKJNSAT *Step 2: Evaluate Steam Tables for saturation temperature.

Standard: The operator obtains the Steam Tables.

Interim Cue: When it is apparent that the operator is seeking the Steam Tables, provide the operatc r with the Steam Tables (Handout 2).

The operator converts Reactor Pressure to absolute pressure by adding 14.7 psia to gage pressure of 942 psig and determines absolute pressure to be 956.7 psia.

The operator determines from Table 1 of the Steam Tables that the saturation temperature is between 536 and 540°F, and determines that he recorded saturation temperature is in error.

The operator calculates the actual saturation temperature to be 539.3"F (962.23-930.63 psi = 3 1.6 psi/4 OF; Actual > 536 "F = 31.6psi/(965.7-930.63 x 4 O F = 3.3 "F + 536 "F = 539.3 "F)

JPM-A2 SRO

JPM-A2 SRO Rev. 111708 Page 5 of 6 Yvaluation Performance Steps SAT/UNSAT *Step 3: Correct Reactor Coolant Temperature Check Data Sheet ahead&

progress, and determine a course of action Standard: The operator places a line through 604 "F, initials it, and enters 539.3 'F.

The operator places a line through 148.1 O F , initials and calculates a n :w AT between the saturation temperature and the bottom head drain temperature of 93.4 "F. (539.3 O F - 445.9"F = 93.4'F)

The operator observes that the AT between the saturation temperature and the bottom head drain temperature will support Recirc Pump B st UT, and directs the RO to continue with the Recirc Pump B start.

TIME FINISH:

Terminating Cue: The JPM is complete.

Evaluator Comments:

System Generic WA: 2.2.12 (3,7/4.1)

JPM-A2 SRO

EXAMINEE HANDOUT Initial Conditions:

The plant is 50% power with Recirc Pump B shutdown for corrective maintenance on its associded MG Set.

0 ERFIS is NOT available, and attempts to restore it have been unsuccessful for the last hour.

0 The MG Set maintenance has been completed, and Recirc Pump restart is in progress in accordifnce with OP 21 10, Reactor Recirculation System.

0 The Reactor Operator has just indicated that while performing the Reactor Coolant Temperaturc Check Data Sheet of OP 41 10, Reactor Recirculation System Surveillance, he has determined that the criteria necessary to start Recirc Pump B is NOT met.

Initiating Cues:

As the CRS, evaluate the surveillance and determine if the RO is correct.

JPM A3 RO Rev 121108 Page 1 of 5 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Assess Radiological Conditions and Determine Required Actions Failure Mode: -

N/A

Reference:

EN-RP- 101. Access Control for Radiologically Controlled Areas (Rev. 4)

Task Number: 2990 100301 Task Performance: AO/RO/SRO _. RO/SRO Only X SE Only __

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

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation - Performance Discuss -

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

Performance: PASS __ FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedKertified Reviewer Date

,pproved by:

,

Operations Training Superintendent Date JPM A3 RO

JPM A3 RO Rev 121108 Page 2 of 5 Oirections:

Discuss the information given on this page with the operator being evaluated. Allow time for him t 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 fc r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical st :p is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measur :.

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 Classroom and you are to perform 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:

0 You have been requested to verify that the RCU Pump A suction, CU-19A7is open and to observe the pump run.

You have an accumulated dose (TEDE) of 1920 mr for the year.

You are the only one available for the job.

It is expected that you will need to be near the suction valve for approximately 10 minutes, and within the pump room, at low dose areas, for a total of about 15 minutes.

Initiating Cues:

Given the Room Survey Map identify the following:

The dose rate at the valve.

The lowest dose rate area.

The highest dose rate area.

Your expected dose based on the stated job time estimates.

And identify whether or not you will need to get a dose extension to perform this job.

JPM A3 RO

JPM A3 RO Rev 121108 Page 3 of 5 Pask Standards:

The operator identifies the:

The dose rate at the valve as 240 mrhr.

The lowest dose rate area as 18 mrhr.

The highest dose rate area as 250 mrhr.

The expected dose as 45.5 mrhr.

That a dose extension is NOT needed.

Required Materials:

Handout 1 - Book of survey maps containing at least 12 survey maps, and as a minimum the Radiological Survey Map for the RWCU A and RWCU B Pump Room.

Simulator Setup:

NIA JPM A3 RO

JPM A3 RO Rev 121108 Page 4 of 5 Provide Candidate with Initial ConditionsKue (Last Page of this JPM), and Handout 1.

Evaluation Performance Steps TIME START:

SATAJNSAT *Step 1: Obtain and review survey map.

Standard: The operator reviews the Book of Survey Maps and identifies Map RB280D for the RCWU A Pump Room.

SAT/UNSAT *Step 2: Determine the doserate in the area of CU-19A.

Standard: The operator reviews the RCWU A Pump Room Survey Map and determines that the dose rate in the vicinity of CU-19A is 240 mrhr.

NOTE: The operator may use print G191178 to determine which vala e on the survey map is the suction valve.

SATIUNSAT *Step 3: Determine area with lowest dose rate.

Standard: The operator reviews the RCWU A Pump Room Survey Map and determines that the area with the lowest dose rate is 18 mrhr by the Siep-Off pad.

SATRJNSAT *Step 4: Determine area with highest dose rate.

Standard: The operator reviews the RCWU A Pump Room Survey Map and determines that the area with the highest dose rate is 250 mrhr.

SATAJNSAT *Step 5: Calculate the expected dose.

Standard: The operator determines that dose expected at the valve by:

240 mrhr x 10 minutes x 1 hour/60 minutes = 40 mr The operator determines the dose expected at the low dose area by:

18 mrhr x 15 minutes x 1 hour/60 minutes = 4.5 mr The operator determines the total expected dose by adding the dose expected at the valve, and the dose expected in the low dose areas as 4 4.5 mr.

JPM A3 RO

JPM A3 RO Rev 121108 Page 5 of 5 SATAJNSAT *Step 6: Identifv whether or not a dose extension is needed to perform this Standard: The operator identifies that the routine admin limit of 2000 mr is imposed, and determines that 80 mr of dose accumulation is allowabl,*

for the job.

The operator determines that a dose extension is NOT needed.

Critical Step TIME FINISH:

Terminating Cue: This JPM is complete.

Evaluator Comments:

System Generic WA's: 2.3.4 (3.2/3.7)

JPM A3 RO

EXAMINEE HANDOUT Initial Conditions:

0 You have been requested to verify that the RCU Pump A suction, CU-l9A, is open and to obser lie the pump run.

You have an accumulated dose (TEDE) of 1920 mr for the year.

0 You are the only one available for the job.

0 It is expected that you will need to be near the suction valve for approximately 10 minutes, and within the pump room, at low dose areas, for a total of about 15 minutes.

InitiatinP Cues:

Given the Room Survey Map identify the following:

0 The dose rate at the valve.

0 The lowest dose rate area.

0 The highest dose rate area.

0 Your expected dose based on the stated job time estimates.

And identify whether or not you will need to get a dose extension to perform this job.

JPM-A3 SRO Rev. 111708 Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Authorize Emergency Exposure Limits Failure Mode: -

N/A

Reference:

OP 3507. Emergency Radiation Exposure Control, (Rev. 39)

Task Number: 34302903 Task Performance: AO/RO/SRO __ RO/SRO - SRO Only X Sequence Critical: Yes _. No 3 Time Critical: Yes _ . 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: 10 minutes Evaluation Results:

Performance: PASS FAIL Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedKertified Reviewer Date Approved by:

Operations Training Manager Date JPM-A3 SRO

JPM-A3 SRO Rev. 111708 Page 2 of 7 Wrections:

Discuss the information given on this page with the operator being evaluated. Allow time for him 1 l3 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 fc r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical SI:p 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 procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

'nitial Conditions:

0 With the plant shutting down due to failed fuel causing high Reactor Coolant System Activity, i LOCA Outside of Containment occurred.

A Site Evacuation is in progress in accordance with Attachment 9.7 of OP 3540 (General Emergency Announcement).

An RP Technician reports that an operator working with him in the Reactor Building has fallen md is severely injured. He has moved the injured person to an area that is somewhat shielded. Due t I rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are 1 )fe-threatening. He also stated that the individual could be retrieved but it would take two people to do so.

The RP Technician estimates that it will take at least ten minutes to retrieve the victim.

Reactor Building Area Radiation Monitors indicate extremely high radiation levels.

Dose rates at the area needing access are 420 R e d H r .

0 The Senior Radiation Protection representative has already concurred with the dose exposure authorization.

Initiating Cues:

As the Shift Manager, select two rescuers from those individuals available in accordance with Attachments 9.1 and 9.5 of OP 3507, Emergency Radiation Exposure Control; and then complete th:

Emergency Dose Commitment portion of Attachment 9.8 to approve the Emergency exposure.

JPM-A3 SRO

JPM-A3 SRO Rev. 111708 Page 3 of 7 Task Standards:

The operator Cllooses ladigan and Walker as rescuers and completes the Emergency Dose Commitment Authorized portion of Attachment 9.8 of OP 3507.

Required Materials:

Handout 1 - List of Available Rescuers in Control Room (Page 6 of 7 of this JPM).

Handout 2 - OP 3507, Emergency Radiation Exposure Control, (Rev 39)

Calculator Simulator Set-Up:

NA JPM-A3 SRO

JPM-A3 SRO Rev. 111708 Page 4 of 7 Yovide Candidate with Initial Conditions/Cue, and Handout 1 (Last two Pages of this JPM).

Evaluation Performance Steps TIME START:

SATAJNSAT Step 1: Obtain Procedure and locates Attachments 9.1.9.5 and 9.8.

Standard: The operator obtains OP 3507 and locates Attachments 9.1,9.5 and 9 8, Interim Cue: When it is apparent that the operator is seeking to find OP 3507, Examiner provide copy (Handout 2).

SATAJNSAT *Step 2: As the Plant Emergency Director, select two rescuers from those individuals available in accordance with Attachments 9.1 and 9.5 of OP 3507, Emergency Radiation Exposure Control.

Standard: The operator recognizes from initial conditions that Dose rates at the ;rea needing access is greater than 420 Rem/Hr, and that based on 10 mimite rescue time, each individual could receive as much as 70 Rem.

The operator determines that rescuers will need to be authorized to receive Emergency Exposure Dose Limits.

The operator reviews List of Available Rescuers in Control Room and determines qualification of potential rescuers.

The operator determines that Jaffe cannot be dispatched as a rescuer (Showing signs of pregnancy).

The operator determines that Gibbs cannot be dispatched as a rescuer (Does NOT Volunteer).

The operator determines that Pearson cannot be dispatched as a rescue+

(Has too much Lifetime Exposure).

The operator determines that Fiske cannot be dispatched as a rescuer (Only STA - TRMOP0894 requires her in Control Room).

The operator determines that Taylor cannot be dispatched as a rescuer (Too young).

The operator selects Madigan and Walker as rescuers.

JPM-A3 SRO

JPM-A3 SRO Rev. 111708 Page 5 of 7 Yvaluation Performance Steps SATRJNSAT *Step 3: As the Plant Emergency Director, complete Attachment 9.8 to approve the Emergency exposure.

Interim Cue: When asked provide Job Number, 047 and RWP number 09-003.

Standard: The operator places 70-75 REM in the Individual TEDE Dose Commitment Authorized block on Page 1 of Attachment 9.8 (Emergency Dose Commitment Authorized Section).

The operator places 140-150 REM in the TEDE Dose Commitment Authorized Collective For Task block on Page 1 of Attachment 9.8 (Emergency Dose Commitment Authorized Section).

The operator approves the Emergency Dose by signing their name in 1 he Approved By block on Page 1 of Attachment 9.8 (Emergency Dose Commitment Authorized Section).

The operator asks the RP Technician to brief Madigan and Walker in accordance with Attachment 9.8.

Critical Step TIME FINISH:

Terminating Cue: This JPM is complete.

Evaluator Comments:

"\stem Generic WA's: 2.3.4 (3.2/3.7)

JPM-A3 SRO

JPM-A3 SRO Rev. 111708 Page 6 of 7 Yandout 1: List of Available Rescuers in Control Room:

RP Name Gender/ Job Employer Current Lifetime Special Status Badge Age Assignment Exposure Exposure

(Y r)

Would prefer not to 12345 Gibbs Male/ Maintenance VY 1800 mr 5.2 R go/ Reports good 49 physical health 12456 Madigan Female/ Engineer VY 45 mr 400 mr Volunteers/ Reports 48 good physical health I2567 Pearson Male NLO VY 125 mr 35.4 R Volunteers/ Reports

/45 good physical health

~~~

12579 Walker Male/ Training VY 6 mr 1400 mr Volunteers/Reports 52 Supervisor good physical health

____

121 10 Jaffe Female/ Security VY 10 mr 65 mr Showing signs but 32 Supervisor NOT Declared Pregnant/Volunteers/

Reports good physica health 12238 Fiske Female/ STA VY 4 mr 120 mr Volunteers/Only STA 46 qualified individual ir Control Room.

12198 Woods Male/ U2 BOP VY 78 mr 1.7 R Volunteers/ Reports 34 good physical health JPM-A3 SRO

EXAMINEE HANDOUT aitial Conditions:

0 With the plant shutting down due to failed fuel causing high Reactor Coolant System Activity. I I LOCA Outside of Containment occurred.

A Site Evacuation is in progress in accordance with Attachment 9.7 of OP 3540 (General Emergency Announcement).

0 An RP Technician reports that an operator working with him in the Reactor Building has fallen and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are ife-threatening. He also stated that the individual could be retrieved but it would take two people to do so.

0 The RP Technician estimates that it will take at least ten minutes to retrieve the victim.

Reactor Building Area Radiation Monitors indicate extremely high radiation levels.

0 Dose rates at the area needing access are 420 Rem/Hr.

The Senior Radiation Protection representative has already concurred with the dose exposure authorization.

Initiating Cues:

As the Shift Manager, s w c t two rescuers from those individuals available in accordance with Attachments 9.1 and 9.5 of OP 3507, Emergency Radiation Exposure Control; and then complete the Emergency Dose Commitment portion of Attachment 9.8 to approve the Emergency exposure.

JPM A4 RO Rev. 111708 Page 1 of 9 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Perform Control Room Emergency Communications Checks Failure Mode: -

N/A

Reference:

OP 3506, Emergency Eauipment Readiness Check, (Rev. 62)

Task Number: 2997270301 Task Performance: AO/RO/SRO __ RO/SRO X SRO Only __

Sequence Critical: Yes __ No 2 Tirne Critical: Yes - No 2 Individual 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:

Operations Training Instructor Date Reviewed by:

SRO LicensedICertified Reviewer Date Approved by:

Operations Training Manager Date JPM A4 RO

JPM A4 RO Rev. 111708 Page 2 of 9 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him o 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 f(3r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical srep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measui ;.

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 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:

The plant is operating at 100%power with all systems operable.

Initiating Cues:

The CRS directs you to perform the Monthly Communications Checks in accordance with Section 5.1.1 and 5.1.2 of OP 3506 and to complete any associated paperwork.

Task Standards:

One of the five State Police Agencies, the Group Call, and the ENS phone notification systems are tested in accordance with Section 5.1 of OP 3506, and the results are recorded on Attachment 9.1 of OP 3506.

Required Materials:

Handout 1 - OP 3506, Emergency Equipment Readiness Check (Rev. 62)

Simulator Setup:

Reset to IC -820.

This JPM should be conducted simultaneously with Ala SRO.

JPM A4 RO

JPM A4 RO Rev. 111708 Page 3 of 9 Provide Candidate with Initial Conditions/Cue (Last Page of this JPM).

-,,valuation Performance Steps TIME START:

SATAJNSAT Step 1: Acquire OP 3506 and review procedure.

Standard: The operator acquires OP 3506 and reviews Section 5.1.

Interim Cue: When it is apparent that the operator is seeking to find OP 3506, Examiner provides copy (Handout 1).

SATAJNSAT Step 2: (NOTES prior to Step 5.1):

The quantities listed in this procedure are to be considered the minimum required. Quantities above those listed are acceptable.

Pens, pencils and scratch paper are readily available and therefore will not be maintained in the EOF and TSC kits the facilitv.

Standard: The operator reads the Notes and proceeds to Step 5.1.

SATLJNSAT Step 3: (Step 5.1/5.1.1) Control Room Emergency Communications Check.

(Operations) (Use Attachment 9.1)

Monthly, the Operations Department shall test the Nuclear Alert Svstem bv contacting, and requestinp a callback from. each of the three states (Vermont, New Hampshire, Massachusetts) using the following procedure:

Standard: The operator obtains Attachment 9.1 and records date and time.

JPM A4 RO

JPM A4 RO Rev. 111708 Page 4 of 9 Evaluation Performance Steps SATAJNSAT Step 4: (NOTE prior to Step 5.1.1.a) The 3 - d i ~ inumber t initiates a point-to-point call to each of the five State Police agencies. The 2-digit alphanumeric number initiates the proup call feature.

Standard: The operator reads Note and proceeds to Step 5.1.1.a.

SATAJNSAT *Stel, 5: (Step 5.1.1.a) Lift handset and dial 213 for Waterburv, VT, 317 for Rockingham, VT, 210 for Northampton, MA, 318 for Shelburne, MA, 212 for Concord, NH.

Standard: The operator lifts the handset and dials 213 for the Waterbury, Vermont Police Station.

NOTE: The Simulator Instructor will answer as Vermont State Police, Waterbury and initidte requested callbacks to the operator by dialing phone extension 126.

SATAJNSAT Step 6: (Caution prior to Step 5.1.1.b) Press down and hold the push-to-tulk button on the handset prior to speakinp. Release after speakins Refer to OP 3504 for instructions on use of the NAS phone.

Standard: The operator reads Caution and proceeds to Step 5.1.1.b.

JPM A4 RO

JPM A4 RO Rev. 111708 Page 5 of 9 Evaluation Performance Steps 3ATNNSAT Step 7: (Step 5.1.1.b) Advise each State Police agency that answers of thr test of the Nuclear Alert System, and record the results on Attachment 9.1.

Standard: The operator presses the push to talk button and indicates that Thvs is the ENVY Control Room, Vernon; and that a test of the NAS Phoi e is in progress, request a call back and release the button. Then, after acknowledgement,replace the handset.

NOTE: The Simulator Instructor will answer as Vermont State Police, Waterbury and init(ate requested callbacks to the operator by dialing phone extension 126.

When the NAS Phone rings back, the operator will pick up the handsct, press the push to talk button and indicate that This is the ENVY Control Room, Vernon, releasing the button after speaking.

After hearing of the test in progress from the initiating station, the operator will press the push to talk pushbutton, acknowledge the te+

release the button, and replace the handset.

The operator records the successful test by checking the YES Box on Attachment 9.1, Section A.l, for Waterbury, Vermont (213), and the associated YES Box for the callback.

NOTE: Only one of the calls to the five State Police Agencies will be performed.

Interim Cue: Examiner inform operator that subsequent NAS Phone Tests to Rockingham, Vermoit, Concord, New Hampshire, Northampton, Massachusetts, and Shelburne Falls, Massachusetts, have been completed satisfactorily.

After cue, the operator records the successful tests by checking the YES Boxes on Attachment 9.1, Section A. 1, for Rockingham, Vermont, Concord, New Hampshire, Northampton, Massachusetts, and Shelbun Le Falls, Massachusetts, and the associated YES Boxes for the callback.

JPM A4 RO

JPM A4 RO Rev. 111708 Page 6 of 9 Evaluation Performance Steps

,AT/UNSAT *Step 8: (Step 5.1.1.c) Test the Group Call capability with the five State Police agencies bv lifting handset and dialing Al. State Emergen=

ODerations facilities may also answer, but are not required for the test. After the test is complete disconnect the group call bv dialiqg A#, then hang up handset.

Standard: The operator picks up the handset, and recognizes that no one else is me the line.

The operator dials A1 and waits for the five State Police Agencies to respond.

NOTE The Simulator operator will answer as each state police agency as follows:

0 Massachusetts State Police, Troop B - Northampton 0 Massachusetts State Police, Shelburne Falls 0 New Hampshire State Police, Concord 0 Vermont State Police, Waterbury Vermont Secondary Warning Point - Rockingham After hearing the five Police Agencies respond, the operator presses the push to talk button and indicates that This is the ENVY Control Room, Vernon; and that a test of the NAS Phone is in progress.

NOTE Once made aware of the test, the Simulator operator will acknowledge the test as eaci state police agency.

After the acknowledgement of all five agencies, the operator disconnei:ts the Group Call by pressing the A#, and replacing the handset.

The operator records the successful test by checking the YES Box on Attachment 9.1, Section A.6, for Successful Group Call Test with VT/NH/MA(A1).

SAT/UNSAT Ster, 9: (Step 5.l.l.d) If any Dart of the NAS svstem fails to operate......

Standard: The operator recognizes that the NAS did NOT fail to operate, and proceeds to Step 5.1.1.e.

JPM A4 RO

JPM A4 RO Rev. 111708 Page 7 of 9 Evaluation Performance Steps SATIUNSAT Step 10: (Step 5.1.1.e) Notify the affected state Emergency Management c~ffice if any part of the system fails to operate.

Standard: The operator recognizes that the NAS did NOT fail to operate, and proceeds to Step 5.1.2.

SAT/UNSAT

NRC FTS ENS phone in the Control Room as follows: Lift the receiver and listen for the dial tone.

Standard: The operator lifts the handset and listens for a dial tone.

SATAJNSAT *Step 12: (Step 5.1.2.b) After receiving a dial tone, dial the first number listed below (or on the sticker located on the telephone base) usiw all 11 dieits. If the first number is busy, proceed with the second number.

1-301-816-5100 1-301-951-0550 Examiner NOTE: Examiner ask the operator what the actual phone number to be used would be.

Standard: The operator indicates that they would dial 1-301-816-5100.

Interim Cue: Examiner direct the operator to dial 4050.

Standard: The operator dials 4050.

NOTE: Simulator Instructor answer as NRC Operations Center.

JPM A4 RO

JPM A4 RO Rev. I11708 Page 8 of 9 Evaluation Performance Steps iAT/UNSAT *Step 13: (Step 5.1.2.c) State your name, location, and the fact that YOU are testing the NRC ENS. Request that the NRC staff member call back at 700-661-4323.

Standard: Operator informs NRC operator who he is, where he is calling from, hat he is testing the ENS, and requests callback at 700-661-4323.

Note: Simulator operator will acknowledge call as NRC operator, and will initiate callbacl using the "NRC to Control Room" auto dial button.

Standard: When the ENS Phone rings back, the operator will pick up the handsit, and indicate that "This is the ENVY Control Room, Vernon."

After hearing of the test in progress from the NRC, the operator will acknowledge the test, and replace the handset.

The operator records the successful test by checking the YES Box on Attachment 9.1, Section B. I for Successful Test with the NRC, and Section B.2 for Callback from the NRC Successful.

LIME FINISH:

Terminating Cue: This JPM is complete.

Evaluator Comments:

System Generic WA's: 2.4.43 (3.2/3.8)

JPM A4 RO

EXAMINEE HANDOUT Initial Conditions:

The plant is operating at 100%power with all systems operable.

Initiating Cues:

The CRS directs you to perform the Monthly Communications Checks in accordance with Section

5. I . 1 and 5.1.2 of OP 3506 and to complete any associated paperwork.

JPM A4 SRO Rev. 121108 Page 1 of 11 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Off-Site Protective Action Recommendations (evacuate)

Failure Mode: -N/A

Reference:

OP 35 11 Off-Site Protective Action Recommendations, (Rev. 26)

OP 3513, Evaluation of Offsite Radiological

- Conditions, (Rev. 3 3 )

Task Number: 2007150501 Task Performance: AO/RO/SRO - RO/SRO - SRO Only X Sequence Critical: Yes _. No 3 Time Critical: Yes - No 3 Operator Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation __ Performance 2Discuss -

Setting: Classroom __ Simulator X Plant Performance Expected Completion Time: 20 minutes Evaluation Results:

Performance: PASS - FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedKertified Reviewer Date

.pproved by:

Operations Training Manager Date JPM A4 SRO

JPM A4 SRO Rev. 121108 Page 2 of 11

)irections:

Discuss the information given on this page with the operator being evaluated. Allow time for him 1 n 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 fc I:

any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical st :p 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 Derson 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.

nitial Conditions:

A reactor transient has occurred resulting in fuel damage.

An elevated release through the plant stack has just begun, and a General Emergency EAL has b&.:en declared 5 minutes ago.

There is no ground release in progress.

Another SRO has been assigned to Use OP 351 1, Off-Site Protective Action Recommendations, Section 5.6, Protective Action Recommendation Based on Plant Conditions, Attachment 9.4, General Emergency Protective Action Recommendations (PARS)Flowchart.

ODPS is operable.

'The EOF is NOT yet manned.

Initiating Cues:

You have been assigned by the PED to implement OP 3513, Evaluation of Off-Site Radiological Conditions, Section 5.9, Initial Evaluation; and prepare a PAR based on Off-Site Radiological Conditions and return it to the PED.

Task Standards:

Operator makes off site Protective Action Recommendations per OP 3511 and OP 3513 and transmits to the PED indicating that Vernon, Hinsdale, Bernardston and Northfield must be evacuated.

JPM A4 SRO

JPM A4 SRO Rev. 121108 Page 3 of 11 lequired Materials:

Handout 1 - OP 3513, Evaluation of Offsite Radiological Conditions (Rev. 33)

Handout 2 - OP 351 1, Off-Site Protective Action Recommendations (Rev. 25)

Handout 3 - Completed PAR based on Plant Conditions (Attachment 9.5 of OP3511) filled out a?

follows:

Current Date Current Time Section I - an S is placed in front of Guilford, Vernon, Hinsdale, Winchester, Bernardston, and Northfield.

Approved By and Date/Time (This PAR should be accomplished just a few minutes before the operator needs to use the completed PAR)

Shift Manager Box Checked This JPM requires the use of a Computer with ODPS capability, and the ERFIS Printer to be available for printing.

Simulator Setup:

Any full power IC.

Insert malfunction RMOlF at .04 (4000 mrhr).

Ensure all HVAC systems are normal and no group 3 isolation is present.

Ensure that simulator is in RUN for a minimum of 15 minutes prior to conduct of JPM to allow Met Data average readings to stabilize.

Reset to IC-824 Examiner Notes:

This JPM should be conducted simultaneously with Ala RO.

JPM A4 SRO

JPM A4 SRO Rev. 121 108 Page 4 of 1 1 rovide Candidate with Initial Conditions/Cue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATAJNSAT Step 1: Obtain Procedure OP 3513.

Standard: The operator obtains OP 35 13.

The operator turns to Section 5.9, Initial Evaluation.

Interim Cue: When it is apparent that the operator is seeking to find OP 3513,Examiner provides copy (Handout 1).

SATAJNSAT Step 2: (Steps 5.9.1E.9.1.a) Immediate Action by the SM/PED or Desipnated Plant Staff Member. Upon receivinp an indication of a significant release of radioactivity is occurrinp and the EOF has not been activated, initiate or assign a aualified individual to perform the appropriate calculations in this procedure to evaluate the off-site radiological conditions.

Standard: The operator recognizes that they have been assigned to evaluate the cff-site radiological conditions and proceeds to Step 5.9.1.b.

SAT/UNSAT Step 3: (NOTE prior to Step 5.9.1.b) Attachment 9.11 is a flow chart available to assist in the identification of dose assessment activities to be considered and implemented.

Standard: The operator reads the Note, refers to Attachment 9.11, and proceeds ti, Step 5.9.1.b.

JPM A4 SRO

JPM A4 SRO Rev. 121108 Page 5 of 11

',valuation Performance Steps SATAJNSAT Step 4: (Step 5.9.1.b) For an actual ground release.. ....

Standard: The operator recognizes that a ground release is NOT in progress, an(

proceeds to Step 5.9.l.c.

SATAJNSAT *Step 5: (Step 5.9.l.c) If the Stack High Range Monitor equals or exceeds 20 m R k r , request the Chemistry Technician to obtain a silver zedite cartridge air sample from the main stack sample point for an iodine release rate determination.

Standard: The operator observes the Stack High Range Monitor to be reading 4(~00 mrhr.

The operator contact and directs the Chemistry Technician to obtain a silver zeolite cartridge air sample from the main stack sample point for an iodine release rate determination.

Interim Cue: When action is taken, Examiner inform operator that the Chemistry Technician acknowledges.

SATAJNSAT *Step 6: (Step 5.9.1.d) If ODPS is operable, then implement Attachment 9.3 to access off-site dose proiection information from ODPS.

Standard: The operator proceeds to Attachment 9.5.

SATAJNSAT Step 7: (Attachment 9.5. Steps l , l . a and NOTE prior top Step l.a.1) Obtain the necessary off-site dose pro.iection information for stack and ground release as follows: IF A STACK RELEASE IS OCCURRING: Meteorological and source term data are automatically input to model. Manual input of data is not necessarv.

Standard: The operator reads the Note and proceeds top Step 1.a. 1.

JPM A4 SRO

JPM A4 SRO Rev. 121108 Page 6 of 11 valuation Performance Steps SATKJNSAT Step 8: (Step l.a.1) Click the "ODPS" menu item on the RTIME menu bar to access the "ODPS Menu"; OR if the workstation has an ERFISL terminal kevboard, press the "ODPS" kev.

Standard: The operator accesses ODPS to "ODPS Menu" screen.

SATAJNSAT Step 9: (Step l.a.2) Click on the "SOURCE TERM DATA" box to display screen.

Standard: The operator Clicks on the "SOURCE TERM DATA" box, and obser ves VYOPF 3513.01 "Source Term Data" screen.

SATKJNS AT Step 10: (NOTE prior to Step l.a.3) ERFIS Printer must be on-line now.

Standard: The operator reads the Note, and proceeds to Step l.a.3.

SATKJNSAT Step 11 (Step l.a.3) Click on the PRINTER icon to obtain record of stack release pro-iectioninformation (Reactor Trip Status and Stack).

Standard: The operator Clicks on the PRINTER icon, and obtains the printout.

SATAJNSAT Step 12: (Step l.a.4) Click the "ODPS" menu item on the RTIME menu bar to access the "ODPS Menu"; OR if the workstation has an ERFIS terminal kevboard, press the "ODPS" kev.

Standard: The operator clicks the "ODPS" menu item on the RTIME menu bar; i>R if the workstation has an ERFIS terminal keyboard, presses the "ODPS" key.

SATKJNSAT Step 13: (Step l.a.5) Click on the "PROTECTIVE ACTION RECOMMENDATIONS LIVE STACK MR/HR" box to displav screen.

Standard: The operator clicks on the "PROTECTIVE ACTION RECOMMENDATIONS LIVE STACK MR/HR" box.

SATKJNSAT Step 14: (Step l.a.6) If ODPS aborts due to bad input (as indicated on screen displav). ........

Standard: The operator recognizes that ODPS does NOT abort. and proceeds to Step l.a.7.

JPM A4 SRO

JPM A4 SRO Rev. 121108 Page 7 of 1 1 Evaluation Performance Steps SATAJNSAT Step 15: (Step l.a.7) When "PROTECTIVE ACTION RECOMMENDATION" screen is displaved, click on the PRINT!+Z icon to obtain stack release off-site dose pro-iectioninformation.

Standard: When the "PROTECTIVE ACTION RECOMMENDATION" screen is displayed, the operator clicks on the PRINTER icon, and obtains the printout.

SATAJNSAT Step 16: (Step l.a.8) Click the "ODPS" menu item on the RTIME menu bar to access the "ODPS Menu"; OR if the workstation has an ERFIS terminal keyboard, press the "ODPS" kev.

Standard: The operator clicks the "ODPS" menu item on the RTIME menu bar to; OR if the workstation has an ERFIS terminal keyboard, presses the "ODPS" key.

SATAJNSAT Step 17: (Step l.a.9) If no ground release is occurring, skip Attachment 9.5&

Step 1.b for wound release and then continue with Attachment 9.5, Step 2.

Standard: The operator recognizes that there is no ground release in progress, an*l proceeds to Step 2 of Attachment 9.5.

SATRJNSAT Step 18: (Steps 2/2.a) Use printed screen information from above to do the following: If multiple release points exist (stack and ground),. .....-.

Standard: The operator recognizes that only one release point exists, and proceec's to Step 2.b.

SATAJNSAT Step 19: (Steps 2.b/2.b.l) If onlv one release point exists (stack or groundh then continue with the following actions: Implement OP 3511 Section 5.7 Step 5.7.5 to formulate Protective Action Recommendations for State authorities.

Standard: The operator recognizes that only one release point exists, and seeks tc find OP3511.

The operator proceeds to Step 5.7.5.

Interim Cue: When it is apparent that the operator is seeking to find OP35 11, Examiner provides copy (Handout 2).

JPM A4 SRO

JPM A4 SRO Rev. 121108 Page 8 of 11

',valuation Performance Steps SATIUNSAT *Step 20: (Step 5.7.5/5.7.5.a) Determllie appropriate Protective Actlan Recommendations (PAR) as follows: (Use Section I1 of Attachmet&

9.5) Compare the calculated dose projection results with EPA Protective Action Guidelines delineated below to determine whether EPA Protective Action Guidelines have been exceeded. If the EP i Protective Action Guidelines have not been exceeded, then complag Attachment 9.5 Section 11, indicatinp that there is no PAR based 4%

radiolog!ical conditions.

Standard: The operator uses information from ODPS or obtained in previous prinout and notes that Total Effective Dose is >1 REM between the Stte Boundary and 5 miles and recognizes that evacuation is needed.

SATKJNSAT Step 21: (Step 5.7.5.b) Attachment 9.2 and Attachment 9.3 are conservativelv based on METPAC plume traiectories, the river vallev effect for stabilitv classes E, F and G, and plume width.

Standard: The operator reads step and proceeds to Note prior to Step 5.7.5.c.

SATKJNSAT Step 22: (NOTE prior to Step 5.7.5.c) The Town of Marlboro, VT is not a VY EPZ town.

Standard: The operator reads Note and proceeds to Step 5.7.5.c.

SATKJNSAT Step 23: (Step 5.7.5.c) I n the EOF, in the initial stages of the event, the p l u i ~

tra-iectorv is determined bv calculatinp a "what if" METPAC 10-mile plume pro.iection with a default source term and actual meteorology using the METPAC Batch Mode with 8 time steps pet:

OP 3513,Attachment 9.9 Standard: The operator recognizes that the EOF is NOT manned, and proceeds t c l Step 5.7.5.d.

SATKJNSAT Step 24: (Step 5.7.5.d) In all cases, use the field team data to verifv the actual downwind direction of the plume. Adiust the PAR as appropriate Standard: The operator recognizes that the Field Team data and the ODPS data a -e the same, and proceeds to Step 5.7.5.e. 1.

Interim Cue: Examiner inform the operator that the Field Team data reflects the ODPS data.

JPM A4 SRO

JPM A4 SRO Rev. 121108 Page 9 of 11 Evaluation Performance Steps SATAJNSAT *Step 25: (Step 5.7.5.e/(3)) Choose the towns affected by the PAR as fo1low:Lf ODPS shows that the PAR (evacuation) is exceeded between the si&

-

e meteoroloPica1 data (wind direction and stability class) to obtain affected towns out to five miles downwind.

Standard: The operator observes that ODPS shows that the PAR is exceeded between five miles and the Site Boundary.

The operator observes the previously obtained printout and determines the wind direction to be 3-7".

The operator observes the previously obtained printout and determines the Stability Class to be A.

The operator refers to Attachment 9.3, using Sector A (3-7"), with a Stability Class A, and determines that Vernon, Hinsdale, Bernardston and Northfield must be evacuated.

ATAJNSAT Step 26: (Step 5.7.5.0 Anv prior protective action recommendations that are still in effect should be included with updated information and documentation (Attachment 9.5).

Standard: The operator recognizes that an initial PAR is being prepared by another operator, and proceeds to Step 5.7.5.g.

Interim Cue: When the operator is seeking any previous PARS,Examiner provide the PAR completed minutes earlier based on Plant Conditions (Handout 3).

SATAJNSAT Step 27: (Step 5.7.5.g) Barring impediments, (e.g., weather or a competing disaster) once a town has been recommended to evacuate, the morq conservative action will be followed even if updated analyses or conditions indicate that sheltering in place would be sufficient.

Standard: The operator recognizes that an initial PAR is being prepared by anothcr operator, and proceeds to Step 5.7.5.h.

Interim Cue: If asked, Examiner cue the operator that there is no unusual weather conditions, nor is there a competing disaster.

JPM A4 SRO

JPM A4 SRO Rev. 121108 Page 10 of 1 1

,valuation Performance Steps SAT/UNSAT *Step 28: (Step 5.7.5.h) Record appropriate PAR information in Section I1 ,&

Attachment 9.5.

Standard: The operator records the current Date and Time on Attachment 9.5.

The operator places an E in the Vermont Town of Vernon, and the New Hampshire Towns of Hinsdale, the Massachusetts Towns of Bernardston and Northfield on Section I1 of Attachment 9.5.

The operator places a check in the ODPS Box on Section I1 of Attachment 9.5.

The operator places their name in the Performed By Box on Section I1 of Attachment 9.5.

The operator seeks and independent verification of the PAR.

Interim Cue: Examiner as independent verifier, sign Attachment 9.5 independent verification.

SAT/UNSAT Step 29: (Step 5.7.6) Forward completed Attachment 9.5 to the Site Rec0vc-a Manager or senior manager in charge.

Standard: The operator presents the completed Attachment 9.5 to the PED, and indicates that the initial PAR either has been recently prepared, or is s.,ill in progress.

Critical Step TIME FINISH:

Terminating Cue: This completes the JPM.

Evaluator Comments:

iystem Generic WAs: 2.4.44 (2.414.4)

JPM A4 SRO

EXAMINEE HANDOUT Initial Conditions:

0 A reactor transient has occurred resulting in fuel damage.

An elevated release through the plant stack has just begun, and a General Emergency EAL has lbeen declared 5 minutes ago.

There is no ground release in progress.

0 Another SRO has been assigned to Use OP 35 11, Off-Site Protective Action Recommendations Section 5.6, Protective Action Recommendation Based on Plant Conditions, Attachment 9.4, General Emergency Protective Action Recommendations (PARS)Flowchart.

ODPS is operable.

The EOF is NOT yet manned.

Initiating Cues:

You have been assigned by the PED to implement OP 3513, Evaluation of Off-Site Radiological Conditions, Section 5.9, Initial Evaluation; and prepare a PAR based on Off-Site Radiological Conditions and return it to the PED.

I JPh -S1 Rev. 121 108 Page 1 if 8 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Shift Rx Level Control From The Main Feed Rep Valve To The Auxiliary Fc Reg Valve Failure Mode: Aux Feed Reg Valve Controller fails such that valve fully opens

Reference:

OP 0105, Reactor Operations, (Rev. 86)

EN-OP-115, Conduct of Operations, (Rev. 6)

Task Number: 2590060101,2590070101,2590080101 Task Performance: AO/RO/SRO __ RO/SRO X SRO Only -

Sequence Critical: Yes - No 3 Time Critical: Yes - No 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: 17 minutes Evaluation Results:

Performance: PASS - FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedKertified Reviewer Date Approved by:

Operations Training Superintendent Date JPM-S 1

JPI'e4-S1 Rev. 12 t 108 Page 2 of 8 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him o 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 fc lr 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 beinp 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.

nitial Conditions:

0 A normal plant shutdown in progress.

0 Reactor Power is = 5-10%.

OP 0105, Reactor Operations Phase 5C, is completed through Step 2.b.6.g.

Initiating Cues:

The CRS directs you to transfer Rx level control from the A FRV to the Auxiliary FRV in accordance with OP 0105, Phase 5C, Step 2.c (Page 136 of 152).

Task Standards:

The operator shifts the Reactor level control in accordance with procedures from the Main Feed Reg Valve to the Aux Feed Reg Valve, and then responds to a failure of the Aux Feed Reg Valve Contro by placing the controller in MANUAL, and controlling Reactor level manually.

Required Materials:

Handout 1 - OP 0105, Reactor Operations, (Rev. 86)

JPM-S 1

JPI4-S 1 Rev. 1211108 Page S of 8 Simulator Setup:

Reset to IC-8 Lower power to 5-10% using OP0105.

Ensure "A"FRV in Auto with "V" displayed on Controller.

Ensure "B"FRV in Manual and closed.

Ensure FDW- 11B is closed.

Insert FDW-13 Controller failure to open valve fully (malf FW-13 to 100% with no ramp) on Key li.

Reset to IC-850 Ensure "A"FRV in Auto with "V" displayed on Controller.

JPM-S 1

JPM-S 1 Rev. 12 L 108 Page L of 8 Provide Candidate with Initial ConditiondCue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATKJNSAT Step 1: Obtain Procedure.

Standard: The operator obtains OP 0105, Rev 86.

Proceeds to Step 2.c of Phase 5C, Page 136 of 152.

Interim Cue: When it is apparent that the operator is seeking to find OP 0105, Examiner provides copy (Handout 1).

SATKJNSAT *Step 2: (Step 2.c.1/2.c.l.a-b) In manual, slowly open the aux. feed reg. valve as follows:

On AUX FEED REG VLV FDW-13 CONTROLLER use the disalav pushbutton to display AUXFRV.V.

Adiust output as reauired bv plant conditions using the adjustment

-

knob.

Standard: The operator presses the D display button until V is displayed (0.0)

The operator turns the knob on the AUX FRV Controller in the clockwise direction to slowly open the FDW-13 valve.

NOTE: The operator may observe FDW-13 Red status lights are ON (two sets, 9-5 and 9-6) (NOT Critical).

SATKJNSAT Step 3: (Step 2.c.2) Check that the main feedwater regulator valve in service closes.

Standard: As the operator is adjusting the FDW-13 Controller, the operator observes the valve position indication on FDW-13 to be increasing, arid valve position on A FRV controller decreases toward 0.

The operator observes Reactor Water Level on LI-6-94NB in Green Band.

The operator observes the Red status light OFF on FRV A.

JPM-S 1

JPI 1-S1 Rev. 12 108 Page 5 of 8 Evaluation Performance Steps SATKJNSAT *Step 4: (Steps 2.c.3/3.a/3.a.l) When the main feedwater regulator valve indicates fully closed perform the following:

Transfer AUX FEED REG VLV FDW-13 CONTROLLER from manual to automatic as follows:

On AUX FEED REG VLV FDW-13 CONTROLLER use the disk*

pushbutton to observe the value of the following:

AUXFRVS AUXFRV.P Standard: The operator observes the valve position indication on A FRV controller at 0.

NOTE: The operator may observe A FRV Red status lights are ON (two sets, 9-5 and 9-6) (NOT Critical).

The operator presses the D display button to observe the S and P values.

QATAJNSAT *Step 5: (Step 2.c.3.a.2.a-b) Using one or both of the followinp steps as plant conditions dictate, ad-iust the FWLC system so that AUXFRV.S and AUXFRV.P indicate the same value.

Adjust AUX FEED REG VLV FDW-13 CONTROLLER to raisehower reactor water level.

Adiust AUXFRVS Standard: The operator balances S and P by using the controller knob to change RPV level, or by changing the setpoint.

NOTE: To change the setpoint, S is selected. To change RPV level P or V is displayed.

SATAJNSAT *Step 6: (Step 2.c.3.a.3) WHEN AUXFRV.S and AUXFRV.P indicate the same value, on AUX FEED REG VLV FDW-13 CONTROLLER depress the A/M pushbutton.

Standard: The operator observes that P (level) and S (setpoint) are equal by changing the number displayed by using the D display pushbutton.

The operator presses the A/M button on the controller.

JPM-S 1

JPIs,II-Sl Rev. 12 I 108 Page f of 8 Evaluation Performance Steps dAT/UNSAT Step 7: (Steps 2.c.3.a.3.a-b) On AUX FEED REG VLV FDW-13 CONTROLLER verifv the green auto LED illuminates.

On AUX FEED REG VLV FDW-13 CONTROLLER verifv the manual LED extinguishes.

Standard: The operator observes the Green M/A LED is ON.

The operator observes the Red M/A LED is OFF.

SATAJNSAT Stew 8: (Steps 2.c.3.a.414.a-b)To adjust the AUX FEED REG VLV F D W - Q CONTROLLER setpoint proceed as follows:

On AUX FEED REG VLV FDW-13 CONTROLLER use the d i s p k pushbutton to displav the AUXFRV.S value.

Ad-iustsetpoint as required bv plant conditions using the adiustment

-

knob.

Standard: The operator adjusts level as necessary by ensuring S is displayed and changing the setpoint using the knob on the FDW-13 controller.

NOTE: The operator may not need to adjust the controller.

SAT/UNSAT *Step 9: (Step 2.c.3.b) Close BLOCKING VALVE FDW-llA(B) for the main feedwater regulating valve h s t removed from service.

Standard: The operator places FDW- 11A control switch to close, spring return to normal, and observe Green light to ON and Red light to OFF.

SIMULATOR INSTRUCTOR: When FDW 11A is CLOSED, insert malfunction on FDW-13 Contro!ler causing valve to go full open.

NOTE: Use Panel Override for Panel 9-6 to watch Blocking Valve position.

JPM-S 1

JPE 1-S1 Rev. 12 108 Page 5 of 8 Evaluation Performance Steps SATAJNSAT Step 10: (Step 2.c.3.c/2.c.3.c.l) Transfer the RX VESSEL LEVEL MAST) 3 CONTROLLER to manual as follows: Verifv MASTER.S and MASTER.P indicate the same value THEN depress the A/M pushbutton Verifv the Preen auto LED extinmishes Verifv the red manual LED illuminates Standard: The operator presses the D display button to observe the S and P values.

When the Reactor level on the Controller is observed, the operator w +L1 note that Reactor water level is higher than expected.

~~

NOTE: If the operator does not notice the unexpectedly high Reactor water level, MCB Annunciator 9-5/E-6, FW CONTROL SYSTEM TROUBLE, will alarm within 1.5-2 minutes, and 9-5E-1, RX WATER LEVEL HILO, will alarm shortly thereafter.

SATAJNSAT *Step 11: (EN-OP-115, Step 5.3) If an automatic control malfunctions, immediately place that control in manual.

Standard: The operator presses the A/M button on the AUX FEED REG FDW- i 3 controller.

The operator observes the Red M/A LED is ON and the Green M/A L ED is OFF.

The operator adjusts level as necessary by ensuring V is displayed and using the knob on the FDW-13 controller to control level at 160.

TIME FINISH:

Terminating Cue: This JPM is complete.

Evaluators Comments:

System: 259002 WA: A4.01 (3.U3.6)

JPM-S 1

EXAMINEE HANDOUT nitial Conditions:

0 A normal plant shutdown in progress.

0 Reactor Power is = 5-1096.

0 OP 0105, Reactor Operations Phase 5C, is completed through Step 2.b.6.g.

Initiating Cues:

The CRS directs you to transfer Rx level control from the A FRV to the Auxiliary FRV in accordai ice with OP 0105, Phase 5C, Step 2.c (Page 136 of 152).

JPR I -S2 Rev. 11 008 Page 1 of 6 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Swap Pressure Regulators (EPR to MPR)

Failure Mode: -NIA

Reference:

OP 2 160, Turbine Generator Support Systems Operation, (Rev. 24)

Task Number: 24 1000 Task Performance: AOROISRO - RO/SRO Only X SE Only __

Sequence Critical: Yes No -

Time Critical: Yes - No 3 Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation - Performance X Discuss _ _

Setting: Classroom _. Simulator X Plant -

Performance Expected Completion Time: 13 minutes Evaluation Results:

Performance: PASS __ FAIL __ Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedICertifiedReviewer Date Approved by:

Operations Training Superintendent Date JPM-S2

JPh I-S2 Rev. 11 008 Page 2 of 6 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him t 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 fc r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical st :p is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measur :.

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 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:

The plant is operating normally at power 0 The white light for the EPR Regulator is lit.

Initiating Cues:

The CRS directs you to transfer control from the EPR to the MPR and secure the EPR for I&C maintenance using Section B.l of OP 2160, Turbine Generator Support Systems Operation.

Task Standards:

The MPR is placed in service in accordance with Procedure OP 2 160, Section B. 1.

Required Materials:

Handout 1 - OP 2160, Turbine Generator Support Systems Operation, (Rev. 24)

Simulator Setup:

LOO%power 0 EPR Regulator in service

-

OR Reset to IC 854 Adjust MPR Stroke to - 10%less than EPR Stroke JPM-S2

JPh 1-S2 Rev. 11 008 Page 3 of 6 rovideCandidate with Initial Conditions/Cue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATAJNSAT Step 1: Obtain Procedure.

Standard: The operator obtains OP 2160, Rev 24.

Proceeds to Section B. 1, Swapping Pressure Regulators.

Interim Cue: When it is apparent that the operator is seeking to find OP 2160, Examiner provides copy (Handout 1).

SATAJNSAT Step 2: (Steps U1.a) If desired, transfer pressure control from EPR to MPR (White light lit for EPR) as follows: If time permits, verifv that the MPR pilot bushing is rotating.

Standard: The operator contacts the A 0 and directs that the MPR pilot bushing he verified rotating.

Interim Cue: As AO, Examiner inform the operator that the MPR pilot bushing is rotating.

SATAJNSAT Step 3: (Step 1.b) Verifv MPR OUTPUT STROKE is approximately 10%

below EPR OUTPUT STROKE setting.

Standard: The operator observes stroke on MPR Stroke (POI-110-22) and EPR Stroke (POI-110-24),compares the two and determines that MPR Output

-

Stokes is 10% below EPR Output Stroke.

SATAJNSAT Step 4: (Step 1.c) Verify bulb for oncoming pressure repulator is sound.

Standard: The operator removes MPR white light bulb and places bulb in a knom n-energized lamp socket to verify that the bulb is good, then replaces bul.3 in the MPR white light socket, or verifies it is sound by observing the intact filament.

JPM-S2

JPh [-S2 Rev. 11 008 Page 4 of 6 Evaluation Performance Steps SATAJNSAT *Step 5: (Step 1.d) Using MPR SET-POINT switch. slowly lower the MPR SET-POINT bv going to LOWER until the MPR OUTPUT STROKE moves in the direction of the EPR OUTPUT STROKE setting.

Standard: The operator rotates MPR Output Switch to the LOWER position, an' L observes that the MPR Output Stroke (POI-110-22) moves in the direction of the EPR Output Stroke (POI-110-24) setting.

SATAJNSAT Step 6: (NOTES prior to Step 1.e) Both white liphts will be lit for a brief time and then only the light for the MPR will be lit.

Reactor pressure may drop slightlv following regulator transfer.

Standard: The operator reads the Notes and proceeds to Step 1.e.

SATAJNSAT *Step 7: (Step 1.e) Continue to slowly lower the MPR SET-POINT until the MPR begins to take control Standard: The operator rotates MPR Output Switch to the LOWER position, and observes that the MPR Output Stroke (POI-1 10-22) moves in the direction of the EPR Output Stroke (POI- 11-24) setting until the MPR takes control.

SATKJNSAT Step 8: (Step l.f.1) Verifv MPR has pressure control as follows:

Verifv white light above MPR SET-POINT switch is illuminated.

Standard: The operator observes the White light above MPR Setpoint Switch is ON.

NOTE: Both the MPR and EPR White lights are ON.

SATAJNSAT Step 9: (Step l.f.2) Verifv white light above EPR SET-POINT switch is extinguished Standard: The operator observes the White light above EPR Setpoint Switch is OFF.

SATKJNSAT Step 10: (Step l.f.3) On CRP 9-5, verifv stable reactor pressure.

Standard: The operator observes reactor pressure constant (as indicated on CRP 4)-

5).

JPM-S2

JPh -S2 Rev. 11 1008 Page 5 of 6 Evaluation Performance Steps SATKJNSAT Step 11: (Step 1.g) If either pressure regulator fails to control pressure, re&

to OT 3115, Reactor Pressure Transients, for immediate actions.

Standard: The operator observes that the MPR is controlling pressure and proce :ds to Step 1.h.

SATAJNSAT *Step 12: (Step 1.h) Using EPR SET-POINT switch, slowly RAISE the EPH-SET-POINT, by going to RAISE. EPR OUTPUT STROKE will slowlv decrease to zero with MPR in control.

Standard: The operator rotates the EPR Setpoint Switch to the RAISE position itntil the EPR Output Stroke slowly lowers to zero.

SATAJNSAT Step 13: (Step l.Ul.i.1) EPR cutout switch may be placed in CUTOUT (OFF),

if required.

Verify alarm 7-6-2, "EPR CONTROL POWER LOSS/T.ROUBLE" is energized.

Standard: The operator places the EPR Cutout Switch to OFF and verifies that alarm 7G-2, "EPR CONTROL POWER LOSS/TROUBLE" is energi.ed.

SATAJNSAT Ster, 14: (Step 1.d)Ad-iust reactor pressure as necessary.

Standard: The operator observes reactor pressure and determines that further adjustment is NOT needed.

Critical Step TIME FINISH:

Terminating Cue: This JPM is complete.

Evaluator Comments:

~ ~

System: 241000 WA: A4.19 (3.Y3.4)

JPM-S2

EXAMINEE HANDOUT Initial Conditions:

The plant is operating normally at power The white light for the EPR Regulator is lit.

Initiating Cues:

The CRS directs you to transfer control from the EPR to the MPR and secure the EPR for I&C maintenance using Section B.l of OP 2160, Turbine Generator Support Systems Operation.

JPh -S3 Rev. 111008 Page 1 o r 10 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Secure RHR from the Shutdown Cooling Mode Failure Mode: NIA

Reference:

OP 2124, Residual Heat Removal System, (Rev. 113)

Task Number: 2050110101 Task Performance: AO/RO/SRO - RO/SRO Only X SE Only -

Sequence Critical: Yes - No 2 Time Critical: Yes - No 2 Indhidual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation __ Performance X Discuss -

Setting: Classroom _. Simulator X Plant __

Performance Expected Completion Time: 12 minutes Evaluation Results:

Performance: PASS - FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedCertified Reviewer Date Approved by:

Operations Training Supervisor Date JPM-S3

JPh ' -S3 Rev. 11 1008 Page 2 c F 10 Oirections:

Discuss the information given on this page with the operator being evaluated. Allow time for him t )

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 fa -

any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical st :p is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measur,:.

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 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:

The plant is operating with RHR in the Shutdown Cooling Mode in accordance with OP 2124, Residual Heat Removal System, Section G, Normal Shutdown Cooling Operational Sequence.

The A RHR Pump is in operation.

The RWCU System is in its normal alignment in accordance with OP 21 12, Reactor Water Clea iup System.

The Condensate System is available.

Initiating Cues:

The CRS has directed you to secure from the Shutdown Cooling Mode in accordance with OP 2124 Section J, Securing the Shutdown Cooling Mode.

Task Standards:

The RHR System has been secured from the Shutdown Cooling Mode in accordance with Steps 1- 1 '

of Section J of OP 2124, Residual Heat Removal System.

Required Materials:

Handout 1 - OP 2124, Residual Heat Removal System (Rev. 113)

JPM-S3

JPh -S3 Rev. 11 1008 Page 3 cF 10 Simulator Setup:

Reset to IC-852 JPM-S3

JPh -S3 Rev. 111008 Page 4 c F 10 3rovide Candidate with Initial ConditiondCue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATAJNSAT Step 1: Obtain Procedure and review prereuuisites Standard: The operator obtains OP 2124, Rev 113.

Proceeds to Section J, Securing Shutdown Cooling Mode.

Interim Cue: When it is apparent that the operator is seeking to find OP 2124, Examiner provides copy (Handout 1).

SATKJNSAT Step 2: (Step 1)If RWCU return to RHR SDC suction line is in service, return RWCU to normal alignment, or secure the RWCU system Der OP 2112.

Standard: The operator recognizes that the RWCU is NOT aligned with its returu to RHR SDC (Initial Conditions), and proceeds to Step 2.

SATAJNSAT *Step 3: (Step 2) On CRP 9-3, close OUTBD INJECTION, RHR-27A(B).

Standard: The operator takes the RHR-27A control switch to CLOSE, and obser ires the Green light ON, and the Red light OFF.

The operator observes A RHR Pump amps and flow on FI-10-139A decreases.

SATAJNSAT *Step 4: (Step 3) Secure the running RHR pumps.

Standard: The operator takes the A RHR Pump control switch to STOP, and observes the Green light ON, and the Red light OFF.

The operator observes A RHR Pump amps decreases to 0.

NOTE: The operator may make a plant announcement concerning the shutdown of the A RHR Pump (Not Critical).

JPM-S3

J P P -S3 Rev. 11I008 Page 5 o 10 dvaluation Performance Steps SATAJNSAT Step 5: (NOTE prior to Step 4) Reactor recirculation pump startup may r~

performed in parallel with securing shutdown cooling;,

Standard: The operator reads the Note and proceeds to Step 4.

SATAJNSAT Step 6: (Step 4) If possible, start the recirc pump(s) at this time per OP 211 10.

Standard: The operator seeks direction regarding the operation of the Recircula: ion Pumps from the CRS.

After cue, the operator proceeds to Step 5.

Interim Cue: Examiner cue operator that another operator will be starting the recirculation pumps in accordance with OP 21 10, and that the securing of the Shutdown Cooling Mode should continue.

SATKJNSAT Step 7: (Step 5 ) On CRP 9-3, open HX BYPASS, RHR-65A.

Standard: The operator opens RHR-65A by taking the control switch to OPEN a,Id observes the Red light ON and the Green light OFF.

SATIUNSAT Step 8: (Step 6) On CRP 9-3, open HX BYPASS. RHR-65B.

Standard: The operator observes the Red light ON and the Green light OFF for RHR-65B, and determines the valve is OPEN.

JPM-S3

JPIL -S3 Rev. 11 1008 Page 6 c F 10 dvaluation Performance Steps SATNNSAT *Step 9: (Step 7) On CRP 9-3, close the following:

S/D CLG SUCTION, RHR-17 S/D CLG SUCTION, RHR-18 PUMP SUCTION, RHR-15A PUMP SUCTION, RHR-15C PUMP SUCTION, RHR-15B PUMP SUCTION, RHR-15D Standard: The operator closes RHR-17 by taking the control switch to CLOSE, md observing the Green light ON and the Red light OFF.

The operator closes RHR-18 by taking the control switch to CLOSE, and observing the Green light ON and the Red light OFF.

The operator closes RHR-15A by taking the control switch to CLOSE, and observing the Green light ON and the Red light OFF.

The operator closes RHR-15C by taking the control switch to CLOSE, and observing the Green light ON and the Red light OFF.

The operator observes the Green light ON and the Red light OFF for RHR-ISB, and determines the valve is CLOSED.

The operator observes the Green light ON and the Red light OFF for RHR-15D, and determines the valve is CLOSED.

NOTE: The operator may close another valve before the one presently stroking closed is CLOSED.

SATAJNSAT Step 10: (Step 8) Place Isolation switch (Radwaste corridor) for shutdown cooling valves RHR-17/18 in LOCKOUT position.

Standard: The operator contacts the A 0 and directs that the Isolation Switch for RHR- 17/18 be placed in the LOCKOUT position.

Interim Cue: As the AO, Examiner inform the operator that the Isolation Switch for RHR-17/18 hz .i been placed in the LOCKOUT position.

JPM-S3

JPPV -S3 Rev. 111908 Page 7 0.10 dvaluation Performance Steps SAT/UNS.AT *Step 11: (Step 9) Open:

PUMP SUCTION, RHR-13A PUMP SUCTION, RHR-13C PUMP SUCTION. RHR-13B PUMP SUCTION, RHR-13D MINIMUM FLOW, RHR-16A MINIMUM FLOW, RHR-16B Standard: The operator opens RHR-13A by taking the Key control switch to OPEN, and observing the Red light ON and the Green light OFF.

The operator opens RHR-13C by taking the Key control switch to OPEN, and observing the Red light ON and the Green light OFF.

NOTE: MCB Annunciator 9 - 3 L - 3 , RHR TORUS SUCT VLV CLOSED, is expected to clew after this action.

The operator observes the Red light ON and the Green light OFF, and determines that RHR-13B is OPEN.

The operator observes the Red light ON and the Green light OFF, and determines that RHR-13D is OPEN.

The operator opens RHR-16A by taking the control switch to OPEN, .md observing the Red light ON and the Green light OFF.

The operator observes the Red light ON and the Green light OFF, and determines that RHR-16B is OPEN.

NOTE: The operator may close another valve before the one presently stroking closed is CLOSED.

JPM-S3

JPW -S3 Rev. 111308 Page 8 0.10 dvaluation Performance Steps SATRJNSAT Step 12: (Steps 10/10.a) Establish keep fill pressure as follows: If condens.&

system pressure is available open RHR30A(B), RHR Loop A(B)

Pressurizing Line.

Standard: The operator contacts the A 0 and directs that RHR-30A be opened.

The operator contacts the A 0 and directs that RHR-30B be opened.

Interim Cue: As the AO, Examiner cue operator that RHR-30A and RHR-30B are OPEN.

SAT/UNSAT Step 13: (CAUTION prior to Step 10.b) Reactor coolant temperature must be

~ 2 1 2 ° Fto use this procedure section.

Standard: The operator reads the Caution and proceeds to Step 10.b.

SATAJNSAT Step 14: (Step 10.b) IF condensate transfer system will be used to provide keep fill water .......

Standard: The operator recognizes that the Condensate Transfer System will NOT be used and proceeds to Step 11.

SATRJNSAT Step 15: (Step 11)Opedcheck open and lock RHR Hx A(B) Inlet, RHR-23A(B).

Standard: The operator directs that RHR-23A be checked open and that the valv :

be locked in the open position.

The operator directs that RHR-23B be checked open and that the valvle be locked in the open position.

Interim Cue: Examiner cue operator that RHR-23A and RHR-23B are OPEN.

JPM-S3

JPb -S3 Rev. llli308 Page 9 o 10 Evaluation Performance Steps SATAJNSAT Step 16: (NOTE prior to Step 12) Manuallv closing RHR-S9A(B) with an RHRSW pump running can result in lifting safetv relief valve SR-lO-SOA(B).

Standard: The operator reads the Note and proceeds to Step 12.

SATAJNSQT *Step 17: (Steps 12/12.a) When the RHRSW pump has run at least 10 minutes after the RHR pump is stopped, then secure the running RHRSm pumps. Observe RHRSW DISCHARGE valve, RHR-S9A(B), C I O Y ; ~

automaticallv.

~ ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~ ~

Interim Cue: Examiner cue operator that the RHRSW Pump has run 10 minutes since the RHR Pump A has been stopped.

Standard: After the cue, the operator takes the A RHRSW Pump to STOP, and observes the Green light ON and the Red light OFF.

After stopping the RHRSW Pump, the operator observes RHR-89A automatically closes by observing the Green light ON and the Red liglit OFF.

The operator observes flow on FI-10-132A decreases to 0.

NOTE: MCB Annunciator 9-3/K-4, RHR SW PUMP A/C Running, is expected to clear after this action.

TIME FINISH:

Terminating Cue: This JPM is complete.

Evaluator Comments:

System: 205000 WA: A4.01 (3.7/3.7)

JPM-S3

EXAMINEE HANDOUT Initial Conditions:

The plant is operating with RHR in the Shutdown Cooling Mode in accordance with OP 2124, Residual Heat Removal System, Section G, Normal Shutdown Cooling Operational Sequence.

0 The A RHR Pump is in operation.

0 The RWCU System is in its normal alignment in accordance with OP 21 12, Reactor Water Cleanup System.

0 The Condensate System is available.

Initiating Cues:

The CRS has directed you to secure from the Shutdown Cooling Mode in accordance with OP 2124, Section J, Securing the Shutdown Cooling Mode.

JPR, -s4 Rev. 111008 Page 1 c F 12 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Line-up for Primary Containment Spray Using Fire System to RHR Loop A Failure Mode: -

NA

Reference:

OE 3107, OE Appendices. Appendix S, (Rev. 25)

Task Number: 2000070501 Task Performance: AORO/SRO - RO/SRO X SRO Only Sequence Critical: Yes - No Time Critical: Yes - No 3 Operator Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation - Performance X Discuss Setting: Classroom - Simulator Plant Performance Expected Completion Time: 17 minutes Evaluation Results:

Performance: PASS - FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedKertified Reviewer Date Approved by:

Operations Training Supervisor Date JPM-S4

JPh -S4 Rev. 11 11008 Page 2 c F 12 lirections:

Discuss the information given on this page with the operator being evaluated. Allow time for him t 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 fo .

any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical stcp 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.

'nitial Conditions:

Drywell pressure is high.

0 Torus Spray is required per EOP-3 and RHR and RHRSW Pumps are unavailable for use.

The Emergency Diesel Generators have been stopped.

No Service Water Pumps are available.

Fire Water Pumps are running.

Initiating Cues:

The CRS has directed you to line-up and spray the TORUS using the Fire System to RHR Loop "A" from the Control Room, IAW OE 3107, Appendix S, Step 2.

Auxiliary Operators have been briefed and are standing by in the field to perform their required actic ns.

NOTE: All communications with the A 0 should be made using the plant communications systems md NOT with the Examiner.

Task Standards:

Complete the valve line-up and spray the Torus using the Fire System to RHR from the Control Roam.

Reauired Materials:

JPM-S4

JPRS -S4 Rev. 111 108 Page30 12 Handout 1 - OE 3107 OE Appendices, Appendix S (Rev. 25)

Simulator Set-Up:

Reset to any IC.

Insert malfunction mfRR-O1A at 1%. Delete when drywell pressure is 8 psig.

Stop both EDGs.

Trip all four SW Pumps on overcurrent.

Verify both Fire Pumps are running.

Place all RHR & RHRSW Pumps in PTL.

Reset to IC-853 Note to Simulator Instructor:

An instructor should be available to control plant parameters and silence alarms unrelated to the JPM.

JPM-S4

JPk -S4 Rev. 111308 Page 4 0.12 rovide Candidate with Initial Conditions/Cue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATKJNSAT Step 1: Obtain Procedure Standard: The operator obtains OE 3107, Appendix S, Rev 25.

Proceeds to Step 2, Primary Containment Spray Using Fire Water.

Interim Cue: When it is apparent that the operator is seeking to find OE 3 117, Examiner provides copy (Handout 1).

SATKJNSAT Step 2: (NOTE prior to Step 2.a) Substep 2.a mav be performed concurrently with the remainder of Step 2.

Standard: The operator reads the Note, and proceeds to Step 2.a SATKJNSAT Step 3: (Steps 2.d2.a.l) Isolate unnecessary Service Water loads as follows:

Close /Check Closed the following RBCCW HX Service Water Outlet valves:

SW-92A SW discharge from A HX SW-92B SW discharge from the B HX Standard: The operator contacts the A 0 and directs that SW-92 A and B be clos :d.

Interim Cue: Simulator Instructor as the A 0 reports SW-92A and SW-92B closed (this action is simulated).

NOTE: The operator may assign the A 0 to perform more than one procedure step during one communication.

JPM-S4

JPNi -S4 Rev. 111108 Page 5 o 12' qvaluation Performance Steps SATKJNSAT Step 4: (Step 2.a.2) CLOSE/check CLOSED the followinP to isolate Turbine r-Building loads:

SW-20 TURB BLDG INLET

-

OR SW-19A SW HEADER CROSS CONNECT and SW-19B SW HEADER CROSS CONNECT Standard: The operator places the SW-20 control switch on CRP 9-6 to CLOSE and observes Green light ON and Red light OFF.

OR The operator places the SW-19A control switch on CRP 9-6 to CLOSE, and observes Green light ON and Red light OFF.

and The operator places the SW-19B control switch on CRP 9-6 to CLOSE, and observes Green light ON and Red light OFF.

NOTE: The operator should perform only one or the other, however performance of both steps is allowed.

jAT/UNSAT Step 5: (Step 2.a.3) Consider isolating RRUs to provide increased flow to {he vessel bv closing the following valves:

SW-315A RRU-5 Inlet SW-316A RRU-6 Inlet SW-317A RRU-7 Inlet SW318A RRU-8 Inlet SW-307A RRU-9 Inlet SW-308A RRU-17A Inlet SW-309A RRU-17B Inlet Standard: The operator contacts the A 0 and directs that the RRUs be isolated.

~ ~ ~ ~~~~

Interim Cue: Simulator Instructor as the A 0 informs the operator that the RRUs are isolated.

Interim Cue: If the operator asks the CRS, Examiner inform the operator that the RRUs are isolate( .

JPM-S4

JPh! -S4 Rev. 111 108 Page 6 o 12

Vvaluation Performance Steps SATAJNSAT Step 6 (NOTE prior to Step 2.a.4) IF a LOCA signal is present, THEN the diesels can be shut down locallv using the MANUAL ENG STOP pushbutton with the REMOTE/AT ENGINE control switch in A7:

ENGINE.

Standard: The operator reads the Note and proceeds to Step 2.a.4.

SATKJNSAT Step 7 (Step 2.a.4) If a diesel generator is idling with the output breaker open, THEN consider shutting down the diesel to provide increased flow to the vessel.

Standard: The operator observes that both Diesel Generators are shutdown.

SATAJNSAT Step 8: (Steps 2.b/2.b.1/2.b.2) If the Fire Water pumps are running, THEN_

stop the Fire Water pumds) as follows:

-

Electric Fire Pump Open circuit breaker on Bus 9 Cubicle 7D Diesel Fire Pump - Place control switch to OFF.

Standard: The operator checks status of Fire Pumps by checking alarms on Pane 9-6, J-9, DIESEL FIRE PUMP RUNNING, and L-9, ELEC FIRE PUMP RUNNING, are LIT and determines that both Fire Water pumps are operating.

The operator contacts the A 0 and directs that both Fire Pumps be shutdown.

Interim Cue: When the operator calls the AO, Simulator Instructor place rfFP-01 to OFF and rfFP-02 to OFF.

THEN, call operator as A 0 and report that both Fire Pumps are OFF.

The operator checks status of Fire Pumps by checking alarms on Pane 9-6, J-9, DIESEL FIRE PUMP RUNNING, and L-9, ELEC FIRE PUMl RUNNING, are DARK and determines that both Fire Water pumps ar ;

shutdown.

JPM-S4

JPW -S4 Rev. 111 108 Page 7 o 12 Yvaluation Performance Steps SATAJNSAT *Step 9: (Step 2.c) OPEN SW-8, Fire Water to Service Water crosstie.

Standard: Operator directs A 0 to open SW-8.

Interim Cue: When the operator calls the AO, Simulator Instructor insert rf-SWR35.

THEN, call operator as A 0 and report that SW-8 is OPEN.

SATAJNSAT Step 10: (Steps 2.d2.d.l) IF RHR loop A is available, THEN Closekheck closed RHR 34A TORUS COOLING.

Standard: The operator checks shut RHR-34A by observing Green light ON and Red light OFF.

SATAJNSAT Step 11: (Steps 2.d.2/2.d.2.a) If a LPCI initiation signal is or was present THEN: In CRP 9-32, locate lOA-K45A-l, timing device for relay 10A-K45A.

Standard: The operator opens cabinet in back of CRP 9-32 and identifies timing device.

SATAJNSAT *Step 12: (Step 2.d.2.b) Rotate set screw in 10A-K45A-l fullv in the counter clockwise direction, to disable the time delav lopic for RHR-27A.

Standard: The operator obtains a screwdriver The operator uses screwdriver to turn set screw counter clockwise until it stops rotating.

SATAJNSAT *Step 13: (Step 2.d.2.c) On CRP 9-32, place switch 10A-S36A UPS FDR TRIP keylock switch to BLOCK.

Standard: The operator uses Key #13 and places the keylock switch 10AS36A tc BLOCK.

The operator observes MCB Annunciator 9-3/C-2, RHR-27A AUTO OPENLJPS FDR TRIP BLK. is LIT.

JPM-S4

JPh -S4 Rev. 11 1008 Page 8 cF 12 Yvaluation Performance Steps SATLJNSAT Step 14: (Steps 2.d.3) Closekheck closed one of the following:

RHR-25A INBD INJECTION RHR 27A. OUBD INJECTION Standard: The operator places the RHR-27A control switch in CLOSE, and observes Green light ON and Red light OFF, and determines that RH?:-

27A is CLOSED.

SATAJNSAT Step 15: (Steps 2.d.4) Go to Step 2.f.

Standard: The operator proceeds to Step 2.f.

SATAJNSAT Step 16: (Steps 2.f/2.f.l) Start available Fire Pumps bv performing the following:

Electric Fire Pump Close circuit Breaker on Bus 9 Cubicle 7D Press control START pushbutton Standard: The operator contacts the A 0 and directs that the Electric Fire Pump be started.

Interim Cue: When the operator calls the AO, Simulator Instructor place rfFP-01 to HAND.

THEN, call operator as A 0 and report that the Electric Fire Pump is Running.

SATAJNSAT Step 17: (Step 2.f.2) Diesel Fire Pump Place Control Switch to TEST Standard: The operator contacts the A 0 and directs that the Diesel Fire Pump be started.

Interim Cue: When the operator calls the AO, Simulator Instructor place rfFP-02 to HAND.

THEN, call operator as A 0 and report that the Diesel Fire Pump is Running.

The operator checks status of Fire Pumps by checking alarms on Panel 9-6, J-9, DIESEL FIRE PUMP RUNNING, and L-9, ELEC FIRE PUMP RUNNING, are LIT and determines that both Fire Water pumps are operating.

JPM-S4

JPM -S4 Rev. 111 108 Page 9 o 12 Yvaluation Performance Steps SATKJNSAT *Step 18: (Step 2.d2.g.l) OPEN RHR-89A RHRSW DISCHARGE as follovs Place RHR-89A TEST kevlock switch lOAS89A1 to TEST Standard: The operator uses the 89NB Test Switch Key and places the switch tc TEST.

The operator observes MCB Annunciator 9-3/M-2, RHR KEYLOCK SW TO MAN OVRD, is LIT.

SATKJNSAT *Step 19: (Step 2.g.2) Throttle open RHR-89A to 40% (white light is lit)

Standard: The operator places the control switch for RHR-89A to OPEN, and observes the Red light ON, and THEN the White Light is ON.

When the White light is ON, the operator allows the control switch fo!

RHR-89A to return to AUTO.

SATKJNSAT *Step 20: (Step 2.h) OPEN RHRSW/RHR emergency inter-tie kevlock valvts RHR-184 EMERGENCY FILL RHR-183 EMERGENCY FILL Standard: The operator uses Key #13 places the Key Lock switch for RHR-184 t )

OPEN and observes the Red light ON and Green light OFF.

The operator uses Key #13 places the Key Lock switch for RHR-183 t.)

OPEN and observes the Red light ON and Green light OFF.

SATAJNSAT Step 21: (CAUTION prior to Step 2.i) It may be necessarv to throttle spray flow using SW-8 to prevent overloading the Fire Water system pump(s).

Standard: The operator the Caution and proceeds to Step 2.i.

SATAJNSAT Step 22: (Step 2.U2.i.l) When Sprav is required THEN: Place RHR A/C LOGIC CTMT SPRAY VLV SHROUD LVL OVRD Kevlock Switch to MANUAL OVRD.

Standard: The operator uses Key #13 and places the RHR A/C LOGIC CTMT SPRAY VLV SHROUD LVL OVRD Keylock Switch to MANUAL OVRD.

JPM-S4

JPM -S4 Rev. 111 108 Page 10 o 12 Yvaluation Performance Steps SATAJNSAT *Step 23: (Step 2.i.2) Place RHR A/C LOGIC CTMT SPRAY VLV LPCI S iG BYPASS (pistol grip) to MAN.

Standard: The operator momentarily places the RHR A/C LOGIC CTMT SPRA Y VLV LPCI SIG BYPASS Pistol grip switch to MAN and releases the switch (spring returns to OFF).

SATAJNSAT Step 24: (NOTE prior to Step 2.i.3) Torus and Drvwell spravs may be operated concurrentlv.

Standard: The operator reads the Note and proceeds to Step 2.i.3.

SATAJNSAT *Step 25: (Step 2.i.3/2.i.3.a) For Torus Spray: OPEN RHR-39A TORUS SPRAY/CLG Standard: The operator places the control switch for RHR-39A to OPEN and observes Red light ON and Green light OFF.

SATAJNSAT *Step 26: (Step 2.i.3.b) OPEN RHR-38A TORUS SPRAY Standard: The operator places the control switch for RHR-38A to OPEN and observes Red light ON and Green light OFF.

The operator observes flow increases on FI- 10-139A and FI- 10-132A SATAJNSAT *Step 27: (Step 2.i.3.c) CLOSEkheck CLOSED RHR 89A, RHRSW DISCHARGE Standard: The operator places the control switch to CLOSE and observes the Gr :en light is ON and the Red and White light is OFF.

SATAJNSAT *Step 28: (Step 2.i.3.d) Place RHR 89A TEST kevlock Switch 10AS89A-1to AUTO and remove kev.

Standard: The operator uses Key #13 and places the RHR 89A TEST keylock switch to AUTO and removes the key from keylock switch.

TIME FINISH:

Terminating Cue: This JPM is complete.

JPM-S4

JPM -S4 Rev. 111 108 Page 11 o 12 Yvaluators Comments:

System: 226001 WA: A4.02 (3.U3.1)

JPM-S4

I EXAMINEE HANDOUT aitial Conditions:

0 Drywell pressure is high.

0 Torus Spray is required per EOP-3 and RHR and RHRSW Pumps are unavailable for use.

0 The Emergency Diesel Generators have been stopped.

0 No Service Water Pumps are available.

0 Fire Water Pumps are running.

Initiating Cues:

The CRS has directed you to line-up and spray the TORUS using the Fire System to RHR Loop A from the Control Room, IAW OE 3107, Appendix S , Step 2.

Auxiliary Operators have been briefed and are standing by in the field to perform their required actions.

NOTE: All communications with the A 0 should be made using the plant communications systems and NOT with the Examiner.

JPM -S5 Rev. 111 108 Page 1 )f 8 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Swap RBCCW & TBCCW Pumps Failure Mode: Complete Loss of RBCCW

Reference:

OP 2182, Reactor Building Closed Cooling Water, (Rev. 34)

RP 2 183, Turbine Building Closed Coolinrr Water. (Rev. 28)

ARS 21004, CRP 9-6 Alarm Response Sheets (Rev. 3)

EN-OP-115, Conduct of Operations, (Rev. 6)

Task Number: 2087170401 Task Performance: AO/RO/SRO __ RO/SRO Only X SE Only __

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

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation - Performance X Discuss Setting: Classroom - Simulator X Plant Performance Expected Completion Time: 8 minutes Evaluation Results:

Performance: PASS - FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedKertified Reviewer Date Approved by:

Operations Training Supervisor Date JPM-S5

JPIV -S5 Rev. 111 IO8 Page2 )f 8 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him ct 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 fo any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical stc p is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measurc .

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 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:

The plant is operating at power.

Scaffolding is being erected around RBCCW Pump A and TBCCW Pump A to support work scheduled during an upcoming Outage.

Initiating Cues:

The CRS has directed you to swap the RBCCW Pumps in accordance with Section D of OP 2182, Reactor Building Component Cooling Water.

THEN, swap of the TBCCW Pumps in accordance with Section H of RP 2183, Turbine Building Component Cooling Water.

Auxiliary Operators have been briefed and are standing by in the field to perform their required actictns.

Task Standards:

The operator starts RBCCW Pump B and places RBCCW Pump A in standby, starts the TBCCW Pump B and places TBCCW Pump A in standby, and then re-starts RBCCW Pump A on a failure of the RBCCW Pump B.

JPM-S5

JPM -S5 Rev. 111 108 Page 3 bf 8 1

Required Materials:

Handout 1 - OP 2182, Reactor Building Component Cooling Water (Rev. 34)

Handout 2 - RP 2183, Turbine Building Component Cooling Water (Rev. 28)

Simulator Setup:

Reset to any 100% power IC.

Ensure RBCCW Pump A and TBCCW Pump A are running.

Enter mfSW_23A, RBCCW A PMP AUTO START FAILURE.

Key 1 malfunction mfSW-OlB, RBCCW PUMP B TRIP

-

OR Reset to IC-854 Note to Simulator Instructor:

An instructor should be available to control plant parameters and silence alarms unrelated to the JPM.

JPM-S5

JPN -S5 Rev. 111 108 Page 4 If 8 Provide Candidate with Initial ConditionsKue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATKJNSAT Step 1: Obtain Procedure.

Standard: The operator obtains OP 2182, Rev 34.

Proceeds to Section D, Transfer of RBCCW Pumps.

Interim Cue: When it is apparent that the operator is seeking to find OP 2182, Examiner provides copy (Handout 1).

SATKJNSAT *Step 2: (Step 1) Start the standby Pump from CRP 9-6.

Standard: The operator places RBCCW Pump B control switch to START, and releases to AUTO, and then observes the Red light ON and the Green light OFF.

The operator observes increasing pressure on PI- 104-19.

SATKJNSAT *Step 3: (Step 2) Allow system pressure to stabilize, then secure the first pumr, and place its control switch in AUTO.

Standard: The operator observes PI- 104-19 stabilizes at -105 psig, and determixs that RBCCW pressure has stabilized.

The operator places RBCCW Pump A control switch in STOP, and releases to AUTO, and then observes the Green light ON and the Red light OFF.

The operator observes PI-104-19 stabilizes at =;77 psig, and determine ;

that RBCCW pressure has stabilized.

JPM-SS

JPM -S5 Rev. 11 1 108 Page 5 )f 8 I

Evaluation Performance Steps SATAJNSAT Step 4: Obtain Procedure.

Standard: The operator obtains RP 2183, Rev 28.

Proceeds to Section H, Transfer of TBCCW Pumps.

Interim Cue: When it is apparent that the operator is seeking to find RP 2183, Examiner provides copy (Handout 2).

SATAJNSAT *Step 5: (Step 1) On CRP 9-6, start the standbv TBCCW PUMP A(B)

P-58-1A(B).

Standard: The operator places TBCCW Pump B control switch to START, and releases to AUTO, and then observes the Red light ON and the Green light OFF.

The operator observes increasing pressure on PI- 104-52.

SATAJNSAT Step 6: (NOTE prior to Step 2) Annunciator 6-5-8, TBCCW HDR PRESS LO may come in while performing the next step.

Standard: The operator reads the Note and proceeds to Step 2.

JPM-S5

JPM -S5 Rev. 111 108 Page6 ,f 8 Evaluation Performance Steps SATAJNSAT *Step 7: (Step 2) Allow system pressure to stabilize, then secure the previouslv running pump and place its control switch in AUTO.

Standard: The operator observes PI-104-52 stabilizes at -1 10 psig, and determir es that TBCCW pressure has stabilized.

The operator places TBCCW Pump A control switch in STOP, and releases to AUTO, and then observes the Green light ON and the Red light OFF.

The operator observes PI-104-52 stabilizes at -65 psig, and determine s that TBCCW pressure has stabilized.

Simulator Instructor: When the operator stops TBCCW Pump A, operate Key 1, which will cause RBCCM' Pump B to trip, and RBCCW Pump A to fail to start.

The operator observes MCB Annunciators 9-6/L-7, RBCCW PUMP N B TRIP, and L-8,RBCCW HDR PRESS LO, as well as the Red light off and Greeflellow lights ON for RBCCW Pump B, and determines that the running RBCCW Pump B has tripped and that RBCCW Pump A has failed to start.

SATAJNSAT *Step 8: (EN-OP-115,Step 5.3 or ARS 21004 for L7 or LS, Operator Actio2

1) If an automatic control malfunctions, immediately place that control in manual.

OR Ensure that the standby RBCCW pump is running.

Standard: The operator places RBCCW Pump A control switch in START, and releases to AUTO, and then observes the Green and Amber lights ON and the Red light OFF.

The operator observes PI-104-19 stabilizes at -77 psig, and determines that RBCCW pressure has stabilized.

NOTE: MCB Annunciator 9-6/L-8 will clear when RBBCW Pump A is restarted.

~~

TIME FINISH:

'erminating Cue: This JPM is complete.

JPM-SS

JPM -S5 Rev. 111 108 Page7 )f 8 Evaluator Comments:

System: 400000 KIA: A2.01 (3.3/3.4)

JPM-S5

EXAMINEE HANDOUT initial Conditions:

0 The plant is operating at power.

0 Scaffolding is being erected around RBCCW Pump A and TBCCW Pump A to support work scheduled during an upcoming Outage.

Initiating Cues:

The CRS has directed you to swap the RBCCW Pumps in accordance with Section D of OP 2182, Reactor Building Component Cooling Water.

THEN, swap of the TBCCW Pumps in accordance with Section H of RP 2183, Turbine Building Component Cooling Water.

Auxiliary Operators have been briefed and are standing by in the field to perform their required actions.

JPM S6 Rev. 111')08 Page 1 I rf 7 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Initiate SLC to the Vessel Failure Mode: RWCU Fails to Isolate

Reference:

OP 21 14, Operation of the Standby Liquid Control System (Rev. 33)

Task Number: 2110050101 Task Performance: AO/RO/SRO - RO/SRO Only X 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 X Plant Performance Expected Completion Time: 5 minutes Evaluation Results:

Performance: PASS - FAIL, __ Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedCertified Reviewer Date Approved by:

Operations Training Superintendent Date JPM-S6

JPN -S6 Rev. 111 108 Page2 ) f 7 irections:

Discuss the information given on this page with the operator being evaluated. Allow time for him tc I 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 fo any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical stc p is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measurc .

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 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.

nitial Conditions:

The plant is experiencing an ATWS.

Initiating Cues:

The CRS has directed you to initiate SLC injection to the reactor vessel in accordance with Append; Y B, Injecting SLC Into the Reactor Vessel, of OP 21 14, Operation of the Standby Liquid Control System.

Task Standards:

Boron is injected to the reactor vessel in accordance with Appendix B of OP 21 14.

Required Materials:

Handout 1 - OP 21 14, Operation of the Standby Liquid Control System (Rev. 33)

JPM-S6

JPk -S6 Rev. 111308 Page3 i f 7 imulator Setup:

Reset to any 100% power IC.

Set up the simulator for ATWS conditions:

Any malfunctions to cause an ATWS (e.g. mfRP-OlA, Failure to Auto Scram, mfRP-OlB, Failure o Manual Scram, mfRP-OlC, Failure of ARI/RPT)

Insert mfRP-09A (Group V failure to isolate)

Insert mfRP-09B (Group V failure to isolate)

Insert mfNM-OSA, (APRM A Failure) 100% Severity Insert mfNM-O5B (APRM B Failure) 100% Severity Reset to IC-855

-

AND Activate Scenario 2009 NRC JPM S6 Fail both SL Squib Valves to fire in SLC System.

Insert mfSL-O2A, SL Squib Valve A Fails to Fire Insert mfSLw02B,SL Squib Valve B Fails to Fire Will need to remove one of the two malfunctions during the performance of the JPM.

JPM-S6

JPNI -S6 Rev. 111 IO8 Page4 i f 7

'rovide Candidate with Initial ConditionsKue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATPUNSAT Step 1: Obtain Procedure.

Standard: The operator obtains OP 21 14, Rev 33.

Proceeds to Appendix B, Injecting SLC Into the Reactor Vessel.

Interim Cue: When it is apparent that the operator is seeking to find OP 21 14, Examiner provides copy (Handout 1).

SATAJNSAT Step 2: (NOTE prior to Step 1)Unless specified otherwise, all controls and indications are on CRP 9-5.

Standard: The operator reads the Note, and proceeds to Step 1.

SATAJNSAT *Step 3: (Step 1) Unlock SLC Switch by positioning the key to the two o'clwk position.

Standard: The operator places Key in the SLC Switch to the two o'clock (right hand) position.

SATAJNSAT *Step 4: (Step 2) Turn SLC switch to SYS 1or SYS 2.

Standard: The operator places the SLC Switch to the SYS 1 or SYS 2 position.

The operator observes the yellow light for the SLC System selected is OFF.

SATAJNSAT Step 5: (Steps 3/3.a) Verify the following events occur: SLC PUMP A(B)

P-45-1A(B) starts.

Standard: The operator observes that SLC Pump A is running by observing the Red light ON and Green light OFF.

JPM-S6

JPN -S6 Rev. 111 108 Page 5 )f7

'valuation Performance Steps SAT/UNSd4T Step 6: (Step 3.b) SLC discharge pressure increases as indicated on PI-11-65.

Standard: The operator observes rising pressure indicated on PI 11-65, stabilizir g at -1500 psig.

SATKJNSAT *Step 7: (Step 3.c) On CRP 9-4, RWCU system isolation valves automaticai&

close:

0 CU-15 (Outlet Isolation) 0 CU-18 (Inlet Isolation) 0 CU-68 (Return Isolation)

Standard: The operator observes valve position for CU valves and recognizes that the RWCU System did NOT isolate.

The operator places the CU-15 control switch to CLOSE, and releases to NORM, and observes Green light ON and red light OFF.

The operator places the CU-18 control switch to CLOSE, and releases to NORM, and observes Green light ON and red light OFF.

The operator places the CU-68 control switch to CLOSE, and releases to NORM, and observes Green light ON and red light OFF.

NOTE: To successfully complete the Critical nature of this step either CU-15 or CU-18 must be clo: ed.

NOTE: The operator may elect to take SLC switch to the other position (per step 4 of Appendix B) before manually closing the RWCU valves. If so, continue on with JPM Steps 8-10, and the:i return to Step 7.

SATKJNSAT Step 8: (NOTE prior to Step 3.d) SLC discharge pressure cycling at relief valve setpoint (1400-1490 psig) may indicate failure of sauib valveto

-

fire.

Standard: The operator reads the Note and proceeds to Step 3.d.

JPM-S6

JPM S 6 Rev. 111 108 Page 6 sf 7 1

Jvaluation Performance Steps SATAJNSAT Step 9: (Step 3.d) Squib valve SLC-l4A(B) fires, as indicated bv:

0 Red flow indicator light on (flow greater than 30 gpm).

0 SLC tank level decreases as indicated on LI-11-66.

Standard: The operator observes the Red light OFF.

SATAJNSAT *Step 10: (Step 4) If the above actions did not result in SLC iniection, then turn the SLC switch to the other position (SYS 2 or SYS l),and repeat verifications of Step 3 Standard: The operator places the SLC Switch to the SYS 1 or SYS 2 position.

The operator observes Red Flow Indicator light is ON.

The operator observes rising pressure indicated on PI 11-65, stabilizins at ;= Reactor Pressure.

The operator observes SLC Tank Level indicator (LI 11-66) and that level indication is lowering.

TIME FINISH:

Terminating Cue: This JPM is complete.

Evaluator Comments:

System: 21 1000 K/A: A4.02 4.214.2 JPM-S6

EXAMINEE HANDOUT iitial Conditions:

The plant is experiencing an ATWS.

Initiating Cues:

The CRS has directed you to initiate SLC injection to the reactor vessel in accordance with Appendix B, Injecting SLC Into the Reactor Vessel, of OP 21 14, Operation of the Standby Liquid Control System.

JPM-S7 Rev. 111008 Page 1 of 7 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Transfer Station Load from the Auxiliarv Transformer to the Startup Transformer Failure Mode: NA

Reference:

OP 2142.4 KV Electrical Svstem (Rev. 50)

Task Number: 2620010101 Task Performance: AO/RO/SRO - RO/SRO SRO Only -

Sequence Critical: Yes __ No 3 Time Critical: Yes - No 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: 5 minutes Evaluation Results:

Performance: PASS - FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicenseaCertified Reviewer Date Approved by:

Operations Training Superintendent Date JPM-S7

JPM-S7 Rev. 111008 Page 2 of 7 Xrections:

Discuss the information given on this page with the operator being evaluated. Allow time for him tc 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 foi any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical stt p 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.

nitial Conditions:

A normal plant shutdown is in progress in accordance OP 0105, Reactor Operations, to support an upcoming Refueling Outage.

Initiating Cues:

The CRS directs you to transfer station load from the auxiliary transformer to the Startup Transformc*r per Section D of OP 2142,4 KV Electrical System (Page 2 1 of 30).

Task Standards:

Station loads are transferred from the Auxiliary to Startup Transformer.

Required Materials:

Handout 1 - OP 2142,4 KV Electrical System, (Rev. 50)

Simulator Set-Up:

Reset to IC-856 JPM-S7

JPM-S7 Rev. 111008 Page 3 of 7 Provide Candidate with Initial Conditions/Cue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATAJNSAT Step 1: Obtain Procedure Standard: The operator obtains OP 2142, Rev 50.

Proceeds to Section D, Transfer of Station Load from Auxiliary Transformer to Startup Transformer.

Interim Cue: When it is apparent that the operator is seeking to find OP 2142, Examiner provides copy (Handout 1).

NOTE: The operator may believe that Appendix D, rather than Section D, of OP 2142 is the appropriate proceed section to use. Appendix D would be used in an Emergency, rather than in a normal situation, and is kept in a side pocket on the MCB so that it is readily available in an emergency. If the operator uses Appendix D rather than Section D of OP 2142, the same steps will be accomplished however, the JPM Script will NOT flow precisely with the actions on Appendix D. IF the operator attempts to use Appendix D, rather than Section D of OP 2142, the Examiner should direct the operator to use Section D of the procedure rather than Appendix D.

SATAJNSAT Step 2: (Step 1) Verify that startup transformers are powered from 115KV_

yard.

Standard: The operator observes that power indicated on 115 KV meter on CRP 9-8.

The operator checks 115 KV line-up to the S/Up transformers.

SATKJNSAT Step 3: (Step 1.a) If auto transformer is not supplying the 115 KV yard..,*,

Standard: The operator observes that the Auto Transformer is supplying the 115 KV Yard, and proceeds to Note prior to Step 2.

SATAJNSAT Step 4: (NOTE prior to Step 2) Steps 2 through 7 only apply if Bus 1 is available and is to be place in service.

Standard: The operator reads the Note, and proceeds to Step 2.

JPM-S7

JPM-S7 Rev. 11 1008 Page 4 of 7

valuation Performance Steps SATAJNSAT *Step 5: (Step 2) Insert sync check handle in BKR 13 socket and turn sync switch on.

Standard: The operator inserts the 4KV sync check handle into breaker 13 switc:k on CRP 9-8 and turns sync check switch to ON.

SATAJNSAT Step 6: (Step 3) Verify bus 1 in phase with startup transformer

{synchroscope at 12 o'clock position).

Standard: The operator observes that the synchroscope is at 12:OO position, White lights OUT, Red lights ON.

SATKJNSAT Standard: The operator reads the Caution, and proceeds to Step 4.

SATKJNSAT *Step 8: (Step 4) Close BKR 13.

Standard: The operator places the switch for breaker 13 on CRP 9-8 to CLOSE iind then releases.

The operator observes the Red light ON above breaker control switch on CRP 9-8.

NOTE: The operator may make a plant announcement concerning the transfer of electrical lmds to the Startup Transformer (Not Critical).

SATAJNSAT Step 9: (Step 5 ) Check that BKR 12 trips open when BKR 13 switch is re1eased Standard: The operator verifies Breaker 12 open by observing Green and Amber lights ON above breaker 12 control switch on CRP 9-8.

SATKJNSAT Step 10: (Step 6) Reset BKR 12 amber light.

Standard: The operator places the switch for breaker 12 on CRP 9-8 to TRIP an(

then releases.

The operator observes the Amber light OFF above breaker 12 switch t m CRP 9-8.

JPM-S7

JPM-S7 Rev. 111008 Page 5 of 7 Evaluation Performance Steps SAT/UNSAT *Step 11: (Step 7)Turn sync check handle to OFF and remove it from the socket.

Standard: The operator turns the Sync check handle at breaker 13 on CRP 9-8 positioned to OFF, and removes the handle from the breaker 13 socke .

SATAJNSAT Step 12: (NOTE prior to Step 8) Steps 8 through 13 only apply if Bus 2 is available and is to be place in service.

Standard: The operator reads the Note and proceeds to Step 8.

SATKJNSAT *Step 13: (Step 8) Insert sync check handle in BKR 23 socket and turn sync switch on.

Standard: The operator inserts the 4KV sync check handle into breaker 23 switcli on CRP 9-8 and turns sync check switch to ON.

SATAJNSAT Step 14: (Step 9) Verify bus 2 in phase with startup transformer (synchroscope at 12 o'clock position).

Standard: The operator observes that the synchroscope is at 12:OO position, Whiie lights OUT, Red lights ON.

SATAJNSAT Step 15: (CAUTION prior to Step 10) If they are not In Phase, do not transfer.

Standard: The operator reads the Caution, and proceeds to Step 10.

SATAJNSAT *Step 16: (Step 10) Close BKR 23.

Standard: The operator places the switch for breaker 23 on CRP 9-8 to CLOSE :%nd then releases.

The operator observes the Red light ON above breaker control switch In CRP 9-8.

SATAJNSAT Step 17: (Step 11) Check that BKR 22 trips open when BKR 23 switch is released.

Standard: The operator verifies Breaker 22 open by observing Green and Amber lights ON above breaker 22 control switch on CRP 9-8.

JPM-S7

JPM-S7 Rev. 11 1008 Page 6 of 7 Evaluation Performance Steps SATAJNSAT Step 18: (Step 12) Reset BKR No 22 amber light.

Standard: The operator places the switch for breaker 22 on CRP 9-8 to TRIP anc then releases.

The operator observes the Amber light OFF above breaker 22 switch c n CRP 9-8.

SATAJNSAT Step 19: (Step 13h3.a) Turn sync check handle OFF and remove from sock et, Place sync check handle on CRP 9-8.

Standard: The operator turns the Sync check handle at breaker 23 on CRP 9-8 positioned to OFF, and removes the handle from the breaker 23 socket The operator places the synch handle on CRP 9-8 TIME FINISH:

Terminating Cue: This JPM is complete.

Evaluators Comments:

System: 262001 WA: A4.04 (3.6/3.7)

JPM-S7

EXAMINEE HANDOUT Initial Conditions:

A normal plant shutdown is in progress in accordance OP 0105, Reactor Operations, to support an upcoming Refueling Outage.

Initiating Cues:

The CRS directs you to transfer station load from the auxiliary transformer to the Startup Transform :r per Section D of OP 2142,4 KV Electrical System (Page 21 of 30).

JPM S 8 Rev. 111i108 Page 1 uf 7 I

VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Rx Startup to Criticality Failure Mode: Short period during,

- startup

Reference:

OP 0105, Reactor Operations, (Rev. 86)

Task Number: 2987240201 Task Performance: AO/RO/SRO - RO/SRO Only X SE Only -

ence Critical: Yes - No 2 Time Critical: Yes - No 2 Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation - Performance X Discuss -

Setting: Classroom _ . Simulator X Plant -

Performance Expected Completion Time: 8 minutes Evaluation Results:

Performance: PASS __ FAIL __ Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedKertified Reviewer Date Approved by:

Operations Training Superintendent Date JPM-S8

JPM -S8 Rev. 111 108 Page2 If7 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him tl 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 fo any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical st1-p is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measurl I

.

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:

0 A plant startup is in progress in accordance with Phase 1A of OP 0105, Reactor Operations.

0 The procedure is complete through step A.26 (Page 21 of 152).

0 The control rods have been withdrawn in the specified sequence of OP 2404.

0 There have been two (2) doublings, and these are recorded on VYOPF 0105.03.

0 The next control rod to be withdrawn is Rod 10-39.

Initiating Cues:

The CRS directs you to continue the startup and take the reactor critical starting with Phase 1A Step 27 of OP 0105, Reactor Operations (Page 21 of 152).

Task Standards:

While pulling control rods to take the reactor critical, a high worth rod takes reactor period to shortc r than 30 seconds. The operator takes action to take the reactor subcritical per OP 0105.

JPM-S8

JPIV -SS Rev. 111 )OS Page3 I f 7 Reauired Materials:

Handout 1 - VYOPF 0105.03 with doubling count rates filled in as follows:

Reactor Startun: I X I In-Seauence: I 1 SRM C 12 I SRM B 13 SRM D Time 0800 Initial in it it1 Lccl -1 Handout 2 - VYOPF 2404.01 (Page 1) filled in as follows:

I Group 1 Array I InsertLimit I Withdraw I Rods 1 Out 1 In I

_ _ _ ~~~~~~~~

Handout 3 - OP 0105, Reactor Operations, (Rev 86.)

_timulatorSetup:

JPM-SS

JPh -S8 Rev. 111008 Page 4 i3f 7

1. Reset to IC 857 (just before critical).

2. Set up mfNM-OlD, SRM D failing high at 100% with ramp of 100 seconds on Key 1.

3. Set up mfNM-OlD, SRM D failing low at 41% with ramp of 5 seconds on Key 2.

4. Ensure:

C120 is on the CRP 9-3 Digital Display.

C023 is on the CRP 9-4 Digital Display.

C121 is on the CRP 9-7 Digital Display

5. Initialize the Rod Worth Minimizer JPM-S8

JPlL -S8 Rev. 11I008 Page 5 of 7 Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) along with Handouts 1 and 2 Evaluation Performance Steps TIME START:

SATAJNSAT *Step 1: (Step 27) Continue to withdraw control rods in such a manner ab to avoid having a sustained period shorter than 30 seconds (desired 100 to 200 seconds).

Standard: The operator places the Rod Select Power Switch to ON.

The operator depresses the 10-39 Select Pushbutton, and observes the White Pushbutton light is ON, and the White Rod Out Permit light ON above the Rod Movement control switch.

The operator places the Notch Out Ovrd Emergency In Switch in NOTCH OVERIDE and observes the yellow light ON.

The operator simultaneously places the Rod Movement Control Switch to NOTCH 01JT and observes the Red Rod Out light ON.

The operator observes the SRM level indications (7-43A through D) 1or increasing count level.

The operator observes the SRM period indications (7-44A through D>for changing Reactor period.

The operator observes SRM for count rate increasing and reactor period.

Examiner NOTE: Just prior to critically the short period alarm will come in. (about 24 Notches on control rod)

Note: Simulator Instructor upon operator placing rod 10-39 20 notches, INSERT KEY 1.

JPM-S8

JPM -S8 Rev. 111 108 Page6 ) f 7 CATNNSAT *Step 2: (Step 2W28.a) If the sustained period becomes shorter than 30 seconds: Use the EMERGENCY IN switch to turn the period.

Standard: The operator observes MCB Annunciator 9-54'-5, SRM PERIOD SHORT.

The operator observes that SRM Period indicator 7-44D indicates a short period, and that the yellow Period light is ON.

The operator observes that SRM Level indicator 7-43D is increasing.

The operator places the Notch Out Ovrd Emergency In Switch the EMERGENCY IN position to reduce the reactor period.

Note: Upon observing the operator using the Notch Out Ovrd Emergency In Switch the EMERGENCY IN position after 2 notches, INSERT KEY 2.

SATAJNSAT *Step 3: (Step 28.b) Insert control rods until the reactor is subcritical.

Standard: The operator continues to insert control rods with EMERGENCY IN switch until the reactor is subcritical as indicated by infinite period on SRM Period indication 7-44A through D, and stable SRM level indications (7-43A through D).

SATAJNSAT Step 4: (Step 28.c) Notify the Shift Manaeer, Operations Manager, and Superintendent Reactor Engineering.

Standard: The operator notifies the CRS of the situations and actions taken.

Critical Step TIME FINISH:

Terminating Cue: This JPM is complete.

Evaluator Comments:

Cystem: 215004 WA: A4.01 (3.9/3.8)

JPM-S8

EXAMINEE HANDOUT

,nitial Conditions:

A plant startup is in progress in accordance with Phase 1A of OP 0105, Reactor Operations.

0 The procedure is complete through step A.26 (Page 21 of 152).

0 The control rods have been withdrawn in the specified sequence of OP 2404.

0 There have been two (2) doublings, and these are recorded on VYOPF 0105.03.

0 The next control rod to be withdrawn is Rod 10-39.

Initiating Cues:

The CRS directs you to continue the startup and take the reactor critical starting with Phase 1A Step 27 of OP 0105, Reactor Operations (Page 21 of 152).

JPIV -P1 Rev. 111708 Page 1 If 8 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Place Charger BC-1-1B in Service Failure Mode: -N/A

Reference:

OP 2146, Operation of Station and Alternate Shutdown System 125-Volt Bataery Chargers, (Rev. 21)

Task Number: 2630070104 Task Performance: AO/RO/SRO X RO/SRO Only - SE Only -

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

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation X Performance -Discuss Setting: Classroom - Simulator - Plant J performance Expected Completion Time: 10 minutes Evaluation Results:

Performance: PASS - FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedlCertified Reviewer Date lpproved by:

Operations Training Superintendent Date JPM-P1

JPIV -P1 Rev. 111708 Page2 If 8

'%rections:

Discuss the information given on this page with the operator being evaluated. Allow time for him ti 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 fo any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical stc p is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measurc .

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

Read to the person beinp 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.

'nitial Conditions:

There is currently no battery charger supplying power to DC Bus 2. Electrical Maintenance personnzl are available for support if needed.

Initiating Cues:

The CRS has directed you to place the BC-1-1B Battery Charger in service in accordance with Sectim B of OP 2146.

Task Standards:

Battery Charger BC-1-1B is placed in service.

Rewired Materials:

Handout 1 - OP 2146, Operation of Station and Alternate Shutdown System 125-Volt Battery Chargers (Rev. 21)

Simulator Setup:

N/A JPM-P1

JPM -P1 Rev. 111708 Page3 If 8

'rovide Candidate with Initial ConditionsKue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATAJNSAT Step 1: Obtain Procedure.

Standard: The operator obtains OP 2146, Rev 21.

Proceeds to Section B, Placing Charger BC-1-1B (BC-1-ID) in Service.

Interim Cue: When it is apparent that the operator is seeking to find OP 2146, Examiner provides copy (Handout 1).

SATAJNSAT Step 2: (NOTES prior to Step 1)This procedure section assumes that no chargers are in service. Use Section D for transfer.

These instructions are for BC-1-1B. Use the description in parentheses for BC-1-1D.

Standard: The operator reads the Notes and proceeds to the Caution prior to Ster 1.

SATAJNSAT Step 3: (CAUTION prior to Step 1)Tripping and damage of DC components may occur if the batterv is not tied to its respective bus, Standard: The operator reads the Caution and proceeds to Step 1.

SATAJNSAT +Step 4: (Step 1)Closekheck closed DC-2 125 VDC MAIN BREAKER.

Standard: The operator verifies that the DC-2 125 VDC Main Breaker is shut by observing the breaker position indicating flag in the CLOSED (Red) condition.

Interim Cue: After checking, Examiner inform Operator that the breaker position indicating flag is Red.

JPM-P 1

JPM -P1 Rev. 111708 Page 4 jf 8

'valuation Performance Steps SATAJNSAT +Step 5: (Steps 2.a-d) At MAIN STATION BATTERY CHARGER BC-l-jB

{BC-l-lD), perform the followinp:

Opedcheck open the AC BREAKER (Input).

Openkheck open the DC BREAKER (Output).

Check or set the EQUALIZE timer to minimum.

Adjust the FLOAT Adjustment Pot counterclockwise 10 Turns.

Standard: The operator verifies that the BC-1-1B AC Breaker is OPEN by observing the breaker switch in the OFF (Down) position.

Interim Cue: After checking, Examiner inform Operator that breaker switch is in the Down position.

Standard: The operator verifies that the BC-1-1B DC Breaker is OPEN by observing the breaker switch in the OFF (Down) position.

Interim Cue: After checking, Examiner inform Operator that breaker switch is in the Down position.

Standard: The operator observes that the BC-1-1B Equalize timer is set to zero ( I).

Interim Cue: After checking, Examiner inform Operator that the timer is set to zero (0).

Standard: Using a screwdriver (simulated) the operator turns the FLOAT adjustment pot 10 turns in the counter-clockwise direction.

Interim Cue: After checking, Examiner inform Operator that the FLOAT Adjustment Pot has been turned 10 turns in the Counter-Clockwise direction.

SAT/UNSAT +*Step 6: (Step 3) Close/check closed Ckt. 6, BATTERY CHARGER BC-l-IE on DC-2 (Ckt. 5, BATTERY CHARGER BC-1-1D on DC-2).

Standard: The operator closeskhecks closed the Ckt. 6 breaker on DC-2 by positioning the breaker handle to the ON (Left) posit ion.

~

lnterim Cue: After checking, Examiner inform Operator that breaker handle is in the Left position.

JPM-P1

JPN -P1 Rev. 111708 Page 5 ,f 8 Evaluation Performance Steps SATKJNSAT +Step 7: (Step 4) Ensure DC-1 TIE TO DC-2 and DC-2 TIE TO DC-1 breakers are both open.

Standard: The operator verifies that the DC-1 TIE TO DC-2 Breaker is OPEN b I observing the DC-1 Tie DC-2 breaker position indicating flag on DC- 1 is in the OPEN (Green) condition.

Interim Cue: After checking, Examiner inform Operator that the breaker position indicating flag is Green.

Standard: The operator verifies that the DC-2 TIE TO DC-1 Breaker is OPEN by observing the DC-2 Tie DC-1 breaker position indicating flag on DC- 2 is in the OPEN (Green) condition.

Interim Cue: After checking, Examiner inform Operator that the breaker position indicating flag is Green.

SATNNSAT +*Step 8: (Step 5 ) At MCC-9A (9Bh close/check closed the 125 VDC BATTERY CHARGER BC-1-1B (BC-1-1D) breaker.

Standard: The operator closeskhecks closed the 125VDC Battery Charger break x-by observing the breaker handle in the ON (UP) position.

Interim Cue: After checking, Examiner inform Operator that the breaker handle in the UP position SATKJNSAT +*Step 9: (Step 6/6.a) At MAIN STATION BATTERY CHARGER BC-l-lIl (BC-1-1D):

Close the DC output breaker.

Standard: The operator closes the DC output breaker by positioning the breaker handle to the ON (Up) position.

Interim Cue: After action, Examiner inform Operator that the breaker handle in the UP position.

JPM-P1

JPN -P1 Rev. 1I I 708 Page6 I f 8

valuation Performance Steps SATKJNSAT +*Step 10: (Step 6/6,b) At MAIN STATION BATTERY CHARGER BC-1-1:ii

{BC-1-1D):

Close the AC input breaker.

Standard: The operator closes the AC input breaker by positioning the breaker handle to the ON (up) position.

~ ~~ ~~ ~

Interim Cue: After action, Examiner inform Operator that the breaker handle in the UP position.

SATKJNSAT +*Step 11: (Step 6.c) Increase voltage bv turning the Float Ad-iust Pot clockwise slowlv enough to limit the voltage to 132 V or until the charger current is about 100 amps.

Standard: The operator rotates the Float Adjust Pot clockwise slowly enough to limit the DC voltage to 132 V or until charger DC current is about lo(

amps iterim Cue: When Operator indicates that he is rotating the potentiometer slowly clockwise, Examiner inform Operator that voltage is approximately 132 volts and that current is approaching 100 amps.

SATAJNSAT Step 12: (Step 7)Request assistance from Electrical Maintenance for final calibration of the charger Standard: The operator requests that Electrical Maintenance perform final calibration of the battery charger.

Interim Cue: When Electrical Maintenance is contacted, Examiner inform Operator that Electriciai 1s are on their way to perform final calibration.

~~~ ~~ ~ ~

Note: (+) JPM Steps 4 through 11 are Sequence Critical TIME FINISH:

Terminating Cue: This JPM is completed.

JPM-P1

JPM -P1 Rev. 111708 Page7 )f 8

-,valuatorComments:

System: 263000 WA's: A3.01 (3.2/3.3)

JPM-P 1

EXAMINEE HANDOUT Initial Conditions:

There is currently no battery charger supplying power to DC Bus 2. Electrical Maintenance personrel are available for support if needed.

Initiating Cues:

The CRS has directed you to place the BC-1-1B Battery Charger in service in accordance with Sectron B of OP 2146.

NOTE: All actions must be simulated. At NO time shall any plant equipment be operated.

JPM P2 Rev. 111 708 Pagelo: 11 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Boron Iniection from the SLC Tank Using the CRD System Failure Mode: NIA

Reference:

OE 3 107, Appendix K, Boron Iniection Using CRD System from the SLC Ta -

k (Rev. 25).

Task Number: 2007600501 Task Performance: AOLROISRO X 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 X Performance __ Discuss Setting: Classroom - Simulator - Plant X Perf'ormance Expected Completion Time: 20 minutes Evaluation Results:

Performance: PASS __ FAIL __ Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO Licensedcertified Reviewer Date Approved by:

Superintendent Operations Training Date JPM-P2

JPM -P2 Rev. 111708 Page20 11 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him tc I 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 fo any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical stc p is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measurt .

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 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:

0 An ATWS has occurred.

0 The EOPs have been entered.

0 The SLC Tank is available.

0 CRD Pump B is in service and CRD Pump A is in Standby.

Initiatinp Cues:

The CRS directs you to line up the CRD System for boron injection from the SLC Tank in accordance with OE 3107, Appendix K, to CRD Pump B. Inform the Control Room when the CRD Pumps can be started.

Task Standards:

The SLC tank and CRD System are lined up to inject into the reactor vessel using CRD Pump B in accordance with Procedure OE 3 107, Appendix K Reauired Materials:

Handout 1 - OE 3107, Appendix K, (Rev. 25)

Simulator Setup:

NIA JPM-P2

JPM P2 Rev. 11 I 08 Page 3 ol 11 Provide Candidate with Initial ConditionsKue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATKJNSAT Step 1: Obtain Procedure.

Standard: The operator obtains OE 3107, Appendix K, Rev 25.

Proceeds to Procedure Step 1.

Interim Cue: When it is apparent that the operator is seeking to find OE 3107, Appendix K, Examiner provides copy (Handout 1).

SATKJNSAT Step 2: Acquire Necessary Tools and Equipment Standard: Tools, fittings, and hose acquired from EOP Toolbox located in the Reactor Building (3 18 elevation)

Interim Cue: Inform Operator that necessary tools, fittings, and hose have been acquired.

SATAJNSAT *Step 3: (Steps 1.a-d) Establish a flowpath from the SLC tank to the CRD pumps using the followinP hose route: From the SLC tank on the 318 elevation down the pipe chase on West wall labeled EOP SL<,

Pipe Chase, Down the pipe chase on the 280 elevation labeled EOe SLC Pipe Chase, Down the HPCI hatch on the 252 elevation to th-g CRD pumps.

Standard: The operator locates the hoses to be used in the SLC Hallway.

The operator routes the hose from the SLC Tanks, down the EOP SLC pipe chase on RB 318 elevation west, down through the EOP pipe ch,s e on RB 303 and 280 elevations, and down through the equipment hat(.h on the 252 elevation to the CRD Pumps.

Interim Cue: As each step of hose routing is simulated, Examiner inform Operator that hose has becn routed and connected.

JPM-P2

I JPM P2 Rev. 111 708 Page 4 0: 11 valuation Performance Steps SATAJNSAT *Step 4: (Step 2/2.a) At the SLC tank: CLOSEkonfirm CLOSED SLC-23 Standbv Liquid Control Tank Drain.

Standard: The operator verifies that SLC-23 closed by rotating the valve operati "ig handle in the clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the valve operating doc s not move.

SATAJNSAT *Step 5: (Step 2.b) Remove Pipe Cap from the 1?hinch tank drain.

Standard: The operator removes the pipe cap from the 1 1/2-inch tank drain.

Interim Cue: After the simulated action, Examiner inform Operator that the pipe cap is OFF.

SATAJNSAT *Step 6: (Step 2.c) Connect hose adaptor to the tank drain.

Standard: The operator connects a hose adaptor to the drain tank.

Interim Cue: After the simulated action, Examiner inform Operator that the hose adaptor is installcd.

SATAJNSAT *Step 7: (Step 2.d) Connect Hose Standard: The operator connects the CRD Pump suction hose to the SLC Tank drain line.

Interim Cue: After the simulated action, Examiner inform Operator that the hose is connected.

SATAJNSAT Step 8: (Step 2.e) Place the SLC tank heater control switch to ONOocateda side of large .iunction box, Rack 25-19, Rx Bldg. elevation 318').

Standard: The operator rotates the SLC tank heater control switch to the ON position.

Interim Cue: After the simulated action, Examiner inform Operator that the switch is in the ON position, and the heaters are energized.

JPM-P2

JPM -P2 Rev. 111 708 Page50 11 Evaluation Performance Steps SATAJNSAT *Step 9: (Steps 3/3.a) In the CRD pump room: CLOSEkonfirm CLOSED :&

following valves:

DW-65 CST Header Demin Water Isol DW-66 CST Header Demin Water Isol Standard: The operator checks DW-65 Closed by rotating the handwheel in the clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel does not move.

Standard: The operator checks DW-66 Closed by rotating the handwheel in the clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel does not move.

SATKJNSAT *Step 10: (Step 3.b) Remove top flanpe from check valve DW-67 (located between DW-66 and DW-65) and replace with mechanical bypass flange with hose connection.

Standard: The operator removes the top flange from check valve DW-67, and attaches the hose connection flange.

Interim Cue: After the simulated action, Examiner inform the operator that the flange is removed. md the hose connection flange is installed.

SAT/UNSAT *Step 11: (Step 3.c) Connect hose to bypass flanpe Standard: The operator connects the SLC suction hose to the mechanical bypass flange.

Interim Cue: After the simulated action, Examiner inform the operator that the SLC suction hose ir connected to the mechanical bypass flange.

JPM-P2

JPM P2 Rev. 11 L"O8 Page 6 ol 11 Evaluation Performance Steps SATAJNSAT *Step 12: (Step 3.d) Request the Control Room to secure both CRD pumps, and verifv neither are running prior to continuing with this procedure.

Standard: The operator contacts the Control Room and requests both CRD Pumr s be secured.

Interim Cue: When requested, Examiner inform Operator that both CRD Pumps are secured.

Standard: The operator enters the CRD Pump Room and determines that both pumps are secured.

Interim Cue: After action, Examiner inform Operator neither CRD Pump is running.

SATAJNSAT *Step 13: (Step 3.e) CLOSE CST-63C, CRD Svs CST Suction Isol.

Standard: The operator closes CST-63C by rotating handwheel in the clockwise direction.

iterim Cue: After the simulated action, Examiner inform the operator that the handwheel rotated clockwise, and has now stopped.

SATAJNSAT *Step 14: (Step 3.0 OPEN DW-66, CST Header Demin Water Isol.

Standard: The operator opens DW-66 by rotating handwheel in the counter-clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel rotated counter-clockwise, and has now stopped.

SATAJNSAT *Step 15: (Step 3.g) OPEN CRD-158A (B), CRD Pump A (B) Suction Filter Bvpass.

Standard: The operator opens DW- 158B by rotating handwheel in the counter-clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel rotated counter-clockwise, and has now stopped.

JPM-P2

JPM P2 Rev. 111 708 Page 7 0: 11 Evaluation Performance Steps SAT/UNSAT *Step 16: (Step 3.h) CLOSE CRD-35A (B), CRD Pump A (B) Suction Filter

-

Inlet.

Standard: The operator closes CRD-35A by rotating handwheel in the clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel rotated clockwise, and has now stopped.

SAT/UNSAT *Step 17: (Step 3.i) CLOSE CRD-37A (B), CRD Pump A (B) Main Flow Stop Check, to maximize CRD flow to the reactor vessel.

Standard: The operator closes CRD-37A by rotating handwheel in the clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel rotated clockwise, and has now stopped.

SATKJNSAT *Step 18: (Step 3.i) CLOSEkonfirm CLOSED CRD-34A (B), CRD Pump A (B) min flow stop check, to maximize CRD flow to reactor vessel.

Standard: The operator closes CRD-34A by rotating handwheel in the clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel rotated clockwise, and has now stopped.

SATAJNSAT *Step 19: (Step 4) At the SLC tank, OPEN SLC-23, Standby Liquid Contro!

Tank Drain.

Standard: The operator opens SLC-23 by rotating the valve operating handle in t le counter-clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the valve operating han Jle rotated counter-clockwise, and has now stopped.

JPM-P2

JPM P2 Rev. 11 I' '08 Page 8 oi 11 Evaluation Performance Steps SATAJNSAT *Step 20: (Steps 5E.a-b) In the CRD pump room, ensure hose is filled bv performing the following: OPEN CRD-lSlA(B) CRD Pump Suctit,n Strainer Drain, to vent anv entrapped air within the hose connectFd to the SLC tank, and CLOSE CRD-lSlA(B) when venting is complete.

Standard: The operator opens CRD-151B by rotating the handwheel in the counterclockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel is rotate 1 counter-clockwise, and the effluent is an aidwater mixture.

Then, Examiner inform Operator that effluent is water only.

The operator closes CRD-15 1B by rotating the handwheel in the clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel rotated clockwise, and has now stopped.

SATAJNSAT *Step 21: (Steps 6/6.a) At the CRD Flow Control Station: OPEN CRD-40, CRD Pump Test Bvpass Line.

Standard: The operator opens CRD-40 by rotating the valve operating handle in he counterclockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the valve operating hardle rotated counter-clockwise, and has now stopped.

SATAJNSAT *Step 22: (Step 6.b) OPEN CRD-40A, CRD Pump Test Bvpass Line.

Standard: The operator opens CRD-40A by rotating the valve operating handle i 1 the counterclockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the valve operating har dle rotated counter-clockwise, and has now stopped.

JPM-P2

JPM -P2 Rev. 11 1 708 Page90 11 Evaluation Performance Steps SATAJNSAT *Step 23: (Step 6.c) CLOSE CRD-42A (B), Drive Water Filter F-16-1A (B)

-Inlet.

Standard: The operator closes CRD-42A or CRD-42B (Whichever is OPEN) by rotating the valve operating handle in the clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the valve operating har dle rotated clockwise, and has now stopped.

SATAJNSAT *Step 24: (Step 6.d) CLOSE CRD-94 Flow Control Station Disch to Rx Vest,&

Standard: The operator closes CRD-94 by rotating the handwheel in the clockwise direction.

Interim Cue: After the simulated action, Examiner inform the operator that the handwheel rotated clockwise, and has now stopped.

SATAJNSAT Step 25: (Step 7)Confirm either: RWCU Svstem is isolated or RWCU dem&

are isolated.

Standard: The operator contacts the Control Room and confirms that the RWCC System or the Demins are isolated.

Interim Cue: Examiner report as the ACRO that the RCWU System is isolated.

SATAJNSAT Step 26: (Step 8B.a) At CRP 9-5: START the CRD mmp(s) and verifv flow bv observing decreasing SLC tank level.

Standard: The operator contacts the Control Room and reports that the CRD System for boron injection from the SLC Tank has been aligned to CR D Pump B in accordance with OE 3 107, Appendix K; and that CRD Purirp B can now be started.

TIME FINISH:

Terminating Cue: This JPM is complete.

JPM-P2

JPM .P2 Rev. 111 708 Page 100 11 Evaluators Comments:

System: 295037 WA's: EAl.10 (3.7/3.9)

JPM-P2

EXAMINEE HANDOUT Initial Conditions:

0 An ATWS has occurred.

0 The EOPs have been entered.

0 The SLC Tank is available.

0 CRD Pump B is in service and CRD Pump A is in Standby.

Initiatine Cues:

The CRS directs you to line up the CRD System for boron injection from the SLC Tank in accordar :e with OE 3 107, Appendix K, to CRD Pump B. Inform the Control Room when the CRD Pumps can be started.

NOTE: All actions must be simulated. At NO time shall any plant equipment be operated.

JPM P3 Rev. 11 l"O8 Page 1 oj 10 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:

Title:

Shifting Air Compressors Failure Mode: The Low Oil Pressure LED is Illuminated

Reference:

OP 4190, Service and Instrument Air System Surveillance, (Rev. 19)

Task Number: 27970301 Task Performance: AO/RO/SRO X RO/SRO Only - SE Only -

Sequence Critical: Yes - No Time Critical: Yes - No J Operator Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation X Performance -Discuss Setting: Classroom - Simulator - Plant Performance Expected Completion Time: 10 minutes Evaluation Results:

Performance: PASS - FAIL - Time Required:

Prepared by:

Operations Training Instructor Date Reviewed by:

SRO LicensedlCertified Reviewer Date Approved by:

Operations Training Superintendent Date JPM-P3

JPM P3 Rev. l l l ' ' 0 8 Page2oi 10 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him tc 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 fo1 any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical ste p is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure I After providing the initiating cue, ask the individual "Do you understand the task?"

Read to the Derson 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 at 100% power.

Initiating Cues:

The CRS directs you to shift the LAG Air Compressors to LEAD and the LEAD Air Compressors t(

LAG in accordance with Section A of OP 4190, Service and Instrument Air System Surveillance.

Task Standards:

The Air Compressors are shifted in accordance with Section A of OP 4190.

Required Materials:

Handout 1 - OP 4190, Service and Instrument Air System (Rev. 19)

Simulator Setup:

NIA JPM-P3

JPM P3 Rev. 1 1 I 08 Page 3 ol 10 Provide Candidate with Initial ConditionsKue (Last Page of this JPM).

Evaluation Performance Steps TIME START:

SATKJNSAT Step 1: Obtain Procedure.

Standard: The operator obtains OP 4190, Rev 19.

Proceeds to Section A, Shifting Air Compressors.

Interim Cue: When it is apparent that the operator is seeking to find OP 4190, Examiner provides copy (Handout 1).

SATKJNSAT Step 2: (NOTE prior to Step 1)If one of the compressors is inoperable, th,e compressor which will become the lag compressor should be the one with the most operating hours indicated on the timer.

Standard: The operator reads the Note and proceeds to Step 1.

SATKJNSAT Step 3: (Step 1)Verifv that the test switches on the test panel, TP-1, for operable pressure switches are in the NORM position.

Standard: After the cue, the operator observes that all test switches are in NORW .

~~

Interim Cue: If switches are not in NORM, Examiner inform operator that all switches are in the NORM position.

JPM-P3

JPM P3 Rev. 11I' '08 Page 4 ol 10 Evaluation Performance Steps SATAJNSAT Step 4: (Step 2) On air compressor control cubicle lA(B,C,D) for all inservice air compressors, verify the following LEDs are extinguished:

Oil Pressure Air Temp LP Out Motor Overload Air Temp HP Out Standard: The operator observes the LEDs on Compressor A Control Panel.

The operator observes the LEDs on Compressor B Control Panel.

The operator observes the LEDs on Compressor C Control Panel.

The operator observes the LEDs on Compressor D Control Panel.

NOTE: The compressors in LEAD will be operating, the compressors in LAG will be not running.

Interim Cue: After checking, Examiner inform the Operator that the LEDs for the two compressor+in LEAD are extinguished.

After checking, Examiner inform the operator that the LEDs for the first compressor in LAG are extinguished.

After checking, Examiner inform the operator that the LED for oil pressure is illuminated on the last compressor that is in LAG.

SATAJNSAT *Step 5: (Steps 2.d2.a.l) If one or more of the LEDs are illuminated, for tlis affected compressor, proceed as follows: On panel CP-1, place th!

associated compressors control switch, CSl-A(B,C.DX to HOLD.

Standard: The operator rotates the affected compressor control switch from LA( i to HOLD.

Interim Cue: After the simulated action, Examiner inform the operator the affected compressor control switch is in HOLD.

JPM-P3

I JPM P3 Rev. 111 708 Page 5 01 10 Evaluation Performance Steps SATKJNSAT Step 6: (Step 2.a.2) Determine and correct the cause of the problem.

Standard: The Operator contacts the CRS, or I&C directly, and reports the probl hm.

Interim Cue: After the simulated action, Examiner inform the Operator that using Time Compress on the oil pressure switch had been replaced by I&C personnel.

SATAJNSAT *Step 7: (Step 2.a.3) On the associated air compressor control cubicle, depress S1, the STARTBESET pushbutton.

Standard: The operator depresses the S 1 pushbutton.

Interim Cue: After the simulated action, Examiner inform the operator the S 1, StartReset pushbut ton has been depressed SATAJNSAT Step 8: (Step 2.a.3.a) On the associated air compressor control cubicle 1A(B, C, D), verifv the followinp LEDs are extinguished:

Oil Pressure Air Temp LP Out Motor Overload Air Temp HP Out Standard: The operator verifies the LEDs are extinguished on the associated air compressor control cubicle.

Interim Cue: Examiner inform the Operator that the LED for the oil pressure is extinguished.

JPM-P3

JPM P3 Rev. 111 108 Page6o 10 Evaluation Performance Steps SATKJNSAT Step 9: (Step 3) On air compressor control cubicle lA(B,C,D), verifv that &l inservice air compressors LOADKJNLOAD switches are in the LOAD position.

Standard: The operator observes that all in-service air compressors LOADLJNLOAD switches are in the LOAD position.

Interim Cue: Examiner inform the Operator that all in-service air compressors LOADLJNLOAD switches are in the LOAD position.

SATKJNSAT *Step 10: (Steps 4/4.a-b) On panel CP-1, place control switch CSl-A(B,C,Dj for the units which are to become the running compressors to LE Q and verifv:

The machines start, load, and sound normal.

Oil pressure is between 20 and 44 psi%

Standard: The operator places the LEADLAG Switches for LAG Air Compressors placed in LEAD.

nterim Cue: After the simulated action, Examiner inform the operator that the switches are in LEAD.

The operator observes that the machine starts, loads and sounds normal.

Interim Cue: After the action, Examiner inform the operator that the machine starts, load, and sour ids normal.

The operator observes the oil pressure is between 20 and 44 psig.

Interim Cue: After the action, Examiner inform the operator that the oil pressure is -30 psig.

JPM-P3

JPM P3 Rev. 111 08 Page 7 of 10 Evaluation Performance Steps SATAJNSAT Step 11: (NOTE prior to Step 5 ) With a compressor selected to LAG, it wild run for approximately 6-7 minutes before shutting down provided there is no air demand for that compressor. If a compressor is selected to LEAD, the compressor will run continuously, cycling oe the unloader. Normally, two compressors are in LEAD and two ii?

-LAG.

Standard: The operator reads the Note and proceeds to Step 5.

SATKJNSAT *Step 12: (Step 5 ) On panel CP-1, place control switch CS1-A(B,C,D) for thg standby compressors to LAG.

Standard: The operator rotates the LEAD/LAG Switches for the Standby Compressors taken to LAG.

Interim Cue: After the simulated action Examiner inform the operator that the switches are in LAC:.

SATKJNSAT Step 13: (Step 6 ) If air demand is normal, verify that the LAG compressor+

shutdown.

Standard: The operator checks for normal air demand.

~ ~~~

Interim Cue: After the simulated action, Examiner inform the operator that air demand is normal.

The operator observes that the LAG compressors remain unloaded ani 1 shutdown after approximately 6 - 7 minutes.

Interim Cue: When the operator indicates that he must wait 6 - 7 minutes, Examiner inform the operator that air pressure is normal, 7 minutes have passed, and the LAG air compressors have stopped.

JPM-P3

JPM P3 Rev. 11l08 P a g e 8 d 10 Evaluation Performance Steps SATKJNSAT Step 14: (Step 7) Verify that the running compressors load and unload to maintain receiver pressure between 98-107 wig.

Standard: The operator observes air header pressure gage PI-105-51 and determi ies that the compressor is loading and unloading between 107 psig.

Interim Cue: When the operator observes air pressure, Examiner inform operator that the compresmr loads at 98 psig, and unloads at 107 psig.

SATKJNSAT Step 15: (NOTES prior to Step 8) An air compressor must have either the manual or thermostat controlled discharge damper open to allow air flow across the air coolers, otherwise the compressor may trip on high temperature.

Unless conditions warrant (Le., air cooler outlet temperatures are high), the discharge dampers should not be repositioned except as directed bv OP 2196.

Standard: The operator reads the Notes and proceeds to Step 8.

SATKJNSAT Step 16: (Step 8) Verify air flow path across the air compressors air coolers.

Standard: The operator verifies the air flow path across the air compressor air coolers.

Interim Cue: When the operator indicates that he will be verifying the air flow across the air compressor air coolers, Examiner inform the operator that the air flow across the air coolers is normal.

SATAJNSAT Step 17: (Step 9) Report any abnormal noises or indications to the Control Room.

Standard: The operator contacts the Control Room, and reports that there are no abnormalities.

Interim Cue: After action, Examiner inform the operator that the Control Room acknowledges thai there are no abnormalities.

JPM-P3

I JPM P3 Rev. 111' '08 Page901 10 Evaluation Performance Steps SATAJNSAT Step 18: (Step 10) Log: Completion in the surveillance logbook.

Standard: The operator logs completion in the Surveillance Logbook.

Interim Cue: When operator indicates he will log result, Examiner inform the operator that the Shift Manager or CRS will perform this.

TIME FINISH:

Terminating Cue: This JPM is complete.

Evaluator Comments:

System: 300000 KA: K4.01 (2.812.9)

JPM-P3

r EXAMINEE HANDOUT Initial Conditions:

The plant is operating at 100% power.

Initiating Cues:

The CRS directs you to shift the LAG Air Compressors to LEAD and the LEAD Air Compressors tt)

LAG in accordance with Section A of OP 4190, Service and Instrument Air System Surveillance.

NOTE: All actions must be simulated. At NO time shall any plant equipment be operated.

I Appendix D Scenario Outline Form ES-D-1 I Facility: VERMONT YANKEE Scenario No.: 1 Op Test No.: 2009 NRC Examiners: Operators: SRO -

RO -

BOP -

1 Initial Conditions: At 100% power DG A has been operating for 30 minutes for Monthly Diesel Generator Slow Start Operability Test (Tech Spec) per OP 4126, Sect B. The test is being performed following a diesel lube oil change. The test must be run for at least two hours at 2700 to 2750 kW and 1600 k 50 kVAR OUT.

RHR Pump B is 00s for severe vibrations that occurred during surveillance testing and is tagged out for Maintenance investigation.

Turnover: RHR Pump B is 00s for severe vibrations that occurred during surveillance testing and is tagged out for Maintenance investigation.

DG A is in operation for the Monthly Diesel Generator Slow Start Operability Test per OP 4126, Sect B. This requires DG B being declared inop IAW T.S. 3.10.8.1

1. With a reactor scram required and the reactor not shutdown, INHIBIT ADS to prevent an uncontrolled RPV depressurization to prevent causing a significant power excursion.

2. 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.

I Appendix D Scenario Outline Form ES-D-1 1 5 mf ED-05Da

-

C-RO Loss of MCC-SA with a failure of the Group 3 Isolation (AC-6B will C - SRO not auto close) Consult Tech Specs TS - SRO 6 mfED05Cb C - BOP 480V MCC-88 will trip causing a half scram (if RPS B was C - SRO transferred to its alternate supply) also the loss of the bus will challenge DW pressure by the loss of power to RRUs 1A and 1 B, alternate RRUs must be started. (This power lost will affect ATWS recovery by preventing the use of cooling water flow to insert the control rods.)

7 mf RP-02A M- ALL Loss of RPS MG Set A, Hydraulic ATWS with MSlV closure mf RD-12A mfRD-128 (20/20%)

8 mf SL-02A C-RO SLC Squib Valve A failure (the loss of 88 takes away SLC Pump C - SRO B) Candidate must recognize that the Squib Valves must be fired locally using the battery.

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

Scenario Event Description NRC Scenario 1 Vermont Yankee 2009 NRC Scenario #1 The crew takes the watch with the plant at 100°/o power and DG # A in operation for the Monthly Diesel Generator Slow Start Operability Test per OP 4126, Sect B. The test must be run for at least two hours at 2700 to 2750 kW and 1600 +50 kVAR OUT. Immediately after turnover, the crew is contacted by VELCO and requested to Raise Main Generator output to heavy load schedule and maximum Lagging (OUT) VAR Load (OP 2140, Sect. H) because a large unit within the system has tripped. The crew will raise Main Generator voltage and VARs but after the Main Generator has been raised to the limit a high turbine vibration will occur requiring the crew to terminate the voltage and VAR increase and lower reactor power to lower the turbine vibration to within vibration limits.

As the reactor and turbine are stabilized at a lower power level the crew must respond to a DG Voltage Regulator Malfunction, caused by the system voltage changes. This requires removing DG A from service, declaring DG A inoperable and entering the appropriate T.S.

The A Recirculation Pump controller will have failed and be slowly increasing A recirc pump speed, requiring the operator to diagnose the condition and go to manual and rebalance flows if/when the flow difference between the two loops exceeds 5%.

After conditions have stabilized MCC-SA will fail and one of the Group 3 Isolation Valves (AC-6B) will fail to auto close, the crew will recognize the failure and manually close the valve.

Additionally FRV B will lockup requiring a reset by the RO. The SRO will consult Tech Specs and identify the LCO per TS 3.5.A.6 After Tech Specs have been addressed for the loss of MCC-SA, and the isolation valve failure corrected, the 480V MCC-8B will have a fault and trip resulting in a loss of power to the bus, this will result in a loss of all AC power to the Vital MG and the alternate power supply to RPS Bus B. If RPS bus B was transferred to its alternate supply (9A) a reactor half scram will result. The crew must diagnose multiple power supply failures and start additional RRUs to maintain DW pressure.

A loss of RPS Bus A will cause a scram condition; some control rod insertion occurs; however, ATWS conditions will remain due to hydraulic lock on the scram discharge volume. The crew will be evaluated controlling and shutting down the plant in accordance with EOP-1 and EOP-2.

When SLC is initiated, the SLC Squib Valve Awill fail to fire. Because of the previous loss of MCC-8B the B SLC Pump/Squib Valve will not be available. The crew must send an A 0 to the Squib Valves and manually fire the Squib Valves with a battery. This will allow the A Pump to discharge through the open Squib Valve and alternate means to insert control rods will be required to shutdown the reactor (Critical Task). The crew will inhibit auto ADS initiation (Critical Task) and terminate and prevent injection as required by EOP-2 (Critical Task). EOP-2 actions to reduce reactor power via control rod insertion and lowering RPV level will be required.

Critical tasks are to inhibit ADS prior to automatic initiation, to terminate and to prevent injection as required by EOP-2, to inject boron into the reactor using the SLC system and/or take alternate means to insert the control rods.

VY 2009 NRC Scenario 1 Page 4 of 28 SIMULATOR EVALUATION GUIDE Eva1uators: Crew:

SM SRO RO BOP

~~

STA Senior Management Observer Critical Task Performance: SAT UNSAT (Circle One)

Lead Evaluator:

Signat u re Date Administered:

Activity Code:

Prepared by: Date:

Reviewed by: Date:

Approved by: Date:

VY 2009 NRC Scenario 1 Page 5 of 28 CREW BRIEF:

-Power level: lOO0/0

-Rod Sequence: Rapid Shutdown Sequence Latched -Rod Group: 22 WC)

-Equipment out of service and/or tagged or abnormalities:

1. RHR Pump B OOS, tagged out for Maintenance investigation yesterday at 1600.

-Reason For Equipment out of Service or tagged:

1. RHR Pump B 00s for severe vibrations during surveillance testing.

-Applicable Tech Spec LCOs:

1. Seven (7) day LCO, TS 3.5.A.3

2. Seven (7) day LCO, TS 3.10.8.1 EOOS Color:

Green 3.10 E-6

-Plant evolutions in progress/Scheduled Shift Evolutions:

1. DG A operating for 30 minutes for Monthly Diesel Generator Slow Start Operability Test (Tech Spec) per OP 4126, Sect B.

VY 2009 NRC Scenario 1 Page 6 of 28 SCENARIO

SUMMARY

TERMINATING CONDITION(S):

1. Once all control rods are inserted and EOP-2 is exited to EOP-1, the scenario may be terminated at the discretion of the Lead Evaluator.

REFERENCES:

1. OP 2140, Main Generator

2. ARS CRP 9-7 Alarm Response Sheets (F-2)

3. ARS CRP 9-8 Alarm Response Sheets (F-2)

4. OP 2126, Diesel Generators

5. OP 4126, Diesel Generators Surveillance Testing

6. OP 0105, Reactor Operations

7. OT 31 10, Positive Reactivity Insertion

8. OP 21 10, Reactor Recirculation System

9. AP 0156, Notification of Significant Events

10. ON 2143 480 VAC

11. ON 3174, Loss of Instrument AC

12. OT 3122, Loss of Normal Power

13. OT 3100, Reactor Scram

14. EOP-1

15. EOP-2

16. EOP-3

17. OE 3107

18. Technical Specifications

VY 2009 NRC Scenario 1 Page 7 of 28 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set UP: 100% Power

1. IC-805

2. CRD Pump B in service Discretionary Distracter Malfunctions/RFs/lOs:

1. rfNM-71-76 All APRM Gain adjusts made to get APRM GAFs in spec (modeled to the plant at 100°/o):71 (1.385)' 72 (1.448)' 7 3 (1.378), 74 (1,383)' 75 (1.287), 76 (1.375)

4. mfRD-126 20% Pre-insert Partial Scram '6'

5. mf SL-02A Pre-insert SLC Squib Valve 'A' fails to fire

6. rFRH-12 Open Pre-nsert RHR 6 ACB

7. mfTU-03A -60% 300 1 Turbine Vibration

8. mf DG-03A 100% 180 2 DG Voltage Regulator Malfunction

9. mfRR-11 B 100% 600 3 Recirc loop "6"controller failure

10. mfED-O5Da 4 LOSSOf 480V MCC-SA

11. mfED-05Cb 5 Trip MCC-8B Supply Bkr

11. mfRP-02A 6 Loss of RPS MG Set A

VY 2009 NRC Scenario 1 Page 8 of 28 SIMULATOR OPERATOR INSTRUCTIONS (Continued)

Additional Instructions:

1. RHR Pump B is in PTL and Danger Tagged

2. Call the Control Room as VELCO and request that they go to their heavy load schedule and their maximum VAR limit, due to a trip of a large unit on the grid

3. Begin the ramp up in turbine vibration after the crew has raised Generator output voltage and maximized the VAR load. The turbine high vibration alarm (Annunciator 7-F-2) should be received immediately after the voltage and VAR is increased. The increase in turbine vibration should stop at -7.5 mils, and will NOT cause a turbine trip.

4. When the crew starts power reduction, modify mfTU-03A to -28 to ramp turbine vibration back (over a two minute ramp) to the pre-transient level, then delete the malfunction.

5. The Recirc controller failure will be investigated, with no cause being found for the duration of the scenario.

6. If directed to adjust Alterex Cooling, respond as directed.

VY 2009 NRC Scenario 1 Page 9 of 28 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Place Main Generator in the Heavy Load Schedule with Maximum VARs IAW OP 2140, Sect. h.

POS CANDIDATE N/O COMMENTS ACTIONS/BEHAVIOR RO Acknowledges request from VELCO to go to the Heavy Load Schedule with Maximum VARs IAW OP 2140, Sect. H.

Informs SRO/SRO SRO Acknowledges request from VELCO and directs Crew to go to the Heavy Load Schedule with Maximum VARs IAW OP 2140, Sect. H.

SRO Briefs crew BOP Obtains and reviews procedure OP 2140 Section H and checks prereqs.

BOP Notify VELCO and ISO-NE that the VY is going to the Heavy Load Schedule.

notified of the VY Generator status respond as VELCO acknowledging the NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 10 of 28

7. BOP Determines Main Generator NOTE: SRO may designate RO parameters and BOP to coordinate the voltage 0 Generator MWe from adjustments between the Main ERFlS point G002, or on Generator and the DG.

panel 9-7, El 9-7-7. Circle instrument used.

345 KV System Voltage 0 Generator VARS from ERFlS point G009, or on panel 9-7 El 9-7-6. Circle instrument used.

7

8. BOP On panel 9-7, raise main NOTE: The crew may receive the generator VARS using Alterex temperature alarm. If so, VOLTAGE ADJUST AC until respond as directed.

system voltage reaches 358 KV and the maximum MVARS lagging (out) allowed per the generator 45 pound capability curve of OP 2140, Figure 1, for the gross MWe output is achieved

9. SRO Monitors Crew and plant performance.

May direct BOP to monitor the output of the A DG per OP 4126

- __ ~~

10. BOP Monitor the output of DG A per OP 4126 and adjust as necessary

-

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 11 of 28 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

High Main Turbine Vibration Requires Power Reduction IAW OP 0105 POS. CANDIDATE ACTIONWBEHAVlOR S N/O I COMMENTS CREW Recognize/Announce Annunciator NOTE: It takes about 2 minutes 7-F-2 (Turbine Excessive for the vibration alarm to occur Vibration) following initiating the malfunction.

SRO Determines turbine bearings vibrations on ERFIS.

Direct power reduction IAW OP-0105 if vibrations approach 10 mils.

May direct reducing VARs back to the normal VAR load.

Notifies or directs notifying IS0 New England and VELCO.

Notifies Maintenance.

BOP Notify VELCO and ISO-NE that raising VY voltage and VARS will be terminated due to high turbine vi bration.

RO Reduce load as directed using Recirc flow.

May shift to coarse control to quickly lower recirc flow NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 12 of 28

. 5.

I

~ ~~

BOP Monitors Turbine Vibration and other plant parameters and reports to crew Responds to Annunciators 9-48-3 and F-3and sends an A 0 up to adjust Recirculation MG Set oil temperatures.

ROLE PLAY: As A 0 respond as directed. In the booth rfSW-58 adjusts Recirc MG Set oil temps.

I Responds as directed if asked to walk down the turbine/generator EVALUATORS CUE: OP 0105 allows power reduction at 10% per minute

6. SRO When Turbine vibrations lower directs stop lowering power EVALUATORS NOTE: May receive alarm 5-E-6 FW Control System trouble. Due to mismatch of level and setpoint during power reduction. The alarm is expected and will clear.

7. RO Stops lowering power and determines position on the P/F Operating Map EVALUATORS CUE: Go to next event at the Examiners discretion.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 13 of 28 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

DG Voltage Regulator Malfunction requires removing the A DG from service. Declaring DG A inoperable and-appropriate T.S.

POS CANDIDATE N/O COMMENTS ACTIONS/BEHAVIOR CREW Acknowledge/respondto DG A NOTE: If transfer from auto voltage regulator to manual voltage regulator FIELD VOLTS INCREASE is not made prior to reaching the trip setpoint DG A will trip. Causing VARS INCREASE Annunciator 8-F-2 8-G-1, DG-A OVERLOAD 0 Inform SRO 0 Dispatch an A 0 to investigate 0 Diagnose A Standby Diesel Generator Auto Voltage Regulator Failure SRO Direct the following NOTE: May direct the A 0 to locally trip the A DG.

0 Dispatch AO/Maintenance to investigate NOTE: May continue on in OP 4126 to remove the A DG from service 0 Enter OP 2126 0 May direct attempting to control voltage manually 0 Direct Manual S/D from the Control Room (Sect. B.)

0 When DG inoperability is determined, consult TS and enter an additional 7-day LCO (TS 3.10.8.1)

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 14 of 28 POS CANDIDATE

-N/O COMMENTS

- BOP ACTIONS/BEHAVlOR Mat transfer from Auto Voltage

- NOTE: May direct the A 0 to locally regulator to Manual Voltage trip the A DG.

Regulator Reduce load to approximately 50%

using the DIESEL GEN SPEED GOVERNOR control switch Control DG voltage and VAR loading using Manual Voltage Control.

Run unit at 50% load for 5 minutes.

Using the DIESEL GEN SPEED GOVERNOR control switch, unload unit to < 200 kw.

Open BKR NO. DG-A, diesel generator output breaker.

Run unloaded for approximately 1 minute.

Reset the SPEED DROOP to "Zero".

May make plant announcement that the A DG is being shutdown Take the DIESEL GEN STOP-START switch to STOP Contact VELCO and inform them that the DG is no longer paralleled to the grid and that normal VY capacitor bank operation may be resumed.

ROLE PLAY: Respond as VELCO and acknowledge report.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 15 of 28 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

Respond to positive reactivity addition caused by failure of the "B" Recirc loop controller POS. CANDIDATE S U N/O COMMENTS ACT1ONS/BEHAVlOR CREW Recognize Power/Recirc flow increasing Identify the Loop "B" controller ramping upward; inform SRO Notify SRO SRO Enteddirect actions IAW OT 31 10 OT 3110 Immediate Actions 0 Transfer the loop " B controller to individual manual control Attempt to lower Recirc flow at < 10% RTP/min to reduce power to pre-transient level RO 0 Transfer the loop " B controller to individual manual control 0 Lower Recirc flow at c 10%

RTP/min to reduce power to pre-transient level RO Verifies position on P/F Operating Map MAY determine that MELLLA has been exceeded and have to insert Rapid Shutdown Sequence rods.

I-NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments: a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 16 of 28 Recirculation MG Set oil ROLE PLAY: As A 0 respond as directed. In the booth rfSW-58 adjusts Recirc MG Set oil temps.

-

6. SRO Notifies Workweek Manager/Maintenance/l&C Notifies RE 7 RO Determines current control rod positions Determines next control rod to be inserted Inserts control rods IAW Rapid Shutdown Sequence Monitors P/F Map Secures from inserting control rods when directed or within MELLA limits Notifies SRO/Crew

8. SRO Conducts Crew Brief Booth Operator: When directed, move to Event 5 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 17 of 28 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

Loss of 480 Volt Bus 9A, Failure of Group 3 Isolation Valve.

- POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR CREW Acknowledge and Recognize:

Annunciator 8-P-2, BATT CHRG FAIUDCP GRD Annunciator 5-E-2, FW VLV LOCKUP SIGNAUAIR FAIL Half Scram Notify SRO/Crew of a loss of 480 Volt MCC-SA.

Diagnose loss of Instrument A.C.

(shifts to alternate but may be restored)

RO Inform SRO of half scram.

Report power, pressure, level BOP Recognizehespondto a Group 3 isolation and bus loss.

Board walkdown to recognize equipment affected Lossof RWCU 0 Diagnose loss of SGT Fan A 0 Diagnose failure of AC-66 to close

~~ ~ ~

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 18 of 28

-

POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR SRO Direct the following actions:

Close AC-6B Backup Group Ill isolation May direct crew to enter OP 2143,480 VAC Buses to diagnose the loss of power Direct call to chemistry for sampling per T.S. 4.6.B.3.b Direct crew to initiate an investigation into bus loss.

Direct restoring the 6 FRV to auto IAW ARS for 5-E-2 May direct restoring RPS power by shifting to the Alternate Supply MCCBB per OT 3122, Step 10 or may use OP 2143 (not a priority)

May direct resetting the Y2 scram.

Enters ON 3174, Loss of Instrument AC

5. RO 0 Restore FRV B to auto IAW ARS for 5-E-2 by resetting the lockup by depressing the lockup pushbutton.

0 Restore RPS power by shifting to the Alternate Supply MCC 8B IAW OT 3122, Step 10 or may use OP 2143 (not a priority) 0 Reset the scram 0 Notify the crew

-

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 19 of 28 POS CANDIDATE U N/O COMMENTS ACTIONS/BEHAVIOR m

BOP When directed, backup Group 3 isolation 0

0 Close AC-6B Inform SRO I

EVALUATOR'S NOTE: If requested to investigate MCC 9A state that the bus tripped because of an apparent fault but that nothing specific is evident and request that the bus is not re-energized while you continue looking.

7. SRO Consult Tech Specs and identify 7 day LCO - 3.7.8.3 (Group Ill) 7 day LCO - 3.7.3 b (SGT Fan A) 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO for 3.6.C.2 (CAMS) until group 2 is reset Notifies Workweek Manager/Maintenance/l&C May Notify RE BOP Isolates RWCU (The system may be re-started).

Booth Operator: When directed, move to event 6 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 20 of 28 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Respond to a loss of 480 Volt M C C I B POS CANDIDATE ACTIONS/BEHAVIOR COMMENTS BOP Recognize and inform the SRO that NOTE: ?hscram only if RPS B was 480V MCC-8B has tripped. swapped to alternate power supply Diagnose loss of Alternate RPS Supply and Y i scram on RPS Bus B.

SRO May direct crew to enter OP 2143, 480 VAC Buses, to diagnose the loss of power BOP Diagnose loss of SLC Pump B Diagnose Loss of RRUs 1A & 1B Loss of power to RClC RHR and Core Spray Valves V13-15, V10-66 V10-31B V10-65B V10-896 V14-11B V10-183 V10-388 V10-398 V14-12B V14-58 V10-166 V14-78 V10-348 V14-268 V10-158 V10-150 V10-138 V10-130 V10-18 V10-26B

...

CRD Coc i g Water Valve PC 22 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 21 of 28 t 3

-POS SRO CANDIDATE ACTIONS/BEHAVIOR Direct crew member and U N/O c

COMMENTS maintenance to investigate reason for loss of 480V MCC-8B.

Direct starting additional RRUs to control DW Pressure.

Determine that the Vital AC is running on the Batteries and that alternate power is NOT available.

EVALUATORS NOTE: If requested to investigate MCC-8B state that the bus tripped because of an apparent fault but that nothing specific is evident and request that the bus is not re-energized for at least another hour while vou continue lookina.

Starts monitors DW Pressure and starts additional RRUs May start to enter TS for the NOTE: Sufficient TS should have SRO inoperable RPS Power Supplies, been observed at this time.

ECCS Valves and B SLC Combined with the loss of the A DG earlier and the ECCS systems the plant is in a 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO. Per TS 3.5 ECCS and 3.10 DGs.

However the Vital Bus running on the Battery may require a shutdown earlier.

May direct preparations to for a normal shutdown per OP 0105 May provide a crew brief on conditions EXAMINERS CUE: When SRO enters T.S., go to Event 7.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 22 of 28 OPERATOR ACTIONS EVENT NUMBER 7 and 8 Crew Task

Description:

Loss of RPS MG Set A, ATWS (45%/55%) and failure of A SLC Squib Valve.

POS CANDIDATE N/O COMMENTS L

1.

-

CREW ACT IONS/BEHAVl OR Recognize failure to scram and MSlV closure Diagnose SRV lifting

2. RO Report Partial Rod Insertion.

place Mode Switch in SHUTDOWN Initiate ARI

3. SRO Direct RO to maintain level from 127" - 177".

4. ROB0 Maintain reactor level as P directed.

0 Determine HPCl not required for level control 0 HPCl tripped and inhibited

-

5. SRO Direct RO/BOP to maintain reactor pressure 800 -

1000 psig using SRVs.

6. RO / Maintain reactor pressure as BOP directed.

-

7. SRO Direct crew to monitor the plant cooldown.

a. BOP When directed, monitor cooldown.

-

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 23 of 28 POS CANDIDATE S N/O COMMENTS ACTIONS/BEHAVIOR SRO When informed of the failure to scram enter and direct crew actions IAW EOP-1 and EOP-2 SRO When directed, verify EOP-1 Table A automatic actions CREW Recognize/respondto high Drywell temperature and pressure, entry into EOP-3; inform SRO SRO Enteddirect actions per EOP-3 0 Restart Drywell RRUs.

BOP When directed:

0 Restart Drywell RRUs.

CREW With a reactor scram required and the reactor EOP-2 not shutdown, INHIBIT ADS CT-1 to prevent an uncontrolled RPV depressurization to prevent causing a significant power excursion.

Standard:

Inhibit ADS prior to automatic initiation.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 24 of 28 3

-

0 Verify ARVRPT initiated 0 Insert control rods with one or more appropriate appendices May direct A 0 to manually operate CRD-v-22 NOTE: Implement appendix F, BB or H of OE 3107.

0 Stabilize pressure RPV pressure 800-1,000 psig with BPVs.

-

16. BOP When directed:

0 Inhibit ADS.

0 Stabilize pressure 800-1000 psig with SRVs.

-

17. SRO Direct terminate/prevent injection per Appendix GG.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 25 of 28

e

I I CANDIDATE ACTIONS/BEHAVIOR

-

N/O COMMENTS

-

CREW During an ATWS with conditions met to perform EOP-2 powerAevel control CT-2 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 IAW OE 3107 Appendix GG within 5 minutes of loss of forced circulation.

SRO Direct SLC injection with A SLC pump

CREW With a reactor scram NOTE: Must use local battery to fire required and the reactor Squib Valve 6 EOP-2 not shutdown, TAKE CT-3 ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to prevent exceeding the primary containment design limits.

Standard:

Actions taken within 10 minutes of the scram failure to implement appropriate appendices and/or inject SLC. Initially SLC will be NOT be available, OE 3107, App I, Alternate SLC injection, firing the squib valves with the local battery.

EVALUATORS NOTE: This step is an Immediate Action, and may be performed without direction.

SLC Pump A will run however its Squib Valve will fail to fire.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 26 of 28

- S

-

POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR

21. RO Notify SRO/Crew of failure of the A Squib Valve to fire 7

22. SRO Direct sending an A 0 to the NOTE: 1.5 VDC Squib valve firing batter Squib Valve RB 318 level (3" available with an alligator clip on each floor) and firing the squib end. (Located in EOP toolbox, 318' using App I of OE 3107, elevation, Reactor Building.)

Alternate SLC injection.

23. RO Direct A 0 to go the Squib Valves on the RB 318' level (3" floor) and firie the squib valves using the battery per App I of OE 3107, Alternate SLC injection Turn SLC switch (keylock) to OFF

-

ROLE PLAY: Wait one minute and notify the control room that the squib valves have been fired.

24. RO When notified of successful local firing of a squib valve, start SLC Pump 6.

25. RO Insert control rods using directed appendices.

26. BOP When directed, terminate/prevent injection per Appendix GG.

I I EVALUATOR NOTE: Torus temperature will reach 110 degrees before power drops to < 2%. This along with an SRV open and level > TAF will satisfy override to terminate and prevent / enter -19" to 9 0 level control leg.

27. RO Recognize when power drops below 2 %; inform SRO

28. SRO Direct RPV level maintained between -1 9 and 90 inches NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 27 of 28 POS CANDIDATE

-8 N/O

-

COMMENTS

-

ACT IONS/BEHAVIOR

29. RO Maintain RPV level between

-19 and 90 inches

-

30. *CREW With a reactor scram NOTE: OE 3107, Section 66 inserting required and the reactor not Control Rods using Cooling Flow will not EOP-2 shutdown, TAKE ACTION be available because CRD-PCV-22 CLG CT-3 WTR PRESS has no power because of TO REDUCE POWER by inserting control rods, to the loss of MCC-8B.

prevent exceeding the primary containment design limits.

Standard:

Actions taken within 10 minutes of the scram Recognize all rods inserted; inform SRO

31. SRO When all control rods inserted, exit EOP-2 and enter/direct actions IAW EOP-1:

0 Verify Table A automatic actions 0 Restore / maintain RPV level 127 - 177 inches.

Commence cooldown at less than 100 degrees F per hour.

-

32. BOP When directed, commence cooldown at less than 100 degrees F per hour.

SRO When all rods inserted, exit EOP-2, enter EOP-1, and direct RPV level restored and maintained 127 -1 77 inches.

l n ario be terminated, once EOP-2 has been exited at the discretlon of the Lead Evaluator, NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 1 Page 28 of 28 OPERATOR ACTIONS ADDITIONAL COMMENTS:

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

I Appendix D Scenario Outline Form ES-D-1 1 Facility: ~ VERMONT YANKEE Scenario No.: 2 Op Test No.: 2009 NRC Examiners: Operators: SRO -

RO -

L Initial Conditions: At -1% power, Startup in progress. OP 0105, Phase 2.D Step 10 A IRM failed upscale during the startup and is bypassed.

RHR Pump C is 00s Turnover: Indefinite LCO due to IRM A 00s (TS Table 3.1.1 and TRM 3.2.5)

RHR Pump C is 00s for severe vibrations during surveillance testing. Tagged out on previous shift; estimated return to service is 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , 7-day LCO due to RHR Pump C00s (TS 3.5.A.3)

MSlV Isolation Testing is NOT required Critical Task: 1. Following a Loss of Normal Power diagnoses B DG failed to auto-start and manually starts B DG and places on 4KV Bus 4.

2. With the reactor shutdown and reactor pressure greater than the shutoff head of the low pressure systems, initiate RPV-ED BEFORE RPV level reaches -1 9 inches

3. Restore and maintain RPV level above TAF (+6 inches)

Event Malf. No. Event Event Description

- No. - - Type*

-

1 NIA R-RO Withdraw control rods to continue the startup R-SRO 2 mfNM-O3C I-RO IRM C h o p Failure, results in half scam.

(100%) I-SRO TS - SRO 3 N/A N - BOP Transfer Reactor Mode Switch to RUN and continue the startup.

N - SRO 4 Failure of CRD Flow Controller Automatic Output Signal 5 mfHP-03 C-BOP HPCl inadvertently injects to the vessel with a controller failure mfHP-04 C-SRO (low - to prevent a reactor scram). The crew will confirm that the HPCl injection is spurious and trip the HPCl turbine. Requires TS-SRo T.S. 3.5.E entry 6 mfED-02A M - ALL Loss of the startup transformers which will result in a LNP and mf ED-02B reactor scram.

7 mfDG-05A C - BOP Both DGs fail to auto start, DG A cannot be started, DG B can mfDG-08B C-SRO be manually started.

IAppendix D Scenario Outline Form ES-D-1 1 8 mf R R-0 1A -

M ALL Core spray line B break in the Drywell between the RPV and OVRD ANN injection check valve resulting in a LOCA and loss of the remaining Core Spray system.

9 RHO1D C - ALL B Loop RHR Pump D trips I

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

t Scenario Event Description NRC Scenario 2 Vermont Yankee 2009 NRC Scenario #2 The crew takes the watch with the plant at 1% power Startup in progress. Currently, they are in OP 0105, Phase 2.D Step 10. After assuming the watch the crew will withdraw control rods to continue the startup. After some control rod movement IRM C will fail inoperative causing a half scram. Because the A IRM failed upscale during the startup and is bypassed, IRM C cannot be bypassed. The SRO must enter Technical Specifications for the two inoperative IRMs. I & C investigates and determines that IRM A can be returned to service and un-bypassed then IRM C can be bypassed and the half scram reset.

After the IRM issue is addressed the crew will-Transfer Reactor Mode Switch to RUN and continue the startup. After several more control rods are withdrawn the CRD Flow Controller will fail high, opening the flow control valve, this will result in higher than normal rod speeds, possibly double notching. The RO must diagnose the change in rod speeds and the controller failure then place the controller in Manual. After the CRD Flow failure a spurious HPCl initiation with a HPCl flow controller failure occurs, HPCl does not inject (to prevent a reactor scram).

The crew will confirm that the HPCl injection is spurious and trip the HPCl turbine. Because both an RHR Pump and HPCI are inoperable Technical Specifications 3.5.E.3 places the plant in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO.

After conditions have stabilized and the Tech Specs addresses a loss of the startup transformer will occur which will result in a LNP and reactor scram. The crew will execute OT 3100, ON 3150 and OT 3122. During the LNP both Emergency Diesel Generators will fail to auto start, DG A cannot be started; DG B can be manually started (Critical Task) and tied to 4 KV Bus 3. If the crew attempts to energize Bus 3 or Bus 4 from the Vernon tie the Vernon Tie will trip.

When the available power supplies are lined-up the Core spray line B will break in the Drywell between the RPV and testable check valve resulting in a LOCA and loss of the remaining Core Spray system. The B Core Spray pump will appear to be available because the pump is running. The break may be diagnosed using the CORE SPRAY HDR DP HI Annunciator which will alarm on break. If the crew does not diagnose the break when the B Core Spray starts the discharge pressure will be low and the flow high because it is discharging into the break and not the reactor. Because of the power failure only RHR Pump D will be available, however this pump will trip. When the crew cannot maintain RPV water level greater then -19 they will enter EOP-5 and emergency depressurize (Critical Task). The crew must lineup and inject with RHRSW and/or locally start the A DG and recover the ECCS equipment supplied by the A DG and/or recover the ID RHR Pump. RPV level must be restored to above TAF (+6)

(Critical Task).

Critical tasks are manually starting DG 9and restoring power to 4kV Bus 4. Inhibit ADS and to prevent an auto blowdown. Then when RPV water level lowers to c 6 enter EOP-5 and emergency depressurize before RPV water level reaches -19 in. After the blowdown restore water level above TAF (+6)by locally starting the A DG or restoring the D RHR Pump and/or lining up and injection with RHR SW.

VY 2009 NRC Scenario 2 Page 4 of 27 SIMULATOR EVALUATION GUIDE Evaluators: Crew:

SM SRO RO BOP STA Senior Management Observer Critical Task Performance: SAT UNSAT (Circle One)

Lead Evaluator:

Signature Date Administered:

Activity Code:

Prepared by: Date:

Reviewed by: Date:

Approved by: Date:

VY 2009 NRC Scenario 2 Page 5 of 27 CREW BRIEF:

-Power level: -1 %

-Rod Sequence: Rod Sequence: A2 -Rod Group: 14

-Equipment out of service and/or tagged or abnormalities:

1. C RHR Pump OOS, tagged out for Maintenance investigation yesterday at 1600.

2. A IRM failed upscale during the startup and is bypassed, I & C investigating.

-Reason For Equipment out of Service or tagged:

1. C RHR Pump 00s for severe vibrations during surveillance testing.

-Applicable Tech Spec LCOs:

1. Seven (7) day LCO, TS 3.5.A.3 EOOS Color:

Green 3.12 E-6

-Plant evolutions in progress/Scheduled Shift Evolutions:

1. Withdraw control rods to continue the startup continuing in OP 0105, Phase 2.D, Step 10.

2. Place reactor mode switch in RUN and continue the startup.

3. MSlV Isolation Testing is NOT required

4. Drywell inerting is in progress purging with RTF-5.

5. Another operator will perform OP 0105, Phase 2.D, Step 10.e to ensure actions to inert the containment and establish Drywell to Torus AP per OP 21 15 are initiated.

VY 2009 NRC Scenario 2 Page 6 of 27 Plant evolutions in progress/Scheduled Shift Evolutions:

A plant S/U is in progress, OP 0105, Phase 2D, Step 9 is complete. The following is a list of equipment status:

1. Reactor Level Control - 1 condensate pump, 1 feed pump, the 10% FRV in auto, letting down to the main condenser at 65 gpm?

2. AOG is running with AOG Recombiners warmed up in Manual, the Hogger is secured with the SJAEs in-service.

3. The EPR is controlling pressure.

4. Currently in OP 0105, Phase 2D Step 10 withdrawing control rods in preparation to shifting to RUN.

5. The Drywell is being air-purged with RTF-5 and is ready to be inerted.

6. Another operator will perform OP 0105, Phase 2.D, Step 10.e to ensure actions to inert the containment and establish Drywell to Torus AP per OP 21 15 are initiated.

VY 2009 NRC Scenario 2 Page 7 of 27 SCENARIO

SUMMARY

TERMINATING CONDITION(S):

1. RPV water level under control

REFERENCES:

1. OP 0105, Reactor Operations

2. OT 31 10, Positive Reactivity Insertion

3. OP 2131, IRM

4. EN-OP-115, Manual Control of Automatic Systems

5. Technical Specifications

6. OT 31 10, Positive Reactivity Insertion

7. OE 3107, EOP/SAG Appendices

a. OP 21 17, SBGT

9. OT 3122, Loss of Normal Power

10. ON 3150, Loss of S/U Transformers

11. EOP-1

12. EOP-3

13. EOP-5

14. OT 3100, Scram

VY 2009 NRC Scenario 2 Page 8 of 27 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set Up: -1% Power

1. IC-806 Discretionary Distracter Malfunctions/RFs/lOs:

No. - MF/RF/IO # Severity Ramp REM # Act. Time Description

- - - - - -

1. ET-C S-B reak Pre-insert Event Trigger to Support Core Spray Break (Key 4)

2. mf CS-03 B Pre-insert CS Inject Vlv12B Fails to Auto Open

3. 1 mfNM-03A 1 100% I 1 Pre-insert 1 1 IRM A Failure

4. mf DG-O5A Pre-insert DG A Fails to Start Pre-insert mfDG-08B DG B failure to Auto Start

5. MF-ED18 Pre-insert BKR 3V4 Switch Failure

6. I mfNM-03C I 5% I I 1 1 I IRM C INOP Failure

7. 1 MfRD-15 Failure of CRD Flow Controller

8. mf HPO3 3 HPCl inadvertently injects mf HPO4 10% 5 3 HPCl Flow controller failure

9. mfED-02A 4 Loss of Startup Transformers mfED-026 4 Loss of Startup Transformers

10. mfRR-OlA 1O/O 5 Core spray line B break in the Drywell between the RPV and testable check valve.

mfAN03Q3 Spurious 5 Core Spray B D/P Header HI

11. RHOlD 6 RHR Pump D Trip

VY 2009 NRC Scenario 2 Page 9 of 27 SIMULATOR OPERATOR INSTRUCTIONS (Continued)

Additional Instructions:

1. A IRM should be bypassed and on range 6

2. Ensure the following: 1 condensate pump, 1 feed pump, aux FRV in auto, 55%

FRVs blocking valves closed and all feed pump discharge valves open.

3. Roll the key locks in panel 9-41, 9-42 to Bypass to allow the 18-inch containment purge valves open when in run.

4. Fill out a current revision of VYOPF 0105.05

5. Update the Condensate Demineralizer status sheet on the 9-7 Panel to reflect the startup status; two demineralizers in service and three on the hold pumps.

6. Verify RWM initialized.

7. After IRM C fails and when contacted by the crew acknowledge the request then allow time for Technical Specifications entry and as I & C report that IRM A can be returned to service and that you will begin trouble-shooting the C IRM.

8. If asked, the cause of the startup transformer loss was due to a direct lightning strike. Maintenance is investigating to determine if any damage was done, they should know within a couple of hours.

9. If no attempts are made to cool/spray the drywell the leak may cause the crew to emergency depressurize to prevent exceeding PSP. This will not effect the outcome of the scenario and this would serve as a substitute critical task to emergency depressurizing on inability to maintain RPV water level >-19.

10. After the D RHR Pump trip respond as the A 0 when called to investigate the pump motor trip. Then after a realistic time report the breaker cubicle appears normal with only and over-current flag showing.

11. If the crew has sent AO/Maintenance to the A DG wait until RPV water level is 6 inches and lowering and then remove the trip and reset the lockout and notify the Control Room that A DG is available (the 100 second timer will prevent immediately starting the DG).

VY 2009 NRC Scenario 2 Page 10 of 27 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Withdraw control rods to continue the startup POS. CANDlDATE COMMENTS ACTIONS/BEHAVIOR

--

1. SRO Directs performance of OP 0105, PHASE 2D, Step 10 Briefs crew on the startup

--

2. RO Verifies correct rod selected for the sequence.

Withdraws control rods IAW the sequence instructions until all APRMs are indicating on-scale.

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.

Check that all APRM downscale alarms are clear.

3. BOP May obtain and review procedure OP 0105, PHASE 2.

Verifies reactor vessel level between 155 and 165 inches.

Will serve as verifier for rod selection and movement and IRM range switching.

EXAMINERS NOTE: Insert IRM malfunction prior to APRM downscales clearing.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 11 of 27 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

IRM C lnop Failure, Requires T.S. entry and insertion of manual half scam.

POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR CREW Recognize/Acknowledge Annunciators:

5-D-3, Rod Withdraw Block 5-N-1, IRM Ch A Hi-Hi/INOP 5-K-1, Auto Scram Ch A 5-L-2, Neutron Mon Power Hi Diagnoses IRM C failed INOP Diagnoses Y2 scram SRO Acknowledges report Diagnoses IRM C INOP, references OP 2131, Section C.

Directs confirmation of IRM C INOP.

Directs I & C to investigate.

Consults Tech Specs - Table 3.1 .l.for two IRMs hop.

(May enter TRM 3.2.5 which is a 7 day LCO.)

Determines the inoperable instrument channels trip system must be placed in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

When I & C investigates and determines that IRM A can be returned to service directs un-bypassing IRM A then direct bypassing IRM C .

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 12 of 27 EVALUATORS NOTE: If contacted as I & C report that IRM A can be returned to service and that you will begin trouble-shooting the C IRM. If NOT contacted call the Control Room and notify them that IRM A can be returned to service.

Resets the half scram NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 13 of 27 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

Transfer Reactor Mode Switch to RUN and continue the startup.

POS CANDIDATE COMMENTS ACTIONS/BEHAVlOR SRO Enteddirect placing the Reactor Mode Switch in RUN RO 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.

Check that all APRM downscale alarms are clear.

Smartly transfer Reactor Mode Switch to RUN.

Transfer recorder switches to APRM channels.

RO Fully withdraw all IRM detectors. NOTE: Proper IRM withdrawal may be determined by selecting each IRM channel for recording as its respective chamber is withdrawn a r d verify that indicated level is decreasing.

SRO Request Reactor Engineering to initiate APRM GAF per OP 4400.

Request RP perform high rad door checks and TB Heater Bay surveillance per OP 0532.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 14 of 27 POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR SRO May direct:

lose main steam line drain talves:

MS-74 MS-77 MS-78 In the Torus Room, MS-23 BOP If directed by SRO Close main steam line drain valves:

MS-74 MS-77 MS-78 Direct A 0 to close (in the Torus Room) MS-23 SRO Directs power ascension per OP 0105 until 1 '/2 bypass valves open NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 15 of 27 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

Failure of CRD Flow Controller Automatic Output Signal

==

POS CANDIDATE COMMENTS ACTIONS/BEHAVlOR RO Recognize Faster control rod speeds CRD system pressures rising Flow Controller output rising Diagnose CRD Flow Controller Failure Announce to SRO/Crew SRO Direct entry into ON 3145, Loss of CRD Regulating Function Direct placing the Flow Controller (FIC-3-301) in MANUAL Directs contacting Work Week Manager and/or I & C to troubleshoot CRD FCV.

RO Places the Flow Controller (FIC-3-301) in MANUAL Verifies proper operation Adjusts Drive Control and Cooling Control Valves as necessary to restore CRD System parameters BOP Contacts Work Week Manager and/or I & C to troubleshoot CRD FCV.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 16 of 27 POS CANDIDATE S U N/O COMMENTS ACTIONSlBEHAVlOR E BOP May direct shifting CRD FCVs May contacts A 0 to coordinate shifting FCVs I I NOTE: If the crew starts to shift CRD FCVs go to the next malfunction

1) EVALUATORS CUE: When CRD Parameters are restored insert Event 5, Inadvertent HPCl initiation. 1 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 17 of 27 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

HPCl inadvertently injects to the vessel with a controller failure. Requires T.S. 3.5.E entry

- POS CANDIDATE

-

N/0 COMMENTS CREW ACT IONS/BEHAVI0R Recognize and inform the SRO of

-

indications of a HPCl system initiation and injection.

SRO When informed of the HPCl system start, verify adequate level IAW OT 3110.

May enter OT 3110 - Positive Reactivity Insertion, Step 2.5. after actions are taken IAW IAW EN-OP-115, Manual Control of Automatic Systems BOP Confirm no initiation signals present. Using two indications Verifies Feedwater control system maintaining RPV water level.

Diagnoses HPCl Controller failure Notifies Crew SRO When adequate level has been verified, direct the BOP to inhibit the HPCl system

~~ ~

BOP When directed, inhibit the HPCl NOTE: The shutdown section of system IAW EN-OP-115, Manual OP 2120 will NOT work in this Control of Automatic Systems situation because the faulty initiation signal will continue to start HPCI.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N10 = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 18 of 27 I ROLE PLAY: When contacted as I&C and/or maintenance and requested to investigate the HPCl problem respond that you will send a technician to the Control Room shortly and then delay.

SRO Recognize and enter T.S. 24 hr NOTE: T.S. Bases states that an LCO IAW T.S. 3.5.E.3. RHR Subsystem consists of 2 pumps, since RHR Pump C is INOP, the subsystem is NOT operable.

SRO Direct the crew to confirm operability of RCIC.

Conduct a Crew brief EVALUATORS CUE: When ready advance to Events 5 and 6

-

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 19 of 27 OPERATOR ACTIONS EVENT NUMBERS 6 and 7 Crew Task

Description:

Loss of the startup transformers which will result in a LNP and reactor scram and both DGs fail to auto start, DG A cannot be started, DG B can be manually started.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

I VY 2009 NRC Scenario 2 Page 20 of 27 POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR SRO When notified the DGs failed to NOTE: Because the A DG has a automatically start transition to App Failure to Start Annunciator A of ON 3122, Station Blackout. Maintenance must be contacted before attempting to start the A DG.

Directs:

CT-1 Attempt to start the B DG IAW EN OP 115, Manual Control of Automatic Systems Placing the service water pump control switches to STOP, then NORMAL.

Placing all ECCS pumps in PULL-TO-LOCK.

Energizing Bus 4 from Vernon tie Attempts to energize Bus 3 or Bus BOP 4 from Vernon tie by closing 3V4 and a feeder breaker to 4KV Bus 3 or 4.

Acknowledges/diagnoses failure of breaker 3V4 to close Reports failure of cross-tying to Vernon.

Directs operator to contact SRO AO/Maintenance to investigate DG A failure to start May direct additional attempts to start the DGs per App A of OT 3122.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 21 of 27 POS CANDlDATE ACTIONS/BEHAVIOR If not previously done UINIO COMMENTS BOP acknowledge/respondto DG A Lockout Trip Annunciator (8-F-2)

Contact AO/Maintenance and directs them to investigate DG A failure to start Diagnoses B DG failed to auto-start and manually starts BDG and places on 4KV Bus 4.

Notifies Crew B DG in service 8 When notified Bus 4 available SRo directs cross-tying buses 8 and 9.

9.

I BOP I Cross-ties buses 8 and 9.

10. Carries out scram action IAW RO ON 3100 Verifies RClC operation when needed.

11. SRO Directs work week manager to check DG A and/or Back-feeding through the Auxiliary Transformer.

ROLE PLAY: If requested as work week manager to investigate DG A and/or Back-feeding through the Auxiliary Transformer respond as directed but delay.

EVALUATORS CUE: When ready advance to Events 5 and 6 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 22 of 27 OPERATOR ACTIONS EVENT NUMBERS 8 and 9 Crew Task

Description:

Core spray line break in the Drywell between the RPV and testable check valve resulting in a LOCA and loss of the remaining Core Spray system and failure of the D RHR Pump.

POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR CREW Recognize/Acknowledgerising NOTE: Core Spray Injection valve drywell pressure 12B is failed closed but the open indication is over-ridden to indicate Notify SRO the valve is open.

Diagnose and Report the A CS and A RHR Pumps have no power.

SRO Enter / Direct actions IAW EOP-1 AND EOP-3:

0 Re-start all available drywell RRUs BEFORE torus pressure reaches 10 psig, spray the torus BOP When directed:

0 Re-start all available drywell RRUs Spray the torus using only those pumps not required for adequate core cooling SRO Direct RPV level maintained between 6 and 177 inches by maximizing CRD and injecting SLC and RClC NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 23 of 27

-

POS CANDIDATE N/O COMMENTS ACT IONS/BEHAV IOR

5. SRO WHEN torus pressure exceeds (RHR Pump D is available and RP\

10 psig, direct the following: pressure is too high to inject.)

0 Verify drywell RRUs secured

- ~~

6. BOP When directed: NOTE: As the crew is spraying the drywell with the D RHR Pump the 0 Verify drywell RRUs pump will trip on overload.

secured 0 Spray the drywell 0 Diagnose trip of RHR Pump D.

0 Report RHR Pump D trip to the SRO 0 Directs an A 0 to investigate the trip of the D RHR Pump.

-

ROLE PLAY: As A 0 acknowledge the direction to investigate the trip of the D RHR Pump. Then after the RPV Blowdown report the breaker cubicle appears normal, but has an over-current flag on reaker front.

CREW Recognize HPCl unavailable Only A Core Spray appears available.

SRO Direct RPV level maintained between 6 and 177 inches by maximizing CRD and injecting SLC and RClC If not previously directed; directs lining up all available Alternate Injection Subsystems (EOP-1, Table D)

RO When directed:

0 Maximize CRD (if available)

Inject SLC NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 24 of 27 1 I L Os CANDIDATE ACTIONS/BEHAVIOR N/O COMMENTS I

I/

0 Inject with RClC SRO When RPV level cannot be maintained above 6 directherify at least 2 injection subsystems lined up for injection.

If RHR Pump D has tripped at this point SRO directs lining up all available Alternate Injection Subsystems (EOP-1, Table D)

EVALUATORS NOTE: When RPV water level reaches 6 contact the Control Room as the AO/Maintenance at the A DG and report that starting problem has been corrected and the Lockout and Shutdown Relay have just been reset. (Note the 100 sec timer must time out before the DG A SRO Direct starting the A DG and placing Bus 4 on DG A BOP After the 100 second timer has timed out start DG A and place it on 4KV Bus 4 Lineup ECCS systems and Alternate Injection Subsystems as directed.

CREW With the reactor shutdown Success path is restore RPV water and reactor pressure greater level using EOP-1 than the shutoff head of the EOP-5 RHR SW low pressure systems, initiate CT-2 RPV-ED BEFORE RPV level Send someone to locally start the A reaches -1 9 inches DG.

Standard: Investigate the trip of the D RHR Enter EOP-5 and initiate RPV- Pump and restore the pump.

ED (begin opening valves)

BEFORE RPV level reaches -

48 inches NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

I VY 2009 NRC Scenario 2 Page 25 of 27 CANDIDATE COMMENTS ACT IONS/BEHAVlOR 3EFORE RPV level reaches -

19, enter / direct actions IAW EOP-5:

B Prevent injection from those CS and RHR Pumps not required to ensure adequate core cooling Open all SRVs BOP/ When directed:

RO 0 Prevent injection from those CS and RHR Pumps not required to ensure adequate core cooling 0 Open all SRVs SRO Direct lining up Alternate Injection Systems per EOP-1, APP D RO/ Line up Fire System and/or BOP RHRSW system SRO When RPV pressure drops below shutoff head of low pressure pumps, direct level restored and maintained 127 to 177 inches.

BOP Observe/Recognize Core Spray NOTE: Core Spray Pump 6 starts B low discharge pressure and and appears to be OK. But when thf high flow. injection valves opens the discharge pressure goes low and the flow high Diagnose failure of B Core indicating runout and that the pump i Spray Pump to inject and Core discharging into the break.

Spray line as the potential source of the break.

SRO Direct securing the B Core Spray Pump NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 26 of 27 POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR RO/ Secure the B Core Spray Pump BOP SRO If not previously lined up directs Success path is restore RPV water lining up all available Alternate level using injection Subsystems (EOP-1, Table D) RHR SW Starting the A DG and supplying power to 4KV Bus 4.

investigatethe trip of the D RHR Pump and restore the pump.

-

ROLE PLAY: Provided SRO directed Work Week ManagedMaintenance to investigate the trip of the D RHR Pump report back that the D RHR Pump breaker problem has been corrected the pump may be restarted.

l If reasonable amount of time has elapsed since the SRO directed lining up RHRSW for injection, report that RHRSW is lined up to inject.

24. SRO Direct:

iniect with the D RHR Start and inject Pump.

If DG A is restored inject with A RHR and A Core Spray.

25. BOP/ Start and inject with D RHR RO Pump, A RHR and/or A Core Spray as available.

26. CREW Restores RPV water level EOP-1 above TAF (+6)

CT-3 I1 27. SRo Conducts Crew Brief TERMINATING CUE: RPV water level above TAF (+6 inches) and under control NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 2 Page 27 of 27 OPERATOR ACTIONS ADDITIONAL COMMENTS:

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

wendixD Scenario Outline Form ES-D-1 1 FaciIity: VERMONT YANKEE Scenario No.: 3 Op Test No.: 2009 NRC Examiners: Operators: SRO -

RO -

BOP -

Initial Conditions: 85% power IC-807 A RHR 00s for severe vibration, maintenance is investigating.

r Turnover: RHR Pump A is 00s while maintenance investigates high vibration. It was tagged out on the previous shift; estimated return to service is 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , 7-day LCO due to RHR Pump A 00s (TS 3.5.A.3)

Swap CRD Pumps, place CRD 6 in service and remove CRD A and from service to allow cooling for oil change scheduled for the next shift.

Critical Tasks: 1. When drywell temperature cannot be restored and maintained below 2808F, initiate RPV-ED (and/or anticipate ED and use bypass valves).

2. IF Reactor water level cannot be determined, Enters EOP-6, RPV Flooding, opens all SRVs and commences injection using Shutdown RPV Flooding Systems until the Main Steam lines are flooded. OR

3. Restores RPV water level and containment parameters with Condensate injecting directly into the RPV AND/OR aligns alternate injection systems such as RHR.

~~ ~

Event Malf. No. Event Event Description No. Type*

1 NIA N - RO Swap CRD Pumps, place CRD B in service and remove CRD A SRO and from service 1 2 NIA R - RO R - SRO Raise power using recirculation flow to 92%

H 3 mfFW-28A Feedwater flow transmitter slow failure upscale, causing the crew I - SRO to take manual control of feedwater in order to recover and 50% over 60 stabilize RPV level.

sec rri

_ _ ~

mfRH-01 B (if SRO - TS Call from the Southeast RHR Corner Room that RHR Pump B necessary) lower motor bearing oil indicating sight glass is empty. Tech Specs Sections 3.5 and determine that a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO, requiring a plant shutdown, has been entered.

I Appendix D Scenario Outline Form ES-D-1 I

~

IOR 6 Recirc Pump discharge valve full open indication fails causing the B Recirc Pump to runback to minimum flow.

IOR RRdi042AS7B IOR RRlo042AS7B IRF rfRR-12 mf EDO6A C-RO Trip of CRD Pump B with a loss of 125 VDC Bus 1 (Inops 4 KV C-SRO Bus 3 ECCS equipment). The crew will implement ON 3159, Loss of Bus DC 1. The SS/SRO will review Tech Specs Sections 3.10 TS - SRO and 3.5 and determine that a second 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO, requiring a plant shutdown, has been entered. (STG 04)

~

mfTC-04A I - BOP EPR Oscillations OT 3115, Reactor PressureTransients - Place MPR in service.

I - SRO mf MS-06 M - CREW Main Steam Line Break in the Drywell mfFW-08A Failure of the Reactor Feedwater Pumps and Core Spray Pump A mfFW-086 Injection Valve require lining up Condensate Pumps to restore RPV water level.

mf FW-08C mf CS-03A

L Scenario Event Description NRC Scenario 3 Vermont Yankee 2009 NRC Scenario #3 The crew takes the watch with the plant at 85% power during a plant startup. The crew will be directed to place CRD B in service and remove CRD A and from service to allow cooling for oil change scheduled for the next shift. After the swap of CRD pumps the crew will raise power using recirculation flow to 92% as directed by Reactor Engineering while they determine if a rod pattern adjustment is required.

After the plant has stabilized a feedwater flow transmitter will slowly fail upscale, causing the crew to take manual control of feedwater in order to recover and stabilize RPV level.

When the RPV water level is stabilized a call will come from the Auxiliary Operator in the Southeast RHR Corner Room that the lower motor bearing sight glass is empty and there is evidence of oil leakage along the shaft. The crew must declare the RHR B Pump inoperative and notify maintenance. The SRO will enter Technical Specification and declare a 24 hr LCO IAW TS 3.5.A.6. After the Technical Specification is entered, the crew briefed and actions are under way to remove the pump from service the B Recirc Pump discharge valve full open indication fails causing the B Recirc Pump to runback to minimum flow. This will require entering OT 3176 and tripping the B Recirc Pump. The crew must respond to pump trip and stuck open Recirc Pump Discharge Valve.

The operating B CRD Pump will trip concurrently with a failure of 125 VDC Bus 1. The crew will implement ON 3159, Loss of Bus DC 1. The SRO will review Tech Specs Sections 3.10 and 3.5 and determine that another 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO, exists. The crew will enter and take actions IAW ON 3159 including directing the crew to manually trip equipment associated with DC-1 (Main Turbine, Recirc MG Field Breakers). When the crew has completed the walkdown of the panels an EPR oscillation will occur; the crew will enter OT 31 15, Reactor Pressure Transients and place MPR in service. If a reactor scram is required or occurs. Control power will be transferred for 4 KV Bus 1 and the crew may recover 4 KV Bus 1.

After the crew has addressed the initial portions of the loss of DC-1 a Main Steam Line Break will occur in the Drywell. The break size will raise Drywell Temperature and because of the previous malfunctions there will be no immediately available systems to spray the drywell. This will raise drywell temperature and pressure to the drywell temperature limit (280°F). The crew may anticipate emergency depressurization and depressurize with the Turbine Bypass Valves (TBVs). If TBVs are not used the crew must enter EOP-5 and emergency depressurize with the SRVs (Critical Task).

If TBVs are used for depressurization then RPV pressure could be lowered to 0 psig. If this occurs with the Drywell at elevated temperatures then RPV water level instruments may become inoperable and the crew must enter RPV Flooding. If RPV Flooding is required the scenario ends when the crew has positive indication of flooding the reactor up to the Main Steam Lines and Primary Containment Parameters are under control (Critical Task).

If SRVs are used then RPV pressure will remain above the saturation pressure for elevated Drywell temperatures. When Emergency Depressurized with the SRVs, the Reactor Feedwater Pumps will trip on High RPV water level and cannot be restarted. Also, the Core Spray Pump A Injection Valve will fail closed. These failures will require lining up Condensate Pumps to

L Scenario Event Description NRC Scenario 3 restore RPV water level. The scenario is ended when Primary Containment parameters and reactor water level are trending to normal levels (Critical Task).

Critical tasks are: Emergency depressurize the drywell when drywell temperature cannot be restored and maintained below 280°F, If the RPV water level instruments become inoperable, flood the reactor to the Main Steam Lines OR Use alternate injection systems to restore RPV water level following the emergency depressurization. The RHR Pump B or Alternate Spray systems will used to control Primary Containment Parameters.

VY 2009 NRC Scenario 3 Page 5 of 30 SIMULATOR EVALUATION GUIDE Evaluators: Crew:

SM SRO RO BOP STA Senior Management Observer Critical Task Performance: SAT UNSAT (Circle One)

Lead Evaluator:

Signature Date Administered:

Activity Code:

Prepared by: Date:

Reviewed by: Date:

Approved by: Date:

VY 2009 NRC Scenario 3 Page 6 of 30 CREW BRIEF:

-Power level: 85%

In OP 0105, Phase 48, Step 23 is completed

-Rod Sequence: Rapid Shutdown -Rod Group: 20

-Equipment out of service and/or tagged or abnormalities:

1. A RHR Pump OOS, tagged out for Maintenance investigation yesterday at 1600.

The plant entered a 7-day LCO (TS 3.5.A.3).

-Reason For Equipment out of Service or tagged:

1. A RHR Pump 00s for severe vibrations during surveillance testing.

-Applicable Tech Spec LCOs:

1. Seven (7) day LCO, TS 3.5.A.3 EOOS Color:

Yellow 1.47 E-5

-Plant evolutions in progress/Scheduled Shift Evolutions:

1. Place CRD 8in service and remove CRD A and from service to allow cooling for oil change scheduled for the next shift.

2. Continue power ascension to 100°/o power, during this shift raise power to 92%

using recirculation flow then allow 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months soak while RE determines if a rod pattern adjustment is necessary.

VY 2009 NRC Scenario 3 Page 7 of 30 SCENARIO

SUMMARY

TERMINATING CONDITION(S):

1. RPV flooded and/or RPV Water Level and Primary Containment parameters under control.

REFERENCES:

1. OP 21 11, CRD System

2. OP 01 05, Reactor Operations

3. OT 31 15, Reactor Pressure Transients

4. OT 31 10, positive Reactivity Insertion

5. OT 31 13 Reactor Low Level

6. OT 31 76,Recirculation Pump Runback Due to Low Feedwater Flow or Discharge Valve Not Full Open

7. ON 3159, LOSSOf DC-1

8. ON 3145, Loss of CRD Regulating Function

9. OT 3100, Reactor Scram

10. Technical Specifications

11. EOP-1, RPV Control

12. EOP-3, Primary Containment Control

13. EOP-5 Emergency Depressurization

14. Possibly EOP-6, RPV Flooding

15. OE 3107, EOP Appendices

16. RP 21 70, Condensate System

17. OP 2172, Feedwater System

VY 2009 NRC Scenario 3 Page 8 of 30 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set UP: 85% Power

1. IC-807 Discretionarv Distracter Malfunctions/RFs/lOs:

No.

1. IOR MF/RF/IO # Severity

-

Ramp REM#

Pre-insert I Act.Time Description Override the A Core Spray CSdi0314ASlA Injection Valve CLOSED

2. rnfCS-03A Pre-insert CS-12A Fails to Auto Open

3. rfRH-11 Open Pre-insert I RHR Pump A ACB

4. mfFW-28A 50% 60 "A"Feedwater transmitter slowly fails to a higher indicated flow

5. IOR Recirc "B" Runback RV-53B, RRlo042AS7B-1 Recirc Discharge Valve, drifts off open seat IOR RRdi042AS7B IOR RRlo042AS7B IRF rfRR-12

6. mfRD-01 B 3 CRD Pump B Trip

7. mf ED-O6A 3 Loss of 125 VDC Bus 1

8. mfTC-04A 75% Pressure Reg Oscillations WR)

9. mfMS-06 0.5 120 Main Steam Line Break in the Drywell

10. mfMS-06 3 120 After Main Steam Line Break in the scram Drywell actions carried out ~ ~

11. mfFW-08A Trip of all RFPs mfFW-08B mfFW-08C mfRH-01 B "B" RHR PUMP BKR TRIP This trip will be necessary if the crew starts pump to feed the RPV.

VY 2009 NRC Scenario 3 Page 9 of 30 SIMULATOR OPERATOR INSTRUCTIONS (Continued)

Additional Instructions:

1. Place a Danger Tag on RHR Pump A control switch

2. If contacted as Work Week Manager / I&C concerning the Feedwater flow transmitter failure, delay determining the cause; no reason will be given before the scenario terminates.

3. If A 0 is directed to trip "A" Recirc MG locally, insert Remote rfRR-15.

4. If A 0 is directed to trip "A" Recirc MG Field Bkr, insert Remote rfRR-17.

5. When electrical maintenance is sent to investigate the loss of DC-1, report that the A charger and the battery breakers have tripped. Maintenance will work with the A 0 to determine when it is possible to transfer bus control power to alternate sources.

6. If an A 0 or maintenance is directed to strip DC-1 wait a few minutes and report that the bus has been stripped.

7. An A 0 may be directed to shift control power for Buses 1, 3 & 8 to alternate. This action should be delayed for buses 3 & 8 until RPV-ED.

Maintenance troubleshooting is NOT complete on Buses 3 and 8.

8. When repowering Bus 1 use rfRR-21A relay reset and rfED-01 for Bus 1 control power to prevent tripping the Recirc Pump.

9. If directed to secure Recirc Pump Seal Purge, use rfRD-11 and rfRD-12.

10. If contacted as Work Week Manager / I&C concerning the pressure regulator failure, delay determining the cause; no reason will be given before the scenario terminates.

VY 2009 NRC Scenario 3 Page 10 of 30 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Swap CRD Pumps, place CRD 6 in service and remove CRD A and from service POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR SRO Directs performance placing CRD B in service and removing CRD A irom service IAW OP 2111, Sect. U.

SRO Briefs crew RO Calls A 0 and requests they monitor the CRD pump Starts CRD pump 1B.

Check that operating parameters have stabilized and readjust as required.

Secure CRD pump 1A.

Check that operating parameters have stabilized and readjust as required.

Check charging header pressure at 1420-1470 psig (Pl-3-234).

If required, throttle CRD-36B to maintain required pressure.

Report that CRD B is in service and CRD A has been removed from service NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 11 of 30 0PERAT0 R ACTIONS EVENT NUMBER 2 Crew Task

Description:

Raise power using recirculationflow to 92%

=

POS CANDlDATE ACT IONS/BEH AVlO R Direct RO to raise reactor power s u No I COMMENTS SRO using control rods and recirculation flow at 1% power every three minutes RO Contact and inform IS0 NE/VELCO of power increase Raise power as directed using control rods and recirc flow at 1%

power every three minutes BOP Contact and inform plant personnel of power increase (Chemistry, RE)

Contact Rx Bldg A 0 to monitor recirc lube oil temperatures if required Monitors plant parameters and reports to crew E PLAY: Respond as A 0 when directed to monitor and/or adjust Recirc MG Set oil NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 12 of 30 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

Feedwater flow transmitter slow failure upscale will occur, causing the crew to take manual control ot feedwater in order to recover and stabilize RPV level.

POS. CANDIDATE N10 COMMENTS ACTIONS/BEHAVIOR CREW RecognizeIAcknowledge NOTE: Crew may notice level failure-Annunciator: from instruments on the 9-5 Panel prior to the annunciator.

5-E-1, RX LEVEL HI/LO Diagnose lowering reactor water level; inform SRO

2. RO Determine that lowering level is a result of a failure of the Feedwater Controller and shift the controller to MANUAL; inform SRO

3. SRO Enter and direct actions IAW OT 3113 (Reactor Low Level):

0 Shift the FW Master Level Controller to MANUAL e Restore water level to pre-transient level

-

4. RO When directed:

Observe Steam Flow and Feed Flow indications for mismatch Restore water level to pre-transient level Gives RPV water level updates

5. RO Identify/Report the cause of the problem as the Feedwater Flow Transmitter A failing upscale NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 13 of 30 I CANDIDATE ACT IONS/BEHAVlOR

- - - - -

S U N/O COMMENTS SRO Request Work Week Manager/Maintenance/I&C investigate problems with Feedwater Flow Summer I

ROLE PLAY: If contacted as Work Week Manager / I&C concerning the Feedwater flow transmitter failure, delay determining the cause; no reason will be given before the scenario terminates.

7. SRO Direct the RO to switch to single element and restore the controller to automatic

8. RO Transfer control to single element Transfer the controller to automatic

9. SRO Conduct a crew brief EVALUATORS CUE: When Feedwater is returned to automatic and crew briefed or when directed to Event 4.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 14 of 30 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

Oil Leak o n RHR Pump B POS. CANDIDATE S U N/O COMMENTS ACTIONS/BEHAVIOR CREW SRO I Repeat back the communication and inform SRO May direct the A 0 to post the area with a slip sign and wipe up the oil. actions Contact the Work Week Manager/Maintenance/I&C to investigate the loss of oil on the B RHR Pump Enter T.S. 3.5.A.6 which requires initiating a reactor shutdown and being in cold shutdown in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Directs BOP to place the B RHR Pump in PTL I

Role Play: As Maintenance contact the Control Room or answer if contacted that you will investigate the leak. Then within two minutes report that the RHR B Pump can be repaired within an hour

3. BOP Places the B RHR Pump in PTL

4. SRO Conduct a crew brief 1 EVALUATORS CUE: When TS is entered or when directed go to Event 5.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 15 of 30 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

B Recirc Pump discharge valve full open indication fails causing the B Recirc Pump to runback tc 4 minimum flow.

-

1.

POS CREW CANDIDATE ACTIONS/BEHAVIOR Recognize/Acknowledge COMMENTS Annunciators Diagnose Runback of the B Recirc Pump Diagnose that the 6Recirc Pump Discharge Valve RV-53B Does NOT indicate full open.

-

2. SRO Direct entry into OT 3176 Direct pushing PB-2 to lower RPV level setpoint Direct Tripping the B Recirc Pump.

Directs NOT to close RV-53B Directs closing RV-43B to prevent reverse rotation.

May enter OT 31 18, Recirculation Pump Trip

3. RO Pushes PB-2 to lower RPV level setpoint to 155 inches Trips the B Recirc Pump MG Set Drive Motor Breaker.

Verifies Recirc Pump Disc Bypass Valve RV-546 is open Closes Recirc Pump Suction LNOTES:

ValveRV-43B

1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 16 of 30 POS CANDIDATE ACTIONS/BEHAVIOR N/O COMMENTS

4. RO Determines if plant operation is above the MELLLA boundary on the power to flow map per Figure 2.4-1 and outside the Exclusion and Buffer Regions Notifies SRO

5. SRO Directs using the Rapid Shutdown Sequence to insert control rods until operation is below the MELLLA boundary and/or outside the Buffer Region and to lower power to less than 45%.

6. RO Starting with the last rod in the last group of the Rapid Shutdown Sequence, insert control rods in reverse order.

7.

Notifies Reactor Engineering.

SRO May direct removing the third reactor feed pump from service per the guidance in OP 0105, Reactor Operations, Section 5.A.

a. BOP Verifies the A Recirc Pump is operating 170% rated speed.

-

9. BOP Monitors Recirc Pump and Motor Currents Recirc Pump Motor (max 333 amps).

Recirc MG Set Motor (max 450 amps).

Dispatch the RBAO to monitor and adjust RR Lube Oil cooling NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 17 of 30 POS CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS lo. SRO Conduct Crew Brief 1 EXAMINERS CUE: Insert Event 6, Loss of DC Bus 1 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 18 of 30 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Loss of CRD Pump B and 125V Bus DC-1.

POS CANDIDATE COMMENTS ACT IONS/BEHAVI0R CREW Recognize/Acknowledge Annunciators:

CRD PUMP B TRIP (9-C-1)

DC-l/DC-2 BKR TRIP (8-N-1)

BATT VOLTAGE LO (8-P-1)

GEN LOSS OF FIELD TRIP (7-c-4)

MG SET A SCP TUBE LOCK (4-8-1) 86 GP DC LOSS (7-A-6)

BUS 3 CTRL PWR LOSS (8-J-7)

Diagnose and report the loss of CRD Pump B Diagnose and report the loss of 125 VDC Bus 1 SRO Direct entry into ON 3145, Loss of CRD Regulating Function Direct entry into ON 3159.

Direct tripping the RWCU Pump BOP Trip the RWCU Pump SRO Direct starting the A CRD Pump.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 19 of 30 POS CANDIDATE N/O COMMENTS ACTIONS/BEHAVIOR RO NOTE: IF CRD pumps are out of Place CRD SYSTEM FLOW service for > 2 minutes, secure recirc CONTROL station in pump seal purge MANUAL.

Adjust the flow controller to zero Start CRD pump 1A Adjust the CRD flow controller to establish 48-52 gpm Balance the CRD flow controller, and then place in BAL or AUTO.

If required, throttle CRD-36A to maintain charging header pressure at 1420-1470 psig Restore recirc pump seal purge to service.

SRO Dispatch operators to manually tripkheck open all breakers on DC-1 per ON 3159.

SRO Request Work Week Manager/Electrical Maintenance concurrence on transferring control power.

Notify Chemistry that RWCU is secured and the need for sampling.

ROLE PLAY: Respond as personnel contacted.

When electrical maintenance is sent to investigate the loss of DC-1, report that the A charger and the battery breakers have tripped. Maintenancewill work with the A 0 to determine when it is possible to transfer bus control power to alternate sources.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 20 of 30 l I I CANDIDATE ACTIONS/BEHAVIOR I s (v N/O I COMMENTS

8. BOP Contact A 0 and direct them to check the RWCU Demineralizers and Holding Pumps I ROLE PLAY: As A 0 respond as directed but delay reporting back to the Control Room on the RWCU Demineralizers.

9. SRO Direct BOP to transfer control power for Busses 1,3, 8 and the DG.

10. BOP Direct the A 0 to transfer DC control power for the Buses 1, 3 and 8 to Alternate.

1 ROLE PLAY: As the A 0 acknowledge direction.

Dispatch an A 0 to monitor and adjust RR Lube Oil cooling I /

ROLE PLAY: Respond as A 0 when directed to monitor and/or adjust Recirc MG Set oil temperatures.

SRO Brief the crew and direct the crew to manually trip the Turbine per ON 3159 if a turbine trip is I I required.

BOOTH OPERATOR: Shift 4Kv Bus 1 Control Power to Alternate ROLE PLAY: As the A 0 report that you have shifted control power for bus 1 to alternate.

Maintenance troubleshooting is NOT complete on buses 3 and 8.

ROLE PLAY: As Electrical Maintenance report that Bus 1 control power can be restored, but that you are still working on Buses 3 and 8.

1 EXAMINERS CUE: When ready, insert Event 7, EPR Oscillations NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 21 of 30 OPERATOR ACTIONS EVENT NUMBER 7 Crew Task

Description:

EPR Oscillations CANDIDATE N/0 COMMENTS ACTIONS/BEHAVIOR Recognize oscillating reactor pressure Enters OT 3115.

Diagnose/Announce EPR failure Enter and direct actions IAW OT 31 15 (Reactor Pressure Transients):

0 Place the EPR in CUTOUT 0 Verify that the MPR has control 0 Lower MPR setpoint as necessary When directed:

Place the EPR in CUTOUT at peak pressure 0 Verify that the MPR has control 0 Lower MPR setpoint as necessary.

Direct BOP to restore pressure to the pre-transientpressure.

When directed, adjust MPR to adjust pressure to pre-transient level.

Direct crew member to contact I&C to check and repair EPR.

May enter OT 31 10, positive Reactivity Insertion Notifies RE NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 22 of 30 I I I CANDIDATE ACTIONS/BEHAVIOR Week Manager / I&C, inform them P

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 23 of 30 OPERATOR ACTIONS EVENT NUMBER 8 Crew Task

Description:

Main Steam Line Break in the Drywell.

'Os I CANDIDATE ACTIONS/BEHAVIOR Is COMMENTS CREW Recognize and inform the SRO of rising Drywell Pressure and reactor scram SRO Enter and direct crew actions IAW OT 3100.

May enter OT 31 10 CREW 1 Report All Rods inserted SRO Enter EOP-1 and EOP-3 and direct actions to control RPV level and pressure and containment SRO Direct the RO to maintain level 127" to 177".

RO When directed, maintain level between 127" and 177".

SRO Direct pressure stabilized between 800-1000 using Bypass Valves.

SRO Direct the BOP to maximize drywell cooling.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 24 of 30

~ _ _ _ _ _ _

POS CANDIDATE N/O COMMENTS ACTIONS/BEHAVIOR

~ ~

-

BOP When directed, attempt to starhestart all available drywell RRUs.

SRO Direct the RO/BOP to backup all appropriate PClS group isolations.

RO/ When directed, backup BOP appropriate PClS group isolations.

SRO Direct the BOP to spray the torus

~~ ~ ~

BOP Attempt to spray the Torus, report the there are no RHR Pumps available CREW When drywell temperature cannot be restored or EOP-3 maintained below 2802F, EOP-5 initiate RPV-ED (or anticipate ED and use bypass valves)

CCT-1 Standard:

RPV-ED initiated prior to exceeding 280". may use bypass valves in anticipation of ED.

SRO May anticipate emergency depressurization and direct use of Bypass Valves Directs defeating PClS Group I isolation interlocks (Main Steam high steam flow not in RUN)

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 25 of 30 Os I CANDIDATE ACTIONS/BEHAVIOR U N/O COMMENTS Defeats PClS Group I isolation interlocks (Main Steam high steam flow not in RUN) OE-3107, Section CC SRO Direct the RO/BOP to terminate and prevent injection from CS and RHR pumps.

May OPEN bypass valves as necessary to depressurize the RPV using the Bypass Valve Opening Jack.

SRO Enter and direct crew actions IAW EOP-5, RPV-ED.

SRO Direct the RO/BOP to terminate and prevent injection from CS and RHR pumps.

RO/ When directed, place CS and BOP RHR pumps in PTL.

SRo RO/

I Direct RO/BOP to open all SRVs.

When directed, opens all SRVs.

BOP 9 after Alternate Emergency Depressurization or EOP-5 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 26 of 30 OPERATOR ACTIONS EVENT NUMBER 9 Crew Task

Description:

Failure of the Reactor Feedwater Pumps and Core Spray Pump A Injection Valve require lining up Condensate Pumps to restore RPV water level.

CANDIDATE COMMENTS ACTIONS/BEHAVIOR I

IF the RPV was depressurized using BPVs Drywell temperature may be above saturation temperature for reactor pressure. RPV Level indication is not reliable Enters EOP-6 RPV Flooding IF NOT PROCEED TO STEP 7.

Direct BOP to close or check closed MSIVs, main steam line drains, RClC isolation valves.

Closes or checks closed MSIVs, main steam line drains, RClC isolation valves.

IF Reactor water level cannot be determined, Enters EOP-6, opens all SRVs and refloods the RPV to the Main Steam Lines NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 27 of 30 SRO Direct RO to commence and increase injection into the RPV to establish the Main Steam Lines Flooded as indicated by

1. SRV Tailpipe Temperatures decreasing

2. Increasing RPV pressure

3. SRV Tailpipe Temperature Pressure Switches.

I RO When directed, commence and and/or increase injection into the RPV with Shutdown RPV Flooding BOP Systems - EOP-6 Table T (Include - Core Spray, Condensate/Feedwater, CRD, and RHR).

scenario CREW IF the RPV was depressurized using SRVs or EOP-6 was not required continue HERE.

Diagnose trip of operating Feedwater Pumps Notify SRO/CREW SRO Direct AO, Work Week Manager, Maintenance to investigate the loss of Feedwater Pumps.

Direct injection with the A Core Spray System BOP Lineup the A Core Spray System for injection Report failure of CS Injection Valve to open NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 28 of 30

11. SRO Directs crew to line up as many Alternate Injection Subsystems as possible EOP-1, Table D.

12. RO Lines up Condensate IAW RP 2170 and/or OP 2172 May also initiate lineups on other Alternate Injection Systems.

13. CREW Restores RPV water level with Condensate injecting directly CT-3 into the RPV OR aligns alternate EOP-1 injection systems.

used.

-

14. SRO Direct securing RRUs 0 Recirc Pumps 0 Placing RHR Pump B in Containment Spray.

-

15. RO/ Verifies shutdown BOP RRUs 0 Recirc Pumps Places RHR Pump B in Containment Spray and manually opens spray valves.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 29 of 30 II CREW Restores Containment parameters using the Alternate CT-3 Systems and manually opens EOP-3 the RHR-RHRSW Valve 183 or RHR Pump B and manually opens the injection valves.

CUE: RPV flooded and/or RPV Water Level and Primary Containment parameters undd control.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 3 Page 30 of 30 OPERATOR ACTIONS ADDITIONAL COMMENTS:

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

\

[ Appendix D Scenario Outline Form ES-D-1 I Facility: VERMONT YANKEE Scenario No.: 4 Op Test No.: 2009 NRC Examiners: Operators: SRO -

RO -

BOP -

IInitial Conditions: 80% power (A and C RFP in service)

" C RHR 00s for severe vibration maintenance is investigating.

Turnover: RHR Pump "C" is 00s while maintenance investigates high vibration. Tagged out on previous shift; estimated return to service is 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , 7-day LCO due to RHR Pump "C" 00s (TS 3.5.A.3)

Perform VYOPF 4120.02, HCI Valve Tests for HPCl Steam Isolation Valves 15 and

16. HPCl Valve surveillance is due.

Critical Task: 1. During an RPV Blowdown with the reactor not shutdown under all conditions perform power/level control TERMINATE AND PREVENT INJECTION into the RPV using appendix GG, until conditions are met to re-establish injection.

2. During an ATWS with a steam leak in the Secondary Containment and two areas exceeding MAX SAFE Emergency Depressurize.

3. After Emergency Depressurizationrestore and maintain RPV water level +127 to

+177 inches.

Event Malf. No. Event Event Description No. Type*

1 N/A Bop Perform VYOPF 4120.02, Valve timing on HPCl Steam Isolation

- SRo Valves 15 and 16. (TS) 1 2 NIA R - RO Lower power to remove the " A Condensate Pump from service R - SRO 3 mfRD-021423 E 1 g:o While inserting control rods a control rod will stick in the core after moving a notch, CRD drive pressure must be raised to move rod (ON 2143).

mfFW-16A '- -

I RO SRo TS SRO Failure of the controlling reactor water level instrument LI-6-94A, will result in a lowering reactor water level (OT 3113) and a TS entry.

I - BOP Failure of the Refuel Floor High Radiation Monitor. RP and I & C mfRM-olP I - SRO (100%) will immediately repair (After TS Call) The crew must restore the TS - SRO GP 3 isolation. (TS) l I Appendix D NUREG 1021 Revision 9

I Appendix D Scenario Outline Form ES-D-1 1 mfMC-08 C - BOP Respond to loss of condenser vacuum /Off -gas explosion 10% at 120 C - SRO sec.

mfOG-03A mfHP-09 M - CREW HPCI Steam Line Leak upstream of HPCI-14, this will result in 25% at 450 Emergency Depressurization as Reactor Building temperatures in sec two areas are above Max Safe. Crew may anticipate RPV-ED.

mfPC-1HP15 C-RO HPCI-15 and 16 will fail to isolate and four control rods fail to insert mfPC-1HP16 during the scram. Entry into EOP-2 should have occurred earlier mfRD-020615 on the scram caused by the loss of vacuum.

mfRD-020611 mfRD-021011 mfRD-021015 C - SRO I

Appendix D NUREG 1021 Revision 9

Scenario Event Description NRC Scenario 4 Vermont Yankee 2009 NRC Scenario #4 The crew takes the watch with the plant at 80% power and RHR Pump C is 00s.

Immediately after turnover the crew is directed to perform VYOPF 4120.02, valve timing on HPCl Steam Isolation Valves 15 and 16. This places the plant in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO, TS 3.5.E.3 Once the Tech Spec is identified, the valves tested and the system returned to operability the crew is directed to remove the A Condensate Pump from service. Crew must lower power to insure that RFP suction pressure is greater than 450 psig. When the operator attempts to insert a control the control rod will not move. The crew must enter the stuck rod procedure ON 3143.

When the crew raises CRD drive water pressure the control rod will move. After verifying that the control rod is operable the crew will resume lowering power, then a failure of the controlling reactor water level instrument LI-6-94A, will result in a lowering reactor water level (OT 31 13) and a TS entry. After the level instrument is addressed the power reduction will continue and the crew will remove the A Condensate Pump from service.

After the Condensate Pump has been removed from service and the crew has been briefed the Refuel Floor High Radiation Monitor will fail upscale (INOP). The crew will take immediate actions and the SRO will enter T.S. 3.2.3. I & C/Radiation Protection will quickly repair the instrument and restore the Radiation Monitor to service. The crew will take actions to reset the group three isolation, restore Reactor Building HVAC and secure SBGT.

As the crew is recovering from the Group three isolation a pocket of Hydrogen Gas will ignite and cause a rupture of the Off-Gas Rupture Diaphragm and subsequent loss of Vacuum.

Reactor power may be lowered in an attempt maintain vacuum, however vacuum will deteriorate to where a reactor scram is required. When the reactor is scrammed, four control rods remain stuck in the core requiring entry into EOP-2. Even though APRMs are downscale they must take EOP-2 actions to terminate and prevent injection (Critical Task). After the scram a HPCl steam line break will occur, requiring the crew to take actions IAW ON 3158, EOP-4.

With the steam leak in the Reactor Building the crew will attempt to manually close HPCl 15 and 15, however HPCI-15 / 16 will fail to close. As temperatures continue to rise two areas will exceed Max Safe which will require RPV-ED IAW EOP-5 (Critical Task). Because of the previous loss of vacuum the Main Condenser will not be available.

Following the RPV-ED the crew must take action to restore and control RPV water level IAW EOP-2 (Critical Task).

Critical tasks are: Emergency depressurize when above the Max Safe limit in two or more areas and terminate and prevent injection and restore and control RPV water level following emergency depressurization.

Appendix D NUREG 1021 Revision 9

I VY 2009 NRC Scenario 4 Page 4 of 25 SIMULATOR EVALUATION GUIDE Evaluators: Crew:

SRO SRO RO BOP

~~

STA Senior Management Observer Critical Task Performance: SAT UNSAT (Circle One)

Lead Evaluator:

Signature Date Administered:

Activity Code:

Prepared by: Date:

Reviewed by: Date:

Approved by: Date:

Appendix D NUREG 1021 Revision 9

VY 2009 NRC Scenario 4 Page 5 of 25 CREW BRIEF:

-Power level: 80%

-Rod Sequence: Rapid Shutdown Sequence Latched -Rod Group: 21 (EOC)

-Equipment out of service and/or tagged or abnormalities:

1. C RHR Pump OOS, tagged out for Maintenance investigation yesterday at 1600.

-Reason For Equipment out of Service or tagged:

1. RHR Pump C 00s for severe vibrations during surveillance testing.

-Applicable Tech Spec LCOs:

1. Seven (7) day LCO, TS 3.5.A.3

2. Tech Spec LCO 3.5.E.3 has been entered for the performance of OP 4120, Sections 8.24 through 28 (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO)

EOOS Color:

Green 3.12 E-6

-Plant evolutions in progress/Scheduled Shift Evolutions:

1. Immediately after shift turnover perform OP 4120, Sections 8.24 through 28 (Valve timing on HPCl Steam Isolation Valves 15 and 16) to verify their operability.

2. After completing the HPCl Surveillance remove the A Condensate Pump from service for a inspection of the motor. A tagout will be developed later.

Appendix D NUREG 1021 Revision 9

VY 2009 NRC Scenario 4 Page 6 of 25 SCENARIO

SUMMARY

TERMINAT1NG CONDIT10N(S):

1. RPV depressurized and reactor water level under control.

REFERENCES:

1. OP 4120, High Pressure Coolant Injection System Surveillance

2. RP 2170, Condensate System

3. OP 0105, Reactor Operations

4. ON 2143, Stuck Control Rod

5. ARS 21003 (9-5) Annunciators

6. OT 31 13, Reactor Low Level

7. ON 3153, Excessive Radiation Levels

8. OP 21 17, Standby Gas Treatment

9. AP 0156,Notification of Significant Events

10. OT 3120, Condenser High Back Pressure

11. ON 3151, Off-Gas Explosion

12. OT 3100, Reactor Scram

13. ON 3158, Reactor Building High Area Temperaturewater Level

14. EOP-2

15. EOP-4

16. EOP-5

17. Technical Specifications Appendix D NUREG 1021 Revision 9

VY 2009 NRC Scenario 4 Page 7 of 25 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set UP: 80% Power

1. IC-808

2. Verify Feedwater Pump B is secured.

3. The next rod to be inserted is 14-23 Discretionarv Distracter Malfunctions/RFsAOs:

1. rfNM-71-76 All APRM Gain adjusts made to get APRM GAFs in spec (modeled to the plant at 100%): 71 (1.385), 72 (1.448), 73 (1.378), 74 (1.383), 75 (1.287) 76 (1.375)

I Severity I I REM# I G

No. MF/RF/IO# Ramp Act. Time Description

1. rfRH-13 I Pre-insert I RHR Pump C Breaker

2. mfRD-020615 Pre-insert Stuck Control Rods 06-15,06-11 mfRD-020611 10-15, 10-11 mf RD-021015 mfRD-021011

3. Stuck Control Rod 14-23

4. mfRN-16A 100% 180 2 Failure of water level instrument LI-6-94A

5. mfRM-01 P 100% 3 Failure of the Refuel Floor High Radiation Monitor High

6. mfMC-08 10% 120 4 Condenser air in-leakage mfOG-03A 4 Off-Gas Sys A Explosion

7. mfHP-09 HPCl Steam Line Leak mfPC-1 HP15 upstream of HPCI-14 mfPC-1 HP16 HPCI-15 and 16 will fail to isolate Appendix D NUREG 1021 Revision 9

VY 2009 NRC Scenario 4 Page 8 of 25 SIMULATOR OPERATOR INSTRUCTIONS (Continued)

Additional Instructions:

1. Place RHR Pump C in PTL and Danger Tag its control switch

2. Reactor Feedwater Pump B must be secured at the beginning of the scenario.

3. After the HPCl MSlVs test is completed or when directed by the chief examiner call the Control Room as Maintenance and request that the A Condensate Pump be removed from service.

4. During Event 3, Stuck Control Rod; when CRD Drive pressure has been raised by 10 - 50 psig delete the malfunction to allow the rod to move.

5. The Level Instrument failure will be investigated, with no cause being found for the duration of the scenario.

6. As RP and/or I & C notified about the refueling floor rad monitor respond that the detector was bumped by a piece of equipment that was being moved and that a loose connection was found and repaired. Request they reset the monitor, re-start RB HVAC and secure SBGT to preserve the current filters.

7. When requested as AO/RP to investigate / conduct surveys in the Reactor Building, inform the Control Room that there is loud noise and steam in the HPCl Room.

0. If requested as Maintenance to attempt local closure of the HPCI-15 and 16 valves, report reactor building entry cannot be made at this time due to temperatures and the steam environment. The valves will remain open for the duration of the scenario.

Appendix D NUREG 1021 Revision 9

VY 2009 NRC Scenario 4 Page 9 of 25 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Perform OP-4120, Sections 8.24 through 28 (Valve timing on HPCl Steam Isolation Valves 15 & 16)

POS. CANDIDATE COMMENTS ACTIONS/BEHAVIOR

1. SRO Directs performance of Test IAW OP 4120, Sect. B.

2. SRO Briefs crew on the test Enter Tech Spec LCO 3.5.E.3, 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO for the performance of OP 4120, Sections 8.24 through 28

3. BOP Obtains and reviews procedure OP 4120 Section B and checks prerequisites.

4. BOP Close and time STEAM NOTE: May use two Stop ISOLATION HPCI-15, record time Watches Close between 30.49 to 41.25 secs.

5. BOP Open and time STEAM ISOLATION Open between 31.1 3 to 42.1 1 HPCI-15, record time secs.

6. BOP Close and time STEAM Close between 32.44 and 43.88 ISOLATION HPCI-16, record time secs.

7. BOP Open and time STEAM ISOLATION Open between 33.29 and 45.03 HPCI-16, record time secs.

8. BOP Notify the crew that OP 4120, Sect.

B. steps 24 through 28 are completed.

L-NOTES:

RO Verifies correct switch positions

1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 10 of 25 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

I VY 2009 NRC Scenario 4 Page 11 of 25 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

Remove Condensate Pump A from service.

-- POS CANDIDATE ACT IONS/BEHAV IOR U I N/O I COMMENTS

1. CREW Acknowledge request from maintenance to remove the A Condensate Pump from service

2. SRO Direct actions IAW OP 0105, Phase 5, Step 17 and RP 2170, Sect. J, Securingflripping of a Condensate Pump at Power 0 Conduct a Crew brief on removing the Condensate Pump from service.

0 Lower reactor power to 5 80 percent (40% per minute) 0 Direct BOP contact VELCO and IS0 New England and notify them of the power reduction ROLE PLAY: As A 0 directed to monitor Recirc MG Set oil temperatures respond as directed.

3. RO When directed, reduce Recirc flow to lower reactor power to I 8 0 percent (at rate directed) until Recirculation Flow is 47.5 - 48 Mlbm/hr When Recirculation Flow is 47.5 - 48 Mlbm/hr notify SRO

4. SRO Directs inserting control rods in the reverse of sequence to lower power feed pump suction pressure is approximately 450 psig NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

I VY 2009 NRC Scenario 4 Page 12 of 25 I POS I CANDlDATEACTIONS/BEHAVIOR I S I U I N/O I COMMENTS EVALUATORS CUE: During this event a Control Rod will become stuck - see the Event 3 for the response

5. BOP Inserts control rods in the reverse of sequence to lower power feed pump suction pressure is approximately 450 psig.

6. SRO When feed pump suction pressure is approximately 450 psig , direct the BOP to secure the "A" Condensate Pump

7. BOP When directed, secure the "A" Condensate Pump Verify Running Condensate Pump amperage is below amber region of current meter.

Direct A 0 to monitor the A Condensate Pump ROLE PLAY: As Turbine Building A 0 report that the check valve is holding that seal leakage is minimal and that the pump is not rotating.

8. SRO Conduct a Shift Brief EVALUATORS CUE: When Condensate pump is secured insert Event 4, Failure of the controlling reactor water level instrument LI-6-94A NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

t VY 2009 NRC Scenario 4 Page 13 of 25 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

While inserting control rods a control rod 14-23 will stick in the core after moving a notch and cannot be moved.

POS. CANDIDATE ACTIONS/BEHAVIOR IS COMMENTS RO Determines control rod 14-23 is stuck and notifies SRO SRO Enters ON 3143 - Stuck Control Rod and directs actions contained in ON 3143 flow chart.

RO 7Takes actions as directed to un-stick control rod per ON 3143 flowchart 0

attempt one notch insert attempt a single notch withdraw 0 determines drive water pressure 0 raises drive water pressure 10-50 Psig 0 attempt to insert control rod one notch (successful) 0 attempt to withdraw one notch (successful) 0 insert rod 14-23 one notch 0 withdraw rod 14-231 one notch return drive water press. to 250-275 0 insert then withdraw rod 14-23 one notch (done twice)

RO 0 Insert then withdraw rod 14-23 one notch (done twice).

-SRO Crew Brief.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 14 of 25 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

Failure of the controlling reactor water level instrument LI-6-94A. T.S. Entry

- POS CANDIDATE COMMENTS ACTIONS/BEHAVIOR 31

1. CREW Recognize/Acknowledge NOTE: Crew may notice level failure Annunciator from instruments on the 9-5 Panel prior to the annunciator.

5-E-1, RX LEVEL HVLO Diagnose level instrument LI-6-94A Failure

-

2. SRO Direct entry into OT 3113, Reactor Low Level Direct Shifting the RX VESSEL MASTER CONTROLLER (FC-6-83) to manual Direct placing VESSEL LEVEL CHANNEL SEL switch to the LI 6-948 channel Direct RO/BOP to contact Work Week Manager / I&C and request they investigate the failure of LI 94A Direct placing RX VESSEL MASTER CONTROLLER (FC-6-83) to auto.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 15 of 25 CANDIDATE COMMENTS ACTIONS/BEHAVIOR Shift the RX VESSEL MASTER CONTROLLER (FC-6-83) to manual Restore RPV water level to the normal band Place VESSEL LEVEL CHANNEL SEL switch to the LI 6-948 channel Return RX VESSEL MASTER CONTROLLER (FC-6-83) to auto When directed, call I&C and ask for assistance to determine problem with LI-6-94A Conduct a Crew Brief EVALUATORS CUE: When Feedwater is stabilized and crew briefed insert Event 5.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 16 of 25 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

Failure of the Refuel Floor High Radiation Monitor. RP and I & C will immediately repair (After TS Cali) the crew must restore the GP 3 isolation.

POS CANDlDATE ACTIONS/BEHAVlOR COMMENTS CREW Recognize/Acknowledge Annunciator:

RX BLDG/REFUEL FLR CH B RAD HI (5-J-1)

Recognize a GP 3 isolation caused by a Refuel Floor Rad Monitor failing upscale.

SRO Direct entry into ON 3153,Excessive Radiation Levels Direct confirming alarm conditions using other RB Rad Indications.

Direct an RP and/or I & C to investigate the Refuel Floor Rad Monitor.

BOP Refer to ARS for Annunciators.

Verify that HVAC isolates and SBGT starts May advise all personnel of potentially high radiation and evacuate Reactor Building.

Request Rad Protection to initiate local surveys.

Monitor radiation levels on other indications.

Refer to ON 3153,Excessive Radiation Levels SRO Direct PClS GP 3 isolation backed UP.

-

NOTES:

~

1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical Task/Step

VY 2009 NRC Scenario 4 Page 17 of 25 r

POS CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS

-

5. BOP Back up PClS GP 3 isolation

6. SRO Time permitting consults Tech Specs 3.2.3.

Enters 3.6.E.2 a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO while the Group 2 isolation Inops the CAM ROLE PLAY: When sufficient actions have been taken and TS identified OR when directed by the Chief Examiner clear the Hi Rad Malfunction mfRNO1P and notify the Control Room that the detector was bumped by a piece of equipment that was being moved and that a loose connection was found and repaired. Request they reset the monitor, restart RB HVAC and secure SBGT to preserve the current filters.

SRO Directs resetting PClS GP 3 isolation IAW OP2115 BOP If an evacuation was directed makes announcement that personnel may re-enter the Reactor Building.

Resets GP 3 Isolation and restores primary Containment lineup IAW OP 21 15 SRO Direct starting RB HVAC and securing SBGT BOP Restarts reactor building ventilation per OP 2192 Secures SBGT train per OP 21 17, Securing SGT Trains After Auto or Manual Start.

SRO I Conduct a Crew Brief I NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 18 of 25 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Respond to loss of condenser vacuum /Off-gas explosion

- POS. CANDIDATE COMMENTS

-CREW ACTIONS/BEHAVlOR Recognize/Acknowledge

~~ ~ ~~~ ~

NOTE: The operators may notice Annunciators: the lowering vacuum and/or high off-gas pressure prior to the COND VAC LO alarm (7H3) Annunciators AOG PRESS HI (6-H-1)

TUBB BLDG RAD HI (3-F-3)

Diagnose lowering condenser vacuum/Off-Gas Explosion Notify the SRO/Crew SRO Enteddirect actions IAW OT 3120, Condenser High Back Pressure and ON 3151, Off-Gas Explosion/

Rupture Disk Failure:

Suspect failure of the SJAE rupture disc.

Because of rapidly lowering Condenser Vacuum may immediately direct Reactor Scam and entry into OT 3100 Direct verifying closed all turbine building outside doors May direct Turbine Building evacuation NOTES: S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

= Critical TasWStep

VY 2009 NRC Scenario 4 Page 19 of 25

~~ ~ ~~~ ~~~ ~~

POS. CANDIDATE N/O COMMENTS ACTIONS/BEHAVlOR

,

CRO May commence a power reduction per OP 0105, until vacuum stabilizes or the plant is shut down Scrams the reactor BOP May dispatch two operators to obtain the correct Radiation Protection equipment and enter the SJAE room and physically inspect the rupture disc for damage.

Direct verifying closed all turbine building outside doors I

LE PLAY: As A 0 directed to enter the SJAE Room respond as directed. As A 0 directed to verify urbine building outside doors respond as directed. Neither of these tasks will be uring - the scenario.

When directed:

0 May shift electrical loads to the Start-up Transformers Trip the Turbine Report four control rods NOT inserted to 00 Direct entry into EOP-2 Directs inhibiting ADS if RPV water level is below Lo-Lo Level When steam flow < 0.5lbm/hr per steam line, place Mode Switch in SHUTDOWN Trip the recirculation pumps and NOTE: Condenser vacuum will enter OT 31 18. continue to degrade.

If directed inhibits ADS NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 20 of 25 individual control rods using OE 3107 Appendix G Directs BOP to install App PP jumpers to bypass MSlV isolation on Lo-Lo Water Level. (9-15 Panel) rods using OE 3107, Appendix G 1 BOOTH OPERATOR: When directed by the Chief Examiner insert HPCl Steam Line Break NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 21 of 25 OPERATOR ACTIONS EVENT NUMBERS 7 & 8 Crew Task

Description:

HPCl Steam Line Leak upstream of HPCI-14, this will result in Alternate or Emergency Depressurization as Reactor Building temperatures in two areas are above max safe.

HPCI-15 and 16 will fail to isolate and four control rods fail to insert during the scram. Entry into EOP-2 should have occurred earlier on the scram with a loss of vacuum.

c1.

POS.

CREW CANDIDATE ACTIONS/BEHAVIOR Recognize/Acknowledge Annunciators:

IS N/O COMMENTS STEAM LEAK DET PANEL TEMP HI (4-H-1)

RX BLDG RAD HI (3-E-3)

Fire Panel Audible Alarm Notify SRO

-

2. SRO Directs entry into ON 3153, Excessive Rad Levels and/or ON 3158, Reactor Building High Area Temperaturewater Level

_. I

3. BOP Enter ON 3153 and/or ON 3158 0 Announce evacuation of the Reactor Building 0 Monitor area radiation levels I Backup Group 3 isolation

-

4. SRO Direct entry into EOP-4 while continuing in EOP-2 I

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 22 of 25 POS. CANDlDATEACTIONS/BEHAVIOR IS IU N/O I COMMENTS BOP 0 Identify rising temps and area rad level in the torus catwalk area 0 Identify HPCl area high temperatures on Allen Bradley; inform SRO 0 Recognize failure of HPCl to isolate; attempt to close valves 0 Report failure of HPCl 15 and 16 to isolate.

SRO 1

Direct BOP to contact Maintenance to investigate failure of HPCI-15 and 16 to isolate.

Direct A 0 / RP to investigate steam leak in the Secondary Containment BOP 0 Stabilize pressure at < 1055 psig using BPVs 0 Contacts Maintenance to investigate failure of HPCI-15 and 16 to isolate.

0 Directs A 0 / RP to investigate steam leak in the Secondary Containment there is steam coming up from the HPCVCRD Room.

Initiate AR I/R PT between -19 to 177 inches using Feed and Condensate NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 23 of 25 POS. [ CANDIDATE ACTIONS/BEHAVIOR

-

N/O COMMENTS SRO Time permitting briefs Crew on plan to E-Depress Determines that a primary system is discharging into the Secondary Containment and two areas are exceeding the same maximum safe operating levels in more than one area.

Directs initiate entry into EOP-5 RPV-ED Directs Terminate and prevent CREW TERMINATE AND PREVENT EOP-2 INJECTION into the RPV using appendix GG CT-1 BOP Verify actions IAW EOP-5:

0 Terminate and prevent injection IAW Appendix GG SRO When injection terminated and prevented, direct all SRVs opened

CREW During an ATWS with a steam leak in the Secondary EOP-5 Containment and two areas CT-2 exceeding MAX SAFE Emergency Depressurize.

Standard:

When directed, open all SRVs SRO When reactor pressure drops below 160 psig, direct level restored and maintained above -1 9 inches and slowly restored using Condensate to between -1 9 and 177 inches NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 24 of 25 POS. CANDIDATE ACTIONS/BEHAVIOR U I N/O I COMMENTS

15. "CREW After Emergency DepressurizationRestore RPV EOP-5 water level. +127 to +177 CT-3 Standard:

When directed, use Condensate to slowly restore level to between -1 9 and 177 inches EVALUATOR: This scenario is completed when the RPV has been depressurized and Feedwater flow is established and RPV water level is above -19 inches.

~~ ~

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2009 NRC Scenario 4 Page 25 of 25 OPERATOR ACTIONS ADDITIONAL COMMENTS:

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

v t e Letter Sequence Draft Other
TAC:U01743, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML090760092, ML090790217, ML090790241, ML090790243, ML090790246, ML090960141, ML090960153
MONTHYEAR2009-02-13 [Table View]

ML090420123: Difference between revisions

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