ML071570274
| ML071570274 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/05/2006 |
| From: | Nease R Operations Branch IV |
| To: | Parrish J Energy Northwest |
| References | |
| 50-397/06-301, ES-301, ES-301-1 50-397/06-301 | |
| Download: ML071570274 (191) | |
Text
ES-301 ADMINISTRATIVE TOPICS OUTLINE FORM ES-301-1 Facility: Columbia Generating Station Date of examination: November 2006 Examination Level (circle one): RO / SRO Operating test number:
Administrative Topic Type Code* Describe activity to be performed (see Note)
D SRO is given a turnover sheet that states a RX S/U is in progress and then parameters that indicate the reactor is critical. He is cued to determine his next Conduct of Operations action. To successfully complete the JPM he has to realize the Reactor is Critical prior to the ECP and take actions per PPM 3.1.2 which states to: stop control rod withdrawal, the CRS should direct the CRO to drive control rods in the reverse order until all rods are fully inserted; POC approval is required to proceed with further rod withdrawal; Consider the applicability of T.S. 3.1.2. He will fill out an attachment indicating what his next action will be and the basis for that action.
N SRO is cued that during an inspection of the Active Fire System in the Control Room, the 18 Halon systems storage tanks were found to be 85% of full charge Conduct of Operations pressure. He is asked to determine if any compensatory measures are required and if they are, what are they. He will refer to PPM 1.3.10B and determine operability. Per PPM 1.3.10B he is to issue an FPSI permit for the inoperable system. Once this is identified he is handed a blank FPSI permit to fill out.
N The SRO is given a turnover sheet that indicates a Division 1 instrument is OOS.
Equipment Control He is then handed a taggout for a Div 2 piece of equipment. The taggout erroneously pulls a fuse for a non-related Div 2 component that is the opposite division of the Div 1 component already OOS. If approved and this fuse is removed, a full scram would occur. He has to determine if he would sign taggout or not and explain why/why not.
D, S The SRO is given data and is required to enter the data into the QEDPS and print out the form. Then, based on the results of the QEDPS, he is to classify the Radiation Control event.
N, S After Scenario #2, Classify the event and fill out a CNF. The scenario should be classified as a Site Area Emergency per EAL 2.2.S.1 (ATWS with power GT Emergency Plan 5%).
Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (< 1; randomly selected)
(S)imulator Page 1
ES-301 ADMINISTRATIVE TOPICS OUTLINE FORM ES-301-1 Facility: Columbia Generating Station Date of examination: November 2006 Examination Level (circle one): RO / SRO Operating test number:
Administrative Topic Type Code* Describe activity to be performed (see Note)
D The RO is given a turnover sheet that states a RX S/U is in progress and then parameters that indicate the reactor is critical. He has to Conduct of Operations realize the Reactor is Critical or will be critical prior to the ECP and take actions per PPM 3.1.2 which states to: stop control rod withdrawal and notify the CRS. He will fill out an attachment indicating what his next action will be and the basis for that action.
M The RO is given that a startup is in progress and plant data showing current APRM indicated Power and Bypass Valve Positions and told to Conduct of Operations complete step Q31 of PPM 3.1.2 and inform the CRS of the results.
When done he will check the block on the attachment indicating APRM readings are GT power readings extrapolated from BPV position.
N The RO is given a section of OSP-INST-H101 that has 3 out of spec reading entered and not identified as out of spec readings. Candidate is Equipment Control told to verify readings and to submit the surveillance to the CRS for review. He should find the 3 out of spec readings and circle them.
N The RO is given a tagout that requires entry into a contaminated area of the plant to hang. His directions are to sign onto a specific RWP to Radiation Control perform the task. He is to determine if the tagout can be hung. The tagout has no discrepancies. When the RWP is reviewed it is discovered that the RWP does not allow entry into contaminated zones of the plant. The candidate will indicate that the task can not be performed.
Emergency Plan Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (< 1; randomly selected)
(S)imulator Page 2
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:
- 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 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
- 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.
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.
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)
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.
Page 2 of 5
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):
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)
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
- 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)
- 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
- 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 NEXT ACTION TO BE TAKEN:
BASIS FOR ACTION:
Page 6 of 6
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 identrified.
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 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.
CUE:
Initial the attachment indicating either actions are or are not required. If actions are required indicate (on the attachment) what they are.
Page 2 of 5
DETERMINE HALON SYSTEM IMPAIRED AND ISSUE A FIRE PROTECTION SYSTEM IMPAIRMENT
- 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 is required to be S/U*
issued.
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 9.1 of PPM 1.3.10B).
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 S/U*
required)
- Building/Elevation: Radwaste Building, 501 elevation S/U*
- Compensatory Action Taken: None (Control Room continually manned) S/U*
- 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 3 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 4 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:
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)
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 LRxxxxxx, Rev. X Page 2 of 9
DETERMINE ACTIONS FOR CRITICALITY OUTSIDE OF ECP (EARLY)
Verify materials current IAW SWP-TQS-01 prior to use.
LRxxxxxx, Rev. X Page 3 of 9
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: 10 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
- 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)
- 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, direction must 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 8 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
- 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
NEXT ACTION TO BE TAKEN:
BASIS FOR ACTION:
DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED 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 LRxxxxxx, Rev. X Page 2 of 9
DETERMINE IF A TAGOUT CAN BE HUNG WITH INFORMATION SUPPLIED Verify materials current IAW SWP-TQS-01 prior to use.
LRxxxxxx, Rev. X Page 3 of 9
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.
Page 2 of 5
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.
REVIEW SURVEILLANCE PROCEDURE OPS-INST-H101 I will be able to perform the assigned task (Initial):
I will not be able to perform the assigned task (Initial and Reason):
LRxxxxxx, Rev. X Page 2 of 9
REVIEW SURVEILLANCE PROCEDURE OPS-INST-H101 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 LRxxxxxx, Rev. X Page 3 of 9
REVIEW SURVEILLANCE PROCEDURE OPS-INST-H101 Verify materials current IAW SWP-TQS-01 prior to use.
LRxxxxxx, Rev. X Page 4 of 9
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.
VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2) 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 LRxxxxxx, Rev. X Page 2 of 9
VERIFY APRM READINGS GT POWER EXTRAPOLATED FROM BYPASS VALVE POSITION (PPM 3.1.2)
Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.
LRxxxxxx, Rev. X Page 3 of 9
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.6 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:
- APRMs indicate 11% power
- Feedwater temperature is 147°F
- House Loads are equal to 1% Core Thermal Power
- BPV#1 is indicating 38 percent open
- BPV#2 is indicating 39 percent open
- BPV#3 is indicating 38 percent open
- BPV#4 is indicating 36 percent open INITIATING You have been directed by the CRS to perform step Q32 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 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: __________
Accept a reading Fills in the following information:
within .2 high or BPV #1 % open is approximately 2.4 S/U*
low BPV #2 % open is approximately 2.5 S/U*
BPV #3 % open is approximately 2.4 S/U*
BPV #4 % open is approximately 2.2 S/U*
House Loads 1% (given) S/U*
Total % CTP is approximately 10.5 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 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 11% power
- Feedwater temperature is 147°F
- House Loads are equal to 1% Core Thermal Power
- BPV#1 is indicating 38 percent open
- BPV#2 is indicating 39 percent open
- BPV#3 is indicating 38 percent open
- BPV#4 is indicating 36 percent open Cue:
You have been directed by the CRS to perform step Q32 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 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 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 #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: __________
Rotates the collar of the arm and; S / U*
Depresses the pushbutton. S / U*
Verifies RCIC-V-46 OPENS S/U (Lube Oil Cooler Water Supply).
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 (LT 125 gpm).
When RCIC flow is GT 125 gpm, verifies RCIC-V-19 CLOSES. S/U Verifies RCIC-FIC-600 CONTROLS RCIC Turbine S/U speed at the flow setpoint (normally 600 GPM).
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 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 #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: __________
VERIFY PRESS SETPOINT S/U AUTO light is LIT DEPRESS PRESS SETPOINT S / U*
PSI pushbutton 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 #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: __________
Identifies all isolations are Refers to GDS screen and notes not complete TIP-V- 5 is not closed and S/U*
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.
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 #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 Notifies Radwaste that they will momentarily lose power to G33- S/U P0026 Verify CB-2/21 while LOCKOUT CIRCUIT AVAIL S/U 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 Verify CB-21/11 red closed light extinguishes S/U Page 2 of 5
- Items are Critical Steps Comments Element Standard Sat/Unsat 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 #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 perform the subsequent actions for ABN-RPS and transfer A RPS to its Alternate power supply. Inform the CRS when the subsequent actions for ABN-RPS have been completed and A RPS has been repowered.
- Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________
If power is available to RWCU-V- S/U*
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:
- 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
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 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 perform the subsequent actions for ABN-RPS and transfer A RPS to its Alternate power supply.
Inform the CRS when the subsequent actions for ABN-RPS have been completed and A RPS has been repowered.
Page 7 of 7
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 Moves selector over Record HD-LIC-1A output signal demand to get % S/U 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 -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 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: __________
Verify WOA-V-51B is open (SE #2)
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)
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)
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 #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.
At E-CP-DG/RP2, Depress the S / U*
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 #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: __________
Closes CRD-V-95 (Scram Air Header S/U*
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)
Install instrument drain plug for S/U CRD-PI-13 by rotating it clockwise Page 2 of 5
- Items are Critical Steps Comments Element Standard Sat/Unsat 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
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
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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.
- 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
- 7. T=60 Insert Control Rods. (Critical Step)
+54.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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.
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 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 to TR-S 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 TR-S.
RO Monitors plant conditions COMMENTS:
Page 3 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 and refers to ARP for Flow Reference Off Normal.
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.
Contacts PSRO and conducts brief.
COMMENTS:
Page 4 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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
- Drive control rod to position 00
SRO Per subsequent actions of ABN-ROD directs Core flow be reduced to LE 80 Mlbm/hr.
May direct resetting rod drift annunciator.
RO Reduces core flow to LT 80 Mlbm/hr.
Reports Reactor Power/Pressure/Level when flow reduction is completed.
Page 5 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 /> May refer to PPM 3.2.1 to verify actions for downpower are complete.
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 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 actions to SRO.
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 - 1 minute after scram is inserted, 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 opened the door to breaker for TSW-P-1A, the breaker closed in.
COMMENTS:
Page 7 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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
- Depresses Manual Scram Pushbuttons
- Initiates ARI
May report Hydraulic ATWS conditions exist.
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.
Page 8 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 BOP Places ADS override switches in INHIBIT.
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.
SRO Directs PPM 5.5.6 (Bypassing MSIV Low RPV level and Steam Tunnel High Temp Isolations) be performed.
- 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.
- 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 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006
- 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 and closed signal SRO Directs RPV/L be lowered and maintained between -80 and -140.
RO When RPV level is LT -65, commences feeding RPV with feedwater to maintain RPV level as directed. Note: RPV level may not get to 65 due to injection of SLC. Feed should NOT be initiated while level is GT -65 except from boron, RCIC and CRD.
Page 10 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 SRO Directs pressure control with SRVs and DEH.
BOP Control RPV Pressure as directed.
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.
Reports flow rate and initial tank level.
Verifies RWCU-V-4 isolation (Refer to event 6).
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.
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 11 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 12 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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.
- 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 13 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006
- 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, 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 14 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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.
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 15 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 16 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 IRF ENV-RWB005 5
> ENV-RWB006 WIND DIRECTION AT 33 FEET Page 17 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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) 100 IMF MAL-CRD007B1 (4) 94 IMF MAL-CRD007B2 (4) 94
>The following set up triggers to initiate batch files
> Trigger 5
> Clear TSW Overrides and start TSW-P-1A TRG 5 "bat 2006scenario2B.txt" Page 18 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006
> 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 19 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 100% 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)
- 7. T=70 M (ALL) RRC-P-1A High Vibration alarms followed by seal failures followed by LOCA.
- 8. T=75 C (BOP) RRC-V-19 fails to Auto close on 1.68 psig isolation signal.
- 9. T=85 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 PSP is exceeded. (Critical Step)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 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 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 Event No. 2
==
Description:==
Accumulator for Control Rod 14-23 Inop. (Tech Spec)
This event is initiated by activating TRIGGER 1 as soon as the crew takes the shift.
Time Position Applicants Actions or Behavior T=10 RO Acknowledges Rod Accumulator Trouble alarm and refers to ARP.
Determines alarm is associated with rod 14-23 and informs SRO.
SRO Directs local investigation.
Role Play - Wait a minute and call 2171 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 />.
Contacts PSRO and conducts brief.
COMMENTS:
Page 4 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 Acknowledges TURB A CNTR OIL PRESS LOW annunciator and refers to ARP.
Provides SRO with current control oil pressure (LT 70 psig).
SRO/RO 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 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 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 Event No. 4
==
Description:==
CRD-P-1A reduced flow and eventual pump trip 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 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.
SRO Refers to ABN-CRD and directs placing CRD-FC-600 (CRD Flow Controller) 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.
SRO Per ABN-CRD directs start of CRD-P-1B, the standby CRD Pump.
RO Starts CRD-P-1B and reports start to SRO.
SRO Directs CRD-FC-600 be nulled and returned to AUTO.
Page 6 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 RO Nulls CRD-FC-600 deviation meter and shifts CRD-FC-600 to AUTOMATIC.
COMMENTS:
Page 7 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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:
- Sump R1 Level Hi Hi
- Suppression Pool Level Hi/Low
- RHR-A Pump Room Water Level High (EOP entry)
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 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 LT +36.
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 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 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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
- Starts HPCS-P-2 (Service Water Pump)
- 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 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 and refers to ARP.
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
SRO Based on annunciators present, may direct tripping of RRC-P-1A.
BOP/RO Reports rising Drywell pressure and High Drywell Pressure annunciator.
SRO May directs a reactor scram prior to 1.68 psig scram.
Page 11 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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
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 (ALERT PER 3.1.A.1).
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)
- 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 Page 12 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 psig. (Refer to Event 8)
RO/BOP Notes B RRC Pump running with no RCC running. Informs SRO and requests to trip RRC pump.
May reports RRC-P-1A tripped.
SRO Directs RRC-P-1B be tripped.
RO/BOP Trips pump by depressing STOP P/B and reports to SRO.
SRO May direct RPV pressure reduction to reduce leak rate. NOTE: At some point in time 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 13 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 Manually closes EDR-V-19 by taking control switch to close. Notes it does close.
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 14 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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.
SRO Ensures parameters are within DSIL, WW/L LT 51, RRC pumps are stopped 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.
Notes that RHR-V-17B lost position indication as soon as the valve C/S was positioned. Reports condition to SRO.
Page 15 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 16 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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.
Time Position Applicants Actions or Behavior T=90 BOP Reports Drywell Temperature as it approaches 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.
Directs ECCS pumps not required for adequate core cooling be stopped from injecting.
RO/BOP Stops ECCS injection as necessary to maintain RPV level.
SRO Requests Wetwell Level and when reported GT 17 foot, directs seven SRVs, ADS preferred, be opened.
Page 17 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 18 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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: Return Columbia back to 100% 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 and 2006scenario1B.txt are in BATCH directory Page 19 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 10: Conditional for trip of CRD-P-1A
> Trigger 11: Conditional to delete RFW-P-AOP/1A events
> Trigger 12: Conditional to fail on seal leakage alarm when it annunciates
>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
> Trigger 4
> RHR A Suction line rupture Page 20 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 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 1800
>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"
> CRD-P-1A SHAFT SEIZURE IMF PMP-CRD001S (10) TRUE TRGSET 10 "X03i121e.eq.0"
>Delete RFW-P-AOP/1A events on AOP switch to Run position TRG 11 "bat 2006scenario1A.txt" TRGSET 11 "X8Ai154R.eq.1"
>Fails of RRC-P-1A seal leakage high when it annunciates IMF ANN-602A6B02 (12) 0 TRGSET 12 "JN06B02.GT.0"
>The following set up triggers to initiate batch files
>Local Bat file loads generic triggers for local plant actions bat local.txt Page 21 of 21
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Facility: Columbia Scenario No: 3 Examiners: Operators:
Initial Conditions: Columbia is in the process of starting up following a 35 day outage. The Reactor is critical and RPV pressure is approximately 600 psig. HPCS-P-1 is OOS and is planned to be returned to service within the next few hours.
Turnover: Continue with the startup by pulling control rods to get BPVs 30% open. The reactivity brief has been completed. The evaluator for CRO1 will be the Peer Checker for pulling control rods. Swap RCC Pumps for run time equalization to RCC-P-1C running and RCC-P-1B in standby (These two evolutions may be done concurrently). A pre-job brief for DW entry is scheduled in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Control Rod withdrawal is to commence at step 35-1 with control rod 10-43.
Event Timeline Event Type* Event Description No.
- 1. T=0 R (RO) Withdraw Control Rods
- 3. T=10 I (SRO/RO) Reed Switch Failure on 42-35 position 8 (Tech Spec)
- 4. T=30 I (SRO/RO) IRM H Fails Downscale (Tech Spec)
- 5. T=40 Min Seismic Earthquake Lockout on TR-S C (SRO/BOP) SM-8 de-energized (TR-B fails to close in on SM-8; DG-2 output breaker fails to auto close but may be manually closed) (Critical step)
- 7. T=60 RHR-P-2C breaker fails to auto/manually close.
C (BOP) LPCS-P-1 and RHR-P-2B breakers fails auto start but can be manually started
- 8. T=70 Spray the Drywell when Wetwell pressure exceeds 12# (Critical Step)
- 9. T=80 Restore RPV level +13 to +54 inches (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 The scenario starts with a plant startup in progress. Reactor is critical at 600 psig and HPCS is OOS. The crew is directed to continue with the startup. The first task is to raise reactor power by pulling control rods to get bypass valves 30% open.
While the control rod pull is going on, the BOP operator will swap RCC pumps to RCC-P-1C running and RCC-P-1B in standby.
About five minutes into the rod pulls control rod 42-35 will loose position indication. The crew will enter ABN-RPIS. The crew will substituting a rod position per SOP-RSCS-OPS and SOP-RWM-OPS. Tech Specs will be referenced.
After control rod pull re-commences, IRM H will fail downscale. The crew will respond and bypass the failed IRM. Tech Specs will be referenced.
The next event is a Minimum Seismic Earthquake. After actions have been completed another tremor will occur and Offsite power will be lost. A reactor scram will occur and the crew will respond to the electrical panel SM-7 will be powered from TR-B. SM-8 will become de-energized when TR-B fails to close in and DG-2 output breaker also fails to close in. Manual actions will close in DG-2 onto SM-8.
The next event is a Operating Basis Earthquake which causes a large LOCA. RPV level will drop. The crew will enter EOP 5.1.1 on RPV/L and EOP 5.2.1 on DW/P. LPCS-P-1 and RHR-P-2B will not automatically start on high DW/P but manual actions will start both pumps. Additionally RHR-P-2FC will not start but can not be manually started. As Primary Containment pressures rise the crew will note they are both the same and conclude drywell pressure response is not consistent with LOCA conditions. Wetwell sprays will be initiated when WW/P exceeds 2 psig. DW sprays will be initiated when WW/P exceeds 12 psig. DW sprays will be secured when DW pressure drops to 1.68 psig and will be initiated again if WW pressure reaches 12 psig.
As RPV level continues to drop RPV pressure will also drop. The crew may take action to lower RPV pressure or allow LOCA to drop pressure to allow LP ECCS injection. When RPV pressure drops to approx 320 psig, LPCS will start to inject and other low pressure ECCS will start to inject as RPV pressure continues to drop.
The scenario will be terminated when RPV level has been returned to normal and Containment sprays have been initiated/re-initiated.
Page 2 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Event No. 1
==
Description:==
Withdraw Control Rods to open BPVs to 30% open.
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 withdraw control rods to open BPVs to 30% open.
RO Withdraws control rods to open BPVs to 30% open.
BOP Monitor plant conditions.
COMMENT:
Page 3 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Event No. 2
==
Description:==
Swap RCC pumps to RCC-P-1C running and RCC-P-1B in standby.
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 swap RCC Pumps.
BOP Refers to PPM 2.8.3 starting at step 5.2.3 and contacts OPS 2 to verify RCC-V-1C and RCC-V-2C are opened.
CUE: As OPS2 report RCC-V-1C and RCC-V-2C are opened.
BOP Places C/S for RCC-P-1C in the Auto after Start position and verifies proper pump operation.
BOP Secure RCC-P-1B and takes C/S for RCC-P-1B to the Auto after Stop position and verifies actions.
BOP Contacts OPS2 to verify discharge check valve closed.
CUE: As OPS2 report the discharge check on RCC-P-1B did close.
BOP Reports completion to SRO.
COMMENT:
Page 4 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Event No. 3
==
Description:==
Failed Reed Switch on Control Rod 42-35 position 08.
This event is initiated when the RO pulls control rod 42-35 to the 08 position.
Time Position Applicants Actions or Behavior T=10 RO When Control Rod 42-35 is pulled to position 08 receives Rod Out Block annunciator.
Pulls ARP and reports alarm to SRO.
RO Notes rod block, insert block and data fault lights illuminated on horizontal P603 panel and informs SRO.
RO Recognizes that no position is displayed on RWM and informs SRO.
SRO Enters ABN-RPIS. Discusses step 4.2 and may contact SNE.
ROLE-PLAY: When ABN-RPIS is entered, step 4.3 states At the direction of the CRS, move the control rod to an operable position per Attachment 7.1 or 7.2.
FLOOR EVALUATOR - Inform the CRS that the SNE has been contacted and has issued a Control Rod Deviation Sheet - hand him the deviation sheet to move rod 42-35 from 08 to 06.
SRO Directs ABN-RPIS (step 4.3) Attachment 7.1 be performed.
RO Refers to ABN-RPIS Attachment 7.1, step 7.1.1 and inserts a substitute value into RSCS and RWM. Per SOP-RSCS-OPS completes section 5.3:
- Verify that a notch is displayed in the SUBSTITUTE POSITION window (RSCS display)
- Verify the displayed notch position is the expected position for the control rod Page 5 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3
- Verify the SEL SUB illuminated on the SUBSTITUTE POSITION SELECTION pushbutton EVALUATOR NOTE: The SEL SUB light WILL NOT be illuminated due to a Simulator Vs. Plant difference - provide a verbal cue to the operators that the light is illuminated.
- Depress the SUBSTITUTE POSITION SELECTION pushbutton
- Refer to SOP-RWM-OPS to substitute a rod position in RWM RO Refers to SOP-RWM-OPS and performs the following:
- Directs SRO to refer to TS 3.1.3, 3.1.6, 3.3.2.1, 3.10.7, and 3.9.5 PRIOR to entering a substitute position SRO Refers to TS as directed, notes no applicability, and directs RO to continue with entering a substitute rod position.
RO Continues with SOP-RWM-OPS:
- Verifies rod selected is correct
- Touches MENUS
- Selects Substitute/Bypass Rod
- Verifies substitute position is not correct and touches up to display correct substitute position
- Selects Substitute Rod Position
- Obtains Independent Verification from BOP operator Notes Rod Out block clears.
BOP Performs Independent Verification as requested.
COMMENT:
Page 6 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Event No. 4
==
Description:==
IRM H Fails Downscale (Tech Spec).
The event is MANUALLY initiated with TRIGGER 1 when SOP-RWM-OPS is completed.
Time Position Applicants Actions or Behavior T=30 RO Acknowledges and reports Rod Out Block and IRM Monitor Downscale annunciators and refers to ARP.
Reports IRM H is reading downscale.
SRO Per both ARPs, directs RO to bypass IRM H.
RO Places IRM H in the bypass position and clears alarms.
SRO Refers to Technical Specification 3.3.1.1 and LCS 1.3.2.1. Notes this IRM channel is not a required IRM channel and that no TS conditions apply and no actions are required.
Conducts brief.
COMMENTS:
Page 7 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Event No. 5
==
Description:==
Min Seismic Earthquake; Lockout on TR-S; SM-8 becomes de-energized (TR-B fails to close in on SM-8; DG-2 output breaker fails to auto close but may be closed in manually) (Critical step)
The event is MANUALLY initiated with TRIGGER 2.
Time Position Applicants Actions or Behavior Critical step for this event is to close in the output breaker for DG-2 to re-power SM-8 loads.
BOOTH OPERATOR - To start this event turn on the EQ machine at low volume, working up to MID volume and run for a total EQ of 15 seconds. Three seconds after EQ machine is on, activate TRIGGER 2.
ROLE-PLAY: When EQ is done, contact the control room as OPS1 and inform them you are in the Reactor Building and shaking has been felt.
T=40 BOP Responds to Minimum Seismic alarm and refers to ARP.
Announces Minimum Seismic Earthquake and directs SRO to ABN-EARTHQUAKE.
Check Red/Yellow Response Spectrum Lights on H13-P823 and reports number of amber lights illuminated to SRO.
SRO Direct actions per ABN-EARTHQUAKE.
Direct OPS-1 to have EOs commence a quick tour of Plant.
BOP Makes plant announcement per ABN-EARTHQUAKE.
BOOTH OPERATOR: When announcement has been completed, turn on the EQ machine (at the mid range level left after first play) for 10 seconds. TWO seconds into this tremor, activate TRIGGER 3.
Page 8 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 T=45 RO Notes reactor scram and performs immediate operator actions of PPM 3.3.1:
- mode switch to shutdown
- monitors and reports power/level/pressure
- inserts SRMs/IRMs
SRO Acknowledges scram report and enters EOP 5.1.1 on low RPV level.
BOP Responds to electrical boards and diagnoses:
- Lockout on TR-S
- SM-7 powered from TR-B
- SM-8 de-energized Attempts to close in TR-B on SM-8:
- Places CB-B8 SYNC SELECTOR to MAN
- Places CB-B8 C/S to the CLOSE position and notes SYNC PERMIT light illuminated but breaker failed to close Closes in DG-2 to re-power SM-8
- Places CB-DG2/8 SYNC SELECTOR to MAN
- Places CB-DG2/8 MODE SELECTOR to C.R. position
- Places CB-DG2/8 C/S to the CLOSE position and verifies it re-powers SM-8 Updates SRO on Electrical Plant status.
Page 9 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 BOP/RO May report drywell pressure rising (due to lack of cooling) and if DW/P reaches 1.68 psig reports it as an EOP entry.
BOP/RO Notes CAS compressors off and directs OPS3 to reset and restart CAS compressors.
BOP Notes MSIVs closed (on loss of both RPS buses). Takes pressure control with SRVs and updates crew.
SRO Directs pressure control with SRVs.
BOP/RO Reports EOP 5.3.1 entry on Secondary Containment dP High.
SRO Enters PPM 5.3.1 on Secondary Containment dP High.
BOP May investigate Secondary Containment EOP entry and start SGT .
ROLE-PLAY - Wait one minutes after request and then activate TRIGGER 23 to reset and restart the CAS compressors. Report completion to the control room.
COMMENTS:
Page 10 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Event No. 6
==
Description:==
OBE; LOCA; Drywell Floor Rupture.
This event manually initiated after actions have been completed for last event and SM-8 has been re-powered.
BOOTH OPERATOR - Turn on the EQ machine at mid volume (where left from last tremor),
working up to full volume. Run EQ for 15 seconds total. Three seconds after EQ machine is on, activate TRIGGER 4.
Time Position Applicants Actions or Behavior T=50 BOP Acknowledges OBE alarm and refers to ARP.
Announces OBE (ALERT per 9.4.A.1).
Check Red/Yellow Response Spectrum Lights on H13-P823 and reports findings to SRO.
RO/BOP Notes rising drywell pressure and reports EOP entry when pressure exceeds 1.68 psig.
As Containment pressures continue to rise, it is noted that Drywell and Wetwell pressures rise together indicating loss of suppression function.
The CRS is informed when condition is recognized.
SRO Enters PPM 5.2.1 and PPM 5.1.1 on high DW/P when DW/P is 1.68#.
Directs initiations, isolations and DG starts for 1.68 psig be verified.
RO Notes RPV level drop and reports EOP entry when RPV/L drops to
+13.
Comments:
Page 11 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Event No. 7
==
Description:==
On 1.68 psig drywell pressure initiations: LPCS-P-1, RHR-P-2B and RHR-P-2C breakers fail to auto close. LPCS-P-1 and RHR-P-2B may be closed manually.
The event is initiated when drywell pressure reaches 1.68 psig.
Time Position Applicants Actions or Behavior T=60 BOP Verifies isolations, DG starts and initiations and notes LPCS-P-1, RHR-P-2B, and RHR-P-2C did not start at 1.68 psig.
Attempts to start RHR-P-2C and notes breaker does not close. Reports failure to start to SRO.
Starts LPCS-P-1 and RHR-P-2B by taking their control switches to START. Verifies both pumps start and system parameters normal.
Reports pump status to CRS.
COMMENTS:
Page 12 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Event No. 8
==
Description:==
Spray Drywell when Wetwell pressure exceeds 12 psig. (Critical Step)
This event is initiated by the SRO when Wetwell pressure exceeds 12 psig.
Time Position Applicants Actions or Behavior Critical Step is to initiate drywell sprays when wetwell pressure exceeds 12 psig.
T=70 BOP Provides EOP entry conditions into PPM 5.2.1 as they occur.
Reports Wetwell pressure when GT 2 psig.
BOP Notes that Drywell and Wetwell pressures are approximately the same pressure and reports condition to SRO. (SITE AREA EMERGENCY PER EAL 3.1.S.1).
SRO Directs Wetwell Sprays be initiated with either RHR loop and that sprays be terminated when WW/P drops below 1.68 psig.
BOP Initiates Wetwell sprays by opening RHR-V-27A/B. Reports Wetwell sprays initiated.
BOP Reports Wetwell pressure when it is GT 12 psig.
SRO Ensures parameters are within DSIL, WW/L LT 51, RRC pumps are stopped 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-2A/2B.
Page 13 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 BOP Checks DSIL and opens RHR-V-16A/B and opens RHR-V-17A/B.
Notes drop in wetwell/drywell pressures and may report drywell spray initiation and a positive effect on containment parameter has been noted.
COMMENTS:
Page 14 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 Event No. 9
==
Description:==
Restoration of RPV level +13 to +54 inches (Critical Step)
This event is initiated by the SRO due to RPV level drop caused by LOCA.
Time Position Critical Step is to restore RPV level to +13 to +54 inch band.
T=80 RO/BOP Continues to supply RPV level reports.
SRO Enters PPM 5.1.1 on low RPV level.
Directs RPV level restoration with both CRD pumps.
RO/BOP Reports RPV level as it drops.
RO/BOP Directs OPS2 to perform ABN-CRD-MAXFLOW and place both CRD suction and drive filters in service.
ROLE-PLAY - Four minutes after request, activate TRIGGER 26. When simulator actions are complete contact the control room and report completion.
SRO Directs RCIC be initiated to recover RPV level.
RO/BOP Initiates RCIC using quick card.
Reports injection as appropriate.
SRO As RPV level continues to drop with CRD and RCIC flow maximized, may directs RPV Pressure be reduced to allow feeding with LP ECCS pumps or wait until pressure is low enough (due to LOCA) to inject.
Page 15 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 RO/BOP Opens SRVs as necessary to drop RPV pressure.
As RPV pressure drops below 470 psig, notes injection valves open for running ECCS pumps.
SRO Directs RPV level maintenance +13 to +54 inches with available low pressure ECCS systems as RPV pressure allows.
RO/BOP Allows low pressure ECCS pumps to inject and removes pumps as necessary to control RPV level in band.
Scenario Termination point is when RPV level has been returned to normal operating band.
Comments:
Page 16 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 CREW TURNOVER INFORMATION Initial Conditions: Columbia is in the process of starting up following a 35 day outage. The Reactor is critical and RPV pressure is approximately 600 psig.
HPCS-P-1 is OOS and is planned to be returned to service within the next few hours.
Turnover: Continue with the startup by pulling control rods to get BPVs 30%
open. The reactivity brief has been completed. The evaluator for CRO1 will be the Peer Checker for pulling control rods. Swap RCC Pumps for run time equalization to RCC-P-1C running and RCC-P-1B in standby (These two evolutions may be done concurrently). A pre-job brief for DW entry is scheduled in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Control Rod withdrawal is to commence at step 35-1 with control rod 10-43.
SIMULATOR SETUP INSTRUCTIONS Reset to IC 118 Tagout HPCS-P-1 and V-4 Acknowledge HPCS BISIs Ensure RWCU dot is over correct C/S Sign off pull sheets through step 34-16. Crew starts on 35-1 Set up Earthquake machine on low volume Mark up Startup Flow Charts per guide Ensure BAT files 2006scenario3A.txt is in BATCH directory Page 17 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3 BAT FILES
>Load this batch file by first initializing the simulator to IC-118, then
>go the expert mode and type "BAT 2006Scenario3.txt" and hit enter.
>Ensure 2006Scenario3.txt & 2006Scenario3A.txt are in BATCH directory.
>* Trigger list *
> Trigger 1: IRM H Fails Downscale
> Trigger 2: Minimum Seismic EQ
> Trigger 3: TR-S lockout; SM-8 de-energizes
> Trigger 4: OBE Earthquake/LOCA
>The following items setup conditions for the beginning of the scenario
> CB-B8 Fail As Is IMF BKR-EPS031 4
> DG-2 Output Breaker fails to auto close IMF BKR-DGN003 3
> CB-RHR-P-2B Fail Auto Close IMF BKR-RHR002 3
> CB-LPCS-P-1 Fail Auto Close IMF BKR-CSS002 3
> CB-RHR-P-2C Fail As Is IMF BKR-RHR003 4
>BKR HPCS-V-4 RACKOUT IRF LOA-EPS140 RACKED-OUT
>Drywell Floor Failure IMF MAL-PCN006 TRUE
> Control Rod 42-35 Reed Switch 08 fails to close IMF MAL-RMC008-4235C 8
>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 IRF ENV-RWB005 5
> ENV-RWB006 WIND DIRECTION AT 33 FEET IRF ENV-RWB006 180 Page 18 of 19
Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station November 2006 NRC SCENARIO #3
> ENV-RWB004 WIND DIRECTION AT 245 FEET IRF ENV-RWB004 180
>The following items are triggered in the scenario
> Trigger 1
> IRM H Fails Downscale IMF MAL-NIS002H (1) 1
> Trigger 2
> Minimum Seismic EQ; TR-S lockout; SM-8 de-energizes IMF MAL-RWB001 (2) 0.1
> Trigger 3
> TRS LOCKOUT IMF MAL-OED001 (3 10) TRUE
> Trigger 4
> (OBE) and LOCA IMF MAL-RRS004B (4 20) 0.9 400
>The following set up triggers to initiate batch files
> OBE Earthquake TRG 4 "bat 2006Scenario3A.txt"
> Local Bat file loads generic triggers for local plant actions bat local.txt 2006Scenario3A.txt OBE Earthquake IMF MAL-RWB001 0.125 Page 19 of 19