ML042080220
| ML042080220 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/13/2004 |
| From: | Gody A Operations Branch IV |
| To: | Muench R Wolf Creek |
| References | |
| 50-482/04-301 50-482/04-301 | |
| Download: ML042080220 (213) | |
Text
Administrative RO A1a WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 001-A K/A NO: 2.1.33 COMPLETION TIME: K/A RATING: 3.4 JOB TITLE: RO REVISION: 0 TASK TITLE: Perform Surveillance Test for AFD DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
MAY BE PERFORMED IN ANY LOCATION WHERE PROPER REFERENCE MATERIAL IS AVAILABLE.
METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
STS SF-002, CORE AXIAL FLUX DIFFERENCE CORE OPERATING LIMITS REPORT TECHNICAL SPECIFICATION 3.2.3 TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04
JPM NO: 001-A RO A1a Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has been stable at 100%. The AFD Monitor Alarm is inoperable.
Initiating Cues: The Control Room Supervisor has directed you to perform STS SF-002 and Determine T/S compliance.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide the candidate with an information only copy of STS SF-002.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
THE FOLLOWING DATA IS PROVIDED ON THE CUE SHEET N41 N42 N43 N44
% Power 100 100 100 100
% Flux Difference -13 -16 -16 -14 Task Standard: Upon completion of this JPM, the operator will have determined that the Plant is in Technical Specification 3.2.3, Action A.
START TIME:
STOP TIME:
PAGE 1 of 3
JPM NO: 001-A RO A1a Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Record data as required Go to Attachment A and on Attachment A enter the data provide on Comments:
the cue sheet
- *Compare % flux Determine that N41 and for each channel to N44 are in the acceptable COLR limits region, determine that N42 and N43 are in the unacceptable region, and annotate the attachment accordingly Determine that the Plant
- *If the indicated is in TS 3.2.3 and report FLUX DIFF is to the Control Room outside the Supervisor.
acceptable limits of COLR on two or more operable PR channels, then perform the actions required by Tech Specs THE JPM IS COMPLETE RECORD STOP TIME STEP 8.1 ON PAGE 1
- CRITICAL STEP PAGE 2 of 3
JPM NO: 001-A RO A1a Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has been stable at 100%. The AFD Monitor Alarm is inoperable.
Initiating Cues: The Control Room Supervisor has directed you to perform STS SF-002 and Determine T/S compliance.
THE FOLLOWING DATA IS PRESENT ON PLANT INSTRUMENTATION N41 N42 N43 N44
% Power 100 100 100 100
% Flux Difference -13 -16 -16 -14 PAGE 3 of 3
Administrative RO A1b WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 002-A K/A NO: 2.1.7 COMPLETION TIME: K/A RATING: 3.7 JOB TITLE: Reactor Operator REVISION: 0 TASK TITLE: Given Data, complete a 1/M plot and determine estimated critical rod position DUTY: Conduct of Operations ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
MAY BE PERFORMED IN ANY LOCATION WHERE PROPER REFERENCE MATERIAL IS AVAILABLE.
METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
GEN 00-002, Hot standby to Minimum Load STS RE-002, Estimated Critical Position SOER 88-2, Premature Criticality Events During Reactor Startup TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04
JPM NO: 002-A RO A1b Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in hot standby recovering from a short forced outage at middle of core life. The crew is performing a reactor startup in accordance with GEN 00-003, Hot Standby To Minimum Load. Initial data has been entered on Figure 1, 1/M Plot which is provided.
Initiating Cues: With the data supplied, complete the 1/M Plot. Estimate the critical rod position per steps 6.21.5.2 and identify any required actions.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide the Candidate with an information only copy of GEN 00-003, thru Step 6..21.5 THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have completed a 1/M Plot that indicates criticality will occur at a rod position higher than the maximum rod height calculated by Reactor Engneering and have notified the CRS that Reactor Engineering must be informed.
START TIME:
STOP TIME:
PAGE 1 of 4
JPM NO: 002-A RO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. *Enter the supplied data Comments:
on Figure 1 (Cf section)
Enter the final rod position and final count STEP 6.21.5.2 rate for each pull in the appropriate section.
(See attached key)
- 2. *Calculate 1/M for each rod withdrawal sequence Calculate a resultant from the data entered and STEP 6.21.5.2 annotate it in 1/M section.
(See attached key)
- CRITICAL STEP PAGE 2 of 4
JPM NO: 002-A RO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- 3. *Determine estimated critical postion for each For each calculated 1/M rod withdrawal sequence place a point on the sequence graph. Use a straight edge to locate the estimated critical position for each pull by taking the line from the last two plots out to the edge of the graph and comparing that position to STEP 6.21.5.2 the ECP
- 4. *Inform Reactor Engineering and maintain Realize that when rods stable reactor conditions are withdrawn to Bank B per step 6.21.5.3 at 185 steps that flux is more than double its initial value.
Note that the ECP is outside the estimated band from the cue sheet.
Note the requirement to maintain the reactor stable and notify reactor engineering Acknowledge Report THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 3 of 4
JPM NO: 002-A RO A1b Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in hot standby recovering from a short forced outage at middle of core life. The crew is performing a reactor startup in accordance with GEN 00-003, Hot Standby To Minimum Load. Initial data has been entered on Figure 1, 1/M Plot which is provided.
Initiating Cues: With the data supplied, complete the 1/M Plot. Estimate the critical rod position per steps 6.21.5.2 and identify any required actions.
THE FOLLOWING DATA IS PROVIDED Initial count rate 520 cps Source Range NI response to rod withdrawals Rod Position A50 A100 B35 B85 B135 B185 C95 C145 Channel SR SR SR SR SR SR SR SR SR SR Cf 553 634 732 881 1019 1300 1575 2166 PAGE 4 of 4
Administrative RO A2 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 003-A K/A NO: 2.2.12 COMPLETION TIME: K/A RATING: 3.0 JOB TITLE: RO REVISION: 0 TASK TITLE: Given Data, Complete the Surveillance Test Data sheet identifying and documenting any out of spec readings.
DUTY: Equipment Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
MAY BE PERFORMED IN ANY LOCATION WHERE PROPER REFERENCE MATERIAL IS AVAILABLE.
METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
STS AB201D, Atmospheric Relief Valve Inservice Valve Test TOOLS/EQUIPMENT: NONE PREPARER: DATE: 4/13/04
JPM NO: 003-A RO A2 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: STS AB-201D, Atmospheric Relief Valve Inservice Valve Test, is being performed in Mode 1 for AB PV-4 only.
Initiating Cues: Some of the steps of the procedure are annotated as complete or NA. Go through the appropriate steps of the procedure for AB PV-4 only performing the steps which have not been marked as performed or NA. The JPM will be complete when you have completed Attachment A and made any necessary entries on the Surveillance Test Routing Sheet based on Attachment A entries only.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide the Candidate with a copy of STS AB-201D. The readings to be annotated are included on the instruction sheet for this JPM.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: This JPM will be complete when Attachment A is complete and Part 3 of the APF 29B 01 is completed noting that :
- Action 2 is required for step 8.4.6, AB PIC-4A Output Indication
- Action 1 is required for step 8.4.9. The valve is inoperable.
- Action 2 is required for step 8.4.17.4.
START TIME:
STOP TIME:
PAGE 1 of 6
JPM NO: 003-A RO A2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. *Check and record open Comments:
indications for AB PV-4 Complete step by per Attachment A recording supplied data on Attachment A as on Attachment Key Should notify CRS of unsatisfactory output indication.
Acknowledge report.
STEP: 8.4.6 CRS will initiate corrective action.
S U
- 2. *Record AB PV-4 Comments:
opening stroke time on Complete step by Attachment A recording supplied data on Attachment A STEP: 8.4.7
- CRITICAL STEP PAGE 2 of 6
JPM NO: 003-A RO A2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 3. *Record AB PV-4 close Comments:
stroke time on Complete step by Attachment A recording supplied data on Attachment A Realize that valve is inoperable per Note 1 of Attachment A.
If candidate announces STEP: 8.4.9 the surveillance has failed and that they intend to suspend the rest of the procedure, acknowledge the failure and inform them to contine on to complete the surveillance.
S U Complete step by
- 4. *Record results of AB recording supplied data Comments:
PV-4 complete cycle on on Attachment A Attachment A STEP: 8.4.15
- CRITICAL STEP PAGE 3 of 6
JPM NO: 003-A RO A2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Complete step by
- 5. *Record test data for recording supplied data Comments:
AB-V344 on Attachment on Attachment A.
A Should notify CRS that corrective action is required.
STEP: 8.4.17.4 Acknowledge report.
CRS will initiate corrective action.
S U Complete step by
- 6. *Record results of AB- recording supplied data Comments:
V007 complete cycle on on Attachment A Attachment A.
STEP: 8.4.19
- CRITICAL STEP PAGE 4 of 6
JPM NO: 003-A RO A2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 7. Complete block 3 of the surveillance routing *Complete block 3 of Comments:
sheet. the STRS as on the attached Key and annotate that Step 8.4.9 made the valve inoperable. Report STEP: Routing Sheet fact to CRS.
Candidate may fill out block 3 for each individual deficiency and use a continuation sheet.
(NOT Critical)
Acknowledge the report. May report directly to CRS that several THE JPM IS deficiencies exist and that COMPLETE the valve is inoperable.
RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 5 of 6
JPM NO: 003-A RO A2 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: STS AB-201D, Atmospheric Relief Valve Inservice Valve Test, is being performed in Mode 1 for AB PV-4 only.
Initiating Cues: Some of the steps of the procedure are annotated as complete or NA. Go through the appropriate steps of the procedure for AB PV-4 only performing the steps which have not been marked as performed or NA. The JPM will be complete when you have completed Attachment A and made any necessary entries on the Surveillance Test Routing Sheet based on Attachment A entries only.
THE FOLLOWING DATA IS PROVIDED STEP AB PV-4 INDICATION AND PIT PARAMETER Found Plant Condition 8.4.6 AB PIC-4A Output indicates approximately 100% ~80%
Green indicating light on AB ZL-4A is out out Red indicating light on AB ZL-4A is lit out Computer point ABE0004 indicates valve NCLSD nclsd If PIT was performed, THEN valve moved from NA closed to open position STEP STROKE TEST PARAMETER MEASURED 8.4.7 AB PV-4 opening stroke time* 15.4 sec 8.4.9 AB PV-4 closing stroke time* 20.1 sec 8.4.15 AB PV-4 Complete Cycle** Complete Cycle - SAT 8.4.17.4 AB PV-4 Steam Trap Inspection 1650 ml 8.4.19 AB PV-4 Complete Cycle Complete Cycle - SAT PAGE 6 of 6
Administrative RO A3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 004-A K/A NO: 2.3.1 COMPLETION TIME: K/A RATING: 2.6 JOB TITLE: RO REVISION: 0 TASK TITLE: Given a Clearance Order for venting/draining a contaminated system in the RCA, Determine the RWP, limits and time allowed to complete the job.
DUTY: Radiation Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED
REFERENCES:
TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04
Administrative RO A3 JPM NO: 004-A RO A3 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are a spare Reactor Operator. Another Operator has contacted you for assistance in completing a Clearance Order in the RCA.
Initiating Cues: The other Operator is requesting assistance in opening BG V0374, RWST To Charging Pump Suction Line Drain Valve, located in the A CCP Room. For this task:
- # identify the correct RWP.
- describe the dress out requirements.
- identify the dosimetry settings .
- consider that you have received 1830 MR dose this calendar year, and estimate your stay time in the lowest dose area of the room.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: #If performed at the RCA entrance. Allow the candidate to access the book of RWPs and tell you which RWP would be correct. When the Candidate indicates they are going to read the posted survey map for the indicated area, provide them with the survey map attached to this JPM.
- If performed in a classroom. Provide the candidate with the attached four RWPs and ask them to select the one appropriate for the job.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have identified:
- RWP 04-045
- dress out requirement of full set
- dosimetry setting of 20 mr Dose and 200 mr Dose Rate
- an estimated stay time of 4 hrs. (4 hrs. X 5mr = 20 mr dose)
START TIME:
STOP TIME:
PAGE 1 of 4
JPM NO: 004-A RO A3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 1 *Identify the correct Comments:
RWP If performed at the RCA entrance. Look in book outside Access Control. Note that RWP 04-045 is for Operations access for contaminated systems venting and draining activities If performed in a classroom. Select the correct RWP from the four provided.
S U In work activity block of
- 2. *Describe the dress RWP 04-045, note that Comments:
out requirements the requirement is for a full set.
Under setting block of 3 *Identify the dosimetry RWP 04-045, note the settings settings are :
- Dose 20 MR
- Rate 200 MR/HR
- CRITICAL STEP PAGE 2 of 4
JPM NO: 004-A RO A3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE Note that the limiting time
- 4. *Estimate your stay time is 20 MR dose from the in the lowest dose area RWP. The survey map of the room indicates a lowest dose area of 5 mr. 20 MR divided by 5 MR = 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> stay time THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 3 of 4
JPM NO: 004-A RO A3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are a spare Reactor Operator. Another Operator has contacted you for assistance in completing aClearance Order in the RCA.
Initiating Cues: The other Operator is requesting assistance in opening BG V0374, RWST To Charging Pump Suction Line Drain Valve, located in the A CCP Room. For this task:
- identify the correct RWP.
- describe the dress out requirements.
- identify the dosimetry settings .
- consider that you have received 1830 MR dose this calendar year, and estimate your stay time in the lowest dose area of the room.
PAGE 4 of 4
Administrative RO A3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 004-A K/A NO: 2.3.1 COMPLETION TIME: K/A RATING: 2.6 JOB TITLE: RO REVISION: 0 TASK TITLE: Given a Clearance Order for venting/draining a contaminated system in the RCA, Determine the RWP, limits and time allowed to complete the job.
DUTY: Radiation Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED
REFERENCES:
TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04
Administrative RO A3 JPM NO: 004-A RO A3 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are a spare Reactor Operator. Another Operator has contacted you for assistance in completing a Clearance Order in the RCA.
Initiating Cues: The other Operator is requesting assistance in opening BG V0374, RWST To Charging Pump Suction Line Drain Valve, located in the A CCP Room. For this task:
- # identify the correct RWP.
- describe the dress out requirements.
- identify the dosimetry settings .
- consider that you have received 1830 MR dose this calendar year, and estimate your stay time in the lowest dose area of the room.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: #If performed at the RCA entrance. Allow the candidate to access the book of RWPs and tell you which RWP would be correct. When the Candidate indicates they are going to read the posted survey map for the indicated area, provide them with the survey map attached to this JPM.
- If performed in a classroom. Provide the candidate with the attached four RWPs and ask them to select the one appropriate for the job.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have identified:
- RWP 04-045
- dress out requirement of full set
- dosimetry setting of 20 mr Dose and 200 mr Dose Rate
- an estimated stay time of 4 hrs. (4 hrs. X 5mr = 20 mr dose)
START TIME:
STOP TIME:
PAGE 1 of 4
JPM NO: 004-A RO A3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 1 *Identify the correct Comments:
RWP If performed at the RCA entrance. Look in book outside Access Control. Note that RWP 04-045 is for Operations access for contaminated systems venting and draining activities If performed in a classroom. Select the correct RWP from the four provided.
S U In work activity block of
- 2. *Describe the dress RWP 04-045, note that Comments:
out requirements the requirement is for a full set.
Under setting block of 3 *Identify the dosimetry RWP 04-045, note the settings settings are :
- Dose 20 MR
- Rate 200 MR/HR
- CRITICAL STEP PAGE 2 of 4
JPM NO: 004-A RO A3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE Note that the limiting time
- 4. *Estimate your stay time is 20 MR dose from the in the lowest dose area RWP. The survey map of the room indicates a lowest dose area of 5 mr. 20 MR divided by 5 MR = 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> stay time THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 3 of 4
JPM NO: 004-A RO A3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are a spare Reactor Operator. Another Operator has contacted you for assistance in completing aClearance Order in the RCA.
Initiating Cues: The other Operator is requesting assistance in opening BG V0374, RWST To Charging Pump Suction Line Drain Valve, located in the A CCP Room. For this task:
- identify the correct RWP.
- describe the dress out requirements.
- identify the dosimetry settings .
- consider that you have received 1830 MR dose this calendar year, and estimate your stay time in the lowest dose area of the room.
PAGE 4 of 4
Administrative SRO A1a WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 005-A K/A NO: 2.1.33 COMPLETION TIME: K/A RATING: 4.0 JOB TITLE: SRO REVISION: 0 TASK TITLE: Review Surveillance Test for AFD and based on ASP results determine any required actions.
DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
MAY BE PERFORMED IN ANY LOCATION WHERE PROPER REFERENCE MATERIAL IS AVAILABLE.
METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
STS SF-002, Axial Flux Differential Core Operating Limits Report Technical Specification 3.2.3 TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04
JPM NO: 005-A SRO A1a Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has been stable at 100% power. The AFD Monitor Alarm is inoperable. A Reactor Operator performed one set of readings per STS SF-002 and then the AFD Monitor Alarm was declared operable.
Initiating Cues: You are to review the completed STS SF-002 for correctness and compliance.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide the candidate with a completed STS SF-002 on which the performer failed to recognize that AFD is out of the acceptable region of the COLR Figure 2.5.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have determined that the test performer failed to recognize that two of the NIs are out of the band acceptable in the COLR and that Technical Specification 3.2.3, Action A applies.
START TIME:
STOP TIME:
PAGE 1 of 3
JPM NO: 005-A SRO A1a Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Go to Attachment A and
- 1. *Record data as enter the data provide on Comments:
required on Attachment the cue sheet A
Determine that N41 and
- Compare % flux N44 are in the acceptable for each channel to region and annotate the COLR limits attachment accordingly.
Determine that N42 and STEP 8.1 N43 are in the unacceptable region and annotate the attachment accordingly.
S U Determine that the Plant
- 2. *If the indicated FLUX is in TS 3.2.3 Condition Comments:
DIFF is outside the A and must reduce acceptable limits of thermal power to <50%
COLR on two or more within 30 minutes.
operable PR channels, then perform the actions required by Tech Specs. THE JPM IS COMPLETE STEP 8.1.2 RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 2 of 3
JPM NO: 005-A SRO A1a Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has been stable at 100% power. The AFD Monitor Alarm is inoperable. A Reactor Operator performed one set of readings per STS SF-002 and then the AFD Monitor Alarm was declared operable.
Initiating Cues: You are to review the completed STS SF-002 for correctness and compliance.
PAGE 3 of 3
Administrative SRO A1b WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 006-A K/A NO: 2.1.20 COMPLETION TIME: K/A RATING: 4.2 JOB TITLE: SRO REVISION: 0 TASK TITLE: Given initial plant conditions of a SG tube leak, determine from the OFN the required actions.
DUTY: Conduct of Operations The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
OFN BB-07A, Steam Generator Tube Leakage TOOLS/EQUIPMENT: NONE PREPARER: DATE: 4/13/04
JPM NO: 006-A SRO A1b Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 1. SG tube leakage has been detected by Main Condenser Vacuum Pump Vent Radiation Monitor GE RE-92 going into Hi Hi Alarm. The crew is performing OFN BB-07A, Steam Generator Tube Leakage. The pressurizer is at program level and stable. Radiation Monitor BM RE-25 is not calibrated.
Initiating Cues: You are the Control Room Supervisor. Beginning at step 9 of OFN 7A, write down the steps you will perform and actions that will be taken.. Use your cue sheet to record your answers.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide an information only copy of OFN 7A, When the candidate indicates they need the conversion chart, provide them with a copy of AIF 21D-004-01-02.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have documented that they will perform Attachment C, Steps C1 and C4. After being cued that EG RE-92 is now inoperable, the Candidate will document that they will perform Step C2 directing that grab samples be performed once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
A sample answer sheet marked key is provided.
START TIME:
STOP TIME:
PAGE 1 of 8
JPM NO: 006-A SRO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. *Monitor SG Tube Comments:
Leakage NOTE Go to Attachment C, action level table Any time the candidate STEP 9 asks what GE RE-92 is reading, cue:
GE RE-92 reads 3.60E-01 µCi/cc.
S U
- 2. *Determine leak rate Comments:
Realize the need to use the conversion chart to determine the lake rate in order to use the table.
When asked, provide the conversion chart.
Realize the need to know what value is displayed by GE RE-92.
When asked:
GE RE-92 reads 3.60E-01 µCi/cc.
Use the conversion chart to determine the leak rate is 60 GPD.
STEP C1
- CRITICAL STEP PAGE 2 of 8
JPM NO: 006-A SRO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Use the chart in step C1
- 3. *Determine action level to determine a 60 GPD Comments:
leak is Action level 1 and go to step C4.
STEP C1 S U
- 4. *Establish NPIS time Comments:
trend Note there is not enough data to apply the notes.
If asked, the event has been in progress for 15 minutes.
STEP C4.a Establish a time trend on NPIS for GE RE-92.
(BM RE-25 is not calibrated per initial instructions)
S U
- 5. *Direct Chemistry to Comments:
obtain grab samples Notify Chemistry to take grab samples of the secondary at the frequency specified n STN CH-020.
STEP C4.b
- CRITICAL STEP PAGE 3 of 8
JPM NO: 006-A SRO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 6. *WHEN leak rate Comments:
stabilizes, THEN reset Realize the conditions radiation monitors. have not been met for this step yet but that this is a continuous action step to reset the rad monitors to be applied when appropriate STEP C4.c S U
- 7. Review procedures. Review OFN 7A, STN CH-020, OFN MA-38, Comments:
EMG E-0, EMG E-3, and the Emergency Plan procedures. (This is a suggested list. It is not critical that the candidate STEP C4.d identify this complete list.)
At this point, cue:
Radiation Monitor GE RE-92 is now inoperable.
- CRITICAL STEP PAGE 4 of 8
JPM NO: 006-A SRO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- 8. *Take actions appropriate for no Realize that no continuous rad monitors continuous rad monitors operable. are available now and return to C1. This condition meets the entry conditions for OFN BB-07A so the Candidate may indicate they are returning to Step 1 of OFN BB-07A.
If the Candidate indicates they are returning to Step 1 of OFN BB-07A, Cue:
All Plant conditions remain the same with the exception of GE RE-92.
STEP C1 S U
- 9. *Determine Action Comments:
Level. Realize that there are no operable continuous rad monitors and go to step C2.
STEP C1
- CRITICAL STEP PAGE 5 of 8
JPM NO: 006-A SRO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 10. *Return GE RE-92 and Comments:
BM RE-25 to perable as Take action to expedite rapidly as possible. trouble shooting on GE RE-92 and calibration on BM RE-25.
STEP C2.a S U
- 11. Direct Chemistry to Direct Chemistry to analyze grab samplesl sample the offgas system Comments:
every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
STEP C2.b S U
- 12. Consider more frequent sampling. Comments:
Realize that not enough data is available to make a definite decision on frequency of sampling but record this as a continuous action step STEP C2.c
- CRITICAL STEP PAGE 6 of 8
JPM NO: 006-A SRO A1b Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 13. Consider temporary Indicate consideration of radiation monitors directing that temporary Comments:
rad monitor be used.
STEP C2.d The JPM is Complete RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 7 of 8
JPM NO: 006-A SRO A1b Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 1. SG tube leakage has been detected by Main Condenser Vacuum Pump Vent Radiation Monitor GE RE-92 going into Hi Hi Alarm. The crew is performing OFN BB-07A, Steam Generator Tube Leakage. The pressurizer is at program level and stable. Radiation Monitor BM RE-25 is not calibrated.
Initiating Cues: You are the Control Room Supervisor. Beginning at step 9 of OFN 7A, write down the steps you will perform and actions that will be taken.. Use your cue sheet to record your answers.
PAGE 8 of 8
Administrative SRO A2 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 007-A K/A NO: 2.2.23 COMPLETION TIME: K/A RATING: 3.8 JOB TITLE: SRO REVISION: 0 TASK TITLE: Given a sequence of events, Determine the end time of an LCO including any extensions.
DUTY: Equipment Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
WCGS Integrated Technical Specifications and Bases, LCO 3.5.2 and Section 1.3 TOOLS/EQUIPMENT: NONE PREPARER: DATE: 4/14/04
JPM NO: 007-A SRO A2 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are the Control Room Supervisor, the Plant is stable in Mode 1.
The A train SI pump has been declared inoperable. The time of discovery is 1000 on 5/08/2004. The B train SI is OPERABLE.
Twelve (12) hours after the A train SI is declared inoperable, the B train RHR pump is declared inoperable.
At 1000 on 5/09/2004, the A train SI pump is restored to OPERABLE status.
Initiating Cues: The Shift Manager directs you to determine when the B train RHR pump must be restored to OPERABLE status to avoid commencing a unit shutdown, including any extensions permitted by Technical Specifications.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Ensure that a copy of Improved Technical Specification is available for the candidate to refer to.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM the candidate will have determined that the extensions allowed by section 1.3, Completion Times, would apply and that LCO 3.5.2 must be exited by 2200 on 12/11/2001.
START TIME:
STOP TIME:
PAGE 1 of 3
JPM NO: 007-A SRO A2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. The A train SI pump has been declared Comments:
inoperable. The time of discovery is 1000 on 5/08/2004. The B train SI is OPERABLE.
- Twelve (12) hours after the A train SI was declared inoperable, the B train RHR pump is declared inoperable
- At 100 on 5/09/2004 the A Train SI pump is *Determine that the restored to operable extensions allowed by status. section 1.3, Completion Times, would apply and that LCO 3.5.2 must be exited by 2200 on 5/11/2004 THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 2 of 3
JPM NO: 007-A SRO A2 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are the Control Room Supervisor, the Plant is stable in Mode 1.
The A train SI pump has been declared inoperable. The time of discovery is 1000 on 5/08/2004. The B train SI is OPERABLE.
Twelve (12) hours after the A train SI is declared inoperable, the B train RHR pump is declared inoperable.
At 1000 on 5/09/2004, the A train SI pump is restored to OPERABLE status.
Initiating Cues: The Shift Manager directs you to determine when the B train RHR pump must be restored to OPERABLE status to avoid commencing a unit shutdown, including any extensions permitted by Technical Specifications.
PAGE 3 of 3
Administrative SRO A3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 008-A K/A NO: 2.3.6 COMPLETION TIME: K/A RATING: 3.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: Given a Release Permit, review for technical accuracy DUTY: Radiation Control The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB PLANT CLASSROOM X METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
AP 07B-001, Radioactive Releases AI 07B- 024, Preparation of Containment Purge Permits APF-07B-001-09-08, Containment Purge Release Permit TOOLS/EQUIPMENT:
PREPARER: DATE: 3/09/04
Administrative SRO A3 JPM NO: 008-A SRO A3 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: It is May 11, 2004, at 0800. You are a spare Senior Reactor Operator. A containment purge has been initiated and stopped. The crew is preparing to initiate the purge again. The Reactor Operator has performed the prepatory steps on page 2 of 3 of the release permit provided.
Initiating Cues: The Shift Manager directs you to examine the permit for accuracy and compliance for the reinitiation. Locate and document the three errors on this permit.
The following readings are indicated on the RM11 High Setpoint Low Setpoint GTRE-22/33 2.06E-03 2.06E-04 GTRE-31/32 1.00E-03 5.83E-05 ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide the candidate with a copy of the partially completed APF 07B-001-09-08, Containment Purge Release Permit THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: At the completion of this JPM, the Candidate will have documented that:
- The RO inadvertently transposed the number for GTRE-22/33 and GTRE-31/32 when establishing the setpoints.
- This permit has expired and cannot be used.
- The reading for GTG 313 exceeds the restart limit and the purge cannot be reinitiated START TIME:
STOP TIME:
PAGE 1 of 3
JPM NO: 008-A SRO A3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Note that the RO
- 1. *Check the release transposed the number for Comments:
conditions GTRE-22/33 and GTRE-31/32 when establishing the setpoints.
Note that the permit has expired
- 2. *Check the special instructions Note that the reading for GTG 313 exceeds the allowable value for
- 3. *Check the restart of the purge Authorization Section, Release Data, and the continuation sheet THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 2 of 3
JPM NO: 008-A SRO A3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: It is May 11, 2004, at 0800. You are a spare Senior Reactor Operator. A containment purge has been initiated and stopped. The crew is preparing to initiate the purge again. The Reactor Operator has performed the prepatory steps on page 2 of 3 of the release permit provided.
Initiating Cues: The Shift Manager directs you to examine the permit for accuracy and compliance for the reinitiation. Locate and document the three errors on this permit.
The following readings are indicated on the RM11 High Setpoint Low Setpoint GTRE-22/33 2.06E-03 2.06E-04 GTRE-31/32 1.00E-03 5.83E-05 PAGE 3 of 3
Administrative (Simulator Scenario #2) SRO A-4 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 009B-A K/A NO: 2.4.41 COMPLETION TIME: K/A RATING: 4.1 JOB TITLE: SRO REVISION: 0 TASK TITLE: After observing an event on the simulator, make the E-plan Classification and Protective Action Recommendation.
DUTY: Emergency Plan The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
AP 06-002, Radiological Emergency Response Plan EPP 06-001, Control Room Operations EPP 06-005, Emergency Classification EPP 06-006, Protective Action Recommendations APF 06-002-01, Emergency Action Levels EPF 06-007-01, WCGS Emergency Notification TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04
JPM NO: 009B-A SRO A-4 Rev 0 Scenario #2 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are the Shift Manager.
Initiating Cues: Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: After the Candidate indicates they would obtain the Emergency Notification form from the Shift Managers desk drawer, present the blank form attached to this JPM.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have made the correct classification and the correct protective action recommendation per the performance page for the scenarion just completed.
START TIME:
STOP TIME:
PAGE 1 of 3
JPM NO: 009B-A SRO A-4 Rev 0 Scenario #2 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U EAL
- 1. *This classification is Comments:
for Scenario #2 3-LRCB1 - Yes 3-LRCB2 - Yes 3-LRCB3 - No 3-LRCB5 - Yes 3-LRCB6 - No 3-LRCB7 - No Alert
- 2. *Perform Attachment A PAR of EPP 06-006 Perform Attachment A of EPP 06-006 Complete EMERGENCY ACTION NOTIFICATION as indicated on attached Key.
- Sections 4, 5, 7, and 8 are critical THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 2 of 3
JPM NO: 009B-A SRO A-4 Rev 0 Scenario #2 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are the Shift Manager.
Initiating Cues: Analyze the events you have just experienced on the simulator, complete an EPF 06-007-01, WCGS Emergency Notification form. Use current plant status.
PAGE 3 of 3
Simulator S1 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO:101-S K/A NO: 029 EA1.02 COMPLETION TIME:15 Minutes K/A RATING: 3.6/3.3 JOB TITLE:RO/SRO REVISION: 0 TASK TITLE: Emergency Borate using EMG FR-S1 DUTY:Anticipated Transient Without Scram ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
EMG FR-S1, Response To Nuclear Power Generation ATWT TOOLS/EQUIPMENT: NONE PREPARER: DATE:
04/13/2004
JPM NO: 101-S S1 Simulator Setup IC 177 On monitor screen:
Monitor ybg8104 Set 1=0.045 Run Read to Examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: Your are the Reactor Operator, an ATWT has occurred, The Control Room Supervisor has entered EMG FR-S1, Safety Injection is not in progress. Five rods failed to insert after PG-19 and 20 were de-energized.
Initiating Cues: The Control Room Supervisor directs you to complete steps 5 through 7 of EMG FR-S1 to commence emergency boration.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide a copy of EMG FR-S1, Steps 5 thru 7 to the Candidate.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have established emergency boration flow via the RWST thru the Normal Charging Pump.
START TIME:
STOP TIME:
PAGE 1 of 6
JPM NO: 101-S S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Initiate Emergency Boration of RCS: Comments:
- Ensure one charging pump running Note that BG HIS-3 for the NCP has a red lite only and flow is indicated on BG FI-121a
- *Align boration flowpath
- a. Ensure boric Rotate handswitch BG acid pumps - HIS-5a and/or BG HIS -
AT LEAST 6a clockwise and note ONE red lite only illuminated.
RUNNING
- b. Open emergency Depress the open button borate to on BG HIS-8104 and note charging red lite only illuminated.
pump suction valve STEP 5.
- CRITICAL STEP PAGE 2 of 6
JPM NO: 101-S S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 2. Verify Charging Flowpath Comments:
- Ensure Charging Pumps to Regen HX Verify red lite only lit on Containment Iso Vlvs BG HIS-8105 and BG
- OPEN HIS-8106.
- Ensure Regen HX to Verify red lite only Loop Cold Leg illuminated on BG-8146 valves - ONLY ONE OR BG 8147. Verify OPEN green lite only on the remaining valve
- Adjust Charging flow to maintain Note pressurizer level at pressurizer level or trending to 27% on BB LI-459A or 460A or 461.
Select manual control and adjust BG FK-462 if necessary to establish desired level.
- Adjust back pressure control to establish Rotate BG HC-182 as between 8-13 gpm necessary to establish 8-seal injection flow to 13 gpm on BG FR 154, each RCP 155, 156, and 157.
STEP 6
- CRITICAL STEP PAGE 3 of 6
JPM NO: 101-S S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Note flow on BG FI-
- 3. *Check Emergency 183A is <30 GPM and Borate Flow Greater Comments:
recognize need to Than 30 GPM perform the RNO for Step 7
STEP 7
- CRITICAL STEP PAGE 4 of 6
JPM NO: 101-S S1 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 4. Perform the following:
Comments:
Depress open button on
- *Align RWST to BN HIS-112D or BN charging pump HIS-112E and note red suction lite only illuminated.
Depress the close pushbutton on BG HIS-112B or BG HIS-112C and verify green lite only is illuminated.
- *Check RWST Check BG FI-121A or flow through EM FI-917A or EM FI-charging system - 917B and note flow is GREATER THAN greater than 90 GPM 90 GPM Determine that
- IF RWST flow Attachment A is not through charging required.
system is less than 90 gpm THEN establish alternate boration flowpath using Attachment A Report to the Control Report to Control Room Control Room Room Supervisor that Supervisor that steps are Supervisor Immediate Borate flow of complete. acknowledges the greater than 90 GPM has report been established via the RWST This completes this JPM STEP 7 RNO RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 5 of 6
JPM NO: 101-S S1 Rev: 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: Your are the Reactor Operator, an ATWT has occurred, The Control Room Supervisor has entered EMG FR-S1, Safety Injection is not in progress. . Five rods failed to insert after PG-19 and 20 were de-energized Initiating Cues: The Control Room Supervisor directs you to complete steps 5 through 7 of EMG FR-S1 to commence emergency boration.
PAGE 6 of 6
In Plant P-3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 202-P K/A NO: 002 A2.01 COMPLETION TIME: 10 Minutes K/A RATING: 4.3/4.4 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: EMG C-0, Loss of All AC, Isolate RCP Seal Leak Off DUTY: Reactor Coolant System The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED
REFERENCES:
EMG C-0, Loss Of All AC Power TOOLS/EQUIPMENT: NONE PREPARER: DATE:
04/13/2004
JPM NO: 202-P P-3 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has experienced a total loss of AC power. EMG C-0 is being performed.
Initiating Cues: The Control Room Supervisor has directed you to perform step 15 of EMG C-0 to isolate the RCP seals.
DO NOT OPERATE ANY EQUIPMENT IN THE PLANT ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide the operator with a copy of EMG C-0, Step 15.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have isolated the valves from the RCP seals.
START TIME:
STOP TIME:
PAGE 1 of 4
JPM NO: 202-P P-3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- 1. Dispatch personnel to locally close valves to isolate RCP seals Go to BG HV-8100 at S U
- *Seal Water Return As operator describes Aux Building , 2000 Comments:
Containment Isolation opening valve cue: level, South Penetration Valve Room. Gently disengage Clutch Lever is clutch lever while turning BG HV-8100 disengaged the handwheel in a clockwise direction. The Stem is retracting.
declutch lever may be Handwheel stops released once it engages.
turning. Continue turning the handwheel clockwise till the stem is fully retracted and the handwheel stops turning.
- *Seal Water Valve is turning in the clockwise direction.
Go to BG V101 at Aux Building, 2000 level, S U Injection Filters Inlet RX Coolant Filter/Seal Isolations Valve will not turn any more. Stem is totally Injection Filter A Valve Comments:
inserted. Room. Rotate the valve BG-V101 operator in the clockwise BG-V105 direction and note the position of the stem.
Go to BG V105 at Aux Valve is turning in the Building, 2000 level, S U clockwise direction. RX Coolant Filter/Seal Valve will not turn any Injection Filter B Valve Comments:
more. Stem is totally Room. Rotate the valve operator in the clockwise inserted direction and note the position of the stem
- CRITICAL STEP PAGE 2 of 4
JPM NO: 202-P P-3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- *CCW Return From S U RCS Isolation Valve Go to the EG HV-61 at the Aux Building, 2000, Comments:
As operator describes EG HV-61 North Penetration Room.
opening valve cue:
Gently disengage clutch Clutch Lever is lever while turning the disengaged handwheel in a clockwise direction. The declutch Stem is inserting.
lever may be released Handwheel stops once it engages. Continue turning. turning the handwheel clockwise till the stem is fully inserted and the handwheel stops turning..
Contact Control Room and Report step complete Call Control Room and Acknowledge report report step 15 complete.
STEP 15 THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 3 of 4
JPM NO: 202-P P-3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has experienced a total loss of AC power. EMG C-0 is being performed.
Initiating Cues: The Control Room Supervisor has directed you to perform step 15 of EMG C-0 to isolate the RCP seals.
DO NOT OPERATE ANY EQUIPMENT IN THE PLANT PAGE 4 of 4
Simulator S2 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 202-S K/A NO: 3.2 006 A1.13 COMPLETION TIME: 25 Minutes K/A RATING: 3.5/3.7 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Fill an SI Accumulator - Mode 3 DUTY: Emergency Core Cooling System (ECCS)
The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
TOOLS/EQUIPMENT: NONE PREPARER: DATE: 04/13/2004
JPM NO: 201-S S2 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are the Reactor Operator with the plant stable in Mode 3. Accumulator "C" level is approximately 40% and annunciator 45C is lit. There is no known leakage past the Accumulator check valves. RWST was sampled yesterday and boron concentration is 2423 ppm. No evolutions have occurred that would have diluted the RWST since the sample.
Initiating Cues: The Control Room Supervisor directs you to raise SI Accumulator "C" level to between 55% - 58% using B SI Pump. RHR Header depressurization is desired during pump run. Safety Injection Pump discharge relief valves are expected to lift upon pump start.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide an information only copy of SYS EP-200 to the Candidate.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)
Task Standard: At the completion of this JPM, the Examinee will have increased SI Accumulator "C" level to 55% - 58% using B Safety Injection Pump.
START TIME:
STOP TIME:
PAGE 1 of 12
JPM NO: 201-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Perform Prerequisites.
Comments:
5.1 - 5.3 Steps 5.1 - 5.3 should be N/A 5.4 Ensure cooling to desired SI pump. Verifies B CCW Train has a running pump.
5.5 Check both SI Train Initial step.
A and B are operable Cue from CRS: BOTH Trains are operable. Initial step.
S U
6.1.1 Check accumulator Determine pressure is pressure less than 619 psig. N/A the step.
Locate RCS or PRZR 6.1.2 Record RCS Pressure pressure indication on RL002. Record the pressure.
6.1.3 Depressurize RHR header if desired.
Locate EJ HIS 8890A or
- Open EJ HIS-8890A or B and open one valve.
8890B N/A the other valve.
- Ensure EM HIS-8964 Check open.
Open Check open.
6.1.4 Using SI Pump A
- CRITICAL STEP PAGE 2 of 12
JPM NO: 201-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 3. Procedure Comments:
6.1.5 Using SI Pump B
- 2. Ensure BN HIS 8813 - Ensures Red Lite lit on OPEN BNIS-8813 Recognizes initial cue
- 3. *Close EM HIS-8821B was that reliefs are expected to lift. *The critical step is to inform the CRS that T.S. 3.5.2 must be entered prior to closing the valve. Press close button and observe Green Lite lit and Red Lite out.
While not critical Mgmt expectations are to make a plant announcement prior to start and to have a NPIS screen displaying pump parameters for the B SI pump.
- 5. *Open EM HIS 8821B *Presses open on EM HIS 8821B. Observe Red Lite lit and Green Lite out. Informs CRS that T.S. 3.5.2 can be exited.
- CRITICAL STEP PAGE 3 of 12
JPM NO: 201-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 4. Fill Accumulator Comments:
Steps 6.1.7 and 6.1.8 6.1.7 for Accumulator A and were marked N/A by the 6.1.8 for Accumulator B. CRS prior to starting.
6.1.9 Fill Accumulator C Locate EP LI-954 or EP LI-955 on RL018.
- 1. Record highest level Record level.
- 3. *Fill to 55 - 58% Monitor level and close EP HIS-8878C when and close EP HIS-8878C. between 55 - 58%. *The critical step is not to exceed 77.8% which would make the Accumulator inoperable.
- 4. Record level change. Record level change for accumulator "C". Final -
initial. Should be from 15 to 18%.
- CRITICAL STEP PAGE 4 of 12
JPM NO: 201-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 5. Continue Procedure Press close button on EM Comments:
6.1.11 Close EM HIS-8888 HIS-8888 and observe Green Lite lit and Red Lite out.
6.1.12 Run SI pump for 5-10 Initial Conditions stated minutes. leakage was not present.
- 6.1.13 Stop SI Pump B.
- Rotate EM HIS-5 to Stop; observe Red Lite out and Green Lite lit.
While not critical, Mgmt expectations are to make a plant announcement when securing B SI pump.
6.1.14 Ensure valves closed. Press Close on valve EJ HIS-8890A opened in step 6.1.3.
EJ HIS-8890B Ensures Green Lite lit and Red Lite out.
6.1.15 Ensure valves open.
As CRS cue:
EM HIS-8964 Ensures Red Lite lit and EM HIS-8871 SYS EJ-323 is in effect.
Leave valves open. Green Lite out.
6.1.16 Check for Chemistry N/A the step.
need to sample.
Acknowledge request. Contacts Turbine 6.1.17 Secure Pump Room Building Operator to stop Cooler. Respond as Turbine Watch: B Pump Room fan at breaker for B Cooler is secured. room.
Initial and Date step.
THE JPM IS COMPLETE 6.1.18 Section 6.1 complete.
RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 5 of 12
JPM NO: 201-S S2 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are the Reactor Operator with the plant stable in Mode 3. Accumulator "C" level is approximately 40% and annunciator 45C is lit. There is no known leakage past the Accumulator check valves. RWST was sampled yesterday and boron concentration is 2423 ppm. No evolutions have occurred that would have diluted the RWST since the sample.
Initiating Cues: The Control Room Supervisor directs you to raise SI Accumulator "C" level to between 55% - 58% using B SI Pump. RHR Header depressurization is desired during pump run.. Safety Injection Pump discharge relief valves are expected to lift upon pump start.
PAGE 12 of 12
In Plant P-3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 202-P K/A NO: 002 A2.01 COMPLETION TIME: 10 Minutes K/A RATING: 4.3/4.4 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: EMG C-0, Loss of All AC, Isolate RCP Seal Leak Off DUTY: Reactor Coolant System The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED
REFERENCES:
EMG C-0, Loss Of All AC Power TOOLS/EQUIPMENT: NONE PREPARER: DATE:
04/13/2004
JPM NO: 202-P P-3 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has experienced a total loss of AC power. EMG C-0 is being performed.
Initiating Cues: The Control Room Supervisor has directed you to perform step 15 of EMG C-0 to isolate the RCP seals.
DO NOT OPERATE ANY EQUIPMENT IN THE PLANT ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide the operator with a copy of EMG C-0, Step 15.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have isolated the valves from the RCP seals.
START TIME:
STOP TIME:
PAGE 1 of 4
JPM NO: 202-P P-3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- 1. Dispatch personnel to locally close valves to isolate RCP seals Go to BG HV-8100 at S U
- *Seal Water Return As operator describes Aux Building , 2000 Comments:
Containment Isolation opening valve cue: level, South Penetration Valve Room. Gently disengage Clutch Lever is clutch lever while turning BG HV-8100 disengaged the handwheel in a clockwise direction. The Stem is retracting.
declutch lever may be Handwheel stops released once it engages.
turning. Continue turning the handwheel clockwise till the stem is fully retracted and the handwheel stops turning.
- *Seal Water Valve is turning in the clockwise direction.
Go to BG V101 at Aux Building, 2000 level, S U Injection Filters Inlet RX Coolant Filter/Seal Isolations Valve will not turn any more. Stem is totally Injection Filter A Valve Comments:
inserted. Room. Rotate the valve BG-V101 operator in the clockwise BG-V105 direction and note the position of the stem.
Go to BG V105 at Aux Valve is turning in the Building, 2000 level, S U clockwise direction. RX Coolant Filter/Seal Valve will not turn any Injection Filter B Valve Comments:
more. Stem is totally Room. Rotate the valve operator in the clockwise inserted direction and note the position of the stem
- CRITICAL STEP PAGE 2 of 4
JPM NO: 202-P P-3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- *CCW Return From S U RCS Isolation Valve Go to the EG HV-61 at the Aux Building, 2000, Comments:
As operator describes EG HV-61 North Penetration Room.
opening valve cue:
Gently disengage clutch Clutch Lever is lever while turning the disengaged handwheel in a clockwise direction. The declutch Stem is inserting.
lever may be released Handwheel stops once it engages. Continue turning. turning the handwheel clockwise till the stem is fully inserted and the handwheel stops turning..
Contact Control Room and Report step complete Call Control Room and Acknowledge report report step 15 complete.
STEP 15 THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 3 of 4
JPM NO: 202-P P-3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has experienced a total loss of AC power. EMG C-0 is being performed.
Initiating Cues: The Control Room Supervisor has directed you to perform step 15 of EMG C-0 to isolate the RCP seals.
DO NOT OPERATE ANY EQUIPMENT IN THE PLANT PAGE 4 of 4
Simulator S2 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 202-S K/A NO: 3.2 006 A1.13 COMPLETION TIME: 25 Minutes K/A RATING: 3.5/3.7 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Fill an SI Accumulator - Mode 3 DUTY: Emergency Core Cooling System (ECCS)
The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
TOOLS/EQUIPMENT: NONE PREPARER: DATE: 04/13/2004
JPM NO: 201-S S2 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are the Reactor Operator with the plant stable in Mode 3. Accumulator "C" level is approximately 40% and annunciator 45C is lit. There is no known leakage past the Accumulator check valves. RWST was sampled yesterday and boron concentration is 2423 ppm. No evolutions have occurred that would have diluted the RWST since the sample.
Initiating Cues: The Control Room Supervisor directs you to raise SI Accumulator "C" level to between 55% - 58% using B SI Pump. RHR Header depressurization is desired during pump run. Safety Injection Pump discharge relief valves are expected to lift upon pump start.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide an information only copy of SYS EP-200 to the Candidate.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)
Task Standard: At the completion of this JPM, the Examinee will have increased SI Accumulator "C" level to 55% - 58% using B Safety Injection Pump.
START TIME:
STOP TIME:
PAGE 1 of 12
JPM NO: 201-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Perform Prerequisites.
Comments:
5.1 - 5.3 Steps 5.1 - 5.3 should be N/A 5.4 Ensure cooling to desired SI pump. Verifies B CCW Train has a running pump.
5.5 Check both SI Train Initial step.
A and B are operable Cue from CRS: BOTH Trains are operable. Initial step.
S U
6.1.1 Check accumulator Determine pressure is pressure less than 619 psig. N/A the step.
Locate RCS or PRZR 6.1.2 Record RCS Pressure pressure indication on RL002. Record the pressure.
6.1.3 Depressurize RHR header if desired.
Locate EJ HIS 8890A or
- Open EJ HIS-8890A or B and open one valve.
8890B N/A the other valve.
- Ensure EM HIS-8964 Check open.
Open Check open.
6.1.4 Using SI Pump A
- CRITICAL STEP PAGE 2 of 12
JPM NO: 201-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 3. Procedure Comments:
6.1.5 Using SI Pump B
- 2. Ensure BN HIS 8813 - Ensures Red Lite lit on OPEN BNIS-8813 Recognizes initial cue
- 3. *Close EM HIS-8821B was that reliefs are expected to lift. *The critical step is to inform the CRS that T.S. 3.5.2 must be entered prior to closing the valve. Press close button and observe Green Lite lit and Red Lite out.
While not critical Mgmt expectations are to make a plant announcement prior to start and to have a NPIS screen displaying pump parameters for the B SI pump.
- 5. *Open EM HIS 8821B *Presses open on EM HIS 8821B. Observe Red Lite lit and Green Lite out. Informs CRS that T.S. 3.5.2 can be exited.
- CRITICAL STEP PAGE 3 of 12
JPM NO: 201-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 4. Fill Accumulator Comments:
Steps 6.1.7 and 6.1.8 6.1.7 for Accumulator A and were marked N/A by the 6.1.8 for Accumulator B. CRS prior to starting.
6.1.9 Fill Accumulator C Locate EP LI-954 or EP LI-955 on RL018.
- 1. Record highest level Record level.
- 3. *Fill to 55 - 58% Monitor level and close EP HIS-8878C when and close EP HIS-8878C. between 55 - 58%. *The critical step is not to exceed 77.8% which would make the Accumulator inoperable.
- 4. Record level change. Record level change for accumulator "C". Final -
initial. Should be from 15 to 18%.
- CRITICAL STEP PAGE 4 of 12
JPM NO: 201-S S2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 5. Continue Procedure Press close button on EM Comments:
6.1.11 Close EM HIS-8888 HIS-8888 and observe Green Lite lit and Red Lite out.
6.1.12 Run SI pump for 5-10 Initial Conditions stated minutes. leakage was not present.
- 6.1.13 Stop SI Pump B.
- Rotate EM HIS-5 to Stop; observe Red Lite out and Green Lite lit.
While not critical, Mgmt expectations are to make a plant announcement when securing B SI pump.
6.1.14 Ensure valves closed. Press Close on valve EJ HIS-8890A opened in step 6.1.3.
EJ HIS-8890B Ensures Green Lite lit and Red Lite out.
6.1.15 Ensure valves open.
As CRS cue:
EM HIS-8964 Ensures Red Lite lit and EM HIS-8871 SYS EJ-323 is in effect.
Leave valves open. Green Lite out.
6.1.16 Check for Chemistry N/A the step.
need to sample.
Acknowledge request. Contacts Turbine 6.1.17 Secure Pump Room Building Operator to stop Cooler. Respond as Turbine Watch: B Pump Room fan at breaker for B Cooler is secured. room.
Initial and Date step.
THE JPM IS COMPLETE 6.1.18 Section 6.1 complete.
RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 5 of 12
JPM NO: 201-S S2 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are the Reactor Operator with the plant stable in Mode 3. Accumulator "C" level is approximately 40% and annunciator 45C is lit. There is no known leakage past the Accumulator check valves. RWST was sampled yesterday and boron concentration is 2423 ppm. No evolutions have occurred that would have diluted the RWST since the sample.
Initiating Cues: The Control Room Supervisor directs you to raise SI Accumulator "C" level to between 55% - 58% using B SI Pump. RHR Header depressurization is desired during pump run.. Safety Injection Pump discharge relief valves are expected to lift upon pump start.
PAGE 12 of 12
Simulator S7 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO:301-S K/A NO: 006 A2.03 COMPLETION TIME:15 Minutes K/A RATING: 3.3/3.7 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: OFN BB-31 S/D LOCA, Isolate RHR Leak DUTY: Emergency Core Cooling System The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
OFN BB-031, Shutdown LOCA TOOLS/EQUIPMENT: NONE PREPARER: DATE:
04/13/2004
JPM NO: 301-S S7 Rev 0 Simulator Setup IC 173 Malfunction mRHR07A and tie to event 1 Ensure Digital Displays are selected to Top BBP0403 and place sticky note on label Bottom BBT0413A and place sticky note on label DNO SIP A, SIP B, and CCP A Run Read to Examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 4. You are the Reactor Operator, a loss of reactor coolant is occurring. A Train RHR system is aligned and operating in the Shutdown Cooling Mode. The crew has entered OFN BB-31 and performed steps 1 thru 26 a. All efforts to isolate the leak so far have been unsuccessful.
Initiating Cues: Per Step 26a RNO, the Control Room Supervisor directs you to perform Attachment C. Pressure is 375 pounds and decreasing.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide a copy of OFN BB-031, Attachment C, to the Candidate..
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have isolated the RCS leak by closing the RCS hot leg to RHR Pump A Suction Valves.
START TIME:
STOP TIME:
PAGE 1 of 5
JPM NO: 301-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Check at least one RHR Determine that red lite Pump - OPERATING IN only is illuminated on EJ Comments:
COOLDOWN MODE HIS-1 with EJ PI-614 indicating discharge pressure and EJ FI-618 STEP C1 indicating flow.
S U Check EJ TR-612 and
- 2. *Check operating RHR determine that Comments:
Pump discharge temperature is greater temperature - than 260°F GREATER THAN 260°F STEP C2 S U
- 3. Isolate flow through operating RHR train Comments:
Operate EJ HIC-606 clockwise until scale
- *Place RHR HX and depress the close bypass controls in pushbutton until the scale manual and close the indicates 0 output valves STEP C3
- CRITICAL STEP PAGE 2 of 5
JPM NO: 301-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 4. Check operating RHR Check EJ TR-612 red pen Pump discharge and note decreasing Comments:
temperature - temperature trend DECREASING:
NOTE: Candidate may perform Step C4 RNO STEP C4 and ensure RHR recirc valves and CCW to HX valves - OPEN if immediate temperature decrease is not apparent.
S U Check EJ TR-612 red pen
- 5. *Check operating RHR and note temperature Comments pump discharge <260°F temperature - LESS THAN OR EQUAL TO 260°F :
NOTE: Temperature may not be <260°F yet Candidate may be STEP C5 required to perform the RNO and loop back to Step C4 until temperature reaches <260°F S U
- 6. Check RHR pump A - Check lineup from hot RUNNING IN legs to HX into cold legs. Comments COOLDOWN MODE NOTE: This was part of initial conditions STEP C6
- CRITICAL STEP PAGE 3 of 5
JPM NO: 301-S S7 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 7. Check RHR pump A for leakage Comments
- Rotate EJ HIS-1 to the
- *Stop RHR Pump A left and note green lite only illuminated. with EJ PI-614 indicating no discharge pressure and EJ FI-618 indicating no flow.
- RCS leakage stopped or reduced Note wide range pressure increasing.
- *Isolate RHR Train A from the RCS by *Depress the close closing RCS hot leg pushbutton on BB HIS-to RHR Pump A 8702A and EJ HIS-suction valves 8701A and note green lites only illuminated.
- Check RCS leakage isolated Note wide range pressure increasing.
Control Room Inform CRS that the leak
- Align RHR Train B Supervisor has been isolated and for RCS cooldown acknowledges the next intended action is to per SYS EJ-120 report perform SYS EJ-120 This completes the JPM RECORD STOP TIME STEP C7 ON PAGE 1
- CRITICAL STEP PAGE 4 of 5
JPM NO: 301-S S7 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 4. You are the Reactor Operator, a loss of reactor coolant is occurring. A Train RHR system is aligned and operating in the Shutdown Cooling Mode. The crew has entered OFN BB-31 and performed steps 1 thru 26 a. All efforts to isolate the leak so far have been unsuccessful.
Initiating Cues: Per Step 26a RNO, the Control Room Supervisor directs you to perform Attachment C. Pressure is 375 pounds and decreasing.
PAGE 5 of 5
In Plant P-1 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 302-P K/A NO: 006 A2.02 COMPLETION TIME: 10 Minutes K/A RATING:3.9/4.3 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Establish Alternate High Head Injection DUTY: Emergency Core Cooling System The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED
REFERENCES:
EMG FR-C1, Response to Inadequate Core Cooling TOOLS/EQUIPMENT: NONE PREPARER: DATE:
04/13/2004
JPM NO: 302-P P-1 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are a spare licensed operator assigned to the shift. The Plant has experienced a loss of coolant accident resulting in a reactor trip and safety injection. The crew has transitioned to EMG FR-C1, Response to Inadequate Core Cooling. The Normal Charging Pump was tagged out for maintenance and the Aux Building Operator is removing the Clearance Order at this time.
Initiating Cues: The Control Room Supervisor directs you to take a copy of Attachment A from EMG C-1, Response to Inadequate Core Cooling, and go to the Aux Building. There you are to coordinate with the Reactor Operator (RO) and perform Attachment A to establish Alternate High Head Injection. The RO is ready to perform step A11 of the attachment.
DO NOT OPERATE ANY EQUIPMENT IN THE PLANT ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Provide the candidate with an information only copy of EMG FR-C1, Attachment A.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have aligned the NCP discharge to the Boron Injection Tank.
START TIME:
STOP TIME:
PAGE 1 of 7
JPM NO: 302-P P-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Open BIT Inlet Valves As RO cue: 8803A indicates no power and Comments:
8803B is not responding.
Perform RNO for Step Critical Step is to open A11. EM HV-8803A.
Locate EM HV-8803A in the BIT room. Gently Locally Open Bit Inlet disengage clutch lever Valves while turning the As applicant describes handwheel in a counter
- EM HV-8803A opening valve cue: clockwise direction. The Clutch Lever is declutch lever may be disengaged released once it engages.
Continue turning the Stem is rising. handwheel counter Handwheel stops clockwise till the stem is turning. fully extended and the handwheel stops turning.
Position indicator points to open.
EM HV-8803B As applicant describes EM HV-8803B is bound opening valve cue: and will not open.
Handwheel will not turn.
Contact Control Room Acknowledge report.
and report status.
Going to step A12.
STEP A11 RNO
- CRITICAL STEP PAGE 2 of 7
JPM NO: 302-P P-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- 2. Open BIT Outlet Valves As RO cue: I have no S U power indicated on either BIT outlet valve. Comments:
Perform RNO.
- Locally Open Bit Outlet The critical task is to Valves open at least one of the BIT outlet valves.
Locate EM HV-8801A EM HV-8801A As applicant describes and 8801B in the North opening valves cue: Piping Penetration room.
EM HV-8801B Clutch Lever is Gently disengage clutch disengaged lever while turning the handwheel in a counter Stem is rising. clockwise direction. The declutch lever may be Handwheel stops released once it engages.
turning. Continue turning the handwheel counter Position indicator points clockwise till the stem is to open. fully extended and the handwheel stops turning.
Contact Control Room and report status. Acknowledge Report.
STEP A12 RNO
- CRITICAL STEP PAGE 3 of 7
JPM NO: 302-P P-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- 3. RO performs steps A13 AS RO cue: The None and A15 from the Control Clearance Order has Room. been removed from the NCP. The Aux Building Watch is standing by while I start the NCP.
I have completed steps A13 and A15. The NCP is running. Perform step A16.a.
S U
- 4. Ensure one train of valves from charging Comments:
header to BIT - OPEN. BG-8483A stem is fully Locate BG-8483A in the retracted and locking A CCP Room. The applicant must
- Locally open BG-8483A. device is installed. recognize that only EM Remove locking device.
Locking device HV-8803A was opened Rotate handwheel removed. at step A11 and ensure counterclockwise and BG-8483A is open to Stem is rising. watch for stem rising.
align for flow.
Stem must be fully Handwheel stops extended and the turning. handwheel stops turning to verify valve is full open.
Locally close BG-8483C.
BG-8483C stem is fully Applicant may or may not BG-8483C may be in a extended and locking close the B Train contaminated area. If so device is installed. valve. Locate BG-8483C have applicant describe in the B CCP Room. the process.
Locking device removed.
Remove locking device.
Stem is inserting. Rotate handwheel clockwise and watch for Handwheel stops stem inserting. Stem must turning. be fully inserted and the handwheel stops turning to verify valve is full Report status to Control closed.
Room. Acknowledge Report
- CRITICAL STEP PAGE 4 of 7
JPM NO: 302-P P-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U 5.Check CCP to BIT Flow As RO cue: I have Meters - FLOW completed step A16. At Comments:
INDICATED. step A17 I still have no BIT flow indicated. I have performed step A17 RNO a. Continue with the RNO for steps b and c.
Step A17 RNO a.
S U
- 6. Check CCP to BIT Flow Meters - FLOW Comments:
INDICATED. Locate BG-8483B in the NCP Room. Ensure valve The critical task is to Locally ensure BG-8483B is Stem is fully extended. is open by checking for open BG-8388.
open. Handwheel will not turn stem fully extended.
counterclockwise. Applicant may attempt to turn handwheel counterclockwise.
Locate BG-8388 in the NCP Room. Ensure valve is open by checking for
- Locally ensure BG-8388 is Stem is fully retracted. stem fully extended.
open. Recognize valve Handwheel is turning. indicates closed. Turn Stem is rising. handwheel in the counterclockwise Stem is fully extended. direction watching for Handwheel will not turn stem movement. Continue counterclockwise. turning handwheel till the stem is fully extended and the handwheel stops turning.
Step A17 RNO b and c
- CRITICAL STEP PAGE 5 of 7
JPM NO: 302-P P-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 7. Report task complete Comments:
Acknowledge report. I Simulate calling the have BIT flow indicated. Control Room and reporting task complete.
THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 6 of 7
JPM NO: 302-P P-1 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: You are a spare licensed operator assigned to the shift. The Plant has experienced a loss of coolant accident resulting in a reactor trip and safety injection. The crew has transitioned to EMG FR-C1, Response to Inadequate Core Cooling. The Normal Charging Pump was tagged out for maintenance and the Aux Building Operator is removing the Clearance Order at this time.
Initiating Cues: The Control Room Supervisor directs you to take a copy of Attachment A from EMG C-1, Response to Inadequate Core Cooling, and go to the Aux Building. There you are to coordinate with the Reactor Operator (RO) and perform Attachment A to establish Alternate High Head Injection. The RO is ready to perform step A11 of the attachment.
DO NOT OPERATE ANY EQUIPMENT IN THE PLANT PAGE 7 of 7
Simulator S4 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 401-S K/A NO: 061 A1.01 COMPLETION TIME: 15 Minutes K/A RATING: 3.9/4.2 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Feed S/Gs with TDAWP DUTY: Auxiliary/Emergency Feedwater System The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
SYS AL-120, Feeding Steam Generators With A Motor Driven or Turbine Driven AFW Pump TOOLS/EQUIPMENT: NONE PREPARER: DATE:
04/13/2004
JPM NO: 401-S S4 Rev 0 Simulator Preparation:
IC 174 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 3 at normal operating temperature and pressure. SG levels are being maintained in the narrow range instruments The Start Up Motor Driven Feed Pump has tripped.
Initiating Cues: The Control Room Supervisor directs you to start the Turbine Driven Auxiliary Feed Water Pump (TDAFWP) and increase SG levels using Section 6.2 of SYS AL-120.
Stabilize level between 50 and 55%. Return the TDAFWP to standby conditions when finished. The procedure prerequisites are satisfied.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide a current copy of SYS AL-120 to the Candidate.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have increase SG level to 50% narrow range using the Turbine Driven Auxiliary Feedwater Pump.
START TIME:
STOP TIME:
PAGE 1 of 11
JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Verify AFP Turb On FC HIS-312A verify mechanical trip/throttle green lite only is lit. Comments:
valve is closed STEP 6.2.1
- CRITICAL STEP PAGE 2 of 11
JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 2. *Close the TDAFWP Comments:
discharge throttle valves to each SG Operate the AL HK-8A
- SG A control to the closed detent position and verify output meter indicates zero.
Operate the AL HK-10A
- SG B control to the closed detent position and verify output meter indicates zero Operate the AL HK-12A
- SG C control to the closed detent position and verify output meter indicates zero Operate the AL HK-6A
- SG D control to the closed detent position and verify output meter indicates zero STEP 6.2.2
- CRITICAL STEP PAGE 3 of 11
JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 3. *Open at least one Comments:
steam supply valve to TDAFWP Depress the open
- Open loop 2 steam pushbutton on AB HIS-supply 5A and verify red lite only is lit And/Or And/Or Depress the open
- Open loop 3 steam pushbutton on AB HIS-supply 6A and verify red lite only is lit STEP 6.2.3 S U
- 4. Start TDAFWP Comments:
- *Open trip/throttle valve Depress the open pushbutton on FC HIS-312A and note red lite only is lit. Note red light only on FC ZL-315A/317A, discharge pressure and flow indicated on AL PI 21A, and the SG flow indicator(s).
Record time opened in
- Time valve opened blank on 6.2.4.2
- Verify discharge Note pressure on AL PI-pressure greater than 21A is >1625 psig and 1625 psig record in blank on 6.2.4.3 STEP 6.2.4
- CRITICAL STEP PAGE 4 of 11
JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 5. *Throttle flow to Comments:
desired steam generators
- SG A Operate the controller on AL HK-8A to the open position until 75,000-100,000 LBM is indicated on AL FI-2A
- SG B Operate the controller on AL HK-10A to the open position until 75,000-100,000 LBM is indicated on AL FI-3A
- SG C Operate the controller on AL HK-12A to the open position until 75,000-100,000 LBM is indicated on AL FI-4A
- SG D Operate the controller on AL HK-6A to the open position until 75,000-100,000 LBM is indicated on AL FI-1A STEP 6.2.5
- CRITICAL STEP PAGE 5 of 11
JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 6. Record TDAFWP total Add the indication on AL flow FI-1A, 2A, 3A, and 4A Comments:
and record sum in blank STEP 6.2.6 provided S U Monitor SG level on
- 7. *Monitor appropriate level recorders and SG Comments:
SG levels NR indicators.
Determine NR levels are STEP 6.2.7 increasing as appropriate
- CRITICAL STEP PAGE 6 of 11
JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Note 50% NR level
level is obtained, Operate the controller on then adjust the flow AL HK-8A until 25%
control valve demand is indicated or to controllers to 25% the signal necessary to demand position stabilize level.
STEP 6.2.8 Note 50% NR level indicated on SG B.
Operate the controller on AL HK-8A until 25%
demand is indicated or to the signal necessary to stabilize level.
Note 50% NR level indicated on SG C.
Operate the controller on AL HK-8A until 25%
demand is indicated or to the signal necessary to stabilize level.
Note 50% NR level indicated on SG D.
Operate the controller on AL HK-8A until 25%
demand is indicated or to the signal necessary to stabilize level.
- CRITICAL STEP PAGE 7 of 11
JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 9. Stop the TDAFWP:
Comments:
- If running after auto Realize this step is NA start then ensure all activation signals are reset/blocked
- *Close Depress the close pushbutton on FC HIS-Trip/Throttle valve 312A and note green lite only is lit. Should check discharge pressure (AL PI-21A) and SG flow indicators (AL FI-1A, 2A, 3A, and 4A) returning to zero.
Record the time the valve
- Time valve closed was closed in blank provided.
- *Close steam supply Depress the close valves to TDAFWP pushbutton on AB HIS-5A and verify green lite only is lit And/Or Depress the close pushbutton on AB HIS-6A and verify green lite only is lit STEP 6.2.9
- CRITICAL STEP PAGE 8 of 11
JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 10. Return TDAFWP Comments:
discharge throttle valves to safeguards lineup.
Operate controller to
Operate controller to latch detent open position
Operate controller to latch detent open position
Operate controller to latch detent open position and note demand meter indicates 100.
- 11. If stopping the TDAFWP Realize this step is NA after auto start, then Comments:
perform the following STEP 6.2.11
- CRITICAL STEP PAGE 9 of 11
JPM NO: 401-S S4 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 12. Section 6.2 complete Report to Control Room Supervisor that section Comments:
STEP 6.2.12 6.2 is complete.
ACKNOWLEDGE THE REPORT THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 10 of 11
JPM NO: 401-S S4 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 3 at normal operating temperature and pressure. SG levels are being maintained in the narrow range instruments The Start Up Motor Driven Feed Pump has tripped.
Initiating Cues: The Control Room Supervisor directs you to start the Turbine Driven Auxiliary Feed Water Pump (TDAFWP) and increase SG levels using Section 6.2 of SYS AL-120.
Stabilize level between 50 and 55%. Return the TDAFWP to standby conditions when finished. The procedure prerequisites are satisfied.
PAGE 11 of 11
Simulator S3 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 501-S K/A NO: E15 EA1.3 COMPLETION TIME: 14 Minutes K/A RATING: 2.8/3.0 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE Isolate Source of Containment Flooding, EMG FR-Z2 DUTY: Containment Flooding The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
EMG FR-Z2, Response To Containment Flooding TOOLS/EQUIPMENT: NONE PREPARER: DATE:
04/13/2004
JPM NO: 501-S S3 Rev 0 Simulator Setup IC 174 Run Override annuns 60E and 60F ON Insert ESW break mWAT07A at 30%
Insert override on P20013a (value 87)
Insert override on P20013b(value 87)
Freeze until JPM begins Read to Examinee I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The crew is recovering from a reactor trip. An Orange Path exists for Critical Safety Function - Containment.
Initiating Cues: The Control Room Supervisor directs you to perform Steps of EMG FR-Z2, Response To Containment Flooding.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide a current copy of EMG FR-Z2 to the Candidate.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have determined the leak location and will have isolated it per EMG FR-Z2.
START TIME:
STOP TIME:
PAGE 1 of 6
JPM NO: 501-S S3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
Indication of 2003 ft 11 in is equal to the design basis LOCA level.
S U
- 2. Try to identify unexpected source of water to sump Comments:
- *Check Essential Compare A Train and Service Water - B Train ESW flow NOT LEAKING indicators, EF FI-53 and
- 54. Note that EF FI-53 is indicating significantly
- ESW Pump Discharge higher than EF FI-54.
Flow - NORMAL Compare A Train and ESW Pump Discharge B Train ESW pressure Pressure - NORMAL indicators, EF PI-01 and
- 02. Note that EF PI-01 is indicating significantly lower than EF PI-02.
Recognize conditions Perform RNO indicate a Leak on A ESW Train.
STEP 1
- CRITICAL STEP PAGE 2 of 6
JPM NO: 501-S S3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Identify from the mimic
- 3. *Close valves and stop on the MCB the ESW Comments:
pumps as necessary to If required: CRS flowpath and possible limit containment directs that A ESW leak location.
flooding. pump remain running to support other loads.
EF HV 45 and 49 are the Close EF HV-49 ESW From CTMT Close EF HV-45 Isolations. EF HV-31 and Check ESW flow and 33 are ESW To CTMT pressure indicators Isolations.
The preferred method Close EF HV-33 would be to close the outlets first (45,49) to
- Close EF HV-31 minimize effects from Check ESW flow and large water column pressure indicators separation. However due to leak location the critical task is to close EF HV-31.
Depress the close STEP 1 RNO pushbutton on the HIS and note green lite only illuminated.
When leak is isolated, ESW flow will decrease and pressure will increase back to the normal bands.
- CRITICAL STEP PAGE 3 of 6
JPM NO: 501-S S3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 4. Identify if any other The operator may or may N/A sources are leaking. not return to complete step 1 since the leak was Comments:
identified at the first substep.
- b. Check CCW Surge Tank Levels. Locate all indicators and determine normal values
- c. Check Reactor Makeup are indicated.
Storage Tank Level.
- d. Check Fire Protection Outer Containment Isolation - CLOSED.
Step 1 Continuation.
S U
- 5. Sample Containment Sumps Comments:
Recognize RHR is not Recognize RHR is not running in recirc mode running in recirc mode and the sumps cannot be and the sumps cannot be sampled.
sampled per the procedure note prior to step 2.
STEP 2
- CRITICAL STEP PAGE 4 of 6
JPM NO: 501-S S3 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 6. Notify Plant Engineering Notify the Control Room of sump level and Supervisor that the TSC Comments:
activity level and obtain needs to be contacted.
a recommended action. Control Room Supervisor acknowledges the report STEP 3 This completes this JPM RECORD STOP TIME ON PAGE 1.
- CRITICAL STEP PAGE 5 of 6
JPM NO: 501-S S3 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The crew is recovering from a reactor trip. An Orange Path exists for Critical Safety Function -Containment.
Initiating Cues: The Control Room Supervisor directs you to perform Steps of EMG FR-Z2, Response To Containment Flooding.
PAGE 6 of 6
Control Room C-1 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 601-C K/A NO: 055 EA1.07 COMPLETION TIME: 30 Minutes K/A RATING: 4.3/4.5 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: EMG C-0, Loss of All AC, Align Alternate Power to Safeguards Bus using OFN NB-030 DUTY: Station Blackout ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM X SIMULATOR/LAB PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED
REFERENCES:
TOOLS/EQUIPMENT: NONE PREPARER: DATE:
04/09/2004
JPM NO: 601-C C-1 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has experienced a complete loss of AC electrical power to the switchyard.
Emergency Diesel Generator B (NE02) is tagged out for maintenance and is currently disassembled. Bus NB01 experienced a bus lockout and Electrical Maintenance estimates it will take three hours to clear it.
Initiating Cues: System Operations has informed the Control Room that they have re-energized the Athens 69KV line. The Control Room Supervisor has directed you to go to OFN NB-30, Loss Of AC Emergency Bus NB01 (NB02), and perform the steps that will restore power to an NB Bus. The Site Watch is presently in the Switchyard.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide the Candidate with a current copy of OFN NB-030.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have performed the steps of the procedure necessary to energize NB02 from the Athens 69KV line.
START TIME:
STOP TIME:
PAGE 1 of 9
JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Check AC Buses - AT Check NB EI-1 and NB LEAST ONE EI-2 and determine both Comments:
ENERGIZED buses have zero voltage STEP 1 When candidate checks NOTE: Candidate may NB EI-1 and NB EI-2 decide from the Initial state that no voltage is conditions that neither indicated bus is energized.
S U If asked: EMG C-0 is in Note that NB01 is locked
- 2. *If entering this progress. out and go to Attachment Comments:
procedure from EMG B step B12 for NB02 C-0 then go to desired attachment STEP 1 RNO S U
- 3. Check NB02 bus Note Annunciator 21A, lockout relays - RESET Bus Lockout - CLEAR Comments:
Annunciator 21A not lit STEP B12
- CRITICAL STEP PAGE 2 of 9
JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 4. Check EDG NE02 - Note that NE02 is tagged RUNNING out in the initial Comments:
conditions and perform STEP B13 the RNO If required cue:
DNO tags are hung on the B EDG start button and output breaker.
S U
- 5. If SM/CRS directs that Should realize that this NB02 be energized from was directed in the initial Comments:
a source other than the conditions of this JPM.
diesel, then go to:
Candidate must recognize
- B16 for normal that NB02 is the only bus offsite power available and can be powered from its Or alternate source. Go to step B18
- B18 for alternate offsite power STEP B13 RNO If candidate proceeds to S U step B16, use the following: Comments:
Check Alarm 022A Annunciator 22A is clear. clear Recognize XNB02 cannot Check transformer be energized from Transformer XNB02 Normal Offsite power XNB02 energized by off and bus PA02 are de- and proceed to step B18.
site power energized.
Go to Step B18
- CRITICAL STEP PAGE 3 of 9
JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 6. *Verify alternate offsite Comments:
power supply -
AVAILABLE Check annunciator 19A
- Check annunciator 19A, XNB01 XFMR Annunciator 19A -
Lockout - CLEAR CLEAR
- Check XNB01 - Note that no power is ENERGIZED BY XNB01 is de-energized. currently supplied to OFFSITE POWER XNB01 and perform the RNO STEP B18 S U
- 7. *Perform the following Comments:
Transition to Attachment
- Energize XNB01 C using Attachment C STEP B18 RNO B.
S U
- 8. Verify Annunciator 12E - Check Annunciator 12E CLEAR Comments:
Annunciator 12E is STEP C1 CLEAR
- CRITICAL STEP PAGE 4 of 9
JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- 9. Verify Power Supply to Contact the Site Operator
- 4 Transformer Load and verify status Tap Changer - ON Circuits 13 and 15 As Site Watch report:
Circuits 13 and 15 are STEP C2 both in the ON position at #4 Transformer.
S U
- 10. Verify Power Supply to Contact the Site Operator
- 5 Transformer Load and verify status. Comments:
Tap Changer - ON Circuits 2 and 4 As Site Watch report:
Circuits 2 and 4 are STEP C3 both in the ON position at #5 Transformer.
S U
- 11. Ensure load tap changers Contact the Site Operator on #4 transformer - and verify status. Comments:
AUTO As Site Watch report:
Load Tap Changer for STEP C4 #4 Transformer is in AUTO
- CRITICAL STEP PAGE 5 of 9
JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 12. Ensure load tap Contact the Site Operator changers on #5 and verify status Comments:
transformer - AUTO As Site Watch report:
Load Tap Changer for STEP C5 #5 Transformer is in AUTO S U
- 13. Ensure breaker 13-8 is As Site Watch report: May Contact Site open and racked in Breaker 13-8 is open Operator and verify Comments:
and racked in status.
STEP C6 OR OR Green Lite is lit and Locate Breaker 13-8 on Red Lite is out. MCB mimic bus and verify Green Lite is Lit and Red Lite is out.
S U
- 14. Ensure Disconnect 13- As Site Watch report: May Contact Site 21 is closed Disconnect 13-21 Operator and verify status Comments:
indicates closed.
STEP C7 OR OR Locate disconnect 13-21 Red lite is lit for indication on MCB and disconnect indication. verifies red lite lit..
- CRITICAL STEP PAGE 6 of 9
JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U After candidate describes Place handswitch 13-48
- 15. *Place breaker 13-48 in proper operation cue: in Pull To Lock (PTL) by Comments:
PTL rotating the switch 13-48 Handswitch is in counterclockwise and STEP C8 the Pull To Lock pulling out on switch.
position. Green Lite is Handswitch will remain lit and Red Lite is out. in the PTL position with the Green Lite lit and the Red Lite out.
S U After candidate describes Locate Breaker 13-8 on
- 16. *Close breaker 13-8 proper operation cue: the MCB. Rotate 1HS- Comments:
SY0018 to the right and STEP C9 Breaker 13-8 indicates note the Green Lite goes closed. Red Lite is lit out and the Red Lite is lit.
and Green Lite is out.
Recognize the Attachment This completes is complete and return to Attachment C. step B18 RNO b. 2 S U Go to B19
- 17. *Perform the following Comments:
- If XNB01 can be energized then go to step B19 STEP B18 RNO b.2
- CRITICAL STEP PAGE 7 of 9
JPM NO: 601-C C-1 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 18. Check NB01 normal Locate Handswitch for supply breaker - OPEN. NB0112 on the MCB and Comments:
NB HIS-2 indicates check NB HIS-2 -OPEN STEP B19 green lite only S U
- 19. Reenergize NB02 from alternate offsite power Comments:
supply
- Place alternate sync NB HS-9 is in the ON *Rotate NB HS-9 to ON transfer switch to ON Position.
- Close NB02 alternate *Rotate NB HIS-5 to the supply breaker NB HIS-5 indicates right and note Green Lite closed goes out and Red Lite is lit
- Place alternate supply sync transfer Rotate NB HS-9 to OFF switch to OFF NB HS-9 is in the OFF (Not Critical)
Position.
- Check NB02 - Check NB EI-2 for ENERGIZED voltage OR Check white NB EI-2 indicates 4200 lite lit for power volts. available.
NB ZL-6 white lite lit.
Report to CRS that NB02 is energized Acknowledge report.
THE JPM IS STEP B20 COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 8 of 9
JPM NO: 601-C C-1 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant has experienced a complete loss of AC electrical power to the switchyard.
Emergency Diesel Generator B (NE02) is tagged out for maintenance and is currently disassembled. Bus NB01 experienced a bus lockout and Electrical Maintenance estimates it will take three hours to clear it.
Initiating Cues: System Operations has informed the Control Room that they have re-energized the Athens 69KV line. The Control Room Supervisor has directed you to go to OFN NB-30, Loss Of AC Emergency Bus NB01 (NB02), and perform the steps that will restore power to an NB Bus. The Site Watch is presently in the Switchyard.
PAGE 9 of 9
In Plant P-2 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 602-P K/A NO: 057 AA1.01 COMPLETION TIME: 20 Minutes K/A RATING: 3.7/3.7 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Align 120 vac Vital Bus to SOLA Xfmr DUTY: Loss of Vital AC Instrument Bus ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB PLANT X CLASSROOM METHOD OF PERFORMANCE: SIMULATED X PERFORMED
REFERENCES:
OFN NN-021 TOOLS/EQUIPMENT: NONE PREPARER: DATE: 2/24/04
JPM NO: 602-P P-2 Rev 0 Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 3 with all items for entering Mode 2 complete. Annunciator 25A, NN01 Bus UV and 25B, NN11 Inv UV, have gone into alarm. The Reactor Operator has verified from OFN NN-021, Loss of 120 VAC Instrument Bus, that Bus NN01 is de energized..
Initiating Cues: The Control Room Supervisor directs you to locally restore power to BUS NN01 using OFN NN-021, Step A4.
DO NOT OPERATE ANY COMPONENTS IN THE PLANT ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide the candidate with an information only copy of OFN NN-21, Attachment A.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have placed the NN01 Bus on the power supply from the SOLA Transformer.
START TIME:
STOP TIME:
PAGE 1 of 5
JPM NO: 602-P P-2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Locally Restore power to Bus NN01 Comments:
- Check NN Bus - NO APPARENT At NN01, 2016 level of DAMAGE the Control Building, check for indication physical damage No damage is evident and no odor of smoke or heat exists.
Look at inverter output
- *Check inverter voltmeter on NN11 NN11 output voltage
- NORMAL Meter indicates 0 voltage Realize that voltage is not normal and perform the RNO to go to Step A5 STEP A4
- CRITICAL STEP PAGE 2 of 5
JPM NO: 602-P P-2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- 2. Align Backup Power to Bus NN01
- *Close backup Breaker operator is Locate NG01ACR3, transformer XNN05 pointing to the closed 2000 level of Control power supply position Building, and rotate the breaker operator up to the closed postion.
White lite is illuminated
- Verify backup power available white light Look at white light on
- LIT NN11 Install the interlock key
- *Open normal Breaker operator is into the lock mechanism and turn. Move the feeder breaker pointing at the open position NN0101 breaker operator to the left until it indicates off.
Move the slide bar to the left and move NN0102
- *Close alternate Breaker operator is pointing at the closed breaker operator to the feeder breaker left until it indicates position closed STEP A5
- CRITICAL STEP PAGE 3 of 5
JPM NO: 602-P P-2 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE
- 3. Refer to applicable Acknowledge report. Call the Control Room Technical Specifications Balance of crew will and report NN01 is refer to Technical powered from the SOLA Specifications. transformer. Note that TS 3.8.7 and 3.8.8 must be referred to.
THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 4 of 5
JPM NO: 602-P P-2 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 3 with all items for entering Mode 2 complete. Annunciator 25A, NN01 Bus UV and 25B, NN11 Inv UV, have gone into alarm. The Reactor Operator has verified from OFN NN-021, Loss of 120 VAC Instrument Bus, that Bus NN01 is de energized..
Initiating Cues: The Control Room Supervisor directs you to locally restore power to BUS NN01 using OFN NN-021, Step A4.
DO NOT OPERATE ANY COMPONENTS IN THE PLANT PAGE 5 of 5
Simulator S6 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 701-S K/A NO: 015 A1.03 COMPLETION TIME: 20 Minutes K/A RATING: 3.7/3.7 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Rx Start Up, 10-8 amps to Point of Adding Heat DUTY: Nuclear Instrumentation System ASP The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
GEN 00-003, Hot Standby to Minimum Load TOOLS/EQUIPMENT: NONE PREPARER: DATE: 04/13/2004
JPM NO: 701-S S6 Rev 0 Simulator Setup IC 175 Run Insert malfunctions mNIS03A, C, and D. Set value to 0 Ensure that GDSU & BB01 are displayed on NPIS.
Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The crew is performing a reactor startup per GEN-003 with the core at Middle of Life (MOL). The reactor is critical at 10-8 AMPS, and the crew is holding at step 6.29 of GEN 00-003. A Reactivity Brief was completed as part of the shift turnover.
Initiating Cues: The Control Room Supervisor directs you to perform the steps necessary to increase reactor power at a rate of .5 to .8 DPM to the point of adding heat (POAH) and stabilize reactor power at 0.5% to 1.0%. Do not exceed a transient SUR of 1.5 DPM or a steady state SUR of 1.0 DPM.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide an information only copy of step 6.29 of GEN 00-003, Hot Standby To Minimum Load, to the Candidate.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have stabilized power at less than 5.0%
and reported the NI failure to the CRS.
START TIME:
STOP TIME:
PAGE 1 of 3
JPM NO: 701-S S-6 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Increase reactor power Ensures Tavg is within the band. Comments:
- Ensure Steam dump valves are adjusted OPTIONAL: Candidate to maintain Tavg may verify the pot on AB between 552°F and PK-507 is set between 562°F 7.1 and 7.3 turns. S/G ARVs not required.
- Adjust control rod *Pull control rods per Exceeding 1.0 DPM steady state SUR or 1.5 height, as necessary, CRS instructions until a transient would fail the to establish desired steady startup rate of 0.5 critical task.
startup rate from 0.5 to < 1.0 DPM steady state to 0.8 DPM is achieved on SE NI 35D and 36D.
Monitor IR indications to observe for overlap into the power range.
S U
- 2. Monitor Power Range Candidate may report rod NIs to stabilize power at positions and SUR to Comments:
0.5 to 1.0%. CRS. Acknowledge reports.
- *Determine that 3 of the 4 NIs are not Notes that NI 41, 43 and indicating properly. 44 are still indicating zero as NI-42 begins increasing form 0.0 to 1.0%
- CRITICAL STEP PAGE 2 of 3
JPM NO: 701-S S-6 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 3. *Check Diverse *At least two of the five Comments:
Indications for entry into diverse indications the power range. should be checked.
- RCS Tavg increasing
- Steam Dumps Opening farther
- S/G Level decreasing
- Start Up Feed Pump flow increasing.
- Loop Delta Ts show increasing power.
S U
- 4. *Insert Control Rods *Stabilize reactor Comments:
and stabilize Reactor power in the power range Power in the power prior to exceeding 5.0%
range. as indicated on NI-42, which would constitute a Mode Change.
S U
- 5. Inform CRS of NI NOTE: JPM is complete Inform CRS failures and status of when power is stabilized. Comments:
reactor power.
Acknowledge report.
THE JPM IS COMPLETE STEP 6.28 RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 3 of 3
JPM NO: 701-S S-6 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The crew is performing a reactor startup per GEN-003 with the core at Middle of Life (MOL). The reactor is critical at 10-8 AMPS, and the crew is holding at step 6.29 of GEN 00-003. A Reactivity Brief was completed as part of the shift turnover.
Initiating Cues: The Control Room Supervisor directs you to perform the steps necessary to increase reactor power at a rate of 0.5 to 0.8 DPM to the point of adding heat (POAH) and stabilize reactor power at 0.5% to 1.0%. Do not exceed a transient SUR of 1.5 DPM or a steady state SUR of 1.0 DPM.
PAGE 3 of 3
Simulator S5 WOLF CREEK JOB PERFORMANCE MEASURE JPM NO: 801-S K/A NO: 008 A4.01 COMPLETION TIME: 25 minutes K/A RATING: 3.3/3.1 JOB TITLE: RO/SRO REVISION: 0 TASK TITLE: Swap CCW Trains DUTY: Component Cooling Water The performance of this task was evaluated against the standards contained in this JPM and determined to be:
[ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY:
EVALUATORS SIGNATURE: DATE:
TASK PERFORMER:
LOCATION OF PERFORMANCE:
CONTROL ROOM SIMULATOR/LAB X PLANT CLASSROOM METHOD OF PERFORMANCE: SIMULATED PERFORMED X
REFERENCES:
SYS EG-201, Transferring Supply Of CCW Service Loop And CCW Train Shutdown TOOLS/EQUIPMENT: NONE PREPARER: DATE: 3/09/04
JPM NO: 801-S S5 Rev 0 Simulator Setup IC 175 (low power IC)
Ensure the NCP is in service Run Read to Performer:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 1. The CCW Service Loop is on the B Train. Maintenance is pending on the B Train CCW Heat Exchanger.
Initiating Cues: The Control Room Supervisor directs you to shift the CCW Service Loop to A Train and secure the B Train pump. The Auxiliary Building Operator is performing the Section 6.2 of SYS EG-201. A reactivity briefing has been performed for the completion of this procedure. The Spent Fuel Pool Cooling was already transferred by the crew.
ASK IF THE OPERATOR UNDERSTANDS THE INITIATING CUES.
Notes: Provide an information only copy of SYS EG-201 to the Candidate.
THE EVALUATOR OR EXAM GROUP SHALL VERIFY THAT THE PROCEDURE REVISION FOR THIS JPM IS CURRENT AND THAT ANY CHANGE AGAINST THE REFERENCED PROCEDURE DOES NOT INVALIDATE THIS JPM. . (PIR 2003-2930)
Task Standard: Upon completion of this JPM, the Candidate will have transferred the CCW Service Loop to A Train with the A CCW Pump running and all B Train Pumps secured.
START TIME:
STOP TIME:
PAGE 1 of 9
JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 1. Start desired Train A CCW Pump Comments:
- Turn off the motor space heater supply Contact the local operator breaker. and direct that breaker PG19NJF118 be turned off Local Operator will acknowledge request and call back immediately and state the breaker has been turned off
- *Start desired CCW Pump Actuate EG HIS-21 to the right. Note that the red lite only is illuminated.
- Verify operating Contact local operator to CCW Pump monitor EG FI-95 or use discharge flow is computer point EGF0095.
greater than 1.5 E6 Note that flow is LBM/HR adequate.
If local operator is contacted they will report that flow is 1.6
- If operating CCW E6 LBM/HR. Determine that this step is Pump discharge flow NA is less than 1.5 E6 LBM/HR then refer to step 4.4 STEP6.1.1
- CRITICAL STEP PAGE 2 of 9
JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 2. Locally verify CCW Contact local operator Train A Pump Room Comments:
Cooler running.
STEP 6.1.2 When called, the local opeator will report the cooler is running.
S U
- 3. If CCW Pump A was started, then verify Comments:
proper room cooler damper alignment:
- GL-D156 - OPEN Contact local operator and ask them to verify that GL-D156 is open
- GL-D157 - CLOSED Contact local operator and ask them to verify that GL-D157 is closed When called, the local STEP 6.1.3 operator will report GL-D156 open and GL-D157 is closed.
- CRITICAL STEP PAGE 3 of 9
JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 4. If CCW Pump C was Realize that the step is started, then verity NA Comments:
proper room cooler damper alignment STEP 6.1.4 S U Depress the open
- 5. *If RHR Train B is not pushbutton on EC HIS-12 Comments:
in service, then ensure and note red lite only is SFP HX B CCW Outlet illuminated.
Vlv is open to provide a flow path for CCW Train B STEP 6.1.5 S U
- 6. *Close CCW Surge Comments:
Tank A and B Vent Valves Depress the close
- EG HIS-9 pushbutton on EG HIS-9 and note green lite only is illuminated.
- EG HIS-10 Depress the close pushbutton on EG HIS-10 and note green lite only is illuminated STEP 6.1.6
- CRITICAL STEP PAGE 4 of 9
JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U Actuate the EG HS-15
- 7. *Open CCW Train A open pushbutton and note Comments:
Supply/Return Valves red lites only illuminted for the Train A Supply If candidate mentions and Return Valves.
reactivity briefing is STEP 6.1.7 required, cue them the briefing was already conducted.
Thermal Barriers will isolate at his point.
When candidate announces the alarms, the Control Room Supervisor will acknowledge the report.
S U Actuate the EG HS-16
- 8. *Close CCW Train B close pushbutton and note Comments:
Supply/Return Valves green lite only on the Train B Supply and STEP 6.1.8 Return Valves.
- CRITICAL STEP PAGE 5 of 9
JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
LBM/HR and <4.3 E6 STEP 6.1.9 LBM/H
- 10. *Open CCW Surge Tank A and B Vent Valves Actuate the EG HIS-9
- EG HIS-9 open pushbutton and note red lite only is illuminated.
- EG HIS-10 Actuate the EG HIS-10 open pushbutton and note STEP 6.1.10 red lite only is illuminated.
- CRITICAL STEP PAGE 6 of 9
JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 11. *Ensure CCW from Comments:
RCP Thermal Barriers are open Actuate BB HIS-13 open
- BB HIS OPEN pushbutton and note red lite only is illuminated Actuate BB HIS-14 open
- BB HIS OPEN pushbutton and note red lite only is illuminated Actuate BB HIS-15 open
- BB HIS OPEN pushbutton and note red lite only is illuminated Actuate BB HIS-16 open
- BB HIS OPEN pushbutton and note red lite only is illuminated STEP 6.1.11 S U
- 12. Section 6.1 complete Announce that section 6.1 is complete and move on Comments:
to section 6.3 to secure B Train.
- CRITICAL STEP PAGE 7 of 9
JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 13. Ensure all train B ECCS Note the handswitch and pumps stopped discharge pressure Comments:
indication for CCP B, STEP 6.3.1 RHR Pump B, and SI Pumpt B all green lite only illuminated with no discharge pressure indicated.
S U
- 14. Align Spent Fuel Pool Announce intention to Cooling Train A for perform SYS EC-120. Comments:
operation using SYS EC- Will be performed by 120 spare RO.
STEP 6.3.2 S U
- 15. Stop the running train B Actuate EG HIS-22 to the CCW Pump left and note green lite Comments:
only illuminated STEP 6.3.3
- CRITICAL STEP PAGE 8 of 9
JPM NO: 801-S S5 Rev 0 TASK NUMBER - ELEMENT CUE STANDARD SCORE S U
- 15. Ensure the motor space Contact the local operator heater breaker for both and direct that breakers Comments:
CCW Pumps are turned PG20GBR240 and on. PG20GBR241 be closed The local operator will STEP 6.3.4 acknowledge the request and report the breakers are closed.
S U
- 16. Section 6.3 complete Announce that Section 6.3 is complete. Comments:
STEP 6.3.5 Acknowledge the report THE JPM IS COMPLETE RECORD STOP TIME ON PAGE 1
- CRITICAL STEP PAGE 9 of 9
JPM NO: 801-S S5 Rev 0 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating and subsequent cues. You may use any approved reference materials normally available to you. Make all written reports, oral reports, and log entries as if the evolution was actually being performed. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions: The Plant is in Mode 1. The CCW Service Loop is on the B Train. Maintenance is pending on the B Train CCW Heat Exchanger.
Initiating Cues: The Control Room Supervisor directs you to shift the CCW Service Loop to A Train and secure the B Train pump. The Auxiliary Building Operator is performing the Section 6.2 of SYS EG-201. A reactivity briefing has been performed for the completion of this procedure. The Spent Fuel Pool Cooling was already transferred by the crew.
PAGE 9 of 9
INITIAL LICENSE EXAM OPERATING TEST # 1 SCENARIO # 1 Revision 03 Week of May 10, 2004
OP-TEST #1 SCENARIO #1 Page 2 of 2 Facility: Wolf Creek NRC Scenario No.: 1 Op-Test No.: 1 Revision 03 Source:
New X Bank - Significantly Modified Bank - Initial Condition Change See page 3 for Examiner/student assignments Initial Conditions: 100% Power, MOL, A MDAFWP is OOS for bearing replacement.
A Safety Injection Pump is OOS for oil change.
Severe Thunderstorm Watch for Coffey County.
Turnover: Maintain current plant conditions.
Event Malf. Event Event No. No. Type* Description 1 mMSS1 I (BOP) Steam Header Pressure Channel fails low. (Affects both MFPs)
T+1 3 2 mPRS0 C (RO) Pzr Spray Valve fails full open in Automatic.
T+11 3A 3 mEPS C (ALL) Vital 4160volt NB02 bus lockout T+18 06B 4 N (BOP)
N/A Tech Spec Required Shutdown due to loss of two AFW pumps.
T+38 R (RO) 5 mFWM M (ALL) Main Feed Line break in Turbine Building T+48 20 6 mAFW0 C (BOP) TDAFW pump fails. Entry to FR-H1.
T+54 2B IOR 7
P01055 C (RO) A CCP fails to Auto Start on Safety Injection.
T+60 B
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
OP-TEST #1 SCENARIO #1 Page 3 of 3 Scenario # 1 Crew Assignments Session 1 Examiners Applicants CRS: Surrogate E1: Steka RO: SRO-I1, Blow E2: McKernon BOP: RO3, Askins Session 2 Examiners Applicants CRS: Surrogate E3: Gage RO: RO4, Link BOP: Surrogate Session 3 Examiners Applicants CRS: Surrogate E3: Gage RO: SRO-I2, Ryan E2: McKernon BOP: RO5, Winn Session 4 Examiners Applicants CRS: Surrogate E3: Gage RO: RO2, Gholson E1: Stetka BOP: RO1, Keating
OP-TEST #1 SCENARIO #1 Page 4 of 4 SCENARIO MISCELLANEOUS INFORMATION SCENARIO OBJECTIVE:
The objective for this scenario is to mitigate a Loss of Heat Sink event by initiating feed and bleed using plant procedures. Initial conditions have one Aux Feedwater (AFW) pump and one Safety Injection (SI) pump out of service for maintenance. The scenario contains a steam header pressure instrument failure and failure of the controller for one PZR spray valve. All will require operator action to prevent a reactor trip. These are followed by a loss of one vital 4160 volt AC bus. The crew must start the alternate train cooling systems to prevent a loss of the reactor coolant pumps (RCP).
The SRO will evaluate technical specifications associated with the vital AC bus loss. For the vital AC bus loss, numerous tech specs are involved, however the SRO must realize the limiting specifications is for AFW, since two pumps are now inoperable, requiring the unit to be in Mode 3 within six hours. The crew will be cued to commence a 1% per minute downpower The major event is a feed line break in the turbine building and a subsequent loss of the Turbine Driven AFW pump. This places the crew in a red path, Loss of Heat Sink, functional recovery procedure. The crew will meet requirements to initiate bleed and feed to the reactor coolant system (RCS). The crew must realize that the only available high head injection pump did not autostart and manually start it to establish a feed path to the RCS. The scenario terminates when the crew has completed the bleed and feed portion of the functional recovery procedure.
The following is the expected major procedure flow path:
- OFN SB-008, INSTRUMENT MALFUNCTIONS
- OFN NB-030, LOSS OF AC EMRGENCY BUS NB01 (NB02)
- OFN MA-038, RAPID PLANT SHUTDOWN
- EMG E-0, REACTOR TRIP OR SAFETY INJECTION
- EMG ES-02, REACTOR TRIP RESPONSE
- EMG FR-H1, LOSS OF HEAT SINK CRITICAL PARAMETERS:
The following parameters may be of value in evaluating crew performance when the scenario is completed:
- Vital AC bus failure:
RCP bearing and motor temperatures.
- Loss of Heat Sink S/G Wide Range Levels RCS pressure Hot Leg/Incore Temperatures High head injection flow (BIT)
PZR PORV and block valve status.
OP-TEST #1 SCENARIO #1 Page 5 of 5 OPERATOR ACTIONS TABLE NOTES:
- 1. Critical Tasks are indicated by a bolded "C" in the position column and in bold type in the actions column.
- 2. Actions required throughout the event are indicated as "(continuous)" in the position column.
- 3. Shaded cells indicate procedural entry points.
OP-TEST #1 SCENARIO #1 Page 6 of 6 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 1 Event
Description:
Steam Header Pressure Channel fails low. (Affects both MFPs)
Time Position Applicant's Actions or Behavior Notes Notes and communicates that level is BOP decreasing in all four S/Gs.
Master Speed Controller must Communicate and takes manual control of be placed in manual and SG CRS/BOP the Master MFP Speed controller. levels stabilized in time to prevent a Rx Trip.
Identify Steam Header Pressure channel RO/BOP 507 has failed low.
Enter and direct OFN SB-008, Instrument CRS Malfunctions, Attachment B.
Verify Steam Header Pressure channel malfunction.
RO/BOP Check Steam Dump select switch NOT in Steam Pressure Mode.
Manually control MFP speed.
At 100% power Main Feed Establish dP IAW Figure 1.
BOP header pressure should read (Operator may match steam and feed flows, (Continuous) ~165 psi higher than S/G then adjust MFP speed to maintain FRVs pressure.
positioned at ~ 80%.)
Place Steam Header Pressure Controller in BOP manual.
Contact WWM to request I&C repair failed CRS channel.
MFP speed controller in manual, all S/G Termination Criteria: levels stable or trending to program level (50%).
OP-TEST #1 SCENARIO #1 Page 7 of 7 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 2 Event
Description:
PZR Spray Valve A fails full open in Automatic.
Time Position Applicant's Actions or Behavior Notes RO/BOP/ Note and Communicate that RCS pressure CRS is decreasing.
Monitor RCS pressure for entry into DNB RO/BOP/
Tech. Spec. at < 2220 psig. T.S. 3.4.1, two hours to restore.
CRS As RCS pressure decreases to < 2220, the CRS/RO crew may energize 2nd set of PZR back-up heaters.
Note and communicate A Spray valve is A spray controller must be failing open.
RO placed in Manual and closed in Place A spray controller in Manual and time to prevent a Rx Trip.
close A spray valve.
Enter and direct OFN SB-008, Instrument CRS Malfunctions, Attachment V.
Verify A Spray Valve controller failed RO open in auto and is now in manual/closed.
Contact WWM to request I&C repair failed CRS channel.
A Spray Valve Controller in Termination Criteria: manual/closed. RCS pressure stable at or trending to program (2235).
OP-TEST #1 SCENARIO #1 Page 8 of 8 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 3 Event
Description:
Vital 4160 volt NB02 bus lockout.
Time Position Applicant's Actions or Behavior Notes Acknowledge and communicates RO/CRS annuniciators for NB02 Bus Lock Out (21A)
Crew may enter OFN NB-030 CRS Direct Actions for ALR 00-021A directly.
Ensures all NB02 supply breakers open.
NB0209 RO/BOP NB0211 NB0212 Align CCW to Red Train:
Start one CCW pump (A or C)
RO/BOP Open Red Train to Service Loop Valves CCW is required to prevent (C) (EG HIS-15) damage to RCPs.
Dispatch operator to locally close Yellow Train to Service Loop (EG HV-16/54).
Dispatch operator to locally shutdown RO/BOP B EDG.
Review and comply with Tech. Specs. The Limiting T.S. action is from T.S. 3.8.1 AC Sources. T.S. 3.7.5, condition C, the CRS CRS T.S. 3.8.9 Distribution Systems. must recognize that two trains T.S. 3.7.8 ESW (per 3.8.1) of AFW are inoperable, T.S. 3.7.5 AFW requiring Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Enter and direct OFN NB-030, Loss of AC CRS Emergency Bus. Attachment B.
Check Rx power < 100%
RO Close FW Heaters Bypass valve, AE HV-38.
OP-TEST #1 SCENARIO #1 Page 9 of 9 OPERATOR ACTIONS Event 3 Continued Check Yellow Train AC Emergency Bus RO De-energized.
Verify CCW Service Loop Aligned to Red Train.
- Start A or C CCW pump.
May have been performed in BOP
- Open Red Train Supply/Return the ALR.
Valves. EG HS-15
- Dispatch Operator to locally close Yellow Train Supply/Return valves.
BOP Check RCP Thermal Barrier L/U Normal BOP Verify Instrument Air from Red Train.
RO/BOP Check RCP Cooling Normal.
Ensure RCP Seal Injection to each RCP RO between 8-13 gpm.
Establish ESW to Red Train
- Start A ESW Pump
CRS - NOT needed for Heat Sink BOP - Close or throttle all TDAFW flow CRS/BOP control valves.
(Crew may decide to leave open/throttled for minimum flow concerns.)
RO/BOP Start Red Train SFP cooling pump.
At panel RP068 (in back), Start Red Train BOP CR AC unit. GK HIS-29.
Determine Bus Lockout is not clear and this CRS is a hold point in procedure at step B12.
Termination Criteria: Red Train ESW and CCW are in service.
OP-TEST #1 SCENARIO #1 Page 10 of 10 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 4 Event
Description:
Tech Spec Required Shutdown (Cue provided from Shift Manager to reduce power at 1% per minute.)
Time Position Applicant's Actions or Behavior Notes Enter and direct actions of OFN MA-038. Crew should commence 10%
Conduct Reactivity Brief with board downpower from pre-shift brief CRS operators. Pre-Shift brief for reduction to then determine remaining 90%. actions.
RO Calculate Boration required. 155 gallons at 15.4 gpm.
Establish 1% per minute power decrease on the Load Set potentiometer.
- Press Decrease Load till Load Limit light is out.
- Select 1%/Minute on Loading Rate.
(Continuous)
- Select Decrease Loading Rate -
ON.
- Decrease Load Set, maintain within 200 MW of actual load.
- Use rods to maintain Tavg/Tref error between 0 and +5 RO
- Energize both PZR B/U heaters.
(Continuous)
- Borate and adjust rods as necessary to maintain rods above RIL.
- Check PZR PORVs / Block Valves RO/BOP
- Check PZR Pressure
- Check PZR Level BOP Control S/G levels to maintain 45-55%.
(Continuous)
May have been performed in BOP Check AE HV-038 - Closed OFN NB-030.
Check Reactor Power < 60%. Recognize CRS hold point in procedure.
Power Reduction in Progress. Rods have Termination Criteria:
automatically stepped in.
OP-TEST #1 SCENARIO #1 Page 11 of 11 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 5 Event
Description:
Main Feed Line break in Turbine Building.
Time Position Applicant's Actions or Behavior Notes Note and communicate level decreasing in BOP all four S/Gs.
BOP Acknowledge and communicate alarms RO/BOP Note S/G Levels are approaching Rx Trip CRS setpoint.
Direct a Rx Trip or respond to a Rx Trip CRS and enter EMG E-0.
Verify Rx Trip
- Rod Bottom Lights Lit.
- Rx Trip and Bypass Bkrs open.
- Neutron Flux decreasing (Intermediate Range & Gamma metrics)
- Transfer NR-45 recorder to Intermediate Range Verify Vital AC Power
- NB01 normal voltage / off site power.
- Determine SI is NOT actuated.
Verify Turbine Trip
- Main Stop valves all closed.
- Generator and exciter bkrs open.
Verify SI NOT required
- All S/G Press > 615 psig RO
- Ctmt Press < 3.5 psig
- RCS Subcooling > 30 degrees
- PZR Level > 6%
OP-TEST #1 SCENARIO #1 Page 12 of 12 OPERATOR ACTIONS Event 5 (Continued)
CRS Ensure Immediate Actions complete.
Identify any immediate concerns.
Management Expectation is to NOT perform any other actions Secure all Condensate Pumps and Heater till the immediate actions are CRS/BOP Drain Pumps after Immediate actions are complete. With a feed break in complete. the Turbine Building it is expected to secure running secondary pumps.
CRS/RO Using procedure verify Immediate Actions BOP of EMG E-0 complete Direct Operator to Monitor CSFSTs and CRS Transition to EMG ES-02 from Step 4 RNO.
EMG E-0 Immediate Actions completed, Termination Criteria:
transition is made to EMG ES-02.
OP-TEST #1 SCENARIO #1 Page 13 of 13 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 1 Event No.: 6 and 7 Event
Description:
Loss of Heat Sink, failure of high head Injection.
Time Position Applicant's Actions or Behavior Notes Crew may enter EMG FR-H1 Conduct Transition Brief for entry to EMG CRS directly based on timing of ES-02.
report of red path.
RO Perform EMG F-0 for CSFST CRS/RO Monitor CSFST on NPIS computer screen BOP after 1st verification with the procedure.
(Continuous)
Note that AFW flow is zero to all S/Gs.
- Note and report that zero flow is indicated to all S/Gs.
After transition to FR-H1 the Recognize that entry conditions are met for crew will be watching for Fold CRS RED path on EMG FR-H1, Loss of Heat Out Page Criteria to go to the Sink. Transition to EMG FR-H1.
steps for Feed and Bleed.
Try to establish AFW Flow. If Fold Out page is met the CRS Determine from Building reports that No crew will go directly to step 27 AFW pump is available. and initiate bleed and feed.
BOP Close all AFW valves Reduce heat input to RCS.
RO/BOP Stop all RCPs Turn off all PZR heaters (3)
Establish S/G pressure control.
BOP IF MSIVs are open, align Steam Dumps.
IF MSIVs are closed, then use ARVs.
OP-TEST #1 SCENARIO #1 Page 14 of 14 OPERATOR ACTIONS Event 6/7 (Continued)
Verify Condensate/Feedwater systems available.
CRS Based on Building reports, determine the Main Feedwater header is unavailable.
Recognize to use the RNO and this places the crew in a loop from step 1 to step 7.
Conduct Quick Brief with crew.
CRS In a procedure loop till the Fold Out Page is met or meet a step criteria.
Monitor S/G WR levels. As level reaches Perform Step for Bleed and Crew 26% proceed to step 27 and initiate bleed Feed.
and feed.
RO/BOP Stop all RCPs May have already performed.
Turn off all PZR heaters RO Actuate Safety Injection Manually start A CCP.
RO Ensures Feed Path Established Checks BIT flow indicated on EM FI-(C) 917A.
ARM both Cold Overpressue Protection RO/BOP circuits. Ensures Bleed Path (C) Ensure Both Block Valves open. Established Open both PZR PORVs.
RO/BOP Verifies BOTH Block valves and BOTH PORVs are open.
Scenario may be terminated Bleed and Feed established per steps 27-Termination Criteria: anytime after bleed and feed 31 of EMG FR-H1.
has been established .
OP-TEST #1 SCENARIO #1 Page 15 of 15 CRITICAL TASK
SUMMARY
POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/
UNSAT Utilizing guidance in the ALR or OFN, CCW established to RCPs prior start a CW pump in the unaffected train RO/BOP to high temperatures meeting and transfer the service loop to the immediate RCP trip criteria.
running train.
Initiate SI and manually start A Bleed and Feed must be Centrifugal Charging Pump to ensure a RO/BOP established prior to S/G dry out.
Feed path, ensure PORVs/Block (3 S/Gs < 8% WR) valves open for a Bleed path.
OP-TEST #1 SCENARIO #1 Page 16 of 16 Booth Instructions Ensure batch file has been loaded into X:\Opensim\Batch folder in the Instructor Station Computer.
Initialize in IC 171 and go to RUN.
On the Expert screen load batch file: a2004SCN01.txt. After file loads FREEZE the simulator.
Hang DNO tags on the following:
Perform Simulator Ready checklist.
OP-TEST #1 SCENARIO #1 Page 17 of 17 BOOTH COMMUNICATIONS AND ACTIONS Unless otherwise directed, all events will be entered when cued from the floor.
When cued from the floor or when crew assumes the watch go to RUN.
WHEN cued from the floor, enter EVENT 1.
When CRS contacts I&C or the Work Week Manager for Steam Header pressure instrument, respond:
I will assemble a team.
WHEN cued from the floor, enter EVENT 2.
When CRS contacts I&C or the Work Week Manager for PZR Spray Valve Failure, respond:
I will assemble a team.
WHEN cued from the floor, enter EVENT 3.
When Aux watch is contacted to isolate B Train CCW, enter EVENT 8.
When Turbine watch is contacted to shutdown B diesel, enter EVENT 9.
When CRS contacts Shift Manager or Call Superintendent, acknowledge communications and respond: Well get back with you.
Wait approximately one minute then call back as Shift Manage and state: Ive talked with the Plant Manager and Vice President. Weather predictions indicate severe storms are heading towards the site. The decision has been made to commence a rapid shutdown at 1% per minute to put the plant in a safer condition.
When cued from the floor, enter EVENT 5.
After the reactor trip, page the Control Room as Turbine Building Watch and state: I saw large amounts of steam and water at the south end of the Turbine Building and have evacuated the building.
During the Main Feed Line Break and EMG FR-H1 the following communications MAY be required:
If asked about break location respond: It appears to be in the main header area above the MFRVs. It does not appear safe to enter the\area.
If asked to investigate TDAFW pump, respond: There is still steam and hot water all around on the 2000 elevation, I will try to make it into the room as it clears.
When directed from the floor, FREEZE the simulator. DO NOT RESET till allowed by the NRC Chief
OP-TEST #1 SCENARIO #1 Page 18 of 18 Examiner.
Batch File:
> BAT a2004SCN01.TXT
>TAGOUT 'A' AFW PUMP MOTOR IRF NALP01A 1 IRF NALP01AX 1 IRF RALH31 1 IRF RALH35 1
>Tag Out "A" SI Pump IRF NEMP01A 1
> AB PT-507 fails low IMF mMSS13 (1) 0 20
> A PZR Sray valve fails full open in Auto IMF mPRS03A (2) 100 30
>Bus Lockout on NB02 IMF mEPS06B (3)
> Main Feed Line break in Turb Bldg IMF mFWM20 (5) 1e+7 45
> Trip of TDAFWP tied to Rx Trip TRGSET 6 "JPPLP4" IMF mAFW02B (6 180)
> A CCP Fails to auto start on SI IOR P01055B 0
> Close EG HV16/54 CCW B to Service Loop TRGSET 8 TRG 8 "SET regh16=0"
> Local Shutdown of B EDG TRGSET 9 IRF RDGS02 (9 5) 0 IRF RDGS10 (9 8) 0 IRF RDGS19 (9 15) 1
>End of File
OP-TEST #1 SCENARIO #1 Page 19 of 19 SHIFT BRIEFING INFORMATION THIS FORM IS FOR TRAINING PURPOSES ONLY CONTROL ROOM TURNOVER CHECKLIST DATE : May 12, 2004 NIGHT SHIFT X DAY SHIFT MODE- 1 OFF-GOING: (PRINT) CRS ON-COMING: (PRINT) CRS RO RO BOP BOP SE SE ON-COMING CRS/SE/RO/BOP REVIEW EVOLUTIONS IN PROGRESS:
A Train Work Week Severe Thunderstorm Watch in effect for next four hours.
Maintenance is trying to complete all work due to weather.
MAINTENANCE IN PROGRESS:
A MD AFW Pump for bearing replacement.
A SI pump, jump up for oil change.
TESTING IN PROGRESS: NONE SIGNIFICANT LCOs IN EFFECT:
3.7.5 AFW, Condition B, 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> to restore.
3.5.2 ECCS, Condition A, 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> to restore.
REACTOR POWER 100 % RCS: 586.5 °F 2235 PSIG ROD CONTROL AUTO X MANUAL CONTROL BANK D 229 STEPS RCS BORON (Cb) 1028 PPM @ DATE/TIME Today/0400 LEAK RATE IDENTIFIED .02 UNIDENTIFIED .001 @ DATE/TIME Today/
(GPM): 0400 COND. AIR INLEAKAGE 13.8 scfm (IAW STN CH-020)
ESF STATUS PANELS AND REACTOR TRIP/BLOCK PANEL PANEL COMPONENT/TRIP/BLOCK REASON SA066X SI A SI and A MDAFW SA066X AFAS A MDAFW TRAINING ONLY ALARM WINDOW DESCRIPTION WINDOW NAME REASON WR/WO 018F NB01 BKR NOT A MDAFW pump 04-2083 OPEARBLE A SI pump 04-2650
OP-TEST #1 SCENARIO #1 Page 20 of 20
INITIAL LICENSE EXAM OPERATING TEST #1 SCENARIO # 2 Revision 03 Week of May 10, 2004
OP-TEST # 1SCENARIO #2 Page 2 of 2 Facility: Wolf Creek NRC Scenario No.: 2 Op-Test No.: 1 Revision 03 Source:
New Bank - Significantly Modified X Bank - Initial Condition Change See page 3 for Examiner/student assignments Initial Conditions: 100% Power, MOL, Normal Charging Pump is OOS for bearing replacement.
Turnover: Maintain current plant conditions.
Event Malf. Event Event No. No. Type* Description 1 mPRS0 I (RO) PZR Pressure Channel Fails High T+1 1C 2 mMSS0 C C S/G ARV fails open in auto, manual available.
T+17 7C (BOP) 3 mFWM C B S/G MFRV fails closed in auto, manual available.
T+26 03B (BOP) 4 mNIS I (RO) Nuclear Instrumentation Channel NI-43 fails high.
T+34 03C 5 mRCS0 M SSE/OBE escalates to Loss of Offsite Power, LBLOCA.
T+45 6A (ALL) 6 mDGS0 C (RO) Both EDGs fail to Auto Start.
T+49 2A/B 7 rBN881 C (RO) A Train RWST suction to RHR fails to align during EMG ES-12, T+70 2A Transfer to Cold Leg Recirc
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
OP-TEST # 1SCENARIO #2 Page 3 of 3 Scenario # 1 Crew Assignments Session 1 Examiners Applicants E1: Stetka CRS: SRO-I1, Blow E2: McKernon RO: RO3, Askins E3: Gage BOP: RO4, Link Session 2 Examiners Applicants E3: Gage CRS: SRO-I2, Ryan E2: McKernon RO: RO5, Winn BOP: Surrogate Session 3 Examiners Applicants E2: McKernon CRS: SRO-U, Camp E3: Gage RO: RO1, Keating E1: Stetka BOP: RO2, Gholson
OP-TEST # 1SCENARIO #2 Page 4 of 4 SCENARIO MISCELLANEOUS INFORMATION SCENARIO OBJECTIVE:
The objective of this scenario is to mitigate a large break LOCA with a failure in the automatic switchover of the Residual Heat Removal (RHR) pump suction to the containment sumps. Initial conditions have the Normal Charging Pump (NCP) out of service as distractor. The NCP has no affect on the scenario. The scenario contains a PZR pressure channel failure, failure of automatic control of a Main Feed Regulating Valve, and a Nuclear Instrument failure, all requiring operator action to prevent a reactor trip. The scenario also contains a failure of a S/G Atmospheric Relief Valve (ARV) as a board awareness issue affecting reactor power.
The SRO will evaluate Technical Specifications for the PZR pressure channel and the Nuclear Instrument failure. The S/G ARV should also be reviewed, however the valve is not inoperable.
The main event is an escalating earthquake. The first part of the event exceeds the Operational Based Earthquake (OBE) causing a small break LOCA. The crew will enter the off normal procedures and the second part of the event then exceeds the Safe Shutdown Earthquake (SSE) resulting in a large break LOCA causing an automatic reactor trip, safety injection actuation and a loss of offsite power.
Post trip failures include both emergency diesels do not auto start and a failure during the automatic switchover of the RHR suction valves. The operator must start both diesels to not enter the loss of all AC contingency procedure. The switchover failure has the Refueling Water Storage Tank (RWST) suction valve to A train RHR fails to close. This is the worse case condition as described in the Wolf Creek Updated Safety Analysis Report (USAR). This results in an open path from the RWST to Containment. The required actions are to secure the A train pump and close the containment suction valve. The operators must realize the remaining train can meet all needs of the accident in progress.
The following is the expected major procedure flow path:
- OFN SB-008, INSTRUMENT MALFUNCTIONS
- Possibly OFN SG-003, NATURAL EVENTS
- OFN BB-007, RCS LEAKAGE
- EMG E-0, REACTOR TRIP OR SAFETY INJECTION
- EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT
- EMG FR-P1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK
- EMG ES-12, TRANSFER TO COLD LEG RECIRCULATION CRITICAL PARAMETERS:
The following parameters may be of value in evaluating crew performance when the scenario is completed:
- RCS Pressure and Temperatures
- RWST Level
OP-TEST # 1SCENARIO #2 Page 5 of 5 OPERATOR ACTIONS TABLE NOTES:
- 1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.
- 2. Actions required throughout the event are indicated as "(continuous)" in the position column.
- 3. Shaded cells indicate procedural entry points.
OP-TEST # 1SCENARIO #2 Page 6 of 6 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 1 Event
Description:
PZR Pressure Channel Fails High Time Position Applicant's Actions or Behavior Notes Notes and communicates alarms for PZR RO PORV Open.
RO may select out the failed Places Master Pressure Controller in RO channel. Action must be taken Manual and decreases output.
in time to prevent a Rx Trip.
RO/BOP/ Monitor RCS pressure for entry into DNB T.S. 3.4.1, two hours to restore.
CRS Tech. Spec. at < 2220 psig.
As RCS pressure decreases to < 2220, the Crew may enter appropriate CRS/RO crew may energize 2nd set of PZR back-up ALRs which will direct entry heaters. to OFN SB-008 CRS Enter and direct OFN SB-008, Attach. K Identify BB PI-457 indicates high.
Select out failed channel.
RO Ensure system stable and return to automatic.
Monitor system response.
Contact Work Week Manager (WWM) and request I&C assistance to trip bi-stables and repair channel. 3.3.1 and 3.3.2 Review and comply with Tech Specs. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to place channel in 3.3.1 Reactor Trip System trip.
Table 3.3.1, Functions 6 and 8. 3.3.2, function 8.b. Verify P-11 CRS 3.3.2 ESFAS Instrumentation bi-stable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Table 3.3.2, Functions1.d and 8.b 3.3.4, Remote S/D, N/A 3.3.4/3.3.6/3.3.7 No Action 3.3.6, CPIS Instrumentation, Function 4 Required 3.3.7, CREVS Instrumentation, Function 4 Master pressure controller back in Auto Termination Criteria: with pressure between 2220 and 2250 psig. T.S. actions identified.
OP-TEST # 1SCENARIO #2 Page 7 of 7 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 2 Event
Description:
C S/G ARV fails open in auto, manual available.
Time Position Applicant's Actions or Behavior Notes The crew may notice the ARV CRS/RO Note and communicate RCS temperature right away and effects on plant BOP and pressure are decreasing.
parameters will not occur.
Note and communicate Rx power has RO increased.
Note that turbine load has decreased but BOP load set is stable.
CRS/RO Note that C S/G ARV is indicating open, BOP BOP take manual control and close the (Continuous) ARV.
If the ARV was closed quickly Diagnose indications as a steam leak. Enter the crew may not enter the off CRS and direct actions of OFN AB-041 normal. The T.S should still be Steamline or Feedline Leak.
reviewed.
Check Rx Power < 100%, if not:
- Close AE HV-038.
If the crew has already closed CRS/RO
Check Tavg/Tref mismatch <3 degrees Check Condenser Hotwell level.
Ensure S/G ARVs closed.
CRS/BOP BOP places ARV in manual/closed.
The ARV is still operable since Refer to T.S. 3.7.4.
CRS it is capable of opening and No action required.
closing.
Contact Work Week Manager (WWM) and CRS request assistance to troubleshoot/repair ARV.
C S/G ARV is in manual/closed. Rx Termination Criteria:
Power is stable at or below 100%.
OP-TEST # 1SCENARIO #2 Page 8 of 8 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 3 Event
Description:
B S/G MFRV fails closed in auto, manual available.
Time Position Applicant's Actions or Behavior Notes Notes and communicates B S/G level is BOP decreasing.
Notes and communicates annunciators 109B BOP and/or 109C, Steam Flow/Feed Flow Mismatch.
Places MFRV B in manual, matches feed Actions must be taken in time to BOP flow to steam flow and stabilizes S/G level. prevent a reactor trip.
Checks Secondary Panels and determines RO there is no instrument failure.
Enter and direct actions of Alarm Response CRS ALR 00-109B or 109C.
Verify Steam/Feed Mismatch.
CRS/BOP Verify NO instrument failures.
Verify NO Secondary transient.
Use manual control on B MFRV and BOP restore S/G level to program. (50%)
CRS/BOP Check for S/G Tube Leakage Contact Work Week Manager (WWM) and CRS request assistance to troubleshoot/repair B MFRV controller.
B S/G level stable at or trending to Termination Criteria: program (50%), with the controller in manual.
OP-TEST # 1SCENARIO #2 Page 9 of 9 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 4 Event
Description:
Nuclear Instrumentation Channel NI-43 fails high.
Time Position Applicant's Actions or Behavior Notes Notes and communicates to the crew rods RO stepping in.
Verifies and communicates, no loss of BOP load has occurred.
Rods must be placed in manual RO Places rod control in manual.
in time to prevent a Rx Trip.
Acknowledge communications and that rod CRS control is in manual.
RO Notes that NI-43 indication is high.
Enter and direct OFN SB-008, Instrument Crew may enter an ALR which CRS Malfunctions, Attachment R. Steps R1 will direct entry to OFN SB-through R3 are already complete. 008.
Bypass Failed Channel at the NI Cabinets.
At Detector Current Comparator Drawer:
- Upper Section switch to N43 CRS/BOP
- Lower Section switch to N43
- Power Mismatch Bypass to N43
- Rod Stop Bypass to N43 At Comparator and Rate Drawer:
- Comparator Channel Defeat to N43.
Conduct Reactivity brief and withdraw control rods back to the parked position.
BOP Peer check rod motion. Management Expectation that CRS/RO all reactivity actions be peer Checks Tavg/Tref within 1 degree checked.
Place rod control in Automatic.
Monitor Rod Control System.
OPERATOR ACTIONS Event 4 Continued
OP-TEST # 1SCENARIO #2 Page 10 of 10 CRS/RO Check channel not used for recorders.
CRS/BOP Remove Control Power Fuses for N43.
Contact Work Week Manager (WWM) and request I&C assistance to trip bi-stables and repair channel.
Review and comply with Tech Specs.
T.S. 3.3.1 Function 2 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to place channel in trip and Perform SR 3.2.4.2 Functions 3 and 6 3.3.1 Reactor Trip System 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to place channel in CRS Table 3.3.1-1, Functions 2, 3 and 6. trip.
Table 3.3.1, Function18, Permissives. Function 18 P-7, P-8, P-9 and P-10 Verify bistable in proper state or be in Mode 2 in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
Technical Requirements Manual TRM 3.3.17 TRM 3.3.17 Reactivity Alarms Perform AFD STS once per hr Conditions A and D Perform QPTR STS once/12 hrs Control Rods are in automatic and Termination Criteria: returned to the park position. Tech Spec time limit has been identified
OP-TEST # 1SCENARIO #2 Page 11 of 11 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 5 Event
Description:
SSE/OBE Earthquake causes SBLOCA escalating to a LBLOCA.
Time Position Applicant's Actions or Behavior Notes Notes and acknowledges Annunciators RO/BOP 098C, 98D and 98E earthquake. OBE earthquake.
CRS will enter OFN SG-003 or Enter and direct actions of OFN SG-003, perform the ALRs. In either CRS Natural Events or Alarm Response 98C, case the SBLOCA will escalate 98D or 98E. requiring entry to OFN BB-007, RCS Leakage.
Note and communicate RCS pressure is decreasing, Containment humidity is RO/BOP increasing. Monitor for entry to DNB T.S.
entry at < 2220 psig.
Enter and direct OFN BB-007 RCS CRS Leakage.
Checks PZR Level - decreasing.
Increase charging flow. RO should increase charging RO Isolate Letdown. flow and isolate letdown.
Check Charging Pump Suction.
CRS/RO Check PZR pressure - stable.
Check S/G Tubes - intact.
CRS/BOP
- Dispatch HP
- Contact Chemistry.
Earthquake escalates to large Break LOCA after 3 minutes.
The crew may not perform all steps listed for OFN BB-007.
OFN BB-007 has been entered.
Termination Criteria:
OP-TEST # 1SCENARIO #2 Page 12 of 12 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 6 Event
Description:
SSE/OBE escalates to Loss of Offsite Power, LBLOCA.
Both Emergency Diesels Fail to Auto Start.
Time Position Applicant's Actions or Behavior Notes Notes and communicates annunciators 98A RO/BOP and 98B. SSE earthquake.
Notes and communicates rapidly decreasing PZR level and pressure.
RO Isolate Letdown.
Maximize Charging.
Automatic actuation will Direct Rx Trip and SI.
CRS probably occur before the crew Enter and direct actions of EMG E-0.
can take action.
RO/BOP Perform Immediate Actions of EMG E-0.
RO Verify Rx Tripped.
BOP Verify Turbine Tripped.
Check AC buses - At least one energized.
EVENT 6 RO Depress Start/Reset pushbutton for both Procedure requires starting (C) EDGs.
both EDGs.
Verify Buses energize.
RO Verify Safety Injection has actuated.
Ensure Immediate Actions complete.
CRS Identify any immediate concerns.
One person from the crew should recognize adverse containment values have been ALL exceeded and communicate this to the rest of the crew.
Termination Criteria:
OP-TEST # 1SCENARIO #2 Page 13 of 13 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 6 Continued Event
Description:
Continue through EMG network till Lo-Lo RWST level reached then execute EMG ES-12 Transfer to Cold Leg Recirc.
Time Position Applicant's Actions or Behavior Notes CRS/RO Check if SI is required - YES Perform EMG E-0 Attach. F for Automatic CRS/RO Signal verification.
Verify AFW > 270 klbm/hr.
Close AC HIS-134 CRS/BOP Reduce AFW to 270 klbm/hr Establish S/G Pressure Control Check PORV/Block Valves.
Check PZR Spray Valves.
CRS/BOP Check PZR Safety Valves.
Check if RCPs should be stopped.
Monitor Critical Safety Function Status CRS/BOP Trees using EMG F-0.
Check if S/Gs are not faulted.
Check if S/G Tubes are intact.
CRS/RO
- Dispatch HP Check S/G levels - controlled increase Check if RCS Intact in Containment NO CRS/RO Ensure BIT inlet and outlets open.
Transition to EMG E-1 At some point a Red Path will occur on This may occur before or after CRS/BOP Integrity due to the large cooldown. The transition to EMG E-1.
CRS should transition to EMG FR-P1.
Enter and exit EMG FR-P1, Response to CRS Imminent Pressurized Thermal Shock.
At step one determine RHR flow > 500gpm CRS/RO and exit procedure.
OP-TEST # 1SCENARIO #2 Page 14 of 14 Event No.: 6 Continued Crew will begin working Enter and Direct EMG E-1, Loss of through EMG E-1 till CRS Reactor or Secondary Coolant. Conduct Annunciator 047D, RWST Lev Transition Brief with Crew.
Lo-Lo 1 alarms.
CRS/RO Monitor Fold Out Page for Cold Leg BOP Recirculation Criteria. RWST Level <
(Continuous) 36%, Annunciator CRS/RO Check if RCPs should be stopped.
Check if S/Gs not faulted.
CRS/BOP Check if S/G Tubes are intact.
Reset SI.
CRS/ RO Reset CIS-A.
Reset CIS-B Annunciator 047D, RWST Level Lo-Lo 1 Termination Criteria: alarms and the Crew transitions to EMG ES-12.
OP-TEST # 1SCENARIO #2 Page 15 of 15 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 7 Event
Description:
EMG ES-12 is entered; RWST Suction Valve BN HV-8812A fails to automatically re-align.
Time Position Applicant's Actions or Behavior Notes Enter and direct action of EMG ES-12. No The first ten steps of EMG ES-transition brief is desired or required.
CRS 12 are critical to establish cold CRS/RO will perform procedure while the leg recirc.
BOP monitors the rest of the plant.
Reset All SI signals.
CRS/RO SIS - SB HIS-42A and 43A.
(C)
RWST Switchover - SB HIS-62 and 63.
Ensures CCW pump running in both trains.
CRS/RO Ensures both CCW to RHR HX valves open.
CRS/RO Ensure CCW to SFP HX valves closed.
Checks Red Train Switchover.
Note that BN HV-8812A is open.
CRS/RO Additional critical action to Perform RNO.
(C) isolate the A Train.
Stop A RHR pump.
Close EJ HV-8811A.
CRS/RO Checks Yellow Train Switchover.
CRS/RO Close both Hot Leg Recirc valves. Operators should realize they (C) Ensures B RHR pump running. should not start A RHR.
Close both SI pump mini-flow valves.
EM HIS-8814A and 8814B CRS/RO OR (C) Using the Power Lockout, close SI pump recirc to RWST.
BN HIS-8813
OP-TEST # 1SCENARIO #2 Page 16 of 16 Event No.: 7 Continued Open Both RHR to CCP/SI suction valves.
EJ HIS-8804A EJ HIS-8804B (Critical)
Open both CVCS to SI suction valves.
EM HIS-8807A and 8807B CRS/RO At least one open. (Critical)
(C) Close both RWST to SI suction valves.
BN HIS-8806A and BN HIS-8806B (Both are Critical)
Close both RWST to CCP suction valves.
BN HIS-112D and BN HIS-112E (Both are Critical)
Resume monitoring Critical Safety CRS Functions.
Cold Leg Recirculation is aligned with Terminate Scenario Termination Criteria:
A RHR pump secured.
OP-TEST # 1SCENARIO #2 Page 17 of 17 CRITICAL TASK
SUMMARY
POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/
UNSAT RO Start both Emergency Diesels by At least one AC Emergency bus pressing the Start/Reset pushbuttons. is powered from its associated diesel generator before transition to EMG C-0, Loss of All AC.
Although only one is required from a Critical Task standpoint, procedure EMG E-0 directs starting any stopped diesel.
CRS/RO Establish Cold Leg Recirc. A RHR pump secured and its Isolate A Train RHR pump. RWST suction valve closed.
Remaining ECCS pumps on at least one train are aligned for suction from B RHR pump.
OP-TEST # 1SCENARIO #2 Page 18 of 18 Booth Instructions Ensure batch file has been loaded into X:\Opensim\Batch folder in the Instructor Station Computer.
Initialize in IC 176 and go to RUN.
On the Expert screen load batch file: a2004SCN02.txt. After file loads FREEZE the simulator.
Hang DNO tags on the following:
Perform Simulator Ready checklist.
OP-TEST # 1SCENARIO #2 Page 19 of 19 BOOTH COMMUNICATIONS AND ACTIONS Unless otherwise directed, all events will be entered when cued from the floor.
If at any time the crew makes contact with the Shift Manager or Call Supt., simply acknowledge their report and respond you will get back with them.
When cued from the floor or when crew assumes the watch go to RUN.
WHEN cued after crew assumes the watch, enter EVENT 1.
When CRS contacts I&C or the Work Week Manager for PZR instrument failure, respond:
I will assemble a team.
WHEN cued from the floor, enter EVENT 2.
When CRS contacts I&C or the Work Week Manager for C ARV, respond:
I will assemble a team.
WHEN cued from the floor, enter EVENT 3.
When CRS contacts I&C or the Work Week Manager for B MFRV failure, respond:
I will assemble a team.
WHEN cued from the floor, enter EVENT 4.
When CRS contacts I&C or the Work Week Manager for NI-43 failure, respond:
I will assemble a team.
WHEN cued from the floor, enter EVENT 5.
During event 5 the CRS may contact personnel outside the Control Room to confirm the earthquake.
Report: I have felt some sort of movement or vibrations.
When directed from the floor, FREEZE the simulator. DO NOT RESET till allowed by the NRC Chief Examiner.
OP-TEST # 1SCENARIO #2 Page 20 of 20 Batch File:
>Bat 2004SCN02.txt
>Tag Out NCP IRF NBGP04 1
>Controlling PZR Press channel fails high IMF mPRS01C (1) 2500 30
>FAIL Open OF "C" S/G ARV IMF mMSS07C (2) 100 20
>"B" MFRV fails in Auto IMF mFWM03B (3) 0 60
>NIS Channel 43 fails high IMF mNIS03C (4) 120 10
>Earthquake occurs causing a SBLOCA escalates to LOCA/LOSP TRGSET 5 (0)
IMF ANN-E098 (5) 0 IMF ANN-D098 (5 4) 0 IMF ANN-C098 (5 10) 0 IMF mRCS07C (5 7) 120 60 IMF ANN-B098 (5 240) 0 IMF ANN-A098 (5 243) 0 IMF mRCS06C (5 243) 80000 120
>LOSP tied to Rx Trip/Both EDG's Fail to auto start TRGSET 6 "JPPLP4" IMF mEPS01A (6 20)
IMF mEPS01B (6 25)
IMF mDGS02A IMF mDGS02B
>Failure of BN HV-8812A to close on RWST Lo-Lo TRGSET 8 "JD047A" IRF rBN8812A (8) 1
>End of File
OP-TEST # 1SCENARIO #2 Page 21 of 21 SHIFT BRIEFING INFORMATION THIS FORM IS FOR TRAINING PURPOSES ONLY CONTROL ROOM TURNOVER CHECKLIST DATE : Today NIGHT SHIFT X DAY SHIFT MODE- 1 OFF-GOING: (PRINT) CRS ON-COMING: (PRINT) CRS RO RO BOP BOP SE SE ON-COMING CRS/SE/RO/BOP REVIEW EVOLUTIONS IN PROGRESS:
MAINTENANCE IN PROGRESS: NCP OOS for Bearing Replacement.
TESTING IN PROGRESS:
SIGNIFICANT LCOs IN EFFECT:
REACTOR POWER 100% % RCS: 586.5 °F 2235 PSIG ROD CONTROL AUTO X MANUAL CONTROL BANK D 229 STEPS RCS BORON (Cb) 1028 PPM @ DATE/TIME Today/0400 LEAK RATE IDENTIFIED .02 UNIDENTIFIED .01 @ DATE/TIME Today/
(GPM): 0400 COND. AIR 13.1 INLEAKAGE (IAW STN CH-020)
ESF STATUS PANELS AND REACTOR TRIP/BLOCK PANEL PANEL COMPONENT/TRIP/BLOCK REASON TRAINING ONLY ALARM WINDOW DESCRIPTION WINDOW NAME REASON WR/WO
INITIAL LICENSE EXAM OPERATING TEST # 1 SCENARIO # 3 Back Up Revision 03 Week of May 10, 2004
OP-TEST #1 SCENARIO #3 Page 2 of 2 Facility: Wolf Creek NRC Scenario No.: 3 Op-Test No.: 1 Revision 03 Source:
New X Bank - Significantly Modified Bank - Initial Condition Change See page 3 for Examiner/student assignments Initial Conditions: Chemistry hold at 30% power, Ready to Enter Gen 00-004 Turnover: Prepare to continue power increase to 100%
Event Malf. Event Event No. No. Type* Description 1 mFWM I C S/G Controlling Level Channel fails high.
02C4 T+1 2 mCVC1 C Normal Charging Pump Trips 3C T+11 3 MCVC0 C Excessive Seal Leak Off A RCP.
6A T+18 4 mRCS0 M S/G Tube Rupture develops on A S/G requiring Rx Trip/SI.
2A T+46 P19019 B&
5 C Both ESW pumps fail to auto start on Safety Injection.
P19028 T+47 B
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
OP-TEST #1 SCENARIO #3 Page 3 of 3 Scenario # 3 Crew Assignments Session 1 Crew A Examiners Applicants E1: CRS:
E2: RO:
E3: BOP:
E4:
Session 2 Crew B Examiners Applicants E1: CRS:
E2: RO:
E3: BOP:
E4:
Session 3 Crew C Examiners Applicants E1: CRS:
E2: RO:
E3: BOP:
E4:
Session 4 Crew D Examiners Applicants E1: CRS:
E2: RO:
E3: BOP:
E4:
OP-TEST #1 SCENARIO #3 Page 4 of 4 SCENARIO MISCELLANEOUS INFORMATION SCENARIO OBJECTIVE:
The objective of this scenario is to mitigate a Steam Generator Tube Rupture (SGTR) using the guidance provided in the EMGs. Initial conditions have the unit in a hold at 30% power for S/G chemistry following a start up from a forced outage. The scenario contains a failure of the controlling level channel for C S/G, requiring operator action to prevent a reactor trip. Following is a trip of the Normal Charging Pump (NCP), which leads to a failure of the A RCP seal. The crew establishes proper conditions, then trips the A RCP.
The SRO will evaluate technical specifications associated with the S/G level channel failure and the loss of an operable reactor coolant loop. Technical Specifications do not allow power operation with less than all four loops operable. The CRS needs to recognize the unit has to be shutdown.
The major event is a SGTR. After the RCP is tripped a SGTR develops on the idle A S/G.
The rupture starts small and gradually increases leading to a manual Reactor Trip and Safety Injection (SI). Both Essential Service Water (ESW) Pumps fail to auto start on the SI requiring manual operator actions. The crew must determine target conditions and successfully cooldown the unit to the target conditions without overcooling which could cause entry into a different mitigation procedure. The scenario is terminated once the crew has stabilized at or below the target.
The following is the expected major procedure flow path:
- OFN SB-008, INSTRUMENT MALFUNCTIONS
- OFN BB-005, RCP MALFUNCTIONS
- OFN BB-007 or 07A during the Steam Generator Tube Leak.
- EMG E-0, REACTOR TRIP OR SAFETY INJECTION
- EMG E-3, STEAM GENERATOR TUBE RUPTURE CRITICAL PARAMETERS:
The following parameters may be of value in evaluating crew performance when the scenario is completed:
- S/G C level
- S/G A level
- Core Exit TCs
- S/G pressures
OPERATOR ACTIONS TABLE NOTES:
OP-TEST #1 SCENARIO #3 Page 5 of 5
- 1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.
- 2. Actions required throughout the event are indicated as "(continuous)" in the position column.
- 3. Shaded cells indicate procedural entry points.
OP-TEST #1 SCENARIO #3 Page 6 of 6 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 1 Event
Description:
C S/G Controlling Level Channel fails high.
Time Position Applicant's Actions or Behavior Notes Notes and communicates annunciator 00-110B, and that C MFRV is going closed.
Stabilize S/G level to prevent a BOP Takes manual control of C MFRV and Rx Trip.
stabilizes level at program level (50%).
Acknowledges communications, enters and CRS may enter OFN SB-008 CRS directs Alarm Response (ALR 00-110B) directly.
Notes and communicates that level RO indicator AE LI-553 is failing high.
Manually controls MFRV to establish S/G level at program.
BOP Select out failed channel.
Returns MFRV controller to auto.
Enter and direct actions of OFN SB-008, CRS Instrument Malfunctions, Attach. F.
Confirms failed channel, channel has been selected out, monitors S/G level to ensure BOP proper control.
Contact Work Week Manager (WWM) to have I&C troubleshoot and trip bi-stables.
CRS Recognize channel does affect AMSAC.
OPERATOR ACTIONS
OP-TEST #1 SCENARIO #3 Page 7 of 7 Event 1 Continued Refer to and comply with T.S. Actions.
Table 3.3.1-1 Function 14 All are 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to trip bi-CRS T.S. 3.3.1, Condition E stables.
Table 3.3.2-1, Functions 5b and 6d.
T.S. 3.3.2, Conditions I and D Review Attach. S, determine instrument CRS does not affect T.S. 3.3.3 or 3.3.4 for Post Accident or Shutdown Monitoring.
S/G level stable or trending to 50%.
Termination Criteria: MFRV back in auto and Tech Specs identified.
OP-TEST #1 SCENARIO #3 Page 8 of 8 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 2 Event
Description:
Normal Charging Pump Trips Time Position Applicant's Actions or Behavior Notes Notes and communicate annunciator 042E /
042A and other alarms.
RO Determine and communicate that the Normal Charging Pump has tripped.
Acknowledge communications. Enter and CRS Crew may go to ALR 042A.
direct Alarm Response (ALR 00-042E)
Reports charging flow is < 45 gpm and no charging pump is running.
B CCP is aligned to the Closes Letdown Orifice Isolations.
normal charging header.
RO Makes plant announcement and starts B Starting A CCP would CCP.
require additional actions.
Manually control BG FCV-121 to control charging flow.
Direct RO to establish letdown flow using CRS ALR or SYS procedure.
Place Letdown HX Outlet Pressure Control in Manual (BG PK-131) and Open between 90% and 100%
Open two Letdown Orifice Isolation Valve(s). If ALR 00-042A was entered, RO Adjust Letdown HX Outlet Pressure these steps will be performed Control to establish Letdown HX Outlet using the system procedure.
Pressure between 340 psig and 360 psig.
Place Letdown HX Outlet Pressure Control in Auto Adjust PZR Master Level Controller to RO stabilize PZR level or establish a trend towards program level.
B CCP is running with normal letdown Termination Criteria:
re-established.
OP-TEST #1 SCENARIO #3 Page 9 of 9 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 3 Event
Description:
Excessive Seal Leak Off A RCP.
Time Position Applicant's Actions or Behavior Notes Notes and communicates alarm 072A.
RO Checks seal leak off A RCP @ 6 gpm.
Acknowledges communication. Enters and May enter OFN BB-005, RCP CRS directs ALR 00-072A. Malfunctions, directly.
Determines RCP A seal leakoff > 5.7.
CRS/RO Transition to OFN BB-005.
Enter and direct OFN BB-005, RCP CRS Malfunctions.
Enter Turn on Code BB3 on the plant RO/BOP computer NPIS screen.
Check RCP Parameters:
- 1 Seal temperature < 230 degrees RO/BOP Motor bearing temperature < 195 degrees Stator Winding temperature < 299 degrees Cue from booth:
Check RCP vibration readings. All frame vibrations < 2 BOP (Located in back panels) All shaft vibrations < 10 All appear steady.
Check Seal leak off < 6 gpm.
RO NO CRS Use RNO and go to Attach. E Determine from Attach. E:
Seal leak off > 6 gpm CRS Total #1 seal flow > 8 gpm Shutdown RCP using Attach. B Direct actions of Attach. B CRS Rx critical at < 48% power.
OP-TEST #1 SCENARIO #3 Page 10 of 10 OPERATOR ACTIONS Event 3 Continued Prepare S/G for RCP S/D Place A MFRV in manual and feed A BOP S/G to 70% narrow range.
(Continuous) When RCP is stopped then place MFRV back in Auto Stop A RCP Place A Spray Valve controller in manual and zero output.
CRS/RO Defeat Tavg and Delta T inputs for Loop A.
Between 3-5 minutes after RCP S/D, close Seal water outlet isolation for A RCP.
Reference T.S. 3.4.4, RCS Loops in Modes All 4 loops required.
CRS 1 and 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to Mode 3.
RCP A is stopped with Seal Leak Off Termination Criteria: isolated, T.S required Shut Down identified.
OP-TEST #1 SCENARIO #3 Page 11 of 11 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 4 Event
Description:
S/G Tube Rupture develops on A S/G requiring Rx Trip/SI.
(Leak ramps in from 50 gpm to 250 gpm.)
Time Position Applicant's Actions or Behavior Notes CRS/RO Note and communicate RCS pressure is BOP decreasing.
Monitor RCS pressure for entry into DNB CRS/RO Tech. Spec. at < 2220 psig.
BOP T.S. 3.4.1, two hours to restore.
As RCS pressure decreases, may energize RO Monitor for DNB T.S.
PZR B/U heaters.
Note and communicate that PZR level is RO decreasing.
May enter OFN BB-007 for RCS Leakage There is a delayed reaction of or OFN BB-07A for S/G Tube Leakage, CRS the off gas radiation monitor depending on indications observed. Initial due to securing A RCP.
actions are the same.
Unit in Modes 1, 2 or 3.
CRS/RO PZR Level >17%
PZR Level stable or increasing - NO Maximizing Charging from B CCP.
RO Monitor PZR level.
(Continuous) When level continues to decrease, Then isolate letdown Note and communicate GE RE-92, CRS/RO Condenser Air Discharge Rad Monitor in BOP alarm.
Diagnose S/G tube leak based on:
GE RE-92 in Alarm.
CRS/RO No indications of leak in Containment or Auxiliary Building.
OPERATOR ACTIONS Event 4 Continued Fold Out Page criteria is met when charging is maximized, letdown isolated and PZR CRS/RO level continues to decrease.
OP-TEST #1 SCENARIO #3 Page 12 of 12 Direct a Reactor Trip and Initiate Safety CRS Injection.
Determined the leak is in excess of the Termination Criteria: capacity of one charging pump, Rx trip and Safety Injection actuated.
OP-TEST #1 SCENARIO #3 Page 13 of 13 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.s: 5 and 6 Event
Description:
During Crew response for immediate actions of EMG E-0, the Main Turbine fails to trip automatically, both ESW pumps fail to Auto Start.
Time Position Applicant's Actions or Behavior Notes Enter and Direct actions of EMG E-0, CRS Reactor Trip or Safety Injection.
RO/BOP Perform Immediate Actions of EMG E-0.
Verify Rx Trip
- Rod Bottom Lights Lit.
- Rx Trip and Bypass Bkrs open.
- Neutron Flux decreasing (Intermediate Range & Gamma metrics)
- Both NB buses - normal voltage /
off site power.
Verify SI actuated
- Determine SI is actuated.
Annunciators 30A and 30B are lit.
Recognize Turbine did not trip.
Manually trip Turbine BOP should trip before a Main BOP
- Main Stop valves all closed. Steam Line Isolation occurs.
- Generator and exciter bkrs open.
At completion of Immediate Actions CRS determine if there are any immediate concerns.
RO Reports both ESW pumps failed to start.
CRS Direct RO to start both ESW pumps.
RO Makes plant announcement and starts (C) both ESW pumps.
OP-TEST #1 SCENARIO #3 Page 14 of 14 OPERATOR ACTIONS Op-Test No.: # 1 Scenario No.: 2 Event No.: 5 (Continued)
Event
Description:
Continuation of the SGTR using EMG E-0 at step 5 and EMG E-3.
Time Position Applicant's Actions or Behavior Notes Check if SI is required.
CRS Recognize SI was manually initiated.
Perform Attach. F to verify automatic actions.
If ESW pumps were not previously started, BOP Attach. F will provide guidance to start them. Ops expectations, per AP 15C-003 though, requires starting ESW/CCW at the end of Immediate Actions.
RO Monitor A S/G level and isolate AFW (Continuous) when Level is > 6% Narrow Range.
Check Plant:
AFW > 270,000 lbm/hr RCS Cold Leg Temperature Stable CRS/RO Place Steam Dumps in Stm Press Mode Check PORVs/Block Valves Check Spray valve/Safeties Closed Check if RCPs should be stopped - NO Direct monitoring of Critical Safety CRS Function Status Trees(CSFST)
CRS/RO Monitor CSFST on NPIS computer screen BOP after 1st verification with the procedure.
(Continuous)
Check S/Gs not faulted.
CRS/RO Check S/Gs Tubes intact:
GE RE-92 normal - NO Operator Actions Event 5 Continued Ensure BIT is not isolated.
CRS/RO Transition to EMG E-3 BOP (Attach. F of EMG E-0 must be completed prior to transition.) A transition brief is not required nor desired.
OP-TEST #1 SCENARIO #3 Page 15 of 15 Monitor RCS pressure for RCP trip CRS/RO criteria.
BOP Does not apply once the cooldown is (Continuous) started.
Identify and isolate ruptured S/G by:
A S/G level increasing uncontrolled.
A ARV set at 1125 and closed.
CRS/BOP Dispatch operator to close low point drain.
Blowdown/Sampling isolated.
Close A MSIV and ensure bypass closed.
Feed flow isolated if level > 6% NR.
CRS/BOP Steam Dumps in Steam Pressure Mode.
Verify ruptured A S/G is isolated.
CRS Do NOT continue till it is.
CRS/RO Check ruptured S/G press > 275 psig.
BOP Block Low Steam Line Pressure SI.
RO Monitor RCS and perform when pressure is (Continuous) less than 1970 and prior to 1830 psig.
Initiate RCS Cooldown If above 550 on Tavg, setting Determine Target Temperature.
the controller directly to the Cooldown using Steam Dumps/ARVs.
target setpoint could cause a CRS/BOP Per Ops Expectations, AP 15C-003, the Main Steam Line Isolation steam dump controller should be lowered (C) requiring the use of the ARVs.
slowly such that only group 1 valves open.
If the main steam line has Once Tavg is below 550 degrees the low isolated, the cooldown must be temperature interlock is by-passed and the performed on the ARVs.
controller is set at Target Setpoint.
Control AFW flow to maintain intact S/G CRS/BOP levels between 29 and 50%.
Operator Actions Event 5 Continued Check PORVs/Block Valves.
Check PZR Safeties closed.
Steps are performed Reset SI CRS/RO concurrently with the Reset CISA and CISB.
cooldown.
Establish Instrument Air to Containment.
Stop the RHR pumps.
CRS/RO Monitor RCS pressure for RHR restart if (Continuous) pressure decrease to < 300 psig.
OP-TEST #1 SCENARIO #3 Page 16 of 16 Stop the RCS Cooldown.
Ensure Steam Dumps close as target CRS/BOP temperature is approached.
(C) Adjust steam dump controller as required to maintain RCS temperature at or below target but greater than 350 degrees.
RCS cooldown is terminated with Termination Criteria:
temperature stable at or below target.
OP-TEST #1 SCENARIO #3 Page 17 of 17 CRITICAL TASK
SUMMARY
POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/
UNSAT CRS/RO Start both Essential Service Water ESW is required to ensure (ESW) Pumps. cooling to safety related components that have actuated during an accident response. At least one train must be started prior to the end of the scenario.
CRS/BOP Conduct the RCS Cooldown during a Max rate cooldown conducted to SGTR to the target conditions. target conditions. When stable at Stabilize at or slightly below the target. target; RCS subcooling >50 degrees and core exit TCs > 350 degrees.
OP-TEST #1 SCENARIO #3 Page 18 of 18 Booth Instructions Ensure batch file has been loaded into X:\Opensim\Batch folder in the Instructor Station Computer.
Initialize in IC 172 and go to RUN.
On the Expert screen load batch file: 2004SCN03.txt. After file loads FREEZE the simulator.
Provide copy of GEN 00-004 for the CRS with Initial Conditions signed off.
Perform Simulator Ready checklist.
OP-TEST #1 SCENARIO #3 Page 19 of 19 BOOTH COMMUNICATIONS AND ACTIONS Unless otherwise directed, all events will be entered when cued from the floor.
When cued from the floor or when crew assumes the watch go to RUN.
WHEN cued after crew assumes the watch, enter EVENT 1.
When CRS contacts I&C or the Work Week Manager for C S/G Level instrument failure, respond:
I will assemble a team.
WHEN cued from the floor, enter EVENT 2.
If CRS contacts the Work Week Manager for the NCP, respond:
I will assemble a team.
WHEN cued from the floor, enter EVENT 3.
When the CRS contacts the Shift Manager or Call Supt about the RCP seal leak off, acknowledge the report and state you will contact management.
When the CRS contacts System Ops about the unit shutdown, acknowledge the report.
WHEN cued from the floor, enter EVENT 4.
During EMG E-3 and possibly OFN BB-007/07A, the CRS will contact Chemistry and HP for assistance in determining the SGTR. Acknowledge their request.
AB V-062 is not modeled.
When directed from the floor, FREEZE the simulator. DO NOT RESET till allowed by the NRC Chief Examiner.
OP-TEST #1 SCENARIO #3 Page 20 of 20 Batch File:
>BAT 2004SCN03.txt
> "C" S/G Level channel fails high IMF mFWM02C4 (1) 100 20
>Normal Charging pump trips IMF mCVC13C (2)
>Excessive seal leakoff "A" RCP IMF mCVC06A (4) 9.5 180 5.7
> SGTR develops on "A" S/G IMF mRCS02A (5) 250 200 50
> Main Turbine fails to Auto Trip IMF mTUR08C
>Both ESW pumps fail to auto start IOR P19019B 0 IOR P19028B 0
>END OF FILE
OP-TEST #1 SCENARIO #3 Page 21 of 21 SHIFT BRIEFING INFORMATION THIS FORM IS FOR TRAINING PURPOSES ONLY CONTROL ROOM TURNOVER CHECKLIST DATE : Today NIGHT SHIFT X DAY SHIFT MODE- 1 OFF-GOING: (PRINT) CRS ON-COMING: (PRINT) CRS RO RO BOP BOP SE SE ON-COMING CRS/SE/RO/BOP REVIEW EVOLUTIONS IN PROGRESS: Borating 100 gallons every 30 minutes to hold power.
MAINTENANCE IN PROGRESS: None TESTING IN PROGRESS:
SIGNIFICANT LCOs IN EFFECT:
REACTOR POWER 30 % RCS: 566.5 °F 2235 PSIG ROD CONTROL AUTO X MANUAL CONTROL BANK D 171 STEPS RCS BORON (Cb) 1360 PPM @ DATE/TIME Today/0400 LEAK RATE IDENTIFIED .02 UNIDENTIFIED .01 @ DATE/TIME Today/
(GPM): 0400 COND. AIR (total) )
INLEAKAGE 13.8 (IAW STN CH-020)
ESF STATUS PANELS AND REACTOR TRIP/BLOCK PANEL PANEL COMPONENT/TRIP/BLOCK REASON TRAINING ONLY ALARM WINDOW DESCRIPTION WINDOW NAME REASON WR/WO 78B/78C PWR RANGE N/A UPR/LWR FLUX Current power level.
DEV 103D FW HTR DUMP N/A VALVE OPN Current power level.
103E HTR DRN TANK N/A DUMP Current power level.
OP-TEST #1 SCENARIO #3 Page 22 of 22