ML090790246
| ML090790246 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 01/27/2009 |
| From: | Schulze W Entergy Nuclear Operations |
| To: | Todd Fish Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML082600332 | List: |
| References | |
| TAC U01743 | |
| Download: ML090790246 (241) | |
Text
{{#Wiki_filter:JPM-A l a RO Rev. 012309 Page 1 of 6 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Perform the RHR System Valve Lineup Failure Mode: Two mispositioned valves.
References:
OP 2124. Residual Heat Removal System. (Rev. 113) AP 0155, Current System Valve And Breaker Lineup and Identification. ( R t s 78) Task Number: -I-Task Performance: AOIROISRO - ROISRO SRO Only - Sequence Critical: Yes - No 3 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: /- 27-Operations Training Instructor (I/ Date Reviewed by: < SRO ~icensed/~krtified Reviewer
/ 27 Date 07
-3 fl J;I,~~(/& 1 '27.67
,pproved by:
Operations raini id ~ d a ~ e r Date
JPM-A 1a RO Rev. 012309 Page 2 of 6 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 :tep 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. Appendix B, Containment Remote Operated Valve Checklist, of OP 2115, Primary Containmerlt, is completed. Initiating Cues: The CRS directs you to perform pages 1 and 2 of Appendix A, RHR System Valve Lineup, of OP 2 124, Residual Heat Removal System. 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-Ala RO Rev. 012309 Page 3 of 6 lequired Materials: Handout 1 - OP2124, Appendix A (Rev. 113) Handout 2 - AP 0155, Current System Valve And Breaker Lineup and Identification, (Rev. 78) A Danger Tag with a Tag Number on it. Simulator Set-UP: 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 OP 21 LO.. Lined up SBGT on Containment Air Purge in accordance with OP 2115 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 ValveISwitch positions ONLY, the Simulator doe.; 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 <he task to be evaluated. This JPM should be conducted simultaneously with A4 SRO. JPM-A 1a RO
JPM-A l a RO Rev. 012309 Page 4 of 6
'rovide Candidate with Initial ConditionsICue (Last Page of this JPM) and Handout 1.
Evaluation Performance Steps TIME START: SATKTNSAT "Step 1: Perform Valve L i n e u ~ Standard: The operator completes the valve lineup and places their initials in t~ie appropriate space on OP 2124 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 Breake*- 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-27-5836) on the lisleup 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 lie 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 obse~Y-es Red light ON, Green light OFF. The operator initials the appropriate space on OP 2124, Appendix A, ,lnd places a note at the bottom of the page indicating that RHR-65B was found out of position..
JPM-A l a RO Rev. 012309 Page 5 of 6 Evaluation Performance S t e ~ s
*Step 2: Track valve position on OP 2124, Appendix A:
Standard: The operator completes the valve lineup and places their initials in t ie 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 req lired position, and leaves the "Initials" column blank) RHR-89B RHR 89B Test Switch RHR-65B - Identified as Out-Of-Position (with Note and bottom of Page indicating that Valve was found out of position - the note is NOT a Critical, identification of the wrong valve position is critical) RHR-65A RHR-89A RHR 89A Test Switch RHR-184 RHR-183 4OTE: 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 2124, Appendix A. "Critical Step TIME FINISH: Terminating Cue: The JPM is complete. Evaluator Comments: ystem Generic WA: 2.1.29 (4.114.0) JPM-Ala RO
EXAMINEE HANDOUT Initial Conditions: The plant is preparing for startup following a Refueling Outage. Shutdown Cooling has been secured. Appendix B, Containment Remote Operated Valve Checklist, of OP 2115, Primary Containnlr nt, 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.
JPM-A2 RO Rev. 011209 Page 1 of 10 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Perform a Drywell Tem~eratureProfile Failure Mode: High Temperature in the Drywell
Reference:
. OP 4115, Primary Containment Surveillance, (Rev. 60)
Task Number: 2997170301 Task Performance: AO/RO/SRO - ROISRO X SRO Only - Sequence Critical: Yes - No 3 Time Critical: Yes - No J 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: . /f 5~h u / - / d 9 Operations Training Lstructor Date Reviewed by: Q A. .Cud! (S /;I/Cf ]?.CAA/ 5 i - 2 7 6) SRO ~icensedl~ertifikd Reviewer Date lpproved by: 2'7 07 Operations Training ~ a ' h a ~ e d Date
JPM-A2 RO Rev. 011209 Page 2 of 10 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 siep 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: The plant is operating at 100% power. MCB Annunciator 9-5/F-2, DRYWELL TROUBLE has alarmed. RBCCW HX A is in service. Initiating Cues: Another operator has responded to the alarm. The CRS directs you to perform the Drywell Temperature Profile in accordance with Section F of C P 4 115, Primary Containment Surveillance. Task Standards: The Drywell Temperature Check is completed in accordance with OP4115 (Rev 60), Section F, VYOPF 4115.05 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 he identified acceptance criteria, and the operator identifies that ( I ) the Duty OfficerIOperations manag :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 4115.05 must be routed to the EQ Coordinator.
JPM-A2 RO Rev. 011209 Page 3 of 10 Lequired Materials: Handout 1 - OP 4115, 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-2 alarms. Remove malfunction and allow plant to stabilize. Freeze the Simulator Ensure that the recorders are ON and RUNNING for 2 minutes Reset to IC# 821 Go to RUN Remove Malfunction MS-06 Ensure that the recorders are ON and RUNNING for 2 minutes
JPM-A2 RO Rev. 011209 Page 4 of 10 'rovide Candidate with Initial ConditionsICue (Last Page of this JPM). Evaluation Performance Steps TIME START: SATNNSAT 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 4115, Examiner provide :opy (Handout 1). SATIUNSAT Step 2: (CAUTION prior to Step 1) If temperatures below 320 foot elevation exceed 215OF, reactor water level instrumentation errors can o c c l ~ Standard: The operator reads the Caution, and proceeds to Step 1. SATIUNSAT Step 3: (Step 1) If necessarv, refer to Figure 2 for temperature probe locations. Standard: The operator may or may not refer to Figure 2, and proceeds to Step 2 . SATNNSAT Step 4: (Steps 2/2.a) If a high Drvwell temperature alarm is received: Calculate the average Drvwell temperature for the various elevations using VYOPF 4115.05. Standard: The operator recognizes that MCB Annunciator 9-5%-2, DRYWELL TROUBLE, is LIT, and proceeds to VYOPF.05.
JPM-A2 RO Rev. 011209 Page 5 of 10 ivaluation Performance Steps SATNNSAT Step 5: (VYOPF 4115.05/NOTE prior to CRP 9-25 data) Identify anv 01 t f service temperature probe with INOP and ensure a WR is submitted. Standard: The operator reads the Note and proceeds to record raw data. SATlUNSAT Step 6: (CRP 9-25 Data) CRP 9-25 TR 1-149, Place a 4 Mark If RRU In Operation. Standard: The operator observes the RRU 1through 4 Return and RRU 1throu4:h 4 Disch Temperatures, and records on VYOPF 4115.05. The operator places a d Mark in space for RRU 1A, 1B, 2A, 2B, 3A and 4A on VYOPF 4115.05. The operator records RBCCW HX in service as A on VYOPF 4115.15 (Initial Conditions). The operator observes MOO8 and records RBCCW HX Outlet Temperature on VYOPF 4115.05. SATIUNSAT *Step 7: (Step A.l) Calculate the average temperature for each Drywell elevation: Drywell Temperature for Elev. 250' in Vicinity of Recirculation Pumps(DBD-OIHVAC-041 01). Standard: The operator calls up ERFIS computer points (or a User Defined Grc up) as required and records the data on VYOPF 4115.05. The operator completes the calculation (2 total sensors12) on VYOPI' 4 1 15.05 and determines that the calculated Drywell Temperature doe s NOT meet the Acceptance Criteria.
JPM-A2 RO Rev. 011209 Page 6 of 10
- valuation Performance Steps SATIUNSAT *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 Grt ,up) as required and records the data on VYOPF 41 15.05. The operator observes temperature points on the Steam Leak Detect. on Touchscreen Monitor and records the data on VYOPF 4115.05. 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 4115.05. The operator completes the calculation (11 total sensors111) on VYC:jPF 4115.05 and determines that the calculated Drywell Temperature doc-,s NOT meet the Acceptance Criteria. IOTE: The operator may record data required in Steps A.3 and A.4 while performing this Step. SATIUNSAT Step 9: (Step A.3) Calculate the average temperature for each Drvwell elevation: Drywell Temperature for Elev. 270' to 315'. Standard: The operator calls up ERFIS computer points (or a User Defined Grcup) as required and records the data on VYOPF 4.115.05. The operator observes temperature points on the Steam Leak Detectir.)n Touchscreen Monitor and records the data on VYOPF 4115.05. The operator completes the calculation (7 total sensors17) on VYOPF 4.115.05 and determines that the calculated Drywell Temperature met ts the Acceptance Criteria.
JPM-A2 RO Rev. 011209 Page 7 of 10
- valuation Performance Steps SATNNSAT Step 10: (Step A.4) Calculate the average temperature for each Drywell elevation: Drvwell Temperatures Above Elev. 315'.
Standard: The operator calls up ERFIS computer points (or a User Defined Grc lup) as required and records the data on VYOPF 41 15.05. The operator observes temperature points on the Steam leak Detectic ~n Touchscreen Monitor and records the data on VYOPF 4115.05. The operator completes the calculation (5 total sensorsfi) on VYOPE; 4115.05 and determines that the calculated Drywell Temperature mezts the Acceptance Criteria. Interim Cue: If operator identifies acceptance criteria is not met and takes no further action, ask the operator to state those additional actions. SATAJNSAT "Step 11: (Section FISteps 2.b.l-4) If the average temperature of an area exceeds the recommended temperature. Notifv the Duty on Call Officer and the Operations Manager. Generate a Condition Report for possible EQ concern due to exceeding the averape recommended temperature. Calculate and document the average temperature once per shift while this condition exists or until an evaluation deems this actiohb not needed. Route a copy of the completed form to the EO 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 possibl: EQ concern. The operator notifies the CRS that this surveillance must be performe,d once per shift. The operator forwards a copy of the completed VYOPF 4115.05 to th : EQ Coordinator. "Critical Step TIME FINISH: - Terminating Cue: The JPM is complete. JPM-A2 RO
JPM-A2 RO Rev. 01 1209 Page 8 of 10
JPM-A2 RO Rev. 01 1209 Page 9 of 10 2valuator Comments: System Generic WA's: 2.2.12 (3.714.1)
EXAMINEE HANDOUT Initial Conditions: The plant is operating at 100% power. MCB Annunciator 9-5/F-2, DRYWELL TROUBLE has alarmed. RBCCW HX A is in service. Initiating Cues: Another operator has responded to the alarm. The CRS directs you to perform the Drywell Temperature Profile in accordance with Section F of IP 4115, Primary Containment Surveillance.
JPM A3 RO Rev 0 11209 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: 2990100301 Task Performance: AOIROISRO - ROISRO Only X SE Only - Sequence Critical: Yes - No 2 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: /j 2 /% ./#fl&&(7 Operations Training Instructor
/-27 Date
-09 4-d 5 / >) -&? ,d~'jh!?:b 27 - r ; 3
/-
Reviewed by: J ; ? ~ ~ X J / /'. SRO ~ i c e n s e d l ~ e r t i f d&viewer d Date Approved by: 4. $?. .
. I^' /
3 -&? 1 2.-7 LI 7 Operations ~ r a i n l hdperintendent
~ Date JPM A3 RO
JPM A3 RO Rev 011209 Page 2 of 5 rirections: Discuss the information given on this page with the operator being evaluated. Allow time for him co 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 s :ep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measu -e. 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. aitial Conditions: You have been requested to verify that the RCU Pump A suction, CU-19A, is open and to obseave the pump run. You have an accumulated dose (TEDE) of 1920 rnr 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 an additional 15 minutes. Pre and Post pump run dose rates are not expected to change. 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 011209 Page 3 of 5
,'ask Standards:
The operator identifies the: The dose rate at the valve as 240 rnrlhr. The lowest dose rate area as 18 mr/hr. The highest dose rate area as 250 mrhr. The expected dose as 44.5 rnr 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 S e t u ~ : JPM A3 RO
JPM A3 RO Rev 01 1209 Page 4 of 5 rovide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1. Evaluation Performance Steps TIME START: SATNNSAT *Step 1: Obtain and review survev map. Standard: The operator reviews the Book of Survey Maps and identifies Map RB280D for the RCWU A Pump Room. SATNNSAT *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 mrkr. NOTE: The operator may use print G 191178 to determine which valve on the survey map is the suction valve. I ATNNSAT "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 rnrlhr by the Step-Off pad. SATNNSAT *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 mrkr. SATNNSAT *Step 5: Calculate the expected dose. Standard: The operator determines that dose expected at the valve by: 240 m r h r x 10 minutes x 1 hour160 minutes = 40 mr The operator determines the dose expected at the low dose area by: 18 m r h r x 15 minutes x 1 hour160 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 t . 5 rnr. JPM A3 RO
JPM A3 RO Rev 011209 Page 5 of 5
*Step 6: Identify whether or not a dose extension is needed to ~erformth job.
Standard: The operator identifies that the routine admin limit of 2000 mr is imposed, and determines that 80 mr of dose accumulation is allowab e for the job. The operator determines that a dose extension is NOT needed.
- Critical Step TIME FINISH:
Terminating Cue: This JPM is complete.
,valuator Comments:
System Generic KIA's: 2.3.4 (3.213.7) JPM A3 RO
EXAMINEE HANDOUT Initial Conditions: You have been requested to verify that the RCU Pump A suction, CU-19A, is open and to obst rve the pump run. You have an accumulated dose (TEDE) of 1920 rnr 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, anc within the pump room, at low dose areas, for an additional 15 minutes. Pre and Post pump run dose rates are not expected to change. Initiatin~Cues: Given the Room Survey Map identify the followirrg: 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 Rev 011209 Page 3 of 5 task Standards: T h e operator identifies the: The dose rate at the valve as 240 rnrlhr. The lowest dose rate area as 18 mrhr. The highest dose rate area as 250 mrkr. The expected dose as 44.5 mr 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 KWCU A and RWCU B Pump Room. Simulator Setup: JPM A3 RO
JPM A4 RO Rev. 011209 Page 1 of 9 VERMONT YANKEE JOB PERFORMANCE MEASCTRE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Perform Control Room Emergency
- Communications Checks Failure Mode: N/A
Reference:
OP 3506, Emergency Equipment Readiness Check. (Rev. 62) Task Number: 2997270301 Task Performance: AOROISRO - ROISRO X SRO Only - Sequence 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: 10 minutes Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: h.// %kk /z,/#Y~ / /-/ 7- d f Operations Training Instructor Date Reviewed by: 2 / J r C + J l/\ q k?, SRO ~icensedldertdiedReviewer
~4~1:~:
/
,. 2 (7-py Date Approved by: :J
' Operations ~ r a i d d$nager n~ Date JPM A4 RO
JPM A4 RO Rev. 0 11209 Page 2 of 9 Directions: Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required f )r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical ::ep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measu .e. 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-throughtt 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 o F 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 A l a SRO. JPM A4 RO
JPM A4 RO Rev. 011209 Page 3 of 9 Provide Candidate with Initial ConditionsICue (Last Page of this JPM).
- valuation Performance Stem TIME START: -
SATfUNSAT 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 provide: copy (Handout 1). SAT/UNSAT Step 2: (NOTES prior to Step 5.1): The quantities listed in this procedure are to be considered the minimum required. Ouantities above those listed are acceptable, Pens, pencils and scratch paper are readily available and therefere will not be maintained in the EOF and TSC kits Material location mav change as long as the material remains wia:U the facilitv. Standard: The operator reads the Notes and proceeds to Step 5.1. SATIUNSAT Step 3: (Step 5.115.1.1) Control Room Emer~encvCommunications Check [Operations) (Use Attachment 9.11 Monthlv, the O~erationsDe~artmentshall test the Nuclear Alert Svstem bv contacting, and requesting a callback from, each of thf: three states (Vermont, New Hampshire. Massachusetts) using t h ~ following procedure: Standard: The operator obtains Attachment 9.1 and records date and time. JPM A4 RO
JPM A4 RO Rev. 0 1 1209 Page 4 of 9 Evaluation Performance Steps SATLTNSAT Step 4: (NOTE prior to Step 5.1.1.a) The 3-digit number 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. SATKINSAT *Step 5: (Step 5.1.1.a) Lift handset and dial 213 for Waterburv, VT, 317 .& 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 iniriate requested callbacks to the operator by dialing phone extension 126. SATIUNSAT Step 6: (Caution prior to Step 5.1.1.b) Press down and hold the push-to- talk button on the handset prior to speaking. Release after speaking, Refer to O P 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. 011209 Page 5 of 9 Evaluation Performance Steps
;AT/UNSAT *Step 7: (Step 5.1.1.b) Advise each State Police agency that answers of the:
test of the Nuclear Alert Svstem, and record the results on Attachment 9.1. Standard: The operator presses the "push to t a l k button and indicates that "Th s is the ENVY Control Room, Vernon;" and that "a test of the NAS Pho le" 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 ini-iate requested callbacks to the operator by dialing phone extension 126. When the NAS Phone rings back, the operator will pick up the handset, press the "push to t a l k 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 t a l k pushbutton, acknowledge the test, release the button, and replace the handset. The operator records the successful test by checking the YES Box on Attachment 9.1, Section A.1, for Waterbury, Vermont (2 13), and the associated YES Box for the callback. NOTE: Only one of the calls to the five State Police Agencies will be Interim Cue: Examiner inform operator that subsequent NAS Phone Tests to Rockingham, Vermont, Concord, New Hampshire, Northan~pton,Massachusetts, and Shelburne Falls, Massachusetts, have been completed satisfactorily. After cue, the operator records the successf~~l tests by checking the Y3S Boxes on Attachment 9.1, Section A. 1, for Rockingham, Vermont, Concord, New Hampshire, Northampton, Massachusetts, and Shelburne Falls, Massachusetts, and the associated YES Boxes for the callback. JPM A4 RO
JPM A4 RO Rev. 011209 Page 6 of 9 Evaluation Performance Steps jAT/UNSAT *Step 8: (Step 5.1.l.c) Test the Group Call capabilitv with the five State Police agencies by lifting handset and dial in^ Al. State Emereel r a Operations facilities may also answer, but are not required for t re test. After the test is complete disconnect the Proup call bv diali;g A#, then hang UD handset. Standard: The operator picks up the handset, and recognizes that no one else .IS one the line. The operator dials A1 and waits for the five State Police Agencies 1.c respond. NOTE The Simulator operator will answer as each state police agency as follows: Massachusetts State Police, Troop B - Northampton Massachusetts State Police, Shelbume Falls New Hampshire State Police, C'oncord Vermont State Police, Waterbury Vermont Secondary Warning Point - Rockingham JOTE Once made aware of the test, the Simulator operator will acknowledge the test as ea:h state police agency. After the acknowledgement of all five agencies, the operator disconn :cts 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/NWMA(A I ). Step 9: (Step 5.1.1.d) If anv part 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. 0 11209 Page 7 of 9 Evaluation Performance Steps SATAJNSAT Step 10: (Step 5.1.1.e) Notify the affected state Emergency Management +.~ff~ce 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. B .2.
*Step 11: (Step 5.1.215.1.2.a) Monthly the Operations Department shall ter 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. S ATAJNSAT *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) e s i n ~ all digits. If the first number is busy, proceed with the second numt,er. 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 1-301-8 16-5100. 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. 011209 Page 8 of 9 Evaluation Performance Steps
;AT/UNSAT *Step 13: (Stea 5.1.2.c) State your name, location, and the fact that vou ar :
testing the NRC ENS. Request that the NRC staff member call ~,ack at 700-661-4323. Standard: Operator informs NRC operator who he is, where he is calling from, that he is testing the ENS, and requests callback at 700-661-4323. Note: Simulator operator will acknowledge call as NRC operator, and will initiate callbac c using the "NRC to Control Room" auto dial button. Standard: When the ENS Phone rings back, the operator will pick up the handset, 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 or, Attachment 9.1, Section B.l for Successful Test with the NRC, and Section B.2 for Callback from the NRC Successful.
'IME FINISH:
Terminating Cue: This JPM is complete. Evaluator Comments: System Generic KJA's: 2.4.43 (3.213.8) 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 Conimunications Checks in accordance with Section 5.1.1 and 5.1.2 of OP 3506 and to complete any associated paperwork.
JPM-Ala SRO Rev. 012309 Page 1 of 7 VERMONT YANKEE NUCLEAR POWER CORPORATION JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Perform the CSIHPCI System Valve Lineup Failure Mode: Two Mispositioned Valvesl
References:
OP 2115. Residual Heat Removal System, (Rev. 1 13) AP 0155, Current System Valve And Breaker Lineup and Identification, (Rc v, 78) Task Number: -- 1 Task Performance: AOROISRO - ROISRO X SRO Only - Sequence Critical: Yes - No 3 Time Critical: Yes - No 3 Operator Performing Task: Examiner: Date of Evaluation: Activity Code: Method of Testing: Simulation - Performance-X 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: /-27-a5 Operations Training Instructor Reviewed by: /C /'O
~L-R 1I ~5 L/Q -& Hd / a7,4F3 SRO ~icensedldertihedReviewer Date dFwf ipproved by: (-2-7 ,O-g Operations ~ r a i n i n ~ h a d i ~ e r Date JPM-Ala SRO
JPM-A 1a SRO Rev. 012309 Page 2 of 7 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 )r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s :ep 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 21 15, Primary Containmet~t,is in progress. Initiating Cues: The CRS directs you to complete Appendix B, Containment Remote Operated Valve Checklist, of 43P 2115, Primary Containment. Task Standards: The operator performs the valve lineup in accordance with OP 2115, 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. 0 12309 Page 3 of 7
- equired Materials:
Handout 1 - OP2 115, 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-1 IB, CS-12B, CS-14B, HPCI-25, HPCI-16, HPCI-15, HPCI-58, and HPCI-57 Handout 2 - AP 01 55, Current System Valve And Breaker Lineup and Identification, (Rev. 78) 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 froril moving. Start Recirc Pump A in accordance with OP 2110. Lined up SBGT on Containment Air Purge in accordance with OP 2115 Reset to IC-820 Examiner Notes: Since the JPM task is focused on the CSIHPCI System ValveISwitch 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. 012309 Page 4 of 7
'rovide Candidate with Initial ConditionsICue (Last Page of this JPM) and Handout 1.
Evaluation Performance Stem TIME START: SATIUNSAT *Step 1: Perform Valve L i n e u ~ Standard: The operator completes the valve lineup and places their initials in tlie appropriate space on OP 2115 Appendix B. The operator discovers CS- 11A 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 asks for recommendation. When asked if there are any Danger tags, Temp Mods or Lineup Deviations associared with the component, state that none: of those exist. IF asked, state that the component is not being controlled as a "No Tag" per EN-OP-102 AND is NOT out of position due to procedural direction. The operator places the CS-1 1A control switch to OPEN and observes the Red status light O N and the Green status light OFF. The operator places their initials in the appropriate space on OP 21 1': Appendix B for CS-11A, and places a Note at the bottom of page 3 identifying that CS-I 1A was discovered to be in the CLOSED positic ln. The operator discovers CS-11B CLOSED, when it should be OPEN. JPM-A 1a SRO
JPM-A 1a SRO Rev. 012309 Page 5 of 7 Interim Cues: If the operator asks for SM assistance, Examiner asks for recommendation. When asked if there are any Danger tags, Temp Mods or Lineup Deviations associated with the component, state that none of those exist. IF asked, state that the component is not being controlled as a "No Tag" per EN-OP-102 AND is NOT out of position due to procedural direction. The operator places the CS-1 1B control switch to OPEN and observ+:s the Green status light ON and the Red status light OFF, and identifies that CS-1 1 B will NOT Open. The operator DOES NOT place their initials in the appropriate space on OP 2115 Appendix B for CS-1 lB, and places a Note at the bottom of page 5 identifying that CS-11 B was discovered to be in the CLOSEKl position, and will NOT OPEN. 'nterim Cues: Once the condition is identified, tell the operator to complete the checklist and addr:ss the operational implications of CS-1 1B failing closed once the checklist is completed.
"Step 2: Track valve position on OP 2115, Appendix B:
Standard: The operator completes the valve lineup and places their initials in tk e appropriate space on OP 2115 Appendix B for the following valves: CS-7A CS-5A CS-11A (Identified as Out-Of-Position (with Note and bottom of Pagte indicating that Valve was found out of position - the note is NOT Critical, identification of the wrong valve position is critical) CS-12A CS-14A CS-7B CS-5B CS-1 1B (Identified as Out-Of-Position (with Note and bottom of Pag : indicating that Valve was found out of position - the note is NOT Critical, identification of the wrong valve position is critical) CS-12B CS-14B HPCI-25 HPCI-16 JPM-A 1a SRO
JPM-A 1a SRO Rev. 012309 Page 6 of 7 HPCI-15 HPCI-58 HPCI-57
*Step 3: Evaluate Technical Specifications Standard: The operator addresses LC0 3.5.A.1 and determines that the valve r lust be correctly positioned prior to entering the Startup mode.
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 2115, Appendix B TIME FINISH: Terminating Cue: The JPM is complete.
- valuator Comments:
System Generic KIA: 2.1.29 (4.114.0) JPM-Ala SRO
EXAMINEE HANDOUT Initial Conditions: The plant is preparing to enter the Startup mode. Appendix B, Containment Remote Operated Valve Checklist, of O P 2 115, Primary Containrnc nt, 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.
JPM-Alb SRO Rev. 0. 2209 Page of 8 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Perform a Core Thermal Hydraulics 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: AOIROISRO - ROISRO - SRO Only X Sequence Critical: Yes X No Time Critical: Yes - No 2 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 m i n m Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: @ d SL CC &-f/#fl.A & Operations raini in^ Instructor i/ Date Reviewed by: / . $7-SRO ~icensedl~ertif%ed ~gviewer Date Approved by: : 7- [ ~ f
/- 2 Operations ~ r a i n i h~ ~d ~ e r v i s o r Date JPM-A 1b SRO
JPM-A 1 b SRO Rev. 01 2209 Page : of 8 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 tcep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measu .e. After providing the initiating cue, ask the individual "Do you understand the task?" Read to the person be in^ 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 ancl you are to perform all actions. You are requested to "talk-through" the procedu:re,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 at 10090 power. A power change from 90% to 100% occurred one hour ago. The 3D Monicore case is available. Control Rods match the case Initiating Cues: You are required to perform the Daily Core Thermal Hydraulics Limit Evaluation in accordance with OP 4401, Core Thermal Hydraulics Limit Evaluation. Identify any notifications and actions required. Task Standards: The Daily Core Thermal Hydraulics Limit Evaluation is performed in accordance with OP 4401, MFLCPR is identified as being out of spec above the admin limit but below the L C 0 3.11 .C limit. Determines that Reactor Engineering must be contacted. Required Materials: Handout 1 - 3D Monicore Case # FMLD 1080319125947 (Modified so that MFLCPR is OOS higt). Handout 2 - OP 4401, Core Thermal Hydraulics Limit Evaluation (Rev. 34) Handout 3 - Thermal Limit Status Board (Copy) JPM-Alb SRO
JPM-Alb SRO Rev. 0: 2209 Page i of 8 Handout 4 - Printout of the R E 0 computer screen showing control rod positions and APRM GAI 's. Simulator Setup: JPM-A 1 b SRO
JPM-A 1b SRO Rev. 01 2209 Page of 8 'rovide Candidate with Initial ConditionsICue (Last Page of this JPM) and Handout #l. Evaluation Performance Steps TIME START: 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 provide: copy (Handout 2). SATIUNSAT 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 (i.e., From cass ID). Standard: The operator reads the Note and proceeds to Step 1. SATIUNSAT 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 performei and that the automatic case has been provided. JPM-Alb SRO
JPM-A1 b SRO Rev. 01 2209 Page : of 8
'valuation Performance Steps
*Step 4: (Step 2) Complete 'VYOPF 4401.01 Standard: The operator evaluates 3D Monicore Case # FMLD 1080319125947 and completes steps 1-6 of VYOPF 4401.01 as follows:
The operator records 3D Monicore Official Monitoring Case TD FMI .D 1080319125947 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 APRh1 GAFs (Handout 3). 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 0.993, and its core l o w ion as 25-26 in Step 4. The operator records the highest MFLPD as 0.798, and its core locatic~n as 21-36-4 in Step 5. The operator records the highest MAPRAT as 0.712, and its core location as 21-36-4 in Step 6. JPM-A1b SRO
JPM-Alb SRO Rev. 0 1 2209 Page ( of 8 7valuation Performance Steps SATAJNSAT Step 5: (NOTE prior to VYOPF 4401.01 Step 7) Any APRM found to bt non-conservative shall be corrected as soon as possible. An A P R U considered inoperable if the AGAF is not restored within 6 hourf , the time of discoverv. Standard: The operator reads the Note and proceeds to Step 7 SATAJNSAT Step 6: (Step 7) Check the APRM system gains using the R E 0 displav o : ~ ERFIS. Standard: The operator calls up the R E 0 display on ERFIS and observes ARPb? System gains. After cue, the operator proceeds to Step 8. Interim Cue: When asked, Examiner inform operator Item #7, APRM gains, has been verified SAT.
' ATAJNSAT *Step 7: (Step 8) Verifv MFLCPR, MFLPD and MAPRAT from Steps 4 - 6 are less than or equal to Administrative Limits posted on Therm:g Limit Status Board. If not, contact Reactor Engineering.
Standard: The operator compares the values recorded on VYOPF 4401.O1 Step; 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 4). When RE is notified, Examiner ack~~owledge as RE. JPM-Alb SRO
JPM-A1 b SRO Rev. 012209 Page ' of 8 Performance Steps
*Step 8: (Step 9) Verify the Acceptance Criteria below are satisfied. If A B, C or D below are not satisfied, enter a~plicableTech. Spec. LC( i Standard: The operator recognizes that Acceptance Criteria A is satisfied.
The operator does sign Step 10 of VYOPF 4401.O1 indicating that tl e surveillance has been performed and that the Acceptance Criteria arc satisfied. The operator notifies the SM of the results of the surveillance. TIME FINISH: Terminating Cue: This JPM is complete. Evaluator Comments: KIA: Generic 2.1.7 (4.414.7) JPM-Alb SRO
EXAMINEE HANDOUT nitial Conditions: The plant is at 100% power. A power change from 90% to 100% occurred one hour ago. The 3D Monicore case is available. Control Rods match the case Initiating Cues: You are required to perform the Daily Core Thermal Hydraulics Limit Evaluation in accordancs with OP 4401, Core Thermal Hydraulics Limit Evaluation. Identify any notifications and actions required.
JPM-A2 SRO Rev. 011209 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 4110. Reactor Recirculation System Surveillance. (Rev. 41) Steam Tables Task Number: - 1-Task Performance: AOIROISRO - ROISRO 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 Required: Prepared by: kJ7-d 9 Operations Training instructor Date Reviewed by: J-8f i ~ du,, / W R 2 [p,7 Approved by: ' SRO ~icensecU~dfiifi&
-7R . K c l k t , s / 3 ,&*
Reviewer Operations ~raidin&ana~er
~. 1 .- '
Date
/ . g-7i/l Date JPM-A2 SRO
JPM-A2 SRO Rev. 011209 Page 2 of 6 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~lr any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s ep 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 throueh" 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 sl.lutdown for corrective maintenance on its associiited 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 acc0rc1:~nce with OP 2110, Reactor Recirculation System. The Reactor Operator has just indicated that while performing the Reactor Coolant Temperature Check Data Sheet of OP 4110, Reactor Recirculation System Surveillance, he has determined tl;at the criteria necessary to start Recirc Pump B is met. Initiating 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 t11en direct that the RO continue the process of starting Recirc Pump B in accordance with OP 2110. JPM-A2 SRO
JPM-A2 SRO Rev. 01 1209 Page 3 of 6
'.equired Materials:
Handout 1 - VYOPF 41 10.05, Reactor Coolant Temperature Check Data Sheet, (Rev. 41), filled i 1 as follows: Recirc Loop A 5 10 Temperature (OF) Recirc Loop B 3(.1,Y Blank I Reactor Pressure (~sie) Bottom Head Drain Temp (OF) (PLC 166, RPVfSVIRV Screen, Ch. 4 (ERFIS Pt S026) Saturation temperature corresponding to above reactor pressure from 536 OF (In Error, Should be saturated steam tables 540) jifference between saturation temperature and bottom head drain 1 44 OF , .emperature Handout 2 - Steam Tables Calculator Simulator Set-Up: NA JPM-A2 SRO
JPM-A2 SRO Rev. 0 11209 Page 4 of 6
'rovide Candidate with Initial ConditionsICue (Last Page of this JPM) and Handout 1.
Evaluation Performance Stew TIME START: SATlUNSAT *Step 1: Review Reactor Coolant Temperature Check Data Sheet a l r e a d ~ b progress. Standard: The operator observes the partially completed VYOPF 4110.05. 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 sat~~ration temperat~r~: and the bottom head drain temperature will NOT support Recirc Puntp B start.
'ATiUNSAT *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 operakor with the Steam Tables (Handout 2). The operator converts Reactor Pressure to absolute pressure by adding 14.7 psia to gage pressure of 947 psig and determines absolute pressure to be 962.7 psia. The operator determines from Table 1 of the Steam Tables that the saturation temperature is between 540 and 544"F, and determines tha: the recorded saturation temperature is in error. The operator calculates the actual saturation temperature to be 540°F. JPM-A2 SRO
JPM-A2 SRO Rev. 011209 Page 5 of 6 Performance Steps
*Step 3: Correct Reactor Coolant Temperature Check Data Sheet a l r e a d d progress, and determine a course of action Standard: The operator places a line through 536"F, initials it, and enters 540"1 .
The operator places a line through 144"F, initials and calculates a new AT between the saturation temperature and the bottom head drain temperature of 148°F. (540°F - 392°F = 148°F) The operator observes that the AT between the saturation temperature and the bottom heacl drain temperature will NOT support Recirc Purnp B start. TIME FINISH: Terminating Cue: The JPM is complete. Evaluator Comments: System Generic KIA: 2.2.12 (3.714.1) JPM-A2 SRO
EXAMINEE HANDOUT Initial Conditions: The plant is 50% power with Recirc Pump B shutdown for corrective maintenance on its assoc ated 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 accordance with OP 2110, Reactor Recirculation System. The Reactor Operator has just indicated that while performing the Reactor Coolant Temperatu~.: Check Data Sheet of OP 41 10, Reactor Recirculation System Surveillance, he has determined r at the criteria necessary to start Recirc Pump B is NOT met. Initiatin~Cues: As the CRS, evaluate the surveillance and determine if the RO is correct.
JPM-A3 SRO Rev. 0 1 1209 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: AOIROISRO - ROISRO - 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 :XDiscuss Setting: Classroom X Simulator - Plant - Performance Expected Completion Time: 10 m i n m Evaluation Results: Performance: PASS FAIL -- Time Required: Prepared by: b/7/ 56 Operations
,/afl raini in^
/
Instructor d& (7
/-J 7-07 Date Reviewed by: ,
/-J SRO ~icensed/~&ific(d ~eviewer Date Approved by: T A . JI fCk~&;s / Q /?
Operations ~ r a i n i n $ ~ a & ~ e r fl~d* / 2--7 Date
-07 JPM-A3 SRO
JPM-A3 SRO Rev. 011209 Page 2 of 7 Discuss the information given on this page with the operator being evaluated. Allow time for hini 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 )r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s ep 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 be in^ 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 ancl you are to perform the actions. You are requested to "talk throueh" 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: With the plant shutting down due to failed fuel causing high Reactor Coolant System Activity, 1 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 and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due .o 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 tc do SO. The RP Technician estimates that it will take at least ten minutes to retrieve the victim. Reactor Building Area Radiation Monitors indxcate extremely high radiation levels. Dose rates at the area needing access are 420 Rem/Hr. The Senior Radiation Protection representative has already concurred with the dose exposure authorization. The Job Number is 047 The RWP is 09-003 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 the Emergency Dose Commitment portion of Attachment 9.8 to approve the Emergency exposure. JPM-A3 SRO
JPM-A3 SRO Rev. 01 1209 Page 3 of 7 Task Standards: The operator chooses Madigan 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: JPM-A3 SRO
JPM-A3 SRO Rev. 0 11209 Page 4 of 7
'rovide Candidate with Initial ConditionsICue, and Handout 1 (Last two Pages of this JPM).
Evaluation Performance Steps TIME START: SATRJNSAT 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 "8. Interim Cue: When it is apparent that the operator is seeking to find OP 3507, Examiner provide copy (Handout 2). JNSAT *Step 2: As the Plant Emergencv Director, select the two most appropriat+~ rescuers from those individuals available in accordance with Attachments 9.1 and 9.5 of OP 3507, Emergency Radiation E x p w ~ Control. SATtUNSAT *Step 3: State the reason(s) whv the other individuals are not the most appropriate. Standard: The operator recognizes from initial conditions that Dose rates at the area needing access is greater than 420 Rem/Hr, and that based on 10 minlte 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 anil determines qualification of potential rescuers. The operator determines that Jaffe cannot be dispatched as a rescuer (Declared pregnant). The operator determines that Gibbs cannot be dispatched as a rescuer (Does NOT Volunteer). The operator determines that Pearson cannot be dispatched as a rescut,r (Has too much Lifetime Exposure). The operator determines that Fiske cannot be dispatched as a rescuer (Only STA - TRMlOP0894 requires her in Control Room). The operator determines that Woods cannot be dispatched as a rescuep, JPM-A3 SRO
JPM-A3 SRO Rev. 011209 Page 5 of 7 (High Lifetime Dose). The operator selects Madigan and Walker as rescuers. "Critical Step TIME FINISH: - Terminating Cue: This JPM is complete. Evaluator Comments: System Generic KIA's: 2.3.4 (3.213.7) JPM-A3 SRO
JPM-A3 SRO Rev. 0 11209 Page 6 of 7
'landout 1: List of Available Rescuers in Control Room:
RP Badge Name Gender1 Age Job Assignment Employer (Ir/- Current Exposure Lifetime Exposure Special Status 12345 Gibbs Male1 49 Maintenance VY
'?I-1800 mr Would prefer not to physical health 12456 Madigan Female1 Engineer VY 45 mr 400 mr Volunteers1 Reports 48 good physical health 12567 Pearson Male A0 VY 125 mr 35.4 R Volunteers1 Reports 145 good physical health 12579 Walker Male1 Training VY 6 mr 1400 mr Volunteers/Reports 52 Supervisor good physical health 12110 Jaffe Female1 Security VY 10 mr 65 mr Declared Pregnant 32 Supervisor /Volunteers/ Reports good physical health 12238 Fiske Female1 STA VY 4 mr 120 mr VolunteersIOnly STA 46 qualified individual in Control Room.
112198 Woods Male1 78 rnr 1.7 R Volunteers1Reports good physical health JPM-A3 SRO
EXAMINEE HANDOUT initial Conditions: With the plant shutting down due to failed fuel causing high Reactor Coolant System Activity, 1 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 and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due o 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 tc do SO. The RP Technician estimates that it will take at least ten minutes to retrieve the victim. Reactor Building Area Radiation Monitors indxcate extremely high radiation levels. Dose rates at the area needing access are 420 RemIHr. The Senior Radiation Protection representative has already concurred with the dose exposure authorization. The Job Number is 047 The RWP is 09-003 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 ti,e Emergency Dose Commitment portion of Attachment 9.8 to approve the Emergency exposure.
JPM A4 SRO Rev. 012309 Page 1 of 12 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Off-Site Protective Action Recommendations (evacuate) Failure Mode: - NIA
Reference:
OP 3511 Off-Site Protective Action Recommendations. (Rev. 26) OP 3513. Evaluation of Offsite Radiological Conditions. (Rev. 33) Task Number: 2007150501 Task Performance: AOIROISRO - RO/SRO - SRO Only X Sequence Critical: Yes - No Time Critical: Yes - No Operator Performing Task: Examiner: Date of Evaluation: Activity Code: Method of Testing: Simulation - Performance X Discuss - Setting: Classroom - Simulator X Plant Performance Expected Completion Time: 20 minu-Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: m.// 5~4t /x// " N4L&&/ Operations ~ r a i h i nInstructor
~ fl
/-27-~7 Date Reviewed by:
SRO ~icensed/~ert$fie#~eviewer
..R, ,/')
]l?&[L~
7
- 1. 2.7.- lr, 3 Date Operations ~ r a i n i n~i a g a ~ e r Date JPM A4 SRO
JPM A4 SRO Rev. 012309 Page 2 of 12 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( r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical qiep 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 fuc4 damage. An elevated release through the plant stack has just begun, and a General Emergency EAL has teen declared five minutes ago. There is no ground release in progress. Another SRO has been assigned to Use OP 3511, 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 13P 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 transm. ts to the PED indicating that Vernon, Hinsdale, Bemardston and Northfield must be evacuated. JPM A4 SRO
JPM A4 SRO Rev. 012309 Page 3 of 12 iequired Materials: Handout 1 - OP 3513, Evaluation of Offsite Radiological Conditions (Rev. 33) Handout 2 Source Term Data Screen Handout 3 Protective Action Recommendations Screen Handout 4 - OP 3511, Off-Site Protective Action Recommendations (Rev. 25) Handout 5 - Completed PAR based on Plant Conditions (Attachment 9.5 of OP 3511) filled out ar follows: Current Date Current Time Section I - an "S" is placed in front of Guilford, Vernon, Hinsdale, Winchester, Bernardston, and Northfield. Approved By and DateITime (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 .06 (6000 mrlhr). 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 Mc t Data average readings to stabilize. Reset to IC-820 Examiner Notes: This JPM should be conducted simultaneously with Ala RO. JPM A4 SRO
JPM A4 SRO Rev. 012309 Page 4 of 12
'rovide Candidate with Initial ConditionsICue (Last Page of this JPM),
Evaluation Performance Steps TIME START: - S ATIUNSAT Step 1: Obtain Procedure OP 3513. Standard: The operator obtains OP 3513. 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). SATKTNSAT Step 2: (Steps 5.9.115.9.1.a) Immediate Action by the SMIPED or Design+W Plant Staff Member. Upon receiving an indication of a significanf release of radioactivitv is occurring and the EOF has not been activated, initiate or assign a qualified 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 t)ff-site radiological conditions and proceeds to Step 5.9.1 .b. SATIUNSAT 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 activitiem be considered and implemented. Standard: The operator reads the Note, refers to Attachment 9.11, and proceeds io Step 5.9.1.b. JPM A4 SRO
JPM A4 SRO Rev. 0 12309 Page 5 of 12 ,valuation Performance Steps SATIUNSAT Step 4: (Step 5.9.1.b) For an actual ground release.. .... Standard: The operator recognizes that a ground release is NOT in progress, an1 proceeds to Step 5.9.1 .c. SATJUNSAT *Step 5: (Step 5.9.l.c) If the Stack High Range Monitor equals or exceeds 20 mR/hr, request the Chemistry Technician to obtain a silver ze & 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 46100 mrhr. The operator contact and directs the Chemistry Technician to obtain i s 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. SATIUNSAT *Step 6: (Step 5.9.l.d) If ODPS is operable. then implement Attachment 9.5 to access off-site dose pro-iectioninformation from ODPS. Standard: The operator proceeds to Attachment 9.5. SATIUNSAT Step 7: (Attachment 9.5. Stem l,l.a and NOTE prior top Step l.a.1) Obtain the necessary off-site dose pro-iectioninformation for stack and ground release as follows: IF A STACK RELEASE IS OCCURRING: ~eteorologicaland source term data are automatically input to model. Manual input of data is not necessary, Standard: The operator reads the Note and proceeds top Step 1.a.1. JPM A4 SRO
JPM A4 SRO Rev. 012309 Page 6 of 12 ,valuation Performance Steps SATAJNSAT Step 8: (Step l.a.1) Click the "ODPS" menu item on the RTIME menu tar to access the "ODPS Menu"; OR if the workstation has an ERFI i terminal key board, press the "ODPS" key. 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 obse ves VYOPF 3513.01 "Source Term Data" screen. S ATAJNSAT 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 13.3. SAT/UNSAT Step 11 (Step l.a.3) Click on the PRINTER icon to obtain record of stacli; release projection information (Reactor Trip Status and Stack). Standard: The operator Clicks on the PRINTER icon, and obtains the printout. Interim Cues: When the operator indicates that they will print the screen, provide operator with a laminated copy of the "Source Tern1 Data" screen. (Handout 2) ATIUNSAT 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" key. Standard: The operator clicks t:he "ODPS" menu item on the RTIME menu bar; OR if the workstation ha:san ERFIS terminal keyboard, presses the "ODYS" key. JPM A4 SRO
JPM A4 SRO Rev. 012309 Page 7 of 12
,AT/UNSAT Step 13: (Step l.a.5) Click on the "PROTECTIVE ACTION RECOMMENDATIONS LIVE STACK MR/HR1'box to display screen.
Standard: The operator clicks on the "PROTECTIVE ACTION RECONIMENDATIONS LIVE STACK MRIHR" box. SATAJNSAT Step 14: (Step l.a.6) If ODPS aborts due to bad input (as indicated on s c r . ~ displav). ........ Standard: The operator recogn.izes that ODPS does NOT abort, and proceeds to Step l.a.7. Evaluation Performance Steps SATIUNSAT Step 15: (Step l.a.7) When "PROTECTIVE ACTION RECOMMENDATION" screen is displayed, click on the PRINTER icon to obtain stack release off-site dose proiection information. Standard: When the "PROTECITIVE ACTION RECOMMENDATION" screer! is displayed, the operator clicks on the PRINTER icon, and obtains the printout. Interim Cue: When the operator indicates that they will print the screen, provide operator with a laminated copy of "Protective Action Recommendations" screen. (Handout 3). SATLTNSAT 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 ERFIfi terminal keyboard, press the "ODPS" kev. Standard: The operator clicks the "ODPS" menu item on the RTIME menu bar 20; 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.fL Step 1.b for ground release and then continue with Attachment 9 5 Step 2. Standard: The operator recognizes that there is no ground release in progress, a1 d proceeds to Step 2 of' Attachment 9.5. JPM A4 SRO
JPM A4 SRO Rev. 012309 Page 8 of 12 3ATNNSAT Step 18: (Steps 212.a) Use printed screen information from above to do thh: following: If multiple release points exist (stack and ground),. , . Standard: The operator recognizes that only one release point exists, and procet ds to Step 2.b. Interim Cue: When operator indicates that they will print the screen, provide operator with lamini ted copy of "Source Term Data" SAT/UNSAT Step 19: (Steps 2.bl2.b.l) If only one release point exists (stack or groundt, 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 :o find OP3511. The operator proceeds to Step 5.7.5. Interim Cue: When it is apparent that the operator is seeking to find OP 3511, Examiner provides copy (Handout 4). Evaluation Performance Steps SATIUNSAT *Step 20: (Step 5.7.515.7.5.a) Determine appropriate Protective Action Recommendations (PAR) as follows: (Use Section I1 of Attachment 9.5) Compare the calculated dose pro-iection results with EPA Protective Action Guidelines delineated below to determine whether EPA Protective Action Guidelines have been exceeded. If the Eq.l, Protective Action Guidelines have not been exceeded, then cornpie& Attachment 9.5 Section 11, indicating that there is no PAR based o n radiological conditions. Standard: The operator uses information from ODPS or obtained in previous printout and notes that Total Effective Dose is >1 REM between the Site Boundary and 5 miles and recognizes that evacuation is needed. SATNNSAT Step 21: (Step 5.7.5.b) Attachment 9.2 and Attachment 9.3 are conservatit& based on METPAC plume traiectories, the river valley effect for stability classes E, F and G, and plume width. Standard: The operator reads step and proceeds to Note prior to Step 5.7.5.c. JPM A4 SRO
JPM A4 SRO Rev. 012309 Page 9 of 12 tAT/UNSAT 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) In the EOF, in the initial stages of the event, the pll me trajectory is determined by calculating: a "what i f ' METPAC 10-mile plume pro-iection with a default source term and actual meteorolonv using the METPAC Batch Mode with 8 time steps g~ OP 3513, Attachment 9.9 Standard: The operator recognizes that the EOF is NOT manned, and proceeds to Step 5.7.5.d. S ATIUNSAT Step 24: (Step 5.7.5.d) In all cases, use the field team data to verify the act-uu downwind direction of the plume. Adiust the PAR as appropriate, Standard: The operator recognizes that the Field Team data and the ODPS data are the same, and procee:ds to Step 5.7.5.e. 1. Interim Cue: Examiner inform the operator that the Field Team data reflects the ODPS data. Evaluation Performance Steps SATKJNSAT *Step 25: (Step 5.7.5.e/(3)) Choose the towns affected bv the PAR as f o l l o w ~ ~ f ODPS shows that the PAR (evacuation) is exceeded between the si& boundary and five miles, then use Attachment 9.3 and appropriate meteorological 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 determine the wind direction to be 3-7". The operator observes the previously obtained printout and determine , 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. JPM A4 SRO
JPM A4 SRO Rev. 0 12309 Page 10 of 12 Step 26: (Step 5.7.5.f) Any 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 anc [her operator, and proceeds to Step 5.7.54. Interim Cue: When the operator is seeking any previous PARS, Examiner provide the PAR corny leted minutes earlier based on Plant Conditions (Handout 5). SATAJNSAT Step 27: (Step 5.7.5.g) Barring impediments, (e.g., weather or a competini; disaster) once a town has been recommended to evacuate, the more conservative action will be followed even if u ~ d a t e danalyses or conditions indicate that sheltering in place would be sufficient. Standard: The operator recognizes that an initial PAR is being prepared by ano:her operator, and proceeds to Step 5.7.5.h. Tnterim 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. 012309 Page 11 of 12 valuation Performance Steps SATIUNSAT *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. 7 The operator places their name in the "Performed By ' Box on Sectioti I1 of Attachment 9.5. The operator seeks an independent verification of the PAR. Interim Cue: Examiner as independent verifier, sign Attachment 9.5 independent verification. Step 29: ( S t e 5.7.6)
~ Forward completed Attachment 9.5 to the Site Recoveia 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: ystem Generic KIA's: 2.4.44 (2.414.4) JPM A4 SRO
JPI I-S1 Rev. 01 f 509 Page I of 9 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXA,M 2009 Task Identification:
Title:
Shift Rx Level Control Frorn The Main Feed Reg, Valve To The Auxiliarv : d Reg Valve Failure Mode: Aux Feed Reg- Valve Controller fails such that valve fullv opens
Reference:
OP 0105, Reactor Operations, (Rev. 86) EN-OP-1 15, Conduct of Operations, (Rev. 6) Task Number: 2590060101,2590070101,2590080101 Task Performance: AO/RO/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: /-%?-09 Operations ~ r d n i Instructor n~ Date Reviewed by: .- / .- -z .7- [ c j
)
SRO ~icens&&ified Reviewer Date Approved by: /. 2 ;7-L, 7 Operations ~ r d i !!fuperintendent n ~ Date JPM-S 1
JI'l.4-S 1 Rev. 01 1509 Page : of 9 Discuss the information given on this page with the operator being evaluated. Allow time for him io ask questions before beginning performance of thc: 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 5 sep 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 be in^ 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 throueh" 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 in progress. Reactor Power is 5%. OP 0105, Reactor Operations Phase 5C. is completed through Step 2.b.6.g. Initiatinp 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 Contr 31 by placing the controller in MANUAL, and controlling Reactor level manually. Required Materials: Handout 1 - OP 0105, Reactor Operations, (Rev. 86) JPM-S 1
Jl': 4-S 1 Rev. 01 1509 Page : of 9 Cimulator Setup: Reset to IC-8 Lower power to 5% using OP0105. Ensure "A" FRV in Auto with "V" displayed on Clontroller. Ensure "B" FRV in Manual and closed. Ensure FDW-1 I B is closed. Insert FDW-13 Controller failure to open valve fully (malf FW-13 to 100% with no ramp) on Key 1 Ensure that RPV level setpoints for the Main and Aux controllers are set to 160". Reset to IC-850 Ensure "A" FRV in Auto with "V" displayed on Clontroller. JPM-S1
JPI 1-S1 Rev. 0 1 !.509 Page 4 of 9 -rovide Candidate with Initial ConditionsICue (Last Page of this JPM). dvaluation Performance Steps TIME START: SAT/UNSAT 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.112.c.l.a-b) In manual, slowlv open the aux. feed reg. valve as follows: On AUX FEED REG VLV FDW-13 CONTROLLER use the disp& pushbutton to display AUXFRV.V. Adiust output as required by plant conditions us in^ the adiustm* 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 senice closes. Standard: As the operator is ad-justing the FDW-13 Controller, the operator observes the valve position indication on FDW-13 to be increasing, aild valve position on A FRV controller decreases toward 0. The operator observes Reactor Water Level on LI-6-94AIB in Green Band. The operator observes the Red status light OFF on FRV A. JPM-S 1
JPJ I-S1 Rev. 0 L 509 Page 5 of 9 Yvaluation Performance Steps SAT/UNSAT *Step 4: (Steps 2.c.313.al3.a.l) When the main feedwater re~ulatorvalve indicates fullv closed perform the followine: Transfer AUX FEED REG VLV FDW-13 CONTROLLER from manual to automatic as follows: On AUX FEED REG VLV FDW-13 CONTROLLER use the display pushbutton to observe the value of the followine: Standard: The operator observes the valve position indication on A FRV contrc;ller at 0. NOTE: The operator may observe A FRV Red status lights are ON (1 wo sets, 9-5 and 9-6) (NOT Critical). The operator presses the "D" display button to observe the S and P values. YAT/UNSAT *Step 5: (Step 2.c.3.a.2.a-b) Using one or both of the follow in^ steps as p l ~ u conditions dictate, ad-iustthe FWLC system so that AUXFRV.S q mJ AUXFRV.P indicate the same value. Ad-iustAUX FEED REG VLV FDW-13 CONTROLLER to raisenower reactor water level. Adiust AUXFRV.St 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 AIM 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 AIM button on the controller. JPM-S 1
JE'I I-S 1 Rev. 01 1509 Page ( of 9 Tvaluation Performance Steps JATNNSAT Step 7: (Steps 2.c.3.a.3.a-b) On AUX FEED REG VLV FDW-13 CONTROLLER verify the green auto LED illuminates. On AUX FEED REG VLV FDW-13 CONTROLLER verifv the manual LED extinguishes. Standard: The operator observes the Green MIA LED is ON. The operator observes the Red MIA LED is OFF. SATlUNSAT Step 8: (Steps 2.c.3.a.414.a-b)To ad-iustthe AUX FEED REG VLV FDW-13 CONTROLLER setpoint proceed as follows: On AUX FEED REG VLV FDW-13 CONTROLLER use the d i s w pushbutton to display the AUXFRV.S value. Adjust setpoint as required by plant conditions using the ad.iusttn-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. SATJUNSAT *Step 9: (Step 2.c.3.b) Close BLOCKING VALVE FDW-11A(B) for the n i i feedwater regulatin~valve just 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 operator starts to close Blocking Valve, insert malfunction on FDW-13 Controller. causing valve to go full open. NOTE: Use Panel Override for Panel 9-6 to watch Blocking Valve position. JPM-S 1
JE'I /I-S1 Rev. 0 1 1509 Page : of 9 ?valuation Performance Steps SATNNSAT Step 10: (Step 2.c.3.cJ2.c.3.c.l) Transfer the RX VESSEL LEVEL MAST I:R CONTROLLER to manual as follows: Verify MASTER3 and MASTER.P indicate the same value THEN depress the AIM pushbutton Verify the Preen auto LED extinguishes Verify the red manual LED illuminates Standard: The operator presser; the "D" display button to observe the S and P values. When the Reactor level on the Controller is observed, the operator w .I1 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- 1 minutes, and 9-YE-1, RX WATER LEVEL HVLO, will alarm shortly thereafter. ' ATLTNSAT 3 *Step 11: (EN-OP-115, Step 5.3) If an automatic control malfunctions, I immediately place that control in manual. Standard: The operator presses the AA4 button on the AUX FEED REG FDW-13 controller. The operator observes the Red MIA LED is ON and the Green MIA I,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". NOTE: Failure criteria is if the feed water pump trips on high reactor level. TIME FINISH: Terminating Cue: This JPM is complete. Evaluators Comments: JPM-S 1
JPI I - S 1 Rev. 01 1509 Page t of 9 jystem: 259002 KIA: A4.01 (3.813.6) JPM-S 1
EXAkIINEE HANDOUT nitial Conditions: A normal plant shutdown in progress. Reactor Power is 5-10%. OP 0105, Reactor Operations Phase 5C, is conlpleted 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 accordaiice with OP 0 105, Phase 5C, Step 2.c (Page 136 of 152).
JPM - S2 Rev. 011309 Page I. of 6 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:
Title:
Advanced Off Gas System, Vacuum Pump Transfer. Failure Mode:
Reference:
OP 2150, Advanced Off Gas Svstem And Air Evacuation Equipment Task Number: 2717 180101 Task Performance: AO/RO/SRO - ROISRO X SRO Only Sequence Critical: Yes- N o 3 Time Critical: Yes- N o 2 Operator Performing Task: Examiner: Date of Evaluation: Activity Code: Method of Testing: Simulation - Performance X Discuss Setting: Classroom - S i m u l a t o r X Plant Performance Expected Completion Time: 15 minutes Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: /-2 7-Date Reviewed by: .sf?h?Od(k/a@&& . (, / 9-7c?'/ SRO ~ i c e n s e d ~ e d f i Reviewer ed Date Approved by: R /G?rn~i</{$ ,g, /ghJ[* Operations ~r/ainingManager Date JPM - S-2
JPM - S2 Rev. 0 1 1309 Page 2 of 6 3irections: Discuss the information given on this page with the operator being evaluated. Allow time 1 >r him to ask questions before beginning performance of the task. As each performance sttq is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comn ents are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a cri ical step. If a critical step is skipped or perfornied unsatisfactorily, then the operator has failed 1ne 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 quections 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: Reactor is at 100% power Initiating Cues: The CRS directs you to shift from AOG Vacuum Pump A to AOG Vacuum I'ump B per OP 2150 Section S. Task Standards: Shift from AOG Vacuum Pump A to AOG Vacuum Pump B is complete. Required Materials: OP 2 150, Advanced Off Gas System And Air Evacuation Equipment Simulator Setup: Any at power IC with AOG and "A'" vacuum pump in service JPM - S-2
JPM - S2 Rev. 01 1309 Page 3 of 6 dvaluation Performance Steps TIME START: Note: All actions are performed on CRP 9-50. SATNNSAT Step 1:Obtain Procedure OP 2150 and review admin limits, precautions -- a,nd prerequisites. Standard: OP 2150 obtained. lidmin limits, precautions and prerequisites reviewed. Interim Cue: Prerequisites SAT. Note: All actions are performed on CRP 9-50.
- valuation Performance Stem Verify the following for the oncoming pump SATNNSAT Step 2:Mode selector switch for VACUUM PUMP B to AUTO.
Standard: Operator observes Vacuum Pump "B" selector switch is to "AUTO". SATNNSAT Step 3:VACNACSL. P-154/152-1%pump switch OFF. Standard: Operator observes Vacuum Pump "B" VACIVACSL, P-1541152- 1B pump switch OFF. Step 4:Check MS-102-lB, Separator T r a ~level , at approximately 112 to 314 full. Standard: Operator requests AO to check level. lterim Cue: As A 0 report level is Y2 full. JPM - S-2
JPM - S2 Rev. 01 1309 Page 4 of 6 Tvaluation Performance Steps SATNNSAT Step 5:Check the on-coming pump PC-OG-llOlB, VLV CONTROLLER FOR PCV-OG-5O1Bin MANUAL. Standard: Operator observes PC-OG-1 101 B is in MANUAL. SATNNSAT *Step 6: START VACUUM PUMP A(B) by momentarilv depress in^ its AUTO pushbutton. SATNNSAT Step 7:Verifv vacuum pumD "B" start. Standard: Operator observes Vacuum Pump "B" red light on and green light of{. S ATkTNSAT Step 8:Confirm AOV-OG-140B and AOV-OG-144B open. Standard: Operator observes AOV-OG-140B and 144B red light ON and green light OFF. Step 9:Check svstem flow increase on FI-2004, SYSTEM OUTLET, and diffenuM pressure increase on PUMP DELTA P on DPI-1606B. Standard: Operator checks for flow increase on FI-2004 and DP increase on DF'I-1606B. SATAJNSAT *Step 10: Secure Vacuum Pump "A" bv placin~the selector switch to " O F I ~ and momentarily depressing the "OFF" PB. Standard: Operator positions Vacuum Pump "A" selector switch to "OFF", d e p esses
~
OFF push-button. S ATAJNSAT Step 11: Verifv Vacuum Pump "A" is stopped. Standard: Operator observes Vacuum Pump "A" red light off and green light on SATIUNSAT Step 12: Confirm AOV-OG-140A and AOV-OG-144A close. Standard: Operator observes AOV-OG-140A and 144A green light ON and red ight OFF.
,valuation Performance Steps JPM - S-2
JPM - S2 Rev. 01 1309 Page 5 of 6 SATNNSAT *Step 13: Return Vacuum Pump "A" selector switch to AUTO position. Standard: Operator positions Vacuum Pump "A" selector switch to AUTO on ( 'RP 9-6. SATNNSAT *Step 14: Shift PC-OG-1101I). VLV CONTROLLER FOR PCV-OG-501Bi& AUTO. Standard: Operator positions PC-OG-1 101 B, VLV CONTROLLER FOR PCV-OG-501B, to AUTO. SATNNSAT *Step 15: Slowly adjust valve flow controller PC-OG-1101B to set OG-501B to accomplish the following:
- a. Achieve an approximate balance between delav pipe flow (FI-2002) and svstem outlet flow (FI-2004).
- b. Achieve desired pressures on system inlet (PI-1301). on adsorbs "G" outlet (PI-13061, and on system outlet (PI-1307).
Standard: Operator adjusts PC-OG-1 lO1B as necessary to insure no alarms are sealed in. SATIUNSAT *Step 16: Place PC-OG-11OlA. VLV CONTROLLER FOR PCV-OG -5OlAb MANUAL to re vent unnecessary valve cvcling. Standard: Operator places valve controller PC-OG-1 1OlA in MANUAL. TIME FINISH: Terminating Cue: Shift from AOG Vacuum Pump A to AOG Vacuum Pump B is complete. Evaluators Comments: - ystem: 271000 KIA's: A4.09 JPM - S-2
JPM - S2 Rev. 011309 Page 6 of 6 nitial Conditions: Reactor is at 100% power Initiatin~Cues: The CRS directs you to shift from AOG Vacuum Pump A to AOG Vacuum Pump B, per OP 2150 Section S. JPM - S-2
JF'I I-S3 Rev. 01 1209 Page 1 )f 11 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Secure RHR from the Shutdown Cooling Mode Failure Mode: N/A
Reference:
OP 2124, Residual Heat Removal Svstem Task Number: 2050110101 Task Performance: AOIROISRO - ROISRO Only X SE Only - Sequence Critical: Yes - No 3 Time Critical: Yes - No 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: 12 minutes Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: Lo14
. ~k&/&c/#~, / 07 ,
Operations Training Instructor Date Reviewed by: /- 2-707 SRO ~icensedldertifie$ Reviewer Date Approved by: (2.,< /'ko,~rn
/ 7 4, ~,
/ 7-[/?
Operations ~ r d i $%pervisor n ~ Date
JPI I-S3 Rev. 01 1209 Page 2 )f 11 Directions: Discuss the information given on this page with the operator being evaluated. Allow time for him o ask questions before beginning performance of thc task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required f Ir any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s ep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measu -e. 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 condition!;, 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 2112, Reactor Water Cleinup System. The Condensate System is available. Initiating Cues: The CRS has directed you to secure from the Shutdown Cooling Mode in accordance with OP 2121, 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- 2 of Section J of OP 2 124, Residual Heat Removal System. Required Materials: Handout 1 - OP 2124, Residual Heat Removal System (Rev. 113)
JPI I -S 3 Rev. 01 1209 Page 3 bf 11 Simulator Setup: Reset to IC-852
JI'I 4-S3 Rev. 01 1209 Page 4 )f 11 Provide Candidate with Initial ConditionsICue (Last Page of this JPM). Evaluation Performance Steps TIME START: S ATIUNSAT Step 1: Obtain Procedure and review prerequisites 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 provide: copy (Handout 1). SATIUNSAT Step 2: (Step 1) If RWCU return to RHR SDC suction line is in service, return RWCU to normal alignment, or secure the RWCU svstervim OP 2112. Standard: The operator recognizes that the RWCU is NOT aligned with its return to RHR SDC (Initial Conditions), and proceeds to Step 2. SATRJNSAT *Step 3: (Step 2) On CRP 9-3, close OUTBD IN.JECTION, RHR-27A(BL Standard: The operator takes the RHR-27A control switch to CLOSE, and obsc rves the Green light ON, and the Red light OFF. The operator observes A RHR Pump amps and flow on FI-10-139A decreases. SATNNSAT *Step 4: (Step 3) Secure the runninp 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 RE IR Pump (Not Critical).
JF'I I-S3 Rev. 01 I209 Page 5 )f 11 Avaluation Performance Steps SATAJNSAT Step 5: (NOTE prior to Step 4) Reactor recirculation puma startup may be performed in ~arallelwith securing shutdown cooling. Standard: The operator reads the Note and proceeds to Step 4. SAT/UNSAT Step 6: (Step 4) If possible, start the recirc pump(s) at this time per OP ;jw Standard: The operator seeks direction regarding the operation of the Recirculzition 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 shc uld continue. SATAJNSAT 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 md observes the Red light ON and the Green light OFF. S ATIUNSAT 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.
JP! I-S3 Rev. 01 i209 Page 6 ~f1 1 Lvaluation Performance Steps S ATIUNSAT *Step 9: (Step 7) On CRP 9-3, close the follow in^: S/D CLG SUCTION, RHR-17 S/D CLG SUCTION, RHR-18 PUMP SUCTION, RHR-1SA PUMP SUCTION, RHR-1SC PUMP SUCTION, RHR-15B PUMP SUCTION, RHR-1SD Standard: The operator closes RHR-17 by taking the control switch to CLOSE, and 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 CLOSi;, 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 observt:~the Green light ON and the Red light OFF for RHR-15B. and determines the valve is CLOSED. The operator observes the Green light ON and the Red light OFF for RHR-ISD, and determines the valve is CLOSED. NOTE: The operator may close another valve before the one presently stroking closed is CLOSED. S AT/UNSAT Step 10: (Step 8) Place Isolation switch (Radwaste corridor) for shutdown cool in^ valves RHR-17/18 in LOCKOUT position. Standard: The operator contacts the A 0 and directs that the Isolation Switch for, RHR- 17118 be placed in the LOCKOUT position. Interim Cue: As the AO, Examiner inform the operator that the Isolation Switch for RHR-17/18 has been placed in the LOCKOUT position.
JPP 1-S3 Rev. 01 209 Page 7 ckf 11 dvaluation Performance Steps SATIUNSAT *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 KHR-13C by taking the Key control switch to OE'EN, 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 clear after this action. The operator observes the Red light ON and the Green light OFF, anrl determines that RHR-13B is OPEN. The operator observes the Red light ON and the Green light OFF, ant 1 determines that RHR-13D is OPEN. The operator opens KHR-16A by taking the control switch to OPEN, and observing the Red light ON and the Green light OFF. The operator observes the Red light ON and the Green light OFF, ancI determines that RHR-16B is OPEN. NOTE: The operator may close another valve before the one presently stroking closed is CLOSED.
JP14-S3 Rev. 0 1 1209 Page 8 )f 11 Evaluation Performance Steps SATIUNSAT Step 12: (Steps 10110.a) Establish keep fill pressure as follows: If conden ,& svstem pressure is available open RHR30A(B), RHR Loop A(Bi 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. SATIUNSAT Step 13: (CAUTION prior to Step 10.b) Reactor coolant temperature mu?*
<212"F to use this procedure section.
Standard: The operator reads the Caution and proceeds to Step 1O.b. YATAJNSAT Step 14: (Step 10.b) IF condensate transfer svstem will be used to provide keep fill water ....... Standard: The operator recognizes that the Condensate Transfer System will NfIT be used and proceeds to Step 11. SATLTNSAT Step 15: (Step 11) Openlcheck open and lock RHR Hx A(B) Inlet, RHR-23A(B). Standard: The operator directs that RHR-23A be checked open and that the va16re be locked in the open position. The operator directs that RHR-23B be checked open and that the val: e be locked in the open position. Interim Cue: Examiner cue operator that RHR-23A and RHR-23B are OPEN.
JF'I I-S3 Rev. 01 1209 Page 9 jf 11 Performance S t e ~ s Step 16: (NOTE prior to Step 12) Manually closing RHR-89A(B) with an RHRSW pump r u n n i n ~can result in lifting safetv relief valve SR-10-80A(B). Standard: The operator reads the Note and proceeds to Step 12.
*Step 17: (Steps 12112.a) When the RHRSW pump has run at least 10 ming-after the RHR pump is stopped. then secure the running RHRSVE pumps. Observe RHRSW DISCHARGE valve, RHR-89A(B), cla,ses 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 lipht OFF. The operator observes flow on FI-10-132A decreases to 0. NOTE: MCB Annunciator 9-3lK-4, RHR SW PUMP AIC Running, is expected to clear after this action. CUE: Steps 13, 14 and 15 will be completed by another operator. TIME FINISH: Terminating Cue: This JPM is complete. Evaluator Comments:
JPh I-S3 Rev. O l 209 Page 10 c f I 1
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. The A RHR Pump is in operation. The RWCU System is in its normal alignment in accordance with OP 2112, Reactor Water Clemup System. The Condensate System is available. Initiating Cues: The CRS has directed you to secure from the Shuttiown Cooling Mode in accordance with OP 212.~, Section J, Securing the Shutdown Cooling Mode.
JE'E I-S4 Rev. 01 i509 Page 1 )f 13 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Line-up for Primary Containment Spray Using Fire System to RHR Loop "P," Failure Mode: NA
Reference:
OE 3 107, OE Appendices, Appendix S. (Rev. 25) Task Number: 2000070501 Task Performance: AO/RO/SRO - 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 -X Discuss Setting: Classroom - Simulator Plant Performance Expected Completion Time: 17 minutes Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: /-)7-d,,7 Operations fr$ning Instructor Date Reviewed by: \J --R ~ C & J I < / 9707' SRO LicensedlCertified Reviewer Date Approved by: /* 27-09 Operations Training Supervisor Date
JI'1 I-S4 Rev. 01 1509 Page 2 )f 13 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 ft rr any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s ep 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 be in^ 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 and has been high for greater than 5 minutes. 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, Auxiliary Operators have been briefed and are standing by in the field to perform their required actims. NOTE: All communications with the A 0 should be made using the plant communications systems and NOT with the Examiner. Task Standards: Complete the valve line-up and spray the Torus using the Fire System to RHR from the Control Roc m. Reauired Materials: JPM-S4
JF'I I-S4 Rev. 01 1509 Page 3 )f 13 Handout 1 - OE 3107 OE Appendices, Appendix S (Rev. 25) Simulator Set-Up: Reset to any IC. Insert malfunction mfRR-OlA 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.
JYF I-S4 Rev. 01 509 Page 4 jf 13 1 Provide Candidate with Initial Conditions/Cue (Last Page of this JPM). Evaluation Performance Steps TIME START: SAT/UNSAT Step 1: Obtain Procedure Standard: The operator obtains OE 3 107, Appendix S, Rev 25. Proceeds 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). SAT/UNSAT Step 2: (NOTE prior to Step 2.a) Substep 2.a may be performed concurrently with the remainder of Step 2. Standard: The operator reads the Note, and proceeds to Step 2.a SAT/UNSAT Step 3: (Steps 2.al2.a.l) Isolate unnecessary Service Water loads as follo\vs: Close /Check Closed the follow in^ 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 closed. Interim Cue: Simulator Instructor as the A 0 reports SW-92A and SW-92B closed (Use rfSW-15) NOTE: The operator may assign the A 0 to perform more than one procedure step during ont3 communication.
JFr 1-S4 Rev. 01 1509 Page 5 rf 13
+ 'valuation Performance Steps SATIUNSAT Step 4: (Step 2.a.2) CLOSEIcheck CLOSED the followins to isolate Turi ,&
Buildins loads: SW-20 TURB BLDG INLET OR SW-19A SW HEADER CROSS CONNECT and SW-19B SW HEADER CROSS CONNECT Standard: The operator checks SW-20 on CRP 9-6 shut by observing Green lig'lt ON and Red light OFF. OR The operator checks SW-19A on CRP 9-6 shut by observing Green 1 ght ON and Red light OFF. and The operator checks SW-19B on CRP 9-6 shut by observing Green light ON and Red light OFF. NOTE: The operator should perform only one or the other, however performance of both steps is allowed. bAT/UNSAT Step 5: (Step 2.a.3) Consider isolatin~RRUs to provide increased flow ta& vessel bv closing the follow in^ valves: SW-315A RRUS Inlet SW-316A RRU-6 Inlet SW-317A RRU-7 Inlet SW-318A 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 isolated.
JF'! I-S4 Rev. 0 1 i 509 Page 6 ,)f13
'valuation Performance Steps SAT/UNSAT 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 ST01 pushbutton with the REMOTEIAT ENGINE control switch in A 1 ENGINE.
Standard: The operator reads the Note and proceeds to Step 2.a.4. S AT/UNSAT Step 7 (Step 2.a.4) If a diesel generator is idling with the output breakel open, THEN consider shutting down the diesel to provide increa.;ed flow to the vessel. Standard: The operator observes that both Diesel Generators are shutdown. SATIUNSAT Step 8: (Steps 2.bl2.b.112.b.2) If the Fire Water pumps are running, THEN stop the Fire Water pump(s) 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 Pan.:l9-6, J-9, DJESEL 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 Pants1 9-6, J-9, DIESEL FIRE PUMP RUNNING, and L-9, ELEC FIRE PUMP RUNNING, are DARK and determines that both Fire Water pumps as-e shutdown.
JP! I-S4 Rev. O l 509 Page 7 ( f 13 valuation Performance Steps SATNNSAT *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. SATKINSAT Step 10: (Steps 2.dl2.d.l) IF RHR loop A is available, THEN Closelcheck closed RHR 34A TORUS COOLING. Standard: The operator checks shut RHR-34A by observing Green light ON an*1 Red light OFF. SATNNSAT Step 11: (Steps 2.d.212.d.2.a) If a LPCI initiation signal is or was present THEN: In CRP 9-32, locate 10A-K45A-1. timin~device for relati 10A-K45A. Standard: The operator opens cabinet in back of CRP 9-32 and identifies timini. device. SATNNSAT Step 12: (Step 2.d.2.b) Rotate set screw in 10A-K45A-1fully in the counte!: clockwise direction, to disable the time delay logic for RHR-27A. Standard: The operator obtains a screwdriver. The operator uses screwdriver to turn set screw counter clockwise un. il it stops rotating. SATIUNSAT *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 t.) BLOCK. The operator observes MCB Annunciator 9-3/C-2, RHR-27A AUTO OPEN/UPS FDR TRIP BLK, is LIT.
JPF I-S4 Rev. 01 509 Page 8 ~f13 1
,valuation Performance Steps SATIUNSAT *Step 14: (Steps 2.d.3) Closelcheck closed one of the followine:
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 Rff R-27A is CLOSED. SATIUNSAT Step 15: (Steps 2.d.4) Go to Step 2.f. Standard: The operator proceeds to Step 2.f. SATIUNSAT Step 16: (Steps 2.fl2.f.l) Start available Fire Pumps bv perform in^ the follow in^: 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, Sirnulator Instructor place rfFP-01 to HAND. THEN, call operator as A 0 and report that the Electric Fire Pump is Running. SATIUNSAT Step 16a: (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.
JPF I-S4 Rev. 0 l 509 Page 9 ( f 13 valuation Performance Steps SATNNSAT *Step 17: Verify both Fire Pumps are running Standard: The operator checks status of Fire Pumps by checking alarms on Pan :l 9-6, J-9, DIESEL FIRE PUMP RUNNING, and L-9, ELEC FIRE PUlv P RUNNING, are LIT and determines that both Fire Water pumps are operating. SATLTNSAT *Step 18: (Step 2.d2.g.l) OPEN RHR-89A RHRSW DISCHARGE as follo Place RHR-89A TEST keylock switch 10AS89Al to TEST Standard: The operator uses the 89AlB Test Switch Key and places the switch to TEST. The operator observes MCB Annunciator 9-3lM-2, RHR KEYLOCK SW TO MAN OVRD, is LIT. SATIUNSAT *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 for RHR-89A to return to AUTO. SATIUNSAT *Step 20: (Step 2.h) OPEN RHRSWIRHR emergency inter-tie keylock v a l a a RHR-184 EMERGENCY FILL RHR-183 EMERGENCY FILL Standard: The operator uses Key #13 places the Key Lock switch for RHR-184 to OPEN and observes the Red light ON and Green light OFF. The operator uses Key #13 places the Key Lock switch for RHR-183 to OPEN and observes the Red light ON and Green light OFF. SATIUNSAT Step 21: (CAUTION prior to Step 2.i) It may be necessary to throttle spray flow using SW-8 to prevent overloading the Fire Water system pump(s). Standard: The operator reads the Caution and proceeds to Step 2.i.
JPI 4-S4 Rev. 01 1509 Page 10 )f 13
'valuation Performance Steps SATLJNSAT Step 22: (Step 2.i12.i.l) When Spray is required THEN: Place RHR AIC:
LOGIC CTMT SPRAY VLV SHROUD LVL OVRD Keylock 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. SATLJNSAT *Step 23: (Step 2.i.2) Place RHR A/C LOGIC CTMT SPRAY VLV LPCI @b BYPASS (pistol grip) to MAN. Standard: The operator momentarily places the RHR A/C LOGIC CTMT SPR 4Y VLV LPCI SIG BYPASS Pistol grip switch to MAN and releases tha: switch (spring retunls to OFF). Step 24: (NOTE prior to Step 2.i.3) Torus and Drywell sprays may be operated concurrently. Standard: The operator reads the Note and proceeds to Step 2.i.3.
*Step 25: (Step 2.i.312.i.3.a) For Torus Spray: OPEN RHR-39A TORUS SPRAYICLG Standard: The operator places the control switch for RHR-39A to OPEN and observes Red light ON and Green light OFF.
SATLJNSAT *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-10-132ri,. SATLJNSAT *Step 27: (Step 2.i.3.c) CLOSEIcheck CLOSED RHR 89A. RHRSW DISCHARGE Standard: The operator places the control switch to CLOSE and observes the Creen light is ON and the Red and White light is OFF. SATLJNSAT *Step 28: (Step 2.i.3.d) Place RHR 89A TEST keylock Switch 10AS89A-11, AUTO and remove kev. Standard: The operator uses Key #13 and places the RHR 89A TEST keylock JPM-S4
JF'I J-S4 Rev. 011509 Page 11 )f 13 switch to AUTO and removes the key from keylock switch. TIME FINISH: Terminating Cue: This JPM is complete.
JPI 4-S4 Rev. 01 1509 Page 12 bf 13
'valuators Comments:
System: 226001 WA: A4.02 (3.113.1)
EXAMINEE HANDOUT Initial Conditions: Drywell pressure is high. 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. Initiatin~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. Auxiliary Operators have been briefed and are standing by in the field to perform their required actaons. NOTE: All communications with the A 0 should be made using the plant communications systems and NOT with the Examiner.
J P M-S5 Rev. 0 1509 Page of 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 2183. Turbine Building Closed Cooling 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: AOIROISRO - ROISRO Only X SE Only - Sequence Critical: Yes - No 2 Time Critical: Yes - No 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 minum Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: N/-/ ~h/B/flg&/ /-27-09 Operations ~ X i n i Instructor g~ Date
,-3 Reviewed by: LT &'. f$-(:, 3 / c) & f9w[L c d - / *27 (27 SRO ~icensedlcerti4'ieddeviewer Date Operations ~ r a i n i n ~ S u ~ e f v i s o r Date
JP! I-S5 Rev. 01 i509 Page 2 of 8 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 ft a any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s ep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measu e. 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. TnitialConditions: 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. Initiatin~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 act~ons. 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 c f the RBCCW Pump B.
JE'I A-S5 Rev. 01 1509 Page : of 8 leauired 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-0 I B, RBCCW PUMP I3 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.
JPP. I-S5 Rev. 01 509 Page 4 of 8 Orovide Candidate with Initial ConditionsICue (Last Page of this JPM). Evaluation Performance Steps TIME START: SATNNSAT 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). SATNNSAT "Step 2: (Step 1) Start the standbv 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 Greefi light OFF. The operator observes increasing pressure on PI-104-19. SATAJNSAT *Step 3: (Step 2) Allow system pressure to stabilize. then secure the first pump and place its control switch in AUTO. Standard: The operator observes PI-104-19 stabilizes at =:I05 psig, and determines that RBCCW pressure has stabilized. The operator places KBCCW Pump A control switch in STOP, and releases to AUTO, artd then observes the Green light ON and the Red light OFF. The operator observes PI-104-19 stabilizes at -77 psig, and determines that RBCCW pressure has stabilized.
JPh l-S5 Rev. 0 l 509 Page 5 of 8 Yvaluation Performance Steps SATIUNSAT 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 standby TBCCW PUMP A(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 observt:~increasing pressure on PI-104-52. S ATNNSAT Step 6: (NOTE prior to Step 2) Annunciator 6-5-8, TBCCW HDR PREf@ LO may come in while performing the next step. Standard: The operator reads the Note and proceeds to Step 2.
JFT I-S5 Rev. 01 509 Page t of 8 Yvaluation Performance Steps SATNNSAT *Step 7: (Step 2) Allow svstem 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 1 psig, 0 and deternii les 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 Rec light OFF. The operator observes PI-104-52 stabilizes at ~ 6 psig, 5 and determin:~ that TBCCW pressure has stabilized. Simulator Instructor: When the operator stops TBCCW F'ump A, operate Key 1, which will cause RBCCW 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 Green/Yellow lights ON for RBCCW Pump B, and determines that the running RBCCbr Pump B has tripped and that RBCCW Pump A has failed to start. SATNNSAT *Ste s 8: . ~
- 1) If an automatic control malfunctions, immediatelv place that control in manual.
OR Ensure that the standbv RBCCW pump is runnine. Standard: The operator places RBCCW Pump A control switch in START, and releases to AUTO, arid then observes the Green and Amber lights ON and the Red light OFF. The operator observes PI-104-19 stabilizes at ~ 7 psig, 7 and determints that RBCCW pressure has stabilized. NOTE: MCB Annunciator 9-6L-8 will dear when RBBCW Pump A is restarted. TIME FINISH:
'erminating Cue: This JPM is complete.
JPb I-S5 Rev. 0 1 509 Page 7 of 8 Yvaluator Comments: System: 400000 KIA: A2.01 (3.313.4)
EXAMINEE HANDOUT initial Conditions: The plant is operating at power. Scaffolding is being erected around RBCCW 13umpA 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 act ions.
JPP I-S6 Rev. 01 209 Page 1 of 7 VERMONT YANKEE JOB PERFORMANCE NIEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Initiate SLC to the Vessel Failure Mode: RWCU Fails to Isolate
Reference:
OP 2114, Operation of the Standby Liquid Control System Task Number: 2110050101 Task Performance: AOIROISRO - ROISRO Only X SE Only - Sequence 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: 5 minutes Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: ,& / d ? Operations raini in^ Instn~ctor Date y
& b,,-,+&&
,,- 7 Reviewed by: J
.( / . 2 7 . -(lp SRO ~ i c e n s e d l ~ e f t i f i d ~ e v i e w e r Date 4pproved by: J ~cQ~II;;/ (;3 / 7-[)7 Operations ~ r a i d suierintendent n~ Date
JPE I-S6 Rev. 01 209 Page 2 of 7 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 r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical sr ep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measill e. 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 Appendix B, Injecting SLC Into the Reactor Vessel, of OP 2114, Operation of the Standby Liquid Control System. Task Standards: Boron is injected to the reactor vessel in accordance: with Appendix B of OP 2114. Rewired Materials: Handout 1 - OP 21 14, Operation of the Standby Liquid Control System (Rev. 33)
JF'P I-S6 Rev. 0 1 i 209 Page 3 of 7 jimulator 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 to Manual Scram, mfRP-OlC, Failure of ARIJRPT) 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-02A, SL Squib Valve A Fails to Fire Insert mfSL-02B, SL Squib Valve B Fails to Fire Will need to remove one of the two malfunctions during the performance of the JPM.
JPF I-S6 Rev. 0 1 209 Page 4 of 7
.'rovide Candidate with Initial ConditionsICue (Last Page of this JPM).
Evaluation Performance Steps TIME START: SATIUNSAT Step 1: Obtain Procedure. Standard: The operator obtains OP 21 14, Rev 33. Proceeds to Appendix B, Lnjecting SLC Into the Reactor Vessel. Interim Cue: When it is apparent that the operator is seeking to find OP 2114, Examiner provides copy (Handout 1). SATIUNSAT Step 2: (NOTE prior to Step 1) Unless specified otherwise, all controls an@ indications are on CRP 9-5. Standard: The operator reads the Note, and proceeds to Step 1. SATIUNSAT *Step 3: (Step1)Unlock SLC Switch bv positioning the key to the two o'clock position. Standard: The operator places Key in the SLC Switch to the two o'clock (right hand) position. SATIUNSAT *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 i*, OFF. SATIUNSAT Step 5: (Steps 313.a) Verifv the following events occur: SLC PUMP A(B) P-45-lA(B) starts. Standard: The operator observes that SLC Pump A is running by observing the Red light ON and Green light OFF.
JE'f I-S6 Rev. 01 1209 Page ,' of 7 {valuation Performance Stem SATKJNSAT Step 6: (Step 3.b) SLC discharpe pressure increases as indicated on PI-11-65. Standard: The operator observes rising pressure indicated on PI 11-65, stabilizing at -1500 psig. SATKJNSAT "Step 7: (Step 3.c) On CRP 9-4, RWCU system isolation valves automatic& close: CU-15 (Outlet Isolation) CU-18 (Inlet Isolation) CU-68 (Return Isolation) Standard: The operator observes valve position for CU valves and recognizes that the RWCU System (lid 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 closed. 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 thcn return to Step 7. SATIUNSAT Step 8: (NOTE prior to Step 3.d) SLC discharge pressure cycling at relie,! valve setpoint (1400-1490 psig) may indicate failure of squib valve* fire. Standard: The operator reads the Note and proceeds to Step 3.d.
JPI' 1-S6 Rev. 0 1 !209 Page 6 of 7 Performance Steps SATAJNSAT Step 9: (Step 3.d) Squib valve SLC-14A(B)fires, as indicated bv: Red flow indicator light on (flow greater than 30 gpm). SLC tank level decreases as indicated on LI-11-66. Standard: The operator observes the Red light OFF.
*Step 10: (Step 4) If the above actions did not result in SLC injection, then turn the SLC switch to the other position (SYS 2 or SYS 1). 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, stabilizing 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: 211000 WA: A4.02 4.214.2
EXAMINEE HANDOUT 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 Appen iix B. Injecting SLC Into the Reactor Vessel, of OP 2114, Operation of the Standby Liquid Control System.
JPM-S7 Rev. 011209 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 K V Electrical System Task Number: 2620010101 Task Performance: AOIROISRO - ROISRO X SRO Only - Sequence Critical: Yes - No 3 Time Critical: Yes - No 3 Operator Performing Task: Examiner: Date of Evaluation: - Activity Code: - Method of Testing: Simulation - Performance -hDiscuss Setting: Classroom - Simulator X Plant Performance Expected Completion Time: 5 rninutes Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: L,-'/ 7-47 I Date
--~ ,7 &..Y Q.
Reviewed by: 1' -R- EmaC,i/ 9 $,. 4 , cz,7Pv ' 4 /'- 9-7 p 7 SRO ~ i c e n s e d / ~ k r t i fReviewer id Date Approved by:
- e (;~i 4; /g-5 yq Operations ~ r a i n i f~L~erintendent i~
,,'/
j%itVlt;. A
/ -% 7 . ~ 7 Date
JPM-S7 Rev. 01 1209 Page 2 of 7 Discuss the information given on this page with the operator being evaluated. Allow time for hirr~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 Ir any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s ep 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 be in^ 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 throu~h"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 Transforn ~ e r per Section D of OP 2142,4 KV Electrical System. Task Standards: Station loads are transferred from the Auxiliary to Startup Transformer. Reauired Materials: Handout 1 - OP 2142,4 KV Electrical System Simulator Set-Up: Reset to IC-856
JPM-S7 Rev. 01 1209 Page 3 of 7 "rovide Candidate with Initial ConditionsICue (Last Page of this JPM). Evaluation Performance Steps TIME START: SATIUNSAT Step 1: Obtain Procedure
, Standard: The operator obtains OP 2142.
Proceeds to Section ID, 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, ra?her than in a normal situation, and is kept in a side pocket on the MCB so that it is readi y 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) Verifv that startur, transformers are powered from 115Ey yard. Standard: The operator observes that power indicated on 115 KV meter on CRF 9-8. The operator checks 115 KV line-up to the S/Up transformers. SATtUNSAT Step 3: (Step 1.a) If auto transformer is not supplying the 115 KV vard.., : Standard: The operator observes that the Auto Transformer is supplying the 1 1f KV Yard, and procee:ds 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 Rev. 0 11209 Page 4 of 7 ,valuation Performance Steps SATAJNSAT *Step 5: (Step 2) Insert svnc check handle in BKR 13 socket and turn svnc: switch on. Standard: The operator inserts the 4KV sync check handle into breaker 13 switc h on CRP 9-8 and turns sync check switch to ON. SATIUNSAT Step 6: (Step 3) Verify bus 1 in phase with startup transformer (svnchroscope at 12 o'clock position). Standard: The operator observes that the synchroscope is at 12:OO position, Wh te lights OUT, Red lights ON. SATIUNSAT Step 7: (CAUTION prior to Step 4) If thev are not In Phase, do not transfer. Standard: The operator reads the Caution, and proceeds to Step 4. SATIUNSAT *Step 8: (Step 4) Close BKR 13. Standard: The operator places the switch for breaker 13 on CRP 9-8 to CLOSE and 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 lclads to the Startup Transformer (Not Critical). SATNNSAT Step 9: (Step 5) Check that BKR 12 trips open when BKR 13 switch is released Standard: The operator verifies Breaker 12 open by observing Green and Amber. lights ON above breaker 12 control switch on CRP 9-8. SATNNSAT Step 10: (Step 6) Reset BKR 12 amber light. Standard: The operator places the switch for breaker 12 on CRP 9-8 to TRIP anti then releases. The operator observes the Amber light OFF above breaker 12 switch ,n CRP 9-8.
JPM-S7 Rev. 0 11209 Page 5 of 7 Yvaluation Performance Steps SATAJNSAT *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 sock :t. SATJUNSAT Step 12: (NOTE prior to Step 8) Steps 8 through 13 onlv applv if Bus 2 is available and is to be place in service. Standard: The operator reads the Note and proceeds to Step 8. SATLTNSAT *Step 13: (Step 8) Insert sync check handle in BKR 23 socket and turn synt; switch on. Standard: The operator inserts the 4KV sync check handle into breaker 23 switch on CRP 9-8 and turns sync check switch to ON. SATAJNSAT Step 14: (Step 9) Verify bus 2 in phase with startuv 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. SATAJNSAT Step 15: (CAUTION prior to Step 10) If thev are not In Phase, do not transfer. Standard: The operator reads the Caution, and proceeds to Step 10. SAT/UNSAT *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 on CRP 9-8. SATmNSAT 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 Ambe1 lights ON above breaker 22 control switch on CRP 9-8.
JPM-S7 Rev. 0 11209 Page 6 of 7 Performance Steps Step 18: (Step 12) Reset BKR No 22 amber li~ht. Standard: The operator places the switch for breaker 22 on CRP 9-8 to TRIP a1 d then releases. The operator observes the Amber light OFF above breaker 22 switch on CRP 9-8. Step 19: (Step 13113.a) Turn sync check handle OFF and remove from sot ket, Place svnc 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 sock::t. The operator places the synch handle on CRP 9-8 TIME FINISH: - Terminating Cue: This JPM is complete. Evaluators Comments: System: 26200 1 K/A: A4.04 (3.613.7)
EXAMINEE HANDOUT ~nitialConditions: 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 Transfort ner per Section D of OP 2142,4 KV Electrical System.
JPF I-S8 Rev. 01 !I09 Page 1 of 7 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 - ROJSRO Only X SE Only - Sequence Critical: Yes - No 3 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: 8 minute~ Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: Reviewed by: 1.-2-7 07 SRO ~icensed/C!ertiff/edReviewer Date ipproved by: 3 A'. &G7kJL i.
.%7-{qp I
Operations ~ r a i d Stperintendent n~ Date
JPP I-S8 Rev. 01 :lo9 Page 2 of 7 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 r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s ep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measul e. 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 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 plant startup is in progress in accordance with Phase 1A of OP 0105,Reactor Operations. The procedure is complete through step A.26 (Page 21 of 152). The control rods have been withdrawn in the specified sequence of OP 2404. There have been two (2) doublings, and these are recorded on VYOPF 0105.03. 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 S t e ~27 of OP 0105,Reactor Operations (Page 20 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.
JPF I-S8 Rev. 01 !I09 Page 3 of 7
',equired Materials:
Handout 1 - VYOPF 0105.03 with doubling count rates filled in as follows: .. . Reactor Startup: I X In-Sequence: I 7 SRM A 13 SRM C 12 SRM B SRM D Time 0800 Initial initialci 4 Handout 2 - VYOPF 2404.01 (Page 1) filled in as follows: Handout 3 - OP 0105, Reactor Operations, (Rev 86.)
'mulator Setup:
JPM-S8
JPI I-S8 Rev. 01 !I09 Page of 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:
C 120 is on the CRP 9-3 Digital Display. B023 is on the CRP 9-4 Digital Display. C 121 is on the CRP 9-7 Digital Display
- 5. Initialize the Rod Worth Minimizer
JPF I-S8 Rev. 01 '.I09 Page 5 of 7
'rovide Candidate with Initial ConditionsICue (Last Page of this JPM) along with Handouts 1 and 1 .
Evaluation Performance Steps TIME START: - SATLTNSAT *Step 1: (Step 27) Continue to withdraw control rods in such a manner a& avoid havinp a sustained period shorter than 30 seconds (desiredm to 200 seconds). Standard: The operator places the Rod Select Power Switch to ON. The operator depresses the 10-39 Select Pushbutton, and observes t h ~ : White Pushbutton light is ON, and the White Rod Out Permit light GN 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 Swit:h to NOTCH OUT ancl observes the Red Rod Out light ON. The operator observes the SRM level indications (7-43A through D) ,or increasing count level. The operator observes the SRM period indications (7-44A through D I 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.
JF'! I-S8 Rev. 01 !lo9 Page 6 of 7
'ATNNSAT *Step 2: (Step 28128.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 9-51P-5, SRM PERIOD SHORT. The operator observes that SRM Period indicator 7-44D indicates a 5 hort 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. SATIUNSAT *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 071 SRM Period indication 7-44A through D, and stable SRM level indications (7-43A through D). SATNNSAT Step 4: (Step 28.c) Notifv the Shift M a n a ~ e rOperations
, 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: Yystem: 215004 KIA: A4.01 (3.913.8) JPM-S8
EXAMINEE HANDOUT Initial Conditions: A plant startup is in progress in accordance wilh Phase 1A of O P 0105, Reactor Operations. The procedure is complete through step A.26 (Page 21 of 152). The control rods have been withdrawn in the specified sequence of OP 2404. There have been two (2) doublings, and these are recorded on VYOPF 0105.03. The next control rod to be withdrawn is Rod 10-39. Initiatinp Cues: The CRS directs you to continue the startup and take the reactor critical starting with Phase 1A Ste;) 22 of OP 0 105, Reactor Operations (Page 20 of 152).
JPb I-P1 Rev. 0 1 509 Page 1 of 8 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Place Charger BC 1 B in Service Failure Mode: N/A
Reference:
OP 2146, Operation of Station and Alternate Shutdown System 125-Volt Ba terv Chargers. (Rev. 2 1) Task Number: 2630070104 Task Performance: AOROISRO X ROISRO Only -.- SE Only - Sequence Critical: Yes X No Time Critical: Yes - No 2 Individual 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:
,- 9 Performance: PASS - FAIL - Time Required:
Prepared by: LL/ // S L L /x/,&A& 27 -3 Operations raini in^ Instructor fl Date Reviewed by: i 7-C? SRO ~icensed~ertifi6d Reviewer Date Approved by: /.27-~<'? Operations ~ r h i n g ~ u ~ e r i n t e n d e n t Date
JPb I-P1 Rev. 0 l 509 Page 2 of 8 Discuss the information given on this page with the operator being evaluated. Allow time for him 3 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 sr ep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure. After providing the initiating cue, ask the individual "Do you understand the task?" Read to the person be in^ 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-throueh" the procedure, stating the parameters you are verifying or checking and the steps you are performing. Inform me upon completion of this task. Tnitial Conditions: There is currently no battery charger supplying power to DC Bus 2. Electrical Maintenance personilel are available for support if needed. Initiating Cues: The CRS has directed you to place the BC 1B Battery Charger in service in accordance with Sect ion B of OP 2146. Task Standards: Battery Charger BC 1B is placed in service. Required Materials: Handout 1 - OP 2146, Operation of Station and Alternate Shutdown System 125-Volt Battery Chargers (Rev. 21) Setup: Provide examiner with pictures of DC-1 & DC-2
JPE I-P1 Rev. 0 1 509 Page 3 of 8 Provide Candidate with Initial ConditionsICue (Last Page of this JPM). dvaluation Performance Steps TIME START: S ATAJNSAT 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 Servi :e. Interim Cue: When it is apparent that the operator is seeking to find OP 2146, Examiner provides copy (Handout 1). SATLTNSAT Step 2: (NOTES prior to Step 1) This procedure section assumes that no c h a r ~ e rare s in service. Use Section D for transfer. These instructions are for BC-1-1B. Use the description in parentheses for BC-1-ID. Standard: The operator reads the Notes and proceeds to the Caution prior to Step 1. SATLTNSAT Step 3: (CAUTION prior to Step 1) Tripping and damage of DC components mav occur if the battery is not tied to its respective b u s Standard: The operator reads the Caution and proceeds to Step 1. SATAJNSAT +Step 4: (Step1) Close/check closed DC-2 125 VDC MAIN BREAKER. Standard: The operator verifies that the DC-2 125 VDC Main Breaker is shut b; observing the breaker position indicating flag in the CLOSED (Red) condition. Interim Cue: After checking, Examiner inform Operator that the breaker position indicating flag i: Red. JPM-PI
JPP I-P1 Rev. 0 1 1 509 Page 4 of 8 Yvaluation Performance Steps AATIUNSAT +Step 5: (Steps 2.a-d) At MAIN STATION BATTERY CHARGER BC {BC-1-ID), perform the follow in^: Openlcheck open the AC BREAKER (Input). Openlcheck 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 positi~n. Standard: The operator verifies that the BC 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 positim. Standard: The operator observes that the BC-1-1B Equalize timer is set to zero (0). 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 beet1 turned 10 turns in the Counter-Clockwise direction. S AT/UNSAT +*Step 6: (Step 3) Closelcheck closed Ckt. 6, BATTERY CHARGER BC-1.m on DC-2 (Ckt. 5, BATTERY CHARGER BC-1-1D on DC-2). Standard: The operator closeslchecks closed the Ckt. 6 breaker on DC-2 by positioning the break.er handle to the ON (Left) position.
~ t e r i mCue: After checking, Examiner inform Operator that breaker handle is in the Left position.
JPM-P1
JPP I-PI Rev. 01 509 Page 5 of 8 valuation Performance Steps SATfUNSAT +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 Iiy 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 i i Green. Standard: The operator verifies; that the DC-2 TIE TO DC-1 Breaker is OPEN 11y 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 i 5 Green. SATAJNSAT +*Step 8: (Step 5 ) At MCC-9A (9B), close/check closed the 125 VDC BATTERY CHARGER BC-1-1B (BC-1-ID) breaker. Standard: The operator closes/checks closed the 125VDC Battery Charger breaiker by observing the breaker handle in the ON (UP) position. Interim Cue: After checking, Examiner inform Operator that the breaker handle in the UP positioli. SATAJNSAT +*Step 9: (Step 616.a) At MAIN STATION BATTERY CHARGER BC-1-12 {BC-1-ID): Close the DC output breaker. Standard: The operator closes the DC output breaker by positioning the breaker handle to the ON (Up) position. lterim Cue: After action, Examiner inform Operator that the breaker handle in the UP position. JPM-P1
JYT I-P1 Rev. 01 1509 Page t of 8 Yvaluation Performance Steps SATAJNSAT +*Step 10: (Step 616.b) At MAIN STATION BATTERY CHARGER BC B {BC-1-ID): 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. SATRJNSAT +*Step 11: (Step 6.c) Increase voltape by turning the Float Adiust Pot clocks& slowly 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 lC0 amps Werim Cue: When Operator indicates that he is rotating the potentiometer slowly clockwise, Examiner inform Operator that voltage is approximately 132 volts and that current i!> approaching 100 amps. SATAJNSAT Step 12: (Step 7) Request assistance from Electrical Maintenance for final calibration of the charper 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 Electricia 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
JPT I-P1 Rev. 01 i 509 Page 7 of 8 Yvaluator Comments: System: 263000 WA's: A3.0 1 (3.213.3)
EXAMINEE HANDOUT Initial Conditions: There is currently no battery charger supplying power to DC Bus 2. Electrical Maintenance person iel are available for support if needed. Initiating Cues: The CRS has directed you to place the BC 1B Battery Charger in service in accordance with Sect ion B of OP 2146. NOTE: All actions must be simulated. At NO time shall any plant equipment be operated.
JPI I-P2 Rev. 01 1509 Page I )f 11 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Boron Iniection from the S I X Tank Using the CRD System Failure Mode: N/A
Reference:
OE 3 107, Appendix K, Boron Iniection Using CRD System from the SLC 'Imk. (Rev. 25). Task Number: 2007600501 Task Performance: AOIROISRO X ROISRO 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 Performance Expected Completion Time: 20 minu= Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: /-2-7-u,? I Date Reviewed by: r- 1 fi,.[-&i-clo f - <>A'. .- /
-'J 7 ,
1.2 -7 fly SRO ~ i c e n s k d l ~ d i f i eReviewer d Date
-1
/~ ~ d a t i&'oTraining 3
Approved by: ,d-R fa ~CAL-~ ~ 2 :k'A{ L /-*a 7( 7
~u~erintendeht ns Date
JPP I-P2 Rev. 0 1 509 Page 2 jf 11 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 r any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s ep is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measu: e. 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 q~restionsyou 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: An ATWS has occurred. The EOPs have been entered. The SLC Tank is available. CRD Pump B is in service and CRD Pump A is in Standby. Initiating Cues: The CRS directs you to line up the CRD System for boron injection from the SLC Tank in accorda,~ce with OE 3107, Appendix K, to CRD Pump B. Inform the Control Room when the CRD Pumps car I 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 3107, Appendix K Required Materials: Handout 1 - OE 3107, Appendix K, (Rev. 25) Pictures of:
- 1. Fitting on SLC Tank Drain
- 2. Fitting going into check valve
- 3. Ends of hoses
'mulator Setup: N/A
JPE I-P2 Rev. 01 : 509 Page 3 ~f11 Provide Candidate with Initial ConditionsICue (Last Page of this JPM). Evaluation Performance Steps TIME START: SATAJNSAT 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 Eauipment Standard: Tools, fittings, and hose acquired from EOP Toolbox located in the Reactor Building (318' elevation) interim Cue: Inform Operator that necessary tools, fittings, and hose have been acquired. SAT/UNSAT *Step 3: (Steps 1.a-d) Establish a flowpath from the SLC tank to the CRO pumps usinp the following hose route: From the SLC tank on thrt 318' elevation down the pipe chase on West wall labeled EOP SL!C Pipe Chase, Down the pipe chase on 303' elevation labeled EOP Pipe Chase, Down the pipe chase on the 280' elevation labeled E(E SLC Pipe Chase, Down the HPCI hatch on the 252' elevation to t: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 SLO pipe chase on RB 318' elevation west, down through the EOP pipe cFase on RB 303' and 280' elevations, and down through the equipment hatch on the 252' elevation to the CRD Pumps. Interim Cue: As each step of hose routing is simulated, Examiner inform Operator that hose has b,:en routed and connected.
JPh I-P2 Rev. O l 509 P a g e 4 ( f 11
'valuation Performance Steps SATNTNSAT *Step 4: (Step 212.a) At the SLC tank: CLOSElconfirm CLOSED SLC-23 Standbv Liquid Control Tank Drain.
Standard: The operator verifies that SLC-23 closed by rotating the valve operat ing handle in the clockwise direction. Interim Cue: After the simulated action, Examiner inform the operator that the valve operating dc 2s not move. SATNTNSAT *Step 5: (Step 2.b) Remove Pipe Cap from the 1 '/z inch tank drain. Standard: The operator removes the pipe cap from the 1 112-inch tank drain. Interim Cue: After the simulated action, Examiner inform Operator that the pipe cap is OFF. SATXTNSAT *Step 6: (Step 2.c) Connect hose adaptor to the tank drain. Standard: The operator connects a hose adaptor to the drain tank. ~nterimCue: After the simulated action, Examiner inform Operator that the hose adaptor is installed. SATNTNSAT *Step 7: (Step 2.d) Connect Hose Standard: The operator connec1.s 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. SATNNSAT Step 8: (Step 2.e) Place the SLC tank heater control switch to ONIlocatet$on side of large junction box, Rack 25-19, Rx Bldg. elevation 318'). Standard: The operator rotates !:heSLC 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.
JPI I-P2 Rev. 01 509 Page 5 ~af11 Performance Steps Step 9:(Steps 313.a) In the CRD pump room: CLOSElconfirm CLOSED the following valves: DW-65 CST Header Demin Water Is01 DW-66 CST Header Demin Water Is01 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 n+)t 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 ni)t move. CATI'UNSAT *Step 10: (Step 3.b) Remove top f l a n ~ from e check valve DW-67 (located between DW-66 and DW-65) and replace with mechanical bvpassr f l a n ~ with e 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. and the hose connection flange is installed. SATNNSAT *Step 11: (Step 3.c) Connect hose to bypass flange Standard: The operator connects the SLC suction hose to the mechanical bypass flange. hterim Cue: After the simulated action, Examiner inform the operator that the SLC suction hose 3 s connected to the mechanical bypass flange.
JF'I' 1-P2 Rev. 01 509 Page 6 gf 11 1 Yvaluation Performance Steps SATNNSAT *Step 12: (Step 3.d) Request the Control Room to secure both CRD pumps, and verifv neither are runninp prior to con ti nu in^ with this procedure. Standard: The operator contacts the Control Room and requests both CRD Pun ps be secured. Interim Cue: When requested, Examiner inform Operator that both CRD Pumps are secured. Standard: The operator enters he 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.
~ t e r i mCue: After the simulated action, Examiner inform the operator that the handwheel rotated clockwise, and has now stopped.
SATIUNSAT *Step 14: (Step 3.f) OPEN DW-66, CST Header Demin Water Isol. Standard: The operator opens IIW-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. SATIUNSAT *Step 15: (Step 3.p) OPEN CRD-158A (B), CRD Pump A (B)Suction Filter Bypass. 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.
JPF I-P2 Rev. 01 509 Page 7 ttf 11 Evaluation Performance Steps SATIUNSAT *Step 16: (Step 3.h) CLOSE CRD-35A (B), CRD Pump A (B) Suction Filte : Inlet. Standard: The operator closes CRD-35B by rotating handwheel in the clockwise direction. Interim Cue: After the simulated action, Examiner inform the operator that the handwheel rotatec clockwise, and has now stopped. SATAJNSAT *Step 17: (Step 3.i) CLOSE CRD-37A (B), CRD Pump A (B) Main Flow St= Check, to maximize CRD flow to the reactor vessel. Standard: The operator closes CRD-37B by rotating handwheel in the c1ockwir:e direction. Interim Cue: After the simulated action, Examiner inform the operator that the handwheel rotated clockwise, and has now stopped. dAT/UNSAT *Step 18: (Step 3,i) CLOSEIconfirm CLOSED CRD-34A (B), CRD Pump .i lB) min flow stop check, to maximize CRD flow to reactor vessel. Standard: The operator closes CRD-34B 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, Standbv Liquid Contrcfi Tank Drain. Standard: The operator opens SLC-23 by rotating the valve operating handle in the counter-clockwise direction. Interim Cue: After the simulated action, Examiner inform the operator that the valve operating handle rotated counter-clockwise, and has now stopped.
JE'I 4-P2 Rev. 0 11509 Page 8 )f 11 Performance Steps
*Step 20: (Steps 515.a-b) In the CRD pump room, ensure hose is filled bv perform in^ the follow in^: OPEN CRD-151A(B) CRD Pump Suc ion Strainer Drain, to vent anv entrapped air within the hose connec to the SLC tank, and CLOSE CRD-151A(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 rotaied counter-clockwise, and the effluent is an airlwater 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. SATKJNSAT *Step 21: (Steps 616.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 ir! the counterclockwise direction. Interim Cue: After the simulated action, Examiner inform the operator that the valve operating hrndle rotated counter-clockwise, and has now stopped. SATLTNSAT *Step 22: (Step 6.b) OPEN CRD-40A, CRD Pump Test Bvpass Line. Standard: The operator opens CRD-4OA by rotating the valve operating handle in the counterclockwise direction. Interim Cue: After the simulated action, Examiner inform the operator that the valve operating ha idle rotated counter-clockwise, and has now stopped.
JPb 1-P2 Rev. 0 l 509 Page 9 ( f 1 1 Yvaluation Performance Steps SATWNSAT *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) b: rotating the valve operating handle in the clockwise direction. Interim Cue: After the simulated action, Examiner inform the operator that the valve operating hzndle rotated clockwise, and has now stopped. SATJUNSAT *Step 24: (Step 6.d) CLOSE CRD-94 Flow Control Station Disch to Rx Ve! &. 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. SATKTNSAT Step 25: (Step 7) Confirm either: RWCU System is isolated or RWCU denn& are isolated. Standard: The operator contacts the Control Room and confirms that the RWCl J System or the Demirls are isolated. Interim Cue: Examiner report as the ACRO that the RCWU System is isolated. SATWNSAT Step 26: (Step 818.a) At CRP 9-5: START the CRD pump(s) and verify flaw by 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 CYD Pump B in accordance with OE 3107, Appendix K; and that CRD Pump B can now be started. TIME FINISH: Terminating Cue: This JPM is complete.
JP?I-P2 Rev. 01 509 Page 10 cf 11 Yvaluators Comments: System: 295037 KIA's: EA 1.10 (3.713.9)
EXAMINEE HANDOUT Initial Conditions: An ATWS has occurred. The EOPs have been entered. The SLC Tank is available. CRD Pump B is in service and CRD Pump A is in Standby. Initiatin~Cues: The CRS directs you to line up the CRD System for boron injection from the SLC Tank in accordaxce with OE 3107, Appendix K, to CRD Pump B. Inform the Control Room when the CRD Pumps call be started. NOTE: All actions must be simulated. At NO time shall any plant equipment be operated.
JPI' I-P3 Rev. 01 1709 Page 1 of 7 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET NRC EXAM 2009 Task Identification:
Title:
Line-up for Alternate Vessel Injection Using, SLC Test Tank Failure Mode: N/A
Reference:
OE 3 107, OE Appendices, Appendix 0 (Rev. 2 5 ) Task Number: 2000310501 Task Performance: AOIROISRO X ROISRO - SRO Only Sequence Critical: Yes - No 3 Time Critical: Yes - No 3 Operator Performing Task: Examiner: Date of Evaluation: Activity Code: Method of Testing: Simulation X Performance -- Discuss Setting: Classroom - Simulator - Plant X Performance Expected Completion Time: 10 minutes Evaluation Results: Performance: PASS - FAIL - Time Required: Prepared by: /'->7 - d y Operations Training Instructor Date fi C, 9 1' s / C/ &' b,u,*4vk~n-
/J
.-R Reviewed by: J. ~ - T . C . MI ~
7
/. z-/c'?
SRO ~icensed/dertikedReviewer Date
.4-J . /2ci;x ,r ,,/(;S X fz;,?pW4
Operations raini in^ ~tiberintendent Date
JPP I-P3 Rev. 01 P.709 Page 2 of 7 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 ft ir any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical s ep is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure After providing the initiating cue, ask the operator "Do you understand the task?" Read to the person being evaluated: Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have. This JPM will be performed in the Plant and you are to simulate all actions. You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing. Inform me upon completion of this task. 'nitial Conditions: Actions are being carried out IAW EOP-1 and reactor water level cannot be maintained above 127". Initiatinr! Cues: The CRS directs you to line-up for alternate vessel injection using the SLC Test Tank per OE 3107 Appendix 0. Task Standards: The SLC Test Tank is lined-up for injection per OE 3 107 Appendix 0 , steps 1-6. Required Materials: Handout 1 - OE 3107 OE Appendices, Appendix 0,(Rev 25)
JPI I-P3 Rev. 01 !709 Page f of 7 -rovide Candidate with Initial ConditionsICue (Last Page of this JPM). Evaluation Performance Steps TIME START: SATNNSAT Step 1: Obtain Procedure. Standard: The operator obtains OE 3107, Appendix 0,Rev 25. Proceeds to Procedure Step 1. Interim Cue: When it is apparent that the operator is seeking to find OE 3107, Appendix 0,Exanliner provides copy (Handout 1). SATNNSAT Step 2: (Step 1) Station an Operator at the SLC Skid Standard: The operator goes to SLC skid, Reactor Building 318'.
*Step 3: (Step 2) Fill the SLC test tank using demineralized water by --
OPENING: DW-41 SLC Sys Demin Water Supply Is01 SLC-29 SLC Test Tank Demin Water Is01 Standard: The operator observt:~tank level on SLC test tank sightglass. Interim Cue: Examiner point to a sightglass level below the Red Minimum Required Level, and indicate that the level is at that point. The operator rotates the DW-41 handwheel in the counter-clockwise direction. Interim Cue: Examiner inform operator that the DW-41 valve handwheel rotates freely counter clockwise and the valve stem rises imtil resistance is felt and stops moving. The operator rotates the SLC-29 handwheel in the counter-clockwise direction. Interim Cue: Examiner inform operator that the SLC-29 valve handwheel rotates freely coilnter clockwise and the valve stem rises until resistance is felt and stops moving. Examiner point to a sightglass level near the top, and indicate that the level is at that point.
JP! I-P3 Rev. 01 !709 Page L of 7 Yvaluation Performance Steps SATIUNSAT Step 4: (Step 3) WHEN fill in^ is complete, THEN CLOSE: DW-41 SLC Sys Demin Water Supply Is01 SLC-29 SLC Test Tank Demin Water Is01 Standard: The operator rotates the DW-41 handwheel in the clockwise directio I. Interim Cue: Examiner inform operator that the DW-41 valve handwheel rotates freely clockwise and the valve stem lowers until resistance is felt and stops moving. The operator rotates the SLC-29 handwheel in the clockwise directicn. Interim Cue: Examiner inform operator that the SLC-29 valve handwheel rotates freely clockwis~: and the valve stem lowers until resistance is felt and stops moving. Step 5: (NOTE prior to Step 4) The test tank will require constant demineralized water make-up to ensure a suction volume for the operating SLC pump. Standard: The operator reads the Note, and proceeds to Step 4. SATRJNSAT *Step 6: (Step 4) Unlock and CLOSE SLC-11 Standby Liquid Control TqnJ Outlet. Standard: The operator removes the lock from SLC-11. The operator rotates the SLC-11 handwheel in the clockwise direction. Interim Cue: Examiner inform operator that the SLC-11 valve handwheel rotates freely clockwise and the valve stem lowers until resistance is felt and stops moving. SAT/UNSAT *Step 7: (Step 5) Unlock and OPEN SLC-41 SLC Test Tank Outlet Isol. Standard: The operator semove:s the lock from SLC-41. The operator rotates the SLC-41 handwheel in the counter-clockwise direction. Interim Cue: Examiner inform operator that the SLC-11 valve handwheel rotates freely counter-clockwise and the valve stem rises until resistance is felt and stops moving.
JPP I-P3 Rev. 0 1 !709 Page 5 of 7 Performance Steps Step 8: (Step 6) Notify the control room that the SLC Test Tank is now I ned up for injection. Standard: The operator calls the control room on the Gaitronics and informs t h ~ ~ m that the SLC test tank is lined up for injection. Interim Cue: Examiner, as the Control Room operator, acknowledge the report. Inform applicant that the Control Room Operator has started an SLC Pump and that a squib valve has fired. NOTE: Applicant should observe Test Tank Level and when thy do, indicate that tank level is three (3) inches below the red minimum tank level line. SATKJNSAT *Step 9: (Step 11) Operator opens DW-41 and throttles open SLC-29 to maintain tank full. Standard: The operator opens valves DW-41 and SLC-29 to maintain Test Tank Level. Interim Cue: Examiner, when the applicant states that they will adjust the valve to maintain tank level, inform them that tank level is steady.
- Critical Step TIME FINISH: -
Terminating Cue: This JPM is complete. Evaluators Comments: aystem: 29503 1 KA: EA1.08 (3.813.9) JPM-P3
JPP I-P3 Rev. 01 1709 Page f of 7
EXAMINEE HANDOUT Initial Conditions: Actions are being carried out IAW EOP-1 and reactor water level cannot be maintained above 127' . Initiatinp Cues: The CRS directs you to line-up for alternate vessel. injection using the SLC Test Tank per OE 3107 Appendix 0. NOTE: All actions must be simulated. At NO time shall any plant equipment be operated.
VY 2009 NRC Scenario 1 Page 4 of 29 SIMULATOR EVALUATION GUIDE Evaluators: Crew: SM SRO RO BOP STA Senior Management Observer Critical Task Performance: SAT UNSAT (Circle One) Lead Evaluatoc Signature Date Administered: Activity Code: Prepared by: hd LL/&#N& - Date: /'27-d7 Reviewed by: .r fi 3 nd;</gK
, d A jtdL44- Date: ,-.z py Approved by:
/ J
, . - Date: .27 7
- C:'
VY 2009 NRC Scenario 1 Page 5 of 29 CREW BRIEF: -Power level: 100% -Rod Sequence: Rapid Shutdown Sequence Latched -Rod Group: 22 (EOC) -Equipment out of service andlor 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 OOS for severe vibrations during surveillance testing.
-Applicable Tech Spec LCOs:
- 1. Seven (7) day LCO, TS 3.5.A.3
- 2. Seven(7)dayLCO,TS3.10.8.1 EOOS Color:
Green 3.10 E-6 -Plant evolutions in progresslScheduled 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 29 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 3110, Positive Reactivity Insertion
- 8. OP 2110, Reactor Recirculation Systern
- 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. OE3107
- 18. Technical Specifications
VY 2009 NRC Scenario 1 Page 7 of 29 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set Up: 100°/~Power
- 1. IC-805
- 2. CRD Pump B in service
- 3. Adjust Kvars to slightly negative
- 4. Place HU barrier on Main Voltage Regulator Auto Adjust Discretionarv Distracter MaIfunctions/RFs/lOs:
- 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) a Group 3 isol (SB-066
VY 2009 NRC Scenario 1 Page 8 of 29 SIMULATOR OPERATOR INSTRUCTIONS (Continued) Additional Instructions:
- 1. RHR Pump B is in PTL and Danger Tagged
- 2. 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.
- 3. 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.
- 4. The Recirc controller failure will be investigated, with no cause being found for the duration of the scenario.
- 5. If directed to adjust Alterex Cooling, respond as directed.
- 6. Transfer APRMs back to RPS B via rfRP-11.
VY 2009 NRC Scenario 1 Page 9 of 29 OPERATOR AC'TIONS EVENT NUMBER 1 Crew Task
Description:
Place Main Generator in the Heavy Load Schedule with Maximum VARs IAW OP 2140, Sect. h. CANDIDATE ACTIONSfBEHAVIOR I S1" INI0 COMMENTS
- 2. RO Adjusts voltage to the Heavy Load Schedule with Maximum VARs IAW OP 2140, Sect. H.
I I Informs SROISRO 1 1 1
- 3. SRO Directs Crew to go to the Heavy Load Schedule with Maximum VARs IAW OP 2140, Sect. H.
- 4. SRO Briefs crew
- 5. BOP Obtains and reviews procedure OP 2140 Section H and checks prereqs.
ROLE PLAY: Whenhf notified of the VY Generator status respo ~das VELCO acknowledging the communication. BOP Determines Main Generator NOTE: SRO may designate RO parameters and BOP to coordinate the voltage 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 Generator VARS from ERFlS point G009, or on panel 9-7 El 9-7-6. Circle instrument used. NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasklStep
VY 2009 NRC Scenario 1 Page 10 of 29 POS. CANDIDATE S U NIO COMMENTS ACTIONSIBEHAVIOR
- 7. 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 SRO Monitors Crew and plant performance. May direct BOP to mon~torthe output of the A DG per OP 4126 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 TaskIStep
VY 2009 NRC Scenario 1 Page 11 of 29 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task
Description:
High Main Turbine Vibration Requires Power Reduction IAW OP 0105 Direct power reduction IAW OP-0105 if vibrations approach May direct reducing VARs back to the normal VAR load. Notifies or directs notifying IS0 New England and VELCO. Notifies Maintenance. May shift to coarse control to quickly lower recirc flow NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasklStep
VY 2009 NRC Scenario 1 Page 12 of 29 other plant parameters and reports Responds to Annunciators 9-4 8-3 and F-3 and sends an A 0 up to adjust Recirculation MG Set oil NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskfStep
VY 2009 NRC Scenario 1 Page 13 of 29 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task
Description:
DG A High Jacket water temperature requires removing DG from service POS CANDIDATE S U 1'410 COMMENTS ACTIONSIBEHAVIOR BOOTH ROLE PLAY: Report as A 0 that an unisolable leak is occurring an DG A jacket water and local temperature is 186 degrees and rising slowly. NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasWStep
VY 2009 NRC Scenario 1 Page 14 of 29 POS CANDIDATE ACTIONSIBEHAVIOR CREW Responds to Annunciator 8-G-5, DG-A JKT CLG TEMP HI/LO SRO Refers to alarm response and directs unloading DG BOP Reduce load using the DIESEL GEN SPEED GOVERNOR control switch Using the DIESEL GEN SPEED GOVERNOR control switch, unload unit to < 200 KW. Open BKR NO. DG-A, diesel generator output breaker. May Run unloaded for approximately 1 minute. May 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.
- 6. SRO Provide a crew brief 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 1 Page 15 of 29 OPERATOR AC'TIONS EVENT NUMBER 4 Crew Task
Description:
Respond to positive reactivity addition caused by failure of the "B" Recirc loop controller POS. CANDIDATE ACTIONSIBEHAVIOR increasing Identify the Loop "B" controller ramping upward; inform SRO Notify SRO
- 2. SRO Enterldirect actions IAW OT 3110 OT 3110 Immediate Actions Transfer the loop " B controller to individual manual control Attempt to lower Recirc flow at c 10% RTP/min to reduce power to pre-transient level
- 3. RO Transfer the loop " B controller to individual manual control Lower Recirc flow at e: 10%
RTP/min to reduce power to pre-transient level
- 4. RO Verifies position on P/F Operating Map MAY determine that MELLLA has been exceeded and have to insert Rapid Shutdown Sequence rods.
NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskIStep
VY 2009 NRC Scenario 1 Page 16 of 29 POS. CANDIDATE ACTIONSIBEHAVIOR
- 5. BOP Responds to or anticipates Annunciators 9-4 9-3 and F-3 and sends an A0 up to adjust Recirculation MG Set oil temperatures.
- 1) ROLE PLAY: As A0 respond as directed. In the booth rfSW-58 adjusts Recirc MG Set oil temps.
1I Booth Operator: When directed, move to Event 5 J NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasklStep
VY 2009 NRC Scenario 1 Page 17 of 29 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task
Description:
Loss of 480 Volt Bus 9A, Failure of Group 3 Isolation Valve. NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical Task/Step
VY 2009 NRC Scenario 1 Page 18 of 29 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 29 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 iar not re-energized while you continue looking. NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskIStep
VY 2009 NRC Scenario 1 Page 20 of 29 NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasWStep
VY 2009 NRC Scenario 1 Page 21 of 29 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task
Description:
Respond to a loss of 480 Volt MCC-8% POS CANDIDATE ACTIONSIBEHAVIOR S U NIO COMMENTS
- 1. BOP Recognize and inform the SRO that NOTE: YZ scram only if RPS B was 480V MCC-8B has tripped. swapped to alternate power supply Diagnose loss of Alternate RPS Supply and YZ scram on RPS Bus B.
- 2. SRO May direct crew to enter OP 2143, 480 VAC Buses, to diagnose the loss of power
- 3. BOP Diagnose loss of SLC Pump B May Respond to Seismic Monitor alarm Diagnose Loss of RRUs 1A & 1B Loss of power to RClC RHR and Core Spray Valves V13-15, V10-66 V10-31B V10-658 V10-89B V14-11B V10-183 V10-38B V10-39B V14-128 V14-58 V10-16B V14-7B V10-348 V14-26B V10-15B V10-15D NOTES:
V10-13B V10-130 V10-18 V10-268
- 1) S = Satisfactory;
-NU - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskJStep
VY 2009 NRC Scenario 1 Page 22 of 29 POS CANDIDATE ACTIONS/BEHAVIOR COMMENTS CRD Cooling Water Valve PCV-22 SRO Direct crew member and 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. I EVALUATOR'S NOTE: If requested to investigate MCC-8B state that the bus tripped because of an 11 1 apparent fault but thatnothing specific is evident and request that the bus !s 1 not re-energized for at least another hour while you continue looking. 1 BOP 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 hours 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 1 EXAMINERS CUE: When SRO enters T.S., go to Event 7. NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskIStep
VY 2009 NRC Scenario 1 Page 23 of 29 OPERATOR ACTIONS EVENT NUMBER 7 and 8 Crew Task
Description:
Loss of RPS MG Set A, ATWS (450/d55%)and failure of A SLC Squib Valve. NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskIStep
VY 2009 NRC Scenario 1 Page 24 of 29 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskJStep
VY 2009 NRC Scenario 1 Page 25 of 29 POS CANDIDATE S U N/O COMMENTS ACTIONS/BEHAVIOR
- 15. SRO Direct per EOP-2:
Inhibit ADS EVALUATOR'S NOTE: This step is an Immediate Action, anci may be performed without direction. Verify ARIIRPT initiated Insert control rods with one or more appropriate appendices May direct A 0 to manually operate CRD-v-22 EVALUATOR'S NOTE: Implement appendix F, 66 or H of OE 3107. Stabilize pressure RPV pressure 800-1,000 psig with BPVs.
- 16. BOP When directed:
Inhibit ADS. Stabilize pressure 800-1000 psig with SRVs. injection per Appendix GG. NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskIStep
VY 2009 NRC Scenario 1 Page 26 of 29 POS CANDIDATE COMMENTS ACTIONSIBEHAVIOR During an ATWS with conditions met to perform powerhevel control TERMINATE AND PREVENT INJECTION into the RPV using appendix GG, until conditions are met to re-establish injection. Standard: Completion of Terminate and prevent injection IAW OE 3107 Appendix GG within 5 minutes of loss of forced circulation. SRO Direct SLC injection with A SLC pump With a reactor scram NOTE: Must use local battery to fire required and the reactor not Squib Valve 6 shutdown, TAKE ACTION TO REDUCE POWER by injecting boron andlor 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. EVALUATOR'S 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 27 of 29 I POS I CANDIDATE ACTIONSIBEHAVIOR 1 1 1 I S U NIO COMMENTS SRO Direct sending an A 0 to the NOTE: 1.5 VDC Squib valve firing battclry Squib Valve RB 318' level available with an alligator clip on each (3rdfloor) and firing the squib end. (Located in EOP toolbox, 318' using App I of OE 3107, elevation, Reactor Building.) Alternate SLC injection. Direct A 0 to go the Squib Valves on the RB 318' level (3rdfloor) and fire 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 B.
- 25. RO Insert control rods using directed appendices.
BOOTH NOTE: Ensure the examiners have seen Terminate & Prevent then level restoration before rod insertion is available
- 26. BOP When directed, terminatelprevent injection per Appendix GG.
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 1 enter -19" to 9 0 level control leg. below 2 %; inform SRO between -19 and 90 inches NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskJStep
VY 2009 NRC Scenario 1 Page 28 of 29 POS CANDIDATE S U N/O COMMENTS ACTIONS/BEHAVIOR RO Maintain RPV level between
-19 and 90 inches *CREW With a reactor scram required and the reactor not EoP-2 shutdown, TAKE ACTION CT-3 TO REDUCE POWER by inserting control rods, to prevent exceeding the primary containment design limits.
Standard: Actions taken within 10 minutes of the scram Recognize all rods inserted; inform SRO SRO When all control rods inserted, exit EOP-2 and enterldirect actions IAW EOP-1: Verify Table A automatic actions Restore 1maintain RPV level 127-177 inches. Commence cooldown at less than 100 degrees F per hour. 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 127-177 inches. ario may be terminated, once EOP-2 has been exited at the discretion 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 TasklStep
VY 2009 NRC Scenario 1 Page 29 of 29 OPERATOR ACTIONS ADDITIONAL COMMENTS: NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasWStep
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 Evaluatoc Signature Date Administered: Activity Code: Prepared by: ~bk/a/$$&-f Date: /-
'1 Reviewed by: rfi6 ? r i d ' l i / ~ . ~ 3 ~ ~Date:
d ~ /,*7-7 07 Approved by: 6? k?$$$dk - Date: /. 97-09
VY 2009 NRC Scenario 2 Page 5 of 27 CREW BRIEF: -Power level: -1.9% -Rod Sequence: Rod Sequence: A2 -Rod Group: 22 -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 OOS 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 air-purge 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 2115 are initiated.
VY 2009 NRC Scenario 2 Page 6 of 27 Plant evolutions in progress1ScheduledShift 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 - one condensate pump, one feed pump, the Aux FRV in Auto.
- 2. AOG is on-line. 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 the Mode Switch 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 2115 are initiated.
VY 2009 NRC Scenario 2 Page 7 of 27 SCENARIO
SUMMARY
PROVIDE OP 2124 APP.C to Examiners for description of Torus Spray steps TERMINATING CONDITION(S):
- 1. RPV water level under control
REFERENCES:
- 1. OP 0105, Reactor Operations
- 2. OT 3110, Positive Reactivity Insertion
- 3. OP 2131, IRM
- 4. EN-OP-115, Manual Control of Automatic Systems
- 5. Technical Specifications
- 6. OT 3110, Positive Reactivity Insertion
- 7. OE 3107, EOPISAG Appendices
- 8. OP 2117, 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
- 15. OP 2124, Appendix C
VY 2009 NRC Scenario 2 Page 8 of 27 SIMULATOR OPERATOR INSTRUCTIONS Simulator Set Up: -1.9% Power
- 1. IC-806
- 2. Ensure as close to rolling Mode Switch as possible with rods (limit control rod operation before going to run)
Discretionarv Distracter Malfunctions/RFs/lOs: DG " B failure to Auto Start
VY 2009 NRC Scenario 2 Page 9 of 27 SIMULATOR OPERATOR INSTRUCTIONS (Continued) Additional Instructions:
"A" IRM should be bypassed.
Ensure the following: one condensate pump, one feed pump, aux FRV in auto, 55% FRVs blocking valves closed and all feed pump discharge valves open. Roll the key-locks in panel 9-41, 9-42 to Bypass to allow the 18-inch containment purge valves open when in run. Fill out a current revision of VYOPF 0105.05 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. Verify RWM initialized. After IRM "C" fails and when contacted by the crew acknowledge the request then allow time for Techrrical 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. 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. If no attempts are made to coollspray the drywell the leak may cause the crew to emergency depressurize to prevent exceeding PSP. This will not affect the outcome of the scenario and this would serve as a substitute critical task to emergency depressurizing on inability to maintain RPV water level >-I9". 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 I'lag showing. If the crew has sent AOIMaintenance 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). After HPCl is secured following ,the spurious injection use soft panel override to place the HPCl INHIBIT switch into INHIBIT.
VY 2009 NRC Scenario 2 Page 10 of 27 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task
Description:
Withdraw control rods to continue the startup CANDIDATE ACTIONSIBEHAVIOR Briefs crew on the startup 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 Check that all APRM downscale alarms are clear. f h Verifies reactor vessel level between 155 and 165 inches. Will serve as verif~erfor rod selection and movement and IRM range switching. 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. 5-D-3, Rod Withdraw Block 5-N-1, IRM Ch A Hi-HiIINOP 5-K-1, Auto Scram Ch A 5-L-2, Neutron Mon Power Hi Diagnoses IRM " C failed INOP Diagnoses 1/2 scram Diagnoses IRM " CINOP, references OP 2131, Section C. Directs I & C to investigate. Consults Tech Specs - Table 3.1.l. for two lRMs Inop. t j2 (May enter TRM 3.2.5 which is a 7 Determines the inoperable instrument channels trip system must be placed in the tripped condition within 12 hours. 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 EVALUATOR'S 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.
- 3. RO Places IRM A Range switch to the correct range Then un-bypasses IRM " A then bypass IRM "C".
Resets the half scram BOOTH NOTE: before IRM A can be un-bypassed, the malfunction must be deleted. for two lRMs Inop. Crew Brief NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical Task/Step
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 ACTlONSlBEHAVlOR lsIU COMMENTS Enterldirect placing the Reactor Mode Switch in RUN 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.
- 3. 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 and verify that indicated level is decreasing.
- 4. 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. EVALUATOR! CUE: When sufficient operator actions are bserv rd, insert Event 4, CRD Flow Controller Fai ure. 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 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskIStep
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 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 ROLE PLAY: If contacted as I & C report that you had just worked on the controller and will send a Tech to the Control Room after their break.
- 5. SRO May direct shifting CRD FCVs RO1 May contacts A 0 to coordinate NOTE: If the crew starts to shift sh~ftingFCVs CRD FCVs go to the next BOP malfunction I --
I EVALUATORS CUE: When CRD Parameters are restored, insert Event 5, Inadvertent HPCl initiation 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 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 S U COMMENTS ACTIONS/BEHAVIOR
- 1. CREW 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 31 10 - Positive Reactivity Insertion, Step 2.5. after actions are taken IAW IAW EN-OP-115, Manual Control of Automatic Systems Confirm no initiation signals present. Using two indications Verifies Feedwater control system maintaining RPV water level. I Diagnoses HPCl Controller failure I l l I 1 Notifies Crew I l l
- 4. SRO When adequate level has been verified, direct the BOP to inhibit the HPCl system
- 5. 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 initiatior signal will continue to start HPCI.
BOOTH NOTE: After HPCl is secured following the spurious injec lion, use soft panel override to place the HPCl INHIBIT switch into INHIBIT. NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskIStep
VY 2009 NRC Scenario 2 Page 18 of 27
- 8. SRO Direct crew to contact I&C and/or maintenance to investigate the HPCl initiation and controller problems.
- 9. CREW When directed, contact I&C and maintenance and request they investigate the HPCl problem.
ROLE PLAY: When contacted as I&C and/or maintenance and re luested to investigate the HPCl problem respond that you will send a technician to the Control R lorn shortly and then delay. NOTE: T.S. Bases states that an RHR Subsystem consists of 2 pumps, since RHR Pump C is INOP, the subsystem is NOT operable.
- 11. SRo Direct the crew to confirm operability of RCIC.
I I Conduct a Crew brief I I I 1 EVALUATORS CUE: When ready, advance to Events 5 and 6 1 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings reqliire 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 TaskfStep
VY 2009 NRC Scenario 2 Page 20 of 27 POS CANDIDATE COMMENTS ACTIONSIBEHAVIOR 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/diagnosesfailure of breaker 3V4 to close Reports failure of cross-tying to Vernon. Directs operator to contact SRO I AOIMaintenance to investigate DG A failure to start I 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 TaskIStep
VY 2009 NRC Scenario 2 Page 21 of 27 I I CANDIDATE ACTIONSIBEHAVIOR If not previously done BOP acknowledgelrespond to DG A Lockout Trip Annunciator (8-F-2) Contact AOIMaintenance and directs them to investigate DG A failure to start Diagnoses " B DG failed to auto-start and manually starts "0DG and places on 4KV Bus 3. Notifies Crew "0DG in service al,,w-ROLE PLAY: When directed as the AOIMaintenance to investigate the failure to start of the 'A' DG, respond as directed. Then 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). When notified Bus 4 available ROLE PLAY: If contacted as maintenance and directed to verify that Buses 8 and 9 may be cross-tied, reply that you have checked the buses and that they may be cross-tied. If the Control Room does NOT contact Work Control or Maintenance then call the Control Room as Maintenance and notify them that the buses may be cross-tied. (This will re-establish Control Room Lighting.)
- 9. Cross-ties buses 8 and 9.
BOP lo' Carries out scram action IAW Ro ON 3100 Verifies RClC operation when needed.
- 11. SRO Directs work week manager to check DG A andlor 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. 1 EVALUATORS CUE: When ready, advance to Events 8 and 9 1 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskIStep
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. the valve is open. Diagnose and Report the " A CS and " A RHR Pumps have no Re-start all available drywell BEFORE torus pressure reaches 10 psig, spray the Re-start all available drywell Spray the torus usirlg only those pumps not required for adequate core cooling 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) * = Critica.1TasWStep
VY 2009 NRC Scenario 2 Page 23 of 27 While attempting to inject RCIC, recognizes that the controller has failed in AU and takes manual control Then recognizes isolation and EXAMINER NOTE: RClC will run for a short time in Manual (RHR Pump "D" is available and R 10 psig, direct the following: pressure is too high to inject.) Verify drywell RRUs pump will trip on overload. Spray the drywell between 6 and 177 inches by maximizing CRD and injecting SLC and RClC If not previously directed; directs NOTES: 1) S = Satisfactory; U - Unsatisfactory; IVIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasWStep
VY 2009 NRC Scenario 2 Page 24 of 27 Maximize CRD (if available) EVALUATORS NOTE: When RPV water level reaches 6", contact the Control Room as the AOIMaintenance at DG A 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 can t;e started.) -
- 12. SRO Direct starting DG A and placing Bus 4 on DG A Directs ADS inhibited -
- 13. BOP After the 100 second timer has timed out start DG A and place it on 4KV Bus 4
- 14. RO/ Inhibits ADS Lineup ECCS systems and Alternate Injection Subsystems as directed.
I 15. *CREW With the reactor shutdown Success path is restore RPV water and reactor pressure greater level using EoP-l than the shutoff head of the E0P-5 RHR SW low pressure systems, initiate CT-2 RPV-ED BEFORE RPV level Send someone to locally start the "A reaches -19 inches DG. Standard: Enter EOP-5 and initiate RPV-ED (begin opening valves) BEFORE RPV level reaches - I 1 48 inches 1 1 1 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 2 Page 25 of 27 Prevent injection from those CS and RHR Pumps not required to ensure adequate Open all SRVs Prevent injection from those CS and RHR Pumps not required to ensure adequate Open all SRVs When RPV pressure drops below shutoff head of low pressure pumps, direct level restored and maintained 127 to
" B low discharge pressure and Diagnose failure of " B Core Spray Pump to inject and Core Spray line as the potential source of the break.
NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasWStep
VY 2009 NRC Scenario 2 Page 26 of 27 I I CANDIDATE ACTIONS/BEHAVIOR Secure the B Core Spray Pump If not previously lined up directs lining up all available Alternate Injection Subsystems (EOP-1, I t COMMENTS Success path is restore RPV water level using RHR SW Starting the "An DG and supplying power to 4KV Bus 4. Investigate the trip of the " D RHR Pump and restore the pump.
- 25. SRO Direct:
Directs starting and injecting with available pumps
- 26. BOP/ Starts and Inject with available RO Pumps
- 27. CREW Restores RPV water level EOP-l above TAF (+6")
CT-3
- 28. 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 TaskIStep
VY 2009 NRC Scenario 2 Page 27 of 27 OPERATOR AC'TIONS ADDITIONAL COMMENTS: NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasWStep
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: @/./ Reviewed by: 7 6 ?
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Date:
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VY 2009 NRC Scenario 3 Page 6 of 30 CREW BRIEF: -Power level: 85% In OP 0105, Phase 4B, Step 23 is completed -Rod Sequence: Rapid Shutdown -Rod Group: 20 -Equipment out of service andlor tagged or abnormalities:
- 1. A RHR Pump OOS, tagged out for Maintenance investigation yesterday at 1600.
The plant entered a 7-day LC0 (TS 3.5.A.3). -Reason For Equipment out of Service or tagged:
- 1. A RHR Pump OOS 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 progress1Scheduled Shift Evolutions:
- 1. Perform OP 4160 Oncemeek Pump Performance Test Section 1.a and b.
- 2. Continue power ascension to 100% power, during this shift raise power to 92%
using recirculation flow then allow 12 hour 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 2111, CRD System
- 2. OP 0105, Reactor Operations
- 3. OT 3115, Reactor Pressure Transients
- 4. OT 3110, positive Reactivity Insertion
- 5. OT 3113 Reactor Low Level
- 6. OT 3176, Recirculation Pump Runback Due to Low Feedwater Flow or Discharge Valve Not Full Open
- 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 2170, 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 MaIfunctions/RFs/lOs: No. MFIRFIIO # Severity Ramp REM # Act. Time Description
- 1. IOR re-~nsert Override RHR-184 CLOSEC RHdi031OAS27
- 2. IOR re-insert Override the A Core Spray CSdi0314ASlA Injection Valve CLOSED
- 3. mfCS-03A re-~nsert CS-12A Fails to Auto Open
- 4. rf RH-11 Open re-~nsert RHR Pump A ACB
- 5. mf FW-28A 50% 60 1 "A" Feedwater transmitter fail!;
to a higher indicated flow
- 6. IOR 2 Recirc "B" Runback, RV-538 RRlo042AS7B-1 Recirc Discharge Valve, drift:;
off open seat IOR RRdi042AS7B IOR RRlo042AS7B IRF rfRR-12
- 7. mfRD-01 B 3 CRD Pump B Trip
- 8. mf ED-O6A 3 Loss of 125 VDC Bus 1
- 9. mfTC-04A 75% 4 Pressure Reg Oscillations (EPR)
- 10. mfMS-06 0.5 120 5 Main Steam Line Break in the Drywell
- 11. mfMS-06 3 120 6 After Main Steam Line Break in thc scram Drywell actions carried out
- 12. mfFW-08A 7 Trip of all RFPs mf FW-08B mf FW-08C .4
VY 2009 IVRC 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 1 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 1 I&C concerning the pressure regulator failure, delay determining the cause; no reason will be given before the scenario terminates.
- 11. Attach a copy of ON 3159 actions to transfer control power Bus 1, 3, 8 and DG B
VY 2009 NRC Scenario 3 Page 10 of 30 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task
Description:
Perform OP 4160 Oncemeek Pump Performance Test Section 1.a and b. CANDIDATE S U N/O COMMENTS ACTIONSIBEHAVIOR
- 1. SRO Briefs Crew Directs performance OP 4160 Oncemeek Pump Performance Test Section 1.a and b.
j i ROLE PLAY: Role play as A0 for pumps checks required below NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TasWStep
VY 2009 NRC Scenario 3 Page 11 of 30 ! p
- 2. BOP TO test the Auxiliary 011 Pump, perform the following:
ON CRP 9-7 take Aux 011Pump Test switch to the TEST I Contacts A 0 to Check I that the auxil~aryoil pump starts and is II operating satisfactorily Place the test switch to NORM Verify the auxiliary otl pump does not automatically stop Stop the auxiliary 011 Pump Verlfy the control switch returns to normal after stop (green flag). To test the Turning Gear Oil Pump, perform the following: On CRP 9-23 take Turn Gear L.O. Pump Test switch to the TEST posttion. Contacts A 0 to check that the turntng gear 011 pump starts and is operating satisfactorily Allow the test switch to return to mid-posltion Verify the turning gear oil pump does not automatically stop Stop the turning gear oil Pump Verify the control switch returns lo AUTO Once the test is complete, continue with EVENT 2 NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.
- 2) * = Critical TaskfStep}}