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{{#Wiki_filter:2006 NRC EXAM - ADMIN JPM RO #2 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
{{#Wiki_filter:2006 NRC EXAM - ADMIN JPM RO #2 PROGRAM TITLE           LICENSED OPERATOR INITIAL TRAINING COURSE TITLE             ADMIN JOB PERFORMANCE MEASURE LESSON TITLE VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
LESSON LENGTH  
MAXIMUM STUDENTS LESSON LENGTH     .5 HRS                         1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                             Rev. No.
  .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 5/15/06 REVISED BY DATE       TECHNICAL REVIEW BY DATE   INSTRUCTIONAL REVIEW BY DATE   APPROVED BY DATE   Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.  
Simulator Guide PQD Code                                         Rev. No.
JPM PQD Code                                                     Rev. No.
Exam PQD Code                                                   Rev. No.
DIVISION TITLE   Nuclear Training DEPARTMENT       Operations Training PREPARED BY       Ron Hayden                                      DATE   5/15/06 REVISED BY                                                         DATE TECHNICAL REVIEW BY                                               DATE INSTRUCTIONAL REVIEW BY                                           DATE APPROVED BY                                                       DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
Page 1 of 5 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
N/A Setup Instructions:
Get Attachment 7.1 and put two boxes to be checked. One states APRM readings ARE GT power readings extrapolated from BPV position and the other states APRM readings ARE NOT GT power readings extrapolated from BPV position.
Get Attachment 7.1 and put two boxes to be checked. One states APRM readings ARE GT power readings extrapolated from BPV position and the other states APRM readings ARE NOT GT power readings extrapolated from BPV position.
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different  
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
 
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Tools/Equipment: N/A                                   Safety Items: N/A Task Number: RO-0906                                   Validation Time: 10 minutes Prerequisite Training: N/A                             Time Critical: NO PPM  
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
Tools/Equipment:
N/A Safety Items:
N/A Task Number:
RO-0906 Validation Time: 10 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
PPM 3.1.2                                Location: Any NUREG 1123 Ref: 2.1.25 (2.8/3.1)                        Performance Method: Perform Page 1 of 5


PPM 3.1.2 Location: Any NUREG 1123 Ref:
VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
2.1.25 (2.8/3.1)
JPM CHECKLIST PROCEDURE   Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION:  listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
Performance Method: Perform VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
INITIAL     Columbia is in the process of starting up following a refueling outage. Current plant CONDITIONS:  conditions are:
Page 2 of 5 JPM CHECKLIST PROCEDURE VALIDATION:
* APRMs indicate 34% power
Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: Columbia is in the process of starting up following a refueling outage. Current plant conditions are: APRMs indicate 34% power Feedwater temperature is 147°F House Loads are equal to 1% Core Thermal Power BPV#1 is indicating 95 percent open BPV#2 is indicating 90 percent open BPV#3 is indicating 93 percent open BPV#4 is indicating 95 percent open INITIATING CUE: You have been directed by the CRS to perform step Q31 of PPM 3.1.2 "Verify the APRM readings are GT power level readings extrapolated from bypass valve position per Attachment 7.1". Present the completed Attachment 7.1 to the examiner with the table of BPV vs. % CTP filled in and a check mark applied to the appropriate box indicating if APRM readings are or are not GT power level readings extrapolated from BPV position.  
* Feedwater temperature is 147°F
* House Loads are equal to 1% Core Thermal Power
* BPV#1 is indicating 95 percent open
* BPV#2 is indicating 90 percent open
* BPV#3 is indicating 93 percent open
* BPV#4 is indicating 95 percent open INITIATING   You have been directed by the CRS to perform step Q31 of PPM 3.1.2 Verify the CUE:        APRM readings are GT power level readings extrapolated from bypass valve position per Attachment 7.1.
Present the completed Attachment 7.1 to the examiner with the table of BPV vs. % CTP filled in and a check mark applied to the appropriate box indicating if APRM readings are or are not GT power level readings extrapolated from BPV position.
Page 2 of 5


VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
* Items are Critical Steps Comments              Element                            Standard                      Sat/Unsat RECORD START TIME: __________
Fills in the following information:
BPV #1 % open is approximately 8.2                  S/U BPV #2 % open is approximately 8.0                  S/U BPV #3 % open is approximately 8.2                  S/U BPV #4 % open is approximately 8.3                  S/U House Loads 1% (given)                              S/U Total % CTP is approximately 33.7                    S/U Indicates in attachment that APRM indicated        S/U*
power levels are GT extrapolated BPV power level readings.
Termination Criteria: Candidate hands the examiner the completed Attachment 7.1 of PPM 3.1.2 and written indication that APRMs readings are GT power readings extrapolated from BPV position.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 3 of 5
Page 3 of 5
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Fills in the following information: BPV #1 % open is approximately 8.2 BPV #2 % open is approximately 8.0 BPV #3 % open is approximately 8.2 BPV #4 % open is approximately 8.3 House Loads 1% (given) Total % CTP is approximately 33.7 S / U S / U S / U S / U S / U S / U    Indicates in attachment that APRM indicated power levels are GT extrapolated BPV power


level readings.
VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
S / U
RESULTS OF JPM:
* Termination Criteria: Candidate hands the examiner the completed Attachment 7.1 of PPM 3.1.2 and written indication that  APRMs readings are GT power readings extrapolated from BPV  
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Candidate completes table on Attachment 7.1 of PPM 3.1.2 and determines APRM readings are GT power level readings extrapolated from BPV position.
Overall Evaluation                                  Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for        Validation/Critical      JPM Completion JPM (Initial Box)                        Time                Time 10 Minutes / NA COMMENTS:
Evaluator's Signature:                                  Date:
Page 4 of 5


position.
STUDENT JPM INFORMATION CARD Initial Conditions:
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information:  Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM  BYPASS VALVE POSITION (PPM 3.1.2)
Page 4 of 5 RESULTS OF JPM:
Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard:  Candidate completes table on Attachment 7.1 of PPM 3.1.2 and determines APRM readings are GT power level readings extrapolated from BPV position.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time  10 Minutes / NA COMMENTS:                              Evaluator's Signature:
Date:
Page 5 of 5 STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is in the process of starting up following a refueling outage.
Columbia is in the process of starting up following a refueling outage.
Current plant conditions are: APRMs are indicating 34% power   Feedwater temperature is 147°F House Loads are equal to 1% Core Thermal Power BPV#1 is indicating 95 percent open BPV#2 is indicating 90 percent open BPV#3 is indicating 93 percent open BPV#4 is indicating 95 percent open Cue: You have been directed by the CRS to perform step Q31 of PPM 3.1.2 "Verify the APRM readings are GT power level readings extrapolated from bypass valve position per  
Current plant conditions are:
.1".
* APRMs are indicating 34% power
* Feedwater temperature is 147°F
* House Loads are equal to 1% Core Thermal Power
* BPV#1 is indicating 95 percent open
* BPV#2 is indicating 90 percent open
* BPV#3 is indicating 93 percent open
* BPV#4 is indicating 95 percent open Cue:
You have been directed by the CRS to perform step Q31 of PPM 3.1.2 Verify the APRM readings are GT power level readings extrapolated from bypass valve position per Attachment 7.1.
Present the completed Attachment 7.1 to the examiner with the table of BPV vs. % CTP filled in and a check mark applied to the appropriate box indicating if APRM readings are or are not GT power level readings extrapolated from BPV position.
Present the completed Attachment 7.1 to the examiner with the table of BPV vs. % CTP filled in and a check mark applied to the appropriate box indicating if APRM readings are or are not GT power level readings extrapolated from BPV position.
2006 NRC EXAM - ADMIN RO #3 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE REVIEW SURVEILLANCE PROCEDURE OSP-INST-H101 LESSON LENGTH
Page 5 of 5
  .5 HRS MAXIMUM STUDENTS 1  INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 5/17/06  REVISED BY DATE        TECHNICAL REVIEW BY DATE  INSTRUCTIONAL REVIEW BY DATE  APPROVED BY DATE  Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


Page 1 of 4 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
2006 NRC EXAM - ADMIN RO #3 PROGRAM TITLE            LICENSED OPERATOR INITIAL TRAINING COURSE TITLE            ADMIN JOB PERFORMANCE MEASURE LESSON TITLE REVIEW SURVEILLANCE PROCEDURE OSP-INST-H101 MAXIMUM STUDENTS LESSON LENGTH      .5 HRS                          1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                            Rev. No.
N/A Setup Instructions:
Simulator Guide PQD Code                                        Rev. No.
JPM PQD Code                                                    Rev. No.
Exam PQD Code                                                    Rev. No.
DIVISION TITLE    Nuclear Training DEPARTMENT        Operations Training PREPARED BY      Ron Hayden                                      DATE  5/17/06 REVISED BY                                                        DATE TECHNICAL REVIEW BY                                                DATE INSTRUCTIONAL REVIEW BY                                            DATE APPROVED BY                                                        DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
 
MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
Print out a blank OSP-INST-H101 and fill in readings. At least one reading should be out of spec.
Print out a blank OSP-INST-H101 and fill in readings. At least one reading should be out of spec.
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: N/A                                   Safety Items: N/A Task Number: RO-0577                                   Validation Time: 20 minutes Prerequisite Training: N/A                             Time Critical: NO PPM  
N/A Safety Items:
N/A Task Number:
RO-0577 Validation Time: 20 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
OSP-INST-H101 Rev. 54 Location: Any NUREG 1123 Ref:
OSP-INST-H101 Rev. 54                   Location: Any NUREG 1123 Ref: 2.2.12 (3.0/3.4)                       Performance Method: Perform Page 1 of 4
2.2.12 (3.0/3.4)
 
Performance Method: Perform Page 2 of 4 JPM CHECKLIST PROCEDURE VALIDATION:
JPM CHECKLIST PROCEDURE         Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION:        listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: Columbia is operating at rated power. CRO2 has just completed filling out the OSP-INST-H101 checks and has asked you for a peer check.
INITIAL           Columbia is operating at rated power. CRO2 has just completed filling out the OSP-CONDITIONS:        INST-H101 checks and has asked you for a peer check.
INITIATING CUE: When you have completed your peer check of the Shift and Daily Instrument Checks (OPS-INST-H101) present them to the examiner (CRS). Circle any errors that you may have found during your review.
INITIATING         When you have completed your peer check of the Shift and Daily Instrument Checks CUE:              (OPS-INST-H101) present them to the examiner (CRS). Circle any errors that you may have found during your review.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
* Items are Critical Steps Comments               Element                             Standard                       Sat/Unsat RECORD START TIME: __________
Notes the following Out Of Spec readings:
Notes the following Out Of Spec readings:             S/U Circles out-of-tolerance readings:
S / U   Circles out-of-tolerance readings: Page 12 CMS-TE-15 (GT 150°F) Page 12 CMS-TE-17 (GT 150°F) Page 13 CMS-TE-16 (GT 150°F)
* Page 12 CMS-TE-15 (GT 150°F)                   S/U*
S / U
* Page 12 CMS-TE-17 (GT 150°F)                   S/U*
* S / U
* Page 13 CMS-TE-16 (GT 150°F)                   S/U*
* S / U
Termination Criteria: Candidate hands the examiner the completed OSP-INST-H101s and has circled Out-Of-Tolerance readings on page 12 and page 13.
* Termination Criteria: Candidate hands the examiner the completed OSP-INST-H101's and has circled Out-Of-Tolerance readings on page 12 and page 13.
RECORD TERMINATION TIME: _________
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 3 of 4 RESULTS OF JPM: REVIEW SURVEILLANCE PROCEDURE OPS-INST-H101 Examinee (Please Print):
Page 2 of 4
______________________________________________
 
Evaluator (Please Print):
RESULTS OF JPM:
______________________________________________
REVIEW SURVEILLANCE PROCEDURE OPS-INST-H101 Examinee (Please Print): ______________________________________________
Task Standard:
Evaluator (Please Print): ______________________________________________
Candidate correctly circles the three Out-Of-Tolerance readings.
Task Standard: Candidate correctly circles the three Out-Of-Tolerance readings.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Overall Evaluation                                   Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time 15 Minutes / NA COMMENTS:                               Evaluator's Signature:
Verified Procedure #/Rev. Used for         Validation/Critical      JPM Completion JPM (Initial Box)                         Time                 Time 15 Minutes / NA COMMENTS:
Date:
Evaluator's Signature:                                   Date:
Page 4 of 4 STUDENT JPM INFORMATION CARD Initial Conditions:
Page 3 of 4
 
STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is operating at rated power.
Columbia is operating at rated power.
CRO2 has just completed filling out the OSP-INST-H101 checks and has asked you for a peer check.
CRO2 has just completed filling out the OSP-INST-H101 checks and has asked you for a peer check.
Cue: When you have completed your peer check of the Shift and Daily Instrument Checks (OPS-INST-H101) present them to the examiner (CRS). Circle any errors that you may have found during your review.  
Cue:
When you have completed your peer check of the Shift and Daily Instrument Checks (OPS-INST-H101) present them to the examiner (CRS).
Circle any errors that you may have found during your review.
Page 4 of 4


2006 NRC EXAM - ADMIN RO #4 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE IF TAGOUT CAN BE HUNG (FAULTED)
2006 NRC EXAM - ADMIN RO #4 PROGRAM TITLE           LICENSED OPERATOR INITIAL TRAINING COURSE TITLE             ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE IF TAGOUT CAN BE HUNG (FAULTED)
LESSON LENGTH  
MAXIMUM STUDENTS LESSON LENGTH     .5 HRS                         1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                             Rev. No.
  .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 9/26/06 REVISED BY DATE       TECHNICAL REVIEW BY DATE   INSTRUCTIONAL REVIEW BY DATE   APPROVED BY DATE   Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.  
Simulator Guide PQD Code                                         Rev. No.
JPM PQD Code                                                     Rev. No.
Exam PQD Code                                                   Rev. No.
DIVISION TITLE   Nuclear Training DEPARTMENT       Operations Training PREPARED BY       Ron Hayden                                      DATE   9/26/06 REVISED BY                                                         DATE TECHNICAL REVIEW BY                                               DATE INSTRUCTIONAL REVIEW BY                                           DATE APPROVED BY                                                       DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED Page 1 of 5 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
N/A Setup Instructions:
Have a tagout for HPCS System that includes HPCS-V-4. Have a RWP that is Non-High Radiation entry with a survey map showing HPCS-V-4 in a high radiation area.
Have a tagout for HPCS System that includes HPCS-V-4. Have a RWP that is Non-High Radiation entry with a survey map showing HPCS-V-4 in a high radiation area.
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: N/A                                   Safety Items: N/A Task Number: RO-1293                                   Validation Time: 15 minutes Prerequisite Training: N/A                             Time Critical: NO PPM  
N/A Safety Items:
N/A Task Number:
RO-1293 Validation Time: 15 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
Location: Any NUREG 1123 Ref: 2.3.10 (2.9/3.3)                        Performance Method: Perform Page 1 of 5


Location: Any NUREG 1123 Ref:
DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED JPM CHECKLIST PROCEDURE             Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION:            listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
2.3.10 (2.9/3.3)
INITIAL               Columbia Generating Station is shutdown during outage R18.
Performance Method: Perform DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED Page 2 of 5 JPM CHECKLIST PROCEDURE VALIDATION:
CONDITIONS:
Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: Columbia Generating Station is shutdown during outage R18.
INITIATING             You have been directed by the Control Room Supervisor to hang tagout D-HPCS-V-CUE:                  102R18-001. Health Physics has been contacted and directed use of RWP-30001421 for the purpose of hanging tags in the Reactor Building.
INITIATING  
Review the task and from the information provided, fill out the attached sheet indicating your ability (or inability) to perform the task assigned.
 
* Items are Critical Steps Comments                   Element                               Standard                         Sat/Unsat RECORD START TIME: __________
CUE: You have been directed by the Control Room Supervisor to hang tagout D-HPCS-V-102R18-001. Health Physics has been contacted and directed use of RWP-30001421 for the purpose of hanging tags in the Reactor Building. Review the task and from the information provided, fill out the attached sheet indicating your ability (or inability) to perform the task assigned.
Fills out the attached sheet indicating that the task can not be performed due to HPCS-V-4             S/U*
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
being in a High Radiation area and the RWP is for Non-High Radiation plant operation/
Fills out the attached sheet indicating that the task can not be performed due to HPCS-V-4 being in a High Radiation area and the RWP  
 
is for Non-High Radiation plant operation/  
 
investigation.
investigation.
S / U
Termination Criteria: Candidate hands the examiner the completed attachment.
* Termination Criteria: Candidate hands the examiner the completed attachment.
RECORD TERMINATION TIME: _________
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED Page 3 of 5 RESULTS OF JPM:
Page 2 of 5
Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard:
Candidate fills out the attached sheet and indicates that the tagout can not be hung due to HPCS-V-4 being in a high radiation area and the RWP is for Non-High Rad operation/investigation.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time  15 Minutes / NA COMMENTS:                              Evaluator's Signature:
Date:
Page 4 of 5 STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia Generating Station is shutdown during outage R18.
Cue:  You have been directed by the Control Room Supervisor to hang tagout D-HPCS-V-102R18-


001. Health Physics has been contacted and directed use of RWP-30001421 for the purpose of  
DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED RESULTS OF JPM:
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Candidate fills out the attached sheet and indicates that the tagout can not be hung due to HPCS-V-4 being in a high radiation area and the RWP is for Non-High Rad operation/investigation.
Overall Evaluation                                  Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for       Validation/Critical      JPM Completion JPM (Initial Box)                        Time                    Time 15 Minutes / NA COMMENTS:
Evaluator's Signature:                                  Date:
Page 3 of 5


hanging tags in the Reactor Building.
STUDENT JPM INFORMATION CARD Initial Conditions:
Review the task and from the information p rovided, fill out the attached sheet indicating your ability (or inability) to perform the task assigned.  
Columbia Generating Station is shutdown during outage R18.
Cue:
You have been directed by the Control Room Supervisor to hang tagout D-HPCS-V-102R18-001.
Health Physics has been contacted and directed use of RWP-30001421 for the purpose of hanging tags in the Reactor Building.
Review the task and from the information provided, fill out the attached sheet indicating your ability (or inability) to perform the task assigned.
Page 4 of 5


Page 5 of 5 I will be able to perform the assigned task (Initial):
I will be able to perform the assigned task (Initial):
I will not be able to perform the assigned task (Initial and Reason):  
I will not be able to perform the assigned task (Initial and Reason):
Page 5 of 5


2006 NRC EXAM - ADMIN JPM RO/SRO #1 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
2006 NRC EXAM - ADMIN JPM RO/SRO #1 PROGRAM TITLE           LICENSED OPERATOR INITIAL TRAINING COURSE TITLE             ADMIN JOB PERFORMANCE MEASURE LESSON TITLE             DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
LESSON LENGTH  
MAXIMUM STUDENTS LESSON LENGTH     .5 HRS                         1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                             Rev. No.
  .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 5/11/06 REVISED BY DATE       TECHNICAL REVIEW BY DATE   INSTRUCTIONAL REVIEW BY DATE   APPROVED BY DATE   Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.  
Simulator Guide PQD Code                                         Rev. No.
JPM PQD Code                                                     Rev. No.
Exam PQD Code                                                   Rev. No.
DIVISION TITLE   Nuclear Training DEPARTMENT       Operations Training PREPARED BY       Ron Hayden                                      DATE   5/11/06 REVISED BY                                                         DATE TECHNICAL REVIEW BY                                               DATE INSTRUCTIONAL REVIEW BY                                           DATE APPROVED BY                                                       DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
Page 1 of  6 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
MINOR REVISION RECORD Minor                   Description                      Affected        Entered Effective    Manager Rev Number                 of Revision                       Pages             By       Date     Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
N/A Setup Instructions:
Make a copy of the current pull sheet from the simulator. Determine where Minimum ECP is and indicate it on copy of pull sheet by placing an '*1' next to the step and at the bottom of the column indicate that a *1 is  
Make a copy of the current pull sheet from the simulator. Determine where Minimum ECP is and indicate it on copy of pull sheet by placing an *1 next to the step and at the bottom of the column indicate that a *1 is Minimum ECP. Ensure it is AFTER step indicated in initial conditions.
'Minimum ECP'. Ensure it is AFTER step indicated in initial conditions.
Have a copy of PPM 3.1.2 startup flowchart available for reference.
Have a copy of PPM 3.1.2 startup flowchart available for reference.
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different  
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
 
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Tools/Equipment: N/A                                   Safety Items: N/A Task Number: RO-0156; SRO-0118                         Validation Time: 16 minutes Prerequisite Training: N/A                             Time Critical: NO PPM  
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
Tools/Equipment:
N/A Safety Items:
N/A Task Number: RO-0156; SRO-0118 Validation Time: 16 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
PPM 3.1.2                                Location: Simulator/Plant/Table Top NUREG 1123 Ref: 2.1.7 3.7/4.4                          Performance Method: Perform Page 1 of 6


PPM 3.1.2 Location: Simulator/Plant/Table Top NUREG 1123 Ref:
DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
2.1.7  3.7/4.4 Performance Method: Perform DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
JPM CHECKLIST PROCEDURE   Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
Page 2 of  6 JPM CHECKLIST PROCEDURE VALIDATION:
INITIAL     A plant startup is in progress. PPM 3.1.2 has been completed as follows: Step L11 has CONDITIONS: been completed, waiting at step L12 ; Step P1 has not yet been completed; Step Q9 has been completed and step Q10 is in progress.
Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: A plant startup is in progress. PPM 3.1.2 has been completed as follows: Step L11 has been completed, waiting at step L12 ; Step P1 has not yet been completed; Step Q9 has been completed and step Q10 is in progress. You are the RO pulling control rods and you note the following indications: Time     0953 Coolant Temp 205°F Control rod   10-47 Control rod position 18 Neutron level 8,000 CPS and rising Period   145 seconds and stable You have been pulling control rods steadily since starting Group 1 of the Pull Sheet.
You are the RO pulling control rods and you note the following indications:
Control rod motion stopped approximately 1 minute ago. INITIATING CUE: Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your next action. When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.  
* Time                     0953
* Coolant Temp             205°F
* Control rod             10-47
* Control rod position     18
* Neutron level           8,000 CPS and rising
* Period                   145 seconds and stable You have been pulling control rods steadily since starting Group 1 of the Pull Sheet.
Control rod motion stopped approximately 1 minute ago.
INITIATING Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your CUE:        next action.
When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.
Page 2 of 6


DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
Page 3 of  6
* Items are Critical Steps Comments                   Element                           Standard                     Sat/Unsat RECORD START TIME: __________
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
SRO Position being                                 Using given information, determines evaluated                                          that the reactor is critical or will be critical before the minimum ECP has been reached.
SRO Position being evaluated Using given information, determines  
Directs RO to (stop control rod withdrawal and to) drive control rods        S/U*
 
in the reverse order until all control rods are fully inserted.
that the reactor is critical or will be critical before the minimum ECP has  
RO position being                                  Using given information, determines evaluated                                          that the reactor is critical or will be critical before the minimum ECP has been reached.
 
Notifies the CRS that he has stopped control rod withdrawal due to reactor        S/U*
been reached.
critical outside ECP.
Directs RO to (stop control rod  
SRO Candidate: To pass the JPM the candidate must state that direction is to be given to the RO to drive control rods in the reverse order until they all are inserted.
 
RO Candidate: To pass the JPM the candidate must state that control rod withdrawal must be stopped and that the CRS must be informed that the reactor is critical prior to the indicated minimum ECP.
withdrawal and to) drive control rods  
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 3 of 6


in the reverse order until all control
rods are fully inserted.
S / U
* RO position being
evaluated Using given information, determines
that the reactor is critical or will be critical before the minimum ECP has
been reached.
Notifies the CRS that he has stopped
control rod withdrawal due to reactor critical outside ECP.
S / U
* SRO Candidate: To pass the JPM the candidate must state that direction is to be given to the RO to drive control rods in the reverse order until they all are inserted. RO Candidate: To pass the JPM the candidate must state that control rod withdrawal must be
stopped and that the CRS must be informed that the reactor is critical prior to the indicated minimum ECP.
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information:  Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
Page 4 of  6 RESULTS OF JPM:
RESULTS OF JPM:
Examinee (Please Print):
Examinee (Please Print): ______________________________________________
______________________________________________
Evaluator (Please Print): ______________________________________________
Evaluator (Please Print):
Task Standard: Candidate determines early criticality and correctly identifies actions for being critical outside of the ECP per PPM 3.1.2.
______________________________________________
Overall Evaluation                                 Exam Code SAT / UNSAT (Circle One)
Task Standard: Candidate determines early criticality and correctly identifies actions for being critical outside of the ECP per PPM 3.1.2.
Verified Procedure #/Rev. Used for         Validation/Critical    JPM Completion JPM (Initial Box)                       Time                   Time 16 Minutes / NA COMMENTS:
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Evaluator's Signature:                                   Date:
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time 16 Minutes / NA COMMENTS:                                     Evaluator's Signature:
Page 4 of 6
Date:
Page 5 of 6 STUDENT JPM INFORMATION CARD Initial Conditions:
A plant startup is in progress. PPM 3.1.2 has been completed as follows: Step L11 has been completed, waiting at step L12 ; Step P1 has not yet been completed; Step Q9 has been completed and step Q10 is in progress.
The following indications are observed: Time    0953 Coolant Temp  205° F Control rod  10-47 Control rod position 18 Neutron level  8,000 CPS and rising Period    145 seconds and stable Control rods have been steadily pulled since starting Group 1 of the Pull


Sheet. Control rod motion stopped approximately 1 minute ago.
STUDENT JPM INFORMATION CARD Initial Conditions:
Cue:     Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your next action.
A plant startup is in progress. PPM 3.1.2 has been completed as follows:
When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.  
Step L11 has been completed, waiting at step L12 ; Step P1 has not yet been completed; Step Q9 has been completed and step Q10 is in progress.
The following indications are observed:
* Time                    0953
* Coolant Temp            205° F
* Control rod            10-47
* Control rod position 18
* Neutron level          8,000 CPS and rising
* Period                  145 seconds and stable Control rods have been steadily pulled since starting Group 1 of the Pull Sheet. Control rod motion stopped approximately 1 minute ago.
Cue:
Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your next action.
When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.
Page 5 of 6


COLUMBIA GENERATING STATION JPM EXAM                       NOVEMBER 2006 Page 6 of 6 NEXT ACTION TO BE TAKEN:            
COLUMBIA GENERATING STATION JPM EXAM NOVEMBER 2006 NEXT ACTION TO BE TAKEN:
BASIS FOR ACTION:
Page 6 of 6


BASIS FOR ACTION:             
2006 NRC EXAM - ADMIN SRO #2 PROGRAM TITLE            LICENSED OPERATOR INITIAL TRAINING COURSE TITLE            ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT MAXIMUM STUDENTS LESSON LENGTH      .5 HRS                              1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                              Rev. No.
Simulator Guide PQD Code                                          Rev. No.
JPM PQD Code                                                      Rev. No.
Exam PQD Code                                                      Rev. No.
DIVISION TITLE    Nuclear Training DEPARTMENT        Operations Training PREPARED BY      Ron Hayden                                        DATE  5/11/06 REVISED BY                                                          DATE TECHNICAL REVIEW BY                                                  DATE INSTRUCTIONAL REVIEW BY                                              DATE APPROVED BY                                                          DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


2006 NRC EXAM - ADMIN SRO #2 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT LESSON LENGTH
DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
  .5 HRS MAXIMUM STUDENTS 1  INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 5/11/06  REVISED BY DATE        TECHNICAL REVIEW BY DATE  INSTRUCTIONAL REVIEW BY DATE  APPROVED BY DATE  Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
N/A Setup Instructions:
 
Ensure candidate has access to a set of Volume One procedures and specifically to PPM 1.3.10B. Have a copy of the Fire Protection System Impairment Notification form ready to give to candidate after impairment is identified.
DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A  FIRE PROTECTION SYSTEM IMPAIRMENT Page 1 of 5 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
Ensure candidate has access to a set of Volume One procedures and specifically to PPM 1.3.10B. Have a copy of the Fire Protection System Impairment Notification form ready to give to candidate after impairment is identified.
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different  
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
 
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Tools/Equipment: N/A                                   Safety Items: N/A Task Number: SRO-0158                                   Validation Time: 20 minutes Prerequisite Training: N/A                             Time Critical: NO PPM  
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
Tools/Equipment:
N/A Safety Items:
N/A Task Number:
SRO-0158 Validation Time: 20 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
PPM 1.3.10B Rev. 13 Location: Simulator/Plant/Table Top NUREG 1123 Ref:
PPM 1.3.10B Rev. 13                     Location: Simulator/Plant/Table Top NUREG 1123 Ref: 2.1.25 2.8/3.1                         Performance Method: Perform Page 1 of 5
2.1.25 2.8/3.1 Performance Method: Perform DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A  FIRE PROTECTION SYSTEM IMPAIRMENT Page 2 of 5 JPM CHECKLIST PROCEDURE VALIDATION:
Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: As the Production SRO, you have just been informed by Plant Inspector that during an inspection of the Active Fire System in the Main Control Room, the 18 Halon system storage tanks (FP-TK-1 thru 18) were found to be 85% of full charge pressure. INITIATING CUE: Based on the report provided determine if compensatory actions are required. Initial the attachment indicating either actions are or are not required. If actions are required indicate (on the attachment) what they are.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Refers to PPM 1.3.10B and notes at least 90% of full charge pressure


is required.
DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT JPM CHECKLIST PROCEDURE          Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION:        listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
S / U Per PPM 1.310B 3.4.3b determines a FPSI permit needs to be issued.
INITIAL            As the Production SRO, you have just been informed by Plant Inspector that during an CONDITIONS:        inspection of the Active Fire System in the Main Control Room, the 18 Halon system storage tanks (FP-TK-1 thru 18) were found to be 85% of full charge pressure.
S / U
INITIATING        Based on the report provided determine if compensatory actions are required. Initial the CUE:              attachment indicating either actions are or are not required. If actions are required indicate (on the attachment) what they are.
* CUE: Once the candidate informs the examiner that a FPSI permit is required to be completed, provide the candidate with a blank form to fill out (Attachment 8.1 of PPM 1.3.10B) and inform him that the Fire Marshall is not on site.
* Items are Critical Steps Comments                    Element                            Standard                    Sat/Unsat RECORD START TIME: __________
The FPSI permit is filled out with the following information: System Impaired: Halon is checked Reason for Impairment: All 18 Halon systems have storage tanks with only 85% of full charge pressure (90% is required) Building/Elevation: Radwaste Building, 501' elevation Compensatory Action Taken: None (Control Room continually manned) Date Impairment Occurred: Today's date is filled in S / U
Refers to PPM 1.3.10B and notes at least 90% of full charge pressure is required.                                                                  S/U Per PPM 1.310B 3.4.3b determines a FPSI permit needs to be issued.           S/U*
* S / U
CUE: Once the candidate informs the examiner that a FPSI permit is required to be completed, provide the candidate with a blank form to fill out (Attachment 8.1 of PPM 1.3.10B) and inform him that the Fire Marshall is not on site.
* S / U
The FPSI permit is filled out with the following information:
* S / U
* System Impaired: Halon is checked                                     S/U*
* S / U
* Reason for Impairment: All 18 Halon systems have storage tanks with only 85% of full charge pressure (90% is required)       S/U*
* Termination Criteria: Student hands the examiner a completed FPSI permit.
* Building/Elevation: Radwaste Building, 501 elevation                 S/U*
* Compensatory Action Taken: None (Control Room continually             S/U*
manned)
* Date Impairment Occurred: Todays date is filled in                   S/U*
Termination Criteria: Student hands the examiner a completed FPSI permit.
RECORD TERMINATION TIME: _________
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A  FIRE PROTECTION SYSTEM IMPAIRMENT Page 3 of 5 RESULTS OF JPM:
Page 2 of 5
Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard:
Candidate identifies that a FPSI perm it is required to be initiated and completes the form with the required information.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time  20 Minutes / NA COMMENTS:                              Evaluator's Signature:
Date:
Page 5 of 6 STUDENT JPM INFORMATION CARD Initial Conditions:
As the Production SRO, you have just been informed by Plant Inspector that during an inspection of the Active Fire System in the Main Control Room, the


18 Halon system storage tanks (FP-TK-1 thru 18) were found to be 85% of full
DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT RESULTS OF JPM:
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Candidate identifies that a FPSI permit is required to be initiated and completes the form with the required information.
Overall Evaluation                                  Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for          Validation/Critical      JPM Completion JPM (Initial Box)                          Time                    Time 20 Minutes / NA COMMENTS:
Evaluator's Signature:                                    Date:
Page 3 of 5


charge pressure.
STUDENT JPM INFORMATION CARD Initial Conditions:
Cue: Based on the report provided determine if compensatory actions are required.
As the Production SRO, you have just been informed by Plant Inspector that during an inspection of the Active Fire System in the Main Control Room, the 18 Halon system storage tanks (FP-TK-1 thru 18) were found to be 85% of full charge pressure.
Initial the attachment indicating either actions are or are not required. If actions are required  
Cue:
Based on the report provided determine if compensatory actions are required.
Initial the attachment indicating either actions are or are not required. If actions are required indicate (on the attachment) what they are.
Page 5 of 6


indicate (on the attachment) what they are.
INITIAL HERE IF NO ACTIONS ARE REQUIRED:
 
Page 6 of 6 INITIAL HERE IF NO ACTIONS ARE REQUIRED:
INITIAL HERE IF ACTIONS ARE REQUIRED:
INITIAL HERE IF ACTIONS ARE REQUIRED:
ACTIONS IF REQUIRED:            
ACTIONS IF REQUIRED:
Page 6 of 6


2006 NRC EXAM - ADMIN JPM SRO #3 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DIV 1 INSTRUMENT OOS/ERROR ON DIVISION 2 TAGOUT THAT WOULD CAUSE FULL SCRAM IF HUNG SUBMITTED FOR APPROVAL LESSON LENGTH  
2006 NRC EXAM - ADMIN JPM SRO #3 PROGRAM TITLE           LICENSED OPERATOR INITIAL TRAINING COURSE TITLE             ADMIN JOB PERFORMANCE MEASURE LESSON TITLE             DIV 1 INSTRUMENT OOS/ERROR ON DIVISION 2 TAGOUT THAT WOULD CAUSE FULL SCRAM IF HUNG SUBMITTED FOR APPROVAL MAXIMUM STUDENTS LESSON LENGTH     .5 HRS                               1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                               Rev. No.
  .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 6/27/06 REVISED BY DATE       TECHNICAL REVIEW BY DATE   INSTRUCTIONAL REVIEW BY DATE   APPROVED BY DATE   Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.  
Simulator Guide PQD Code                                           Rev. No.
JPM PQD Code                                                       Rev. No.
Exam PQD Code                                                       Rev. No.
DIVISION TITLE     Nuclear Training DEPARTMENT         Operations Training PREPARED BY       Ron Hayden                                        DATE   6/27/06 REVISED BY                                                           DATE TECHNICAL REVIEW BY                                                   DATE INSTRUCTIONAL REVIEW BY                                               DATE APPROVED BY                                                           DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


DIVISION 1 INSTRUMENT OOS/DIVISION 2 INSTRUMENT TAG OUT TO SRO FOR APPROVAL Page 1 of 5 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
DIVISION 1 INSTRUMENT OOS/DIVISION 2 INSTRUMENT TAG OUT TO SRO FOR APPROVAL MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
N/A Setup Instructions:
Have appropriate INOP sheets filled out for OOS equipment; Have appropriate Tag out printed for opposite divisional equipment.
Have appropriate INOP sheets filled out for OOS equipment; Have appropriate Tag out printed for opposite divisional equipment.
Candidate needs access to procedures and drawings.
Candidate needs access to procedures and drawings.
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: N/A                                   Safety Items: N/A Task Number: SRO-0464; 0434                             Validation Time: 20 minutes Prerequisite Training: N/A                             Time Critical: NO PPM  
N/A Safety Items:
N/A Task Number:
SRO-0464; 0434 Validation Time: 20 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
PPM 1.3.64                              Location: EOF / Simulator NUREG 1123 Ref: 2.2.13 (3.6/3.8)                        Performance Method: Perform Page 1 of 5


PPM 1.3.64 Location: EOF / Simulator NUREG 1123 Ref:
DIVISION 1 INSTRUMENT OOS/DIVISION 2 INSTRUMENT TAG OUT TO SRO FOR APPROVAL JPM CHECKLIST PROCEDURE         Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION:        listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
2.2.13  (3.6/3.8)
INITIAL           Columbia is operating at 100% power. The following equipment are OOS: TMU-P-1C CONDITIONS:        for motor inspection; APRM A which failed downscale (cause not yet determined);
Performance Method: Perform DIVISION 1 INSTRUMENT OOS/DIVISION 2 INSTRUMENT TAG OUT TO SRO FOR APPROVAL Page 2 of 5 JPM CHECKLIST PROCEDURE VALIDATION:
MS-PS-23A which has a failed relay (RPS-RLY-K6A). The channel has been placed in a trip condition by pulling a fuse as per TSAS 3.3.1.1A. A half scram is present on the RPS A side. You have been given a clearance order to approve.
Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: Columbia is operating at 100% power. The following equipment are OOS: TMU-P-1C for motor inspection; APRM A which failed downscale (cause not yet determined);
INITIATING         Fill out the attachment indicating if you would approve hanging the clearance order or CUE:              if you would not approve hanging the clearance order. Provide written justification to support your decision. When completed, present the filled out attachment to the examiner.
MS-PS-23A which has a failed relay (RPS-RLY-K6A). The channel has been placed in a trip condition by pulling a fuse as per TSAS 3.3.1.1A. A half scram is present on the RPS 'A' side. You have been given a clearance order to approve. INITIATING CUE: Fill out the attachment indicating if you would approve hanging the clearance order or if you would not approve hanging the clearance order. Provide written justification to support your decision. When completed, present the filled out attachment to the examiner.
* Items are Critical Steps Comments               Element                             Standard                       Sat/Unsat RECORD START TIME: __________
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Checks block indicating clearance order is           S/U*
Checks block indicating clearance order is NOT approved. S / U
NOT approved.
* Justifies NOT approving the clearance order due to the fact that E-FUSE-H13P611/AAF7 should not be on the tag out for MS-LS-24D.
Justifies NOT approving the clearance order due to the fact that E-FUSE-H13P611/AAF7 should not be on the tag out for MS-LS-24D.
A Division 1 equipment is OOS (MS-PS-23A) with a half scram already in on the 'A' RPS side. The clearance order mistakenly removes E-FUSE-H13P611/AAF7, which is a Div 2 instrument that would generate a half scram on the 'B' RPS side. Thus, if the  
S/U*
A Division 1 equipment is OOS (MS-PS-23A) with a half scram already in on the A RPS side. The clearance order mistakenly removes E-FUSE-H13P611/AAF7, which is a Div 2 instrument that would generate a half scram on the B RPS side. Thus, if the clearance was hung, it would result in a full scram.
Termination Criteria: Student hands the examiner the completed Attachment.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 2 of 5


clearance was hung, it would result in a full scram. S / U
DIVISION 1 INSTRUMENT OOS/DIVISION 2 INSTRUMENT TAG OUT TO SRO FOR APPROVAL RESULTS OF JPM:
* Termination Criteria: Student hands the examiner the completed Attachment.
Examinee (Please Print): ______________________________________________
RECORD TERMINATION TIME: _________
Evaluator (Please Print): ______________________________________________
Transfer to "Results of JPM" page the following information:  Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Task Standard: Candidate completes the attachment checking the NOT approval block and provides appropriate justification as described in JPM.
DIVISION 1 INSTRUMENT OOS/DIVISION 2 INSTRUMENT TAG OUT TO SRO FOR APPROVAL Page 3 of 5 RESULTS OF JPM:
Overall Evaluation                                     Exam Code SAT / UNSAT (Circle One)
Examinee (Please Print):
Verified Procedure #/Rev. Used for           Validation/Critical      JPM Completion JPM (Initial Box)                           Time                 Time 20 Minutes / NA COMMENTS:
______________________________________________
Evaluator's Signature:                                     Date:
Evaluator (Please Print):
Page 3 of 5
______________________________________________
 
Task Standard: Candidate completes the attachment checking the NOT approval block and provides appropriate justifica tion as described in JPM.
STUDENT JPM INFORMATION CARD Initial Conditions:
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time 20 Minutes / NA COMMENTS:                               Evaluator's Signature:
Date:
Page 4 of 5 STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is operating at 100% power.
Columbia is operating at 100% power.
The following equipment are OOS: TMU-P-1C for motor inspection APRM A which failed downscale (cause not yet determined) MS-PS-23A which has a failed relay (RPS-RLY-K6A). The channel has been placed in a trip condition by pulling a fuse as per TSAS 3.3.1.1A. A half scram is present on the RPS 'A' side.
The following equipment are OOS:
You have been given a clearance order to e ither approve or disapprove the hanging of.
* TMU-P-1C for motor inspection
Cue: Fill out the attachment indicating if you would approve hanging the clearance order or if you would not approve hanging the clearance order.
* APRM A which failed downscale (cause not yet determined)
* MS-PS-23A which has a failed relay (RPS-RLY-K6A). The channel has been placed in a trip condition by pulling a fuse as per TSAS 3.3.1.1A.
A half scram is present on the RPS A side.
You have been given a clearance order to either approve or disapprove the hanging of.
Cue:
Fill out the attachment indicating if you would approve hanging the clearance order or if you would not approve hanging the clearance order.
Provide written justification to support your decision.
Provide written justification to support your decision.
When completed, present the filled out attachment to the examiner.  
When completed, present the filled out attachment to the examiner.
Page 4 of 5


Page 5 of 5 (Place a check mark in the appropriate box and provide justification below)
(Place a check mark in the appropriate box and provide justification below)
Clearance Order Approved Clearance Order NOT Approved JUSTIFICATION:                
Clearance Order Approved                         Clearance Order NOT Approved JUSTIFICATION:
Page 5 of 5


2006 NRC EXAM - ADMIN SRO #4 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS LESSON LENGTH  
2006 NRC EXAM - ADMIN SRO #4 PROGRAM TITLE           LICENSED OPERATOR INITIAL TRAINING COURSE TITLE             ADMIN JOB PERFORMANCE MEASURE LESSON TITLE ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS MAXIMUM STUDENTS LESSON LENGTH     .5 HRS                         1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                             Rev. No.
  .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 10/26/06 REVISED BY DATE       TECHNICAL REVIEW BY DATE   INSTRUCTIONAL REVIEW BY DATE   APPROVED BY DATE   Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.  
Simulator Guide PQD Code                                         Rev. No.
JPM PQD Code                                                     Rev. No.
Exam PQD Code                                                   Rev. No.
DIVISION TITLE   Nuclear Training DEPARTMENT       Operations Training PREPARED BY       Ron Hayden                                      DATE   10/26/06 REVISED BY                                                         DATE TECHNICAL REVIEW BY                                               DATE INSTRUCTIONAL REVIEW BY                                           DATE APPROVED BY                                                       DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS Page 1 of 7 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Setup Instructions:
N/A Setup Instructions:
Candidate needs a calculator and access to ABN-OG.
Candidate needs a calculator and access to ABN-OG.
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: N/A                                   Safety Items: N/A Task Number: SRO-0658                                   Validation Time: 10 minutes Prerequisite Training: N/A                             Time Critical: NO PPM  
N/A Safety Items:
N/A Task Number:
SRO-0658 Validation Time: 10 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
ABN-OG Rev. 1 Location: Simulator/Table Top NUREG 1123 Ref:
ABN-OG Rev. 1                           Location: Simulator/Table Top NUREG 1123 Ref: 271000A2.04 (4.1)                       Performance Method: Perform Page 1 of 7
271000A2.04 (4.1)
Performance Method: Perform ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE  AND DETERMINE ACTIONS Page 2 of 7 JPM CHECKLIST PROCEDURE VALIDATION:
Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: Columbia is operating at full power. Various alarms are locked in due to suspected fuel pin damage. Offgas system parameters are as follows: OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is reading 7721 mr/hr INITIATING CUE: Based on the above information, per ABN-OG, determine what action, if any, should be taken. Fill in the result of your conclusion on the attachment provided.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Refers to ABN-OG and, using bases for step 4.1.2 calculates the following: Main Condenser Gross gamma activity = OG-RR-604 X OG-FR-


620 divided by 1000.
ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS JPM CHECKLIST PROCEDURE        Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION:      listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
S / U  Main Condenser Gross gamma activity = 7721 mr/hr times 43  
INITIAL          Columbia is operating at full power. Various alarms are locked in due to suspected fuel CONDITIONS:      pin damage. Offgas system parameters are as follows:
 
OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is reading 7721 mr/hr INITIATING        Based on the above information, per ABN-OG, determine what action, if any, should be CUE:              taken. Fill in the result of your conclusion on the attachment provided.
SCFM divided by 1000 OR Main Condenser Gross gamma activity = 332.003 mCi/sec S / U  Based on a Main Condenser Gross gamma activity reading of 332 mCi/sec, candidate determines that a power reduction per PPM 3.2.4 to maintain Main Condenser Gross gamma activity LT 332 mCi/sec is required. Additionally, Technical Specification 3.7.5  
* Items are Critical Steps Comments                    Element                            Standard                    Sat/Unsat RECORD START TIME: __________
 
Refers to ABN-OG and, using bases for step 4.1.2 calculates the following:
should be referred to.
S/U Main Condenser Gross gamma activity = OG-RR-604 X OG-FR-620 divided by 1000.
S / U
Main Condenser Gross gamma activity = 7721 mr/hr times 43 SCFM divided by 1000 OR                                                     S/U Main Condenser Gross gamma activity = 332.003 mCi/sec Based on a Main Condenser Gross gamma activity reading of 332 mCi/sec, candidate determines that a power reduction per PPM               S/U*
* Termination Criteria: Student hands the examiner the completed attachment.
3.2.4 to maintain Main Condenser Gross gamma activity LT 332 mCi/sec is required. Additionally, Technical Specification 3.7.5 should be referred to.
Termination Criteria: Student hands the examiner the completed attachment.
RECORD TERMINATION TIME: _________
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE  AND DETERMINE ACTIONS Page 3 of 7 RESULTS OF JPM:
Page 2 of 7
Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard:  Candidate fills out the attachment and has determined that a power reduction per PPM 3.2.4 is required to maintain Main Condenser Gross gamma activity LT 332 mCi/sec and that Technical Specifi cation 3.7.5 should be referred to.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time  10 Minutes / NA COMMENTS:                              Evaluator's Signature:
Date:
Page 5 of 7 STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is operating at full power. Various alarms are locked in due to suspected fuel pin damage. Offgas system parameters are as follows: OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is


reading 7721 mr/hr Cue: Based on the above, per ABN-OG, determine what action, if any, should be taken.
ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS RESULTS OF JPM:
Fill in the result of your conclusion on the
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Candidate fills out the attachment and has determined that a power reduction per PPM 3.2.4 is required to maintain Main Condenser Gross gamma activity LT 332 mCi/sec and that Technical Specification 3.7.5 should be referred to.
Overall Evaluation                                  Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for        Validation/Critical      JPM Completion JPM (Initial Box)                        Time                  Time 10 Minutes / NA COMMENTS:
Evaluator's Signature:                                    Date:
Page 3 of 7


attachment provided.  
STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia is operating at full power.
Various alarms are locked in due to suspected fuel pin damage.
Offgas system parameters are as follows:
OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is reading 7721 mr/hr Cue:
Based on the above, per ABN-OG, determine what action, if any, should be taken.
Fill in the result of your conclusion on the attachment provided.
Page 5 of 7


Page 6 of 7 INITIAL HERE IF NO ACTIONS ARE REQUIRED:
INITIAL HERE IF NO ACTIONS ARE REQUIRED:
INITIAL HERE IF ACTIONS ARE REQUIRED:   INITIALS HERE ACTIONS IF REQUIRED: Reactor downpower per PPM 3.2.4 is required to maintain Main Condenser Gross gamma activity less that 332 mCi/sec.
INITIAL HERE IF ACTIONS ARE REQUIRED:                     INITIALS HERE ACTIONS IF REQUIRED:           Reactor downpower per PPM 3.2.4 is required to maintain Main Condenser Gross gamma activity less that 332 mCi/sec.
Technical Specification 3.7.5 should be referred to.      
Technical Specification 3.7.5 should be referred to.
Page 6 of 7


Page 7 of 7 INITIAL HERE IF NO ACTIONS ARE REQUIRED:
INITIAL HERE IF NO ACTIONS ARE REQUIRED:
INITIAL HERE IF ACTIONS ARE REQUIRED:
INITIAL HERE IF ACTIONS ARE REQUIRED:
ACTIONS IF REQUIRED:            
ACTIONS IF REQUIRED:
Page 7 of 7
 
2006 NRC EXAM - ADMIN JPM SRO #5 PROGRAM TITLE            LICENSED OPERATOR INITIAL TRAINING COURSE TITLE            ADMIN JOB PERFORMANCE MEASURE LESSON TITLE CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)
MAXIMUM STUDENTS LESSON LENGTH      .5 HRS                          1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                                      Rev. No.
Simulator Guide PQD Code                                                  Rev. No.
JPM PQD Code                                                              Rev. No.
Exam PQD Code                                                              Rev. No.
DIVISION TITLE    Nuclear Training DEPARTMENT        Operations Training PREPARED BY        Ron Hayden                                                DATE  8/17/06 REVISED BY                                                                  DATE TECHNICAL REVIEW BY                                                          DATE INSTRUCTIONAL REVIEW BY                                                      DATE APPROVED BY                                                                  DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


2006 NRC EXAM - ADMIN JPM SRO #5 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)
LESSON LENGTH
  .5 HRS MAXIMUM STUDENTS 1  INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 8/17/06  REVISED BY DATE        TECHNICAL REVIEW BY DATE  INSTRUCTIONAL REVIEW BY DATE  APPROVED BY DATE  Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)
CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)
Page 1 of 4 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
2006 NRC Scenario #2 has been completed Setup Instructions:
2006 NRC Scenario #2 has been completed Setup Instructions:
After completion of 2006 NRC Scenario #2 this JPM is to be performed.
After completion of 2006 NRC Scenario #2 this JPM is to be performed.
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: N/A                                   Safety Items: N/A Task Number: SRO-0529, SRO-0629                         Validation Time: 15 minutes Prerequisite Training: N/A                             Time Critical: Yes 30 minutes PPM  
N/A Safety Items:
N/A Task Number:
SRO-0529, SRO-0629 Validation Time: 15 minutes Prerequisite Training:
N/A Time Critical: Yes 30 minutes PPM  


==Reference:==
==Reference:==
PPM 13.1.1                              Location: Simulator NUREG 1123 Ref: 2.4.41 2.3/4.1                          Performance Method: Perform Page 1 of 4


PPM 13.1.1 Location: Simulator NUREG 1123 Ref:
CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)
2.4.41  2.3/4.1 Performance Method: Perform CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)
JPM CHECKLIST PROCEDURE         Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION:        listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
Page 2 of 4 JPM CHECKLIST PROCEDURE VALIDATION:
INITIAL           You have just been relieved as the SRO following the scenario. It is not raining outside.
Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: You have just been relieved as the SRO following the scenario. It is not raining outside.INITIATING  
CONDITIONS:
INITIATING         The Shift Manager has directed you to classify the event and initiate a CNF for the just CUE:              completed scenario. This will be the initial classification for this scenario. Present a completed Classification Notification Form to the examiner. This is a time critical JPM and your time starts now.
* Items are Critical Steps Comments                Element                              Standard                      Sat/Unsat RECORD START TIME: __________
Fills in the following information:
Checks block 1a or 1b (Emergency or Drill)            S/U Checks block 4.a and enters date and time            S/U*
Checks block 5c (Site Area Emergency)                S/U*
Block 7 enters 5 mph for Wind Speed                  S/U Block 7 enters 180 as Wind Direction                  S/U Block 7 checks No for precipitation                  S/U Block 7 enters Stability Class F                      S/U Checks block 8 No Release                            S/U Checks block 9 N/A                                    S/U Checks block 10 NA                                    S/U Checks block 11 No                                    S/U Block 12 enters 2.2.S.1 and adds a                  S/U*
description                                          S/U Checks one block 13 (a, b, or d)
Termination Criteria: Student hands the examiner the completed Classification Notification Form.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 2 of 4


CUE: The Shift Manager has directed you to classify the event and initiate a CNF for the just completed scenario. This will be the initial classification for this scenario. Present a completed Classification Notification Form to the examiner. This is a time critical JPM and your time starts now.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Fills in the following information: Checks block 1a or 1b (Emergency or Drill) Checks block 4.a and enters date and time  Checks block 5c (Site Area Emergency) Block 7 enters 5 mph for Wind Speed Block 7 enters 180 as Wind Direction Block 7 checks No for precipitation Block 7 enters Stability Class F Checks block 8 No Release Checks block 9 N/A Checks block 10 NA Checks block 11 No Block 12 enters 2.2.S.1 and adds a
description Checks one block 13 (a, b, or d)
S / U S / U
* S / U
* S / U S / U S / U S / U S / U S / U S / U S / U S / U
* S / U Termination Criteria: Student hands the examiner the completed Classification Notification Form.
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information:  Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)
CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)
Page 3 of 4 RESULTS OF JPM:
RESULTS OF JPM:
Examinee (Please Print):
Examinee (Please Print): ______________________________________________
______________________________________________
Evaluator (Please Print): ______________________________________________
Evaluator (Please Print):
Task Standard: Candidate completes a Classification Notification Form with the required information.
______________________________________________
Overall Evaluation                                 Exam Code SAT / UNSAT (Circle One)
Task Standard:
Verified Procedure #/Rev. Used for       Validation/Critical    JPM Completion JPM (Initial Box)                       Time                 Time 15 Minutes / 30 minutes COMMENTS:
Candidate completes a Classification Notification Form with the required information.
Evaluator's Signature:                                   Date:
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Page 3 of 4
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time 15 Minutes / 30 minutes COMMENTS:                               Evaluator's Signature:
Date:
Page 4 of 4 STUDENT JPM INFORMATION CARD Initial Conditions:
You have just been relieved as the SRO following the scenario. It is not raining outside. Cue:  The Shift Manager has directed you to classify the event and initiate a Classification Notification Form for the just completed


scenario.
STUDENT JPM INFORMATION CARD Initial Conditions:
You have just been relieved as the SRO following the scenario. It is not raining outside.
Cue:
The Shift Manager has directed you to classify the event and initiate a Classification Notification Form for the just completed scenario.
This will be the initial classification for this scenario.
This will be the initial classification for this scenario.
Present the completed CNF to the examiner.
Present the completed CNF to the examiner.
THIS IS A TIME CRITICAL JPM AND YOUR TIME STARTS NOW  
THIS IS A TIME CRITICAL JPM AND YOUR TIME STARTS NOW Page 4 of 4
 
2006 NRC EXAM - JPM #1 PROGRAM TITLE            INITIAL LICENSED OPERATOR TRAINING COURSE TITLE              JOB PERFORMANCE MEASURE LESSON TITLE              REMOVING HEATER 1A, 1B, AND 1C FROM SERVICE (SIMULATOR)
LESSON LENGTH      .5 HRS    MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                              Rev. No.
Simulator Guide PQD Code                                          Rev. No.
JPM PQD Code                                                      Rev. No.
Exam PQD Code                                                    Rev. No.
DIVISION TITLE    Nuclear Training DEPARTMENT        Operations Training PREPARED BY        Ron Hayden                                      DATE  9/02/06 REVISED BY                                                          DATE TECHNICAL REVIEW BY                                                  DATE INSTRUCTIONAL REVIEW BY                                              DATE APPROVED BY                                                          DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


2006 NRC EXAM - JPM #1 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE REMOVING HEATER 1A, 1B, AND 1C FROM SERVICE (SIMULATOR) LESSON LENGTH 
MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date     Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
.5 HRS  MAXIMUM STUDENTS 1  INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha yd en          DATE 9/02/06  REVISED BY DATE        TECHNICAL REVIEW BY DATE  INSTRUCTIONAL REVIEW BY DATE  APPROVED BY DATE  Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                           JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
A 100% IC Special Setup Instructions:
A 100% IC Special Setup Instructions:
N/A JPM Instructions:
N/A JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Current procedure shall be used by evaluator and student. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.
Current procedure shall be used by evaluator and student. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                   Safety Items: None Task Number: RO-0377                                   Validation Time: 15 Minutes Prerequisite Training: N/A                             Time Critical:   NO PPM  
None Safety Items:
None Task Number:
RO-0377 Validation Time:
15 Minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
PPM 2.2.7 Rev. 38 Location: Simulator NUREG 1123 Ref: 259001A4.03 (2.9/3.0)
PPM 2.2.7 Rev. 38                       Location: Simulator NUREG 1123 Ref: 259001A4.03 (2.9/3.0)                   Performance Method: Perform Page 1 of 5
Performance Method: Perform   Page 1 of 5  


JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.
JPM CHECKLIST PROCEDURE           Regarding procedure copies for evaluator and student, if the procedure revision is VALIDATION          different from that listed on the JPM, verify that the critical task steps are the same.
Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: BPA has requested Columbia reduce power to 60% for economic dispatch. CRO1 is aware of the evolution and is monitoring hotwell level. INITIATING CUE: The CRS has directed you to remove Feedwater Heaters 1A, 1B and 1C from service per PPM 2.2.7 Section 5.2. Notify the CRS when heaters 1A, 1B and 1C have been removed from service.
Evaluator copy may be used for marking step completion, and comments.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
INITIAL             BPA has requested Columbia reduce power to 60% for economic dispatch. CRO1 is CONDITIONS:        aware of the evolution and is monitoring hotwell level.
CUE: Cue response of simulated actions based on procedure and student actions Candidate is given PPM 2.2.7 Section  
INITIATING         The CRS has directed you to remove Feedwater Heaters 1A, 1B and 1C from service CUE:                per PPM 2.2.7 Section 5.2. Notify the CRS when heaters 1A, 1B and 1C have been removed from service.
 
* Items are Critical Steps Comments                   Element                         Standard                           Sat/Unsat RECORD START TIME: __________
5.2 Moves selector over demand to get %  
CUE: Cue response of simulated actions based on procedure and student actions Candidate is given   Moves selector over      Record HD-LIC-1A output signal PPM 2.2.7 Section     demand to get %                                                             S/U 5.2                  open depresses A/M           Places HD-LIC-1A in MANUAL pushbutton to                                                              S/U*
 
display M selects valve           SLOWLY RAISE HD-LIC-1A output demand (far right)      signal to 100%                                     S/U*
open Record HD-LIC-1A output signal S / U depresses A/M pushbutton to
and depresses the up arrow pushbutton OPEN the following:
 
* HV-V-23A Startup Vent (H13-P832)             S/U*
display 'M' Places HD-LIC-1A in MANUAL S / U
* BS-DV-1A BS Dump (H13-P832)                   S/U*
* selects valve demand (far right)
depresses the down       LOWER output signal on HD-LIC-1A                 S/U*
 
arrow pushbutton        to 0% to CLOSE HD-LCV-1A Moves selector over     Record HD-LIC-1B output signal demand to get %                                                             S/U open depresses A/M            Places HD-LIC-1B in MANUAL pushbutton to                                                              S/U*
and depresses the up
display M Page 2 of 5
 
arrow pushbutton SLOWLY RAISE HD-LIC-1A output  
 
signal to 100%
S / U
* OPEN the following: HV-V-23A Startup Vent (H13-P832) BS-DV-1A BS Dump (H13-P832)
S / U
* S / U
* depresses the down  
 
arrow pushbutton LOWER output signal on HD-LIC-1A to 0% to CLOSE HD-LCV-1A S / U
* Moves selector over demand to get %  


open Record HD-LIC-1B output signal S / U  depresses A/M pushbutton to  
selects valve          SLOWLY RAISE HD-LIC-1B output demand (far right)    signal to 100%                            S/U*
 
and depresses the up arrow pushbutton OPEN the following:
display 'M' Places HD-LIC-1B in MANUAL S / U
* HV-V-23E Startup Vent (H13-P832)     S/U*
* Page 2 of  5
* BS-DV-1B BS Dump (H13-P832)           S/U*
 
depresses the down     LOWER output signal on HD-LIC-1B         S/U*
Page 3 of  5 selects valve demand (far right) and depresses the up  
arrow pushbutton      to 0% to CLOSE HD-LCV-1B Moves selector over   Record HD-LIC-1C output signal demand to get %                                                  S/U open depresses A/M         Places HD-LIC-1C in MANUAL pushbutton to                                                    S/U*
 
display M selects valve         SLOWLY RAISE HD-LIC-1C output demand (far right)    signal to 100%                           S/U*
arrow pushbutton SLOWLY RAISE HD-LIC-1B output
and depresses the up arrow pushbutton OPEN the following:
 
* HV-V-23I Startup Vent (H13-P832)     S/U*
signal to 100%
* BS-DV-1C BS Dump (H13-P832)           S/U*
S / U
depresses the down     LOWER output signal on HD-LIC-1C         S/U*
* OPEN the following: HV-V-23E Startup Vent (H13-P832) BS-DV-1B BS Dump (H13-P832)
arrow pushbutton      to 0% to CLOSE HD-LCV-1C Termination Criteria: The operator informs the CRS that heaters 1A, 1B, and 1C have been removed from service.
S / U
* S / U
* depresses the down  
 
arrow pushbutton LOWER output signal on HD-LIC-1B to 0% to CLOSE HD-LCV-1B S / U
* Moves selector over demand to get %
 
open Record HD-LIC-1C output signal S / U depresses A/M pushbutton to
 
display 'M' Places HD-LIC-1C in MANUAL S / U
* selects valve demand (far right)
 
and depresses the up
 
arrow pushbutton SLOWLY RAISE HD-LIC-1C output  
 
signal to 100%
S / U
* OPEN the following: HV-V-23I Startup Vent (H13-P832) BS-DV-1C BS Dump (H13-P832)
S / U
* S / U
* depresses the down  
 
arrow pushbutton LOWER output signal on HD-LIC-1C to 0% to CLOSE HD-LCV-1C S / U
* Termination Criteria: The operator informs the CRS that heaters 1A, 1B, and 1C have been removed from service.
RECORD TERMINATION TIME: _________
RECORD TERMINATION TIME: _________
Transfer the following information to the "Results of JPM" page: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.
Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.
Page 4 of 5 RESULTS OF JPM: REMOVE HEATERS 1A, 1B,  AND 1C FROM SERVICE Examinee (Please Print):
Page 3 of 5
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard:
Heaters 1A, 1B, and 1C have been removed from service per PPM 2.2.7.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial box) Validation/Critical Time JPM Completion Time  15 Minutes / NA COMMENTS:                                      Evaluator's Signature:
Date: 


STUDENT JPM INFORMATION CARD Initial Conditions:   BPA has requested Columbia reduce power to 60% for economic dispatch.
RESULTS OF JPM:
Cue: The CRS has directed you to remove Feedwater Heaters 1A, 1B and 1C from service per PPM 2.2.7  
REMOVE HEATERS 1A, 1B, AND 1C FROM SERVICE Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Heaters 1A, 1B, and 1C have been removed from service per PPM 2.2.7.
Overall Evaluation                                Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for        Validation/Critical    JPM Completion JPM (Initial box)                      Time                Time 15 Minutes / NA COMMENTS:
Evaluator's Signature:                                  Date:
Page 4 of 5


Section 5.2.
STUDENT JPM INFORMATION CARD Initial Conditions:
BPA has requested Columbia reduce power to 60% for economic dispatch.
Cue:
The CRS has directed you to remove Feedwater Heaters 1A, 1B and 1C from service per PPM 2.2.7 Section 5.2.
Notify the CRS when heaters 1A, 1B and 1C have been removed from service.
Notify the CRS when heaters 1A, 1B and 1C have been removed from service.
Page 5 of  5
Page 5 of 5
 
2006 NRC EXAM - JPM #2 PROGRAM TITLE            INITIAL LICENSED OPERATOR TRAINING COURSE TITLE            JOB PERFORMANCE MEASURE LESSON TITLE            RESTORE RPS A FROM ALTERNATE POWER SOURCE (SIMULATOR)
MAXIMUM STUDENTS LESSON LENGTH      .5 HRS                          1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                                  Rev. No.
Simulator Guide PQD Code                                              Rev. No.
JPM PQD Code                                                          Rev. No.
Exam PQD Code                                                        Rev. No.
DIVISION TITLE    Nuclear Training DEPARTMENT        Operations Training PREPARED BY      Ron Hayden                                            DATE 9/02/06 REVISED BY                                                              DATE TECHNICAL REVIEW BY                                                      DATE INSTRUCTIONAL REVIEW BY                                                  DATE APPROVED BY                                                              DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use


2006 NRC EXAM - JPM #2 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RESTORE RPS A FROM ALTERNATE POWER SOURCE (SIMULATOR)
RESTORE RPS A FROM ALTERNATE POWER SOURCE MINOR REVISION RECORD Minor                       Description                      Affected      Entered  Effective  Manager Rev Number                   of Revision                       Pages           By       Date     Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
LESSON LENGTH
  .5 HRS MAXIMUM STUDENTS 1  INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 9/02/06  REVISED BY DATE        TECHNICAL REVIEW BY DATE  INSTRUCTIONAL REVIEW BY DATE  APPROVED BY DATE  Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use RESTORE RPS A FROM ALTERNATE POWER SOURCE Page 1 of 7 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
Any IC with a normal electrical lineup - all load centers energized Ensure AR-EX-1B is in service Special Setup Instructions:
Any IC with a normal electrical lineup - all load centers energized Ensure AR-EX-1B is in service Special Setup Instructions:
Open RPS EPA BKR 3A, acknowledge all annunciators, and allow plant to stabilize.
Open RPS EPA BKR 3A, acknowledge all annunciators, and allow plant to stabilize.
JPM Instructions:
JPM Instructions:
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                     Safety Items: None Task Number: RO-0248                                       Validation Time: 15 minutes Prerequisite Training: N/A                                 Time Critical: NO PPM  
None Safety Items:
None Task Number:
RO-0248 Validation Time: 15 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
ABN-RPS Rev. 4 Location: SIMULATOR NUREG 1123 Ref: 212000 A4.14 (3.8/3.8)
ABN-RPS Rev. 4                             Location: SIMULATOR NUREG 1123 Ref: 212000 A4.14 (3.8/3.8)                     Performance Method: PERFORM Page 1 of 7
Performance Method:
 
PERFORM RESTORE RPS A FROM ALTERNATE POWER SOURCE Page 2 of 7 JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.
RESTORE RPS A FROM ALTERNATE POWER SOURCE JPM CHECKLIST PROCEDURE           Regarding procedure copies for evaluator and student, if the procedure revision is VALIDATION          different from that listed on the JPM, verify that the critical task steps are the same.
Evaluator copy may be used for marking step completion, and comments.
Evaluator copy may be used for marking step completion, and comments.
INITIAL CONDITIONS: A loss of RPS 'A' occurred 20 minutes ago. All maintenance and surveillance testing has been stopped. Investigation revealed a failure of the 'A' RPS MG set motor. INITIATING CUE:
INITIAL             A loss of RPS A occurred 20 minutes ago. All maintenance and surveillance CONDITIONS:        testing has been stopped. Investigation revealed a failure of the A RPS MG set motor.
The CRS has directed you to transfer 'A' RPS to its Alternate power supply by performing steps 4.1 through 4.8 of ABN-RPS. Inform the CRS when the subsequent actions for ABN-RPS have been completed and 'A' RPS has been restored.
INITIATING CUE: The CRS has directed you to transfer A RPS to its Alternate power supply by performing steps 4.1 through 4.8 of ABN-RPS. Inform the CRS when the subsequent actions for ABN-RPS have been completed and A RPS has been restored.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
* Items are Critical Steps Comments                 Element                             Standard                     Sat/Unsat RECORD START TIME: __________
Candidate is given  
Candidate is given                                 If power is available to RWCU-V-              S/U*
ABN-RPS                                            104 (Cleanup System Bypass), then THROTTLE OPEN RWCU-V-104 If alternate Gland Exhaust (AR-EX-1A/B) is required then start the alternate Gland Exhauster and place              N/A the tripped Gland Exhauster in OFF.
Otherwise N/A If the alternate Mechanical Vacuum Pump (AR-P-1A/B) is requires then                N/A start the alternate Mechanical Vacuum Pump. Otherwise N/A Page 2 of 7


ABN-RPS  If power is available to RWCU-V-104 (Cleanup System Bypass), then THROTTLE OPEN RWCU-V-104 S / U
RESTORE RPS A FROM ALTERNATE POWER SOURCE ENSURE automatic actions have occurred. Verifies:
* If alternate Gland Exhaust (AR-EX-
* Half Scram                        S/U
* The following valves close:
o RRC-V-20 o FDR-V-4 o EDR-V-20 o RWCU-V-4 o RHR-V-8 o RHR-V-40 o RHR-V-75A and 75B o RHR-V-23 o RHR-V-53A and 53B o MS-V-67A-D o MS-V-19
* RC-1 trips
* AR-EX-1A trips
* AR-P-1A trips
* Refers to Attachment 7.1 for list of annunciation CUE: When Attachment 7.1 is referenced, inform candidate that another operator has verified annunciation per Attachment 7.1 and no discrepancies were noted.
IF the condition of the RPS MG set is known to be operable, then restart the RPS MG set and repower the bus        N/A per PPM 2.7.6. Otherwise N/A If the condition of the RPS MG set is uncertain then repower RPS A or B from H13-P610 as follows:
* Check power available from        S/U the RPS Alternate Power Supply, MC-6B, by observing the Alternate Feed white light illuminated.
* Place the RPS power source selector switch in the position S/U*
(ALT A) to be powered from the Alternate Supply Page 3 of 7


1A/B) is required then start the  
RESTORE RPS A FROM ALTERNATE POWER SOURCE When RPS power has been restored stabilized, then perform the following:
If restoring RPS A then perform the following:
Depresses the two Rx
* Reset the Half Scram at H13-      S/U*
Scram Logic A1/B1 and                P603 A2/B2 reset P/Bs on P603
* Reset Main Steam Line Rad Monitor alarms at H13-P606 o MS-RIS-610A              S/U*
o MS-RIS-610C              S/U*
Depress the following pushbuttons at H13-P601:
o Isolation logic A & B reset P/Bs      S/U*
o Isolation logic C & D reset P/Bs      S/U*
Return RWCU to service per SOP-          S/U RWCU-START CUE: Inform the candidate that another operator is placing RWCU into service and to continue with ABN-RPS.
Reset RC-1 by depressing WMA-          S/U*
RMS-FAZ/3AXY pushbutton.
If RHR SDC was in service then           N/A refer to ABN-RHR-SDC. Otherwise N/A Open RRC-V-20                          S/U*
Open EDR-V-20                          S/U*
Candidate may                                  If FDR-V-3 and FDR-V-4 have been voice concern for                              isolated for LT 8 hours, then open the overflowing sump                              following:
FDR-V-3 already opened          o FDR-V-3                            S/U S/U*
o FDR-V-4 Page 4 of 7


alternate Gland Exhauster and place the tripped Gland Exhauster in OFF. Otherwise N/A N/A   If the alternate Mechanical Vacuum Pump (AR-P-1A/B) is requires then
RESTORE RPS A FROM ALTERNATE POWER SOURCE If FDR-V-3 and FDR-V-4 have been        N/A isolated for GT 8 hours..
Otherwise N/A May direct communication    Refer to TS 3.3.1.1 for RPS and LCS      S/U to CRS                      1.4.1 for coolant chemistry control.
May direct communication    Determine cause and correct              S/U to CRS May direct communication    Evaluate resumption of maintenance      S/U to CRS                      and surveillance activities Termination Criteria: Candidate informs CRS that ABN-RPS has been completed for the restoration of RPS A.
RECORD TERMINATION TIME: _________
Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.
Page 5 of 7


start the alternate Mechanical Vacuum Pump. Otherwise N/A N/A RESTORE RPS A FROM ALTERNATE POWER SOURCE Page 3 of 7 ENSURE automatic actions have occurred. Verifies: Half Scram The following valves close:
RESULTS OF JPM:
o RRC-V-20 o FDR-V-4 o EDR-V-20 o RWCU-V-4 o RHR-V-8 o RHR-V-40 o RHR-V-75A and 75B o RHR-V-23 o RHR-V-53A and 53B o MS-V-67A-D o MS-V-19 RC-1 trips AR-EX-1A trips AR-P-1A trips Refers to Attachment 7.1 for list of annunciation S / U CUE: When Attachment 7.1 is referenced, inform candidate that another operator has verified annunciation per Attachment 7.1 and no discrepancies were noted.
RESTORE RPS A FROM ALTERNATE POWER SOURCE Examinee (Please Print): ______________________________________________
IF the condition of the RPS MG set is known to be operable, then restart
Evaluator (Please Print): ______________________________________________
Task Standard: The subsequent actions for ABN-RPS have been completed and RPS A has been re-powered from Alternate Power Supply.
Overall Evaluation                                  Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for         Validation/Critical      JPM Completion JPM (Initial Box)                        Time                Time 15 Minutes / NA COMMENTS:
Evaluator's Signature:                                  Date:
Page 6 of 7


the RPS MG set and repower the bus per PPM 2.7.6. Otherwise N/A N/A  If the condition of the RPS MG set is uncertain then repower RPS A or B from H13-P610 as follows: Check power available from the RPS Alternate Power Supply, MC-6B, by observing the Alternate Feed white light illuminated. Place the RPS power source selector switch in the position (ALT A) to be powered from the Alternate Supply S / U  S / U
STUDENT JPM INFORMATION CARD Initial Conditions:
* RESTORE RPS A FROM ALTERNATE POWER SOURCE Page 4 of 7 When RPS power has been restored stabilized, then perform the
A loss of RPS A occurred 20 minutes ago.
 
All maintenance and surveillance testing has been stopped.
following: If restoring RPS A then perform the following:
Investigation revealed a failure of the A RPS MG set motor.
Depresses the two Rx Scram Logic A1/B1 and A2/B2 reset P/B's on P603 Reset the Half Scram at H13-P603 S / U
Cue:
* Reset Main Steam Line Rad Monitor alarms at H13-P606 o MS-RIS-610A o MS-RIS-610C S / U
The CRS has directed you to transfer A RPS to its Alternate power supply by performing steps 4.1 through 4.8 of ABN-RPS.
* S / U
Inform the CRS when the subsequent actions for ABN-RPS have been completed and A RPS has been restored.
* Depress the following pushbuttons at
Page 7 of 7
 
H13-P601:
o Isolation logic A & B reset P/Bs o Isolation logic C & D reset P/Bs S / U
* S / U
* Return RWCU to service per SOP-RWCU-START S / U CUE: Inform the candidate that another operator is placing RWCU into service and to continue with ABN-RPS. Reset RC-1 by depressing WMA-RMS-FAZ/3AXY pushbutton.
S / U
* If RHR SDC was in service then refer to ABN-RHR-SDC. Otherwise N/A N/A  Open RRC-V-20 S / U
* Open EDR-V-20 S / U
* Candidate may voice concern for overflowing sump FDR-V-3 already opened If FDR-V-3 and FDR-V-4 have been isolated for LT 8 hours, then open the
 
following:
o FDR-V-3 o FDR-V-4    S / U S / U
* RESTORE RPS A FROM ALTERNATE POWER SOURCE Page 5 of 7 If FDR-V-3 and FDR-V-4 have been isolated for GT 8 hours-.. Otherwise N/A N/A  May direct communication to CRS Refer to TS 3.3.1.1 for RPS and LCS 1.4.1 for coolant chemistry control.
S / U  May direct communication
 
to CRS Determine cause and correct S / U  May direct communication
 
to CRS Evaluate resumption of maintenance
 
and surveillance activities S / U Termination Criteria: Candidate informs CRS that ABN-RPS has been completed for the restoration of RPS A. RECORD TERMINATION TIME: _________
Transfer the following information to the "Results of JPM" page: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.
 
Page 6 of 7 RESULTS OF JPM:
RESTORE RPS A FROM ALTERNATE POWER SOURCE Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: The subsequent actions for ABN-RPS have been completed and RPS A has been re-powered from Alternate Power Supply.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time  15 Minutes / NA COMMENTS:                                Evaluator's Signature:
Date:
Page 7 of 7 STUDENT JPM INFORMATION CARD Initial Conditions:
A loss of RPS 'A' occurred 20 minutes ago.
All maintenance and surveillance testing has been stopped. Investigation revealed a failure of the 'A' RPS MG set motor.
Cue: The CRS has directed you to transfer 'A' RPS to its Alternate power supply by performing steps 4.1 through 4.8 of ABN-RPS.
Inform the CRS when the subsequent actions for ABN-RPS have been completed and 'A'


RPS has been restored.  
2006 NRC EXAM - JPM #3 PROGRAM TITLE            INITIAL LICENSED OPERATOR TRAINING COURSE TITLE              JOB PERFORMANCE MEASURE LESSON TITLE              TRANSFER SL-21 FROM SL-11 to SM-2 (SIMULATOR)
LESSON LENGTH      .5 HRS    MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                                Rev. No.
Simulator Guide PQD Code                                            Rev. No.
JPM PQD Code                                                        Rev. No.
Exam PQD Code                                                        Rev. No.
DIVISION TITLE    Nuclear Training DEPARTMENT        Operations Training PREPARED BY        Ron Hayden                                          DATE  09/02/06 REVISED BY                                                              DATE TECHNICAL REVIEW BY                                                    DATE INSTRUCTIONAL REVIEW BY                                                DATE APPROVED BY                                                            DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


2006 NRC EXAM - JPM #3 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE TRANSFER SL-21 FROM SL-11 to SM-2 (SIMULATOR)
MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
LESSON LENGTH
.5 HRS  MAXIMUM STUDENTS 1  INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 09/02/06  REVISED BY DATE        TECHNICAL REVIEW BY DATE  INSTRUCTIONAL REVIEW BY DATE  APPROVED BY DATE  Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
Any IC where SM-2 is powered and supplying power to SL-21.
Any IC where SM-2 is powered and supplying power to SL-21.
Special Setup Instructions:
Special Setup Instructions:
Line 678: Line 648:
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                     Safety Items: None Task Number: RO-0390                                       Validation Time: 10 Minutes Prerequisite Training: N/A                                 Time Critical: No PPM  
None Safety Items: None Task Number:
RO-0390 Validation Time:
10 Minutes Prerequisite Training: N/A Time Critical:
No PPM  


==Reference:==
==Reference:==
PPM 2.7.1B Section 5.6 Rev. 24 Location: Simulator NUREG 1123 Ref: 262001 A4.01 (3.4/3.7)
PPM 2.7.1B Section 5.6 Rev. 24             Location: Simulator NUREG 1123 Ref: 262001 A4.01 (3.4/3.7)                     Performance Method: Perform Page 1 of 5
Performance Method: Perform   Page 1 of 5
 
JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: SL-21 is currently being powered from SL-11. INITIATING CUE: The CRS has directed you to transfer SL-21 from SL-11 to SM-2 by performing a break before make transfer. Inform the CRS when SL-21 is being powered from 
 
SM-2.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
CUE:  Cue response of simulated actions based on procedure and student actions Notifies Radwaste that they will momentarily lose power to G33-
 
P0026  S / U Candidate should
 
refer to PPM
 
2.7.1B Section 5.6, and when proper
 
procedure section
 
is found, given his
 
copy of the PPM Verify CB-2/21 while LOCKOUT CIRCUIT AVAIL light is illuminated S / U  If CB-2/21 is closed THEN
 
verify CB-2/21 red light illuminated. Otherwise N/A S / U  If CB-2/21 is not closed THEN perform the following: Otherwise
 
N/A  N/A  Verify CB-21/2 green tripped light is illuminated and the green
 
position flag is being displayed in
 
the CB-21/2 control switch
 
window  S / U  2 Hand Operation OK Place and Hold the control switch for CB-21/2 in the close position S / U
* 2 Hand Operation OK Place CB-21/11 control switch to the Trip position S / U
* Verify CB-21/11 green tripped light illuminates S / U  Page 2 of 5  


JPM CHECKLIST PROCEDURE            Procedure copies for evaluator and student, if procedure revision is different from VALIDATION          that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL              SL-21 is currently being powered from SL-11.
CONDITIONS:
INITIATING CUE:      The CRS has directed you to transfer SL-21 from SL-11 to SM-2 by performing a break before make transfer. Inform the CRS when SL-21 is being powered from SM-2.
* Items are Critical Steps Comments                Element                            Standard                Sat/Unsat RECORD START TIME: __________
CUE: Cue response of simulated actions based on procedure and student actions Candidate should                                    Notifies Radwaste that they will refer to PPM                                        momentarily lose power to G33-          S/U 2.7.1B Section 5.6,                                P0026 and when proper procedure section                                  Verify CB-2/21 while LOCKOUT CIRCUIT AVAIL                    S/U is found, given his copy of the PPM                                    light is illuminated If CB-2/21 is closed THEN verify CB-2/21 red light                S/U illuminated. Otherwise N/A If CB-2/21 is not closed THEN perform the following: Otherwise          N/A N/A Verify CB-21/2 green tripped light is illuminated and the green      S/U position flag is being displayed in the CB-21/2 control switch window 2 Hand Operation OK            Place and Hold the control switch for CB-21/2 in the close position      S/U*
2 Hand Operation OK            Place CB-21/11 control switch to the Trip position                      S/U*
Verify CB-21/11 green tripped light illuminates                        S/U Page 2 of 5
* Items are Critical Steps Comments                Element                        Standard                Sat/Unsat Verify CB-21/11 red closed light extinguishes                            S/U Verify CB-2/21 green tripped light extinguishes                      S/U Verify CB-2/21 red closed light illuminates                            S/U Release the control switch for CB-21/2                                S/U Termination Criteria: Candidate informs the CRS that SL-21 is being supplied from SM-2.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 3 of 5
Page 3 of 5
* Items are Critical StepsComments Element Standard Sat/Unsat Verify CB-21/11 red closed light extinguishes S / U  Verify CB-2/21 green tripped


light extinguishes S / U  Verify CB-2/21 red closed light illuminates S / U  Release the control switch for  
RESULTS OF JPM:
TRANSFER SL-21 FROM SL-11 to SM-2 Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: SL-21 power supply is transferred from SL-11 to SM-2 per PPM 2.7.1B.
Overall Evaluation                                    Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for             Validation/Critical      JPM Completion JPM                                    Time                    Time 10 Minutes / NA COMMENTS:
Evaluator's Signature:                                      Date:
Page 4 of 5


CB-21/2  S / U Termination Criteria: Candidate informs the CRS that SL-21 is being supplied from SM-2.
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information:  Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 4 of 5 RESULTS OF JPM:
TRANSFER SL-21 FROM SL-11 to SM-2 Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: SL-21 power supply is transferred from SL-11 to SM-2 per PPM 2.7.1B.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM Validation/Critical Time JPM Completion Time  10 Minutes / NA COMMENTS:                                        Evaluator's Signature:
Date:
STUDENT JPM INFORMATION CARD Initial Conditions:
STUDENT JPM INFORMATION CARD Initial Conditions:
SL-21 is currently being powered from SL-11.
SL-21 is currently being powered from SL-11.
Cue: The CRS has directed you to transfer SL-21 from SL-11 to SM-2 b y performin g a break before make transfer.
Cue:
Inform the CRS when SL-21 is bein g powered from   SM-2.
The CRS has directed you to transfer SL-21 from SL-11 to SM-2 by performing a break before make transfer.
Page 5 of 5  
Inform the CRS when SL-21 is being powered from SM-2.
Page 5 of 5


2006 NRC EXAM - JPM #4 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE MANUALLY INITIATES CONTAINMENT ISOLATIONS FOR THE TIP SYSTEM (SIMULATOR) (ALT PATH)
2006 NRC EXAM - JPM #4 PROGRAM TITLE             INITIAL LICENSED OPERATOR TRAINING COURSE TITLE             JOB PERFORMANCE MEASURE MANUALLY INITIATES CONTAINMENT ISOLATIONS FOR THE TIP LESSON TITLE              SYSTEM (SIMULATOR) (ALT PATH)
LESSON LENGTH  
LESSON LENGTH     .5 HRS   MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                             Rev. No.
.5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 05/18/06 REVISED BY DATE         TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
Simulator Guide PQD Code                                         Rev. No.
MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
JPM PQD Code                                                     Rev. No.
Exam PQD Code                                                   Rev. No.
DIVISION TITLE     Nuclear Training DEPARTMENT         Operations Training PREPARED BY       Ron Hayden                                      DATE 05/18/06 REVISED BY                                                         DATE TECHNICAL REVIEW BY                                                 DATE INSTRUCTIONAL REVIEW BY                                             DATE APPROVED BY                                                         DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
 
MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
Reset to IC-14.
Reset to IC-14.
Ensure GDS screen on P601 is displayed. Fail TIP-V-5 open. Trip both RFW pumps. After scram place mode switch in shutdown.
Ensure GDS screen on P601 is displayed.
Fail TIP-V-5 open.
Trip both RFW pumps.
After scram place mode switch in shutdown.
Special Setup Instructions:
Special Setup Instructions:
None JPM Instructions:
None JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                     Safety Items: None Task Number: RO-0314                                       Validation Time: 15 Minutes Prerequisite Training: N/A                                 Time Critical: No PPM  
None Safety Items: None Task Number:
RO-0314 Validation Time:
15 Minutes Prerequisite Training: N/A Time Critical:
No PPM  


==Reference:==
==Reference:==
ABN-TIPS Rev. 0 Location: Simulator NUREG 1123 Ref: 223002 A2.03 A3.01 A3.02 Performance Method: Perform   Page 1 of 6  
ABN-TIPS Rev. 0                             Location: Simulator NUREG 1123 Ref: 223002 A2.03 A3.01 A3.02                   Performance Method: Perform Page 1 of 6


JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: The plant was operating at full power when both RFW pumps tripped. RPV level dropped to less than -50 inches. INITIATING CUE: The CRS has directed you to ensure all isolations for -50 inches RPV level signal per EOP 5.1.1. Another licensed operator will verify initiations and DG starts.
JPM CHECKLIST PROCEDURE             Procedure copies for evaluator and student, if procedure revision is different from VALIDATION            that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL               The plant was operating at full power when both RFW pumps tripped. RPV level CONDITIONS:            dropped to less than -50 inches.
INITIATING CUE:       The CRS has directed you to ensure all isolations for -50 inches RPV level signal per EOP 5.1.1. Another licensed operator will verify initiations and DG starts.
Inform the CRS when EOP isolations for -50 inches have been verified.
Inform the CRS when EOP isolations for -50 inches have been verified.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
* Items are Critical Steps Comments                   Element                           Standard                 Sat/Unsat RECORD START TIME: __________
Candidate is not given any reference material to start this JPM. Candidate may refer to GDS screen or quick card to determine required isolations. GDS will indicate TIP-V-5 is opened in addition to the valve lights on P601.
Candidate is not given any reference material to start this JPM.
Identifies all isolations are not complete Refers to GDS screen or quick card and notes TIP-V- 5 is not closed and informs the CRS S / U
Candidate may refer to GDS screen or quick card to determine required isolations. GDS will indicate TIP-V-5 is opened in addition to the valve lights on P601.
* CUE: When informed that TIP-V- 5 is opened, inform the candidate "You are directed to take the necessary actions to isolate the penetration per ABN-TIPS" and hand the candidate his procedure copy.
Identifies all isolations are   Refers to GDS screen or quick not complete                    card and notes TIP-V- 5 is not         S/U*
If necessary, THEN CLOSE the following TIP Drive Unit Breakers: Otherwise N/A N/A CUE: When step is read, inform candidate that the TIP Drive Unit Breakers are all closed The Manual Drive switch is labeled MANUAL Verify the following for each Drive Control Unit (A through E)
closed and informs the CRS CUE: When informed that TIP-V- 5 is opened, inform the candidate You are directed to take the necessary actions to isolate the penetration per ABN-TIPS and hand the candidate his procedure copy.
(H13-P607): The Mode switch is in the OFF position The Manual Drive switch is in the OFF position The Manual Valve Control switch is in the CLOSED  
If necessary, THEN CLOSE the following TIP Drive Unit                 N/A Breakers: Otherwise N/A CUE: When step is read, inform candidate that the TIP Drive Unit Breakers are all closed Verify the following for each Drive Control Unit (A through E)
(H13-P607):
* The Mode switch is in the         S/U OFF position The Manual Drive switch
* The Manual Drive switch is labeled MANUAL                                                        S/U is in the OFF position
* The Manual Valve Control switch is in the CLOSED         S/U position Place the MODE switch to the MAN position for each Drive            S/U*
Control Unit (A through E)
Page 2 of 6
* Items are Critical Steps Comments                Element                          Standard                  Sat/Unsat Verify the following:
* The READY light is                  S/U illuminated
* The IN-SHIELD light is S/U illuminated. (If any detectors are NOT IN-SHIELD, proceed to the following step)
CUE: Inform candidate that the detector position is at the posted IN-SHIED location
* The detector position is at the posted IN-SHIELD              S/U location, + 1 May/May not refer CRS to      REFER to Technical applicable Tech Spec          Specification 3.6.1.3                      S/U If any detector is NOT IN-SHIELD, THEN RETRACT each affected detector to the IN-                N/A SHIELD position as follows (otherwise N/A):
* PLACE the Manual Drive Control switch on the appropriate Drive Control Unit to the REV position
* VERIFY the IN-SHIELD light is illuminated If the detector is still not IN-SHIELD, THEN CONSIDER MANUALLY CRANKING the                      N/A affected detector to the IN-SHIELD position from the Drive Mechanism per PPM 10.27.74.
Otherwise N/A Page 3 of 6
* Items are Critical Steps Comments                  Element                            Standard                Sat/Unsat If the detector is still not IN-SHIELD OR the isolation valve has failed to close, THEN ISOLATE the affected TIP line(s) as follows: Otherwise N/A
* Obtain permission from the          S/U CRS/Shift Manager to fire the applicable squib valve(s)
CUE: IF asked, the CRS/Shift Manager gives permission to fire the squib valve (Candidate may already assume he has permission from last communication/cue).
Obtains key #35 and          PLACE the key lock valve Isolates TIP shear valve      control switch on the appropriate (TIP-V-5).                    valve control drawer to the FIRE position for the channel that did        S/U*
not isolate VERIFY the applicable squib Monitor lights are illuminated            S/U VERIFY TIP SHEAR VLV CLOSED OR CKT CONTINUITY LOSS                            S/U annunciator (H13-P601.A12-5.1) is illuminated VERIFY the green ALL VALVES SHUT light at the TIP                    S/U*
ISOLATION status display on H13-P601 is illuminated Termination Criteria: Student informs CRS that all isolations for -50 inches have been verified and that the squib valve was fired to isolate TIP-V-5 penetration.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 4 of 6


position    S / U  S / U  S / U  Place the MODE switch to the
RESULTS OF JPM:
MANUALLY INITIATES CONTAINMENT ISOLATIONS FOR THE TIP SYSTEM Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Verifies isolations for -50 inch RPV level signal and isolates TIP-V-5 line that did not isolate.
Overall Evaluation                                    Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for            Validation/Critical          JPM Completion JPM                                    Time                        Time 15 Minutes / NA COMMENTS:
Evaluator's Signature:                                        Date:
Page 5 of 6


MAN position for each Drive Control Unit (A through E)
S / U
* Page 2 of 6
Page 3 of 6
* Items are Critical StepsComments Element Standard Sat/Unsat Verify the following: The READY light is illuminated The IN-SHIELD light is illuminated. (If any detectors are NOT IN-
SHIELD, proceed to the following step)
S / U  S / U  CUE:  Inform candidate that the detector position is at the posted IN-SHIED location The detector position is at the posted IN-SHIELD
location, + 1"  S / U  May/May not refer CRS to applicable Tech Spec REFER to Technical
Specification 3.6.1.3 S / U  If any detector is NOT IN-SHIELD, THEN RETRACT each affected detector to the IN-
SHIELD position as follows (otherwise N/A
): PLACE the Manual Drive Control switch on the appropriate Drive Control Unit to the REV position VERIFY the IN-SHIELD light is illuminated N/A  If the detector is still not IN-SHIELD, THEN CONSIDER MANUALLY CRANKING the affected detector to the IN-SHIELD position from the Drive Mechanism per PPM 10.27.74. Otherwise N/A N/A Page 4 of 6
* Items are Critical StepsComments Element Standard Sat/Unsat If the detector is still not IN-SHIELD OR the isolation valve has failed to close , THEN ISOLATE the affected TIP line(s) as follows: Otherwise
N/A Obtain permission from the CRS/Shift Manager to
fire the applicable squib
valve(s)        S / U CUE: IF asked, the CRS/Shift Manager gives permission to fire the squib valve (Candidate may already assume he has permission from last communication/cue).
Obtains key #35 and Isolates TIP shear valve (TIP-V-5).
PLACE the key lock valve
control switch on the appropriate
valve control drawer to the FIRE
position for the channel that did
not isolate S / U
* VERIFY the applicable squib Monitor lights are illuminated S / U  VERIFY TIP SHEAR VLV CLOSED OR CKT CONTINUITY LOSS
annunciator (H13-P601.A12-5.1) is illuminated S / U  VERIFY the green ALL VALVES SHUT light at the TIP ISOLATION status display on H13-P601 is illuminated S / U
* Termination Criteria: Student informs CRS that all isolations for -50 inches have been verified and that the squib valve was fired to isolate TIP-V-5 penetration.
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information:  Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 5 of 6 RESULTS OF JPM:
MANUALLY INITIATES CONTAINMENT ISOLATIONS FOR THE TIP SYSTEM Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: Verifies isolations for -50 inch RPV level signal and isolates TIP-V-5 line that did not isolate. Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM Validation/Critical Time JPM Completion Time  15 Minutes / NA COMMENTS:                                        Evaluator's Signature:
Date:
STUDENT JPM INFORMATION CARD Initial Conditions:
STUDENT JPM INFORMATION CARD Initial Conditions:
The plant was operating at full power when both RFW pumps tripped.
The plant was operating at full power when both RFW pumps tripped.
RPV level dropped to less than -50 inches.
RPV level dropped to less than -50 inches.
Cue: The CRS has directed you to ensure all isolations for a -50 inch RPV level si g nal per EOP 5.1.1.
Cue:
Another licensed operator will verif y initiations and DG starts.
The CRS has directed you to ensure all isolations for a -50 inch RPV level signal per EOP 5.1.1.
Inform the CRS when EOP isolations for  
Another licensed operator will verify initiations and DG starts.
-50 inches have been verified.
Inform the CRS when EOP isolations for
Page 6 of 6  
          -50 inches have been verified.
Page 6 of 6


2006 NRC EXAM - JPM #5 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE LOWER RPV PRESSURE USING DEH (SIMULATOR)
2006 NRC EXAM - JPM #5 PROGRAM TITLE             INITIAL LICENSED OPERATOR TRAINING COURSE TITLE             JOB PERFORMANCE MEASURE LESSON TITLE LOWER RPV PRESSURE USING DEH (SIMULATOR)
LESSON LENGTH
LESSON LENGTH     .5 HRS   MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                             Rev. No.
.5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 09/02/06 REVISED BY DATE       TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
Simulator Guide PQD Code                                         Rev. No.
Page 2 of 7 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                           JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
JPM PQD Code                                                     Rev. No.
Exam PQD Code                                                   Rev. No.
DIVISION TITLE     Nuclear Training DEPARTMENT         Operations Training PREPARED BY       Ron Hayden                                      DATE 09/02/06 REVISED BY                                                         DATE TECHNICAL REVIEW BY                                                 DATE INSTRUCTIONAL REVIEW BY                                             DATE APPROVED BY                                                         DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
 
MINOR REVISION RECORD Minor                       Description                      Affected        Entered  Effective Manager Rev Number                   of Revision                       Pages             By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
Reset to IC where reactor is scrammed and RPV/P is approximately 920 psig.
Reset to IC where reactor is scrammed and RPV/P is approximately 920 psig.
Special Setup Instructions:
Special Setup Instructions:
None JPM Instructions:
None JPM Instructions:
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
The evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.
The evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                     Safety Items: None Task Number: RO-0348                                       Validation Time: 10 minutes Prerequisite Training:       N/A                           Time Critical:   No PPM  
None Safety Items: None Task Number:
RO-0348 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical:
No PPM  


==Reference:==
==Reference:==
SOP-DEH-QC Rev. 1 Location: Simulator NUREG 1123 Ref: 241000 A4.02 (4.1/4.1)
SOP-DEH-QC Rev. 1                   Location:       Simulator NUREG 1123 Ref: 241000 A4.02 (4.1/4.1)                     Performance Method:       Perform Page 2 of 7
Performance Method: Perform Page 3 of 7 JPM CHECKLIST PROCEDURE VALIDATION Verify the revision number of procedure copies for evaluator and student. If the procedure revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.INITIAL CONDITIONS: Columbia has just scrammed due to low RPV level. Another operator is returning RPV Level back to the normal operating band. INITIATING CUE: The CRS has directed you to lower RPV pressure to 850 psig at the rate of 25 psig per minute using DEH in Automatic per SOP-DEH-QC. Inform the CRS when RPV


pressure is 850 psig.
JPM CHECKLIST PROCEDURE          Verify the revision number of procedure copies for evaluator and student. If the VALIDATION          procedure revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
INITIAL            Columbia has just scrammed due to low RPV level. Another operator is returning RPV CONDITIONS:        Level back to the normal operating band.
VERIFY PRESS SETPOINT AUTO light is LIT S / U The candidate
INITIATING          The CRS has directed you to lower RPV pressure to 850 psig at the rate of 25 psig per CUE:                minute using DEH in Automatic per SOP-DEH-QC. Inform the CRS when RPV pressure is 850 psig.
 
* Items are Critical Steps Comments                 Element                               Standard                   Sat/Unsat RECORD START TIME: __________
should get quick card in the ARP  
The candidate                                      VERIFY PRESS SETPOINT                     S/U should get quick                                   AUTO light is LIT card in the ARP DEPRESS PRESS SETPOINT                    S / U*
 
book holder in PSI pushbutton front of DEH panel VERIFY PRESS SETPOINT PSI                 S/U pushbutton light is LIT VERIFY the current pressure               S/U setpoint APPEARS in the DISPLAY and DISPLAY DEMAND window ENTER the desired pressure               S / U*
book holder in  
setpoint (850) with the numerical keyboard VERIFY the desired pressure               S/U setpoint APPEARS in the DISPLAY DEMAND window DEPRESS ENTER                             S / U*
 
VERIFY the following:
front of DEH panel DEPRESS PRESS SETPOINT  
* The old (but still current)         S/U pressure setpoint remains in the DISPLAY window
 
* The HOLD light is LIT Page 3 of 7
PSI pushbutton S / U*  VERIFY PRESS SETPOINT PSI
* Items are Critical Steps Comments Element                 Standard               Sat/Unsat DEPRESS PRESS RATE,                     S / U*
 
PSI/MIN VERIFY PRESS RATE,                       S/U PSI/MIN light is LIT VERIFY PRESS SETPOINT PSI               S/U light is EXTINGUISHED VERIFY the current selected             S/U pressure setpoint rate of change APPEARS in the DISPLAY window IF the displayed pressure setpoint rate of change is acceptable, THEN PROCEED to                           N/A Step 5.5.1.o. Otherwise N/A IF the displayed pressure setpoint rate of change is not acceptable, S / U*
pushbutton light is LIT S / U  VERIFY the current pressure setpoint APPEARS in the DISPLAY and DISPLAY  
THEN ENTER a new value with the numerical keyboard (25), and PERFORM the following:
 
VERIFY the value selected               S/U APPEARS in the DISPLAY DEMAND window DEPRESS ENTER                           S / U*
DEMAND window S / U  ENTER the desired pressure setpoint (850) with the numerical keyboard S / U*  VERIFY the desired pressure setpoint APPEARS in the DISPLAY DEMAND window S / U  DEPRESS ENTER S / U*   VERIFY the following: The old (but still current) pressure setpoint remains in the DISPLAY window The HOLD light is LIT S / U Page 4 of 7
VERIFY the new pressure                 S/U setpoint rate of change APPEARS in the DISPLAY window DEPRESS PRESS SETPOINT PSI pushbutton to DISPLAY the           S / U*
* Items are Critical StepsComments  Element Standard Sat/Unsat DEPRESS PRESS RATE, PSI/MIN S / U*   VERIFY PRESS RATE, PSI/MIN light is LIT S / U  VERIFY PRESS SETPOINT PSI  
following:
 
* The new pressure setpoint in the DISPLAY DEMAND window.
light is EXTINGUISHED S / U  VERIFY the current selected  
* The current value for the pressure setpoint in the DISPLAY window Page 4 of 7
 
* Items are Critical Steps Comments                Element                              Standard                  Sat/Unsat DEPRESS GO and                            S / U*
pressure setpoint rate of change APPEARS in the DISPLAY  
VERIFY the following:
 
* GO light BACKLIGHTS                  S/U
window S / U  IF the displayed pressure setpoint  
* HOLD light is EXTINGUISHED
 
* Current pressure setpoint changes at the predetermined rate (25) until it is equal to the new setpoint in the DISPLAY DEMAND window
rate of change is acceptable, THEN PROCEED to Step 5.5.1.o. Otherwise N/A N/A  IF the displayed pressure setpoint rate of change is not acceptable, THEN ENTER a new value with the numerical keyboard (25), and PERFORM the following:
* GO light extinguishes when new setpoint is reached PERFORM the following:
S / U*  VERIFY the value selected APPEARS in the DISPLAY  
* VERIFY Steam Supply                  S/U Pressure (MS-PR-1C) responds as the DISPLAY value changes IF pressure does not respond, THEN DEPRESS the HOLD N/A pushbutton and investigate.
 
Otherwise N/A Termination Criteria: Candidate informs the CRS that RPV Pressure has been lowered to 850 psig using DEH.
DEMAND window S / U  DEPRESS ENTER S / U*   VERIFY the new pressure  
RECORD TERMINATION TIME: _________
 
Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.
setpoint rate of change APPEARS in the DISPLAY  
 
window S / U  DEPRESS PRESS SETPOINT PSI pushbutton to DISPLAY the  
 
following: The new pressure setpoint in the DISPLAY DEMAND window. The current value for the pressure setpoint in the DISPLAY window S / U*
Page 5 of 7
Page 5 of 7
* Items are Critical StepsComments  Element  Standard  Sat/Unsat DEPRESS GO and  VERIFY the following: GO light BACKLIGHTS HOLD light is EXTINGUISHED Current pressure setpoint changes at the predetermined rate (25)


until it is equal to the new setpoint in the DISPLAY
RESULTS OF JPM:
 
LOWER RPV PRESSURE USING DEH Examinee (Please Print): ______________________________________________
DEMAND window GO light extinguishes when new setpoint is
Evaluator (Please Print): ______________________________________________
 
reached S / U*  S / U    PERFORM the following: VERIFY Steam Supply Pressure (MS-PR-1C) responds as the DISPLAY
 
value changes S / U  IF pressure does not respond, THEN DEPRESS the HOLD
 
pushbutton and investigate. Otherwise N/A N/A Termination Criteria: Candidate informs the CRS that RPV Pressure has been lowered to 850 psig using DEH.
RECORD TERMINATION TIME: _________
Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.
Page 6 of 7 RESULTS OF JPM:
LOWER RPV PRESSURE USING DEH Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: RPV Pressure has been lowered to 850 psig at the rate of 25 psig/minute with DEH in Automatic as per SOP-DEH-QC.
Task Standard: RPV Pressure has been lowered to 850 psig at the rate of 25 psig/minute with DEH in Automatic as per SOP-DEH-QC.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Overall Evaluation                               Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial box) Validation/Critical Time JPM Completion Time 10 Minutes / NA COMMENTS:                             Evaluator's Signature:
Verified Procedure #/Rev. Used for       Validation/Critical    JPM Completion JPM (Initial box)                       Time                 Time 10 Minutes / NA COMMENTS:
Date:  
Evaluator's Signature:                             Date:
Page 6 of 7


Page 7 of 7 STUDENT JPM INFORMATION CARD Initial Conditions:
STUDENT JPM INFORMATION CARD Initial Conditions:
Columbia has just scrammed due to low RPV level.
Columbia has just scrammed due to low RPV level.
Another operator is returning RPV Level back to the normal operating band.
Another operator is returning RPV Level back to the normal operating band.
Cue: The CRS has directed you to lower Reactor Pressure to 850 psig at the rate of 25 psig/minute using DEH in Automatic per SOP-DEH-QC.
Cue:
The CRS has directed you to lower Reactor Pressure to 850 psig at the rate of 25 psig/minute using DEH in Automatic per SOP-DEH-QC.
Inform the CRS when RPV pressure is 850 psig.
Inform the CRS when RPV pressure is 850 psig.
2006 NRC EXAM - JPM #6 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE MANUAL RCIC INITIATION FOR VESSEL INJECTION (ALT PATH) (SIM)
Page 7 of 7
LESSON LENGTH
 
.5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY DATE   REVISED BY DATE       TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
2006 NRC EXAM - JPM #6 PROGRAM TITLE             INITIAL LICENSED OPERATOR TRAINING COURSE TITLE             JOB PERFORMANCE MEASURE LESSON TITLE             MANUAL RCIC INITIATION FOR VESSEL INJECTION (ALT PATH) (SIM)
Page 1 of 5 MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                           JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
LESSON LENGTH     .5 HRS   MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                               Rev. No.
IC-14. Place the Mode switch to Shutdown. Trip both RFPs when level is approximately -5 inches. Ensure RPV level is less than 13 inches and no high-pressure injection systems are injecting.
Simulator Guide PQD Code                                           Rev. No.
JPM PQD Code                                                       Rev. No.
Exam PQD Code                                                     Rev. No.
DIVISION TITLE     Nuclear Training DEPARTMENT         Operations Training PREPARED BY                                                           DATE REVISED BY                                                           DATE TECHNICAL REVIEW BY                                                   DATE INSTRUCTIONAL REVIEW BY                                               DATE APPROVED BY                                                           DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
 
MINOR REVISION RECORD Minor                       Description                      Affected      Entered  Effective  Manager Rev Number                   of Revision                       Pages           By       Date     Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
IC-14.
Place the Mode switch to Shutdown.
Trip both RFPs when level is approximately -5 inches. Ensure RPV level is less than 13 inches and no high-pressure injection systems are injecting.
Special Setup Instructions:
Special Setup Instructions:
Fail RCIC-V-46 to not open automatically (manual operation allowed). MAL MOV-RCI010F 3 - Fail auto open JPM Instructions:
Fail RCIC-V-46 to not open automatically (manual operation allowed).
MAL MOV-RCI010F 3 - Fail auto open JPM Instructions:
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
The evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.
The evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                           Safety Items: None Task Number: RO-0656, RO-0268                                   Validation Time: 5 min.
None Safety Items: None Task Number:
Prerequisite Training: N/A                                       Time Critical:   No PPM  
RO-0656, RO-0268 Validation Time: 5 min. Prerequisite Training: N/A Time Critical:
No PPM  


==Reference:==
==Reference:==
SOP-RCIC-INJECTION-QC rev. 1 Location: Simulator NUREG 1123 Ref: 2170000A4.04 (3.6,3.6)
SOP-RCIC-INJECTION-QC rev. 1                     Location: Simulator NUREG 1123 Ref: 2170000A4.04 (3.6,3.6)                           Performance Method: Perform Page 1 of 5
Performance Method: Perform Page 2 of 5 JPM CHECKLIST PROCEDURE VALIDATION Verify the revision number of procedure copies for evaluator and student. If the procedure revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.INITIAL CONDITIONS: The Reactor is shutdown and it has been decided to use RCIC for RPV level control. PPM 5.1.1 has been entered on low RPV level. INITIATING
 
CUE: The CRS has directed you to manually start the RCIC system for vessel injection using the RCIC-INJECTION Quick Card. Inform the CRS when RCIC is injecting into the RPV and system operation has been verified.
* Items are Critical Steps Comments  Element  Standard  Sat/Unsat RECORD START TIME: __________
Rotates the collar and depresses
 
the pushbutton.
S / U*  Verifies RCIC-V-46  OPENS (Lube Oil Cooler Water Supply).
S / U Candidate should
 
reference quick
 
card located in ARP holder in
 
front of RCIC system  Notes RCIC-V-46 failed to open.
Takes C/S to open and verifies


JPM CHECKLIST PROCEDURE        Verify the revision number of procedure copies for evaluator and student. If the VALIDATION        procedure revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.
INITIAL          The Reactor is shutdown and it has been decided to use RCIC for RPV level control.
CONDITIONS:
PPM 5.1.1 has been entered on low RPV level.
INITIATING        The CRS has directed you to manually start the RCIC system for vessel injection CUE:              using the RCIC-INJECTION Quick Card. Inform the CRS when RCIC is injecting into the RPV and system operation has been verified.
* Items are Critical Steps Comments                Element                              Standard                  Sat/Unsat RECORD START TIME: __________
Candidate should                                  Rotates the collar and depresses          S / U*
reference quick                                  the pushbutton.
card located in ARP holder in                                    Verifies RCIC-V-46 OPENS                  S/U front of RCIC                                    (Lube Oil Cooler Water Supply).
system                                            Notes RCIC-V-46 failed to open.
Takes C/S to open and verifies            S / U*
valve opens.
valve opens.
S / U*  Verifies RCIC-P-2 running (Barometric Condenser Vacuum Pump). S / U  Verifies RCIC-V-45 OPENS (Steam to Turbine)
Verifies RCIC-P-2 running (Barometric Condenser Vacuum               S/U Pump).
S / U   Verifies RCIC Turbine speed  
Verifies RCIC-V-45 OPENS (Steam to Turbine)                         S/U Verifies RCIC Turbine speed rising.                                   S/U Verifies RCIC-V-13 OPENS (RPV Injection).                           S/U Page 2 of 5
 
* Items are Critical Steps Comments                Element                             Standard                 Sat/Unsat When RCIC-V-45 OPENS (Steam to Turbine), verifies:
rising. S / U   Verifies RCIC-V-13 OPENS (RPV Injection).
* RCIC-V-25 and S/U RCIC-V-26 CLOSE(Steam Line Warm up Drains to Main Condenser)
S / U Page 3 of 5
S/U
* Items are Critical StepsComments  Element Standard Sat/Unsat When RCIC-V-45 OPENS (Steam to Turbine), verifies: RCIC-V-25 and RCIC-V-26 CLOSE(Steam Line Warm up Drains to Main  
* RCIC-V-4 and RCIC-V-5 CLOSE (Cond Pump Discharge to EDR)
 
S/U
Condenser) RCIC-V-4 and RCIC-V-5 CLOSE (Cond Pump Discharge to EDR) SW-P-1B Running (20 second time delay S / U   S / U S / U   Verifies RCIC-V-19 (Min Flow
* SW-P-1B Running (20 second time delay Verifies RCIC-V-19 (Min Flow valve) OPENS during low flow S/U conditions (Discharge pressure GT 125 psig and flow LT 75 gpm).
S/U When RCIC flow is GT 150 gpm, verifies RCIC-V-19 CLOSES.
Verifies RCIC-FIC-600 CONTROLS RCIC Turbine S/U speed at the flow setpoint (normally 600 GPM).
Monitors RPV Level and                  S/U pressure.
Adjusts RCIC-FIC-600 to                S/U maintain the required flow.
Verifies SW-V-34 open (RCIC            S/U pump room cooled return H13-P825).
Termination Criteria: Candidate informs the CRS that the RCIC system is injecting into the vessel and that RCIC-V-46 had to be manually opened.
RECORD TERMINATION TIME: _________
Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.
Page 3 of 5


valve) OPENS during low flow conditions (Discharge pressure GT 125 psig and flow LT 75 gpm). When RCIC flow is GT 150 gpm, verifies RCIC-V-19 CLOSES.
RESULTS OF JPM:
S / U  S / U  Verifies RCIC-FIC-600 CONTROLS RCIC Turbine
MANUAL INITIATION OF RCIC FOR VESSEL INJECTION Examinee (Please Print): ______________________________________________
 
Evaluator (Please Print): ______________________________________________
speed at the flow setpoint (normally 600 GPM).
S / U  Monitors RPV Level and
 
pressure.
S / U  Adjusts RCIC-FIC-600 to maintain the required flow.
S / U  Verifies SW-V-34 open (RCIC pump room cooled return H13-
 
P825). S / U Termination Criteria: Candidate informs the CRS that the RCIC system is injecting into the vessel and that RCIC-V-46 had to be manually opened.
RECORD TERMINATION TIME: _________
Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.
Page 4 of 5 RESULTS OF JPM:
MANUAL INITIATION OF RCIC FOR VESSEL INJECTION Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: RCIC system is manually initiated and system operation is verified per RCIC-INJECTION-QC.
Task Standard: RCIC system is manually initiated and system operation is verified per RCIC-INJECTION-QC.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Overall Evaluation                                 Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial box) Validation/Critical Time JPM Completion Time 5 Minutes / NA COMMENTS:                                 Evaluator's Signature:
Verified Procedure #/Rev. Used for       Validation/Critical    JPM Completion JPM (Initial box)                       Time                 Time 5 Minutes / NA COMMENTS:
Date:  
Evaluator's Signature:                             Date:
Page 4 of 5


Page 5 of 5 STUDENT JPM INFORMATION CARD Initial Conditions:
STUDENT JPM INFORMATION CARD Initial Conditions:
The Reactor is shutdown and it has been decided to use RCIC for level control.
The Reactor is shutdown and it has been decided to use RCIC for level control.
PPM 5.1.1 has been entered on RPV level control.
PPM 5.1.1 has been entered on RPV level control.
Cue: The CRS has directed you to manually start the RCIC system, using the RCIC-INJECTION Quick Card, for  
Cue:
The CRS has directed you to manually start the RCIC system, using the RCIC-INJECTION Quick Card, for vessel injection.
Inform the CRS when RCIC is injecting into the RPV and system operation has been verified.
Page 5 of 5


vessel injection.
2006 NRC EXAM - JPM #7 PROGRAM TITLE            INITIAL LICENSED OPERATOR TRAINING COURSE TITLE              JOB PERFORMANCE MEASURE LESSON TITLE              RB HVAC FAILURE; START SGT (ALT PATH) (SIMULATOR)
Inform the CRS when RCIC is injecting into the RPV
LESSON LENGTH      .5 HRS    MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                                Rev. No.
Simulator Guide PQD Code                                            Rev. No.
JPM PQD Code                                                        Rev. No.
Exam PQD Code                                                        Rev. No.
DIVISION TITLE    Nuclear Training DEPARTMENT        Operations Training PREPARED BY        Ron Hayden                                          DATE  9/02/06 REVISED BY                                                              DATE TECHNICAL REVIEW BY                                                    DATE INSTRUCTIONAL REVIEW BY                                                DATE APPROVED BY                                                            DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


and system operation has been verified.
MINOR REVISION RECORD Minor                   Description                        Affected      Entered  Effective  Manager Rev Number                 of Revision                         Pages           By       Date   Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
 
2006 NRC EXAM - JPM #7 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RB HVAC FAILURE; START SGT (ALT PATH) (SIMULATOR)
LESSON LENGTH
.5 HRS  MAXIMUM STUDENTS 1  INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 9/02/06  REVISED BY DATE        TECHNICAL REVIEW BY DATE  INSTRUCTIONAL REVIEW BY DATE  APPROVED BY DATE  Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
Any IC where REA-FN-1B is running.
Any IC where REA-FN-1B is running.
Special Setup Instructions:
Special Setup Instructions:
Line 993: Line 905:
JPM Instructions:
JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                         Safety Items: None Task Number: RO-0491; RO-0383                                 Validation Time: 10 Minutes Prerequisite Training: N/A                                     Time Critical: No PPM  
None Safety Items: None Task Number:
RO-0491; RO-0383 Validation Time:
10 Minutes Prerequisite Training: N/A Time Critical:
No PPM  


==Reference:==
==Reference:==
ARP 4.812.R2 9-1; SOP-SGT-START-DIV/2-QC Rev. 0 Location: Simulator NUREG 1123 Ref:
ARP 4.812.R2 9-1; SOP-SGT-START-               Location: Simulator DIV/2-QC Rev. 0 NUREG 1123 Ref: 295035 EA1.01 (3.6/3.6)                       Performance Method: Perform EA1.02 (3.8/3.8)
295035 EA1.01 (3.6/3.6)
Page 1 of 5
EA1.02 (3.8/3.8)
Performance Method: Perform    Page 1 of 5
 
JPM CHECKLIST PROCEDURE VALIDATION Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: A 'RX BLDG HVAC DIV1 and DIV2 Board R Trouble' alarm have just annunciated. The alarms were acknowledged on P851 S1 and S2. INITIATING CUE: The CRS has directed you to investigate and respond to the Reactor Building HVAC annunciators.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Responds to the back panel
 
4.812.R2 and notes annunciator
'RX BLDG EXH FAN B TRIP' (9-1) is illuminated. Refers to ARP S / U  Checks REA-FN-1B tripped S / U  Attempts to start the other RB Exhaust Ran REA-FN-1A and
 
notes it will not start S / U
* Places the control switch for ROA-FN-1B to STOP/
 
PTL If neither fan can be started, perform the following: Immediately secures any
 
operating Reactor Building Inlet fan, ROA-FN-1A (1B)
S / U
* Close: ROA-V-1 ROA-V-2 REA-V-1 REA-V-2  S / U
* S / U
* S / U
* S / U
* Start one train of the SGT System to maintain Reactor Building
 
pressure negative S / U
* CUE: If candidate decides to start the 'A' SGT train, cue candidate to use the 'B' SGT Train SOP-SGT-START and SOP-SGT-START-DIV/2-QC Refers to SOP-SGT-START-DIV/2-QC and starts SGT as follows:  S / U  Page 2 of 5  


JPM CHECKLIST PROCEDURE            Procedure copies for evaluator and student, if procedure revision is different from VALIDATION          that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL              A RX BLDG HVAC DIV1 and DIV2 Board R Trouble alarm have just CONDITIONS:          annunciated. The alarms were acknowledged on P851 S1 and S2.
INITIATING CUE:      The CRS has directed you to investigate and respond to the Reactor Building HVAC annunciators.
* Items are Critical Steps Comments                  Element                            Standard                Sat/Unsat RECORD START TIME: __________
Responds to the back panel 4.812.R2 and notes annunciator          S/U RX BLDG EXH FAN B TRIP (9-1) is illuminated.
Refers to ARP Checks REA-FN-1B tripped                S/U Attempts to start the other RB Exhaust Ran REA-FN-1A and              S/U*
notes it will not start If neither fan can be started, perform the following:
Immediately secures any Places the control switch                                                S/U*
operating Reactor Building Inlet for ROA-FN-1B to STOP/
fan, ROA-FN-1A (1B)
PTL Close:
* ROA-V-1                          S/U*
* ROA-V-2                          S/U*
* REA-V-1                          S/U*
* REA-V-2                          S/U*
Start one train of the SGT System to maintain Reactor Building            S/U*
pressure negative CUE: If candidate decides to start the A SGT train, cue candidate to use the B SGT Train SOP-SGT-START                                      Refers to SOP-SGT-START-and SOP-SGT-                                        DIV/2-QC and starts SGT as              S/U START-DIV/2-QC                                      follows:
Page 2 of 5
* Items are Critical Steps Comments                Element                          Standard                Sat/Unsat are not the same. If Takes the C/S for and fan    If necessary, THEN place the SOP-SGT-START                                                                              S/U that was not taken to PTL    following fans in PTL:
is referenced, and not the Quick previously - to PTL
* ROA-FN-1A Card, the ROA and
* ROA-FN-1B REA fan control
* REA-FN-1A switches will not
* REA-FN-1B be placed in PTL.
If necessary, THEN close the following valves: Otherwise N/A          N/A Momentarily turn SGT-FN-1B2 fan control switch from AUTO to        S/U*
PTL SYS. START Verify the following:
* Main Heaters energize as indicated by Main Heater        S/U ON light and B2 amp meters
* SGT-V-5B2 OPENS                  S/U
* SGT-FN-1B2 STARTS Note: to prevent a fan trip    S/U flow should be GT 750 CFM and LT 5378 CFM If required to operate in manual flow control, THEN refer to SOP          N/A
                                                  -SGT-START. Otherwise N/A Termination Criteria: Candidate informs the CRS that REA-FN-1B tripped, REA-FN-1A would not start and SGT B train was started and is operating.
Note: If candidate continues with the ARP actions after SGT is started, inform the candidate that the termination point of the JPM has been reached.
RECORD TERMINATION TIME: _________
Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 3 of 5
Page 3 of 5
* Items are Critical StepsComments Element Standard Sat/Unsat are not the same. If SOP-SGT-START


is referenced, and  
RESULTS OF JPM:
RB HVAC FAILURE; START SGT Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: Reactor Building Ventilation has been secured and SGT B train has been started to maintain Secondary Containment pressure.
Overall Evaluation                                  Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for            Validation/Critical        JPM Completion JPM                                  Time                      Time 10 Minutes / NA COMMENTS:
Evaluator's Signature:                                      Date:
Page 4 of 5


not the Quick Card, the ROA and REA fan control
STUDENT JPM INFORMATION CARD Initial Conditions:
A RX BLDG HVAC DIV1 and DIV2 Board R Trouble alarm have just annunciated. The alarms were acknowledged on P851 S1 and S2.
Cue:
The CRS has directed you to investigate and respond to the Reactor Building HVAC annunciators.
Page 5 of 5


switches will not
2006 NRC EXAM - JPM #8 PROGRAM TITLE        INITIAL LICENSED OPERATOR TRAINING COURSE TITLE          JOB PERFORMANCE MEASURE LESSON TITLE          HPCS SYSTEM INITIATION / SW FAILS TO AUTO START (SIM) (ALT PATH)
 
MAXIMUM STUDENTS LESSON LENGTH      .5 HRS                          1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                                  Rev. No.
be placed in PTL. Takes the C/S for and fan that was not taken to PTL
Simulator Guide PQD Code                                              Rev. No.
 
JPM PQD Code                                                          Rev. No.
previously - to PTL If necessary, THEN place the
Exam PQD Code                                                         Rev. No.
 
DIVISION TITLE    Nuclear Training DEPARTMENT        Operations Training PREPARED BY      Ron Hayden                                            DATE 9/02/06 REVISED BY                                                              DATE TECHNICAL REVIEW BY                                                      DATE INSTRUCTIONAL REVIEW BY                                                  DATE APPROVED BY                                                              DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use
following fans in PTL:  ROA-FN-1A ROA-FN-1B REA-FN-1A REA-FN-1B S / U  If necessary, THEN close the following valves:
Otherwise N/A N/A  Momentarily turn SGT-FN-1B2 fan control switch from AUTO to PTL SYS. START S / U
* Verify the following: Main Heaters energize as indicated by Main Heater ON light and B2 amp meters SGT-V-5B2 OPENS SGT-FN-1B2 STARTS Note: to prevent a fan trip flow should be GT 750 CFM and LT 5378 CFM S / U  S / U  S / U  If required to operate in manual flow control, THEN refer to SOP
-SGT-START.
Otherwise N/A N/A Termination Criteria: Candidate informs the CRS that REA-FN-1B tripped, REA-FN-1A would not start and SGT 'B' train was started and is operating. Note: If candidate continues with the ARP actions after SGT is started, inform the candidate that the termination point of the JPM has been reached.
RECORD TERMINATION TIME: _________
Transfer to "Results of JPM" page the following information:  Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 4 of 5 RESULTS OF JPM:
RB HVAC FAILURE; START SGT Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: Reactor Building Ventilation has been secured and SGT B train has been started to maintain Secondary Containment pressure.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM Validation/Critical Time JPM Completion Time  10 Minutes / NA COMMENTS:                                        Evaluator's Signature:
Date:
STUDENT JPM INFORMATION CARD Initial Conditions:
A 'RX BLDG HVAC DIV1 and DIV2 Board R Trouble' alarm have just annunciated. The alarms were acknowledged on P851 S1 and S2.
Cue: The CRS has directed you to investigate and respond to the Reactor Building HVAC annunciators.
Page 5 of 5


2006 NRC EXAM - JPM #8 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE HPCS SYSTEM INITIATION / SW FAILS TO AUTO START (SIM) (ALT PATH)
MINOR REVISION RECORD Minor                       Description                      Affected      Entered  Effective  Manager Rev Number                   of Revision                       Pages           By       Date     Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
LESSON LENGTH
  .5 HRS MAXIMUM STUDENTS 1  INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 9/02/06  REVISED BY DATE        TECHNICAL REVIEW BY DATE  INSTRUCTIONAL REVIEW BY DATE  APPROVED BY DATE  Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
Insert a malfunction that prevents HPCS-P-2 from starting automatically but may be started manually.
Insert a malfunction that prevents HPCS-P-2 from starting automatically but may be started manually.
Special Setup Instructions:
Special Setup Instructions:
Insert a manual scram and allow RPV/L to recover to about 0" then trip both RFP's.
Insert a manual scram and allow RPV/L to recover to about 0 then trip both RFPs.
JPM Instructions:
JPM Instructions:
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                       Safety Items: None Task Number: RO-0235; RO-0459                               Validation Time: 5 minutes Prerequisite Training: N/A                                   Time Critical: NO PPM  
None Safety Items:
None Task Number:
RO-0235; RO-0459 Validation Time: 5 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
SOP-HPCS-INJECTION-QC Rev. 2 Location: SIMULATOR NUREG 1123 Ref:
SOP-HPCS-INJECTION-QC Rev. 2 Location: SIMULATOR NUREG 1123 Ref: 264000A3.06 (3.1/3.2)                       Performance Method: PERFORM Page 1 of 5
264000A3.06 (3.1/3.2)
Performance Method:
PERFORM   Page 1 of 5  


JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.
JPM CHECKLIST PROCEDURE             Regarding procedure copies for evaluator and student, if the procedure revision is VALIDATION            different from that listed on the JPM, verify that the critical task steps are the same.
Evaluator copy may be used for marking step completion, and comments.
Evaluator copy may be used for marking step completion, and comments.
INITIAL CONDITIONS: A failure of the master controller caused RPV level to drop. The Control Room Supervisor directed a manual scram prior to +13" being reached. Both Reactor Feed Pumps then tripped as RPV level approached 0".
INITIAL               A failure of the master controller caused RPV level to drop. The Control Room CONDITIONS:          Supervisor directed a manual scram prior to +13 being reached. Both Reactor Feed Pumps then tripped as RPV level approached 0.
INITIATING CUE:
INITIATING CUE: The CRS has directed you to initiate the HPCS and bring RPV level back to a band of +13 to +54. Inform the CRS when RPV level is in the band.
The CRS has directed you to initiate the HPCS and bring RPV level back to a band of +13" to +54". Inform the CRS when RPV level is in the band.
* Items are Critical Steps Comments                   Element                             Standard                       Sat/Unsat RECORD START TIME: __________
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
Refers to HPCS INJECTION                         S/U QUICK CARD CUE: If asked, inform candidate that Arm and Depress pushbutton may be used.
Refers to HPCS INJECTION  
IF directed by the CRS/Shift Manager, THEN ARM and DEPRESS the HPCS MANUAL                        S/U*
INITIATION pushbutton.
Otherwise, N/A this step and proceed to the next step START HPCS-P-1                                  S/U Verify HPCS-V-12 OPENS, during low flow conditions (approximately 1300 gpm)                        S/U (Minimum Flow Bypass)
Verify HPCS-P-2 running Notes HPCS-P-2 is not running and              S/U*
takes the Control Switch for HPCS-P-2 to the START position Notes HPCS-P-2 start and verifies                S/U proper system operation Page 2 of 5


QUICK CARD S / U CUE: If asked, inform candidate that Arm and Depress pushbutton may be used.
IF required, THEN RESET the              N/A Reactor Level 8 Seal In. Otherwise N/A OPEN HPCS-V-4 (RPV Injection)            S/U VERIFY injection into the RPV            S/U WHEN flow rate is GT 1300 gpm,          S/U THEN VERIFY HPCS-V-12 CLOSES Closes HPCS-V-4 when      Operate HPCS-V-4 as necessary to        S/U RPV level is in band      MAINTAIN RPV level between +13 to +54 inches Termination Criteria: Student informs CRS that RPV level is in the band given and that HPCS-P-2 did not auto start but was started manually.
IF directed by the CRS/Shift Manager, THEN ARM and DEPRESS the HPCS MANUAL INITIATION pushbutton.
RECORD TERMINATION TIME: _________
Otherwise, N/A this step and proceed
Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.
Page 3 of 5


to the next step S / U
RESULTS OF JPM:
* START HPCS-P-1 S / U  Verify HPCS-V-12 OPENS, during
HPCS SYSTEM INITIATION (SW FAILS TO START)
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: The HPCS SW Pump (HPCS-P-2) has been manually started.
Overall Evaluation                                Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for        Validation/Critical    JPM Completion JPM (Initial Box)                        Time                Time 5 Minutes / NA COMMENTS:
Evaluator's Signature:                                  Date:
Page 4 of 5


low flow conditions (approximately 1300 gpm)
(Minimum Flow Bypass)
S / U  Verify HPCS-P-2 running Notes HPCS-P-2 is not running and takes the Control Switch for HPCS-P-2 to the START position S / U
* Notes HPCS-P-2 start and verifies proper system operation S / U  Page 2 of 5
Page 3 of 5 IF required, THEN RESET the Reactor Level 8 Seal In. Otherwise N/A N/A  OPEN HPCS-V-4 (RPV Injection)
S / U  VERIFY injection into the RPV S / U  WHEN flow rate is GT 1300 gpm, THEN VERIFY HPCS-V-12
CLOSES S / U  Closes HPCS-V-4 when RPV level is in band Operate HPCS-V-4 as necessary to MAINTAIN RPV level between +13
to +54 inches S / U Termination Criteria: Student informs CRS that RPV level is in the band given and that HPCS-P-2 did not auto start but was started manually. RECORD TERMINATION TIME: _________
Transfer the following information to the "Results of JPM" page: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.
Page 4 of 5 RESULTS OF JPM: HPCS SYSTEM INITIATION (SW FAILS TO START)
Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: The HPCS SW Pump (HPCS-P-2) has been manually started.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time  5 Minutes / NA COMMENTS:                                  Evaluator's Signature:
Date:
STUDENT JPM INFORMATION CARD Initial Conditions:
STUDENT JPM INFORMATION CARD Initial Conditions:
A failure of the master controller caused RPV level to drop.
A failure of the master controller caused RPV level to drop.
The Control Room Supervisor directed a manual scram prior to +13" being reached. Both Reactor Feed Pumps then tripped as RPV level approached 0".
The Control Room Supervisor directed a manual scram prior to +13 being reached.
Cue: The CRS has directed you to initiate the HPCS system using the Arm and Depress pushbutton, verify proper system operation, and bring RPV level back to a band of +13" to  
Both Reactor Feed Pumps then tripped as RPV level approached 0.
Cue:
The CRS has directed you to initiate the HPCS system using the Arm and Depress pushbutton, verify proper system operation, and bring RPV level back to a band of +13 to
      +54.
Inform the CRS when RPV level is in the band.
Page 5 of 5


+54". Inform the CRS when RPV level is in the band.
2006 NRC EXAM - In Plant JPM #2 PROGRAM TITLE          OPERATIONS TRAINING COURSE TITLE            JOB PERFORMANCE MEASURE LESSON TITLE            START AND PARALLEL DG-2 ON CR EVACUATION (ALT PATH) (Plant)
Page 5 of 5  
LESSON LENGTH    0.5    MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                            Rev. No.
Simulator Guide PQD Code                                        Rev. No.
JPM PQD Code                                                    Rev. No.
Exam PQD Code                                                  Rev. No.
DIVISION TITLE    Nuclear Training DEPARTMENT        Operations Training PREPARED BY      Ron Hayden                                      DATE  5/22/06 REVISED BY                                                        DATE TECHNICAL REVIEW BY                                                DATE INSTRUCTIONAL REVIEW BY                                            DATE APPROVED BY                                                        DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.


2006 NRC EXAM - In Plant JPM #2 PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE START AND PARALLEL DG-2 ON CR EVACUATION (ALT PATH) (Plant)
MINOR REVISION RECORD Minor                   Description                      Affected      Entered  Effective  Manager Rev Number                 of Revision                       Pages           By       Date     Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
LESSON LENGTH 0.5  MAXIMUM STUDENTS 1  INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 5/22/06  REVISED BY DATE        TECHNICAL REVIEW BY DATE  INSTRUCTIONAL REVIEW BY DATE  APPROVED BY DATE  Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
N/A Special Setup Instructions:
MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A JPM Instructions:
N/A Special Setup Instructions:
N/A JPM Instructions:
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.
The evaluator and student shall use current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                   Safety Items: None Task Number: RO-0700                                   Validation Time: 10 Minutes Prerequisite Training: N/A                             Time Critical: NO PPM  
None Safety Items: None Task Number:
RO-0700 Validation Time:
10 Minutes Prerequisite Training: N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
ABN-CR-EVAC Rev. 9 Location:
ABN-CR-EVAC Rev. 9                       Location: Plant NUREG 1123 Ref: 219000A4.13 (3.9/3.8)                   Performance Method: Simulate Page 1 of 5
Plant NUREG 1123 Ref:
219000A4.13 (3.9/3.8)
Performance Method: Simulate   Page 1 of 5
 
JPM CHECKLIST PROCEDURE VALIDATION: Procedure copies for evaluator and student, if procedure revision is different from that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments. INITIAL CONDITIONS: The Control Room has been abandoned due to a fire in the back panels. The Remote Shutdown Panel is manned. INITIATING CUE:
The CRS has directed you to start DG-2 per ABN-CR-EVAC Section 7.5. Another operator has been dispatched to pull the control power fuses from HPCS-P-1 and to trip the HPCS DG. Inform the CRS when DG-2 has been started and has assumed SM-8 loads. CONTROL MANIPULATIONS WILL NOT BE PERFORMED. ALL ACTIONS AND STEPS WILL BE SIMULATED.
* Items are Critical Steps Comments  Element  Standard  Sat/Unsat RECORD START TIME: __________
Cue:  If Student checks, cue that DG-2 is not running.
Candidate is given ABN-CR-EVAC At E-CP-DG/RP2, Depress the Emergency Stop Pushbutton S / U*  Inform the CRS that DG-2 has
 
been tripped S / U Cue:  When candidate dials correct phone number for the RSD (2649 or 2569) to informs the CRS, respond as the CRS.
Place the Diesel Engine Mode Selector to MAINT S / U*  Resets the Lockout Relay (E-RLY-86/DG2)
S / U*  Ensures Diesel Engine Control
 
Selector is in LOCAL S / U Cue: When candidate checks, inform him that the Diesel Engine Control Selector is in the Control Room position.
Places Diesel Engine Control Selector in LOCAL S / U*  Places DG-RMS-DG-2/FTS56B in the EMERG position S / U* Cue:  If candidate asks, respond as the CRS to place Diesel Engine Mode Selector Switch to AUTO. If candidate waits until prompted by the CRS cue that the phone is ringing and, when answered, inform candidate as the CRS to initiate DG-2 Auto fast-start and loading.
Page 2 of 5  


JPM CHECKLIST PROCEDURE            Procedure copies for evaluator and student, if procedure revision is different from VALIDATION:          that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.
INITIAL              The Control Room has been abandoned due to a fire in the back panels. The Remote CONDITIONS:          Shutdown Panel is manned.
INITIATING CUE:      The CRS has directed you to start DG-2 per ABN-CR-EVAC Section 7.5. Another operator has been dispatched to pull the control power fuses from HPCS-P-1 and to trip the HPCS DG. Inform the CRS when DG-2 has been started and has assumed SM-8 loads. CONTROL MANIPULATIONS WILL NOT BE PERFORMED. ALL ACTIONS AND STEPS WILL BE SIMULATED.
* Items are Critical Steps Comments                Element                                Standard                Sat/Unsat RECORD START TIME: __________
Cue: If Student checks, cue that DG-2 is not running.
Candidate is given                                  At E-CP-DG/RP2, Depress the            S / U*
ABN-CR-EVAC                                        Emergency Stop Pushbutton Inform the CRS that DG-2 has            S/U been tripped Cue: When candidate dials correct phone number for the RSD (2649 or 2569) to informs the CRS, respond as the CRS.
Place the Diesel Engine Mode            S / U*
Selector to MAINT Resets the Lockout Relay (E-            S / U*
RLY-86/DG2)
Ensures Diesel Engine Control            S/U Selector is in LOCAL Cue: When candidate checks, inform him that the Diesel Engine Control Selector is in the Control Room position.
Places Diesel Engine Control            S / U*
Selector in LOCAL Places DG-RMS-DG-2/FTS56B              S / U*
in the EMERG position Cue: If candidate asks, respond as the CRS to place Diesel Engine Mode Selector Switch to AUTO. If candidate waits until prompted by the CRS cue that the phone is ringing and, when answered, inform candidate as the CRS to initiate DG-2 Auto fast-start and loading.
Page 2 of 5
* Items are Critical Steps Comments                Element                            Standard                    Sat/Unsat Places the Diesel Engine                  S/U*
1B1/1B2 Mode Selector to AUTO Cue: When switch is taken to AUTO inform candidate that DG-2 did NOT start.
If DG-2 failed to Auto start, THEN start DG-2 by depressing S/U*
the Diesel Engine 1B1/1B2 Start pushbutton Cue: If candidate checks, cue that DG-2 is running.
If E-CB-DG2/8 did not automatically close, THEN place S/U*
E-CB-DG2/8 control switch to close. Otherwise N/A Cue: If candidate checks, cue that E-CB-DG2/8 did NOT automatically close.
Places E-CB-DG2/8 control                  S/U*
switch to CLOSE Cue: If candidate checks, cue that E-CB-DG2/8 is now closed.
Termination Criteria: Candidate informs the CRS that DG-2 has started and has assumed SM-8 loads.
RECORD TERMINATION TIME: _________
Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
Page 3 of 5
Page 3 of 5
* Items are Critical Steps Comments  Element  Standard  Sat/Unsat Places the Diesel Engine 1B1/1B2 Mode Selector to AUTO S / U
* Cue:  When switch is taken to AUTO inform candidate that DG-2 did NOT start.
If DG-2 failed to Auto start, THEN start DG-2 by depressing the Diesel Engine 1B1/1B2 Start


pushbutton S / U
RESULTS OF JPM:
* Cue:  If candidate checks, cue that DG-2 is running.
START AND PARALLEL DG-2 ON CR EVAC.
If E-CB-DG2/8 did not automatically close, THEN place
Examinee (Please Print): ______________________________________________
 
Evaluator (Please Print): ______________________________________________
E-CB-DG2/8 control switch to
 
close. Otherwise N/A S / U
* Cue:  If candidate checks, cue that E-CB-DG2/8 did NOT automatically close.
Places E-CB-DG2/8 control
 
switch to CLOSE S / U
* Cue:  If candidate checks, cue that E-CB-DG2/8 is now closed.
Termination Criteria: Candidate informs the CRS that DG-2 has started and has assumed SM-8 loads.
RECORD TERMINATION TIME: _________
Transfer to JPM Results Page the following information:  Procedures validated prior to use; Comments from marked up evaluator's procedure copy;  Unsatisfactory critical tasks;  Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.
RESULTS OF JPM: START AND PARALLEL DG-2 ON CR EVAC.
Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: DG-2 has been started and has assumed SM-8 load per ABN-CR-EVAC.
Task Standard: DG-2 has been started and has assumed SM-8 load per ABN-CR-EVAC.
Overall Evaluation Exam Code SAT / UNSAT (Circle One)
Overall Evaluation                                 Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for JPM Validation/Critical Time JPM Completion Time 10 Minutes / NA COMMENTS:                                     Evaluator's Signature:
Verified Procedure #/Rev. Used for           Validation/Critical     JPM Completion JPM                                  Time                  Time 10 Minutes / NA COMMENTS:
Date:     Page 4 of 5  
Evaluator's Signature:                                   Date:
Page 4 of 5


STUDENT JPM INFORMATION CARD Initial Conditions:
STUDENT JPM INFORMATION CARD Initial Conditions:
The Control Room has been abandoned due to a fire in the back panels.
The Control Room has been abandoned due to a fire in the back panels.
The Remote Shutdown Panel is manned.
The Remote Shutdown Panel is manned.
Cue: The CRS has directed you to start DG-2 per ABN-CR-EVAC Section 7.5.
Cue:
The CRS has directed you to start DG-2 per ABN-CR-EVAC Section 7.5.
Another operator has been dispatched to pull the control power fuses from HPCS-P-1 and to trip the HPCS DG.
Another operator has been dispatched to pull the control power fuses from HPCS-P-1 and to trip the HPCS DG.
Inform the CRS when DG-2 has been started and has  
Inform the CRS when DG-2 has been started and has assumed SM-8 loads.
 
assumed SM-8 loads.
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
ALL ACTIONS AND STEPS WILL BE SIMULATED.
ALL ACTIONS AND STEPS WILL BE SIMULATED.
Page 5 of 5  
Page 5 of 5


2006 NRC EXAM -IN PLANT JPM #3 PROGRAM TITLE INITIAL LICENSED TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE  RESPOND TO CONTROL ROOM HVAC HIGH RADIATION (PLANT) (ALT PATH) LESSON LENGTH  
2006 NRC EXAM -IN PLANT JPM #3 PROGRAM TITLE           INITIAL LICENSED TRAINING COURSE TITLE             JOB PERFORMANCE MEASURE RESPOND TO CONTROL ROOM HVAC HIGH RADIATION LESSON TITLE            (PLANT) (ALT PATH)
  .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 05/22/06 REVISED BY DATE       TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
MAXIMUM STUDENTS LESSON LENGTH     .5 HRS                         1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                           Rev. No.
MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
Simulator Guide PQD Code                                       Rev. No.
N/A Special Setup Instructions:
JPM PQD Code                                                   Rev. No.
N/A JPM Instructions:
Exam PQD Code                                                   Rev. No.
DIVISION TITLE   Nuclear Training DEPARTMENT       Operations Training PREPARED BY       Ron Hayden                                      DATE 05/22/06 REVISED BY                                                         DATE TECHNICAL REVIEW BY                                               DATE INSTRUCTIONAL REVIEW BY                                           DATE APPROVED BY                                                       DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
 
MINOR REVISION RECORD Minor                       Description                      Affected      Entered  Effective  Manager Rev Number                   of Revision                       Pages           By       Date     Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Special Setup Instructions:
N/A JPM Instructions:
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment:
Tools/Equipment: None                                     Safety Items: None Task Number: RO-0114                                       Validation Time: 10 minutes Prerequisite Training: N/A                                 Time Critical: NO PPM  
None Safety Items:
None Task Number: RO-0114 Validation Time: 10 minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
ABN-RAD-CR Rev. 4 Location: PLANT NUREG 1123 Ref:
ABN-RAD-CR Rev. 4                           Location: PLANT NUREG 1123 Ref: 288000A2.02 (3.7/3.8)                     Performance Method: SIMULATE Page 1 of 5
288000A2.02 (3.7/3.8)
Performance Method: SIMULATE Page 1 of 5  


JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same. Evaluator copy may be used for marking step completion, and comments.
JPM CHECKLIST PROCEDURE           Regarding procedure copies for evaluator and student, if the procedure revision is different from that VALIDATION          listed on the JPM, verify that the critical task steps are the same. Evaluator copy may be used for marking step completion, and comments.
INITIAL CONDITIONS: A Reactor Building High Radiation signal is present. All automatic actions have been verified. The "B" Control Room Ventilation and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating. A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A/B reads 5,000 CPM).
INITIAL             A Reactor Building High Radiation signal is present. All automatic actions have been CONDITIONS:        verified. The "B" Control Room Ventilation and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating. A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A/B reads 5,000 CPM).
No alarm is observed on the Southeast side (WOA-RIS-32A/B reads normal).
No alarm is observed on the Southeast side (WOA-RIS-32A/B reads normal).
INITIATING CUE: The CRS has directed you to isolate the Northwest Remote Air Intake per ABN-RAD-CR. Notify the CRS when actions per ABN-RAD-CR have been completed for the high radiation condition. CONTROL MANIPULATIONS WILL NOT BE PERFORMED. ALL ACTIONS AND STEPS WILL BE SIMULATED.
INITIATING         The CRS has directed you to isolate the Northwest Remote Air Intake per ABN-RAD-CUE:                CR. Notify the CRS when actions per ABN-RAD-CR have been completed for the high radiation condition. CONTROL MANIPULATIONS WILL NOT BE PERFORMED. ALL ACTIONS AND STEPS WILL BE SIMULATED.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
* Items are Critical Steps Comments                     Element                                     Standard                         Sat/Unsat RECORD START TIME: __________
Candidate is given ABN-RAD-CR Verify WOA-V-51B is open (SE #2) Remote intake outboard isolation S / U Cue: If candidate checks WOA-V-51B is open and independent verification of the step has been performed.
Candidate is given                                         Verify WOA-V-51B is open (SE #2)                     S/U ABN-RAD-CR                                                  Remote intake outboard isolation Cue: If candidate checks WOA-V-51B is open and independent verification of the step has been performed.
Verify WOA-V-52B is open (SE #2)
Verify WOA-V-52B is open (SE #2)                     S/U Remote intake inboard isolation Cue: If candidate checks WOA-V-52B is open and independent verification of the step has been performed.
Remote intake inboard isolation S / U Cue: If candidate checks WOA-V-52B is open and independent verification of the step has been performed.
Unlock and close WOA-V-51A, NW
Unlock and close WOA-V-51A, NW
(#1) Remote Intake Outboard Isolation. If remote air intake #1 is isolated using only valve WOA-V-52A, then N/A this step and step  
(#1) Remote Intake Outboard Isolation. If remote air intake #1 is               S/U*
isolated using only valve WOA-V-52A, then N/A this step and step 7.1.4 Cue: When student attempts to close WOA-V-51A, inform the student that the operator is broken and the valve is danger tagged in the open position.
STEP IS N/A                    Verify WOA-V-51D Opens, NW (#1)
N/A Remote Intake Purge, (WOA-V-51A Closed)
Page 2 of 5


7.1.4  S / U
Unlock and close WOA-V-52A, NW            S/U*
* Cue: When student attempts to close WOA-V-51A, inform the student that the operator is broken and the valve is danger tagged in the open position.
(#1) Remote Intake Inboard Isolation E-CP-COHV/1 is                                        If remote air intake #1 is isolated        S/U*
STEP IS N/A Verify WOA-V-51D Opens, NW (#1)
labeled COHV-1.                                        using only valve WOA-V-52A, then Cover for F4 is                                       remove fuse F4 in Control, Cable labeled with a 4 and                                   Spreading and Critical Switchgear door aid indicates Rooms Control Panel E-CP-COHV/1 TB-F4.
Remote Intake Purge, (WOA-V-51A
(RW 525) to open WOA-V-51D, NW
(#1) Remote Intake Purge. Otherwise N/A Cue: If candidate checks, WOA-V-51D opens.
Termination Criteria: Student informs CRS that the NW Remote Air Intake is isolated, only WOA-V-52A is closed, and Fuse F4 has been pulled.
RECORD TERMINATION TIME: _________
Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.
Page 3 of 5


Closed) N/A  Page 2 of 5  
RESULTS OF JPM:
RESPOND TO CONTROL ROOM HVAC HIGH RADIATION (ONE INTAKE)
Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: The Northwest Remote Air Intake to the Control Room Ventilation System is isolated per ABN-RAD-CR.
Overall Evaluation                                  Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for          Validation/Critical        JPM Completion JPM (Initial Box)                          Time                      Time 10 Minutes / NA COMMENTS:
Evaluator's Signature:                                    Date:
Page 4 of 5


Page 3 of  5 Unlock and close WOA-V-52A, NW (#1) Remote Intake Inboard Isolation S / U
* E-CP-COHV/1 is labeled COHV-1. 
Cover for F4 is
labeled with a 4 and
door aid indicates
TB-F4. If remote air intake #1 is isolated using only valve WOA-V-52A, then remove fuse F4 in Control, Cable
Spreading and Critical Switchgear Rooms Control Panel E-CP-COHV/1 (RW 525) to open WOA-V-51D, NW
(#1) Remote Intake Purge. Otherwise
N/A S / U
* Cue:  If candidate checks, WOA-V-51D opens. Termination Criteria: Student informs CRS that the NW Remote Air Intake is isolated, only WOA-V-52A is closed, and Fuse F4 has been pulled. RECORD TERMINATION TIME: _________
Transfer the following information to the "Results of JPM" page: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.
Page 4 of  5 RESULTS OF JPM: RESPOND TO CONTROL ROOM HVAC HIGH RADIATION            (ONE INTAKE)
Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: The Northwest Remote Air Intake to the Control Room Ventilation System is isolated per ABN-RAD-CR.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time  10 Minutes / NA COMMENTS:                                  Evaluator's Signature:
Date:
STUDENT JPM INFORMATION CARD Initial Conditions:
STUDENT JPM INFORMATION CARD Initial Conditions:
A Reactor Building High Radiation signal is present All automatic actions have been verified The "B" Control Room Ventilation and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A/B reads 5,000 CPM) No alarm is observed on the Southeast side (WOA-RIS-32A/B reads normal)
* A Reactor Building High Radiation signal is present
Cue: The CRS has directed you to isolate the Northwest Remote Air Intake per ABN-RAD-CR. Notify the CRS when actions per ABN-RAD-CR have been  
* All automatic actions have been verified
 
* The "B" Control Room Ventilation and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating
completed for the high radiation condition.
* A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A/B reads 5,000 CPM)
* No alarm is observed on the Southeast side (WOA-RIS-32A/B reads normal)
Cue:
The CRS has directed you to isolate the Northwest Remote Air Intake per ABN-RAD-CR.
Notify the CRS when actions per ABN-RAD-CR have been completed for the high radiation condition.
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
ALL ACTIONS AND STEPS WILL BE SIMULATED.
ALL ACTIONS AND STEPS WILL BE SIMULATED.
Page 5 of 5  
Page 5 of 5


2006 NRC EXAM - IN PLANT JPM #1 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE INSERT CONTROL RODS BY VENTING SCRAM AIR HEADER (Plant)
2006 NRC EXAM - IN PLANT JPM #1 PROGRAM TITLE           INITIAL LICENSED OPERATOR TRAINING COURSE TITLE             JOB PERFORMANCE MEASURE LESSON TITLE             INSERT CONTROL RODS BY VENTING SCRAM AIR HEADER (Plant)
LESSON LENGTH  
MAXIMUM STUDENTS LESSON LENGTH     .5 HRS                         1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code                                           Rev. No.
  .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No. Simulator Guide PQD Code Rev. No. JPM PQD Code Rev. No. Exam PQD Code Rev. No. DIVISION TITLE Nuclear Trainin g  DEPARTMENT O perations Trainin g  PREPARED BY Ron Ha y den DATE 5/22/06 REVISED BY DATE       TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager  
Simulator Guide PQD Code                                       Rev. No.
JPM PQD Code                                                   Rev. No.
Exam PQD Code                                                   Rev. No.
DIVISION TITLE   Nuclear Training DEPARTMENT       Operations Training PREPARED BY       Ron Hayden                                      DATE 5/22/06 REVISED BY                                                         DATE TECHNICAL REVIEW BY                                               DATE INSTRUCTIONAL REVIEW BY                                           DATE APPROVED BY                                                       DATE Operations Training Manager


MINOR REVISION RECORD Minor Rev Number Description of Revision Affected Pages Entered By Effective Date Manager Approval                         JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
MINOR REVISION RECORD Minor                       Description                      Affected      Entered  Effective  Manager Rev Number                   of Revision                       Pages           By       Date     Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:
N/A Special Setup Instructions:
N/A Special Setup Instructions:
N/A JPM Instructions:
N/A JPM Instructions:
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the "Results of JPM" page.
The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.
Tools/Equipment: Pre-staged EOP Tools Safety Items:
Tools/Equipment: Pre-staged EOP Tools                     Safety Items: None Task Number: RO-0680                                       Validation Time: 9 Minutes Prerequisite Training: N/A                                 Time Critical: NO PPM  
None Task Number:
RO-0680 Validation Time:
9 Minutes Prerequisite Training:
N/A Time Critical:
NO PPM  


==Reference:==
==Reference:==
PPM 5.5.11 Location: PLANT NUREG 1123 Ref:
PPM 5.5.11                                 Location: PLANT NUREG 1123 Ref: 295037EA1.05 (3.9/4.0)                     Performance Method: SIMULATE Page 1 of 5
295037EA1.05 (3.9/4.0)
Performance Method: SIMULATE Page 1 of 5  


JPM CHECKLIST PROCEDURE VALIDATION Regarding procedure copies for evaluator and student, if the procedure revision is different from that listed on the JPM, verify that the critical task steps are the same.
JPM CHECKLIST PROCEDURE             Regarding procedure copies for evaluator and student, if the procedure revision is VALIDATION            different from that listed on the JPM, verify that the critical task steps are the same.
Evaluator copy may be used for marking step completion, and comments.
Evaluator copy may be used for marking step completion, and comments.
INITIAL CONDITIONS: A scram has been initiated and the blue scram lights are extinguished at H13-P603.
INITIAL               A scram has been initiated and the blue scram lights are extinguished at H13-P603.
Reactor pressure is stable at 930 psig and Reactor Power is 38%. INITIATING CUE:
CONDITIONS:          Reactor pressure is stable at 930 psig and Reactor Power is 38%.
The CRS has directed you to insert control rods by venting the Scram Air Header per PPM 5.5.11 Tab D. Inform the CRS when actions are completed to vent the Scram Air Header. THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.
INITIATING CUE:       The CRS has directed you to insert control rods by venting the Scram Air Header per PPM 5.5.11 Tab D. Inform the CRS when actions are completed to vent the Scram Air Header. THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
* Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
* Items are Critical Steps Comments                   Element                             Standard                       Sat/Unsat RECORD START TIME: __________
CUE: If asked, inform candidate that control rod density is .156.
CUE: If asked, inform candidate that control rod density is .156.
PPM 5.1.1 Tab D is  
PPM 5.1.1 Tab D is                                   Closes CRD-V-95 (Scram Air                     S/U*
 
given to candidate                                  Header Isolation)
given to candidate Closes CRD-V-95 (Scram Air  
Closes CRD-V-729 (CRD-PI-13                   S/U*
 
Header Isolation)
S / U
* Closes CRD-V-729 (CRD-PI-13  
 
isolation)
isolation)
S / U
Note: Pre-staged crescent wrench is used to remove instrument drain plug.
* Note: Pre-staged crescent wrench is used to remove instrument drain plug.
Removes instrument drain       Rotates instrument drain plug plug for CRD-PI-13.             counterclockwise on CRD-PI-13 S/U*
Removes instrument drain  
until drain plug is removed Cue candidate that the drain line plug is removed if rotated in proper direction.
 
Open CRD-V-729 (CRD-PI-13                     S/U*
plug for CRD-PI-13. Rotates instrument drain plug
 
counterclockwise on CRD-PI-13 until drain plug is removed S / U
* Cue candidate that the drain line plug is removed if rotated in proper direction.
Open CRD-V-729 (CRD-PI-13  
 
isolation)
isolation)
S / U
Cue: Inform candidate that the scram air header is fully depressurized and no further rod motion is observed.
* Cue: Inform candidate that the scram air header is fully depressurized and no further rod motion is observed.
Closes CRD-V-729 (CRD-PI-13                     S/U isolation)
Closes CRD-V-729 (CRD-PI-13 isolation)
Page 2 of 5
S / U  Page 2 of 5  
* Items are Critical Steps Comments                  Element                            Standard                  Sat/Unsat Install instrument drain plug for            S/U CRD-PI-13 by rotating it clockwise Cue candidate that the drain line plug is installed if rotated in proper direction.
 
Open CRD-V-729 (CRD-PI-13                    S/U isolation)
Open CRD-V-95 (Scram Air Header              S/U Isolation)
Termination Criteria: Student informs CRS that actions to vent Scram Air Header have been completed.
RECORD TERMINATION TIME: _________
Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.
Page 3 of 5
Page 3 of 5
* Items are Critical StepsComments Element Standard Sat/Unsat Install instrument drain plug for CRD-PI-13 by rotating it clockwise S / U Cue candidate that the drain line plug is installed if rotated in proper direction.
Open CRD-V-729 (CRD-PI-13


isolation)
RESULTS OF JPM:
S / U  Open CRD-V-95 (Scram Air Header
INSERT CONTROL ROD BY VENTING SCRAM AIR HEADER Examinee (Please Print): ______________________________________________
Evaluator (Please Print): ______________________________________________
Task Standard: The scram air header has been vented per PPM 5.5.11 Tab D.
Overall Evaluation                                  Exam Code SAT / UNSAT (Circle One)
Verified Procedure #/Rev. Used for        Validation/Critical      JPM Completion JPM (Initial Box)                        Time                Time 10 Minutes / NA COMMENTS:
Evaluator's Signature:                                  Date:
Page 4 of 5


Isolation)
S / U Termination Criteria: Student informs CRS that actions to vent Scram Air Header have been completed.
RECORD TERMINATION TIME: _________
Transfer the following information to the "Results of JPM" page: Procedures validated prior to use; Comments from marked up evaluator's procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.
Page 4 of 5 RESULTS OF JPM: INSERT CONTROL ROD BY VENTING SCRAM AIR HEADER Examinee (Please Print):
______________________________________________
Evaluator (Please Print):
______________________________________________
Task Standard: The scram air header has been vented per PPM 5.5.11 Tab D.
Overall Evaluation Exam Code SAT / UNSAT  (Circle One)
Verified Procedure #/Rev. Used for JPM (Initial Box) Validation/Critical Time JPM Completion Time  10 Minutes / NA COMMENTS:                                        Evaluator's Signature:
Date:
STUDENT JPM INFORMATION CARD Initial Conditions:
STUDENT JPM INFORMATION CARD Initial Conditions:
A scram has been initiated and the blue scram lights are extinguished at H13-P603 Reactor pressure is stable at 930 psig and Reactor Power is 38%.
A scram has been initiated and the blue scram lights are extinguished at H13-P603 Reactor pressure is stable at 930 psig and Reactor Power is 38%.
Cue: The CRS has directed you to insert control rods by venting the Scram Air Header per PPM 5.5.11 Tab D. Inform the CRS when actions are completed to vent the Scram Air Header. THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.
Cue:
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
The CRS has directed you to insert control rods by venting the Scram Air Header per PPM 5.5.11 Tab D.
Page 5 of 5  
Inform the CRS when actions are completed to vent the Scram Air Header.
THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.
CONTROL MANIPULATIONS WILL NOT BE PERFORMED.
Page 5 of 5


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 1 of 22 Facility: Columbia                               Scenario No:    1 Examiners:       Operators:
Appendix D                               SCENARIO OUTLINE                                 FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Facility: Columbia                             Scenario No:    1 Examiners:                                             Operators:
Initial conditions: Columbia is at 85% power due to an economic dispatch request from BPA. REA-FN-1A is OOS due to bearing replacement. REA-FN-1B is protected.
Initial conditions: Columbia is at 85% power due to an economic dispatch request from BPA. REA-FN-1A is OOS due to bearing replacement. REA-FN-1B is protected.
Turnover: Return Columbia to 90% power with flow. There are no preconditioning limits associated with the power/flow increase.
Turnover: Return Columbia to 90% power with flow. There are no preconditioning limits associated with the power/flow increase.
Event No. Timeline Event Type*
Event     Timeline   Event Type*     Event Description No.
Event Description
: 1.       T=0         R (RO)       Raises Reactor Power with recirculation flow.
: 1. T=0 R (RO) Raises Reactor Power with recirculation flow.
: 2.       T=10         C (SRO)     Accumulator for a Control Rod Inop (Tech Spec #1)
: 2. T=10 C (SRO) Accumulator for a Control Rod Inop (Tech Spec #1)
: 3.       T=20         C (RO)       Slow drop of RFW-P-1A Control Oil Pressure with failure of RFW-P-AOP/1A to start.
: 3. T=20 C (RO) Slow drop of RFW-P-1A Control Oil Pressure with failure of RFW-P-AOP/1A to start.
: 4.       T=30         C (RO)       CRD-P-1A reduced flow and pump trip.
: 4. T=30 C (RO) CRD-P-1A reduced flow and pump trip.
: 5.       T=45           C         RHR-A Suction piping rupture that is isolated by closing RHR-V-4A.
: 5. T=45 C (SRO/BOP)
(SRO/BOP)      (Critical Step) (Tech Spec)
RHR-A Suction piping rupture that is isolated by closing RHR-V-4A.
: 6.       T=50         N (BOP)     Performs PPM 5.5.23 to fill SP with HPCS.
(Critical Step) (Tech Spec)
: 7.       T=70       M (ALL)       RRC-P-1A High Vibration alarms followed by seal failures followed by LOCA.
: 6. T=50 N (BOP) Performs PPM 5.5.23 to fill SP with HPCS.
: 8.       T=75         C (BOP)     EDR-V-19 fails to Auto close on 1.68 psig isolation signal.
: 7. T=70 M (ALL) RRC-P-1A High Vibration alarms followed by seal failures followed by LOCA. 8. T=75 C (BOP) EDR-V-19 fails to Auto close on 1.68 psig isolation signal.
: 9.       T=85         C (BOP)     RHR-V-17B breaker trips when C/S taken to open (results in the inability to spray drywell)
: 9. T=85 C (BOP) RHR-V-17B breaker trips when C/S taken to open (results in the  
: 10.      T=90                      Initiates an Emergency Depressurization when DW/T cannot be maintained below 330°F or when PSP is exceeded. (Critical Step)
                        * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 22


inability to spray drywell)
Appendix D                               SCENARIO OUTLINE                                 FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 The scenario starts with Columbia at 86% due to economic dispatch. The crew will be directed to raise power back to 100% after turnover. After the power increase, accumulator for rod 14-23 will annunciate.
: 10. T=90  Initiates an Emergency Depressurization when DW/T cannot be maintained below 330°F or when PSP is exceeded. (Critical Step) * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Report from the field will be a valve failure with pressure LT required by Tech Specs. The SRO will declare rod 14-23 inoperable.
 
The next event will occur after the power increase. Due to a failed pump, the A RFP control oil pressure low alarm will annunciate. The crew will note that the Auxiliary Oil Pump should have started when this alarm is received but did not. The crew will start the Auxiliary Oil Pump and control oil pressure will return to normal.
Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 2 of 22 The scenario starts with Columbia at 86% due to economic dispatch. The crew will be directed to raise power back to 100% after turnover. After the power increase, accumulator for rod 14-23 will annunciate. Report from the field will be a valve failure with pressure LT required by Tech Specs. The SRO will declare  
The next event is a slow failure of CRD-P-1A. CRD system pressure will drop and the crew will take actions to start the standby CRD pump which will restore system pressure.
 
The next event is a rupture in RHR-P-2A suction piping. Suppression pool level will drop and EOP 5.2.1 will be entered. Additionally ABN-Flooding will be entered. Report from the field will be that the leak is between the RHR pump and the suction valve. The crew will close RHR-V-4A and pull the control power fuses on the pump to prevent it from starting. Closing RHR-V-4A will stop the leak and PPM 5.5.23 will be used to return SP/L to normal with HPCS.
rod 14-23 inoperable.
The next event is high vibrations on RRC-P-1A. The lower and upper seals will quickly fail and cause a small LOCA. DW/P will rise and the crew should take actions to scram the reactor. With RHR-A already being OOS, sprays will be initiated with RHR-B. When WW/P exceeds 12 psig, the crew will attempt to spray the drywell. When RHR-V-17B is opened to initiate sprays it will lose power and the crew will not be able to spray the drywell. On the 1.68 psig initiation, EDR-V-19 will fail to auto close. Manual actions to close the valve will result in the valve closing.
The next event will occur after the power increase. Due to a failed pump, the A RFP control oil pressure low alarm will annunciate. The crew will note that the Auxiliary Oil Pump should have started when this alarm is received but did not. The crew will start the Auxiliary Oil Pump and control oil pressure will return to normal. The next event is a slow failure of CRD-P-1A. CRD system pressure will drop and the crew will take actions to start the standby CRD pump which will restore system pressure.
The next event is a rupture in RHR-P-2A suc tion piping. Suppression pool level will drop and EOP 5.2.1 will be entered. Additionally ABN-Flooding will be entered. Report from the field will be that the leak is between the RHR pump and the suction valve. The cr ew will close RHR-V-4A and pull the control power fuses on the pump to prevent it from starting. Closi ng RHR-V-4A will stop the leak and PPM 5.5.23 will be used to return SP/L to normal with HPCS.
The next event is high vibrations on RRC-P-1A. The lower and upper seals will quickly fail and cause a small LOCA. DW/P will rise and the crew should take actions to scram the reactor. With RHR-A already being OOS, sprays will be initiated with RHR-B. When WW/P exceeds 12 psig, the crew will attempt to spray the drywell. When RHR-V-17B is opened to initiate sprays it will lose power and the crew will not be able to spray the drywell. On the 1.68 psig initiation, EDR-V-19 will fail to auto close. Manual actions to  
 
close the valve will result in the valve closing.
When it is determined that Drywell temperature cannot be maintained below 330°F or when PSP has been exceeded, the crew will enter EOP 5.1.3 and initiate an Emergency Depressurization.
When it is determined that Drywell temperature cannot be maintained below 330°F or when PSP has been exceeded, the crew will enter EOP 5.1.3 and initiate an Emergency Depressurization.
The scenario will be terminated when an Emergency Depressurization has been initiated and RPV level is being returned to normal.
The scenario will be terminated when an Emergency Depressurization has been initiated and RPV level is being returned to normal.
Appendix D                                          SCENARIO OUTLINE                                        FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 3 of 22 Event No. 1
Page 2 of 22


== Description:==
Appendix D                                SCENARIO OUTLINE                                    FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 1


Raises Reactor Power with recirculation flow. This event is initiated by the SRO and is given in the turnover information.
==
Time Position Applicants Actions or Behavior T=0 SRO Directs RO to raise Reactor power w ith flow at a directed rate of change.
Description:==
RO Depresses Master Controller raise pushbutton while monitoring RPV Power, Pressure and Level.
Raises Reactor Power with recirculation flow.
This event is initiated by the SRO and is given in the turnover information.
Time           Position                           Applicants Actions or Behavior T=0             SRO         Directs RO to raise Reactor power with flow at a directed rate of change.
RO         Depresses Master Controller raise pushbutton while monitoring RPV Power, Pressure and Level.
Monitors rate of power increase to be less that rate given by SRO.
Monitors rate of power increase to be less that rate given by SRO.
BOP Provides Peer Checks to RO as necessary.
BOP         Provides Peer Checks to RO as necessary.
COMMENTS:  
COMMENTS:
Page 3 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 4 of 22 Event No. 2  
Appendix D                               SCENARIO OUTLINE                                 FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 2


== Description:==
==
Description:==
Accumulator for Control Rod 14-23 Inop. (Tech Spec)
Accumulator for Control Rod 14-23 Inop. (Tech Spec)
This event is initiated by activating TRIGGER 1 when the power increase has been completed.
This event is initiated by activating TRIGGER 1 when the power increase has been completed.
Time Position Applicants Actions or Behavior T=10 RO Acknowledges Rod Accumulator Trouble alarm P603-A7 6-7, and refers to ARP. Verifies CRD Pump in operation. Determines alarm is associated with rod 14-23 and informs SRO.
Time         Position                           Applicants Actions or Behavior T=10             RO         Acknowledges Rod Accumulator Trouble alarm P603-A7 6-7, and refers to ARP.
Verifies CRD Pump in operation.
Determines alarm is associated with rod 14-23 and informs SRO.
Refers SRO to SOP-CRD-HCU.
Refers SRO to SOP-CRD-HCU.
SRO Directs local investigation.
SRO         Directs local investigation.
Role Play - Wait a minute and call 2242 and report as OPS2 that you have found accumulator valve CRD-V-111/14-23 (the accumulator's nitrogen charging valve) has a stem to disk separation.
Role Play - Wait a minute and call 2242 and report as OPS2 that you have found accumulator valve CRD-V-111/14-23 (the accumulators nitrogen charging valve) has a stem to disk separation.
Accumulator pressure is down to 920 psig and you cannot stop the pressure drop which appears to be  
Accumulator pressure is down to 920 psig and you cannot stop the pressure drop which appears to be slowly dropping.
 
SRO         Refers to Tech Spec 3.1.5. Notes surveillance pressure requirement for each accumulator is GT 940 psig.
slowly dropping.
Determines accumulator for rod 14-23 is inop and enters TS 3.1.5 Condition A - Declare the associated control rod inoperable within 8 hours.
SRO Refers to Tech Spec 3.1.5. Notes surveillance pressure requirement for each accumulator is GT 940 psig.
May contact SNE for reactivity plan to insert rod 14-23.
Determines accumulator for rod 14-23 is inop and enters TS 3.1.5  
 
Condition A - Declare the associated control rod inoperable within 8  
 
hours. May contact SNE for reactivity plan to insert rod 14-23.
Contacts PSRO and conducts brief.
Contacts PSRO and conducts brief.
COMMENTS:  
COMMENTS:
Page 4 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 5 of 22 Event No. 3  
Appendix D                               SCENARIO OUTLINE                                   FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 3


== Description:==
==
Description:==
Slow drop of RFW-P-1A Control Oil Pressure with failure of RFW-P-AOP/1A to start.
Slow drop of RFW-P-1A Control Oil Pressure with failure of RFW-P-AOP/1A to start.
The event is initiated by activating TRIGGER 2 (It takes 2 minutes to get alarm)
The event is initiated by activating TRIGGER 2 (It takes 2 minutes to get alarm)
Time Position Applicants Actions or Behavior T=20 RO/BOP Acknowledges TURB A CNTR OIL PRESS LOW annunciator P840-A1 5-1, and refers to ARP.
Time           Position                           Applicants Actions or Behavior T=20           RO/BOP       Acknowledges TURB A CNTR OIL PRESS LOW annunciator P840-A1 5-1, and refers to ARP.
Provides SRO with current control oil pressure (LT 70 psig) on RFT-PI-
Provides SRO with current control oil pressure (LT 70 psig) on RFT-PI-2/1A.
 
SRO/RO/BOP Notes that RFW-P-AOP/1A should have started per ARP but is not running.
2/1A. SRO/RO/BOP Notes that RFW-P-AOP/1A s hould have started per ARP but is not running. SRO Directs RFW-P-AOP/1A be started (RO may start pump without direction - auto action that should have occurred but did not).
SRO         Directs RFW-P-AOP/1A be started (RO may start pump without direction - auto action that should have occurred but did not).
RO/BOP Starts RFW-P-AOP/1A and reports start to SRO.
RO/BOP       Starts RFW-P-AOP/1A and reports start to SRO.
Reports control oil pressure returned to normal and clearing of control oil  
Reports control oil pressure returned to normal and clearing of control oil pressure low annunciator.
 
pressure low annunciator.
Acknowledges annunciator for RFW-P-AOP/1A running.
Acknowledges annunciator for RFW-P-AOP/1A running.
SRO Contacts Production SRO/System Engineer to investigate problem with RFW-P-AOP/1A.
SRO         Contacts Production SRO/System Engineer to investigate problem with RFW-P-AOP/1A.
ROLE-PLAY: If OPS3 is contacted report no leak observed.
ROLE-PLAY: If OPS3 is contacted report no leak observed.
COMMENTS:  
COMMENTS:
Page 5 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 6 of 22 Event No. 4  
Appendix D                               SCENARIO OUTLINE                               FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 4


==
==
Line 1,439: Line 1,295:
CRD-P-1A reduced flow and eventual pump trip (in 6 minutes)
CRD-P-1A reduced flow and eventual pump trip (in 6 minutes)
This event is initiated by activating TRIGGER 3 (It takes 1 minute to get alarm)
This event is initiated by activating TRIGGER 3 (It takes 1 minute to get alarm)
Time Position Applicants Actions or Behavior T=30 RO Acknowledges Charge Water Press Low annunciator P603-A7 3-8, and refers to ARP.
Time           Position                           Applicants Actions or Behavior T=30             RO         Acknowledges Charge Water Press Low annunciator P603-A7 3-8, and refers to ARP.
Provides SRO with current reading on CRD-PIS-600 and indicates that it continues to drop.
Provides SRO with current reading on CRD-PIS-600 and indicates that it continues to drop.
Refers SRO to ABN-CRD.
Refers SRO to ABN-CRD.
Acknowledges RWCU Pump trouble alarms associated with the drop in CRD pressure (Takes about 4 minutes P602-A5 4-7 and 4-8).
Acknowledges RWCU Pump trouble alarms associated with the drop in CRD pressure (Takes about 4 minutes P602-A5 4-7 and 4-8).
SRO Refers to ABN-CRD and direct s placing CRD-FC-600 (CRD Flow Controller) in MANUAL at zero output.
SRO         Refers to ABN-CRD and directs placing CRD-FC-600 (CRD Flow Controller) in MANUAL at zero output.
Refers to Tech Spec 3.1.5.
Refers to Tech Spec 3.1.5.
RO Places CRD-FC-600 in MANUAL at zero output.
RO         Places CRD-FC-600 in MANUAL at zero output.
Acknowledges CRD Abnormal Operation annunciator and reports the trip of CRD-P-1A (takes 6 minutes).
Acknowledges CRD Abnormal Operation annunciator and reports the trip of CRD-P-1A (takes 6 minutes).
Acknowledges accumulator alarms if/as they occur.
Acknowledges accumulator alarms if/as they occur.
SRO Per ABN-CRD directs start of CRD-P-1B, the standby CRD Pump (Standby pump may be started before CRD-P-1A trips if crew determines that CRD-P-1A is failing).
SRO         Per ABN-CRD directs start of CRD-P-1B, the standby CRD Pump (Standby pump may be started before CRD-P-1A trips if crew determines that CRD-P-1A is failing).
Acknowledges RWCU trouble alarms associated with the loss of CRD  
Acknowledges RWCU trouble alarms associated with the loss of CRD flow.
Page 6 of 22


flow.
Appendix D               SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 RO Starts CRD-P-1B and reports start to SRO.
Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 7 of 22 RO Starts CRD-P-1B and reports start to SRO.
SRO Directs CRD-FC-600 be nulled and returned to AUTO.
SRO Directs CRD-FC-600 be nulled and returned to AUTO.
Contacts production SRO/Work Week Leader concerning CRD-P-1A.
Contacts production SRO/Work Week Leader concerning CRD-P-1A.
RO Nulls CRD-FC-600 deviation meter and shifts CRD-FC-600 to AUTOMATIC.
RO Nulls CRD-FC-600 deviation meter and shifts CRD-FC-600 to AUTOMATIC.
Reports accumulator alarms clear after CRD pump starts.
Reports accumulator alarms clear after CRD pump starts.
Contacts OPS2 to check CRD-P-1B operation.
Contacts OPS2 to check CRD-P-1B operation.
COMMENTS:
COMMENTS:
Appendix D                                          SCENARIO OUTLINE                                        FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 8 of 22 Event No. 5
Page 7 of 22


== Description:==
Appendix D                                SCENARIO OUTLINE                                FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 5
 
==
Description:==
Rupture in the RHR-A suction piping causing RHR-A room level to rise and Suppression Pool Level to drop.
Rupture in the RHR-A suction piping causing RHR-A room level to rise and Suppression Pool Level to drop.
The event is initiated by activating TRIGGER 4. (It takes about 1 minute to get alarm)
The event is initiated by activating TRIGGER 4. (It takes about 1 minute to get alarm)
Time Position Applicants Actions or Behavior Critical step for this event is to stop Suppression Pool leak by closing RHR-V-4A.
Time           Position                           Applicants Actions or Behavior Critical step for this event is to stop Suppression Pool leak by closing RHR-V-4A.
T=45 BOP Acknowledges alarms associated with lowering Suppression Pool level and rising water level in RHR-A Pump Room as they occur: Leak Det Reactor Bldg Floor Sump R1 Leakage high, P601-A3 2-7 Sump R1 Level Hi Hi, P602-A13 2-1 Suppression Pool Level Hi/Low, P601-A11 2-3 and P601-A12 2-3 RHR-A Pump Room Water Level High (EOP entry), 3P601-A4 5-3 Refers to ARPs as necessary.
T=45               BOP         Acknowledges alarms associated with lowering Suppression Pool level and rising water level in RHR-A Pump Room as they occur:
* Leak Det Reactor Bldg Floor Sump R1 Leakage high, P601-A3 2-7
* Sump R1 Level Hi Hi, P602-A13 2-1
* Suppression Pool Level Hi/Low, P601-A11 2-3 and P601-A12 2-3
* RHR-A Pump Room Water Level High (EOP entry), 3P601-A4 5-3 Refers to ARPs as necessary.
Reports Suppression Pool level dropping giving actual level.
Reports Suppression Pool level dropping giving actual level.
Reports EOP entry into PPM 5.2.1 on low suppression pool level when level drops to -2".
Reports EOP entry into PPM 5.2.1 on low suppression pool level when level drops to -2.
Reports EOP entry into PPM 5.3.1 when RHR-A Room Level alarm  
Reports EOP entry into PPM 5.3.1 when RHR-A Room Level alarm annunciates (and BISI) (EOP entry is +6 inches above floor).
 
SRO         Directs field investigation by OPS2.
annunciates (and BISI) (EOP entry is +6 inches above floor).
Enters PPM 5.2.1 on Suppression Pool level LT -2.
SRO Directs field investigation by OPS2.
BOP         Verifies FDR-V-607 is closed (H13-P632).
Enters PPM 5.2.1 on Suppression Pool level LT -2".
BOP Verifies FDR-V-607 is closed (H13-P632).
Refers SRO to ABN-FLOODING and ABN-RAD-SPILL as appropriate.
Refers SRO to ABN-FLOODING and ABN-RAD-SPILL as appropriate.
Page 8 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 9 of 22 ROLE-PLAY - Two minutes after being directed to investigate, report that there is a crack in the piping coming from the suppression pool to RHR-P-2A. The rupture is located between the RHR pump and the suction valve. Room level report (if requested) should be consistent with alarms in at the time. ROOM LEVEL REPORTS WILL ALWAYS BE LESS THAN +36".
Appendix D                             SCENARIO OUTLINE                                   FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 ROLE-PLAY - Two minutes after being directed to investigate, report that there is a crack in the piping coming from the suppression pool to RHR-P-2A. The rupture is located between the RHR pump and the suction valve. Room level report (if requested) should be consistent with alarms in at the time.
SRO Enters PPM 5.3.1.
ROOM LEVEL REPORTS WILL ALWAYS BE LESS THAN +36.
Refers ABN-FLOODING (and ABN-R AD-SPILL) and directs actions: Make local evacuation announcement START RHR-P-2B Pull control Power fuses for RHR-P-2A Close RHR-V-4A Monitor ECCS rooms adjacent to RHR-P-2A room for flooding May directs PPM 5.5.27 be performed by maintenance.
SRO       Enters PPM 5.3.1.
Refers ABN-FLOODING (and ABN-RAD-SPILL) and directs actions:
* Make local evacuation announcement
* START RHR-P-2B
* Pull control Power fuses for RHR-P-2A
* Close RHR-V-4A
* Monitor ECCS rooms adjacent to RHR-P-2A room for flooding May directs PPM 5.5.27 be performed by maintenance.
ROLE-PLAY - Two minutes after request to pull RHR-P-2A fuses, initiate TRIGGER 5 and report control fuses for RHR-P-2A pulled to Control Room.
ROLE-PLAY - Two minutes after request to pull RHR-P-2A fuses, initiate TRIGGER 5 and report control fuses for RHR-P-2A pulled to Control Room.
BOP Obtains key #3 from key locker and closes RHR-V-4A. Reports valve closed when appropriate. Reports SP level stops dropping when RHR-V-
BOP       Obtains key #3 from key locker and closes RHR-V-4A. Reports valve closed when appropriate. Reports SP level stops dropping when RHR-V-4A closes.
 
4A closes.
Starts RHR-P-2B by placing its C/S to START. Verifies pump operation and SW-P-1B start.
Starts RHR-P-2B by placing its C/S to START. Verifies pump operation and SW-P-1B start.
ROLE-PLAY - If asked, the final level report will depend on actual SP level decrease (but will always be LT 36") (Use 1" drop in SP level is 1 inch rise in room flooding level).
ROLE-PLAY - If asked, the final level report will depend on actual SP level decrease (but will always be LT 36) (Use 1 drop in SP level is 1 inch rise in room flooding level).
SRO Reviews Tech Specs for RHR-V-4A not being full open. TS 3.5.1 (Condition A applies - restore within 7 days), 3.6.1.5 (Condition A  
SRO       Reviews Tech Specs for RHR-V-4A not being full open. TS 3.5.1 (Condition A applies - restore within 7 days), 3.6.1.5 (Condition A applies - restore within 7 days), and 3.6.2.3 (Condition A applies -
 
applies - restore within 7 days), and 3.6.2.3 (Condition A applies -  
 
restore within 7 days) apply in Mode 1.
restore within 7 days) apply in Mode 1.
Tech Spec for SP Water level is 3.6.2.2A.
Tech Spec for SP Water level is 3.6.2.2A.
Conducts brief.
Conducts brief.
COMMENTS: Note: SP/T high alarm received due to uncovering of the detector at 9".
COMMENTS: Note: SP/T high alarm received due to uncovering of the detector at 9.
Page 9 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 10 of 22 Event No. 6  
Appendix D                             SCENARIO OUTLINE                                 FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 6


== Description:==
==
Description:==
Performs PPM 5.5.23 to fill Suppression Pool with HPCS.
Performs PPM 5.5.23 to fill Suppression Pool with HPCS.
This event initiated by the SRO per EOP PPM 5.2.1.
This event initiated by the SRO per EOP PPM 5.2.1.
Time Position Applicants Actions or Behavior SRO Directs Suppression Pool level be raised to 0" per PPM 5.5.23.
Time           Position                         Applicants Actions or Behavior SRO       Directs Suppression Pool level be raised to 0 per PPM 5.5.23.
T=50 BOP Pulls PPM 5.5.23 and performs the following:
T=50               BOP       Pulls PPM 5.5.23 and performs the following:
Ensure HPCS-V-1 is opened Start HPCS-P-1 and ensure HPCS-V-12 opens Starts HPCS-P-2 (Service Water Pump)
* Ensure HPCS-V-1 is opened
Open HPCS-V-23 to raise flow to suppression pool to 7175 gpm and verifies HPCS-V-12 closes When suppression pool level reaches 0 inches, closes HPCS-V-
* Start HPCS-P-1 and ensure HPCS-V-12 opens
 
* Starts HPCS-P-2 (Service Water Pump)
23 and ensures HPCS-V-12 opens Stops HPCS-P-1 and ensures HPCS-V-12 closes.
* Open HPCS-V-23 to raise flow to suppression pool to 7175 gpm and verifies HPCS-V-12 closes
* When suppression pool level reaches 0 inches, closes HPCS-V-23 and ensures HPCS-V-12 opens
* Stops HPCS-P-1 and ensures HPCS-V-12 closes.
Reports suppression pool level to SRO.
Reports suppression pool level to SRO.
Comments:  
Comments:
Page 10 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 11 of 22 Event No. 7  
Appendix D                             SCENARIO OUTLINE                               FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 7


== Description:==
==
Description:==
RRC-P-1A High Vibration alarms followed by LOCA requires manual scram prior to automatic scram at 1.68 psig drywell pressure. High Drywell EOP Entry into PPM 5.1.1 and re-entry into 5.2.1.
RRC-P-1A High Vibration alarms followed by LOCA requires manual scram prior to automatic scram at 1.68 psig drywell pressure. High Drywell EOP Entry into PPM 5.1.1 and re-entry into 5.2.1.
The event is MANUALLY initiated with TRIGGER 6. Time Position Applicants Actions or Behavior T=70 RO Acknowledges RRC-P-1A high vibration alarm, P602-A6 2-4 and refers to ARP. Refers SRO to SOP-RRC-SINGLE LOOP or SOP-RRC-SHUTDOWN.
The event is MANUALLY initiated with TRIGGER 6.
SRO Directs local investigation.
Time       Position                           Applicants Actions or Behavior T=70             RO         Acknowledges RRC-P-1A high vibration alarm, P602-A6 2-4 and refers to ARP.
Refers SRO to SOP-RRC-SINGLE LOOP or SOP-RRC-SHUTDOWN.
SRO         Directs local investigation.
ROLE-PLAY: A minute after being sent report vibration readings pegged high on all channels.
ROLE-PLAY: A minute after being sent report vibration readings pegged high on all channels.
Reports annunciators as the occur: Motor Bearing Oil Level High Outer Seal Leakage High Leak Detection Drywell Floor Drain Flow High Staging Flow Hi/Lo RECIRC A or B Pump/Motor Temp High EOP entry into PPM 5.3.1 on Rx. Bldg High Rad (ARM-RIS-13 reading approximately 200mr/hr)
Reports annunciators as the occur:
SRO Based on annunciators present, may direct tripping of RRC-P-1A.  
* Motor Bearing Oil Level High
* Outer Seal Leakage High
* Leak Detection Drywell Floor Drain Flow High
* Staging Flow Hi/Lo
* RECIRC A or B Pump/Motor Temp High
* EOP entry into PPM 5.3.1 on Rx. Bldg High Rad (ARM-RIS-13 reading approximately 200mr/hr)
SRO         Based on annunciators present, may direct tripping of RRC-P-1A.
Page 11 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 12 of 22 BOP/RO Reports Suppression Pool High/Low alarms.
Appendix D                   SCENARIO OUTLINE                               FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 BOP/RO Reports Suppression Pool High/Low alarms.
Reports rising Drywell pressure and High Drywell Pressure Alert annunciator when it annunciates.
Reports rising Drywell pressure and High Drywell Pressure Alert annunciator when it annunciates.
Reports Reactor Building high rad annunciator when it alarms as an EOP  
Reports Reactor Building high rad annunciator when it alarms as an EOP entry.
 
SRO   May directs a reactor scram prior to 1.68 psig scram.
entry. SRO May directs a reactor scram prior to 1.68 psig scram.
RO   Inserts a manual scram and performs immediate scram actions:
RO Inserts a manual scram and performs immediate scram actions: Places Reactor Mode Switch in SHUTDOWN Monitors Power, Pressure, and Level Verifies all rods inserted Inserts IRMs and SRMs by depressing INSERT P/B Reports EOP entry on low RPV water level.
* Places Reactor Mode Switch in SHUTDOWN
SRO Enters PPM 5.1.1 on Low RPV level.
* Monitors Power, Pressure, and Level
BOP Recognizes and calls out Drywell pressure 1.68 EOP entry (and other PPM 5.2.1 entries as they occur).
* Verifies all rods inserted
SRO Enters PPM 5.2.1 and re-enters PPM 5.1.1 on high drywell pressure. Directs PPM 3.3.1 performance.
* Inserts IRMs and SRMs by depressing INSERT P/B Reports EOP entry on low RPV water level.
Directs RPV level controlled +13" to +54" with available systems.
SRO   Enters PPM 5.1.1 on Low RPV level.
RO Lines up on Startup Flow Control Valves using quick card: Place RFW-LIC-600 in MANUAL (if RFW pumps running)
BOP   Recognizes and calls out Drywell pressure 1.68 EOP entry (and other PPM 5.2.1 entries as they occur).
Place RFW-SC-601A and 601B in MDEM (If pumps running)  
SRO   Enters PPM 5.2.1 and re-enters PPM 5.1.1 on high drywell pressure.
 
Directs PPM 3.3.1 performance.
Appendix D                                          SCENARIO OUTLINE                                        FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 13 of 22 If RFW pump trips on 54.5" may have to restart it (per Quick Card): 2.1.1 If desired then transfer RPV level control to RFW-FCV-10A/10B per SOP-RFW-FCV-QC. Otherwise N/A 2.1.2 If performing this section following a reactor scram, then verify RFW-V-112A and RFW-V-112B have started to close. Otherwise N/A 2.1.3 Verify MSIVs are open 2.1.4 Verify at least two high level seal ins are reset (H13-P601) 2.1.5 Verify RFW-SC-601A(B) is in MDVP at 0% (Speed
Directs RPV level controlled +13 to +54 with available systems.
RO   Lines up on Startup Flow Control Valves using quick card:
* Place RFW-LIC-600 in MANUAL (if RFW pumps running)
* Place RFW-SC-601A and 601B in MDEM (If pumps running)
Page 12 of 22


Controller)(H13-P601) 2.1.6 Hold the trip/reset switch to reset until the HP and LP stop valves  
Appendix D            SCENARIO OUTLINE                                    FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 If RFW pump trips on 54.5 may have to restart it (per Quick Card):
2.1.1 If desired then transfer RPV level control to RFW-FCV-10A/10B per SOP-RFW-FCV-QC. Otherwise N/A 2.1.2 If performing this section following a reactor scram, then verify RFW-V-112A and RFW-V-112B have started to close. Otherwise N/A 2.1.3 Verify MSIVs are open 2.1.4 Verify at least two high level seal ins are reset (H13-P601) 2.1.5 Verify RFW-SC-601A(B) is in MDVP at 0% (Speed Controller)(H13-P601) 2.1.6 Hold the trip/reset switch to reset until the HP and LP stop valves indicate full open (H13-P840)
Raise turbine speed using RFW-SC-601A(B) in MDVP (turbine will roll on Main Steam at approximately 60% GV position) 2.1.8 Transfer RFW-SC-601A(B) to MDEM as soon as practical (GT 800 rpm) 2.1.9 If performing this section following a reactor scram, then verify RFW-V-112A and RFW-V-112B are fully closed. Otherwise N/A 2.1.10 Verify feedwater lineup appropriate for plant conditions 2.1.11 Raise turbine speed to raise RFP discharge pressure as necessary to control RPV level Page 13 of 22


indicate full open (H13-P840)
Appendix D                   SCENARIO OUTLINE                                   FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1
Raise turbine speed using RFW-SC-601A(B) in MDVP (turbine will roll on Main Steam at approximately 60% GV position) 2.1.8 Transfer RFW-SC-601A(B) to MDEM as soon as practical (GT 800 rpm)  2.1.9 If performing this section following a reactor scram, then verify RFW-V-112A and RFW-V-112B are fully closed. Otherwise N/A 2.1.10 Verify feedwater lineup appropriate for plant conditions 2.1.11 Raise turbine speed to raise RFP discharge pressure as necessary
* Close RFW-V-112A and 112B
 
* Adjust RFW speed to maintain GT 100 psid on startup valve
to control RPV level
* Adjust RFW-LIC-620 to control level and place in AUTO when RPV/L is 36 inches Maintains RPV level with available systems.
 
SRO   Directs Isolations, Initiations and DG starts be verified for +13 and 1.68 psig. (Refer to Event 8)
Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 14 of 22 Close RFW-V-112A and 112B Adjust RFW speed to maintain GT 100 psid on startup valve Adjust RFW-LIC-620 to control level and place in AUTO when RPV/L is 36 inches Maintains RPV level with available systems.
SRO Directs Isolations, Initiations and DG starts be verified for +13" and 1.68 psig. (Refer to Event 8)
RO/BOP Notes B RRC Pump running with no RCC running. Informs SRO and requests to stop RRC pump.
RO/BOP Notes B RRC Pump running with no RCC running. Informs SRO and requests to stop RRC pump.
May reports RRC-P-1A tripped.
May reports RRC-P-1A tripped.
SRO Directs RRC-P-1B be stopped.
SRO   Directs RRC-P-1B be stopped.
RO/BOP Stops pump by depressing STOP P/B and reports to SRO.
RO/BOP Stops pump by depressing STOP P/B and reports to SRO.
SRO May direct RPV pressure reduction to reduce leak rate.
SRO   May direct RPV pressure reduction to reduce leak rate.
NOTE: approximately 17 minutes after Trigger 6 is initiated, the MSIVs will close on MS Tunnel Temp High. SRO would then direct pressure  
NOTE: approximately 17 minutes after Trigger 6 is initiated, the MSIVs will close on MS Tunnel Temp High. SRO would then direct pressure control with SRVs.
BOP  Maintains RPV Pressure at directed pressure band.
COMMENTS:
Page 14 of 22


control with SRVs.
Appendix D                                 SCENARIO OUTLINE                                   FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 8
BOP Maintains RPV Pressure at directed pressure band.
COMMENTS: 
 
Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 15 of 22 Event No. 8  
 
== Description:==


==
Description:==
EDRV-19 fails to Auto Close on 1.68 psig Drywell pressure signal.
EDRV-19 fails to Auto Close on 1.68 psig Drywell pressure signal.
This event is inserted at the beginning of the scenario.
This event is inserted at the beginning of the scenario.
Time Position Applicants Actions or Behavior SRO Directs Isolations, Initiations and DG starts be verified for +13" and 1.68 psig. BOP Verifies Isolations, Initiations and DG starts be verified for +13" and 1.68 psig.
Time           Position                           Applicants Actions or Behavior SRO         Directs Isolations, Initiations and DG starts be verified for +13 and 1.68 psig.
BOP Notes EDR-V-19 failed to close and manually closes EDR-V-19 by taking control switch to close. Notes it does go closed.
BOP         Verifies Isolations, Initiations and DG starts be verified for +13 and 1.68 psig.
BOP Reports to SRO that EDR-V-19 fa iled to isolate on 1.68 psig isolation signal but was closed manually.
BOP         Notes EDR-V-19 failed to close and manually closes EDR-V-19 by taking control switch to close. Notes it does go closed.
BOP         Reports to SRO that EDR-V-19 failed to isolate on 1.68 psig isolation signal but was closed manually.
Reports remainder of isolations, Initiations and DG starts have been verified.
Reports remainder of isolations, Initiations and DG starts have been verified.
COMMENTS:  
COMMENTS:
Page 15 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 16 of 22 Event No. 9  
Appendix D                               SCENARIO OUTLINE                                 FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 9


== Description:==
==
Breaker for RHR-V-17B trips when C/S taken to open results in the inability to spray drywell. This event is inserted at the beginning of the scenario.
Description:==
Time Position Applicants Actions or Behavior T=85 BOP Provides EOP entry conditions into PPM 5.2.1 as they occur.
Breaker for RHR-V-17B trips when C/S taken to open results in the inability to spray drywell.
This event is inserted at the beginning of the scenario.
Time         Position                           Applicants Actions or Behavior T=85               BOP         Provides EOP entry conditions into PPM 5.2.1 as they occur.
Reports Wetwell pressure when GT 2 psig.
Reports Wetwell pressure when GT 2 psig.
SRO Directs Wetwell Sprays be initiated with RHR-P-2B.
SRO         Directs Wetwell Sprays be initiated with RHR-P-2B.
Directs sprays be terminated when WW/P drops below 1.68 psig.
Directs sprays be terminated when WW/P drops below 1.68 psig.
BOP Initiates Wetwell sprays by opening RHR-V-27B.
BOP         Initiates Wetwell sprays by opening RHR-V-27B.
Reports Wetwell sprays initiated.
Reports Wetwell sprays initiated.
BOP Reports Wetwell pressure when it is GT 12 psig (Approximately 11 minutes after Trigger 6 initiates).
BOP         Reports Wetwell pressure when it is GT 12 psig (Approximately 11 minutes after Trigger 6 initiates).
SRO Ensures parameters are within DSIL, WW/L LT 51', RRC pumps are stopped (RRC-P-1B) and directs Drywell Cooling Fans be secured.
SRO         Ensures parameters are within DSIL, WW/L LT 51, RRC pumps are stopped (RRC-P-1B) and directs Drywell Cooling Fans be secured.
RO/BOP Stops Drywell Cooling Fans and reports completion to SRO.
RO/BOP         Stops Drywell Cooling Fans and reports completion to SRO.
SRO Directs Drywell sprays be initiated with RHR-P-2B.
SRO         Directs Drywell sprays be initiated with RHR-P-2B.
BOP Checks DSIL and opens RHR-V-16B and attempts to open RHR-V-17B.  
BOP         Checks DSIL and opens RHR-V-16B and attempts to open RHR-V-17B.
Page 16 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 17 of 22 BOP Notes that RHR-V-17B lost position indication as soon as the valve C/S was positioned. Reports condition to SRO.
Appendix D                             SCENARIO OUTLINE                                   FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 BOP         Notes that RHR-V-17B lost position indication as soon as the valve C/S was positioned. Reports condition to SRO.
SRO Sets Wetwell Pressure, Wetwell Level (PSP) and Drywell Temperature as a KEY parameters due to inability to spray.
SRO         Sets Wetwell Pressure, Wetwell Level (PSP) and Drywell Temperature as a KEY parameters due to inability to spray.
RO/BOP Reports Drywell Temperature as it rises towards 330°F.
RO/BOP       Reports Drywell Temperature as it rises towards 330°F.
Reports trend of parameters as it approaches PSP limits.
Reports trend of parameters as it approaches PSP limits.
RO/BOP If RCIC was initiated for level control, it may trip on high backpressure.
RO/BOP       If RCIC was initiated for level control, it may trip on high backpressure.
ROLE-PLAY - If asked to manually open RHR-V-17B, wait five minutes and report valve is stuck in the closed position and you can not get it opened.
ROLE-PLAY - If asked to manually open RHR-V-17B, wait five minutes and report valve is stuck in the closed position and you can not get it opened.
COMMENTS:  
COMMENTS:
Page 17 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 18 of 22 Event No. 10  
Appendix D                               SCENARIO OUTLINE                               FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 10


== Description:==
==
Description:==
Initiates an EMERGENCY DEPRESSURIZATION when Drywell Temperature approaches 330°F or PSP is exceeded.
Initiates an EMERGENCY DEPRESSURIZATION when Drywell Temperature approaches 330°F or PSP is exceeded.
This event is initiated when it is determined that Drywell Temperature cannot be maintained LT 330°F or PSP is exceeded.
This event is initiated when it is determined that Drywell Temperature cannot be maintained LT 330°F or PSP is exceeded.
Critical step is to initiate an EMERGENCY DEPRESSURIZATION when drywell Temperature cannot be restored and maintained LT 330°F or when PSP has been exceeded.
Critical step is to initiate an EMERGENCY DEPRESSURIZATION when drywell Temperature cannot be restored and maintained LT 330°F or when PSP has been exceeded.
Time Position Applicants Actions or Behavior T=90 BOP Reports Drywell Temperature as it approaches 330°F(Approximately 16 minutes after Trigger 6 initiated DW/T reaches 330°F).
Time         Position                           Applicants Actions or Behavior T=90               BOP         Reports Drywell Temperature as it approaches 330°F(Approximately 16 minutes after Trigger 6 initiated DW/T reaches 330°F).
Reports WW Pressure and WW Level as they apply to PSP curve.
Reports WW Pressure and WW Level as they apply to PSP curve.
SRO When Drywell Temperature cannot be maintained below 330°F or when PSP is exceeded, determines that an ED is required:
SRO         When Drywell Temperature cannot be maintained below 330°F or when PSP is exceeded, determines that an ED is required:
Follows overrides to PPM 5.1.3, Emergency RPV Depressurization.
Follows overrides to PPM 5.1.3, Emergency RPV Depressurization.
Directs ECCS pumps not required for adequate core cooling be stopped from injecting.
Directs ECCS pumps not required for adequate core cooling be stopped from injecting.
RO/BOP Stops ECCS injection as necessary to maintain RPV level.  
RO/BOP         Stops ECCS injection as necessary to maintain RPV level.
Page 18 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 19 of 22 SRO Requests Wetwell Level and when reported GT 17 foot, directs seven SRVs, ADS preferred, be opened.
Appendix D                         SCENARIO OUTLINE                                 FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 SRO       Requests Wetwell Level and when reported GT 17 foot, directs seven SRVs, ADS preferred, be opened.
RO/BOP Opens seven ADS SRVs as directed and reports completion to SRO.
RO/BOP     Opens seven ADS SRVs as directed and reports completion to SRO.
SRO Directs RPV/L maintenance +13 inches to +54 inches.
SRO       Directs RPV/L maintenance +13 inches to +54 inches.
Termination Cue: The scenario can be terminated when the reactor has been Emergency Depressurized and RPV level is under control in the band of +13 inches to +54 inches.
Termination Cue: The scenario can be terminated when the reactor has been Emergency Depressurized and RPV level is under control in the band of +13 inches to +54 inches.
Comments:  
Comments:
Page 19 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 20 of 22 SRO TURNOVER INFORMATION Initial Conditions:
Appendix D                   SCENARIO OUTLINE                     FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 SRO TURNOVER INFORMATION Initial Conditions: Columbia is at approximately 85% power due to an economic dispatch request from BPA. REA-FN-1A is OOS due to bearing replacement. REA-FN-1B is protected.
Columbia is at approximately 85% power due to an economic dispatch request from BPA. REA-FN-1A is OOS due to bearing replacement. REA-FN-1B is protected.
Turnover: Increase Reactor Power to 90% power with flow. The reactivity brief has been completed and there are no preconditioning limits associated with the power/flow increase.
Turnover: Increase Reactor Power to 90% power with flow. The reactivity brief has been completed and there are no preconditioning limits associated with the  
SIMULATOR SETUP INSTRUCTIONS Reset to IC-120 Tag REA-FN-1A Protect REA-FN-1B Ensure CRD-P-1A is running with dot above it Ensure Bat 2006scenario1A.txt is in BATCH directory Page 20 of 22


power/flow increase.
Appendix D                    SCENARIO OUTLINE                      FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 2006scenario1.txt
SIMULATOR SETUP INSTRUCTIONS Reset to IC-120 Tag REA-FN-1A Protect REA-FN-1B Ensure CRD-P-1A is running with dot above it Ensure Bat 2006scenario1A.txt is in BATCH directory
>RON HAYDEN
>
>This scenario starts out at a reduced power level (approx 85%).
>
>Load this batch file by first initializing the simulator to AN 85% IC,
>then go to expert and type "BAT 2006scenario1.txt" and hit enter.
>
>Note: The following Batch Files need to be in the OPENSIM Batch
>file directory:  2006scenario#1.txt; 2006scenario1A.txt
>
>*************************
>* Trigger list *
>*************************
>
> Trigger 1: Accumulator Alarm Control Rod 14-23
> Trigger 2: Failure of RFW-P-AOP/1A to Auto start
> Trigger 3: CRD-P-1A reduced head followed by pump trip
> Trigger 4: RHR A Suction line rupture
> Trigger 5: Rackout RHR-P-2A
> Trigger 6: RRC-P-1A Pump Fails and LOCA
> Trigger 7: Conditional for RHR-V-17A control power fuses failing
> Trigger 11: Conditional to delete RFW-P-AOP/1A events
>
>**********************************************************************
>The following items setup conditions for the beginning of the scenario
>**********************************************************************
>
>REA-FN-1A Racked out IRF LOA-EPS330 RACKED-OUT
>
>EDR-V-19 Fails to Auto Close IMF AOV-SCN002F 3
>
>**********************************************************************
>The following items are triggered in the scenario
>**********************************************************************
>
> Trigger 1
>Accumulator alarm on control rod 14-23 IMF MAL-CRD001-1423 (1)
>
>Trigger 2
>RFW-A CONTROL OIL PRESS METER SIGNAL IOR IND-FPT015 (2) 68 120
>RFW-A BEARING OIL PRESS METER SIGNAL IOR IND-FPT016 (2) 18 120
> ANN-840A1E02 TURB A LUBE OIL PRESS LOW IMF ANN-840A1E01 (2 110) 0
>
> Trigger 3
>CRD-P-1A REDUCED HEAD IMF PMP-CRD001H (3) 100 1200
>
> CRD-P-1A SHAFT SEIZURE/TRIP IMF PMP-CRD001S (3 360) TRUE Page 21 of 22


Appendix D                                           SCENARIO OUTLINE                                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 21 of 22 2006scenario1.txt
Appendix D                     SCENARIO OUTLINE                     FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1
>RON HAYDEN
>
> >This scenario starts out at a reduced power level (approx 85%).
> Trigger 4
> >Load this batch file by first initializing the simulator to AN 85% IC, >then go to expert and type "BAT 2006scenario1.txt" and hit enter.
> RHR A Suction line rupture IMF MAL-RHR001 (4) 8400 180
> >Note: The following Batch Files need to be in the OPENSIM Batch 
>
>file directory:  2006scenario#1.txt; 2006scenario1A.txt
>Trigger 5
> >*************************
> Rackout RHR-P-2A Breaker IRF LOA-EPS384 (5) RACKED-OUT
>* Trigger list *
>
>*************************
> Trigger 6
> > Trigger 1: Accumulator Alarm Control Rod 14-23
> RRC-P-1A High Vibration/Pump Failure/LOCA IMF MAL-RRP002A (6) 16
> Trigger 2: Failure of RFW-P-AOP/1A to Auto start
> RRC-P-1A Low Bearing Oil Level Alarm IMF ANN-602A6A03 (6 30) 0
> Trigger 3: CRD-P-1A reduced head followed by pump trip
> RRC-P-1A Lower Seal failure IMF MAL-RRP001A (6 60) 100
> Trigger 4: RHR A Suction line rupture
> RRC-P-1A Upper Seal Failure IMF MAL-RRP001C (6 60) 100
> Trigger 5: Rackout RHR-P-2A
> RRC-P-1A Shaft Seizure trip IMF PMP-RRP001S (6 180) TRUE
> Trigger 6: RRC-P-1A Pump Fails and LOCA
> Small LOCA IMF MAL-RRS004A (6 90) .4 300
> Trigger 7: Conditional for RHR-V-17A control power fuses failing
>
> Trigger 11: Conditional to delete RFW-P-AOP/1A events
> Large Steam Leak in Containment IMF MAL-RRS009A (6 600) 30900000 900
> >**********************************************************************
>
>The following items setup conditions for the beginning of the scenario 
>**********************************************************************
>**********************************************************************
>The following items are set up for conditionals
> >REA-FN-1A Racked out IRF LOA-EPS330 RACKED-OUT
>**********************************************************************
> >EDR-V-19 Fails to Auto Close IMF AOV-SCN002F 3 
>
> >**********************************************************************
> RHR-V-17B control power fails when red light illuminates IMF MOV-RHR011F (7) 0 TRGSET 7 "X01I276P.GT.0"
>The following items are triggered in the scenario
>
>**********************************************************************
>Delete RFW-P-AOP/1A events on AOP switch to Run position TRG 11 "bat 2006scenario1A.txt" TRGSET 11 "X8Ai154R.eq.1"
> > Trigger 1 
>
>Accumulator alarm on control rod 14-23 IMF MAL-CRD001-1423 (1)
>**********************************************************************
> >Trigger 2
>The following set up triggers to initiate batch files
>RFW-A  CONTROL OIL PRESS METER SIGNAL IOR IND-FPT015 (2) 68 120
>**********************************************************************
>RFW-A  BEARING OIL PRESS METER SIGNAL IOR IND-FPT016 (2) 18 120
>
> ANN-840A1E02  TURB A LUBE OIL PRESS LOW IMF ANN-840A1E01 (2 110)  0 
>Local Bat file loads generic triggers for local plant actions bat local.txt 2006scenario1A.txt
> > Trigger 3 
>
>CRD-P-1A REDUCED HEAD IMF PMP-CRD001H (3) 100 1200
> This file supplements 2006scenario1 and deletes overrides and
> > CRD-P-1A SHAFT SEIZURE/TRIP IMF PMP-CRD001S (3 360)  TRUE Appendix D                                          SCENARIO OUTLINE                                        FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Page 22 of 22
>malfunctions associated with failure of RFW-AOP to auto start.
> > Trigger 4  
>
> RHR A Suction line rupture IMF MAL-RHR001 (4) 8400 180  
>Remove overrides for RFW-A Control Oil Pressure meter DOR IND-FPT015 DOR IND-FPT016 DMF ANN-840A1E01 Page 22 of 22
> >Trigger 5  
> Rackout RHR-P-2A Breaker IRF LOA-EPS384 (5) RACKED-OUT  
> > Trigger 6
> RRC-P-1A High Vibration/Pump Failure/LOCA IMF MAL-RRP002A (6) 16  
> RRC-P-1A Low Bearing Oil Level Alarm IMF ANN-602A6A03 (6 30) 0  
> RRC-P-1A Lower Seal failure IMF MAL-RRP001A (6 60) 100  
> RRC-P-1A Upper Seal Failure IMF MAL-RRP001C (6 60) 100  
> RRC-P-1A Shaft Seizure trip IMF PMP-RRP001S (6 180) TRUE  
> Small LOCA IMF MAL-RRS004A (6 90) .4 300  
> > Large Steam Leak in Containment IMF MAL-RRS009A (6 600) 30900000 900  
> >**********************************************************************  
>The following items are set up for conditionals  
>**********************************************************************  
> > RHR-V-17B control power fails when red light illuminates IMF MOV-RHR011F (7) 0 TRGSET 7 "X01I276P.GT.0" > >Delete RFW-P-AOP/1A events on AOP switch to Run position TRG 11 "bat 2006scenario1A.txt" TRGSET 11 "X8Ai154R.eq.1" > >**********************************************************************  
>The following set up triggers to initiate batch files  
>**********************************************************************  
> >Local Bat file loads generic triggers for local plant actions bat local.txt 2006scenario1A.txt  
> > This file supplements 2006scenario1 and deletes overrides and  
>malfunctions associated with failure of RFW-AOP to auto start.  
> >Remove overrides for RFW-A Control Oil Pressure meter DOR IND-FPT015 DOR IND-FPT016 DMF ANN-840A1E01


Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Facility: Columbia                               Scenario No:     2 Examiners:       Operators:
Appendix D                             SCENARIO OUTLINE                         FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Facility: Columbia                             Scenario No:   2 Examiners:                                           Operators:
Initial conditions: Columbia is operating at full power. CAS-C-1C is tagged out for motor replacement.
Initial conditions: Columbia is operating at full power. CAS-C-1C is tagged out for motor replacement.
Turnover: Preparations are being made to perform the DG-1 quarterly surveillance. After turnover transfer SM-1 from the Normal power supply to the Startup power supply in preparation.
Turnover: Preparations are being made to perform the DG-1 quarterly surveillance. After turnover transfer SM-1 from the Normal power supply to the Startup power supply in preparation.
Event No. Timeline Event Type*
Event     Timeline   Event Type*       Event Description No.
Event Description
: 1. T=0           N (BOP)       Transfers SM-1 from Normal to Startup power per PPM 2.7.1A
: 1. T=0 N (BOP) Transfers SM-1 from Normal to Startup power per PPM 2.7.1A
: 2. T=10         I (SRO/RO)     B Flow Unit Failure (Tech Spec)
: 2. T=10 I (SRO/RO)
: 3. T=25         C (SRO/RO)     Control Rod 38-23 Drifts In (Tech Spec)
B Flow Unit Failure (Tech Spec)
R (RO)      Recirc flow is lowered to LE 80 Mlbm/hr.
: 3. T=25 C (SRO/RO)
: 4. T=40       C (SRO/BOP)     Ground on the operating TSW pump; Standby TSW pump does not start; Operating TSW pump trips on overcurrent - Total Loss of R (RO)      TSW. Recirc flow is lowered to 60 Mlbm/hr and a manual scram is inserted.
R (RO) Control Rod 38-23 Drifts In (Tech Spec)
: 5. T=45           M (ALL)       Hydraulic ATWS.
Recirc flow is lowered to LE 80 Mlbm/hr.
RPV level lowered to -65 inches to LL. (Critical Step)
: 4. T=40 C (SRO/BOP)
SLC started - Only one SLC pump starts
R (RO) Ground on the operating TSW pump; Standby TSW pump does not start; Operating TSW pump trips on overcurrent - Total Loss of TSW. Recirc flow is lowered to 60 Mlbm/hr and a manual scram is  
: 6. T=50           C (RO)       RWCU-V-4 fails to Auto close on SLC Initiation
 
: 7. T=60                         Insert Control Rods. (Critical Step)
inserted.
: 8. T=75                         EOP 5.1.2 exited, PPM 5.1.1 entered. RPV level raised +13 to
: 5. T=45 M (ALL) Hydraulic ATWS.
                                      +54.
RPV level lowered to -65 inches to LL. (Critical Step) SLC started - Only one SLC pump starts
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 20
: 6. T=50 C (RO) RWCU-V-4 fails to Auto close on SLC Initiation
: 7. T=60 Insert Control Rods. (Critical Step)
: 8. T=75 EOP 5.1.2 exited, PPM 5.1.1 entered. RPV level raised +13" to  
+54". * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 20 Appendix D                                          SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 The scenario will start with Columbia at full power. Turnover information will have the crew getting ready to support a DG-1 quarterly surveillance by transferring SM-1 from Normal to Startup power.
After the transfer a Flow Unit failure will occur. The crew should take actions to bypass it and refer
 
to Tech Specs.
The next event is a control rod drifting in. The crew should enter ABN-ROD and take actions to insert the control rod. Reactor flow will be reduced to LE 80 Mlbm/hr. Tech Specs will be
 
referenced.
The next event is a failure of the operating TSW pump. The crew will take actions to start the standby TSW pump which will not start. ABN-TSW will direct RRC flow be lowered to 60 Mlbm/hr and a manual scram be inserted. After the scram is inserted OPS1 will contact the control room and report that TSW-P-1A's breaker closed when the door to the breaker was opened.
When a scram is inserted the crew will recognize a hydraulic ATWS has occurred. PPM 5.1.1 will
 
be exited to PPM 5.1.2. RPV/L will be lowered to reduce reactor power. The crew will establish a LL (-65") and maintain RPV/L between -80" and -140".
After RPV Level drops to -50" and both RRC Pumps have tripped off, SLC will be initiated and only one of the SLC pumps will start. Additionally, RWCU-V-4 will fail to auto close but will be


closed when the control switch is taken to close.
Appendix D                              SCENARIO OUTLINE                          FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 The scenario will start with Columbia at full power. Turnover information will have the crew getting ready to support a DG-1 quarterly surveillance by transferring SM-1 from Normal to Startup power.
After the transfer a Flow Unit failure will occur. The crew should take actions to bypass it and refer to Tech Specs.
The next event is a control rod drifting in. The crew should enter ABN-ROD and take actions to insert the control rod. Reactor flow will be reduced to LE 80 Mlbm/hr. Tech Specs will be referenced.
The next event is a failure of the operating TSW pump. The crew will take actions to start the standby TSW pump which will not start. ABN-TSW will direct RRC flow be lowered to 60 Mlbm/hr and a manual scram be inserted. After the scram is inserted OPS1 will contact the control room and report that TSW-P-1As breaker closed when the door to the breaker was opened.
When a scram is inserted the crew will recognize a hydraulic ATWS has occurred. PPM 5.1.1 will be exited to PPM 5.1.2. RPV/L will be lowered to reduce reactor power. The crew will establish a LL (-65) and maintain RPV/L between -80 and -140.
After RPV Level drops to -50 and both RRC Pumps have tripped off, SLC will be initiated and only one of the SLC pumps will start. Additionally, RWCU-V-4 will fail to auto close but will be closed when the control switch is taken to close.
The crew will perform PPM 5.5.6 and PPM 5.5.1 and prevent a RCIC start by closing RCIC-V-1.
The crew will perform PPM 5.5.6 and PPM 5.5.1 and prevent a RCIC start by closing RCIC-V-1.
The crew will take actions to insert control rods and perform PPM 5.5.10 and 5.5.11. When the first Scram/Reset/Scram is attempted, all control rods will insert. The crew will exit PPM 5.1.2, stop SLC injection, and enter PPM 5.1.1. RPV/L will be returned to normal.
The crew will take actions to insert control rods and perform PPM 5.5.10 and 5.5.11. When the first Scram/Reset/Scram is attempted, all control rods will insert. The crew will exit PPM 5.1.2, stop SLC injection, and enter PPM 5.1.1. RPV/L will be returned to normal.
The scenario will be terminated when RPV/L is returned to +13' to +54" level band.
The scenario will be terminated when RPV/L is returned to +13 to +54 level band.
Page 2 of 20 Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 1
Page 2 of 20
 
Appendix D                               SCENARIO OUTLINE                         FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 1


==
==
Line 1,715: Line 1,623:
Transfers SM-1 from Normal to Startup power per PPM 2.7.1A.
Transfers SM-1 from Normal to Startup power per PPM 2.7.1A.
This event is initiated by the SRO and is given in the turnover information.
This event is initiated by the SRO and is given in the turnover information.
Time Position Applicants Actions or Behavior T=0 SRO Directs RO to transfer SM-1 from TR-N (normal power) to TR-S (Startup power) per PPM 2.7.1A.
Time           Position                           Applicants Actions or Behavior T=0             SRO         Directs RO to transfer SM-1 from TR-N (normal power) to TR-S (Startup power) per PPM 2.7.1A.
BOP Refers to PPM 2.7.1A section 5.6 and performs the following: Place CB-S1 Sync Selector switch in the MANUAL position Place CB-S1 control switch to CLOSE position Place CB-N1 control switch to TRIP position Place CB-S1 sync selector switch to OFF position Informs SRO that SM-1 is being powered from Startup.
BOP         Refers to PPM 2.7.1A section 5.6 and performs the following:
RO Monitors plant conditions COMMENTS:     Page 3 of 20 Appendix D                                          SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 2
* Place CB-S1 Sync Selector switch in the MANUAL position
* Place CB-S1 control switch to CLOSE position
* Place CB-N1 control switch to TRIP position
* Place CB-S1 sync selector switch to OFF position Informs SRO that SM-1 is being powered from Startup.
RO         Monitors plant conditions COMMENTS:
Page 3 of 20


== Description:==
Appendix D                              SCENARIO OUTLINE                                FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 2


B Flow Unit Failure - Tech Spec. The event is manually initiated by activating TRIGGER 1 after SM-1 is transferred to Startup power.
==
Time Position Applicants Actions or Behavior T=10 I (SRO/RO) Acknowledges alarms for Flow Reference Off Normal, P603-A8 3-6 and Rod Out Block and refers to ARP.
Description:==
B Flow Unit Failure - Tech Spec.
The event is manually initiated by activating TRIGGER 1 after SM-1 is transferred to Startup power.
Time         Position                             Applicants Actions or Behavior T=10       I (SRO/RO)     Acknowledges alarms for Flow Reference Off Normal, P603-A8 3-6 and Rod Out Block and refers to ARP.
Determines the B Flow Unit has failed (light illuminated on apron on P603) and informs SRO.
Determines the B Flow Unit has failed (light illuminated on apron on P603) and informs SRO.
SRO Directs backpanel status be checked.
SRO         Directs backpanel status be checked.
Directs the B Flow Unit be bypassed per ARP step.
Directs the B Flow Unit be bypassed per ARP step.
RO Bypasses B Flow Unit by placing bypass switch to the B position on P603.
RO         Bypasses B Flow Unit by placing bypass switch to the B position on P603.
Verifies bypass light illuminated for B Flow Unit. Reports alarms cleared.
Verifies bypass light illuminated for B Flow Unit. Reports alarms cleared.
SRO Refers to Tech Specs 3.3.1.1, LCS 1.3.2.1, and TS Bases page 3.3.1.1-9 for  
SRO         Refers to Tech Specs 3.3.1.1, LCS 1.3.2.1, and TS Bases page 3.3.1.1-9 for flow unit failure in Mode 1 (place in trip within 12 hours).
 
flow unit failure in Mode 1 (place in trip within 12 hours).
Contacts PSRO and conducts brief.
Contacts PSRO and conducts brief.
COMMENTS:
COMMENTS:
Page 4 of 20 Appendix D                                          SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 3
Page 4 of 20


== Description:==
Appendix D                              SCENARIO OUTLINE                          FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 3
 
==
Description:==
. Control Rod 38-23 Drift In. (Tech Spec)
. Control Rod 38-23 Drift In. (Tech Spec)
The event is manually initiated by activating TRIGGER 2 after flow unit has been bypassed/brief has occurred.
The event is manually initiated by activating TRIGGER 2 after flow unit has been bypassed/brief has occurred.
Time Position Applicants Actions or Behavior T=25 RO Acknowledges drift alarm and identifies 38-23 as having the drift light illuminated. Informs SRO of rod drift.
Time         Position                           Applicants Actions or Behavior T=25           RO           Acknowledges drift alarm and identifies 38-23 as having the drift light illuminated. Informs SRO of rod drift.
Takes immediate actions of ABN-ROD:
Takes immediate actions of ABN-ROD:
Selects rod Depress Insert or the Continuously Insert P/B Drive control rod to position 00 Release and verify rod remains full in Informs SRO of actions.
* Selects rod
BOP Pulls ARP for drifting rod and refers SRO to ABN-ROD.
* Depress Insert or the Continuously Insert P/B
SRO Per subsequent actions of ABN-R OD directs Core flow be reduced to LE 80 Mlbm/hr.
* Drive control rod to position 00
* Release and verify rod remains full in Informs SRO of actions.
BOP         Pulls ARP for drifting rod and refers SRO to ABN-ROD.
SRO         Per subsequent actions of ABN-ROD directs Core flow be reduced to LE 80 Mlbm/hr.
Directs resetting rod drift annunciator.
Directs resetting rod drift annunciator.
May direct an edge rod be selected.
May direct an edge rod be selected.
Page 5 of 20 Appendix D                                           SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 RO Reduces core flow to LT 80 Mlbm/hr.
Page 5 of 20
 
Appendix D                           SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 RO           Reduces core flow to LT 80 Mlbm/hr.
Reports Reactor Power/Pressure/Level when flow reduction is completed.
Reports Reactor Power/Pressure/Level when flow reduction is completed.
SRO Refers to Tech Spec 3.1.3 C: verifies total # of slow and inop rods is LE 8 Control rod is fully inserted within 3 hours Disarm within 4 hours ROLE PLAY - If sent to isolate 38-23 per tech spec, wait three minutes and then activate TRIGGER 3 and report CRD-V-101 and CRD-V-102 for rod 38-23 are closed.
SRO           Refers to Tech Spec 3.1.3 C:
* verifies total # of slow and inop rods is LE 8
* Control rod is fully inserted within 3 hours
* Disarm within 4 hours ROLE PLAY - If sent to isolate 38-23 per tech spec, wait three minutes and then activate TRIGGER 3 and report CRD-V-101 and CRD-V-102 for rod 38-23 are closed.
FLOOR ROLE PLAY - If asked, the Mon Run shows no thermal limits exceeded.
FLOOR ROLE PLAY - If asked, the Mon Run shows no thermal limits exceeded.
RO May selects an edge rod to minimize alarms.
RO           May selects an edge rod to minimize alarms.
COMMENTS:
COMMENTS:
Page 6 of 20 Appendix D                                          SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 4
Page 6 of 20


== Description:==
Appendix D                              SCENARIO OUTLINE                          FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 4
Ground on operating TSW pump and standby pump will not start - Total Loss of TSW. The event is manually initiated by activating TRIGGER 4 after rod tech specs are referenced.
 
Time Position Applicants Actions or Behavior T=40 BOP Acknowledges OL/Gnd alarm, investigates and reports rising amps on TSW-P-1B.
==
Description:==
Ground on operating TSW pump and standby pump will not start - Total Loss of TSW.
The event is manually initiated by activating TRIGGER 4 after rod tech specs are referenced.
Time       Position                           Applicants Actions or Behavior T=40             BOP         Acknowledges OL/Gnd alarm, investigates and reports rising amps on TSW-P-1B.
Refers SRO to ABN-TSW.
Refers SRO to ABN-TSW.
SRO Per ARP directs monitoring motor current and temperature and consider swapping to TSW-P-1A.
SRO         Per ARP directs monitoring motor current and temperature and consider swapping to TSW-P-1A.
Refers to ABN-TSW and directs TSW-P-1A start.
Refers to ABN-TSW and directs TSW-P-1A start.
Note: TSW-P-1B trips in  
BOP          Attempts to manually start TSW-P-1A, notes it does not start, and reports Note:                         actions to SRO.
TSW-P-1B trips in 1.5                          Reports trip (and lockout) of TSW-P-1B resulting a total loss of TSW.
minutes SRO          Per subsequent actions of ABN-TSW, directs RRC flow be reduced to 60 Mlbm/hr.
RO          Reduces RRC flow to 60 Mlbm/hr and reports completion to SRO.
SRO          Directs a manual scram be inserted.
BOOTH OPERATOR - After the scram is inserted and before the crew takes the MT off line, ACTIVATE TRIGGER 5 to remove overrides and start TSW-P-1A.
ROLE-PLAY: As OPS1 contact the control room and inform them that when you walked by SM-75 the breaker for TSW-P-1A closed.
COMMENTS:
Page 7 of 20


1.5 minutes BOP Attempts to manually start TSW-P-1A, notes it does not start, and reports actions to SRO.
Appendix D                                 SCENARIO OUTLINE                       FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 5
Reports trip (and lockout) of TSW-P-1B resulting a total loss of TSW.
SRO Per subsequent actions of ABN-TSW, directs RRC flow be reduced to 60 Mlbm/hr. RO Reduces RRC flow to 60 Mlbm/hr and reports completion to SRO.
SRO Directs a manual scram be inserted.
BOOTH OPERATOR - After the scram is inserted and before the crew takes the MT off line, ACTIVATE TRIGGER 5 to remove overrides and start TSW-P-1A. ROLE-PLAY: As OPS1 contact the control room and inform them that when you walked by SM-75 the breaker for TSW-P-1A closed.
COMMENTS:  Page 7 of 20 Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 5  


== Description:==
==
Description:==
Hydraulic ATWS.
Hydraulic ATWS.
This event initiated by the SRO per EOP PPM 5.1.1.
This event initiated by the SRO per EOP PPM 5.1.1.
Time Position Applicants Actions or Behavior Critical step for this event is to start SLC and lower RPV level to reduce RPV power.
Time           Position                           Applicants Actions or Behavior Critical step for this event is to start SLC and lower RPV level to reduce RPV power.
T=45 RO Manually scrams the reactor and performs immediate operator actions of PPM 3.3.1: mode switch to shutdown monitors/reports power/level/pressure Notes all rods not inserted and APRMs NOT downscale and continues with immediate scram actions:
T=45               RO         Manually scrams the reactor and performs immediate operator actions of PPM 3.3.1:
Depresses Manual Scram Pushbuttons Initiates ARI inserts SRMs/IRMs Reports EOP entry on scram required and Reactor Power GT 5%.
* mode switch to shutdown
* monitors/reports power/level/pressure
* Notes all rods not inserted and APRMs NOT downscale and continues with immediate scram actions:
* Depresses Manual Scram Pushbuttons
* Initiates ARI
* inserts SRMs/IRMs Reports EOP entry on scram required and Reactor Power GT 5%.
Reports (Hydraulic ATWS) failure to scram condition exists.
Reports (Hydraulic ATWS) failure to scram condition exists.
SRO Enters PPM 5.1.1 and exits to PPM 5.1.2 due to ATWS.
SRO         Enters PPM 5.1.1 and exits to PPM 5.1.2 due to ATWS.
Directs ADS be inhibited.
Directs ADS be inhibited.
Directs manual control of HPCS.
Directs manual control of HPCS.
BOP Places ADS override switches in INHIBIT.
BOP         Places ADS override switches in INHIBIT.
Page 8 of 20 Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Takes manual control of HPCS by holding HPCS-P-1 control switch to stop and arming and depressing manual HPCS initiation P/B.
Page 8 of 20
 
Appendix D                   SCENARIO OUTLINE                         FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Takes manual control of HPCS by holding HPCS-P-1 control switch to stop and arming and depressing manual HPCS initiation P/B.
Closes HPCS-V-4 after it is full open.
Closes HPCS-V-4 after it is full open.
SRO Directs PPM 5.5.6 (Bypassing MSIV Low RPV level and Steam Tunnel High Temp Isolations) be performed.
SRO     Directs PPM 5.5.6 (Bypassing MSIV Low RPV level and Steam Tunnel High Temp Isolations) be performed.
BOP Performs PPM 5.5.6: At P609, inserts key in MS-RMS-S84 and places to the BYPASS At P611, inserts key in MS-RMS-S85 and places to the BYPASS Verifies alarms and reports completion to SRO.
BOP     Performs PPM 5.5.6:
SRO Directs RCIC start be prevented by closing RCIC-V-1.
* At P609, inserts key in MS-RMS-S84 and places to the BYPASS
BOP Closes RCIC-V-1 and verifies TRIP annunciator.
* At P611, inserts key in MS-RMS-S85 and places to the BYPASS Verifies alarms and reports completion to SRO.
SRO Directs PPM 5.5.1 (Overriding ECCS RPV Injection Valve logic) be performed.
SRO     Directs RCIC start be prevented by closing RCIC-V-1.
BOP Performs PPM 5.5.1 by: At P625, places key for HPCS-V-4 in OVERRIDE position At P629, places key for LPCS-V-5 in OVERRIDE position Page 9 of 20 Appendix D                                          SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 At P629, places key for RHR-V-42A in OVERRIDE position At P618, places key for RHR-V-42B in OVERRIDE position At P618, places key for RHR-V-42C in OVERRIDE position Verifies alarms and updates crew when completed.
BOP     Closes RCIC-V-1 and verifies TRIP annunciator.
SRO Directs stopping and preventing all injection into RPV except from boron injection systems, RCIC and CRD.
SRO     Directs PPM 5.5.1 (Overriding ECCS RPV Injection Valve logic) be performed.
RO Stops and prevents all injection into RPV except from boron injection systems, RCIC and CRD. by lining feedwater up on startup valves using quick card: Places RFW-LIC-600 to MANUAL Places RFW-SC-601A and 601B to MDEM Closes RFW-V-112A and V-112B Opens RFW-V-118 Ensures startup valve controller in manual with a closed signal SRO Directs RPV/L be lowered to LT -65" and maintained between -80" and
BOP     Performs PPM 5.5.1 by:
* At P625, places key for HPCS-V-4 in OVERRIDE position
* At P629, places key for LPCS-V-5 in OVERRIDE position Page 9 of 20


-140". Page 10 of 20 Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 RO Reports RPV level as it drops and at -50".
Appendix D                    SCENARIO OUTLINE                          FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2
* At P629, places key for RHR-V-42A in OVERRIDE position
* At P618, places key for RHR-V-42B in OVERRIDE position
* At P618, places key for RHR-V-42C in OVERRIDE position Verifies alarms and updates crew when completed.
SRO    Directs stopping and preventing all injection into RPV except from boron injection systems, RCIC and CRD.
RO      Stops and prevents all injection into RPV except from boron injection systems, RCIC and CRD. by lining feedwater up on startup valves using quick card:
* Places RFW-LIC-600 to MANUAL
* Places RFW-SC-601A and 601B to MDEM
* Closes RFW-V-112A and V-112B
* Opens RFW-V-118
* Ensures startup valve controller in manual with a closed signal SRO    Directs RPV/L be lowered to LT -65 and maintained between -80 and
                  -140.
Page 10 of 20
 
Appendix D                     SCENARIO OUTLINE                           FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 RO       Reports RPV level as it drops and at -50.
When RPV level is LT -65, commences feeding RPV with feedwater to maintain RPV level as directed.
When RPV level is LT -65, commences feeding RPV with feedwater to maintain RPV level as directed.
BOP/RO Announces EOP entry conditions as they occur: PPM 5.2.1 on Hi DW Pressure / DW Temperature / WW Level PPM 5.3.1 on MS Tunnel Temperature Hi Hi SRO Enters PPM 5.2.1 and PPM 5.3.1 as EOP entries are announced.
BOP/RO     Announces EOP entry conditions as they occur:
Directs EOP initiations, actuations and DG starts be verified for -50 inch  
PPM 5.2.1 on Hi DW Pressure / DW Temperature / WW Level PPM 5.3.1 on MS Tunnel Temperature Hi Hi SRO       Enters PPM 5.2.1 and PPM 5.3.1 as EOP entries are announced.
Directs EOP initiations, actuations and DG starts be verified for -50 inch and 1.68 psig.
SRO      Directs pressure control with SRVs and DEH.
BOP      Control RPV Pressure as directed.
SRO      Verifies that both RRC pumps have tripped on -50 RPV/L.
Directs SLC injection.
Page 11 of 20


and 1.68 psig.
Appendix D                             SCENARIO OUTLINE                           FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 RO         Initiates SLC as directed using quick card:
SRO Directs pressure control with SRVs and DEH.
* Removes SLC key blanks and installs keys for switches
BOP Control RPV Pressure as directed.
* Places both SLC System control switches to OPER position Verifies SLC system operation and notes only one SLC pump starts when suction valves get full opened.
SRO Verifies that both RRC pumps have tripped on -50" RPV/L.
Directs SLC injection.
Page 11 of 20 Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 RO Initiates SLC as directed using quick card: Removes SLC key blanks and installs keys for switches Places both SLC System control switches to OPER position Verifies SLC system operation and notes only one SLC pump starts when suction valves get full opened.
Reports flow rate (37 gpm) and initial tank level (4800 gal).
Reports flow rate (37 gpm) and initial tank level (4800 gal).
Verifies RWCU-V-4 isolation (Refer to event 6).
Verifies RWCU-V-4 isolation (Refer to event 6).
ROLE-PLAY - If sent to investigate the SLC pump, five minutes after being sent, report nothing obviously wrong with the pump or the breaker.
ROLE-PLAY - If sent to investigate the SLC pump, five minutes after being sent, report nothing obviously wrong with the pump or the breaker.
Comments:
Comments:
Page 12 of 20 Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 6  
Page 12 of 20
 
Appendix D                                 SCENARIO OUTLINE                         FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 6


== Description:==
==
RWCU-V-4 does not close when SLC is initiated. This event is initiated active from the beginning of the scenario and becomes evident when SLC is started. Time Position Applicants Actions or Behavior T=50 RO Initiates SLC as directed.
Description:==
RO Verifies SLC system operation and notes only one SLC pump starts.
RWCU-V-4 does not close when SLC is initiated.
This event is initiated active from the beginning of the scenario and becomes evident when SLC is started.
Time         Position                             Applicants Actions or Behavior T=50               RO           Initiates SLC as directed.
RO           Verifies SLC system operation and notes only one SLC pump starts.
Reports flow rate and initial tank level.
Reports flow rate and initial tank level.
Verifies RWCU-V-4 isolation.
Verifies RWCU-V-4 isolation.
RO Notes RWCU-V-4 is still opened.
RO           Notes RWCU-V-4 is still opened.
Takes control switch to close and notes valve goes closed.
Takes control switch to close and notes valve goes closed.
RO Reports RWCU-V-4 failure to auto close to SRO.
RO           Reports RWCU-V-4 failure to auto close to SRO.
COMMENTS:
COMMENTS:
Page 13 of 20 Appendix D                                          SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 7
Page 13 of 20


== Description:==
Appendix D                                SCENARIO OUTLINE                        FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 7


==
Description:==
Inserts Control Rods (Critical Step).
Inserts Control Rods (Critical Step).
The event initiated by SRO by performance of PPM 5.1.2 flow chart.
The event initiated by SRO by performance of PPM 5.1.2 flow chart.
Time Position Applicants Actions or Behavior Critical step for this event is to insert control rods by performing PPM 5.5.10 and 5.5.11.
Time           Position                           Applicants Actions or Behavior Critical step for this event is to insert control rods by performing PPM 5.5.10 and 5.5.11.
SRO Directs PPM 5.5.10 and 5.5.11 be performed to insert rods.
SRO         Directs PPM 5.5.10 and 5.5.11 be performed to insert rods.
BOP Performs PPM 5.5.10: At P650, pulls one fuse on TB1 (FO1, FO2, FO3, or FO4)
BOP         Performs PPM 5.5.10:
At P650, pulls one fuse on TB2 (FO1, FO2, FO3, or FO4)
* At P650, pulls one fuse on TB1 (FO1, FO2, FO3, or FO4)
BOP Performs PPM 5.5.11 to insert control rods and determines Tab B and F to be performed:
* At P650, pulls one fuse on TB2 (FO1, FO2, FO3, or FO4)
BOP         Performs PPM 5.5.11 to insert control rods and determines Tab B and F to be performed:
Starts both CRD pumps (May have OPS2 place both suction and drive water filters in service per ABN-CRD-MAXFLOW.
Starts both CRD pumps (May have OPS2 place both suction and drive water filters in service per ABN-CRD-MAXFLOW.
ROLE-PLAY - Three minutes after request for ABN-CRD-MAXFLOW ACTIVATE TRIGGER 26. When trigger actions completed report completion to control room.
ROLE-PLAY - Three minutes after request for ABN-CRD-MAXFLOW ACTIVATE TRIGGER 26.
BOP Performs Tab B: Places SDV HIGH LEVEL TRIP C/S to BYPASS Notes scram cannot be reset and performs Attachment 6.11: At P611 installs jumper between RPS-RLY-K9B stud 2  
When trigger actions completed report completion to control room.
BOP         Performs Tab B:
* Places SDV HIGH LEVEL TRIP C/S to BYPASS
* Notes scram cannot be reset and performs Attachment 6.11:
* At P611 installs jumper between RPS-RLY-K9B stud 2 and RPS-RLY-K12F stud 4
* At P611 installs jumper between RPS-RLY-K9D stud 2 and RPS-RLY-K12H stud 4 Page 14 of 20


and RPS-RLY-K12F stud 4 At P611 installs jumper between RPS-RLY-K9D stud 2  
Appendix D                    SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2
* At P609 installs jumper between RPS-RLY-K9A stud 2 and RPS-RLY-K12E stud 4
* At P609 installs jumper between RPS-RLY-K9C stud 2 and RPS-RLY-K12G stud 4
* At P603 resets the scram BOOTH OPERATOR: When Scram is Reset, and the Scram Discharge Volume Vent and Drain valves are full open, activate TRIGGER 6 which deletes ATWS.
BOP    When SDV has drained for more than 2 minutes:
* Checks rod density
* Initiates a manual scram Notes all rods inserted and reports condition to SRO.
COMMENTS:
Page 15 of 20


and RPS-RLY-K12H stud 4 Page 14 of 20 Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 At P609 installs jumper between RPS-RLY-K9A stud 2 and RPS-RLY-K12E stud 4 At P609 installs jumper between RPS-RLY-K9C stud 2
Appendix D                               SCENARIO OUTLINE                           FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 8


and RPS-RLY-K12G stud 4 At P603 resets the scram BOOTH OPERATOR: When Scram is Reset, and the Scram Discharge Volume Vent and Drain valves are full open, activate TRIGGER 6 which deletes ATWS.
==
BOP When SDV has drained for more than 2 minutes: Checks rod density Initiates a manual scram Notes all rods inserted and reports condition to SRO.
Description:==
EOP 5.1.2 exited, PPM 5.1.1 entered. RPV level raised +13 to +54.
This event is initiated by report from BOP that all rods are in approximately 40 minutes after the start of the scenario.
Time          Position                          Applicants Actions or Behavior T=75                SRO        Acknowledges All rods in report and directs SLC system be secured.
RO        Stops both SLC systems by returning control switches to normal.
Reports SLC secures to SRO.
SRO        Announces exit of PPM 5.1.2 and entry into PPM 5.1.1.
Directs RPV level be raised to normal operating band of +13 inches to
                              +54 inches.
RO        Raises RPV level to band given with feed and condensate system.
Reports RPV level in band as appropriate.
Termination Cue: The scenario can be terminated when SLC has been secured and RPV level has been returned to normal operating band of +13 inches to +54 inches.
COMMENTS:
COMMENTS:
Page 15 of 20 Appendix D                                          SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 8
Page 16 of 20


== Description:==
Appendix D                            SCENARIO OUTLINE                FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 SRO TURNOVER INFORMATION Initial conditions: Columbia is operating at full power. CAS-C-1C is tagged out for motor replacement.
Turnover: Preparations are being made to perform the DG-1 quarterly surveillance. After turnover transfer SM-1 from the Normal power supply to the Startup power supply in preparation.
NRC SCENARIO #2 SETUP Reset Simulator to IC 119 Hang tags on CAS-C-1C Ensure bat files 2006scenario2A, 2B, and 2C are in the BATCH directory Put Turnover on SM Window Page 17 of 20


EOP 5.1.2 exited, PPM 5.1.1 entered. RPV level raised +13" to +54". This event is initiated by report from BOP that all rods are in approximately 40 minutes after the start of the scenario.
Appendix D                                SCENARIO OUTLINE              FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 BAT FILE 2006Sscenario2.txt
Time Position Applicants Actions or Behavior T=75 SRO Acknowledges "All rods in report" and directs SLC system be secured.
>Load this batch file by first initializing the simulator to IC-14, then
RO Stops both SLC systems by returning control switches to normal.
>go the expert mode and type "BAT 2006scenario2.txt" and hit enter.
Reports SLC secures to SRO.
>
SRO Announces exit of PPM 5.1.2 and entry into PPM 5.1.1.
>Ensure 2006scenario2.txt & 2006scenario2A.txt,
Directs RPV level be raised to normal operating band of +13 inches to
>2006Scenario2B.txt, and 2006Scenario2C.txt are in BATCH directory.
>
>*************************
>* Trigger list *
>*************************
>
> Trigger 1: B Flow Unit Failure
> Trigger 2: Control Rod 38-23 Drifts in
> Trigger 3: Isolate Control Rod 38-23
> Trigger 4: Ground on TSW-P-1B (Also puts in Hydraulic ATWS)
> Trigger 5: Clear TSW overrides and start TSW-P-1A
> Trigger 6: Clear ATWS
>
>**********************************************************************
>The following items setup conditions for the beginning of the scenario
>**********************************************************************
>
>DISC CAS-C-1C IRF LOA-EPS127 DISCONNECT
>
> TSW-P-1A Start prevented IOR OVR-TSW001E ON IOR OVR-TSW001G OFF
>
>SLC-P-1B Failure to Start IOR OVR-SLC002C OFF
>
>RWCU-V-4 Fails to Auto Close IMF MOV-RWU010F 4
>
>SET MET DATA
> ENV-RWB002 AMBIENT TEMP AT 33 FEET IRF ENV-RWB002 90
> ENV-RWB001 AMBIENT DELTA TEMP ELEV 245-33' IRF ENV-RWB001 2
> ENV-RWB007 WIND SPEED AT 33 FEET IRF ENV-RWB007 5
> ENV-RWB005 WIND SPEED AT 245 FEET Page 18 of 20


+54 inches.
Appendix D                               SCENARIO OUTLINE         FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 IRF ENV-RWB005 5
RO Raises RPV level to band given with feed and condensate system.
> ENV-RWB006 WIND DIRECTION AT 33 FEET IRF ENV-RWB006 180
Reports RPV level in band as appropriate.
> ENV-RWB004 WIND DIRECTION AT 245 FEET IRF ENV-RWB004 180
Termination Cue:  The scenario can be terminated when SLC has been secured and RPV level has been returned to normal operating band of +13 inches to +54 inches.
>
COMMENTS:
>ANN-840A4A04 CW PMP A MOTOR TRIP OFF IMF ANN-840A4A04 1
Page 16 of 20 Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 SRO TURNOVER INFORMATION Initial conditions:
> ANN-840A4B04 CW PUMP A MOTOR OL/GND OFF IMF ANN-840A4B04 1
Columbia is operating at full power. CAS-C-1C is tagged out for motor replacement.
> ANN-840A5A07 TSW PMP A MOTOR TRIP IMF ANN-840A5A07 1
Turnover: Preparations are being made to perform the DG-1 quarterly surveillance. After turnover transfer SM-1 from the Normal power supply
>
>**********************************************************************
>The following items are triggered in the scenario
>**********************************************************************
>
>Trigger 1 - B Flow Unit Failure IMF MAL-NIS006B (1) 0
>
> Trigger 2 - Control Rod 38-23 Drifts In IMF MAL-RMC004-3823 (2) 0
>
>Trigger 3 - Isolate Rod 38-23
> Isolate Control Rod 38-23 by closing CRD-V-101 and CRD-V-102 IRF LOA-CRD092 (3) CLOSE IRF LOA-CRD277 (3) CLOSE
>
>Trigger 4 - TSW-P-1B ground/trip
> TSW-P-1B WINDING GROUND IMF MOT-TSW004G (4) 60 999
> ANN-840A5H07 TSW PMP B MOTOR OL/GND IMF ANN-840A5H07 (4 5) 0
>
> ATWS IMF MAL-CRD007A1 (4) 100 IMF MAL-CRD007A2 (4) 94 IMF MAL-CRD007B1 (4) 100 IMF MAL-CRD007B2 (4) 94
>
>**********************************************************************
>The following set up triggers to initiate batch files
>**********************************************************************
>
Page 19 of 20


to the Startup power supply in preparation.
Appendix D                               SCENARIO OUTLINE           FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2
NRC SCENARIO #2 SETUP Reset Simulator to IC 119 Hang tags on CAS-C-1C Ensure bat files 2006scenario2A, 2B, and 2C are in the BATCH directory Put Turnover on SM Window Page 17 of 20 Appendix D                                           SCENARIO OUTLINE                             FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 BAT FILE 2006Sscenario2.txt
> Trigger 5
>Load this batch file by first initializing the simulator to IC-14, then  >go the expert mode and type "BAT 2006scenario2.txt" and hit enter.
> Clear TSW Overrides and start TSW-P-1A (2B initiates 2C Bat file)
> >Ensure 2006scenario2.txt & 2006scenario2A.txt, 
TRG 5 "bat 2006scenario2B.txt"
>2006Scenario2B.txt, and 2006Scenario2C.txt are in BATCH directory.
>
> >*************************
> Trigger 6
>* Trigger list *
>Clear ATWS TRG 6 "bat 2006scenario2A.txt"
>*************************
>
> > Trigger 1: B Flow Unit Failure
>Local Bat file loads generic triggers for local plant actions bat local.txt BAT FILE 2006Sscenario2A.txt
> Trigger 2: Control Rod 38-23 Drifts in
>This file supplements 2006 Scenario#2 and clears Hydraulic ATWS DMF MAL-CRD007A1 DMF MAL-CRD007A2 DMF MAL-CRD007B1 DMF MAL-CRD007B2
> Trigger 3: Isolate Control Rod 38-23  > Trigger 4: Ground on TSW-P-1B (Also puts in Hydraulic ATWS) > Trigger 5: Clear TSW overrides and start TSW-P-1A > Trigger 6: Clear ATWS
>
> >********************************************************************** >The following items setup conditions for the beginning of the scenario
BAT FILE 2006scenario2b.txt
>**********************************************************************
>This file supplements 2006 Scenario#2 and clears TSW-P-1A
> >DISC CAS-C-1C IRF LOA-EPS127 DISCONNECT 
>Overrides and starts TSW-P-1A DOR OVR-TSW001E DOR OVR-TSW001G "bat 2006scenario2c.txt"
> > TSW-P-1A Start prevented IOR OVR-TSW001E ON IOR OVR-TSW001G OFF 
>
> >SLC-P-1B Failure to Start IOR OVR-SLC002C  OFF
BAT FILE 2006scenario2c.txt
> >RWCU-V-4 Fails to Auto Close IMF MOV-RWU010F  4
>This file supplements 2006 Scenario#2 and starts TSW-P-1A IOR OVR-TSW001G ON Page 20 of 20}}
> >SET MET DATA > ENV-RWB002  AMBIENT TEMP AT 33 FEET IRF ENV-RWB002 90 > ENV-RWB001  AMBIENT DELTA TEMP ELEV 245-33' IRF ENV-RWB001 2 > ENV-RWB007  WIND SPEED AT 33 FEET IRF ENV-RWB007 5 > ENV-RWB005  WIND SPEED AT 245 FEET Page 18 of 20 Appendix D                                          SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 IRF ENV-RWB005 5 > ENV-RWB006  WIND DIRECTION AT 33 FEET IRF ENV-RWB006 180 > ENV-RWB004  WIND DIRECTION AT 245 FEET IRF ENV-RWB004 180
> >ANN-840A4A04  CW PMP A MOTOR TRIP OFF IMF ANN-840A4A04  1  > ANN-840A4B04  CW PUMP A MOTOR OL/GND OFF IMF ANN-840A4B04  1  > ANN-840A5A07  TSW PMP A MOTOR TRIP IMF ANN-840A5A07  1 
> >********************************************************************** >The following items are triggered in the scenario
>**********************************************************************
> >Trigger 1 - B Flow Unit Failure IMF MAL-NIS006B (1)  0 
> > Trigger 2 - Control Rod 38-23 Drifts In IMF MAL-RMC004-3823 (2) 0
> >Trigger 3 - Isolate Rod 38-23
> Isolate Control Rod 38-23 by closing CRD-V-101 and CRD-V-102 IRF LOA-CRD092 (3)  CLOSE IRF LOA-CRD277 (3)  CLOSE 
> >Trigger 4 - TSW-P-1B ground/trip > TSW-P-1B WINDING GROUND IMF MOT-TSW004G (4) 60 999 > ANN-840A5H07  TSW PMP B MOTOR OL/GND IMF ANN-840A5H07 (4 5)  0 
> > ATWS IMF MAL-CRD007A1 (4) 100 IMF MAL-CRD007A2 (4) 94 IMF MAL-CRD007B1 (4) 100 IMF MAL-CRD007B2 (4) 94
> >********************************************************************** >The following set up triggers to initiate batch files
>**********************************************************************
> Page 19 of 20 Appendix D                                          SCENARIO OUTLINE                            FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2
  > Trigger 5 > Clear TSW Overrides and start TSW-P-1A (2B initiates 2C Bat file)
TRG 5 "bat 2006scenario2B.txt" > > Trigger 6 >Clear ATWS TRG 6 "bat 2006scenario2A.txt" > >Local Bat file loads generic triggers for local plant actions bat local.txt BAT FILE 2006Sscenario2A.txt  
>This file supplements 2006 Scenario#2 and clears Hydraulic ATWS DMF MAL-CRD007A1 DMF MAL-CRD007A2 DMF MAL-CRD007B1 DMF MAL-CRD007B2  
> BAT FILE 2006scenario2b.txt  
>This file supplements 2006 Scenario#2 and clears TSW-P-1A >Overrides and starts TSW-P-1A DOR OVR-TSW001E DOR OVR-TSW001G "bat 2006scenario2c.txt" > BAT FILE 2006scenario2c.txt  
>This file supplements 2006 Scenario#2 and starts TSW-P-1A IOR OVR-TSW001G ON Page 20 of 20}}

Revision as of 12:09, 23 November 2019

Generation Station - 11-2006 - Operating Exam As-Given
ML063540359
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 05/15/2006
From: Hayden R
Energy Northwest
To:
NRC Region 4
References
50-397/06-301 50-397/06-301
Download: ML063540359 (160)
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Text

2006 NRC EXAM - ADMIN JPM RO #2 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 5/15/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Get Attachment 7.1 and put two boxes to be checked. One states APRM readings ARE GT power readings extrapolated from BPV position and the other states APRM readings ARE NOT GT power readings extrapolated from BPV position.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0906 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 3.1.2 Location: Any NUREG 1123 Ref: 2.1.25 (2.8/3.1) Performance Method: Perform Page 1 of 5

VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL Columbia is in the process of starting up following a refueling outage. Current plant CONDITIONS: conditions are:

  • House Loads are equal to 1% Core Thermal Power
  • BPV#1 is indicating 95 percent open
  • BPV#2 is indicating 90 percent open
  • BPV#3 is indicating 93 percent open
  • BPV#4 is indicating 95 percent open INITIATING You have been directed by the CRS to perform step Q31 of PPM 3.1.2 Verify the CUE: APRM readings are GT power level readings extrapolated from bypass valve position per Attachment 7.1.

Present the completed Attachment 7.1 to the examiner with the table of BPV vs. % CTP filled in and a check mark applied to the appropriate box indicating if APRM readings are or are not GT power level readings extrapolated from BPV position.

Page 2 of 5

VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Fills in the following information:

BPV #1 % open is approximately 8.2 S/U BPV #2 % open is approximately 8.0 S/U BPV #3 % open is approximately 8.2 S/U BPV #4 % open is approximately 8.3 S/U House Loads 1% (given) S/U Total % CTP is approximately 33.7 S/U Indicates in attachment that APRM indicated S/U*

power levels are GT extrapolated BPV power level readings.

Termination Criteria: Candidate hands the examiner the completed Attachment 7.1 of PPM 3.1.2 and written indication that APRMs readings are GT power readings extrapolated from BPV position.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5

VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate completes table on Attachment 7.1 of PPM 3.1.2 and determines APRM readings are GT power level readings extrapolated from BPV position.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is in the process of starting up following a refueling outage.

Current plant conditions are:

  • APRMs are indicating 34% power
  • House Loads are equal to 1% Core Thermal Power
  • BPV#1 is indicating 95 percent open
  • BPV#2 is indicating 90 percent open
  • BPV#3 is indicating 93 percent open
  • BPV#4 is indicating 95 percent open Cue:

You have been directed by the CRS to perform step Q31 of PPM 3.1.2 Verify the APRM readings are GT power level readings extrapolated from bypass valve position per Attachment 7.1.

Present the completed Attachment 7.1 to the examiner with the table of BPV vs. % CTP filled in and a check mark applied to the appropriate box indicating if APRM readings are or are not GT power level readings extrapolated from BPV position.

Page 5 of 5

2006 NRC EXAM - ADMIN RO #3 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE REVIEW SURVEILLANCE PROCEDURE OSP-INST-H101 MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 5/17/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Print out a blank OSP-INST-H101 and fill in readings. At least one reading should be out of spec.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0577 Validation Time: 20 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

OSP-INST-H101 Rev. 54 Location: Any NUREG 1123 Ref: 2.2.12 (3.0/3.4) Performance Method: Perform Page 1 of 4

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL Columbia is operating at rated power. CRO2 has just completed filling out the OSP-CONDITIONS: INST-H101 checks and has asked you for a peer check.

INITIATING When you have completed your peer check of the Shift and Daily Instrument Checks CUE: (OPS-INST-H101) present them to the examiner (CRS). Circle any errors that you may have found during your review.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Notes the following Out Of Spec readings: S/U Circles out-of-tolerance readings:

  • Page 12 CMS-TE-15 (GT 150°F) S/U*
  • Page 12 CMS-TE-17 (GT 150°F) S/U*
  • Page 13 CMS-TE-16 (GT 150°F) S/U*

Termination Criteria: Candidate hands the examiner the completed OSP-INST-H101s and has circled Out-Of-Tolerance readings on page 12 and page 13.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 2 of 4

RESULTS OF JPM:

REVIEW SURVEILLANCE PROCEDURE OPS-INST-H101 Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate correctly circles the three Out-Of-Tolerance readings.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 15 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 3 of 4

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating at rated power.

CRO2 has just completed filling out the OSP-INST-H101 checks and has asked you for a peer check.

Cue:

When you have completed your peer check of the Shift and Daily Instrument Checks (OPS-INST-H101) present them to the examiner (CRS).

Circle any errors that you may have found during your review.

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2006 NRC EXAM - ADMIN RO #4 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE IF TAGOUT CAN BE HUNG (FAULTED)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 9/26/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Have a tagout for HPCS System that includes HPCS-V-4. Have a RWP that is Non-High Radiation entry with a survey map showing HPCS-V-4 in a high radiation area.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-1293 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

Location: Any NUREG 1123 Ref: 2.3.10 (2.9/3.3) Performance Method: Perform Page 1 of 5

DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL Columbia Generating Station is shutdown during outage R18.

CONDITIONS:

INITIATING You have been directed by the Control Room Supervisor to hang tagout D-HPCS-V-CUE: 102R18-001. Health Physics has been contacted and directed use of RWP-30001421 for the purpose of hanging tags in the Reactor Building.

Review the task and from the information provided, fill out the attached sheet indicating your ability (or inability) to perform the task assigned.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Fills out the attached sheet indicating that the task can not be performed due to HPCS-V-4 S/U*

being in a High Radiation area and the RWP is for Non-High Radiation plant operation/

investigation.

Termination Criteria: Candidate hands the examiner the completed attachment.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

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DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate fills out the attached sheet and indicates that the tagout can not be hung due to HPCS-V-4 being in a high radiation area and the RWP is for Non-High Rad operation/investigation.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 15 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 3 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia Generating Station is shutdown during outage R18.

Cue:

You have been directed by the Control Room Supervisor to hang tagout D-HPCS-V-102R18-001.

Health Physics has been contacted and directed use of RWP-30001421 for the purpose of hanging tags in the Reactor Building.

Review the task and from the information provided, fill out the attached sheet indicating your ability (or inability) to perform the task assigned.

Page 4 of 5

I will be able to perform the assigned task (Initial):

I will not be able to perform the assigned task (Initial and Reason):

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2006 NRC EXAM - ADMIN JPM RO/SRO #1 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 5/11/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Make a copy of the current pull sheet from the simulator. Determine where Minimum ECP is and indicate it on copy of pull sheet by placing an *1 next to the step and at the bottom of the column indicate that a *1 is Minimum ECP. Ensure it is AFTER step indicated in initial conditions.

Have a copy of PPM 3.1.2 startup flowchart available for reference.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0156; SRO-0118 Validation Time: 16 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 3.1.2 Location: Simulator/Plant/Table Top NUREG 1123 Ref: 2.1.7 3.7/4.4 Performance Method: Perform Page 1 of 6

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL A plant startup is in progress. PPM 3.1.2 has been completed as follows: Step L11 has CONDITIONS: been completed, waiting at step L12 ; Step P1 has not yet been completed; Step Q9 has been completed and step Q10 is in progress.

You are the RO pulling control rods and you note the following indications:

  • Time 0953
  • Coolant Temp 205°F
  • Neutron level 8,000 CPS and rising
  • Period 145 seconds and stable You have been pulling control rods steadily since starting Group 1 of the Pull Sheet.

Control rod motion stopped approximately 1 minute ago.

INITIATING Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your CUE: next action.

When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.

Page 2 of 6

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

SRO Position being Using given information, determines evaluated that the reactor is critical or will be critical before the minimum ECP has been reached.

Directs RO to (stop control rod withdrawal and to) drive control rods S/U*

in the reverse order until all control rods are fully inserted.

RO position being Using given information, determines evaluated that the reactor is critical or will be critical before the minimum ECP has been reached.

Notifies the CRS that he has stopped control rod withdrawal due to reactor S/U*

critical outside ECP.

SRO Candidate: To pass the JPM the candidate must state that direction is to be given to the RO to drive control rods in the reverse order until they all are inserted.

RO Candidate: To pass the JPM the candidate must state that control rod withdrawal must be stopped and that the CRS must be informed that the reactor is critical prior to the indicated minimum ECP.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 6

DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate determines early criticality and correctly identifies actions for being critical outside of the ECP per PPM 3.1.2.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 16 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

A plant startup is in progress. PPM 3.1.2 has been completed as follows:

Step L11 has been completed, waiting at step L12 ; Step P1 has not yet been completed; Step Q9 has been completed and step Q10 is in progress.

The following indications are observed:

  • Time 0953
  • Coolant Temp 205° F
  • Neutron level 8,000 CPS and rising
  • Period 145 seconds and stable Control rods have been steadily pulled since starting Group 1 of the Pull Sheet. Control rod motion stopped approximately 1 minute ago.

Cue:

Using the given information, PPM 3.1.2, and the supplied pull sheets, determine your next action.

When you have determined your next action, write it on the page provided along with the basis for the decision and hand it to the examiner.

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COLUMBIA GENERATING STATION JPM EXAM NOVEMBER 2006 NEXT ACTION TO BE TAKEN:

BASIS FOR ACTION:

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2006 NRC EXAM - ADMIN SRO #2 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 5/11/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Ensure candidate has access to a set of Volume One procedures and specifically to PPM 1.3.10B. Have a copy of the Fire Protection System Impairment Notification form ready to give to candidate after impairment is identified.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0158 Validation Time: 20 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 1.3.10B Rev. 13 Location: Simulator/Plant/Table Top NUREG 1123 Ref: 2.1.25 2.8/3.1 Performance Method: Perform Page 1 of 5

DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL As the Production SRO, you have just been informed by Plant Inspector that during an CONDITIONS: inspection of the Active Fire System in the Main Control Room, the 18 Halon system storage tanks (FP-TK-1 thru 18) were found to be 85% of full charge pressure.

INITIATING Based on the report provided determine if compensatory actions are required. Initial the CUE: attachment indicating either actions are or are not required. If actions are required indicate (on the attachment) what they are.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Refers to PPM 1.3.10B and notes at least 90% of full charge pressure is required. S/U Per PPM 1.310B 3.4.3b determines a FPSI permit needs to be issued. S/U*

CUE: Once the candidate informs the examiner that a FPSI permit is required to be completed, provide the candidate with a blank form to fill out (Attachment 8.1 of PPM 1.3.10B) and inform him that the Fire Marshall is not on site.

The FPSI permit is filled out with the following information:

  • System Impaired: Halon is checked S/U*
  • Reason for Impairment: All 18 Halon systems have storage tanks with only 85% of full charge pressure (90% is required) S/U*
  • Building/Elevation: Radwaste Building, 501 elevation S/U*
  • Compensatory Action Taken: None (Control Room continually S/U*

manned)

  • Date Impairment Occurred: Todays date is filled in S/U*

Termination Criteria: Student hands the examiner a completed FPSI permit.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 2 of 5

DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate identifies that a FPSI permit is required to be initiated and completes the form with the required information.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 20 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 3 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

As the Production SRO, you have just been informed by Plant Inspector that during an inspection of the Active Fire System in the Main Control Room, the 18 Halon system storage tanks (FP-TK-1 thru 18) were found to be 85% of full charge pressure.

Cue:

Based on the report provided determine if compensatory actions are required.

Initial the attachment indicating either actions are or are not required. If actions are required indicate (on the attachment) what they are.

Page 5 of 6

INITIAL HERE IF NO ACTIONS ARE REQUIRED:

INITIAL HERE IF ACTIONS ARE REQUIRED:

ACTIONS IF REQUIRED:

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2006 NRC EXAM - ADMIN JPM SRO #3 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DIV 1 INSTRUMENT OOS/ERROR ON DIVISION 2 TAGOUT THAT WOULD CAUSE FULL SCRAM IF HUNG SUBMITTED FOR APPROVAL MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 6/27/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DIVISION 1 INSTRUMENT OOS/DIVISION 2 INSTRUMENT TAG OUT TO SRO FOR APPROVAL MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Have appropriate INOP sheets filled out for OOS equipment; Have appropriate Tag out printed for opposite divisional equipment.

Candidate needs access to procedures and drawings.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0464; 0434 Validation Time: 20 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 1.3.64 Location: EOF / Simulator NUREG 1123 Ref: 2.2.13 (3.6/3.8) Performance Method: Perform Page 1 of 5

DIVISION 1 INSTRUMENT OOS/DIVISION 2 INSTRUMENT TAG OUT TO SRO FOR APPROVAL JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL Columbia is operating at 100% power. The following equipment are OOS: TMU-P-1C CONDITIONS: for motor inspection; APRM A which failed downscale (cause not yet determined);

MS-PS-23A which has a failed relay (RPS-RLY-K6A). The channel has been placed in a trip condition by pulling a fuse as per TSAS 3.3.1.1A. A half scram is present on the RPS A side. You have been given a clearance order to approve.

INITIATING Fill out the attachment indicating if you would approve hanging the clearance order or CUE: if you would not approve hanging the clearance order. Provide written justification to support your decision. When completed, present the filled out attachment to the examiner.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Checks block indicating clearance order is S/U*

NOT approved.

Justifies NOT approving the clearance order due to the fact that E-FUSE-H13P611/AAF7 should not be on the tag out for MS-LS-24D.

S/U*

A Division 1 equipment is OOS (MS-PS-23A) with a half scram already in on the A RPS side. The clearance order mistakenly removes E-FUSE-H13P611/AAF7, which is a Div 2 instrument that would generate a half scram on the B RPS side. Thus, if the clearance was hung, it would result in a full scram.

Termination Criteria: Student hands the examiner the completed Attachment.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 2 of 5

DIVISION 1 INSTRUMENT OOS/DIVISION 2 INSTRUMENT TAG OUT TO SRO FOR APPROVAL RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate completes the attachment checking the NOT approval block and provides appropriate justification as described in JPM.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 20 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 3 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating at 100% power.

The following equipment are OOS:

  • TMU-P-1C for motor inspection
  • APRM A which failed downscale (cause not yet determined)
  • MS-PS-23A which has a failed relay (RPS-RLY-K6A). The channel has been placed in a trip condition by pulling a fuse as per TSAS 3.3.1.1A.

A half scram is present on the RPS A side.

You have been given a clearance order to either approve or disapprove the hanging of.

Cue:

Fill out the attachment indicating if you would approve hanging the clearance order or if you would not approve hanging the clearance order.

Provide written justification to support your decision.

When completed, present the filled out attachment to the examiner.

Page 4 of 5

(Place a check mark in the appropriate box and provide justification below)

Clearance Order Approved Clearance Order NOT Approved JUSTIFICATION:

Page 5 of 5

2006 NRC EXAM - ADMIN SRO #4 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/26/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Candidate needs a calculator and access to ABN-OG.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0658 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

ABN-OG Rev. 1 Location: Simulator/Table Top NUREG 1123 Ref: 271000A2.04 (4.1) Performance Method: Perform Page 1 of 7

ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL Columbia is operating at full power. Various alarms are locked in due to suspected fuel CONDITIONS: pin damage. Offgas system parameters are as follows:

OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is reading 7721 mr/hr INITIATING Based on the above information, per ABN-OG, determine what action, if any, should be CUE: taken. Fill in the result of your conclusion on the attachment provided.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Refers to ABN-OG and, using bases for step 4.1.2 calculates the following:

S/U Main Condenser Gross gamma activity = OG-RR-604 X OG-FR-620 divided by 1000.

Main Condenser Gross gamma activity = 7721 mr/hr times 43 SCFM divided by 1000 OR S/U Main Condenser Gross gamma activity = 332.003 mCi/sec Based on a Main Condenser Gross gamma activity reading of 332 mCi/sec, candidate determines that a power reduction per PPM S/U*

3.2.4 to maintain Main Condenser Gross gamma activity LT 332 mCi/sec is required. Additionally, Technical Specification 3.7.5 should be referred to.

Termination Criteria: Student hands the examiner the completed attachment.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 2 of 7

ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE AND DETERMINE ACTIONS RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate fills out the attachment and has determined that a power reduction per PPM 3.2.4 is required to maintain Main Condenser Gross gamma activity LT 332 mCi/sec and that Technical Specification 3.7.5 should be referred to.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 3 of 7

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating at full power.

Various alarms are locked in due to suspected fuel pin damage.

Offgas system parameters are as follows:

OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm OFFGAS SYSTEM EXHAUST FLOW, OG-FR-620, is reading 43 SCFM SJAE CONDENSER OUTLET RADIATION MONITOR, OG-RR-604, is reading 7721 mr/hr Cue:

Based on the above, per ABN-OG, determine what action, if any, should be taken.

Fill in the result of your conclusion on the attachment provided.

Page 5 of 7

INITIAL HERE IF NO ACTIONS ARE REQUIRED:

INITIAL HERE IF ACTIONS ARE REQUIRED: INITIALS HERE ACTIONS IF REQUIRED: Reactor downpower per PPM 3.2.4 is required to maintain Main Condenser Gross gamma activity less that 332 mCi/sec.

Technical Specification 3.7.5 should be referred to.

Page 6 of 7

INITIAL HERE IF NO ACTIONS ARE REQUIRED:

INITIAL HERE IF ACTIONS ARE REQUIRED:

ACTIONS IF REQUIRED:

Page 7 of 7

2006 NRC EXAM - ADMIN JPM SRO #5 PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 8/17/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

2006 NRC Scenario #2 has been completed Setup Instructions:

After completion of 2006 NRC Scenario #2 this JPM is to be performed.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0529, SRO-0629 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: Yes 30 minutes PPM

Reference:

PPM 13.1.1 Location: Simulator NUREG 1123 Ref: 2.4.41 2.3/4.1 Performance Method: Perform Page 1 of 4

CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from that VALIDATION: listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL You have just been relieved as the SRO following the scenario. It is not raining outside.

CONDITIONS:

INITIATING The Shift Manager has directed you to classify the event and initiate a CNF for the just CUE: completed scenario. This will be the initial classification for this scenario. Present a completed Classification Notification Form to the examiner. This is a time critical JPM and your time starts now.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Fills in the following information:

Checks block 1a or 1b (Emergency or Drill) S/U Checks block 4.a and enters date and time S/U*

Checks block 5c (Site Area Emergency) S/U*

Block 7 enters 5 mph for Wind Speed S/U Block 7 enters 180 as Wind Direction S/U Block 7 checks No for precipitation S/U Block 7 enters Stability Class F S/U Checks block 8 No Release S/U Checks block 9 N/A S/U Checks block 10 NA S/U Checks block 11 No S/U Block 12 enters 2.2.S.1 and adds a S/U*

description S/U Checks one block 13 (a, b, or d)

Termination Criteria: Student hands the examiner the completed Classification Notification Form.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 2 of 4

CLASSIFY THE EVENTS FOR 2006 NRC DYNAMIC EXAM SCENARIO #2 (SAE)

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate completes a Classification Notification Form with the required information.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 15 Minutes / 30 minutes COMMENTS:

Evaluator's Signature: Date:

Page 3 of 4

STUDENT JPM INFORMATION CARD Initial Conditions:

You have just been relieved as the SRO following the scenario. It is not raining outside.

Cue:

The Shift Manager has directed you to classify the event and initiate a Classification Notification Form for the just completed scenario.

This will be the initial classification for this scenario.

Present the completed CNF to the examiner.

THIS IS A TIME CRITICAL JPM AND YOUR TIME STARTS NOW Page 4 of 4

2006 NRC EXAM - JPM #1 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE REMOVING HEATER 1A, 1B, AND 1C FROM SERVICE (SIMULATOR)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 9/02/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

A 100% IC Special Setup Instructions:

N/A JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

Current procedure shall be used by evaluator and student. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0377 Validation Time: 15 Minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 2.2.7 Rev. 38 Location: Simulator NUREG 1123 Ref: 259001A4.03 (2.9/3.0) Performance Method: Perform Page 1 of 5

JPM CHECKLIST PROCEDURE Regarding procedure copies for evaluator and student, if the procedure revision is VALIDATION different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL BPA has requested Columbia reduce power to 60% for economic dispatch. CRO1 is CONDITIONS: aware of the evolution and is monitoring hotwell level.

INITIATING The CRS has directed you to remove Feedwater Heaters 1A, 1B and 1C from service CUE: per PPM 2.2.7 Section 5.2. Notify the CRS when heaters 1A, 1B and 1C have been removed from service.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Candidate is given Moves selector over Record HD-LIC-1A output signal PPM 2.2.7 Section demand to get % S/U 5.2 open depresses A/M Places HD-LIC-1A in MANUAL pushbutton to S/U*

display M selects valve SLOWLY RAISE HD-LIC-1A output demand (far right) signal to 100% S/U*

and depresses the up arrow pushbutton OPEN the following:

  • HV-V-23A Startup Vent (H13-P832) S/U*
  • BS-DV-1A BS Dump (H13-P832) S/U*

depresses the down LOWER output signal on HD-LIC-1A S/U*

arrow pushbutton to 0% to CLOSE HD-LCV-1A Moves selector over Record HD-LIC-1B output signal demand to get % S/U open depresses A/M Places HD-LIC-1B in MANUAL pushbutton to S/U*

display M Page 2 of 5

selects valve SLOWLY RAISE HD-LIC-1B output demand (far right) signal to 100% S/U*

and depresses the up arrow pushbutton OPEN the following:

  • HV-V-23E Startup Vent (H13-P832) S/U*
  • BS-DV-1B BS Dump (H13-P832) S/U*

depresses the down LOWER output signal on HD-LIC-1B S/U*

arrow pushbutton to 0% to CLOSE HD-LCV-1B Moves selector over Record HD-LIC-1C output signal demand to get % S/U open depresses A/M Places HD-LIC-1C in MANUAL pushbutton to S/U*

display M selects valve SLOWLY RAISE HD-LIC-1C output demand (far right) signal to 100% S/U*

and depresses the up arrow pushbutton OPEN the following:

  • HV-V-23I Startup Vent (H13-P832) S/U*
  • BS-DV-1C BS Dump (H13-P832) S/U*

depresses the down LOWER output signal on HD-LIC-1C S/U*

arrow pushbutton to 0% to CLOSE HD-LCV-1C Termination Criteria: The operator informs the CRS that heaters 1A, 1B, and 1C have been removed from service.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5

RESULTS OF JPM:

REMOVE HEATERS 1A, 1B, AND 1C FROM SERVICE Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Heaters 1A, 1B, and 1C have been removed from service per PPM 2.2.7.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial box) Time Time 15 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

BPA has requested Columbia reduce power to 60% for economic dispatch.

Cue:

The CRS has directed you to remove Feedwater Heaters 1A, 1B and 1C from service per PPM 2.2.7 Section 5.2.

Notify the CRS when heaters 1A, 1B and 1C have been removed from service.

Page 5 of 5

2006 NRC EXAM - JPM #2 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RESTORE RPS A FROM ALTERNATE POWER SOURCE (SIMULATOR)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 9/02/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

RESTORE RPS A FROM ALTERNATE POWER SOURCE MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any IC with a normal electrical lineup - all load centers energized Ensure AR-EX-1B is in service Special Setup Instructions:

Open RPS EPA BKR 3A, acknowledge all annunciators, and allow plant to stabilize.

JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0248 Validation Time: 15 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

ABN-RPS Rev. 4 Location: SIMULATOR NUREG 1123 Ref: 212000 A4.14 (3.8/3.8) Performance Method: PERFORM Page 1 of 7

RESTORE RPS A FROM ALTERNATE POWER SOURCE JPM CHECKLIST PROCEDURE Regarding procedure copies for evaluator and student, if the procedure revision is VALIDATION different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL A loss of RPS A occurred 20 minutes ago. All maintenance and surveillance CONDITIONS: testing has been stopped. Investigation revealed a failure of the A RPS MG set motor.

INITIATING CUE: The CRS has directed you to transfer A RPS to its Alternate power supply by performing steps 4.1 through 4.8 of ABN-RPS. Inform the CRS when the subsequent actions for ABN-RPS have been completed and A RPS has been restored.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Candidate is given If power is available to RWCU-V- S/U*

ABN-RPS 104 (Cleanup System Bypass), then THROTTLE OPEN RWCU-V-104 If alternate Gland Exhaust (AR-EX-1A/B) is required then start the alternate Gland Exhauster and place N/A the tripped Gland Exhauster in OFF.

Otherwise N/A If the alternate Mechanical Vacuum Pump (AR-P-1A/B) is requires then N/A start the alternate Mechanical Vacuum Pump. Otherwise N/A Page 2 of 7

RESTORE RPS A FROM ALTERNATE POWER SOURCE ENSURE automatic actions have occurred. Verifies:

  • The following valves close:

o RRC-V-20 o FDR-V-4 o EDR-V-20 o RWCU-V-4 o RHR-V-8 o RHR-V-40 o RHR-V-75A and 75B o RHR-V-23 o RHR-V-53A and 53B o MS-V-67A-D o MS-V-19

  • RC-1 trips
  • AR-EX-1A trips
  • AR-P-1A trips
  • Refers to Attachment 7.1 for list of annunciation CUE: When Attachment 7.1 is referenced, inform candidate that another operator has verified annunciation per Attachment 7.1 and no discrepancies were noted.

IF the condition of the RPS MG set is known to be operable, then restart the RPS MG set and repower the bus N/A per PPM 2.7.6. Otherwise N/A If the condition of the RPS MG set is uncertain then repower RPS A or B from H13-P610 as follows:

  • Check power available from S/U the RPS Alternate Power Supply, MC-6B, by observing the Alternate Feed white light illuminated.
  • Place the RPS power source selector switch in the position S/U*

(ALT A) to be powered from the Alternate Supply Page 3 of 7

RESTORE RPS A FROM ALTERNATE POWER SOURCE When RPS power has been restored stabilized, then perform the following:

If restoring RPS A then perform the following:

Depresses the two Rx

Scram Logic A1/B1 and P603 A2/B2 reset P/Bs on P603

o MS-RIS-610C S/U*

Depress the following pushbuttons at H13-P601:

o Isolation logic A & B reset P/Bs S/U*

o Isolation logic C & D reset P/Bs S/U*

Return RWCU to service per SOP- S/U RWCU-START CUE: Inform the candidate that another operator is placing RWCU into service and to continue with ABN-RPS.

Reset RC-1 by depressing WMA- S/U*

RMS-FAZ/3AXY pushbutton.

If RHR SDC was in service then N/A refer to ABN-RHR-SDC. Otherwise N/A Open RRC-V-20 S/U*

Open EDR-V-20 S/U*

Candidate may If FDR-V-3 and FDR-V-4 have been voice concern for isolated for LT 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, then open the overflowing sump following:

FDR-V-3 already opened o FDR-V-3 S/U S/U*

o FDR-V-4 Page 4 of 7

RESTORE RPS A FROM ALTERNATE POWER SOURCE If FDR-V-3 and FDR-V-4 have been N/A isolated for GT 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />..

Otherwise N/A May direct communication Refer to TS 3.3.1.1 for RPS and LCS S/U to CRS 1.4.1 for coolant chemistry control.

May direct communication Determine cause and correct S/U to CRS May direct communication Evaluate resumption of maintenance S/U to CRS and surveillance activities Termination Criteria: Candidate informs CRS that ABN-RPS has been completed for the restoration of RPS A.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

Page 5 of 7

RESULTS OF JPM:

RESTORE RPS A FROM ALTERNATE POWER SOURCE Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: The subsequent actions for ABN-RPS have been completed and RPS A has been re-powered from Alternate Power Supply.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 15 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 6 of 7

STUDENT JPM INFORMATION CARD Initial Conditions:

A loss of RPS A occurred 20 minutes ago.

All maintenance and surveillance testing has been stopped.

Investigation revealed a failure of the A RPS MG set motor.

Cue:

The CRS has directed you to transfer A RPS to its Alternate power supply by performing steps 4.1 through 4.8 of ABN-RPS.

Inform the CRS when the subsequent actions for ABN-RPS have been completed and A RPS has been restored.

Page 7 of 7

2006 NRC EXAM - JPM #3 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE TRANSFER SL-21 FROM SL-11 to SM-2 (SIMULATOR)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 09/02/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any IC where SM-2 is powered and supplying power to SL-21.

Special Setup Instructions:

Transfer SL-21 to SL-11 per PPM 2.7.1B section 5.2.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0390 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

PPM 2.7.1B Section 5.6 Rev. 24 Location: Simulator NUREG 1123 Ref: 262001 A4.01 (3.4/3.7) Performance Method: Perform Page 1 of 5

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL SL-21 is currently being powered from SL-11.

CONDITIONS:

INITIATING CUE: The CRS has directed you to transfer SL-21 from SL-11 to SM-2 by performing a break before make transfer. Inform the CRS when SL-21 is being powered from SM-2.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Candidate should Notifies Radwaste that they will refer to PPM momentarily lose power to G33- S/U 2.7.1B Section 5.6, P0026 and when proper procedure section Verify CB-2/21 while LOCKOUT CIRCUIT AVAIL S/U is found, given his copy of the PPM light is illuminated If CB-2/21 is closed THEN verify CB-2/21 red light S/U illuminated. Otherwise N/A If CB-2/21 is not closed THEN perform the following: Otherwise N/A N/A Verify CB-21/2 green tripped light is illuminated and the green S/U position flag is being displayed in the CB-21/2 control switch window 2 Hand Operation OK Place and Hold the control switch for CB-21/2 in the close position S/U*

2 Hand Operation OK Place CB-21/11 control switch to the Trip position S/U*

Verify CB-21/11 green tripped light illuminates S/U Page 2 of 5

  • Items are Critical Steps Comments Element Standard Sat/Unsat Verify CB-21/11 red closed light extinguishes S/U Verify CB-2/21 green tripped light extinguishes S/U Verify CB-2/21 red closed light illuminates S/U Release the control switch for CB-21/2 S/U Termination Criteria: Candidate informs the CRS that SL-21 is being supplied from SM-2.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5

RESULTS OF JPM:

TRANSFER SL-21 FROM SL-11 to SM-2 Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: SL-21 power supply is transferred from SL-11 to SM-2 per PPM 2.7.1B.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM Time Time 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

SL-21 is currently being powered from SL-11.

Cue:

The CRS has directed you to transfer SL-21 from SL-11 to SM-2 by performing a break before make transfer.

Inform the CRS when SL-21 is being powered from SM-2.

Page 5 of 5

2006 NRC EXAM - JPM #4 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE MANUALLY INITIATES CONTAINMENT ISOLATIONS FOR THE TIP LESSON TITLE SYSTEM (SIMULATOR) (ALT PATH)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 05/18/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Reset to IC-14.

Ensure GDS screen on P601 is displayed.

Fail TIP-V-5 open.

Trip both RFW pumps.

After scram place mode switch in shutdown.

Special Setup Instructions:

None JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0314 Validation Time: 15 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

ABN-TIPS Rev. 0 Location: Simulator NUREG 1123 Ref: 223002 A2.03 A3.01 A3.02 Performance Method: Perform Page 1 of 6

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The plant was operating at full power when both RFW pumps tripped. RPV level CONDITIONS: dropped to less than -50 inches.

INITIATING CUE: The CRS has directed you to ensure all isolations for -50 inches RPV level signal per EOP 5.1.1. Another licensed operator will verify initiations and DG starts.

Inform the CRS when EOP isolations for -50 inches have been verified.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Candidate is not given any reference material to start this JPM.

Candidate may refer to GDS screen or quick card to determine required isolations. GDS will indicate TIP-V-5 is opened in addition to the valve lights on P601.

Identifies all isolations are Refers to GDS screen or quick not complete card and notes TIP-V- 5 is not S/U*

closed and informs the CRS CUE: When informed that TIP-V- 5 is opened, inform the candidate You are directed to take the necessary actions to isolate the penetration per ABN-TIPS and hand the candidate his procedure copy.

If necessary, THEN CLOSE the following TIP Drive Unit N/A Breakers: Otherwise N/A CUE: When step is read, inform candidate that the TIP Drive Unit Breakers are all closed Verify the following for each Drive Control Unit (A through E)

(H13-P607):

  • The Mode switch is in the S/U OFF position The Manual Drive switch
  • The Manual Drive switch is labeled MANUAL S/U is in the OFF position
  • The Manual Valve Control switch is in the CLOSED S/U position Place the MODE switch to the MAN position for each Drive S/U*

Control Unit (A through E)

Page 2 of 6

  • Items are Critical Steps Comments Element Standard Sat/Unsat Verify the following:
  • The READY light is S/U illuminated
  • The IN-SHIELD light is S/U illuminated. (If any detectors are NOT IN-SHIELD, proceed to the following step)

CUE: Inform candidate that the detector position is at the posted IN-SHIED location

  • The detector position is at the posted IN-SHIELD S/U location, + 1 May/May not refer CRS to REFER to Technical applicable Tech Spec Specification 3.6.1.3 S/U If any detector is NOT IN-SHIELD, THEN RETRACT each affected detector to the IN- N/A SHIELD position as follows (otherwise N/A):
  • PLACE the Manual Drive Control switch on the appropriate Drive Control Unit to the REV position
  • VERIFY the IN-SHIELD light is illuminated If the detector is still not IN-SHIELD, THEN CONSIDER MANUALLY CRANKING the N/A affected detector to the IN-SHIELD position from the Drive Mechanism per PPM 10.27.74.

Otherwise N/A Page 3 of 6

  • Items are Critical Steps Comments Element Standard Sat/Unsat If the detector is still not IN-SHIELD OR the isolation valve has failed to close, THEN ISOLATE the affected TIP line(s) as follows: Otherwise N/A
  • Obtain permission from the S/U CRS/Shift Manager to fire the applicable squib valve(s)

CUE: IF asked, the CRS/Shift Manager gives permission to fire the squib valve (Candidate may already assume he has permission from last communication/cue).

Obtains key #35 and PLACE the key lock valve Isolates TIP shear valve control switch on the appropriate (TIP-V-5). valve control drawer to the FIRE position for the channel that did S/U*

not isolate VERIFY the applicable squib Monitor lights are illuminated S/U VERIFY TIP SHEAR VLV CLOSED OR CKT CONTINUITY LOSS S/U annunciator (H13-P601.A12-5.1) is illuminated VERIFY the green ALL VALVES SHUT light at the TIP S/U*

ISOLATION status display on H13-P601 is illuminated Termination Criteria: Student informs CRS that all isolations for -50 inches have been verified and that the squib valve was fired to isolate TIP-V-5 penetration.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 4 of 6

RESULTS OF JPM:

MANUALLY INITIATES CONTAINMENT ISOLATIONS FOR THE TIP SYSTEM Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Verifies isolations for -50 inch RPV level signal and isolates TIP-V-5 line that did not isolate.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM Time Time 15 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 5 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant was operating at full power when both RFW pumps tripped.

RPV level dropped to less than -50 inches.

Cue:

The CRS has directed you to ensure all isolations for a -50 inch RPV level signal per EOP 5.1.1.

Another licensed operator will verify initiations and DG starts.

Inform the CRS when EOP isolations for

-50 inches have been verified.

Page 6 of 6

2006 NRC EXAM - JPM #5 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE LOWER RPV PRESSURE USING DEH (SIMULATOR)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 09/02/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Reset to IC where reactor is scrammed and RPV/P is approximately 920 psig.

Special Setup Instructions:

None JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0348 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-DEH-QC Rev. 1 Location: Simulator NUREG 1123 Ref: 241000 A4.02 (4.1/4.1) Performance Method: Perform Page 2 of 7

JPM CHECKLIST PROCEDURE Verify the revision number of procedure copies for evaluator and student. If the VALIDATION procedure revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.

INITIAL Columbia has just scrammed due to low RPV level. Another operator is returning RPV CONDITIONS: Level back to the normal operating band.

INITIATING The CRS has directed you to lower RPV pressure to 850 psig at the rate of 25 psig per CUE: minute using DEH in Automatic per SOP-DEH-QC. Inform the CRS when RPV pressure is 850 psig.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

The candidate VERIFY PRESS SETPOINT S/U should get quick AUTO light is LIT card in the ARP DEPRESS PRESS SETPOINT S / U*

book holder in PSI pushbutton front of DEH panel VERIFY PRESS SETPOINT PSI S/U pushbutton light is LIT VERIFY the current pressure S/U setpoint APPEARS in the DISPLAY and DISPLAY DEMAND window ENTER the desired pressure S / U*

setpoint (850) with the numerical keyboard VERIFY the desired pressure S/U setpoint APPEARS in the DISPLAY DEMAND window DEPRESS ENTER S / U*

VERIFY the following:

  • The old (but still current) S/U pressure setpoint remains in the DISPLAY window
  • The HOLD light is LIT Page 3 of 7
  • Items are Critical Steps Comments Element Standard Sat/Unsat DEPRESS PRESS RATE, S / U*

PSI/MIN VERIFY PRESS RATE, S/U PSI/MIN light is LIT VERIFY PRESS SETPOINT PSI S/U light is EXTINGUISHED VERIFY the current selected S/U pressure setpoint rate of change APPEARS in the DISPLAY window IF the displayed pressure setpoint rate of change is acceptable, THEN PROCEED to N/A Step 5.5.1.o. Otherwise N/A IF the displayed pressure setpoint rate of change is not acceptable, S / U*

THEN ENTER a new value with the numerical keyboard (25), and PERFORM the following:

VERIFY the value selected S/U APPEARS in the DISPLAY DEMAND window DEPRESS ENTER S / U*

VERIFY the new pressure S/U setpoint rate of change APPEARS in the DISPLAY window DEPRESS PRESS SETPOINT PSI pushbutton to DISPLAY the S / U*

following:

  • The new pressure setpoint in the DISPLAY DEMAND window.
  • The current value for the pressure setpoint in the DISPLAY window Page 4 of 7
  • Items are Critical Steps Comments Element Standard Sat/Unsat DEPRESS GO and S / U*

VERIFY the following:

  • GO light BACKLIGHTS S/U
  • HOLD light is EXTINGUISHED
  • Current pressure setpoint changes at the predetermined rate (25) until it is equal to the new setpoint in the DISPLAY DEMAND window
  • GO light extinguishes when new setpoint is reached PERFORM the following:
  • VERIFY Steam Supply S/U Pressure (MS-PR-1C) responds as the DISPLAY value changes IF pressure does not respond, THEN DEPRESS the HOLD N/A pushbutton and investigate.

Otherwise N/A Termination Criteria: Candidate informs the CRS that RPV Pressure has been lowered to 850 psig using DEH.

RECORD TERMINATION TIME: _________

Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.

Page 5 of 7

RESULTS OF JPM:

LOWER RPV PRESSURE USING DEH Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: RPV Pressure has been lowered to 850 psig at the rate of 25 psig/minute with DEH in Automatic as per SOP-DEH-QC.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial box) Time Time 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 6 of 7

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia has just scrammed due to low RPV level.

Another operator is returning RPV Level back to the normal operating band.

Cue:

The CRS has directed you to lower Reactor Pressure to 850 psig at the rate of 25 psig/minute using DEH in Automatic per SOP-DEH-QC.

Inform the CRS when RPV pressure is 850 psig.

Page 7 of 7

2006 NRC EXAM - JPM #6 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE MANUAL RCIC INITIATION FOR VESSEL INJECTION (ALT PATH) (SIM)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY DATE REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

IC-14.

Place the Mode switch to Shutdown.

Trip both RFPs when level is approximately -5 inches. Ensure RPV level is less than 13 inches and no high-pressure injection systems are injecting.

Special Setup Instructions:

Fail RCIC-V-46 to not open automatically (manual operation allowed).

MAL MOV-RCI010F 3 - Fail auto open JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0656, RO-0268 Validation Time: 5 min.

Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-RCIC-INJECTION-QC rev. 1 Location: Simulator NUREG 1123 Ref: 2170000A4.04 (3.6,3.6) Performance Method: Perform Page 1 of 5

JPM CHECKLIST PROCEDURE Verify the revision number of procedure copies for evaluator and student. If the VALIDATION procedure revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.

INITIAL The Reactor is shutdown and it has been decided to use RCIC for RPV level control.

CONDITIONS:

PPM 5.1.1 has been entered on low RPV level.

INITIATING The CRS has directed you to manually start the RCIC system for vessel injection CUE: using the RCIC-INJECTION Quick Card. Inform the CRS when RCIC is injecting into the RPV and system operation has been verified.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Candidate should Rotates the collar and depresses S / U*

reference quick the pushbutton.

card located in ARP holder in Verifies RCIC-V-46 OPENS S/U front of RCIC (Lube Oil Cooler Water Supply).

system Notes RCIC-V-46 failed to open.

Takes C/S to open and verifies S / U*

valve opens.

Verifies RCIC-P-2 running (Barometric Condenser Vacuum S/U Pump).

Verifies RCIC-V-45 OPENS (Steam to Turbine) S/U Verifies RCIC Turbine speed rising. S/U Verifies RCIC-V-13 OPENS (RPV Injection). S/U Page 2 of 5

  • Items are Critical Steps Comments Element Standard Sat/Unsat When RCIC-V-45 OPENS (Steam to Turbine), verifies:
  • RCIC-V-25 and S/U RCIC-V-26 CLOSE(Steam Line Warm up Drains to Main Condenser)

S/U

  • RCIC-V-4 and RCIC-V-5 CLOSE (Cond Pump Discharge to EDR)

S/U

  • SW-P-1B Running (20 second time delay Verifies RCIC-V-19 (Min Flow valve) OPENS during low flow S/U conditions (Discharge pressure GT 125 psig and flow LT 75 gpm).

S/U When RCIC flow is GT 150 gpm, verifies RCIC-V-19 CLOSES.

Verifies RCIC-FIC-600 CONTROLS RCIC Turbine S/U speed at the flow setpoint (normally 600 GPM).

Monitors RPV Level and S/U pressure.

Adjusts RCIC-FIC-600 to S/U maintain the required flow.

Verifies SW-V-34 open (RCIC S/U pump room cooled return H13-P825).

Termination Criteria: Candidate informs the CRS that the RCIC system is injecting into the vessel and that RCIC-V-46 had to be manually opened.

RECORD TERMINATION TIME: _________

Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5

RESULTS OF JPM:

MANUAL INITIATION OF RCIC FOR VESSEL INJECTION Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: RCIC system is manually initiated and system operation is verified per RCIC-INJECTION-QC.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial box) Time Time 5 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

The Reactor is shutdown and it has been decided to use RCIC for level control.

PPM 5.1.1 has been entered on RPV level control.

Cue:

The CRS has directed you to manually start the RCIC system, using the RCIC-INJECTION Quick Card, for vessel injection.

Inform the CRS when RCIC is injecting into the RPV and system operation has been verified.

Page 5 of 5

2006 NRC EXAM - JPM #7 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RB HVAC FAILURE; START SGT (ALT PATH) (SIMULATOR)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 9/02/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any IC where REA-FN-1B is running.

Special Setup Instructions:

Prevent REA-FN-1A from auto/manually starting. Trip REA-FN-1B.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0491; RO-0383 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

ARP 4.812.R2 9-1; SOP-SGT-START- Location: Simulator DIV/2-QC Rev. 0 NUREG 1123 Ref: 295035 EA1.01 (3.6/3.6) Performance Method: Perform EA1.02 (3.8/3.8)

Page 1 of 5

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL A RX BLDG HVAC DIV1 and DIV2 Board R Trouble alarm have just CONDITIONS: annunciated. The alarms were acknowledged on P851 S1 and S2.

INITIATING CUE: The CRS has directed you to investigate and respond to the Reactor Building HVAC annunciators.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Responds to the back panel 4.812.R2 and notes annunciator S/U RX BLDG EXH FAN B TRIP (9-1) is illuminated.

Refers to ARP Checks REA-FN-1B tripped S/U Attempts to start the other RB Exhaust Ran REA-FN-1A and S/U*

notes it will not start If neither fan can be started, perform the following:

Immediately secures any Places the control switch S/U*

operating Reactor Building Inlet for ROA-FN-1B to STOP/

fan, ROA-FN-1A (1B)

PTL Close:

  • ROA-V-1 S/U*
  • ROA-V-2 S/U*
  • REA-V-1 S/U*
  • REA-V-2 S/U*

Start one train of the SGT System to maintain Reactor Building S/U*

pressure negative CUE: If candidate decides to start the A SGT train, cue candidate to use the B SGT Train SOP-SGT-START Refers to SOP-SGT-START-and SOP-SGT- DIV/2-QC and starts SGT as S/U START-DIV/2-QC follows:

Page 2 of 5

  • Items are Critical Steps Comments Element Standard Sat/Unsat are not the same. If Takes the C/S for and fan If necessary, THEN place the SOP-SGT-START S/U that was not taken to PTL following fans in PTL:

is referenced, and not the Quick previously - to PTL

  • ROA-FN-1A Card, the ROA and
  • ROA-FN-1B REA fan control
  • REA-FN-1A switches will not
  • REA-FN-1B be placed in PTL.

If necessary, THEN close the following valves: Otherwise N/A N/A Momentarily turn SGT-FN-1B2 fan control switch from AUTO to S/U*

PTL SYS. START Verify the following:

  • Main Heaters energize as indicated by Main Heater S/U ON light and B2 amp meters
  • SGT-V-5B2 OPENS S/U
  • SGT-FN-1B2 STARTS Note: to prevent a fan trip S/U flow should be GT 750 CFM and LT 5378 CFM If required to operate in manual flow control, THEN refer to SOP N/A

-SGT-START. Otherwise N/A Termination Criteria: Candidate informs the CRS that REA-FN-1B tripped, REA-FN-1A would not start and SGT B train was started and is operating.

Note: If candidate continues with the ARP actions after SGT is started, inform the candidate that the termination point of the JPM has been reached.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5

RESULTS OF JPM:

RB HVAC FAILURE; START SGT Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Reactor Building Ventilation has been secured and SGT B train has been started to maintain Secondary Containment pressure.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM Time Time 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

A RX BLDG HVAC DIV1 and DIV2 Board R Trouble alarm have just annunciated. The alarms were acknowledged on P851 S1 and S2.

Cue:

The CRS has directed you to investigate and respond to the Reactor Building HVAC annunciators.

Page 5 of 5

2006 NRC EXAM - JPM #8 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE HPCS SYSTEM INITIATION / SW FAILS TO AUTO START (SIM) (ALT PATH)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 9/02/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Insert a malfunction that prevents HPCS-P-2 from starting automatically but may be started manually.

Special Setup Instructions:

Insert a manual scram and allow RPV/L to recover to about 0 then trip both RFPs.

JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0235; RO-0459 Validation Time: 5 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

SOP-HPCS-INJECTION-QC Rev. 2 Location: SIMULATOR NUREG 1123 Ref: 264000A3.06 (3.1/3.2) Performance Method: PERFORM Page 1 of 5

JPM CHECKLIST PROCEDURE Regarding procedure copies for evaluator and student, if the procedure revision is VALIDATION different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL A failure of the master controller caused RPV level to drop. The Control Room CONDITIONS: Supervisor directed a manual scram prior to +13 being reached. Both Reactor Feed Pumps then tripped as RPV level approached 0.

INITIATING CUE: The CRS has directed you to initiate the HPCS and bring RPV level back to a band of +13 to +54. Inform the CRS when RPV level is in the band.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Refers to HPCS INJECTION S/U QUICK CARD CUE: If asked, inform candidate that Arm and Depress pushbutton may be used.

IF directed by the CRS/Shift Manager, THEN ARM and DEPRESS the HPCS MANUAL S/U*

INITIATION pushbutton.

Otherwise, N/A this step and proceed to the next step START HPCS-P-1 S/U Verify HPCS-V-12 OPENS, during low flow conditions (approximately 1300 gpm) S/U (Minimum Flow Bypass)

Verify HPCS-P-2 running Notes HPCS-P-2 is not running and S/U*

takes the Control Switch for HPCS-P-2 to the START position Notes HPCS-P-2 start and verifies S/U proper system operation Page 2 of 5

IF required, THEN RESET the N/A Reactor Level 8 Seal In. Otherwise N/A OPEN HPCS-V-4 (RPV Injection) S/U VERIFY injection into the RPV S/U WHEN flow rate is GT 1300 gpm, S/U THEN VERIFY HPCS-V-12 CLOSES Closes HPCS-V-4 when Operate HPCS-V-4 as necessary to S/U RPV level is in band MAINTAIN RPV level between +13 to +54 inches Termination Criteria: Student informs CRS that RPV level is in the band given and that HPCS-P-2 did not auto start but was started manually.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

Page 3 of 5

RESULTS OF JPM:

HPCS SYSTEM INITIATION (SW FAILS TO START)

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: The HPCS SW Pump (HPCS-P-2) has been manually started.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 5 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

A failure of the master controller caused RPV level to drop.

The Control Room Supervisor directed a manual scram prior to +13 being reached.

Both Reactor Feed Pumps then tripped as RPV level approached 0.

Cue:

The CRS has directed you to initiate the HPCS system using the Arm and Depress pushbutton, verify proper system operation, and bring RPV level back to a band of +13 to

+54.

Inform the CRS when RPV level is in the band.

Page 5 of 5

2006 NRC EXAM - In Plant JPM #2 PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE START AND PARALLEL DG-2 ON CR EVACUATION (ALT PATH) (Plant)

LESSON LENGTH 0.5 MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 5/22/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

N/A JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0700 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

ABN-CR-EVAC Rev. 9 Location: Plant NUREG 1123 Ref: 219000A4.13 (3.9/3.8) Performance Method: Simulate Page 1 of 5

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION: that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The Control Room has been abandoned due to a fire in the back panels. The Remote CONDITIONS: Shutdown Panel is manned.

INITIATING CUE: The CRS has directed you to start DG-2 per ABN-CR-EVAC Section 7.5. Another operator has been dispatched to pull the control power fuses from HPCS-P-1 and to trip the HPCS DG. Inform the CRS when DG-2 has been started and has assumed SM-8 loads. CONTROL MANIPULATIONS WILL NOT BE PERFORMED. ALL ACTIONS AND STEPS WILL BE SIMULATED.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Cue: If Student checks, cue that DG-2 is not running.

Candidate is given At E-CP-DG/RP2, Depress the S / U*

ABN-CR-EVAC Emergency Stop Pushbutton Inform the CRS that DG-2 has S/U been tripped Cue: When candidate dials correct phone number for the RSD (2649 or 2569) to informs the CRS, respond as the CRS.

Place the Diesel Engine Mode S / U*

Selector to MAINT Resets the Lockout Relay (E- S / U*

RLY-86/DG2)

Ensures Diesel Engine Control S/U Selector is in LOCAL Cue: When candidate checks, inform him that the Diesel Engine Control Selector is in the Control Room position.

Places Diesel Engine Control S / U*

Selector in LOCAL Places DG-RMS-DG-2/FTS56B S / U*

in the EMERG position Cue: If candidate asks, respond as the CRS to place Diesel Engine Mode Selector Switch to AUTO. If candidate waits until prompted by the CRS cue that the phone is ringing and, when answered, inform candidate as the CRS to initiate DG-2 Auto fast-start and loading.

Page 2 of 5

  • Items are Critical Steps Comments Element Standard Sat/Unsat Places the Diesel Engine S/U*

1B1/1B2 Mode Selector to AUTO Cue: When switch is taken to AUTO inform candidate that DG-2 did NOT start.

If DG-2 failed to Auto start, THEN start DG-2 by depressing S/U*

the Diesel Engine 1B1/1B2 Start pushbutton Cue: If candidate checks, cue that DG-2 is running.

If E-CB-DG2/8 did not automatically close, THEN place S/U*

E-CB-DG2/8 control switch to close. Otherwise N/A Cue: If candidate checks, cue that E-CB-DG2/8 did NOT automatically close.

Places E-CB-DG2/8 control S/U*

switch to CLOSE Cue: If candidate checks, cue that E-CB-DG2/8 is now closed.

Termination Criteria: Candidate informs the CRS that DG-2 has started and has assumed SM-8 loads.

RECORD TERMINATION TIME: _________

Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5

RESULTS OF JPM:

START AND PARALLEL DG-2 ON CR EVAC.

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: DG-2 has been started and has assumed SM-8 load per ABN-CR-EVAC.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM Time Time 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

The Control Room has been abandoned due to a fire in the back panels.

The Remote Shutdown Panel is manned.

Cue:

The CRS has directed you to start DG-2 per ABN-CR-EVAC Section 7.5.

Another operator has been dispatched to pull the control power fuses from HPCS-P-1 and to trip the HPCS DG.

Inform the CRS when DG-2 has been started and has assumed SM-8 loads.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

ALL ACTIONS AND STEPS WILL BE SIMULATED.

Page 5 of 5

2006 NRC EXAM -IN PLANT JPM #3 PROGRAM TITLE INITIAL LICENSED TRAINING COURSE TITLE JOB PERFORMANCE MEASURE RESPOND TO CONTROL ROOM HVAC HIGH RADIATION LESSON TITLE (PLANT) (ALT PATH)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 05/22/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

N/A JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0114 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

ABN-RAD-CR Rev. 4 Location: PLANT NUREG 1123 Ref: 288000A2.02 (3.7/3.8) Performance Method: SIMULATE Page 1 of 5

JPM CHECKLIST PROCEDURE Regarding procedure copies for evaluator and student, if the procedure revision is different from that VALIDATION listed on the JPM, verify that the critical task steps are the same. Evaluator copy may be used for marking step completion, and comments.

INITIAL A Reactor Building High Radiation signal is present. All automatic actions have been CONDITIONS: verified. The "B" Control Room Ventilation and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating. A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A/B reads 5,000 CPM).

No alarm is observed on the Southeast side (WOA-RIS-32A/B reads normal).

INITIATING The CRS has directed you to isolate the Northwest Remote Air Intake per ABN-RAD-CUE: CR. Notify the CRS when actions per ABN-RAD-CR have been completed for the high radiation condition. CONTROL MANIPULATIONS WILL NOT BE PERFORMED. ALL ACTIONS AND STEPS WILL BE SIMULATED.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Candidate is given Verify WOA-V-51B is open (SE #2) S/U ABN-RAD-CR Remote intake outboard isolation Cue: If candidate checks WOA-V-51B is open and independent verification of the step has been performed.

Verify WOA-V-52B is open (SE #2) S/U Remote intake inboard isolation Cue: If candidate checks WOA-V-52B is open and independent verification of the step has been performed.

Unlock and close WOA-V-51A, NW

(#1) Remote Intake Outboard Isolation. If remote air intake #1 is S/U*

isolated using only valve WOA-V-52A, then N/A this step and step 7.1.4 Cue: When student attempts to close WOA-V-51A, inform the student that the operator is broken and the valve is danger tagged in the open position.

STEP IS N/A Verify WOA-V-51D Opens, NW (#1)

N/A Remote Intake Purge, (WOA-V-51A Closed)

Page 2 of 5

Unlock and close WOA-V-52A, NW S/U*

(#1) Remote Intake Inboard Isolation E-CP-COHV/1 is If remote air intake #1 is isolated S/U*

labeled COHV-1. using only valve WOA-V-52A, then Cover for F4 is remove fuse F4 in Control, Cable labeled with a 4 and Spreading and Critical Switchgear door aid indicates Rooms Control Panel E-CP-COHV/1 TB-F4.

(RW 525) to open WOA-V-51D, NW

(#1) Remote Intake Purge. Otherwise N/A Cue: If candidate checks, WOA-V-51D opens.

Termination Criteria: Student informs CRS that the NW Remote Air Intake is isolated, only WOA-V-52A is closed, and Fuse F4 has been pulled.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

Page 3 of 5

RESULTS OF JPM:

RESPOND TO CONTROL ROOM HVAC HIGH RADIATION (ONE INTAKE)

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: The Northwest Remote Air Intake to the Control Room Ventilation System is isolated per ABN-RAD-CR.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

  • A Reactor Building High Radiation signal is present
  • All automatic actions have been verified
  • The "B" Control Room Ventilation and Emergency Filtration systems have been secured and the "A" Control Room ventilation (WMA-FN-51A) and Emergency Filtration Fans (WMA-FN-54A) are operating
  • A Hi-Hi radiation alarm has been confirmed on the Northwest remote air intake (WOA-RIS-31A/B reads 5,000 CPM)
  • No alarm is observed on the Southeast side (WOA-RIS-32A/B reads normal)

Cue:

The CRS has directed you to isolate the Northwest Remote Air Intake per ABN-RAD-CR.

Notify the CRS when actions per ABN-RAD-CR have been completed for the high radiation condition.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

ALL ACTIONS AND STEPS WILL BE SIMULATED.

Page 5 of 5

2006 NRC EXAM - IN PLANT JPM #1 PROGRAM TITLE INITIAL LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE INSERT CONTROL RODS BY VENTING SCRAM AIR HEADER (Plant)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 5/22/06 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

N/A JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: Pre-staged EOP Tools Safety Items: None Task Number: RO-0680 Validation Time: 9 Minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 5.5.11 Location: PLANT NUREG 1123 Ref: 295037EA1.05 (3.9/4.0) Performance Method: SIMULATE Page 1 of 5

JPM CHECKLIST PROCEDURE Regarding procedure copies for evaluator and student, if the procedure revision is VALIDATION different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL A scram has been initiated and the blue scram lights are extinguished at H13-P603.

CONDITIONS: Reactor pressure is stable at 930 psig and Reactor Power is 38%.

INITIATING CUE: The CRS has directed you to insert control rods by venting the Scram Air Header per PPM 5.5.11 Tab D. Inform the CRS when actions are completed to vent the Scram Air Header. THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

  • Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: If asked, inform candidate that control rod density is .156.

PPM 5.1.1 Tab D is Closes CRD-V-95 (Scram Air S/U*

given to candidate Header Isolation)

Closes CRD-V-729 (CRD-PI-13 S/U*

isolation)

Note: Pre-staged crescent wrench is used to remove instrument drain plug.

Removes instrument drain Rotates instrument drain plug plug for CRD-PI-13. counterclockwise on CRD-PI-13 S/U*

until drain plug is removed Cue candidate that the drain line plug is removed if rotated in proper direction.

Open CRD-V-729 (CRD-PI-13 S/U*

isolation)

Cue: Inform candidate that the scram air header is fully depressurized and no further rod motion is observed.

Closes CRD-V-729 (CRD-PI-13 S/U isolation)

Page 2 of 5

  • Items are Critical Steps Comments Element Standard Sat/Unsat Install instrument drain plug for S/U CRD-PI-13 by rotating it clockwise Cue candidate that the drain line plug is installed if rotated in proper direction.

Open CRD-V-729 (CRD-PI-13 S/U isolation)

Open CRD-V-95 (Scram Air Header S/U Isolation)

Termination Criteria: Student informs CRS that actions to vent Scram Air Header have been completed.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. The marked up procedure and remaining JPM pages may be discarded.

Page 3 of 5

RESULTS OF JPM:

INSERT CONTROL ROD BY VENTING SCRAM AIR HEADER Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: The scram air header has been vented per PPM 5.5.11 Tab D.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

STUDENT JPM INFORMATION CARD Initial Conditions:

A scram has been initiated and the blue scram lights are extinguished at H13-P603 Reactor pressure is stable at 930 psig and Reactor Power is 38%.

Cue:

The CRS has directed you to insert control rods by venting the Scram Air Header per PPM 5.5.11 Tab D.

Inform the CRS when actions are completed to vent the Scram Air Header.

THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

Page 5 of 5

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Facility: Columbia Scenario No: 1 Examiners: Operators:

Initial conditions: Columbia is at 85% power due to an economic dispatch request from BPA. REA-FN-1A is OOS due to bearing replacement. REA-FN-1B is protected.

Turnover: Return Columbia to 90% power with flow. There are no preconditioning limits associated with the power/flow increase.

Event Timeline Event Type* Event Description No.

1. T=0 R (RO) Raises Reactor Power with recirculation flow.
2. T=10 C (SRO) Accumulator for a Control Rod Inop (Tech Spec #1)
3. T=20 C (RO) Slow drop of RFW-P-1A Control Oil Pressure with failure of RFW-P-AOP/1A to start.
4. T=30 C (RO) CRD-P-1A reduced flow and pump trip.
5. T=45 C RHR-A Suction piping rupture that is isolated by closing RHR-V-4A.

(SRO/BOP) (Critical Step) (Tech Spec)

6. T=50 N (BOP) Performs PPM 5.5.23 to fill SP with HPCS.
7. T=70 M (ALL) RRC-P-1A High Vibration alarms followed by seal failures followed by LOCA.
8. T=75 C (BOP) EDR-V-19 fails to Auto close on 1.68 psig isolation signal.
9. T=85 C (BOP) RHR-V-17B breaker trips when C/S taken to open (results in the inability to spray drywell)
10. T=90 Initiates an Emergency Depressurization when DW/T cannot be maintained below 330°F or when PSP is exceeded. (Critical Step)
  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 The scenario starts with Columbia at 86% due to economic dispatch. The crew will be directed to raise power back to 100% after turnover. After the power increase, accumulator for rod 14-23 will annunciate.

Report from the field will be a valve failure with pressure LT required by Tech Specs. The SRO will declare rod 14-23 inoperable.

The next event will occur after the power increase. Due to a failed pump, the A RFP control oil pressure low alarm will annunciate. The crew will note that the Auxiliary Oil Pump should have started when this alarm is received but did not. The crew will start the Auxiliary Oil Pump and control oil pressure will return to normal.

The next event is a slow failure of CRD-P-1A. CRD system pressure will drop and the crew will take actions to start the standby CRD pump which will restore system pressure.

The next event is a rupture in RHR-P-2A suction piping. Suppression pool level will drop and EOP 5.2.1 will be entered. Additionally ABN-Flooding will be entered. Report from the field will be that the leak is between the RHR pump and the suction valve. The crew will close RHR-V-4A and pull the control power fuses on the pump to prevent it from starting. Closing RHR-V-4A will stop the leak and PPM 5.5.23 will be used to return SP/L to normal with HPCS.

The next event is high vibrations on RRC-P-1A. The lower and upper seals will quickly fail and cause a small LOCA. DW/P will rise and the crew should take actions to scram the reactor. With RHR-A already being OOS, sprays will be initiated with RHR-B. When WW/P exceeds 12 psig, the crew will attempt to spray the drywell. When RHR-V-17B is opened to initiate sprays it will lose power and the crew will not be able to spray the drywell. On the 1.68 psig initiation, EDR-V-19 will fail to auto close. Manual actions to close the valve will result in the valve closing.

When it is determined that Drywell temperature cannot be maintained below 330°F or when PSP has been exceeded, the crew will enter EOP 5.1.3 and initiate an Emergency Depressurization.

The scenario will be terminated when an Emergency Depressurization has been initiated and RPV level is being returned to normal.

Page 2 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 1

==

Description:==

Raises Reactor Power with recirculation flow.

This event is initiated by the SRO and is given in the turnover information.

Time Position Applicants Actions or Behavior T=0 SRO Directs RO to raise Reactor power with flow at a directed rate of change.

RO Depresses Master Controller raise pushbutton while monitoring RPV Power, Pressure and Level.

Monitors rate of power increase to be less that rate given by SRO.

BOP Provides Peer Checks to RO as necessary.

COMMENTS:

Page 3 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 2

==

Description:==

Accumulator for Control Rod 14-23 Inop. (Tech Spec)

This event is initiated by activating TRIGGER 1 when the power increase has been completed.

Time Position Applicants Actions or Behavior T=10 RO Acknowledges Rod Accumulator Trouble alarm P603-A7 6-7, and refers to ARP.

Verifies CRD Pump in operation.

Determines alarm is associated with rod 14-23 and informs SRO.

Refers SRO to SOP-CRD-HCU.

SRO Directs local investigation.

Role Play - Wait a minute and call 2242 and report as OPS2 that you have found accumulator valve CRD-V-111/14-23 (the accumulators nitrogen charging valve) has a stem to disk separation.

Accumulator pressure is down to 920 psig and you cannot stop the pressure drop which appears to be slowly dropping.

SRO Refers to Tech Spec 3.1.5. Notes surveillance pressure requirement for each accumulator is GT 940 psig.

Determines accumulator for rod 14-23 is inop and enters TS 3.1.5 Condition A - Declare the associated control rod inoperable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

May contact SNE for reactivity plan to insert rod 14-23.

Contacts PSRO and conducts brief.

COMMENTS:

Page 4 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 3

==

Description:==

Slow drop of RFW-P-1A Control Oil Pressure with failure of RFW-P-AOP/1A to start.

The event is initiated by activating TRIGGER 2 (It takes 2 minutes to get alarm)

Time Position Applicants Actions or Behavior T=20 RO/BOP Acknowledges TURB A CNTR OIL PRESS LOW annunciator P840-A1 5-1, and refers to ARP.

Provides SRO with current control oil pressure (LT 70 psig) on RFT-PI-2/1A.

SRO/RO/BOP Notes that RFW-P-AOP/1A should have started per ARP but is not running.

SRO Directs RFW-P-AOP/1A be started (RO may start pump without direction - auto action that should have occurred but did not).

RO/BOP Starts RFW-P-AOP/1A and reports start to SRO.

Reports control oil pressure returned to normal and clearing of control oil pressure low annunciator.

Acknowledges annunciator for RFW-P-AOP/1A running.

SRO Contacts Production SRO/System Engineer to investigate problem with RFW-P-AOP/1A.

ROLE-PLAY: If OPS3 is contacted report no leak observed.

COMMENTS:

Page 5 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 4

==

Description:==

CRD-P-1A reduced flow and eventual pump trip (in 6 minutes)

This event is initiated by activating TRIGGER 3 (It takes 1 minute to get alarm)

Time Position Applicants Actions or Behavior T=30 RO Acknowledges Charge Water Press Low annunciator P603-A7 3-8, and refers to ARP.

Provides SRO with current reading on CRD-PIS-600 and indicates that it continues to drop.

Refers SRO to ABN-CRD.

Acknowledges RWCU Pump trouble alarms associated with the drop in CRD pressure (Takes about 4 minutes P602-A5 4-7 and 4-8).

SRO Refers to ABN-CRD and directs placing CRD-FC-600 (CRD Flow Controller) in MANUAL at zero output.

Refers to Tech Spec 3.1.5.

RO Places CRD-FC-600 in MANUAL at zero output.

Acknowledges CRD Abnormal Operation annunciator and reports the trip of CRD-P-1A (takes 6 minutes).

Acknowledges accumulator alarms if/as they occur.

SRO Per ABN-CRD directs start of CRD-P-1B, the standby CRD Pump (Standby pump may be started before CRD-P-1A trips if crew determines that CRD-P-1A is failing).

Acknowledges RWCU trouble alarms associated with the loss of CRD flow.

Page 6 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 RO Starts CRD-P-1B and reports start to SRO.

SRO Directs CRD-FC-600 be nulled and returned to AUTO.

Contacts production SRO/Work Week Leader concerning CRD-P-1A.

RO Nulls CRD-FC-600 deviation meter and shifts CRD-FC-600 to AUTOMATIC.

Reports accumulator alarms clear after CRD pump starts.

Contacts OPS2 to check CRD-P-1B operation.

COMMENTS:

Page 7 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 5

==

Description:==

Rupture in the RHR-A suction piping causing RHR-A room level to rise and Suppression Pool Level to drop.

The event is initiated by activating TRIGGER 4. (It takes about 1 minute to get alarm)

Time Position Applicants Actions or Behavior Critical step for this event is to stop Suppression Pool leak by closing RHR-V-4A.

T=45 BOP Acknowledges alarms associated with lowering Suppression Pool level and rising water level in RHR-A Pump Room as they occur:

  • Leak Det Reactor Bldg Floor Sump R1 Leakage high, P601-A3 2-7
  • Sump R1 Level Hi Hi, P602-A13 2-1
  • Suppression Pool Level Hi/Low, P601-A11 2-3 and P601-A12 2-3
  • RHR-A Pump Room Water Level High (EOP entry), 3P601-A4 5-3 Refers to ARPs as necessary.

Reports Suppression Pool level dropping giving actual level.

Reports EOP entry into PPM 5.2.1 on low suppression pool level when level drops to -2.

Reports EOP entry into PPM 5.3.1 when RHR-A Room Level alarm annunciates (and BISI) (EOP entry is +6 inches above floor).

SRO Directs field investigation by OPS2.

Enters PPM 5.2.1 on Suppression Pool level LT -2.

BOP Verifies FDR-V-607 is closed (H13-P632).

Refers SRO to ABN-FLOODING and ABN-RAD-SPILL as appropriate.

Page 8 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 ROLE-PLAY - Two minutes after being directed to investigate, report that there is a crack in the piping coming from the suppression pool to RHR-P-2A. The rupture is located between the RHR pump and the suction valve. Room level report (if requested) should be consistent with alarms in at the time.

ROOM LEVEL REPORTS WILL ALWAYS BE LESS THAN +36.

SRO Enters PPM 5.3.1.

Refers ABN-FLOODING (and ABN-RAD-SPILL) and directs actions:

  • Make local evacuation announcement
  • START RHR-P-2B
  • Pull control Power fuses for RHR-P-2A
  • Close RHR-V-4A
  • Monitor ECCS rooms adjacent to RHR-P-2A room for flooding May directs PPM 5.5.27 be performed by maintenance.

ROLE-PLAY - Two minutes after request to pull RHR-P-2A fuses, initiate TRIGGER 5 and report control fuses for RHR-P-2A pulled to Control Room.

BOP Obtains key #3 from key locker and closes RHR-V-4A. Reports valve closed when appropriate. Reports SP level stops dropping when RHR-V-4A closes.

Starts RHR-P-2B by placing its C/S to START. Verifies pump operation and SW-P-1B start.

ROLE-PLAY - If asked, the final level report will depend on actual SP level decrease (but will always be LT 36) (Use 1 drop in SP level is 1 inch rise in room flooding level).

SRO Reviews Tech Specs for RHR-V-4A not being full open. TS 3.5.1 (Condition A applies - restore within 7 days), 3.6.1.5 (Condition A applies - restore within 7 days), and 3.6.2.3 (Condition A applies -

restore within 7 days) apply in Mode 1.

Tech Spec for SP Water level is 3.6.2.2A.

Conducts brief.

COMMENTS: Note: SP/T high alarm received due to uncovering of the detector at 9.

Page 9 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 6

==

Description:==

Performs PPM 5.5.23 to fill Suppression Pool with HPCS.

This event initiated by the SRO per EOP PPM 5.2.1.

Time Position Applicants Actions or Behavior SRO Directs Suppression Pool level be raised to 0 per PPM 5.5.23.

T=50 BOP Pulls PPM 5.5.23 and performs the following:

  • Ensure HPCS-V-1 is opened
  • Start HPCS-P-1 and ensure HPCS-V-12 opens
  • Open HPCS-V-23 to raise flow to suppression pool to 7175 gpm and verifies HPCS-V-12 closes
  • When suppression pool level reaches 0 inches, closes HPCS-V-23 and ensures HPCS-V-12 opens
  • Stops HPCS-P-1 and ensures HPCS-V-12 closes.

Reports suppression pool level to SRO.

Comments:

Page 10 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 7

==

Description:==

RRC-P-1A High Vibration alarms followed by LOCA requires manual scram prior to automatic scram at 1.68 psig drywell pressure. High Drywell EOP Entry into PPM 5.1.1 and re-entry into 5.2.1.

The event is MANUALLY initiated with TRIGGER 6.

Time Position Applicants Actions or Behavior T=70 RO Acknowledges RRC-P-1A high vibration alarm, P602-A6 2-4 and refers to ARP.

Refers SRO to SOP-RRC-SINGLE LOOP or SOP-RRC-SHUTDOWN.

SRO Directs local investigation.

ROLE-PLAY: A minute after being sent report vibration readings pegged high on all channels.

Reports annunciators as the occur:

  • Motor Bearing Oil Level High
  • Outer Seal Leakage High
  • Leak Detection Drywell Floor Drain Flow High
  • Staging Flow Hi/Lo
  • RECIRC A or B Pump/Motor Temp High
  • EOP entry into PPM 5.3.1 on Rx. Bldg High Rad (ARM-RIS-13 reading approximately 200mr/hr)

SRO Based on annunciators present, may direct tripping of RRC-P-1A.

Page 11 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 BOP/RO Reports Suppression Pool High/Low alarms.

Reports rising Drywell pressure and High Drywell Pressure Alert annunciator when it annunciates.

Reports Reactor Building high rad annunciator when it alarms as an EOP entry.

SRO May directs a reactor scram prior to 1.68 psig scram.

RO Inserts a manual scram and performs immediate scram actions:

  • Places Reactor Mode Switch in SHUTDOWN
  • Monitors Power, Pressure, and Level
  • Verifies all rods inserted
  • Inserts IRMs and SRMs by depressing INSERT P/B Reports EOP entry on low RPV water level.

SRO Enters PPM 5.1.1 on Low RPV level.

BOP Recognizes and calls out Drywell pressure 1.68 EOP entry (and other PPM 5.2.1 entries as they occur).

SRO Enters PPM 5.2.1 and re-enters PPM 5.1.1 on high drywell pressure.

Directs PPM 3.3.1 performance.

Directs RPV level controlled +13 to +54 with available systems.

RO Lines up on Startup Flow Control Valves using quick card:

  • Place RFW-LIC-600 in MANUAL (if RFW pumps running)
  • Place RFW-SC-601A and 601B in MDEM (If pumps running)

Page 12 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 If RFW pump trips on 54.5 may have to restart it (per Quick Card):

2.1.1 If desired then transfer RPV level control to RFW-FCV-10A/10B per SOP-RFW-FCV-QC. Otherwise N/A 2.1.2 If performing this section following a reactor scram, then verify RFW-V-112A and RFW-V-112B have started to close. Otherwise N/A 2.1.3 Verify MSIVs are open 2.1.4 Verify at least two high level seal ins are reset (H13-P601) 2.1.5 Verify RFW-SC-601A(B) is in MDVP at 0% (Speed Controller)(H13-P601) 2.1.6 Hold the trip/reset switch to reset until the HP and LP stop valves indicate full open (H13-P840)

Raise turbine speed using RFW-SC-601A(B) in MDVP (turbine will roll on Main Steam at approximately 60% GV position) 2.1.8 Transfer RFW-SC-601A(B) to MDEM as soon as practical (GT 800 rpm) 2.1.9 If performing this section following a reactor scram, then verify RFW-V-112A and RFW-V-112B are fully closed. Otherwise N/A 2.1.10 Verify feedwater lineup appropriate for plant conditions 2.1.11 Raise turbine speed to raise RFP discharge pressure as necessary to control RPV level Page 13 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1

  • Close RFW-V-112A and 112B
  • Adjust RFW speed to maintain GT 100 psid on startup valve
  • Adjust RFW-LIC-620 to control level and place in AUTO when RPV/L is 36 inches Maintains RPV level with available systems.

SRO Directs Isolations, Initiations and DG starts be verified for +13 and 1.68 psig. (Refer to Event 8)

RO/BOP Notes B RRC Pump running with no RCC running. Informs SRO and requests to stop RRC pump.

May reports RRC-P-1A tripped.

SRO Directs RRC-P-1B be stopped.

RO/BOP Stops pump by depressing STOP P/B and reports to SRO.

SRO May direct RPV pressure reduction to reduce leak rate.

NOTE: approximately 17 minutes after Trigger 6 is initiated, the MSIVs will close on MS Tunnel Temp High. SRO would then direct pressure control with SRVs.

BOP Maintains RPV Pressure at directed pressure band.

COMMENTS:

Page 14 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 8

==

Description:==

EDRV-19 fails to Auto Close on 1.68 psig Drywell pressure signal.

This event is inserted at the beginning of the scenario.

Time Position Applicants Actions or Behavior SRO Directs Isolations, Initiations and DG starts be verified for +13 and 1.68 psig.

BOP Verifies Isolations, Initiations and DG starts be verified for +13 and 1.68 psig.

BOP Notes EDR-V-19 failed to close and manually closes EDR-V-19 by taking control switch to close. Notes it does go closed.

BOP Reports to SRO that EDR-V-19 failed to isolate on 1.68 psig isolation signal but was closed manually.

Reports remainder of isolations, Initiations and DG starts have been verified.

COMMENTS:

Page 15 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 9

==

Description:==

Breaker for RHR-V-17B trips when C/S taken to open results in the inability to spray drywell.

This event is inserted at the beginning of the scenario.

Time Position Applicants Actions or Behavior T=85 BOP Provides EOP entry conditions into PPM 5.2.1 as they occur.

Reports Wetwell pressure when GT 2 psig.

SRO Directs Wetwell Sprays be initiated with RHR-P-2B.

Directs sprays be terminated when WW/P drops below 1.68 psig.

BOP Initiates Wetwell sprays by opening RHR-V-27B.

Reports Wetwell sprays initiated.

BOP Reports Wetwell pressure when it is GT 12 psig (Approximately 11 minutes after Trigger 6 initiates).

SRO Ensures parameters are within DSIL, WW/L LT 51, RRC pumps are stopped (RRC-P-1B) and directs Drywell Cooling Fans be secured.

RO/BOP Stops Drywell Cooling Fans and reports completion to SRO.

SRO Directs Drywell sprays be initiated with RHR-P-2B.

BOP Checks DSIL and opens RHR-V-16B and attempts to open RHR-V-17B.

Page 16 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 BOP Notes that RHR-V-17B lost position indication as soon as the valve C/S was positioned. Reports condition to SRO.

SRO Sets Wetwell Pressure, Wetwell Level (PSP) and Drywell Temperature as a KEY parameters due to inability to spray.

RO/BOP Reports Drywell Temperature as it rises towards 330°F.

Reports trend of parameters as it approaches PSP limits.

RO/BOP If RCIC was initiated for level control, it may trip on high backpressure.

ROLE-PLAY - If asked to manually open RHR-V-17B, wait five minutes and report valve is stuck in the closed position and you can not get it opened.

COMMENTS:

Page 17 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 Event No. 10

==

Description:==

Initiates an EMERGENCY DEPRESSURIZATION when Drywell Temperature approaches 330°F or PSP is exceeded.

This event is initiated when it is determined that Drywell Temperature cannot be maintained LT 330°F or PSP is exceeded.

Critical step is to initiate an EMERGENCY DEPRESSURIZATION when drywell Temperature cannot be restored and maintained LT 330°F or when PSP has been exceeded.

Time Position Applicants Actions or Behavior T=90 BOP Reports Drywell Temperature as it approaches 330°F(Approximately 16 minutes after Trigger 6 initiated DW/T reaches 330°F).

Reports WW Pressure and WW Level as they apply to PSP curve.

SRO When Drywell Temperature cannot be maintained below 330°F or when PSP is exceeded, determines that an ED is required:

Follows overrides to PPM 5.1.3, Emergency RPV Depressurization.

Directs ECCS pumps not required for adequate core cooling be stopped from injecting.

RO/BOP Stops ECCS injection as necessary to maintain RPV level.

Page 18 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 SRO Requests Wetwell Level and when reported GT 17 foot, directs seven SRVs, ADS preferred, be opened.

RO/BOP Opens seven ADS SRVs as directed and reports completion to SRO.

SRO Directs RPV/L maintenance +13 inches to +54 inches.

Termination Cue: The scenario can be terminated when the reactor has been Emergency Depressurized and RPV level is under control in the band of +13 inches to +54 inches.

Comments:

Page 19 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 SRO TURNOVER INFORMATION Initial Conditions: Columbia is at approximately 85% power due to an economic dispatch request from BPA. REA-FN-1A is OOS due to bearing replacement. REA-FN-1B is protected.

Turnover: Increase Reactor Power to 90% power with flow. The reactivity brief has been completed and there are no preconditioning limits associated with the power/flow increase.

SIMULATOR SETUP INSTRUCTIONS Reset to IC-120 Tag REA-FN-1A Protect REA-FN-1B Ensure CRD-P-1A is running with dot above it Ensure Bat 2006scenario1A.txt is in BATCH directory Page 20 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1 2006scenario1.txt

>RON HAYDEN

>

>This scenario starts out at a reduced power level (approx 85%).

>

>Load this batch file by first initializing the simulator to AN 85% IC,

>then go to expert and type "BAT 2006scenario1.txt" and hit enter.

>

>Note: The following Batch Files need to be in the OPENSIM Batch

>file directory: 2006scenario#1.txt; 2006scenario1A.txt

>

>*************************

>* Trigger list *

>*************************

>

> Trigger 1: Accumulator Alarm Control Rod 14-23

> Trigger 2: Failure of RFW-P-AOP/1A to Auto start

> Trigger 3: CRD-P-1A reduced head followed by pump trip

> Trigger 4: RHR A Suction line rupture

> Trigger 5: Rackout RHR-P-2A

> Trigger 6: RRC-P-1A Pump Fails and LOCA

> Trigger 7: Conditional for RHR-V-17A control power fuses failing

> Trigger 11: Conditional to delete RFW-P-AOP/1A events

>

>**********************************************************************

>The following items setup conditions for the beginning of the scenario

>**********************************************************************

>

>REA-FN-1A Racked out IRF LOA-EPS330 RACKED-OUT

>

>EDR-V-19 Fails to Auto Close IMF AOV-SCN002F 3

>

>**********************************************************************

>The following items are triggered in the scenario

>**********************************************************************

>

> Trigger 1

>Accumulator alarm on control rod 14-23 IMF MAL-CRD001-1423 (1)

>

>Trigger 2

>RFW-A CONTROL OIL PRESS METER SIGNAL IOR IND-FPT015 (2) 68 120

>RFW-A BEARING OIL PRESS METER SIGNAL IOR IND-FPT016 (2) 18 120

> ANN-840A1E02 TURB A LUBE OIL PRESS LOW IMF ANN-840A1E01 (2 110) 0

>

> Trigger 3

>CRD-P-1A REDUCED HEAD IMF PMP-CRD001H (3) 100 1200

>

> CRD-P-1A SHAFT SEIZURE/TRIP IMF PMP-CRD001S (3 360) TRUE Page 21 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #1

>

> Trigger 4

> RHR A Suction line rupture IMF MAL-RHR001 (4) 8400 180

>

>Trigger 5

> Rackout RHR-P-2A Breaker IRF LOA-EPS384 (5) RACKED-OUT

>

> Trigger 6

> RRC-P-1A High Vibration/Pump Failure/LOCA IMF MAL-RRP002A (6) 16

> RRC-P-1A Low Bearing Oil Level Alarm IMF ANN-602A6A03 (6 30) 0

> RRC-P-1A Lower Seal failure IMF MAL-RRP001A (6 60) 100

> RRC-P-1A Upper Seal Failure IMF MAL-RRP001C (6 60) 100

> RRC-P-1A Shaft Seizure trip IMF PMP-RRP001S (6 180) TRUE

> Small LOCA IMF MAL-RRS004A (6 90) .4 300

>

> Large Steam Leak in Containment IMF MAL-RRS009A (6 600) 30900000 900

>

>**********************************************************************

>The following items are set up for conditionals

>**********************************************************************

>

> RHR-V-17B control power fails when red light illuminates IMF MOV-RHR011F (7) 0 TRGSET 7 "X01I276P.GT.0"

>

>Delete RFW-P-AOP/1A events on AOP switch to Run position TRG 11 "bat 2006scenario1A.txt" TRGSET 11 "X8Ai154R.eq.1"

>

>**********************************************************************

>The following set up triggers to initiate batch files

>**********************************************************************

>

>Local Bat file loads generic triggers for local plant actions bat local.txt 2006scenario1A.txt

>

> This file supplements 2006scenario1 and deletes overrides and

>malfunctions associated with failure of RFW-AOP to auto start.

>

>Remove overrides for RFW-A Control Oil Pressure meter DOR IND-FPT015 DOR IND-FPT016 DMF ANN-840A1E01 Page 22 of 22

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Facility: Columbia Scenario No: 2 Examiners: Operators:

Initial conditions: Columbia is operating at full power. CAS-C-1C is tagged out for motor replacement.

Turnover: Preparations are being made to perform the DG-1 quarterly surveillance. After turnover transfer SM-1 from the Normal power supply to the Startup power supply in preparation.

Event Timeline Event Type* Event Description No.

1. T=0 N (BOP) Transfers SM-1 from Normal to Startup power per PPM 2.7.1A
2. T=10 I (SRO/RO) B Flow Unit Failure (Tech Spec)
3. T=25 C (SRO/RO) Control Rod 38-23 Drifts In (Tech Spec)

R (RO) Recirc flow is lowered to LE 80 Mlbm/hr.

4. T=40 C (SRO/BOP) Ground on the operating TSW pump; Standby TSW pump does not start; Operating TSW pump trips on overcurrent - Total Loss of R (RO) TSW. Recirc flow is lowered to 60 Mlbm/hr and a manual scram is inserted.
5. T=45 M (ALL) Hydraulic ATWS.

RPV level lowered to -65 inches to LL. (Critical Step)

SLC started - Only one SLC pump starts

6. T=50 C (RO) RWCU-V-4 fails to Auto close on SLC Initiation
7. T=60 Insert Control Rods. (Critical Step)
8. T=75 EOP 5.1.2 exited, PPM 5.1.1 entered. RPV level raised +13 to

+54.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 The scenario will start with Columbia at full power. Turnover information will have the crew getting ready to support a DG-1 quarterly surveillance by transferring SM-1 from Normal to Startup power.

After the transfer a Flow Unit failure will occur. The crew should take actions to bypass it and refer to Tech Specs.

The next event is a control rod drifting in. The crew should enter ABN-ROD and take actions to insert the control rod. Reactor flow will be reduced to LE 80 Mlbm/hr. Tech Specs will be referenced.

The next event is a failure of the operating TSW pump. The crew will take actions to start the standby TSW pump which will not start. ABN-TSW will direct RRC flow be lowered to 60 Mlbm/hr and a manual scram be inserted. After the scram is inserted OPS1 will contact the control room and report that TSW-P-1As breaker closed when the door to the breaker was opened.

When a scram is inserted the crew will recognize a hydraulic ATWS has occurred. PPM 5.1.1 will be exited to PPM 5.1.2. RPV/L will be lowered to reduce reactor power. The crew will establish a LL (-65) and maintain RPV/L between -80 and -140.

After RPV Level drops to -50 and both RRC Pumps have tripped off, SLC will be initiated and only one of the SLC pumps will start. Additionally, RWCU-V-4 will fail to auto close but will be closed when the control switch is taken to close.

The crew will perform PPM 5.5.6 and PPM 5.5.1 and prevent a RCIC start by closing RCIC-V-1.

The crew will take actions to insert control rods and perform PPM 5.5.10 and 5.5.11. When the first Scram/Reset/Scram is attempted, all control rods will insert. The crew will exit PPM 5.1.2, stop SLC injection, and enter PPM 5.1.1. RPV/L will be returned to normal.

The scenario will be terminated when RPV/L is returned to +13 to +54 level band.

Page 2 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 1

==

Description:==

Transfers SM-1 from Normal to Startup power per PPM 2.7.1A.

This event is initiated by the SRO and is given in the turnover information.

Time Position Applicants Actions or Behavior T=0 SRO Directs RO to transfer SM-1 from TR-N (normal power) to TR-S (Startup power) per PPM 2.7.1A.

BOP Refers to PPM 2.7.1A section 5.6 and performs the following:

  • Place CB-S1 Sync Selector switch in the MANUAL position
  • Place CB-S1 control switch to CLOSE position
  • Place CB-N1 control switch to TRIP position
  • Place CB-S1 sync selector switch to OFF position Informs SRO that SM-1 is being powered from Startup.

RO Monitors plant conditions COMMENTS:

Page 3 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 2

==

Description:==

B Flow Unit Failure - Tech Spec.

The event is manually initiated by activating TRIGGER 1 after SM-1 is transferred to Startup power.

Time Position Applicants Actions or Behavior T=10 I (SRO/RO) Acknowledges alarms for Flow Reference Off Normal, P603-A8 3-6 and Rod Out Block and refers to ARP.

Determines the B Flow Unit has failed (light illuminated on apron on P603) and informs SRO.

SRO Directs backpanel status be checked.

Directs the B Flow Unit be bypassed per ARP step.

RO Bypasses B Flow Unit by placing bypass switch to the B position on P603.

Verifies bypass light illuminated for B Flow Unit. Reports alarms cleared.

SRO Refers to Tech Specs 3.3.1.1, LCS 1.3.2.1, and TS Bases page 3.3.1.1-9 for flow unit failure in Mode 1 (place in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).

Contacts PSRO and conducts brief.

COMMENTS:

Page 4 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 3

==

Description:==

. Control Rod 38-23 Drift In. (Tech Spec)

The event is manually initiated by activating TRIGGER 2 after flow unit has been bypassed/brief has occurred.

Time Position Applicants Actions or Behavior T=25 RO Acknowledges drift alarm and identifies 38-23 as having the drift light illuminated. Informs SRO of rod drift.

Takes immediate actions of ABN-ROD:

  • Selects rod
  • Depress Insert or the Continuously Insert P/B
  • Release and verify rod remains full in Informs SRO of actions.

BOP Pulls ARP for drifting rod and refers SRO to ABN-ROD.

SRO Per subsequent actions of ABN-ROD directs Core flow be reduced to LE 80 Mlbm/hr.

Directs resetting rod drift annunciator.

May direct an edge rod be selected.

Page 5 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 RO Reduces core flow to LT 80 Mlbm/hr.

Reports Reactor Power/Pressure/Level when flow reduction is completed.

SRO Refers to Tech Spec 3.1.3 C:

  • verifies total # of slow and inop rods is LE 8
  • Control rod is fully inserted within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
  • Disarm within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ROLE PLAY - If sent to isolate 38-23 per tech spec, wait three minutes and then activate TRIGGER 3 and report CRD-V-101 and CRD-V-102 for rod 38-23 are closed.

FLOOR ROLE PLAY - If asked, the Mon Run shows no thermal limits exceeded.

RO May selects an edge rod to minimize alarms.

COMMENTS:

Page 6 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 4

==

Description:==

Ground on operating TSW pump and standby pump will not start - Total Loss of TSW.

The event is manually initiated by activating TRIGGER 4 after rod tech specs are referenced.

Time Position Applicants Actions or Behavior T=40 BOP Acknowledges OL/Gnd alarm, investigates and reports rising amps on TSW-P-1B.

Refers SRO to ABN-TSW.

SRO Per ARP directs monitoring motor current and temperature and consider swapping to TSW-P-1A.

Refers to ABN-TSW and directs TSW-P-1A start.

BOP Attempts to manually start TSW-P-1A, notes it does not start, and reports Note: actions to SRO.

TSW-P-1B trips in 1.5 Reports trip (and lockout) of TSW-P-1B resulting a total loss of TSW.

minutes SRO Per subsequent actions of ABN-TSW, directs RRC flow be reduced to 60 Mlbm/hr.

RO Reduces RRC flow to 60 Mlbm/hr and reports completion to SRO.

SRO Directs a manual scram be inserted.

BOOTH OPERATOR - After the scram is inserted and before the crew takes the MT off line, ACTIVATE TRIGGER 5 to remove overrides and start TSW-P-1A.

ROLE-PLAY: As OPS1 contact the control room and inform them that when you walked by SM-75 the breaker for TSW-P-1A closed.

COMMENTS:

Page 7 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 5

==

Description:==

Hydraulic ATWS.

This event initiated by the SRO per EOP PPM 5.1.1.

Time Position Applicants Actions or Behavior Critical step for this event is to start SLC and lower RPV level to reduce RPV power.

T=45 RO Manually scrams the reactor and performs immediate operator actions of PPM 3.3.1:

  • mode switch to shutdown
  • monitors/reports power/level/pressure
  • Notes all rods not inserted and APRMs NOT downscale and continues with immediate scram actions:
  • inserts SRMs/IRMs Reports EOP entry on scram required and Reactor Power GT 5%.

Reports (Hydraulic ATWS) failure to scram condition exists.

SRO Enters PPM 5.1.1 and exits to PPM 5.1.2 due to ATWS.

Directs ADS be inhibited.

Directs manual control of HPCS.

BOP Places ADS override switches in INHIBIT.

Page 8 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Takes manual control of HPCS by holding HPCS-P-1 control switch to stop and arming and depressing manual HPCS initiation P/B.

Closes HPCS-V-4 after it is full open.

SRO Directs PPM 5.5.6 (Bypassing MSIV Low RPV level and Steam Tunnel High Temp Isolations) be performed.

BOP Performs PPM 5.5.6:

  • At P609, inserts key in MS-RMS-S84 and places to the BYPASS
  • At P611, inserts key in MS-RMS-S85 and places to the BYPASS Verifies alarms and reports completion to SRO.

SRO Directs RCIC start be prevented by closing RCIC-V-1.

BOP Closes RCIC-V-1 and verifies TRIP annunciator.

SRO Directs PPM 5.5.1 (Overriding ECCS RPV Injection Valve logic) be performed.

BOP Performs PPM 5.5.1 by:

  • At P625, places key for HPCS-V-4 in OVERRIDE position
  • At P629, places key for LPCS-V-5 in OVERRIDE position Page 9 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2

  • At P629, places key for RHR-V-42A in OVERRIDE position
  • At P618, places key for RHR-V-42B in OVERRIDE position
  • At P618, places key for RHR-V-42C in OVERRIDE position Verifies alarms and updates crew when completed.

SRO Directs stopping and preventing all injection into RPV except from boron injection systems, RCIC and CRD.

RO Stops and prevents all injection into RPV except from boron injection systems, RCIC and CRD. by lining feedwater up on startup valves using quick card:

  • Places RFW-LIC-600 to MANUAL
  • Places RFW-SC-601A and 601B to MDEM
  • Closes RFW-V-112A and V-112B
  • Opens RFW-V-118
  • Ensures startup valve controller in manual with a closed signal SRO Directs RPV/L be lowered to LT -65 and maintained between -80 and

-140.

Page 10 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 RO Reports RPV level as it drops and at -50.

When RPV level is LT -65, commences feeding RPV with feedwater to maintain RPV level as directed.

BOP/RO Announces EOP entry conditions as they occur:

PPM 5.2.1 on Hi DW Pressure / DW Temperature / WW Level PPM 5.3.1 on MS Tunnel Temperature Hi Hi SRO Enters PPM 5.2.1 and PPM 5.3.1 as EOP entries are announced.

Directs EOP initiations, actuations and DG starts be verified for -50 inch and 1.68 psig.

SRO Directs pressure control with SRVs and DEH.

BOP Control RPV Pressure as directed.

SRO Verifies that both RRC pumps have tripped on -50 RPV/L.

Directs SLC injection.

Page 11 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 RO Initiates SLC as directed using quick card:

  • Removes SLC key blanks and installs keys for switches
  • Places both SLC System control switches to OPER position Verifies SLC system operation and notes only one SLC pump starts when suction valves get full opened.

Reports flow rate (37 gpm) and initial tank level (4800 gal).

Verifies RWCU-V-4 isolation (Refer to event 6).

ROLE-PLAY - If sent to investigate the SLC pump, five minutes after being sent, report nothing obviously wrong with the pump or the breaker.

Comments:

Page 12 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 6

==

Description:==

RWCU-V-4 does not close when SLC is initiated.

This event is initiated active from the beginning of the scenario and becomes evident when SLC is started.

Time Position Applicants Actions or Behavior T=50 RO Initiates SLC as directed.

RO Verifies SLC system operation and notes only one SLC pump starts.

Reports flow rate and initial tank level.

Verifies RWCU-V-4 isolation.

RO Notes RWCU-V-4 is still opened.

Takes control switch to close and notes valve goes closed.

RO Reports RWCU-V-4 failure to auto close to SRO.

COMMENTS:

Page 13 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 7

==

Description:==

Inserts Control Rods (Critical Step).

The event initiated by SRO by performance of PPM 5.1.2 flow chart.

Time Position Applicants Actions or Behavior Critical step for this event is to insert control rods by performing PPM 5.5.10 and 5.5.11.

SRO Directs PPM 5.5.10 and 5.5.11 be performed to insert rods.

BOP Performs PPM 5.5.10:

  • At P650, pulls one fuse on TB1 (FO1, FO2, FO3, or FO4)
  • At P650, pulls one fuse on TB2 (FO1, FO2, FO3, or FO4)

BOP Performs PPM 5.5.11 to insert control rods and determines Tab B and F to be performed:

Starts both CRD pumps (May have OPS2 place both suction and drive water filters in service per ABN-CRD-MAXFLOW.

ROLE-PLAY - Three minutes after request for ABN-CRD-MAXFLOW ACTIVATE TRIGGER 26.

When trigger actions completed report completion to control room.

BOP Performs Tab B:

  • Places SDV HIGH LEVEL TRIP C/S to BYPASS
  • Notes scram cannot be reset and performs Attachment 6.11:
  • At P611 installs jumper between RPS-RLY-K9B stud 2 and RPS-RLY-K12F stud 4
  • At P611 installs jumper between RPS-RLY-K9D stud 2 and RPS-RLY-K12H stud 4 Page 14 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2

  • At P609 installs jumper between RPS-RLY-K9A stud 2 and RPS-RLY-K12E stud 4
  • At P609 installs jumper between RPS-RLY-K9C stud 2 and RPS-RLY-K12G stud 4

BOP When SDV has drained for more than 2 minutes:

  • Checks rod density
  • Initiates a manual scram Notes all rods inserted and reports condition to SRO.

COMMENTS:

Page 15 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 Event No. 8

==

Description:==

EOP 5.1.2 exited, PPM 5.1.1 entered. RPV level raised +13 to +54.

This event is initiated by report from BOP that all rods are in approximately 40 minutes after the start of the scenario.

Time Position Applicants Actions or Behavior T=75 SRO Acknowledges All rods in report and directs SLC system be secured.

RO Stops both SLC systems by returning control switches to normal.

Reports SLC secures to SRO.

SRO Announces exit of PPM 5.1.2 and entry into PPM 5.1.1.

Directs RPV level be raised to normal operating band of +13 inches to

+54 inches.

RO Raises RPV level to band given with feed and condensate system.

Reports RPV level in band as appropriate.

Termination Cue: The scenario can be terminated when SLC has been secured and RPV level has been returned to normal operating band of +13 inches to +54 inches.

COMMENTS:

Page 16 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 SRO TURNOVER INFORMATION Initial conditions: Columbia is operating at full power. CAS-C-1C is tagged out for motor replacement.

Turnover: Preparations are being made to perform the DG-1 quarterly surveillance. After turnover transfer SM-1 from the Normal power supply to the Startup power supply in preparation.

NRC SCENARIO #2 SETUP Reset Simulator to IC 119 Hang tags on CAS-C-1C Ensure bat files 2006scenario2A, 2B, and 2C are in the BATCH directory Put Turnover on SM Window Page 17 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 BAT FILE 2006Sscenario2.txt

>Load this batch file by first initializing the simulator to IC-14, then

>go the expert mode and type "BAT 2006scenario2.txt" and hit enter.

>

>Ensure 2006scenario2.txt & 2006scenario2A.txt,

>2006Scenario2B.txt, and 2006Scenario2C.txt are in BATCH directory.

>

>*************************

>* Trigger list *

>*************************

>

> Trigger 1: B Flow Unit Failure

> Trigger 2: Control Rod 38-23 Drifts in

> Trigger 3: Isolate Control Rod 38-23

> Trigger 4: Ground on TSW-P-1B (Also puts in Hydraulic ATWS)

> Trigger 5: Clear TSW overrides and start TSW-P-1A

> Trigger 6: Clear ATWS

>

>**********************************************************************

>The following items setup conditions for the beginning of the scenario

>**********************************************************************

>

>DISC CAS-C-1C IRF LOA-EPS127 DISCONNECT

>

> TSW-P-1A Start prevented IOR OVR-TSW001E ON IOR OVR-TSW001G OFF

>

>SLC-P-1B Failure to Start IOR OVR-SLC002C OFF

>

>RWCU-V-4 Fails to Auto Close IMF MOV-RWU010F 4

>

>SET MET DATA

> ENV-RWB002 AMBIENT TEMP AT 33 FEET IRF ENV-RWB002 90

> ENV-RWB001 AMBIENT DELTA TEMP ELEV 245-33' IRF ENV-RWB001 2

> ENV-RWB007 WIND SPEED AT 33 FEET IRF ENV-RWB007 5

> ENV-RWB005 WIND SPEED AT 245 FEET Page 18 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2 IRF ENV-RWB005 5

> ENV-RWB006 WIND DIRECTION AT 33 FEET IRF ENV-RWB006 180

> ENV-RWB004 WIND DIRECTION AT 245 FEET IRF ENV-RWB004 180

>

>ANN-840A4A04 CW PMP A MOTOR TRIP OFF IMF ANN-840A4A04 1

> ANN-840A4B04 CW PUMP A MOTOR OL/GND OFF IMF ANN-840A4B04 1

> ANN-840A5A07 TSW PMP A MOTOR TRIP IMF ANN-840A5A07 1

>

>**********************************************************************

>The following items are triggered in the scenario

>**********************************************************************

>

>Trigger 1 - B Flow Unit Failure IMF MAL-NIS006B (1) 0

>

> Trigger 2 - Control Rod 38-23 Drifts In IMF MAL-RMC004-3823 (2) 0

>

>Trigger 3 - Isolate Rod 38-23

> Isolate Control Rod 38-23 by closing CRD-V-101 and CRD-V-102 IRF LOA-CRD092 (3) CLOSE IRF LOA-CRD277 (3) CLOSE

>

>Trigger 4 - TSW-P-1B ground/trip

> TSW-P-1B WINDING GROUND IMF MOT-TSW004G (4) 60 999

> ANN-840A5H07 TSW PMP B MOTOR OL/GND IMF ANN-840A5H07 (4 5) 0

>

> ATWS IMF MAL-CRD007A1 (4) 100 IMF MAL-CRD007A2 (4) 94 IMF MAL-CRD007B1 (4) 100 IMF MAL-CRD007B2 (4) 94

>

>**********************************************************************

>The following set up triggers to initiate batch files

>**********************************************************************

>

Page 19 of 20

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #2

> Trigger 5

> Clear TSW Overrides and start TSW-P-1A (2B initiates 2C Bat file)

TRG 5 "bat 2006scenario2B.txt"

>

> Trigger 6

>Clear ATWS TRG 6 "bat 2006scenario2A.txt"

>

>Local Bat file loads generic triggers for local plant actions bat local.txt BAT FILE 2006Sscenario2A.txt

>This file supplements 2006 Scenario#2 and clears Hydraulic ATWS DMF MAL-CRD007A1 DMF MAL-CRD007A2 DMF MAL-CRD007B1 DMF MAL-CRD007B2

>

BAT FILE 2006scenario2b.txt

>This file supplements 2006 Scenario#2 and clears TSW-P-1A

>Overrides and starts TSW-P-1A DOR OVR-TSW001E DOR OVR-TSW001G "bat 2006scenario2c.txt"

>

BAT FILE 2006scenario2c.txt

>This file supplements 2006 Scenario#2 and starts TSW-P-1A IOR OVR-TSW001G ON Page 20 of 20

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