ML051250312
| ML051250312 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 01/31/2005 |
| From: | Hironori Peterson NRC/RGN-III/DRS/OLB |
| To: | Nuclear Management Co |
| References | |
| 50-331/05-301 50-331/05-301 | |
| Download: ML051250312 (365) | |
Text
QF-1030-11 Rev. 1 (FP-T-SAT-30)
SITE: DAEC TASK TITLE: Survey Map review and dose Calculations to determine the adequacy of the RWP dose setting and determine if a dose extension is required.
JPM NUMBER: 2.3.10-02 REV. 1 RELATED PRA INFORMATION:
TASK NUMBERS: 1.11 (Senior Reactor Operator)
K/A NUMBERS: Generic 2.3.10-02 3.3 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 25 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.3.10-02, Survey Map review and dose Calculations to determine the adequacy of the RWP dose setting and determine if a dose extension is required, Rev. 1 JPM Number: 2.3.10-02 JPM
Title:
Survey Map review and dose Calculations to determine the adequacy of the RWP dose setting and determine if a dose extension is required.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.3.10-02, Survey Map review and dose Calculations to determine the adequacy of the RWP dose setting and determine if a dose extension is required, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The plant is operating at about 60% power.
The date is currently 12/12/04. You are the CRS.
The piping supporting Level Transmitter LT-1065B, to the drain valve of 1T93A Moisture Separator Drain Tank that controls the Drain to the 1E-05A heater, has failed.
The old piping and LT have been removed. The New piping and LT are ready for installation.
Brad Pit is the only qualified welder who can perform the job.
A welder apprentice has run all of the required material to the job site.
The following are the estimated times required for the job:
- 10 minutes to prep the welds.
- 20 minutes to secure the new LT and pipes in place.
- 15 minutes to actually weld the pipes.
Brad has received 1855 mrem for the year.
Scaffolding for the job has been erected at location 5 on the survey map.
INITIATING CUES (IF APPLICABLE):
Given a Duane Arnold survey map, determine the specific dose for the job, and any other dose considerations, if any.
Show all work assumptions on the survey map.
Page 3 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.3.10-02, Survey Map review and dose Calculations to determine the adequacy of the RWP dose setting and determine if a dose extension is required, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. Survey map of the Heater Bay at 61% power.
- 2. Copy of ACP 1411.17 to write on.
General
References:
ACP 1411.17, Rev. 16 Task Standards:
- Determines that the total dose for the prep, support and weld is approximately 157.5 mrem.
- Determine that the worker will need a dose extension.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Determine the dose needed for the job.
Critical Y (SEQ-)
Standard: Determines that the total dose for the prep, support and weld is approximately 157.5 mrem +/-1.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note, the Candidate may add some additional dose for the trip to and from the job.
This will not affect the fact that Brad will need a dose extension for the job.
Page 4 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.3.10-02, Survey Map review and dose Calculations to determine the adequacy of the RWP dose setting and determine if a dose extension is required, Rev. 1 Performance Step: Determine if the worker will need a dose extension.
Critical Y (SEQ-)
Standard: Determine that the worker will need a dose extension.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Per ACP 1411.17, the workers first line supervisor may extend the individuals Critical Y SEQ-) dose.
Standard: Determine that Brads supervisor or higher will have to extend his dose to greater than 2000 mrem.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete when the candidate has determined the dose for the weld job, and the first line supervisor, or higher, must grant a dose extension.
If the Candidate continues on with ACP 1411.17 requirements, Cue him that the Shift Manager will identify the other requirements. The JPM is complete.
Stop Time:
Page 5 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.3.10-02, Survey Map review and dose Calculations to determine the adequacy of the RWP dose setting and determine if a dose extension is required, Rev. 1 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None SIMULATOR PREPARATIONS:
None INSTRUCTOR ACTIONS:
- Ensure that there is a copy a Duane Arnold Energy Center HP Survey map of the Heater Bay.
- Ensure that there is a copy of ACP-1411.17, Occupational Dose Limits and Upgrades.
Page 6 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.3.10-02, Survey Map review and dose Calculations to determine the adequacy of the RWP dose setting and determine if a dose extension is required, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
The plant is operating at about 60% power.
The Date is currently 12/12/04. You are the CRS.
The piping supporting Level Transmitter LT-1065B, to the drain valve of 1T93A Moisture Separator Drain Tank that controls the Drain to the 1E-05A heater, has failed.
The old piping and LT have been removed. The New piping and LT are ready for installation.
Brad Pit is the only qualified welder who can perform the job.
A welder apprentice has run all of the required material to the job site.
The following are the estimated times required for the job:
- 10 minutes to prep the welds.
- 20 minutes to secure the new LT and pipes in place.
- 15 minutes to actually weld the pipes.
Brad has received 1855 mrem for the year.
Scaffolding for the job has been erected at location 5 on the survey map.
INITIATING CUES (IF APPLICABLE):
Given a Duane Arnold survey map, determine the specific dose for the job, and any other dose considerations, if any.
Show all work assumptions on the survey map.
Page 7 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.3.10-02, Survey Map review and dose Calculations to determine the adequacy of the RWP dose setting and determine if a dose extension is required, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 8 of 8
AIP 406 INJECTION WITH SBLC
Purpose:
To use the SBLC System as an alternate means of injecting water into the RPV when normal injection systems are inadequate or unavailable.
Location: Control Room Panel 1C05, RB 833', RB 812, RB 786, TB Basement Equipment Required: (1) GE #75 Key, (1) #2081 Key Instructions:
CAUTION Alternate Injection from the SBLC Tank is NOT authorized during an ATWS since it is reserved for boron injection.
(1) To inject from the SBLC TANK, perform the following (actions taken at 1C05 unless specified otherwise):
(a) Unlock STANDBY LIQUID CONTROL Switch HS-2613 and place the switch in the PUMPS A AND B RUN position. __________
(b) Verify system operation using any of the following indications: __________
- SBLC Pumps A/B Red Running Lights ON
- SBLC Squib White Lights OFF
- SBLC Flow, FI-2620
- SBLC Pressure, PI-2605
- SBLC Tank Level, LI-2600A (c) If not previously performed, deenergize SBLC tank heaters when SBLC tank level reaches about 30% by placing the following breakers in the OFF position. __________
Breaker Location 1B3446 RB, 786 Level, F5 1B1426 RB, 812 Level, E10 AIP 406 Page 1 of 6 Rev. 5
AIP 406 INJECTION WITH SBLC (d) Secure SBLC Pumps as tank level approaches 0%. __________
(e) As directed by the CRS, refill the SBLC tank as follows:
- 1. To refill with sodium boron solution, return the system to the Standby Readiness condition per OI 153. __________
- 2. To refill with Condensate Service Water, unlock and open V-26-13, Demin Water Supply to 1T-218, on the RB 833 Level. __________
(f) As directed by the CRS, continue injection into the RPV by repeating Steps (a) through (e). __________
(2) To inject from the TEST TANK, perform the following (actions taken on the RB 833' level unless specified otherwise):
(a) Verify SBLC Pumps secured. __________
(b) Unlock and close V-26-1, SBLC Storage Tank 1T-218 Outlet Isolation. __________
(c) Open V-09-60, 1T-218 Demin Water Supply Isolation. __________
(d) Unlock and open V-26-18, SBLC Test Tank 1T-217 Outlet Isolation. __________
(e) Unlock and throttle open V-26-14, Demin Water Supply Isolation, as necessary to maintain test tank level above 1/4 full on local sight glass LG-2604. __________
AIP 406 Page 2 of 6 Rev. 5
AIP 406 INJECTION WITH SBLC (f) If the Squib Valves were NOT previously opened, perform the following at 1C05:
- 1. Unlock and place STANDBY LIQUID CONTROL Switch HS-2613 in the PUMPS A AND B RUN position. __________
- 2. Verify both Squib Valve Ready lights turn OFF and SBLC SQUIB VALVE CONTINUITY LOSS (1C05A, F-3) annunciator is activated. __________
- 3. Return and lock STANDBY LIQUID CONTROL Switch HS-2613 in the STOP position. __________
NOTE Local operation of the SBLC pumps is authorized in the following steps to minimize the impact on control room resources.
(g) Commence injection into the RPV by locally starting SBLC Pumps using handswitches HS-2608 and HS-2610. __________
(h) Verify system operation using any of the following local and/or remote indications: __________
1C05
- SBLC Flow, FI-2620
- SBLC Pressure, PI-2605 Local
- SBLC Flow, FIT-2620
- SBLC Pressure, PI-2606
- SBLC Tank Level, LG-2604 AIP 406 Page 3 of 6 Rev. 5
AIP 406 INJECTION WITH SBLC NOTE Continue performing actions in Step (i) until directed by the control room to secure injection.
CAUTION SBLC pump(s) should be secured if test tank level drops below 1/4 full to prevent pump damage.
(i) Control SBLC Test Tank Level between 1/4 full and full as indicated on local gage LG-2604 by performing the following actions, as necessary:
- 1. Throttle V-26-14, DEMIN WATER SUPPLY ISOLATION. __________
- 2. Locally start/stop SBLC Pumps using handswitches HS-2608 and HS-2610. __________
(j) If necessary, start an additional Demin Water Pump using local handswitches in the TB Basement. __________
Restoration:
(1) When no longer required for RPV injection, secure the SBLC pumps and return the system to the Standby Readiness Condition per OI 153. __________
AIP 406 Page 4 of 6 Rev. 5
AIP 406 INJECTION WITH SBLC
References:
(1) OI 153, Standby Liquid Control System (2) P&ID M-109, Condensate & Demineralized Water System (3) P&ID M-126, Standby Liquid Control System AIP 406 Page 5 of 6 Rev. 5
AIP 406 INJECTION WITH SBLC Usage Level CONTINUOUS USE Effective Date:
TECHNICAL REVIEW Prepared by: Date:
Technical Date:
Review by:
Operations Reviewed by: Date:
Operations Committee PROCEDURE APPROVAL Approved by Procedure Owner: Date:
Operations Support Manager Approved by: Date:
DAEC Plant Manager AIP 406 Page 6 of 6 Rev. 5
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV.
JPM NUMBER: 2.1.12-01 REV. 0 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 1.11 (Senior Reactor Operator)
TASK TITLE(S):
K/A NUMBERS: Generic 2.1.12 4.0 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 30 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 JPM Number: 2.1.2-01 JPM
Title:
Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
You are the on shift Shift Manager.
The plant is operating in MODE 1.
HPCI has just received a spurious auto initiation signal and injected into the RPV.
The initiation signal will not reset and HPCI has been secured.
INITIATING CUES (IF APPLICABLE):
You are to determine the Administrative and Regulatory requirements for this event.
Page 3 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 JPM PERFORMANCE INFORMATION Required Materials: 1. ACP 114.4
- 2. ACP 114.5
- 3. ACP 1402.3 General
References:
- 1. ACP 114.4
- 2. ACP 114.5
- 3. ACP 1402.3 Task Standards:
- Determine that HPCI is inoperable and enter TS 3.5.1 Condition F.
- Determine that a CAP must be written.
- Identify that the HPCI initiation is due to an INVALID signal.
- Determine that HPCI is an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable to the NRC.
- Determine that an LER is required.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Determine HPCI is inoperable due to the Aux Oil Pump being in Pull to Lock.
Critical Y (SEQ-)
Standard: Determine that HPCI is inoperable and enter TS 3.5.1 Condition F.
14-day LCO and verify that RCIC is Operable Immediately.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the Candidate states that he will have to fill out the LCO paper work, (which includes the Safety Function Determination paper work).
Cue him that someone else will fill out the applicable paper work.
Page 4 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 Performance Step: Determine that a CAP (Corrective Action Program) is required.
Critical Y (SEQ-)
Standard: The Candidate will indicate that a CAP is required for the HPCI event.
Performance: SATISFACTORY UNSATISFACTORY Comments: EVALUATOR, if the Candidate has identified the Tech Specs and NRC reporting requirements before he states that he will initiate a CAP, it is not necessary for the Candidate to fill out the Pre-Screening portion of the CAP.
EVALUATOR, when the Candidate determines that a CAP is required, hand him the attached ACTION REQUEST. Cue him as follows:
- Tell him that the Computer is down.
- Assume that what the RO has done is Complete and Correct. With the information given, you are to fill out the Pre-Screener portion of this CAP.
Evaluator note that the purpose of this JPM is not to test the Candidates knowledge of the CAP system, but to have him determine the TS and Nuclear reporting requirements of this event.
Comments on the filling out of CAP sections Part I and Part II.
He will X that HPCI is inoperable.
NOTE the following is a sample of what the Candidate MAY put in the blanks for Basis for Operability and Compensatory Actions. The following are examples of what the Candidate may enter.
In the Basis for Operability section the Candidate will describe why HPCI is inoperable. His words will reflect that HPCIs Aux Oil Pump is placed in Pull to Lock, this will eliminate any auto initiation for the HPCI turbine.
In the Compensatory Actions section the Candidate may put NONE, he may put that they entered the LCO for HPCI, or they may state that they put the HPCI Aux Oil Pump in PTL.
He will X the Unplanned LCO Action Statement entry for HPCI being inoperable.
He will X the External Notification required box and explain the following NRC reporting requirements.
Page 5 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 Performance Step: Determine Reportability of the event to the NRC.
Critical Y (SEQ-) Review whether the initiation and injection were due to a valid or invalid signal.
Standard: Identify that the HPCI initiation is due to an INVALID signal.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Determine Reportability of the event to the NRC.
Critical Y (SEQ-)
Standard: Determine that HPCI is an 8-hour reportable event. (50.72(b)(3)(v)(d).
Performance: SATISFACTORY UNSATISFACTORY Comments: If the Candidate does not go any further with the reportability, CUE- him that you understand that ALL Reportability Requirements are completed.
Performance Step: Determine Reportability of the event to the NRC.
Critical Y (SEQ-)
Standard: Determine that HPCI requires a LER.
Performance: SATISFACTORY UNSATISFACTORY Comments: Evaluator there are a few options for the LER, any ONE of the following are acceptable:
50.73(a)(2)(iv)(a), 50.73(a)(2)(vii)(d).
Page 6 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 Performance Step: Internal notification requirements.
Critical n (SEQ-)
Standard: Determine that upper plant management must be notified.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note, this may not specifically be mentioned, because the initiation of the CAP will perform this function.
Terminating Cues: When the candidate has discussed the above, inform him that the JPM is complete.
Stop Time:
Page 7 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 8 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 INSTRUCTOR ACTIONS:
Read the initiating Cues.
Page 9 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 TURNOVER SHEET INITIAL CONDITIONS:
You are the on shift Shift Manager.
The plant is operating in MODE 1.
HPCI has just received a spurious auto initiation signal and injected into the RPV.
The initiation signal will not reset and HPCI has been secured.
INITIATING CUES (IF APPLICABLE):
You are to determine the your administrative requirements for this event.
Page 10 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1-12-01, Determine Administrative Requirements for an Automatic Initiation of HPCI and injection into the RPV, Rev. 0 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 11 of 11
QF-1030-11 Rev. 1 (FP-T-SAT-30)
SITE: DAEC TASK TITLE: PERFORM REQUIRED ACTIONS FOR RPV INJECTION WITH THE SBLC TEST TANK JPM NUMBER: 295031-10 REV. 3 RELATED PRA INFORMATION:
TASK NUMBERS: NSPEO 47.08 and RO 95.43 K/A NUMBERS: EA1.08 (3.8/3.9)
APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: X Perform:
EVALUATION LOCATION: In-Plant: X Control Room:
Simulator: Other:
Lab:
Time for Completion: 15 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 10
QF-1030-11 Rev. 1 (FP-T-SAT-30) 295031-10, Perform Required Actions for RPV Injection with the SBLC Test Tank, Rev. 3 JPM Number: 295031-10 JPM
Title:
PERFORM REQUIRED ACTIONS FOR RPV INJECTION WITH THE SBLC TEST TANK Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 10
QF-1030-11 Rev. 1 (FP-T-SAT-30) 295031-10, Perform Required Actions for RPV Injection with the SBLC Test Tank, Rev. 3 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
- RPV level is +100 inches and lowering at 1" every 15 minutes.
- RPV pressure is 800 psig and lowering 1psig every 5 minutes.
- Two Demin Water Pumps are running.
- The SBLC system has been used for injection, but the SBLC tank is empty.
INITIATING CUES (IF APPLICABLE):
- The OSS directs you to coordinate with the NSOE and perform RPV injection with the Standby Liquid Control system test tank IAW AIP 406, INJECTION WITH SBLC.
Page 3 of 10
QF-1030-11 Rev. 1 (FP-T-SAT-30) 295031-10, Perform Required Actions for RPV Injection with the SBLC Test Tank, Rev. 3 JPM PERFORMANCE INFORMATION Required Materials: AIP 406, Rev. 3 General
References:
EOP-SP Section 400, Alternate Injection Procedures Task Standards: 1. Operator simulates unlocking and closing of V-26-01.
- 2. Operator simulates opening V-09-60.
- 3. Operator simulates unlocking and opening V-26-18.
- 4. Operator simulates unlocking and throttling open V-26-14.
- 5. Operator simulates starting the A and B SBLC pumps.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
When the Candidate gets AIP 406, he will review the procedure and determine that the first section will be N/Aed, as it has already been completed in the control room.
Performance Step: Verify that the SBL pumps are secured.
Critical N (SEQ-)
Standard: Pumps secured Performance: SATISFACTORY UNSATISFACTORY Cue: When the operator asks if the SBLC pumps are secured, inform him that Comments: they are not running.
Page 4 of 10
QF-1030-11 Rev. 1 (FP-T-SAT-30) 295031-10, Perform Required Actions for RPV Injection with the SBLC Test Tank, Rev. 3 Performance Step: Unlock and close V-26-1, SBLC STORAGE TANK 1T-218 OUTLET ISOLATION.
Critical Y (SEQ-)
Standard: Operator simulates using a 2081 key, unlocks and closes V-26-1.
Performance: SATISFACTORY UNSATISFACTORY Cue: V-26-1 is closed.
Comments: Note that the Candidate will indicate that he will turn the valve handwheel in the right or clockwise direction, and as he does this the stem of the valve will lower until it disappears.
Note, all of the locks on this system use a 2081 key. It is on the Aux and Seconds key ring.
Performance Step: Open V-09-60, 1T-218 DEMIN WATER SUPPLY ISOLATION.
Critical Y (SEQ-)
Standard: Operator simulates opening Performance: SATISFACTORY UNSATISFACTORY Cue: When the operator demonstrates the ability to correctly operate a valve, Comments: inform the operator that the V-09-60 is open.
Performance Step: Open V-26-18, SBLC TEST TANK 1T-217 OUTLET ISOLATION.
Critical Y (SEQ-)
Standard: Operator simulates unlocking and opening V-26-18.
Performance: SATISFACTORY UNSATISFACTORY Cue: V-26-18 is open.
Comments: Note that the Candidate will indicate that he will turn the valve handwheel in the left or counter clockwise direction, and as he does this the stem of the valve will rise above the valve handwheel.
Page 5 of 10
QF-1030-11 Rev. 1 (FP-T-SAT-30) 295031-10, Perform Required Actions for RPV Injection with the SBLC Test Tank, Rev. 3 Performance Step: Unlock and throttle open V-26-14, DEMIN WATER SUPPLY ISOLATION as Critical Y (SEQ-) necessary to maintain test tank level above 1/4 full on local sight glass LG2604 Standard: The operator simulates unlocking and throttling open V-26-14.
Performance: SATISFACTORY UNSATISFACTORY Cue: V-26-14 is open. If the operator asks if SBLC Test Tank level is rising, Comments: inform the operator that tank level is rising.
Performance Step: If the Squib Valves were NOT previously opened, perform the following at Critical N (SEQ-) 1C05.
- Unlock and place STANDBY LIQUID CONTROL Switch HS-2613 in the PUMPS A AND B RUN position.
- Verify both Squib Valve Ready lights turn OFF and SBLC SQUIB VALVE CONTINUITY LOSS (1C05A, F-3) annunciator is activated.
- Return and lock STANDBY LIQUID CONTROL Switch HS-2613 in the STOP position.
Standard: These steps have already been completed, and will be N/Aed.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note the turnover stated that SBLC was already injected into the RPV. This means that the squibs have already been fired. These steps can be N/Aed.
Performance Step: Commence injecting into the RPV by locally starting SBLC pumps using Critical Y (SEQ-) handswitches HS-2608 and HS-2610.
Standard: The operator simulates starting SBLC pumps via HS-2608 and HS-2610. The operator also calls the control room and informs them that he is injecting into the RPV with Demin water via the SBLC test tank.
Performance: SATISFACTORY UNSATISFACTORY Cue: When asked, inform the operator that both pumps are running.
Comments:
Page 6 of 10
QF-1030-11 Rev. 1 (FP-T-SAT-30) 295031-10, Perform Required Actions for RPV Injection with the SBLC Test Tank, Rev. 3 Performance Step: Verify system operation using any of the local and/or remote indications.
Critical N (SEQ-)
Standard: The operator either calls the control room or verifies locally that SBLC is operating normally.
Performance: SATISFACTORY UNSATISFACTORY Cue: If the Candidate calls the control room, give him the following SBLC Comments: parameters:
- SBLC flow 60 gpm
- SBLC Pressure 850 psig
- SBLC Test tank level 1/2 full and stable.
If the Candidate decides to use the local parameters, he will point out the local flow and pressure indicators and give appropriate values.
- The turnover stated that RPV pressure is about 800 psig, the discharge pressure given should be a little higher than 800 psig.
- For a flow, these are positive displacement pumps that are required to pump 26.2 gpm per pump against a reactor pressure of 1000 psig. So the total flow should be between 60 and 70 gpm.
CUE after the parameters are given, inform the Candidate that another operator will monitor the SBLC flows.
Terminating Cues: SBLC pumps started and test tank level being maintained (simulated).
Stop Time:
Page 7 of 10
QF-1030-11 Rev. 1 (FP-T-SAT-30) 295031-10, Perform Required Actions for RPV Injection with the SBLC Test Tank, Rev. 3 SIMULATOR SET UP:
JPM is inplant therefore no Simulator requirements INSTRUCTOR ACTIONS:
- 1. Note any discrepancies in the comments section.
- 2. Initial all steps you observe the student perform.
- 3. Inform the student that all communications should be directed to the instructor, and that all actions are to be simulated.
- 4. Pass out the JPM Turnover to the student and read initial conditions and initiating cue to student.
Page 8 of 10
QF-1030-11 Rev. 1 (FP-T-SAT-30) 295031-10, Perform Required Actions for RPV Injection with the SBLC Test Tank, Rev. 3 TURNOVER SHEET INITIAL CONDITIONS:
- RPV level is +100 inches and lowering at 1" every 15 minutes.
- RPV pressure is 800 psig and lowering 1psig every 5 minutes.
- Two Demin Water Pumps are running.
- The SBLC system has been used for injection, but the SBLC tank is empty.
INITIATING CUES (IF APPLICABLE):
- The OSS directs you to coordinate with the NSOE and perform RPV injection with the Standby Liquid Control system test tank IAW AIP 406, INJECTION WITH SBLC.
Page 9 of 10
QF-1030-11 Rev. 1 (FP-T-SAT-30) 295031-10, Perform Required Actions for RPV Injection with the SBLC Test Tank, Rev. 3 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 10 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30)
+ JOB PERFORMANCE MEASURE (JPM)
SITE: DAEC JPM TITLE: Switch CRD Pump Discharge Filters JPM NUMBER: 201001-03 REV. 8 RELATED PRA INFORMATION:
TASK NUMBER(S) / NSPEO 30.12 TASK TITLE(S):
K/A NUMBERS: 201001 A2.05 2.9/2.9 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: X Perform:
EVALUATION LOCATION: In-Plant: X Control Room:
Simulator: Other:
Lab:
Time for Completion: 15 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY:
Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 201001-03, Switch CRC Pump Discharge Filters, Rev. 8 JPM Number: 201001-03 JPM
Title:
Switch CRD Pump Discharge Filters Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 201001-03, Switch CRC Pump Discharge Filters, Rev. 8 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
- The CRD system is in its normal configuration with the exception of reference leg backfill, and the plant is operating at 100% steady state.
- Reactor level instruments reference leg backfill system is secured.
- During review of the NSPEO logs, the STA identified that the reading on the CRD Discharge Filter P is reading 15 psid and initiated a WRC to change the filter.
- The GEMAC Reactor Level Instruments Reference Legs Backfill Systems has been isolated IAW OI-880, Section J-1 and will remain isolated for repairs to the backfills supply line.
INITIATING CUES (IF APPLICABLE):
- The CRS has directed you to place the standby CRD discharge filter 1F-201B[A] in service IAW OI-255, Control Rod Drive Hydraulic System.
Page 3 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 201001-03, Switch CRC Pump Discharge Filters, Rev. 8 JPM PERFORMANCE INFORMATION Required Materials: OI 255, Control Rod Drive Hydraulic System, Section 6.3.1 General
References:
- 1. OI 255, Control Rod Drive Hydraulic System, Rev 53, Section 6.3.1 Task Standards: 1. Operator simulates closing V-17-18[15].
- 2. Operator simulates closing V-17-20[17].
- 3. V-17-22[21] is open (simulated).
- 4. V-17-21[22] is closed (simulated).
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: A note indicates that the Discharge Filter should be changed if the P is >10 Critical N (SEQ-) psid at 40 gpm system flow.
Standard: This implies that PDIS 1812 is reading greater than 10 psid.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the student asks what PDIS 1812 is reading; Cue him that PDIS 1812 is currently reading approximately 15 psid Performance Step: Shutdown the GEMAC Reactor Level Instruments Reference Legs Backfill Critical N (SEQ-) Systems has been isolated IAW OI-880, Section J-1.
Standard: Turnover item, the GEMAC Reactor Level Instruments Reference Legs Backfill Systems has been isolated IAW OI-880, Section J-1.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 201001-03, Switch CRC Pump Discharge Filters, Rev. 8 Performance Step: Verify that V-17-14[13], the inlet isolation valve to standby filter 1F-201B[A], is Critical N (SEQ-) open.
Standard: Operator simulates verifying V-17-14[13] is open.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the operator wants to verify that the valve is OPEN by taking the hand wheel in the closed, (clockwise), direction, Cue him that the valve hand wheel turns in that direction.
Performance Step: Verify that V-17-22[21], the outlet isolation valve to standby filter 1F-201B[A], is Critical N (SEQ-) closed.
Standard: Operator simulates verifying V-17-22[21] is closed.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the operator wants to verify that the valve is CLOSED by taking the hand wheel in the closed, clockwise), direction, Cue him that the valve hand wheel DOES NOT turn in that direction.
Performance Step: Vent the Filter 1F-201B[A] as follows:
Critical N (SEQ-)
Open the Combined Vent/Drain Line Isolation, V-17-20(17).
Standard: Operator simulates opening V-17-20(17).
Performance: SATISFACTORY UNSATISFACTORY Comments: When told he will turn the valve in the Counter Clockwise direction to OPEN the valve; Cue the Candidate that the valve turns in the stated direction for a while, then stops.
Page 5 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 201001-03, Switch CRC Pump Discharge Filters, Rev. 8 Performance Step: Vent the Filter as follows, continued:
Critical N (SEQ-)
Crack open CRD Pump Discharge Filter 1F-201B(A) Vent Valve V-17-18(15) and vent as necessary.
Standard: 1F-201B(A) Vent Valve V-17-18(15) simulated cracked open.
Performance: SATISFACTORY UNSATISFACTORY Comments: When told he will turn the valve in the Counter Clockwise direction to crack OPEN the valve; Cue the Candidate that the valve turns in the stated direction.
If the operator asks if he can hear flow noise; Cue him that he can hear flow noise when V-17-18 is opened.
If asked if the flow noise is steady, e.g. not like it is pushing air bubbles; Cue him that the flow sounds steady.
Performance Step: Vent the Filter 1F-201B[A] as follows, continued:
Critical Y (SEQ-)
Close V-17-18(15) and V-17-20(17).
Standard: Operator simulates closing V-17-18(15) and V-17-20(17).
Performance: SATISFACTORY UNSATISFACTORY Evaluator, the Critical portion of this step is to have ONE of the two valves Comments: CLOSED. Therefore, if the Candidate proceeds and only one of these valves is closed, the Critical portion of this step is satisfied.
When told he will turn the valve in the Clockwise direction to CLOSE the valve; Cue the Candidate that the valve turns in the stated direction until it stops.
When one or both of the valves are closed and if the operator asks if the flow noise has stopped; Cue him that the flow noise has stopped.
Page 6 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 201001-03, Switch CRC Pump Discharge Filters, Rev. 8 Performance Step: Slowly open V-17-22[21], the outlet isolation valve to 1F-201B[A].
Critical Y (SEQ-)
Standard: Operator simulates opening V-17-22[21].
Performance: SATISFACTORY UNSATISFACTORY Comments: When told he will turn the valve in the Counter Clockwise direction to OPEN the valve; Cue the Candidate that the valve turns in the stated direction until it stops.
Performance Step: Slowly close V-17-21[22], the outlet isolation valve to 1F-201A[B].
Critical Y (SEQ-)
Standard: Operator simulates closing V-17-21[22].
Performance: SATISFACTORY UNSATISFACTORY Comments: When told he will turn the valve in the Clockwise direction to CLOSE the valve; Cue the Candidate that the valve turns in the stated direction until it stops.
Performance Step: Verify that CRD system flow is 40 GPM and a drive water pressure is Critical N (SEQ-) approximately 260 psid as indicated on FI-1814 CRD SYSTEM FLOW and PDI-1825A (CRD PRESSURE) DRIVE WATER DELTA P, respectively, at 1C05 Standard: Operator simulates calling the control room and having the control room operator verify that system flow is 40 GPM and drive water pressure is approximately 260 psid.
Performance: SATISFACTORY UNSATISFACTORY Comments: When the operator calls the control room Cue him that system flow is 40 gpm and drive water delta P is about 260 Page 7 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 201001-03, Switch CRC Pump Discharge Filters, Rev. 8 Performance Step: Restore the Reactor Level Instrumentation Backfill System in service per OI-880, Critical N (SEQ-) Section J-1.
Standard: Operator simulates calling the control room and asking if he should restore Reactor Level Instrumentation Backfill System in service per OI-880, Section J-1.
Performance: SATISFACTORY UNSATISFACTORY Comments: When the operator calls the control room Cue him that someone else will restore the reference leg back fill system Terminating Cues: When the Operator simulates calling the control room and asking if he should restore Reactor Level Instrumentation Backfill System in service per OI-880, Section J-1 Stop Time:
Page 8 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 201001-03, Switch CRC Pump Discharge Filters, Rev. 8 TURNOVER SHEET INITIAL CONDITIONS:
- The CRD system is in its normal configuration with the exception of reference leg backfill, and the plant is operating at 100% steady state.
- Reactor level instruments reference leg backfill system is secured.
- During review of the NSPEO logs, the STA identified that the reading on the CRD Discharge Filter P is reading 15 psid and initiated a WRC to change the filter.
- The GEMAC Reactor Level Instruments Reference Legs Backfill Systems has been isolated IAW OI-880, Section J-1 and will remain isolated for repairs to the backfills supply line.
INITIATING CUES (IF APPLICABLE):
- The CRS has directed you to place the standby CRD discharge filter 1F-201B in service IAW OI 255, Control Rod Drive Hydraulic System.
Page 9 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 201001-03, Switch CRC Pump Discharge Filters, Rev. 8 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Historical Record: (Optional)
Page 10 of 10
6.0 ISOLATION OF A MAIN STEAM LINE DURING POWER OPERATION ............................... 1 6.0ISOLATION OF A MAIN STEAM LINE DURING POWER OPERATION CAUTION Closure of MSIVs in two Main Steam Lines may result in a half scram on the Reactor Protection System.
(1) Reduce reactor power to 65 percent or less. ___________
NOTE Unless two valve isolation is required to meet PCIS criteria or other plant conditions, the CRS has the discretion to close only the outboard or the inboard MSIV in accordance with step 2 or step 3 below. (Due to the difficulty of equalizing around the first MSIV during recovery.)
(2) At 1C04, slow close CV4413 [CV4416, CV4419, or CV4421] A[B,C, or D] outboard MSIV. Control valve by holding HS4413B [HS4416B, HS4419B or HS4421B] in test. When MSIV CV4413 [CV4416, CV4419, or CV4421] indicates full closed, place HS4413A [HS4416A, HS4419A or HS4421A] in close, then release HS4413B
[HS4416B, HS4419B, or HS4421B]. ___________
CAUTION Exercise caution when performing the following step to ensure the inboard MSIV selected is in the same main steam line as the outboard MSIV closed in Step (2).
(3) At 1C03, slowly close CV4412 [CV4415, CV4418, or CV4420] A[B,C, or D] inboard MSIV. Control valve by holding HS4412B, [HS4415B, HS4418B, or HS4420B] in test. When MSIV CV4412 [CV4415, CV4418, or CV4420] indicates full closed, place HS4412A [HS4415A, HS4418A, or HS4420A] in close. Then release HS4412B [HS4415B, HS4418B, or HS4420B]. ___________
(4) If reactor operation is to continue at power levels greater than 65% with one steamline isolated, refer to IPOI 3, "Power Operations", Section 6.0, STEADY STATE POWER OPERATIONS ABOVE 65% POWER WITH ONE STEAMLINE ISOLATED. ___________
(5) To preclude cooling in the idle MSL and buildup of condensate, open MSL drain valves MO4423, MO-4424 and CV-1064 MSL Header Drain. ___________
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Isolate a MSIV at Power JPM NUMBER: 239001-03 REV. 1 RELATED PRA INFORMATION:
TASK NUMBER(S) / 48.04 TASK TITLE(S):
K/A NUMBERS: 239001 A2.10 3.8/3.9 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 9
QF-1030-11 Rev. 2 (FP-T-SAT-30) 239001-03, Isolate a MSIV at Power, Rev. 1 JPM Number: 239001-03 JPM
Title:
Isolate a MSIV at Power Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 9
QF-1030-11 Rev. 2 (FP-T-SAT-30) 239001-03, Isolate a MSIV at Power, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
(If initial conditions do not exactly match read this step)
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- The system engineer for the Main Steam System has informed the Shift Manager that they have just discovered that the C outboard MSIV, CV-4419 did not meet the specification for the Leak Rate Test performed during the last outage. As a result, it must be declared inoperable for its PCIS function.
- It has been determined that the C main steam line must be isolated.
- The Shift Manager has completed the Technical Specification determination.
- Reactor power has been lowered to approximately 63% power in preparation to isolate the C main steam line.
INITIATING CUES (IF APPLICABLE):
- As the CRS I direct you manually isolate the C Main Steam Line by closing both MSIVs on the C Steam Line.
Page 3 of 9
QF-1030-11 Rev. 2 (FP-T-SAT-30) 239001-03, Isolate a MSIV at Power, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: A simulator operator is required to perform the JPM.
General
References:
- 1. OI 683 Main Steam, Rev. 43 Task Standards: 1. Close CV-4419
- 2. Close CV-4418 Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Reduce reactor power to 65% or less.
Critical N (SEQ-)
Standard: Power verified at <65%.
Performance: SATISFACTORY UNSATISFACTORY Comments: This is a turnover item.
Performance Step: At 1C04, slow close CV-4419 outboard MSIV. Control valve by holding HS4419B Critical Y (SEQ-) in test.
When CV-4419 indicates full closed, place HS4419A in CLOSE, then release HS4419B.
Standard: CV-4419 closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 9
QF-1030-11 Rev. 2 (FP-T-SAT-30) 239001-03, Isolate a MSIV at Power, Rev. 1 Performance Step: At 1C03, slowly close CV-4418 inboard MSIV. Control valve by holding HS4418B Critical Y (SEQ-) in test.
When MSIV CV-4418 indicates full closed, Place HS4418A in close. Then release HS4418B.
Standard: CV-4418 is closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: If reactor operation is to continue at power levels greater than 65% with one Critical N (SEQ-) steamline isolated, refer to IPOI 3, Power Operations, Section 6 STEADY STATE POWER OPERATIONS ABOVE 65% POWER WITH ONE STEAMLINE ISOLATED.
Standard: If steady state power operations above 65% are expected, IPOI 3 must be addressed. The Candidate will ask the CRS if steady state power operations above 65% is expected.
Performance: SATISFACTORY UNSATISFACTORY Comments: WHEN the Candidate questions if steady state power is expected to be above 65%
or IF the candidate pulls IPOI 3, CUE him that we are planning on raising power above 65%, and another operator will be taking care of that IPOI 3 action.
Performance Step: To preclude cooling in the idle MSL and build up of condensate, open MSL drain Critical N (SEQ-) valve MO-4423.
Standard: MO-4423 is opened.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 5 of 9
QF-1030-11 Rev. 2 (FP-T-SAT-30) 239001-03, Isolate a MSIV at Power, Rev. 1 Performance Step: To preclude cooling in the idle MSL and build up of condensate, open MSL drain Critical N (SEQ-) valve MO-4424.
Standard: MO-4424 is opened.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: To preclude cooling in the idle MSL and build up of condensate, open CV-1064, Critical N (SEQ-) MSL Header Drain.
Standard: CV-1064 is opened.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: When CV-1064 is opened, the task is complete.
Stop Time:
Page 6 of 9
QF-1030-11 Rev. 2 (FP-T-SAT-30) 239001-03, Isolate a MSIV at Power, Rev. 1 SIMULATOR SET UP:
The power must be less than 65% for this JPM.
EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 7 of 9
QF-1030-11 Rev. 2 (FP-T-SAT-30) 239001-03, Isolate a MSIV at Power, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
- The system engineer for the Main Steam System has informed the Shift Manager that they have just discovered that the C outboard MSIV, CV-4419 did not meet the specification for the Leak Rate Test performed during the last outage. As a result, it must be declared inoperable for its PCIS function.
- It has been determined that the C main steam line must be isolated.
- The Shift Manager has completed the Technical Specification determination.
- Reactor power has been lowered to approximately 63% power in preparation to isolate the C main steam line.
INITIATING CUES (IF APPLICABLE):
- As the CRS I direct you manually isolate the C Main Steam Line by closing both MSIVs on the C Steam Line.
Page 8 of 9
QF-1030-11 Rev. 2 (FP-T-SAT-30) 239001-03, Isolate a MSIV at Power, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Historical Record: (Optional)
Page 9 of 9
DEFEAT 1 RCIC LOW RPV PRESSURE ISOLATION AND 211" DEFEAT 20 22 29 34 401 13 26 23 25 24 21 37 02 07 1C06 10 1C05 11 36 18 1C04 27 15 EOP Override 28 16 Switch Locations 17 DEFEAT 1 1C03 19 30 2 3 41 39 45 42 35 4
32 33 14 1
43 44 402 38 40 DEFEAT 1 Page 1 of 6 Rev. 1
DEFEAT 1 RCIC LOW RPV PRESSURE ISOLATION AND 211" DEFEAT (CONTINUED)
Purpose:
To permit RCIC Steam Isolation valves to be opened, or to remain open, when RPV Pressure is 50 psig or less. To remove the 211" RCIC shutdown signal from the RCIC Turbine Steam Supply Valve. These actions are to support RPV Pressure and Level Control actions.
Location: 1C04, 1C30, 1C33 Equipment Required: (4) Keys #2235 Instructions:
NOTE Placing E51A-SA[B] in OVERRIDE/TEST, or HS-2437 or HS-2400A in OVERRIDE will activate annunciator RCIC STEAM LINE ISOLATION OVERRIDE (1C14B, B-5).
(1) At Panel 1C33, place MO-2400 AUTO OPEN SIGNAL OVERRIDE keylock switch HS-2400A in OVERRIDE position and confirm amber light is ON. __________
(2) At Panel 1C30, place MO-2401 AUTO OPEN SIGNAL AND RPV HI LEVEL OVERRIDE keylock switch HS-2437 in OVERRIDE position and confirm amber light is ON. __________
(3) At Panel 1C30, place LO STM PRESS ISOL OVERRIDE keylock switch E51A-SA in OVERRIDE/TEST position. __________
(4) At Panel 1C33, place RCIC LO STM PRESS ISOL OVERRIDE keylock switch E51A-SB in OVERRIDE/TEST position. __________
(5) If there is no RCIC initiation signal (1C05A, B-1) REACTOR LO-LO LEVEL TRIP present, operate RCIC per OI 150 as needed for pressure and level control. __________
DEFEAT 1 Page 2 of 6 Rev. 1
DEFEAT 1 RCIC LOW RPV PRESSURE ISOLATION AND 211" DEFEAT (CONTINUED)
NOTE MO-2404 TURBINE STEAM SUPPLY will be open due to the RCIC initiation signal.
(6) If a low Reactor Steam Pressure (RPV < 50 psig) condition exists, and there is a RCIC initiation signal (1C05A, B-1) REACTOR LO-LO LEVEL TRIP present, complete the following steps:
(a) Verify the following: __________
Valve Description Position MO-2400 RCIC INBD STEAM LINE ISOL CLOSED MO-2401 RCIC OUTBD STEAM LINE ISOL CLOSED MO-2405 TURBINE STOP VALVE CLOSED (b) At Panel 1C04, reset RCIC Auto Isolation by depressing HS-2458 RCIC OUTBD ISOL LOGIC MO-2401 SEALED-IN (A Logic) and HS-2459 RCIC INBD ISOL LOGIC MO-2400 SEALED-IN (B Logic) pushbuttons and verify RCIC Isolation amber lights are off. __________
CAUTION Caution should be used when warming up RCIC steam lines as both MO-2400 and MO-2401 are gate valves. Limit rate of pressure increase when warming RCIC Steam Supply Line to prevent thermal shock and water hammer.
(c) At Panel 1C04, slowly throttle open MO-2400 RCIC INBD STEAM LINE ISOL to the intermediate position. __________
(d) Crack open MO-2401 RCIC OUTBD STEAM LINE ISOL valve. __________
DEFEAT 1 Page 3 of 6 Rev. 1
DEFEAT 1 RCIC LOW RPV PRESSURE ISOLATION AND 211" DEFEAT (CONTINUED)
(e) When PI-2403 (RCIC PRESSURES) STEAM INLET PRESSURE is approximately equal to reactor pressure, fully open MO-2401 RCIC OUTBD STEAM LINE ISOL valve. __________
(f) Continue throttling open MO-2400 RCIC INBD STEAM LINE ISOL until fully open. __________
NOTE When MO-2405 TURBINE STOP VALVE is opened with MO-2404 TURBINE STEAM SUPPLY valve open, MO-2512 RCIC INJECT will auto open.
Turbine RPMs and RCIC pump flow will increase when MO-2405 TURBINE STOP VALVE is opened.
(g) Reset MO-2405 TURBINE STOP VALVE Motor Control as follows:
- 1. Place HS-2405 TURBINE STOP VALVE MOTOR CONTROL in CLOSE until the motor operator shows full closed. __________
- 2. Open MO-2405 with HS-2405 TURBINE STOP VALVE MOTOR CONTROL. __________
(h) Verify that annunciator (1C04C, A-5) RCIC MO-2405 TURBINE TRIP resets as MO-2405 TURBINE STOP VALVE leaves the full closed position. __________
(i) Verify MO-2512 RCIC INJECT valve opens. __________
(j) Confirm that RCIC Turbine RPMs and pump flow are increasing. __________
DEFEAT 1 Page 4 of 6 Rev. 1
DEFEAT 1 RCIC LOW RPV PRESSURE ISOLATION AND 211" DEFEAT (CONTINUED)
Restoration:
NOTE If a RCIC isolation signal is present when E51A-SA or E51A-SB is returned to NORMAL, RCIC will isolate.
(1) At Panel 1C33, place keylock switch E51A-SB in NORMAL position. __________
(2) At Panel 1C30, place keylock switch E51A-SA in NORMAL position. __________
NOTE If High Reactor Water Level signal (211") is present and HS-2437 is returned to NORMAL, RCIC will auto shutdown (MO-2404 closes).
(3) At Panel 1C30, place keylock switch HS-2437 in NORMAL position and confirm amber light is OFF. __________
(4) At Panel 1C33, place keylock switch HS-2400A in NORMAL position and confirm amber light is OFF. __________
(5) At Panel 1C14, verify annunciator RCIC STEAM LINE ISOLATION OVERRIDE (1C14B, B-5) is reset. __________
References:
(1) APED E51-009, Sheets 1-6 (2) E-121, Sheets 29, 30 (3) OI 150, Reactor Core Isolation Cooling System (4) DCP 1450/1 DEFEAT 1 Page 5 of 6 Rev. 1
DEFEAT 1 RCIC LOW RPV PRESSURE ISOLATION AND 211" DEFEAT (CONTINUED)
Usage Level Continuous Use Effective Date:
TECHNICAL REVIEW Prepared by: Date:
Technical Review by: Date:
Operations Staff Technical Review by: Date:
EOP Coordinator Reviewed by: Date:
Operations Committee PROCEDURE APPROVAL I am responsible for the technical content of this procedure.
Approved by Procedure Owner: Date:
Operations Approved by: Date:
Plant Manager, Nuclear DEFEAT 1 Page 6 of 6 Rev. 1
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV JPM NUMBER: 217000-12 REV. 3 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 95.11 TASK TITLE(S):
K/A NUMBERS: 217000 A2.02 3.8/3.7 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 JPM Number: 217000-12 JPM
Title:
DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- The reactor has scrammed in response to a LOCA.
- The only system available for injection is RCIC.
- RPV pressure is <50 psig.
- RCIC had started due to an automatic initiation signal and has isolated on low reactor pressure.
INITIATING CUES (IF APPLICABLE):
- The CRS directs you to defeat the RCIC low RPV pressure isolation signal by installing Defeat 1, then establish RCIC injection into the RPV to restore RPV level to 170 to 211.
Page 3 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 JPM PERFORMANCE INFORMATION Required Materials: 1. EOP-Defeat 1 General
References:
EOP Defeat 1, Rev. 1 Task Standards:
- HS 2400A, MO-2400 Auto Open Signal Override, in override.
- HS 2437, MO-2401 Auto Open Signal and RPV Hi Level Override in override.
- RCIC auto isolation logic A and B reset.
- MO-2401 is fully open.
- MO-2400 is fully open.
- MO-2405 reset and open.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Evaluator, the simulator driver will acknowledge annunciators for the installation of the EOP 1 defeats.
Performance Step: At panel 1C33, place MO-2400 AUTO OPEN SIGNAL OVERRIDE, keylock Critical Y (SEQ-) switch HS-2400A in OVERRIDE position and confirm amber light is on.
Standard: HS-2400A in override and amber light is on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 Performance Step: At 1C30, place MO-2401 AUTO OPEN SIGNAL AND RPV HI LEVEL Critical Y (SEQ-) OVERRIDE, keylock switch HS-2437 in OVERRIDE position and confirm amber light is on.
Standard: HS-2437 in override and amber light is on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C30, place the LO STM PRESS ISOL OVERRIDE keylock switch E51A-SA in Critical Y (SEQ-) the OVERRIDE/TEST position.
Standard: E51A-SA placed in the override/test position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C33, place the RCIC LO STM PRESS ISOL OVERRIDE keylock switch E51A-Critical Y (SEQ-) SB in the OVERRIDE/TEST position.
Standard: E51A-SB placed in the override/test position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 5 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 Performance Step: If there is no RCIC initiation signal present, (1C05A B-1 is NOT alarming), then Critical N (SEQ-) operate RCIC per OI 150 as needed for pressure and level control.
Standard: Verify that 1C05A B-1 is alarming.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE: IF the simulator set up is such that annunciator 1C05A B-1 is not alarming; CUE the candidate that annunciator 1C05A B-1 is currently alarming.
Performance Step: If a Reactor Steam Pressure (RPV < 50 psig), condition exists and there is a Critical N (SEQ-) RCIC initiation signal, (1C05A B-1), REACTOR LO-LO LEVEL TRIP, present, complete the following steps:
Verify the following:
- MO 2405 TURBINE STOP VALVE CLOSED Standard: MO 2400, 2401 and 2405 verified CLOSED.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE, the Candidate may verify closed by taking HS-2405 TURBINE STOP VALVE MOTOR CONTROL to the closed position until its indication is GREEN.
This will re-join the valve stem to the valve disc.
Page 6 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 Performance Step: At 1C04 reset RCIC Auto Isolation by depressing HS-2458 RCIC OUTBD ISOL Critical Y (SEQ-) LOGIC MO-2401 SEALED-IN (A logic) and HS-2459 RCIC INBD ISOL LOGIC MO-2400 SEALED-IN (B logic) pushbuttons and verify RCIC isolation amber lights are off.
Standard: RCIC auto isolation pushbuttons, HS-2458 and HS-2459 pushed and amber lights off.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C04, slowly throttle open MO-2400 RCIC INBD STEAM LINE ISOL to the Critical N (SEQ-) intermediate position.
Standard: MO-2400 throttled open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Crack open MO-2401 RCIC OUTBD STEAM LINE valve.
Critical N (SEQ-)
Standard: MO-2401 cracked open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 7 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 Performance Step: When PI-2403 (RCIC PRESSURES) STEAM INLET PRESSURE is Critical Y (SEQ-) approximately equal to reactor pressure, fully open MO-2401, RCIC OUTBD STEAM LINE ISOL valve.
Standard: RCIC pressure is equal to reactor pressure MO-2401 open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Continue throttling open MO-2400, RCIC INBD STEAM LINE ISOL until fully Critical Y (SEQ-) opened.
Standard: MO-2400 full open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Reset MO-2405 TURBINE STOP VALVE motor control as follows:
Critical Y (SEQ-)
- Place HS-2405 TURBINE STOP VALVE MOTOR CONTROL in close until the motor operator shows full closed.
- Open MO-2405 with HS-2405 TURBINE STOP VALVE MOTOR CONTROL.
Standard: MO-2405 driven closed to re-latch then re-opened.
Performance: SATISFACTORY UNSATISFACTORY Comments: HS-2405 may have been closed previously to verify MO-2405 closed.
Note that this step will cause MO-2512 to automatically open and initiate RCIC system flow into the reactor.
Page 8 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 Performance Step: Verify that annunciator 1C04C A-5 RCIC MO-2405 TURBINE TRIP resets as Critical N (SEQ-) MO-2405 TURBINE STOP VALVE leaves the full closed position.
Standard: Annunciator 1C04C A-5 RCIC MO-2405 TURBINE TRIP resets as the valve opens.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Verify that MO-2512 RCIC Inject valve opens Critical N (SEQ-)
Standard: MO-2512 is verified open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Confirm that RCIC Turbine RPMs and pump flow are increasing.
Critical N (SEQ-)
Standard: RCIC turbine RPMs increasing as indicated on SI-2457 and pump flow are increasing as indicated on FIC-2509.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the JPM is run with a low RPV pressure, the RCIC turbine RPMs will be low.
If the RCIC RPMs are below 2000, a P & L, in OI 150, states that we should trip the RCIC turbine.
IF the Candidate asks if he should allow RCIC to run at low RPMs; CUE him that we will continue to run RCIC until RPV level is back in the band of 170 to 211.
Page 9 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 Terminating Cues: When the candidate informs you that RCIC is injecting and there is a noticeable level rise, the JPM is complete.
Stop Time:
Page 10 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 SIMULATOR SET UP:
- Reset to any Non-shutdown IC EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None required SIMULATOR OVERRIDES:
None required SIMULATOR REMOTE FUNCTIONS:
None Page 11 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 INSTRUCTOR ACTIONS:
- 1. Place the simulator in run and perform the following:
o SCRAM the reactor.
o RPV level must be below 119.5", to do this, Secure Condensate and Feed injection.
While taking the actions of the next bullet, ensure that injection into the RPV is not allowed by HPCI, RHR, CS, or condensate and feed.
Take any actions required to cause a RCIC AUTO initiation and to establish RPV pressure at approximately 50 psig.
o Verify the following:
RCIC is isolated.
RCIC AUTO initiation signal is present.
RCIC high level trip is reset.
- 2. Place the simulator in run.
- 3. Read initial conditions and initiating cues to the operator.
Page 12 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 TURNOVER SHEET INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- The reactor has scrammed in response to a LOCA.
- The only system available for injection is RCIC.
- RPV pressure is <50 psig.
- RCIC had started due to an automatic initiation signal and has isolated on low reactor pressure.
INITIATING CUES (IF APPLICABLE):
- The CRS directs you to defeat the RCIC low RPV pressure isolation signal by installing Defeat 1, then establish RCIC injection into the RPV to restore RPV level to 170 to 211.
Page 13 of 14
QF-1030-11 Rev. 2 (FP-T-SAT-30) 217000-12, DEFEAT THE RCIC LOW RPV PRESSURE ISOLATION AND 211" INTERLOCK AND INJECT INTO THE RPV, Rev. 3 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 14 of 14
12.0 DRAINING TO RADWASTE ................................................................................................. 1 12.0 DRAINING TO RADWASTE NOTE The preferred method of draining the Reactor vessel is through the RWCU System because the water can be treated, thus reducing the potential radiological hazard, prior to discharge to the Radwaste System.
This section may be used in conjunction with EOP 2, Primary Containment Control (T/L) when RHR is in the Torus Cooling Mode.
Reducing the Torus water level below 8 feet will uncover Torus coating repairs. This will require inspections/repairs to be performed to assure the coating repairs have not degraded/cracked.
CAUTION Do not exceed 150°F water temperature received in Radwaste due to Radwaste tank temperature limits.
(1) Inform Health Physics that RHR system mode of operation will be changing and radiation levels in the affected corner rooms, torus area, and RHR valve room may be changing. ___________
(2) If performing Torus drain to Radwaste in conjunction with EOP 2, perform EOP Defeat 13 if necessary. ___________
(3) Verify A[B] RHR LOOP is operating in one of the following modes:
(a) Torus Cooling mode per Section 5.3 or 5.4. ___________
(b) Shutdown Cooling mode per Section 5.5. ___________
(c) LPCI Mode per Section 4.2 or 5.1. ___________
(4) Notify RW Operator to line up to receive water from the RHR System. ___________
(5) When RW is aligned, open MO-1937 INBD RHR DRAIN TO RW ISOL valve on 1C03. ___________
CAUTION If operating the RHR System in the Shutdown Cooling mode, a rapid loss of Reactor vessel water inventory may result when flow is initiated from the RHR loop to RW.
NOTE When MO-1936 is throttled open, the increase in RHR loop flow will be the drain rate to RW.
MO-1936 and MO-1937 will close on a Group 2 PCIS isolation signal. MO-1937 will close on a Group 4 PCIS isolation signal if HS-1937A SHUTDOWN COOLING 135#
INTERLOCK ENABLE is in the SHUTDOWN CLG position.
(6) Slowly throttle open MO-1936 OUTBD RHR DRAIN TO RW THRTL ISOL valve on 1C03 until recorder FR-1971 A & B RHR LOOP FLOW indicates an increase in RHR loop flow. ___________
(a) If operating in the Shutdown Cooling mode, monitor Reactor vessel water level on either of the following level indications: ___________
Indication Description Panel LI-4541 FLOOD UP RANGE 1C04 LI-4559/4560/4561 A/B/C GEMAC LEVEL 1C05 (b) If operating in the Torus Cooling mode, monitor Torus level on UR-4325 on 1C03 or LR-4384C and 4385B on 1C29. ___________
(7) When the desired level has been reached secure draining to RW as follows: __________
(a) Close the following valves on 1C03: ___________
Valve Description Position MO-1936 OUTBD RHR DRAIN TO RW THRTL ISOL NORM/CLOSED MO-1937 INBD RHR DRAIN TO RW ISOL CLOSE (b) Notify the RW Operator that draining of the RHR System is complete. ___________
DEFEAT 13 RHR DISCHARGE TO RADWASTE ISOLATION DEFEAT 20 22 29 34 401 13 26 23 25 24 21 37 02 07 1C06 10 1C05 11 36 18 1C04 27 15 EOP Override Switch Locations 28 16 17 DEFEAT 13 1C03 19 30 41 39 45 42 35 32 33 1 2 14 43 44 402 38 40 DEFEAT 13 Page 1 of 4 Rev. 1
DEFEAT 13 RHR DISCHARGE TO RADWASTE ISOLATION DEFEAT (CONTINUED)
Purpose:
To allow RHR Discharge to Radwaste Valves to remain open with the presence of a Group II Isolation signal. This defeat allows the Torus to be drained via the Radwaste System as directed by EOP-2.
Location: Panels 1C05, 1C14, 1C32, and 1C33 Equipment Required: (2) Keys # 2235 Instructions:
NOTE Taking HS-1936A [HS-1937B] to OVERRIDE position will activate annunciator GROUP 2 MO-1936 OR MO-1937 OVERRIDE (1C14A, C-5).
(1) At Panel 1C32, place GROUP 2 MO-1936 ISOLATION OVERRIDE keylock switch HS-1936A in OVERRIDE position and confirm amber light is ON. __________
(2) At Panel 1C33, place GROUP 2 MO-1937 ISOLATION OVERRIDE keylock switch HS-1937B in OVERRIDE position and confirm amber light is ON. __________
(3) At 1C05 reset PCIS Division 1 and 2 with reset pushbuttons. __________
Restoration:
(1) At Panel 1C33, place keylock switch HS-1937B in NORMAL and confirm amber light is OFF. __________
(2) At Panel 1C32, place keylock switch HS-1936A in NORMAL and confirm amber light is OFF. __________
(3) At Panel 1C14, verify annunciator GROUP 2 MO-1936 OR MO-1937 OVERRIDE (1C14A, C-5) is reset. __________
DEFEAT 13 Page 2 of 4 Rev. 1
DEFEAT 13 RHR DISCHARGE TO RADWASTE ISOLATION DEFEAT (CONTINUED)
References:
(1) Bechtel E-122, Sheets 7 & 15 (2) APED A71-003, Sheets 1, 7, 9, 12, 13 & 16 (3) P&ID M-119 (4) DCP-1450, DCRDR 1C04 Modification DEFEAT 13 Page 3 of 4 Rev. 1
DEFEAT 13 RHR DISCHARGE TO RADWASTE ISOLATION DEFEAT (CONTINUED)
Usage Level CONTINUOUS USE Effective Date:
TECHNICAL REVIEW Prepared by: Date:
Technical Review by: Date:
Operations Staff Technical Review by: Date:
EOP Coordinator Reviewed by: Date:
Operations Committee PROCEDURE APPROVAL I am responsible for the technical content of this procedure.
Approved by Procedure Owner: Date:
Operations Approved by: Date:
Plant Manager, Nuclear DEFEAT 13 Page 4 of 4 Rev. 1
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Drain Torus to Rad Waste. AP, must install Defeat 13 JPM NUMBER: 219000-04 REV. 0 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 95.60 TASK TITLE(S):
K/A NUMBERS: 219000 A2.16 2.9/3.2 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 30 Minutes Time Critical: NO Alternate Path / Faulted: YES TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 JPM Number: 219000-04 JPM
Title:
Drain Torus to Rad Waste. AP, must install Defeat 13 Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
If at anytime you need to N/A any steps that are not required due to the current plant conditions, I will act as the CRS to grant approval.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- A plant transient has occurred.
- EOP 2 has been entered due to a High Torus Level.
- RHR is currently operating in the Torus Cooling Mode per Section 5.4, Normal Torus Cooling.
INITIATING CUES (IF APPLICABLE):
- As the CRS, I direct you to lower Torus level IAW OI 149, Residual Heat Removal System, to 10.3 feet.
Page 3 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 JPM PERFORMANCE INFORMATION Required Materials: 1. OI 149 Residual Heat Removal System Rev. 90
- 2. EOP Defeat 13 Rev.1 General
References:
Task Standards: Per Defeat 13
- HS-1936A in override and amber light is on
- HS-1937B in override and amber light is on
- DIV 1 and 2 PCIS pushbuttons pushed.
Per OI 149
- MO-1937 opened
- MO-1936 throttled opened After torus level is lowered:
- MO-1936 closed
- MO-1937 closed Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Inform Health Physics that RHR system mode of operation will be changing and Critical N (SEQ-) radiation levels in the affected corner rooms, torus area, and RHR valve room may be changing.
Standard: HPs notified and informed via the plant page or telephone.
Performance: SATISFACTORY UNSATISFACTORY Comments: Role-play as HP that you will monitor the affected areas.
Page 4 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 Performance Step: If performing Torus Drain to Radwaste in conjunction with EOP 2, perform EOP Critical N (SEQ-) Defeat 13 as necessary.
Standard: Candidate determines that there is a Group 2 isolation signal present and Defeat 13 is required.
Performance: SATISFACTORY UNSATISFACTORY Comments:
At this point the candidate will transition from OI 149 to EOP Defeat 13 Performance Step: At 1C-32, place GROUP 2 MO-1936 ISOLATION OVERRIDE keylock switch HS-Critical Y (SEQ-) 1936A in OVERRIDE position and confirm amber light is ON.
Standard: HS-1936A in override and amber light is on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C-33, place GROUP 2 MO-1937 ISOLATION OVERRIDE keylock switch HS Critical Y (SEQ-) 1937B in OVERRIDE position and confirm amber light is ON.
Standard: HS-1937B in override and amber light is on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 5 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 Performance Step: At 1C-05, reset PCIS Division 1 and 2 with reset pushbuttons.
Critical Y (SEQ-)
Standard: Div 1 and 2 reset pushbuttons pushed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
At this point the candidate will transition from EOP Defeat 13 back to OI 149 Performance Step: Verify A[B] RHR LOOP is operating in one of the following modes:
Critical N (SEQ-)
- Torus Cooling mode per section 5.3 or 5.4.
- Shutdown Cooling mode per section 5.5.
- LPCI Mode per section 4.2 or 5.1.
Standard: Turnover item, RHR is in torus cooling per section 5.4.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Notify Rad Waste Operator to line up to receive water from the RHR System.
Critical N (SEQ-)
Standard: RW operator notified.
Performance: SATISFACTORY UNSATISFACTORY Comments: Role play as RW operator and inform the operator that you are lined up to receive water from RHR.
Page 6 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 Performance Step: When RW is aligned, Open MO-1937 INBD RHR DRAIN TO RW ISOL valve on Critical Y (SEQ-) 1C-03.
Standard: MO-1937 opened.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Slowly throttle Open MO-1936 INOUTBD RHR DRAIN TO RW THRTL ISOL valve Critical Y (SEQ-) on 1C-03 until recorder FR-1971 A & B RHR LOOP FLOW indicates an increase in RHR flow.
Standard: MO-1936 throttled open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: If operating in the Torus Cooling Mode, monitor Torus level on UR-4325 on 1C03 Critical N (SEQ-) or LR-4384C and LR-4384B on 1C-29.
Standard: Torus level monitored on UR-4325 on 1C-03 or LR-4384C and LR-4384B on 1C29.
Performance: SATISFACTORY UNSATISFACTORY Comments: IF desired to speed up the JPM and you are certain that he is using the above indicated level instruments, (certain means that he has pointed to them),
CUE the candidate that the Torus level is now 10.3 feet.
Page 7 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 Performance Step: When the desired level has been reached secure draining to RW as follows:
Critical Y (SEQ-)
Standard: MO-1936 Closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: When the desired level has been reached secure draining to RW as follows:
Critical Y (SEQ-)
Standard: MO-1937 closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Notify Rad Waste that draining of the RHR system to the torus is complete.
Critical N (SEQ-)
Standard: Rad Waste notified.
Performance: SATISFACTORY UNSATISFACTORY Comments: Role play as the RW operator that you understand that the draining of the Torus has been secured.
Terminating Cues: When the Rad Waste in notified that the draining is complete, the JPM is completed.
Stop Time:
Page 8 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 SIMULATOR SET UP:
Reset to any full power IC.
EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
NOTE: The below malfunctions are suggested as a minimum to create the needed conditions for the JPM, if other JPM setups require these to be altered that is acceptable as long as the intent of this JPM is not changed.
Time Malf. No. Malfunction Title ET Delay F. Sev. Ramp I. Sev.
T=0 MS21A Spurious group 2 isolation T=0 MS21B Spurious group 2 isolation SIMULATOR OVERRIDES:
As necessary SIMULATOR REMOTE FUNCTIONS:
NOTE: The below remote functions are suggested as a minimum to create the needed conditions for the JPM, if other JPM setups require these to be altered that is acceptable as long as the intent of this JPM is not changed.
Time Rem. No. Remote Title Position.
Set up CS01 V-21-1 A CS suction form CST VLV 100 Page 9 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 INSTRUCTOR ACTIONS:
- 1. Place the simulator in run and perform the following:
- Raise torus level by inserting Remote Function CS01 at 100.
- When torus level is just above 10.4', and Torus Hi/Lo Level annunciator 1C03B, D-9 is activated;
- Set Remote function CS01 to 0.
- To implement a group 2 isolation perform one of the following:
- Allow level to lower to below 170".
- Allow a D/W pressure to be greater than 2 PSIG.
- IMF MS21A and MS21B spurious group 2 isolations.
- Mark-up QRCs for placing torus cooling in operation, and leave out as a procedure in progress.
- 2. Read initial conditions and initiating cues to the operator.
Page 10 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 TURNOVER SHEET INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- A plant transient has occurred.
- EOP 2 has been entered due to a High Torus Level.
- RHR is currently operating in the Torus cooling Mode per section 5.4, Normal Torus Cooling.
INITIATING CUES (IF APPLICABLE):
- As the CRS, I direct you to lower Torus level IAW OI 149, Residual Heat Removal System, to 10.3 feet.
Page 11 of 12
QF-1030-11 Rev. 2 (FP-T-SAT-30) 219000-04, Drain the Torus to Rad Waste (AP, must install Defeat 13), Rev. 0 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 12 of 12
6.7 SECURING WELL WATER PUMPS TO ALLOW RESETTING/OVERRIDING GROUP 7 ISOLATION.............................................................................................................. 1 6.8 RESTARTING WELL WATER PUMPS AFTER RESETTING/OVERRIDING GROUP 7 ISOLATION.............................................................................................................. 2 6.7 SECURING WELL WATER PUMPS TO ALLOW RESETTING/OVERRIDING GROUP 7 ISOLATION (1) If a PCIS Group 7 isolation exists and a well water pump is running, perform the following steps, as applicable, to secure the operating well water pumps(s), otherwise N/A this step:
(a) Secure 1P-58A[B, C] as follows:
- 1. Reduce A[B, C] well water pump 1P-58A[B, C] flow to zero by either:
- a. In remote: Adjust Flow Controller FC 4414A[B, C] at panel 1C23 to zero percent. ___________
- b. In local: Close MO4414A[B, C] locally. ___________
2.Place the respective handswitches at panel 1C06 to the STOP position. _________
Switch Pump HS4417A A Well Water Pump 1P-58A HS4422A B Well Water Pump 1P-58B HS4483A C Well Water Pump 1P-58C
- 3. Observe the respective indicating lights at panel 1C06 and verify the affected well water pumps are secured. ___________
- 4. Adjust MO4414A[B, C] position as follows:
- a. In remote: Adjust Flow Controller FC4414A[B, C] at panel 1C23 to 10%[20%, 10%] ___________
- b. If operating in local, open MO4414A[B, C] to approximately 10%[20%,
10%] ___________
(b) Secure D Well Water Pump 1P-58D as follows:
- 1. Lower D well water pump 1P-58D flow to zero per one of the following:
- a. In Auto: Flow Controller FC4414D on panel 1C23 ___________
- b. In Hand: The manual speed adjustment dial at 1C373 ___________
- 2. Observe the respective indicating lights on panel 1C06 and verify that D well water pump 1P-58D is not running. ___________
Usage Level Continuous Use 6.8 RESTARTING WELL WATER PUMPS AFTER RESETTING/OVERRIDING GROUP 7 ISOLATION (1) If well water is not in operation, restore well water flow as follows:
NOTE It is preferable to start either well water pump 1P-58A or 1P-58C when restoring well water flow since they are lower head pumps and can be more easily controlled. Per CRS/OSM direction, any available well water pump may be started, as required.
(a) Start well water pump 1P-58A[B, C] as follows:
- 1. At 1C23 verify FC4414A[B, C] well water controller is set at 10%[20%, 10%] open ______
- a. If local control is desired, verify the local/remote handswitch for MO4414A[B, C] in LOCAL and verify that MO4414A[B, C] is approximately 10%[20%, 10%] open ___________
- 2. Start the A[B, C] well water pump 1P-58A[B, C] by performing the following as necessary:
- a. If starting the pump from 1C06, momentarily place the respective handswitch to the START position. ___________
Switch Pump
HS4417A A Well Water Pump 1P-58A HS4422A B Well Water Pump 1P-58B HS4483A C Well Water Pump 1P-58C
- b. At the respective well house, push the START button at the local pump control panel. ___________
- 3. Verify the red light is on for the respective well water pump on 1C06. ___________
- 4. Adjust flow as desired by adjusting FC4414A[B, C] at 1C23 or adjusting MO4414A[B, C] at the respective well house. ___________
(b) Start well water pump 1P-58D per one of the following methods:
- 1. If starting the pump from 1C23, perform the following:
- a. Adjust FC4414D well water controller to start D well water pump 1P-58D and achieve the desired pump speed, system flow and pressure. _____
- 2. If starting the pump in HAND (local), perform the following:
- a. Verify the speed dial is set at zero. ___________ .
- b. Verify the HAND/OFF/AUTO switch at panel 1C373 is in the HAND position. ___________
- c. Adjust the manual speed adjust knob to achieve the desired pump speed, system flow and pressure. ___________
- 3. Verify that the red running light is on at 1C06 for 1P-58D. ___________
DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT 20 22 29 34 2 1 401 13 26 23 25 24 21 37 02 07 1C06 10 1C05 11 36 18 1C04 27 15 EOP Override 28 16 Switch Locations 17 DEFEAT 4 1C03 19 30 41 39 45 42 35 32 33 14 43 44 402 38 40 DEFEAT 4 Page 1 of 6 Rev. 8
DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT
Purpose:
To restore Drywell Cooling and shift Drywell Cooling Fans to fast speed when plant conditions allow for their use.
Location: 1C25 Equipment Required: (2) Keys #2235 Instructions:
NOTE A PCIS Group 7 Isolation can be confirmed by the following indications:
- Annunciator REACTOR LO-LO-LO LEVEL TRIP (1C05A, A-1) is activated.
- At 1C31, the amber GROUP 7 SEALED-IN light is ON.
CAUTION If a PCIS Group 7 exists, the Drywell Cooling loops will automatically isolate. With Drywell Cooling isolated, the potential exits to void portions of the Drywell Cooling header. This could create the potential for a water hammer when the Well Water supply to Drywell Cooling is restored. To preclude a water hammer, Well Water must be secured prior to restoring Drywell Cooling.
(1) If a PCIS Group 7 Isolation exists AND any Well Water Pump is running, secure all ________
operating Well Water Pumps per OI 408, Section 6.7.
NOTE Taking HS-4321A[B] to OVERRIDE will activate annunciator DRYWELL COOLING ISOL VLV AND LOW SPEED FAN OVERRIDE (1C14B, C-4).
The following steps are performed at Control Room Panel 1C25.
(2) Place GROUP 7 CHANNEL A DW COOLING AND FAN SPEED OVERRIDE ________
keylock switch HS-4321A to OVERRIDE position and confirm amber light is ON.
(3) Place GROUP 7 CHANNEL B DW COOLING AND FAN SPEED OVERRIDE ________
keylock switch HS-4321B to OVERRIDE position and confirm amber light is ON.
DEFEAT 4 Page 2 of 6 Rev. 8
DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT (4) Verify the following:
(a) Any Drywell Cooling Fan that was operating in standby, starts in high ________
speed.
(b) If high Drywell pressure exists, verify that any running Drywell Cooling ________
Fan shifts from low speed (amber light) to high speed (red light).
(5) Verify MODE SELECT switches HS-5718A and B are in START position. ________
CAUTION If Well Water has been out of service, water could drain from Drywell Cooling loops.
Well Water must be restored in a slow, controlled manner to preclude the potential for a water hammer. A normal system startup meets this requirement.
(6) If Well Water was NOT in operation and a Well Water Pump can be restarted, start ________
a Well Water Pump and SLOWLY restore Well Water flow per OI 408, Section 6.8.
DEFEAT 4 Page 3 of 6 Rev. 8
DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT Restoration:
(1) If necessary, reset the PCIS Group 7 Isolation seal-in logic as follows: ________
(a) At 1C31, depress GROUP 7 ISOLATION RESET SWITCH HS-4841X to ________
reset the Group 7 logic.
(b) At 1C31, verify that the amber GROUP 7 SEALED-IN light is OFF. ________
(2) At 1C25, perform the following:
(a) Place keylock switch HS-4321A to NORMAL position and confirm amber ________
light is OFF.
(b) Place keylock switch HS-4321B to NORMAL position and confirm amber ________
light is OFF.
(c) Place Mode Select Switches HS-5718A to INOP and back to the START ________
position.
(d) Place Mode Select Switches HS-5718B to INOP and back to the START ________
position.
(3) At 1C14, verify annunciator DRYWELL COOLING ISOL VLV AND LOW SPEED ________
FAN OVERRIDE (1C14B, C-4) is reset.
DEFEAT 4 Page 4 of 6 Rev. 8
DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT
References:
(1) Bechtel E-113, Sheets 80, 86-90, 94 (2) P&IDs M-144 (Sheet 1), M-157 (3) M155-206, Sheets 3, 4, 5 (4) DCP-1450, DCRDR 1C04 Modification (5) NG-97-0666, Mitigating the Potential for Water Hammer In Drywell Cooling Piping (6) AR 96-1909.03 (7) AR 29294 (8) NG-02-0145, Response To Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions (9) NRC Safety Evaluation for DAEC Response To Generic Letter 96-06, dated March 29, 2002, Docket No. 50-331 (10) ECP 1569, Group 7 Isolation Seal-In Relay DEFEAT 4 Page 5 of 6 Rev. 8
DEFEAT 4 DRYWELL COOLER ISOLATION DEFEAT Usage Level CONTINUOUS USE Effective Date:
TECHNICAL REVIEW Prepared by: Date:
Technical Review by: Date:
Operations Reviewed by: Date:
Operations Committee PROCEDURE APPROVAL Approved by Procedure Owner: Date:
Operations Support Manager Approved by: Date:
DAEC Plant Manager DEFEAT 4 Page 6 of 6 Rev. 8
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Install EOP Defeat 4 to restore Drywell cooling. (Alternate Path requires Well Water to be secured prior to installing Defeat 4, then Well Water must be restarted).
JPM NUMBER: 400000-02 REV. 1 RELATED PRA None INFORMATION:
TASK NUMBER(S)/ 95.14 TASK TITLE(S):
K/A NUMBERS: 400000 A4.01 3.1/3.0 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: YES TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 JPM Number: 400000-02 JPM
Title:
Install EOP Defeat 4 to restore Drywell cooling. (Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted).
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
If at anytime you need to N/A any steps that are not required due to the current plant conditions, I will act as the CRS to grant approval.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- A plant Scram has occurred.
- RPV level lowered rapidly, but now is restored.
- EOP 1 and 2 have been entered.
- Drywell pressure is above 2 psig.
- Drywell temperatures are rising.
INITIATING CUES (IF APPLICABLE):
Page 3 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. EOP Defeat 4, Rev. 8
- 2. OI 408, Rev. 64 General
References:
Task Standards:
- FC 4414D is dialed to zero flow.
- HS-4321A taken to OVERRIDE position and amber light is ON.
- HS-4321B taken to OVERRIDE position and amber light is ON.
- HS 4417A for A Well Water Pump taken to start.
- A Well flow adjusted at 1C23 via FC 4414A.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: If a PCIS Group 7 Isolation exists AND any well water pump is running, secure Critical N (SEQ-) all operating well water pumps per OI 408, Section 6.7.
Standard: It is determined that a group 7 isolation exists, AND the running well water pumps must be secured.
Performance: SATISFACTORY UNSATISFACTORY Comments:
At this point the operator will leave EOP Defeat 4 and enter OI 408, Well Water System, and secure the running well water pumps.
Also NOTE that the only running well water pump is the D Well.
Page 4 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 Performance Step: If a PCIS group 7 isolation exists and a well water pump is running, perform the Critical N (SEQ-) following steps, as applicable, to secure the operating well water pumps, otherwise N/A this step.
Standard: The operator determines that the only well water pump that is running is the D Well.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note, the Candidate will N/A the steps for the A, B, and C Well Water pumps.
Performance Step: Secure the D Well Water Pump 1P-58D as follows:
Critical Y (SEQ-)
- Lower the D well water pump 1P-58D flow to zero.
- IN Auto: Flow controller FC-4414D on Panel 1C23.
Standard: FC 4414D is dialed down until the pump trips. This occurs when flow is below 400 gpm.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that the controller will not go to 0, it stops at 2 on the LED display. The key is to get the flow below 400 gpm. This will trip the pump.
Note, in the evolution, you will receive the D Well lo flow alarm.
Performance Step: Observe the respective indicating lights on panel 1C06 and verify that D well water Critical N (SEQ-) pump 1P-58D is not running.
Standard: Verified on 1C06 that the D Well is not running.
Performance: SATISFACTORY UNSATISFACTORY Comments:
At this point the operator will leave OI 408, Well Water System, and enter and re-enter EOP Defeat 4.
Page 5 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 Performance Step: Place GROUP 7 CHANNEL A DW COOLING AND FAN SPEED OVERRIDE Critical Y (SEQ-) keylock switch HS-4321A to OVERRIDE position and confirm amber light is ON.
Standard: HS-4321A taken to OVERRIDE position and amber light is ON.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Place GROUP 7 CHANNEL B DW COOLING AND FAN SPEED OVERRIDE Critical Y (SEQ-) keylock switch HS-4321B to OVERRIDE position and confirm amber light is ON.
Standard: HS-4321B taken to OVERRIDE position and amber light is ON.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Verify the following:
Critical N (SEQ-)
- If high drywell pressure exists, verify that any running drywell cooling fan shifts from low speed (amber light) to high speed (red light).
Standard: DW fans verified shifted to high speed.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that there are 14 fans to verify.
Page 6 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 Performance Step: Verify MODE SELECT switches HS-5718 A and B are in START position.
Critical N (SEQ-)
Standard: MODE SELECT switches HS-5718 A and B are verified in START position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: If well water was not in operation and a well water pump can be restarted, start a Critical N (SEQ-) well water pump and SLOWLY restore well water flow per OI 408, Section 6.8.
Standard: It is determined that Well Water can be restarted.
Performance: SATISFACTORY UNSATISFACTORY Comments: When the Candidate comes to this step, if he says that he would ask the CRS what he should do, Cue, reread the initiating cue and ask the Candidate what he recommends.
At this point the operator will leave EOP Defeat 4 and enter OI 408, Well Water System, and restart the well water system.
Page 7 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 Performance Step: If well water is not in operation restore well water as follows:
Critical N (SEQ-)
- Start the 1P-58A as follows:
o At 1C23 verify that FC 4414A well water controller is set a 10% open.
Standard: FC 4414A well water controller is set a 10% open.
Performance: SATISFACTORY UNSATISFACTORY Comments: Based on the note on page 34 of OI 408, if the operator asks if it is ok to start the A Well, or if he asks the CRS which Well he wants started:
Cue him to start the A well.
Performance Step: Start the A well water pump 1P-58A by performing the following as necessary:
Critical Y (SEQ-)
- Place the respective handswitch to START position.
o HS 4417A A Well Water Pump 1P-58A.
Standard: HS 4417A for A Well Water Pump taken to start.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C06, verify the red light is on for the respective well water pump.
Critical N (SEQ-)
Standard: Red light for the A well is verified ON.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 8 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 Performance Step: Adjust flow as desired by adjusting FC4414A at 1C23.
Critical Y (SEQ-)
Standard: A Well flow adjusted at 1C23 via FC4414A. Flow should be adjusted to between 350 and 750 gpm.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the operator wants to continue on to restart the D or C well, Cue him that another operator will re-start other wells as needed.
Note that the flow reference is in the Precautions and Limitations portion of the OI 920.
Terminating Cues: When the well water is restored to the drywell the JPM is complete.
Stop Time:
Page 9 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 SIMULATOR SET UP:
Reset to any full power IC.
EVENT TRIGGERS:
As necessary SIMULATOR MALFUNCTIONS:
NOTE: The below malfunctions are suggested as a minimum to create the needed conditions for the JPM, if other JPM setups require these to be altered that is acceptable as long as the intent of this JPM is not changed.
Time Malf. No. Malfunction Title ET Delay F. Sev. Ramp I. Sev.
T=0 RR30 Reactor bottom drain leak 10 As is T=0 MS32 Spurious group 7 isolation SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 10 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 INSTRUCTOR ACTIONS:
- 1. Place the simulator in run and perform the following:
- Insert malfunction RR30 to raise the drywell pressure to > 2 psig.
- Insert malfunction MS 32 to give a group 7 isolation.
- Secure All wells except D Well.
- 2. Read initial conditions and initiating cues to the operator.
Page 11 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- A plant Scram has occurred.
- RPV level lowered rapidly, but now is restored.
- EOP 1 and 2 have been entered.
- Drywell pressure is above 2 psig.
- Drywell temperatures are rising.
INITIATING CUES (IF APPLICABLE):
Page 12 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30) 400000-02, Install EOP Defeat 4 to restore Drywell cooling.
(Alternate Path requires Well Water to be secured prior to installing Defeat 4, and then Well Water must be restarted), Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 13 of 13
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01 JPM NUMBER: 2.1.7-06 REV. 1 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 1.07 (Reactor Operator)
TASK TITLE(S):
K/A NUMBERS: Generic 2.1.7 3.7 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 JPM Number: 2.1.7-06 JPM
Title:
Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
- It is 1200 noon.
- You are a control room RO.
- Another RO has just taken the 1200 sump pump readings, but has been called upon to assist in a pre-job brief for other plant work.
- You have just been handed the following Drywell sump readings:
o FQ-3707, Floor Drain Totalizer reading 124950 o FQ-3708, Equipment Drain Totalizer 332145
- The STP cover sheet has been signed by the CRS and for the purpose of this JPM you have also signed it.
INITIATING CUES (IF APPLICABLE):
- As the Control Room Supervisor, I direct you to complete the sump calculations for the Drywell Equipment and Floor Drain sump pumps per STP 3.0.0-01, Instrument Checks.
Page 3 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. STP 3.0.0-01, Attachment 1 & 2, Rev. 50
- 2. Calculator General
References:
STP 3.0.0-01, Rev. 50 Task Standards:
- Determine that D/W Floor Drain Sump Leakage calculates out to 1.9 gpm (plus or minus 0.1).
- Determine that D/W Equipment Drain Sump Leakage calculates out to 1.5 gpm (plus or minus 0.1).
- Determine that you are outside of the acceptance band for the STP.
o Page 8 of STP 3.0.0-01, is unacceptable if the unidentified leakage is Greater than 1.
o For this they must notify the CRS and inform them that we must comply with OI 920.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Evaluator Cue, At any time if the Candidate asks for the Drywell Sump Leakage Graph or the Calculation log sheet, hand him the attachments.
STP 3.0.0-01, Attachment 1 Unidentified Average Leak Rate Calculation.
Performance Step: For the 1200 readings the candidate will fill in the following numbers for the Critical N (SEQ-) unidentified leakage:
- FQ 3707, present reading ___124950___ Time of Reading ___1200__
Standard: 124950 filled in line a for FQ-3707.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 Performance Step: For the 1200 readings the candidate will fill in the following numbers:
Critical N (SEQ-)
- FQ 3707 previous reading __124500_____ Time of Reading ____0800.___
Standard: Verifies 124500 is filled in on line b for FQ-3707.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: For the 1200 readings the candidate will fill in the following numbers:
Critical N (SEQ-)
- For line c, the candidate will subtract the PREVIOUS sump reading from the PRESENT sump reading; 124950
-124500 450 Standard: After the subtraction, determine that 450 gallons were pumped from the Floor Drain Sump Pumps.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 5 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 Performance Step: For the 1200 readings the candidate will fill in the following numbers:
Critical N (SEQ-)
- Time interval (a-b) ______4_____ hours x 60 = ____240____ min.
Standard: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the time interval and 240 for the total minutes.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: For the 1200 readings the candidate will fill in the following numbers:
Critical Y (SEQ-)
- Unidentified average leak rate =
Total Gallons Pumped (c) [450]
Time Interval (minutes) (d)[240] = ___1.9___ gpm.
Standard: Determines that the unidentified leakage equals 1.9 gpm (plus or minus 0.1).
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: For the 1200 readings the candidate will fill in the following numbers.
Critical N (SEQ-)
- Confirm unidentified average leak rate (e) is 5 gpm (Note 1)
Standard: Operator will initial that the leakage is < 5 gpm.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 6 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 STP 3.0.0-01, Attachment 2 Identified Average Leak Rate Calculation.
Performance Step: For the 1200 readings the candidate will fill in the following numbers for the Critical N (SEQ-) identified leakage:
- FQ 3708 present reading ___332145___ Time of Reading ___1200__
Standard: 332145 filled in line a for FQ-3708.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: For the 1200 readings the candidate will fill in the following numbers:
Critical N (SEQ-)
- FQ 3708 previous reading __331785_____ Time of Reading ____0800___
Standard: Verifies 331785 is filled in on line b for FQ-3708.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 7 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 Performance Step: For the 1200 readings the candidate will fill in the following numbers:
Critical N (SEQ-)
- For line c, the candidate will subtract the PREVIOUS sump reading from the PRESENT sump reading; 332145
-331785 360 Standard: After the subtraction, determine that 360 gallons were pumped from the Equipment Drain Sump Pumps.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: For the 1200 readings the candidate will fill in the following numbers:
Critical N (SEQ-)
- Time interval (a-b) ______4_____ hours x 60 = ____240____ min.
Standard: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the time interval and 240 for the total minutes.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 8 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 Performance Step: For the 1200 readings the candidate will fill in the following numbers:
Critical Y (SEQ-)
- Unidentified average leak rate =,
Total Gallons Pumped (c) [360]
Time Interval (minutes) (d)[240] = ___1.5___ gpm.
Standard: Determines that the unidentified leakage equals 1.5 gpm (plus or minus 0.1).
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: For the 1200 readings the candidate will fill in the following numbers:
Critical N (SEQ-)
- Add identified (e) and unidentified (Att 1,e) + ________.
1.5 1.9
3.4 Standard
3.4 gpm total leakage for f.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: For the 1200 readings the candidate will fill in the following numbers Critical N (SEQ-)
- Confirm unidentified average leak rate (f) is 25 gpm.
Standard: Operator will initial that the leakage is < 25 gpm.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 9 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 Per STP 3.0.0-1, page 8 per the acceptance criteria Performance Step: The acceptance criteria for this sump reading states the following:
Critical Y (SEQ-)
- If 1.0 gpm, comply with OI 920, Section 2.0.
Standard: Determine that the Unidentified Leakage is greater than 1 gpm and we must comply with OI 920 Section 2.0.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE if the Candidate wants to pursue the actions of OI 920, inform him that the CRS will take care of the requirements of OI 920.
Terminating Cues: When the CRS has been notified that the Unidentified leakage is greater than 1 gpm which is out of compliance with the ACCEPTANCE CRITERIA, or the requirements of OI 920 are discussed with the CRS, the JPM is complete.
Stop Time:
Page 10 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 11 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 INSTRUCTOR ACTIONS:
Find a quiet place that has access to a calculator and OIs.
Give the candidate a marked up copy of the applicable portion of STP 3.0.0-01, INSTRUMENT CHECKS.
This will include the following:
- Copies of pages 1-10.
- Initial the NOTE and the PREREQUISITES blank on page 6.
- On page 8, o Circle MODE 1 in the Reactor MODE section.
o Initial the 000, and 0400 with a WT, for both the unidentified and identified leakage.
o Initial the 0800 with a Lg, for both the unidentified and identified leakage.
o Initial NOTE 1 with WT and Lg.
o N/A the Date and Time for 3.4.5-06 performed.
- On page 9, o Fill in the unidentified sump readings through the 0800 time frame. See attachment on page 16 of this JPM. Do Not fill in anything in the 1200 time slot. (In red on the attachment).
o Initial the note at the top of the page with WT and Lg.
o Initial NOTE 1 at the bottom of the page with WT and Lg.
- On page 10, o Fill in the unidentified sump readings through the 0800 time frame. See attachment on page 17 of this JPM. Do Not fill in anything in the 1200 time slot. (In red on the attachment).
o Initial the note at the top of the page with WT and Lg.
- On Page11, o Fill in the Start Time in column 2 as 0715.
o Fill in the Completion Time in column 2 as 0910.
o Initial with Lg.
o In the next Time blank in column 2 initial with JS.
This copy of the STP will be given to the candidate to perform the JPM.
Also at the time of the turnover, give the candidate a marked up copy of the Operators Sump Calculation sheet. Fill it in with the numbers as shown on page 18 of this JPM.
Page 12 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
- It is 1200 noon.
- You are a control room RO.
- Another RO has just taken the 1200 sump pump reading, but has been called upon to assist in a pre-job brief for other plant work.
- You have just been handed the following Drywell sump readings:
o FQ-3707, Floor Drain Totalizer reading 124950 o FQ-3708, Equipment Drain Totalizer 332145
- The STP cover sheet has been signed by the CRS and for the purpose of this JPM you have also signed it.
INITIATING CUES (IF APPLICABLE):
- As the Control Room Supervisor, I direct you to complete the sump calculations for the Drywell Equipment and Floor Drain sump pumps per STP 3.0.0-01, Instrument Checks.
Page 13 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 ATTACHMENT 1 UNIDENTIFIED AVERAGE LEAK RATE CALCULATION (Note: Not required in MODE 4 )
All readings are to be taken at Panel 1C19.
0000 a. FQ 3707 present reading _____124473___ Time of Reading ____0000___
- b. FQ 3707 previous reading ____124463____ Time of Reading ___ _2000___
- c. Total gallons pumped (a-b) ______10_____
- d. Time interval (a-b) ______4_____ hours x 60 = ___240_____ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = ____.04__ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) ________WT_____
Operators Initials 0400 a. FQ 3707 present reading _____124483____ Time of Reading _____0400__
- b. FQ 3707 previous reading ____124473____ Time of Reading ___ _0000___
- c. Total gallons pumped (a-b) ________10____
- d. Time interval (a-b) ) ______4_____ hours x 60 = ___240_____ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = ____.04__ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) ________WT_____
Operators Initials 0800 a. FQ 3707 present reading _____ 124500____ Time of Reading ____ _0800__
- b. FQ 3707 previous reading _____124483____ Time of Reading _____0400__
- c. Total gallons pumped (a-b) _______17____
- d. Time interval (a-b) _____4______ hours x 60 = ____240____ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = ___.07___ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) _________LG______
Operators Initials 1200 a. FQ 3707 present reading ______124950___ Time of Reading ____1200___
- b. FQ 3707 previous reading _____ 124500____ Time of Reading ___0800____
- c. Total gallons pumped (a-b) ______ 450___
- d. Time interval (a-b) ______4_____ hours x 60 = ____240____ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = ___1.9___ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) _______________
Operators Initials 1600 a. FQ 3707 present reading ________________ Time of Reading ___________
- b. FQ 3707 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) ______________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) _______________
Operators Initials 2000 a. FQ 3707 present reading ________________ Time of Reading ___________
- b. FQ 3707 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) ______________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) _______________
Operators Initials Note 1: May be > 5 gpm if STP 3.4.4-01 in progress to reclassify unidentified leakage.
Page 14 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 ATTACHMENT 2 IDENTIFIED AVERAGE LEAK RATE CALCULATION (Note: Not required in MODE 4 )
All readings are to be taken at Panel 1C19.
0000 a. FQ 3708 present reading ____331064_____ Time of Reading ____0000___
- b. FQ 3708 previous reading ___330705_______ Time of Reading __2000_____
- c. Total gallons pumped (a-b) _____359______
- d. Time interval (a-b) ______4_____ hours x 60 = ____240____ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = __1.50___ gpm
- f. Add identified (e) and unidentified (Att 1, e) =_____1.53___
- g. Confirm total average leak rate (f) is 25 gpm ________WT_____
Operators Initials 0400 a. FQ 3708 present reading _____331425______ Time of Reading ____0400___
- b. FQ 3708 previous reading ____331064_____ Time of Reading _____0000__
- c. Total gallons pumped (a-b) ______361____
- d. Time interval (a-b) ______4_____ hours x 60 = ____240____ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = ___1.50__ gpm
- f. Add identified (e) and unidentified (Att 1, e) =_____1.54__
- g. Confirm total average leak rate (f) is 25 gpm ________WT_____
Operators Initials 0800 a. FQ 3708 present reading ______331785____ Time of Reading _____0800__
- b. FQ 3708 previous reading _____331425_____ Time of Reading ____0400___
- c. Total gallons pumped (a-b) _____360______
- d. Time interval (a-b) ______4_____ hours x 60 = ____240____ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = __1.50___ gpm
- f. Add identified (e) and unidentified (Att 1, e) =______1.57__
- g. Confirm total average leak rate (f) is 25 gpm _________LG______
Operators Initials 1200 a. FQ 3708 present reading _______332145___ Time of Reading _____1200__
- b. FQ 3708 previous reading ______331785____ Time of Reading _____0800__
- c. Total gallons pumped (a-b) ________360__
- d. Time interval (a-b) ______4_____ hours x 60 = ____240____ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = __1.50___ gpm
- f. Add identified (e) and unidentified (Att 1, e) =_______3.4_____
- g. Confirm total average leak rate (f) is 25 gpm ____________________
Operators Initials 1600 a. FQ 3708 present reading ________________ Time of Reading ___________
- b. FQ 3708 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) ______________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Add identified (e) and unidentified (Att 1, e) =____________
- g. Confirm total average leak rate (f) is 25 gpm ____________________
Operators Initials 2000 a. FQ 3708 present reading ________________ Time of Reading ___________
- b. FQ 3708 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) ______________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Add identified (e) and unidentified (Att 1, e) =____________
- g. Confirm total average leak rate (f) is 25 gpm ____________________
Operators Initials _________
Page 15 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 This is the portion of the leakage document that can be transferred over to the entire leakage form for the JPM
+ TIME UNIDENTIFIED IDENTIFIED (FLOOR DRAIN) (EQUIPMENT)
FQ3707 GAL GPM FQ3708 GAL GPM 4-HR 24- 4-HR 24- 4-HR 24- 4-HR 24-HR HR HR HR PREVIOUS 0800 2000 2400 124412 10 328905 360 0400 124423 11 .04 329265 360 1.5 SUNDAY 0800 124433 10 60 .04 .04 329624 359 2160 1.5 1.5 1200 124443 10 .04 329984 360 1.5 1600 124452 9 .04 330345 361 1.5 2000 124463 11 61 .04 .04 330705 360 2156 1.5 1.5 2400 124473 10 .04 .04 331064 359 1.5 1.5 0400 124483 10 .04 331425 361 1.5 MONDAY 0800 124500 17 67 .07 .046 331785 360 2161 1.5 1.5 1200 124950 332145 1600 2000 2400 0400 Page 16 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-06, Perform REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 17 of 17
ABNORMAL OPERATING PROCEDURE AOP 672.2 OFFGAS RADIATION/REACTOR COOLANT HIGH ACTIVITY
- 5. If the MSIVs are closed and fuel failure is suspected, then obtain permission from the CRS and establish a leakage path to the main condenser as follows:
- a. At 1C04, isolate the main steam supply to Offgas and SJAEs by placing the ________
following handswitches in the CLOSE position:
Switch Description HS-1362A SJAE & OFFGAS MSL A STEAM SUPPLY MO-1362A HS-1362B SJAE & OFFGAS MSL B STEAM SUPPLY MO-1362B
- b. At 1C07, isolate the main steam supply to the Turbine Steam Seal System by ________
placing the following handswitches in the CLOSE position:
Switch Description HS-1169 MAIN STEAM SUPPLY MO-1169 HS-1170 REGULATOR BYPASS MO-1170
- c. At 1C07, verify that the main steam supply to MSR 2nd Stage Reheat is ________
isolated by verifying the following handswitch is in the CLOSE position:
Switch Description HS-1054 MAIN STEAM TO MSR SECOND STAGE MO-1054 & MO-1055
- d. At 1C07, verify that Mechanical Vacuum Pump 1P-32 is secured. ________
- e. At 1C04, establish the preferred MSIV leakage path by placing the following ________
handswitches in the OPEN position Switch Description HS-1043 MSL HEADER DRAINS BYPASS MO-1043 HS-1044 MSL DRAIN ORIFICE BYPASS MO-1044
- f. If the preferred MSIV leakage path cannot be established, establish the alternate ________
path by opening MSL HEADER DRAIN CV-1064 using HS-1064 on 1C04.
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity.
JPM NUMBER: 272000-03 REV. 1 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 94.21 TASK TITLE(S):
K/A NUMBERS: 272000 A2.11 3.4/3.7 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 JPM Number: 272000-03 JPM
Title:
Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, has been entered due to fuel failure.
- The MSIVs have isolated.
INITIATING CUES (IF APPLICABLE):
- The CRS directs you to establish a leakage path to the main condenser IAW AOP 672.2 Step 5.
Page 3 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. AOP 672.2, Rev. 29 General
References:
Task Standards:
- MO-1362A Closed
- MO-1362B Closed
- MO-1169 Closed
- MO 1054 and MO1055 are Closed
- Mechanical Vacuum Pump is secured
- MO-1043 Open
- MO-1044 Open Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: At 1C04, isolate the main steam supply to Offgas and SJAEs by placing the Critical Y (SEQ-) following handswitches in the CLOSE position.
Standard: MO 1362A is closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 Performance Step: At 1C04, isolate the main steam supply to Offgas and SJAEs by placing the Critical Y (SEQ-) following handswitches in the CLOSE position.
Standard: MO 1362 B is closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C07, isolate the main steam supply to the Turbine Steam Seal System by Critical Y (SEQ-) placing the following handswitches in the CLOSE position:
- MO-1169 MAIN STEAM SUPPLY MO-1169.
Standard: MO-1169 is closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C07, isolate the main steam supply to the Turbine Steam Seal System by Critical N (SEQ-) placing the following handswitches in the CLOSE position:
- MO-1170 REGULATOR BYPASS MO-1170.
Standard: MO- 1170 is verified closed.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note MO-1170 is a normally closed valve, unless the steam seal regulator is inoperable. MO-1170 will be verified closed or closed if open.
Page 5 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 Performance Step: At 1C07, verify that the main steam supply to MSR 2nd Stage Reheat is isolated Critical Y (SEQ-) by verifying the following handswitch is in the CLOSE position:
- HS-1054 MAIN STEAM TO MSR SECOND STAGE MO-1054 & MO-1055.
Standard: MO-1054 and 1055 are closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C07, verify that Mechanical Vacuum Pump 1P-32 is secured.
Critical Y (SEQ-)
Standard: 1P-32 is secured.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that per the AOP, the Candidate may just take the HS for the Mechanical Vacuum Pump to stop to secure it, or he may get OI 691 and secure the pump per section 5.0. After he secures the pump, there are steps for the inplant operator to perform, cue the Candidate that the inplant operator will finish the actions of OI 691, section 5.0.
Performance Step: At 1C04, establish the preferred MSIV leakage path by placing the following Critical Y (SEQ-) handswitches in the OPEN position:
Standard: MO-1043 is Opened.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 6 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 Performance Step: At 1C04, establish the preferred MSIV leakage path by placing the following Critical Y (SEQ-) handswitches in the OPEN position:
- MO-1044 MSL DRAIN ORIFICE BYPASS MO-1044.
Standard: MO-1044 is Opened.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: If the preferred MSIV leakage path cannot be established, establish the Critical N (SEQ-) alternate path by opening MSL HEADER DRAIN CV-1064 using HS-1064 on 1C04.
Standard: Leakage path can be established.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete when MO-1044 is full open.
Stop Time:
Page 7 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 SIMULATOR SET UP:
Reset to any full power IC.
EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
NOTE: The below malfunctions are suggested as a minimum to create the needed conditions for the JPM, if other JPM setups require these to be altered that is acceptable as long as the intent of this JPM is not changed.
Time Malf. No. Malfunction Title ET Delay F. Sev. Ramp I. Sev.
T=0 RX01 Fuel failure 10 As is SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 8 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 INSTRUCTOR ACTIONS:
- 1. Place the simulator in run and perform the following:
Note that the following are suggestions. The Setup may vary based on the set of JPMs to be performed.
For this JPM, the main thing is to have the MSIVs closed.
- Insert malfunctions.
- Insert a manual scram.
- Take the mode switch to shutdown.
- Place feedwater to 158 in auto.
o If necessary secure ECCS injection.
o Close the MSIVs.
o Start the Mechanical Vacuum Pump
- 2. Read initial conditions and initiating cues to the operator.
Page 9 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, have been entered due to fuel failure.
- The MSIVs have isolated.
INITIATING CUES (IF APPLICABLE):
- The CRS directs you to establish a leakage path to the main condenser IAW AOP 672.2 Step 5.
Page 10 of 11
QF-1030-11 Rev. 2 (FP-T-SAT-30) 272000-03, Establish a Leakage Path to the Main Condenser IAW AOP 672.2, Offgas Radiation/Reactor Coolant High Activity, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 11 of 11
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
1 of 10 1
Usage Level CONTINUOUS Effective Date: __________________
Verified By: Date:
Testing and Surveillance Validated By: Date:
Operations Verified By: Date:
System Engineering Approved By: Date:
Procedures Reviewed By: Date:
Operations Committee Approved By: Date:
DAEC Plant Manager
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
2 of 10 1
1.0 PURPOSE 1.1 The purpose of this procedure is to functionally test the RPS Manual Scram Channels.
1.2 This procedure, when performed in its entirety, FULLY SATISFIES the RPS Instrumentation Channel Functional Test requirements for the Manual Scram function.
1.3 This procedure, when performed in its entirety, FULLY SATISFIES the RPS Instrumentation Logic System Functional Test (LSFT) requirements for the Manual Scram function.
2.0 BRIEFING INFORMATION 2.1 PERFORMANCE INFORMATION 2.1.1 There are two (2) RPS Manual Scram channels (A3 and B3) to be functionally tested within this procedure. Testing of individual logic trains is organized as follows:
STP Sections Logic Channel 7.1 Channel A3 7.2 Channel B3 Testing of logic channels may be performed in any convenient order provided only one logic channel is tested at a time. While an instrument channel in one trip system is being tested, all other instrument trip channels shall be operable and un-tripped to preclude an unwarranted RPS SCRAM. All steps pertaining to a particular channel are to be performed in sequence and the steps carried through to completion, unless stated otherwise.
2.1.2 The following personnel are recommended to perform this STP:
1 Operations 2.1.3 The following test equipment is required for performance of this STP:
None 2.1.4 Due to possible age-related failure, the Scram Pilot solenoid valves will be checked for blow fuses prior to performing this surveillance (Prerequisite 6.4). These fuses will be replaced in RFO 19. This verification will no longer be necessary after fuse replacement. (OTH027214) 2.2 GENERAL CAUTIONS 2.2.1 This test will initiate several Half Scrams for the channel under test.
2.3 SPECIAL PRECAUTIONS 2.3.1 None
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
3 of 10 1
3.0 REFERENCES
3.1 Applicable drawings:
3.1.1 APED C71-004 <4,6,7,7A,8,9,11,14>
3.1.2 APED C51-027 <12,14,18,20,23,24,45,47>
3.1.3 NEDC-30851P-A, Technical Specification Improvement Analyses for BWR Reactor Protection System (AR 96-1409) 4.0 GENERAL INSTRUCTIONS 4.1 Steps marked with a "TS" immediately to the right of the step signoff line are required by Technical Specifications. If these steps do not meet their acceptance criteria or cannot be performed, a NRC reportable condition may exist and shall be reported to the Control Room Supervisor (CRS) immediately.
4.2 An Action Request (AR) shall be completed for any problems encountered with "TS" marked steps during the performance of this test/inspection.
4.3 The CRS shall be notified immediately and the appropriate Limiting Conditions for Operation section of Technical Specifications referred to whenever problems are encountered during the performance of this STP.
4.4 If any equipment or components are observed to be in a state of disrepair during the performance of this STP, appropriate corrective maintenance shall be initiated.
5.0 APPENDICES 5.1 None
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
4 of 10 1
Prerequisites Performance Date: ____________________ INITIALS 6.0 PREREQUISITES 6.1 Verify no testing or maintenance is being performed on any RPS channels. ________
(CRS) 6.2 At 1C05, verify the following:
6.2.1 SCRAM GROUP A 1 2 3 4 lights are on. ________
(OPS) 6.2.2 SCRAM GROUP B 1 2 3 4 lights are on. ________
(OPS) 6.3 At 1C05, verify the following annunciators reset:
6.3.1 "A" RPS AUTO SCRAM (1C05A, A-2) ________
(OPS) 6.3.2 "B" RPS AUTO SCRAM (1C05B, A-2) ________
(OPS) 6.3.3 "A" RPS BACK-UP SCRAM HALF SCRAM (1C05A, E-4) ________
(OPS) 6.3.4 "B" RPS BACK-UP SCRAM HALF SCRAM (1C05B, E-4) ________
(OPS) 6.4 At 1C131A through 1C131H, verify NO blown Scram Pilot solenoid valve ________
fuses. (OPS)
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
5 of 10 1
Channel - A3 Performance Date: ____________________ INITIALS 7.0 PROCEDURE 7.1 RPS CHANNEL A3 MANUAL SCRAM FUNCTIONAL TEST 7.1.1 At 1C15, visually confirm the following:
AND 4 RESET relay C71A-K19A is open.
AND 3 RESET relay C71A-K19C is open.
7.1.2 At 1C05, perform the following:
- a. Depress and release REACTOR MANUAL SCRAM A ________
pushbutton C71A-S3A.
- b. Confirm "A" RPS MANUAL SCRAM annunciator (1C05A, A-3) ________
is actuated.
- c. Confirm "A" RPS BACK-UP SCRAM HALF SCRAM ________
annunciator (1C05A, E-4) is actuated.
- d. Confirm white SCRAM GROUP A 1 2 3 4 lights are off. ________ TS
- e. Confirm red REACTOR MANUAL SCRAM A pushbutton ________
C71A-S3A indicating light is on.
7.1.3 Confirm the following computer points type out:
- a. B657 C71A-K15A1 REACTOR MANUAL SCRAM SCRAM ________
- b. D536 MANUAL SCRAM CHNL A TRIP ________
7.1.4 At 1C15, confirm white SCRAM GROUP A 1 2 3 4 lights are off. ________
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
6 of 10 1
Channel - A3 Performance Date: ____________________ INITIALS 7.1.5 At 1C05, perform the following:
- a. Reset Half Scram using REACTOR SCRAM RESET ________
handswitch C71A-S5.
- b. Confirm "A" RPS MANUAL SCRAM annunciator (1C05A, A-3) ________
is reset.
- c. Confirm "A" RPS BACK-UP SCRAM HALF SCRAM annunciator (1C05A, E-4) is reset. ________
- d. Confirm white SCRAM GROUP A 1 2 3 4 lights are on. ________
- e. Confirm red REACTOR MANUAL SCRAM A pushbutton ________
C71A-S3A indicating light is off.
7.1.6 Confirm the following computer points type out:
- a. B657 C71A-K15A1 REACTOR MANUAL SCRAM RSET ________
- b. D536 MANUAL SCRAM CHNL A RSET ________
7.1.7 At 1C15, confirm white SCRAM GROUP A 1 2 3 4 lights are on. ________
7.1.8 At 1C15, visually confirm the following:
AND 4 RESET relay C71A-K19A is open.
AND 3 RESET relay C71A-K19C is open.
Performed by: Date: Time:
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
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Channel - B3 Performance Date: ____________________ INITIALS 7.2 RPS CHANNEL B3 MANUAL SCRAM FUNCTIONAL TEST 7.2.1 At 1C17, visually confirm the following:
AND 4 RESET relay C71A-K19B is open.
AND 3 RESET relay C71A-K19D is open.
7.2.2 At 1C05, perform the following:
- a. Depress and release REACTOR MANUAL SCRAM B ________
pushbutton C71A-S3B.
- b. Confirm "B" RPS MANUAL SCRAM annunciator (1C05B, A-3) ________
is actuated.
- c. Confirm "B" RPS BACK-UP SCRAM HALF SCRAM ________
annunciator (1C05B, E-4) is actuated.
- d. Confirm white SCRAM GROUP B 1 2 3 4 lights are off. ________ TS
- e. Confirm red REACTOR MANUAL SCRAM B pushbutton ________
C71A-S3B indicating light is on.
7.2.3 Confirm the following computer points type out:
- a. B615 C71A-K15B1 REACTOR MANUAL SCRAM SCRAM ________
- b. D537 MANUAL SCRAM CHNL B TRIP ________
7.2.4 At 1C17, confirm white SCRAM GROUP B 1 2 3 4 lights are off. ________
7.2.5 At 1C05, perform the following:
- a. Reset Half Scram using REACTOR SCRAM RESET ________
handswitch C71A-S5.
- b. Confirm "B" RPS MANUAL SCRAM annunciator (1C05B, A-3) ________
is reset.
- c. Confirm "B" RPS BACK-UP SCRAM HALF SCRAM ________
annunciator (1C05B, E-4) is reset.
- d. Confirm white SCRAM GROUP B 1 2 3 4 lights are on. ________
- e. Confirm red REACTOR MANUAL SCRAM B pushbutton ________
C71A-S3B indicating light is off.
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
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Channel - B3 Performance Date: ____________________ INITIALS 7.2.6 Confirm the following computer points type out:
- a. B615 C71A-K15B1 REACTOR MANUAL SCRAM RSET ________
- b. D537 MANUAL SCRAM CHNL B RSET ________
7.2.7 At 1C17, confirm white SCRAM GROUP B 1 2 3 4 lights are on. ________
7.2.8 At 1C17, visually confirm the following:
AND 4 RESET relay C71A-K19B is open.
AND 3 RESET relay C71A-K19D is open.
Performed by: Date: Time:
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
9 of 10 1
Performance Date: ____________________ INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 If this STP is performed for any reason other than for satisfying the PURPOSE as stated in Section 1.0, indicate below (otherwise mark this step "N/A"):
8.2 If a DCF, Procedure Work Request (PWR), or Action Request (AR) was written due to problems encountered with the performance of this procedure, list the applicable number(s) below and attach a copy of each to this procedure. ("N/A" blocks as appropriate.)
DCF No. ________ PWR No. _________ AR No. _________
DCF No. ________ PWR No. _________ AR No. _________
8.3 All Technical-Specification-required items, as indicated by "TS", have been performed satisfactorily.
8.3.1 Section 7.1 ( ) YES ( ) NO CRS notified ________
8.3.2 Section 7.2 ( ) YES ( ) NO CRS notified ________
8.4 All other items checked in this test have been performed satisfactorily.
8.4.1 Section 7.1 ( ) YES ( ) NO CRS notified ________
8.4.2 Section 7.2 ( ) YES ( ) NO CRS notified ________
SURVEILLANCE TEST PROCEDURE STP 3.3.1.1-21 DAEC DUANE ARNOLD ENERGY CENTER TITLE: MANUAL SCRAM FUNCTIONAL TEST Page Rev.
10 of 10 1
Performance Date: ____________________ INITIALS 8.5 Indicate any relevant test comments below, otherwise mark this step "N/A":
Operations Date Surveillance Coordinator Date 9.0 ATTACHMENTS 9.1 None
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Perform Manual Scram Functional Test STP 3.3.1.1-21 JPM NUMBER: 212000-15 REV. 1 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 1.07 TASK TITLE(S):
K/A NUMBERS: 212000 A4.02 3.6/3.7 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 JPM Number: 212000-15 JPM
Title:
Perform Manual Scram Functional Test STP 3.3.1.1-21 Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- STP 3.3.1.1-21, Manual Scram Functional Test for the A side is due.
- Plant conditions are stable.
- The STP cover sheet has been signed in by the CRS and for the purpose of this JPM you have also signed it.
INITIATING CUES (IF APPLICABLE):
- As the CRS, I direct you to perform STP 3.3.1.1-21, Manual Scram Functional Test.
Page 3 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. STP 3.3.1.1-21, Rev 1.
General
References:
Task Standards:
- REACTOR MANUAL SCRAM A pushbutton C71A-S3A depressed and released.
- Half Scram Reset using REACTOR SCRAM RESET handswitch C71A-S5.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: From the STP Prerequisites:
Critical N (SEQ-) At 1C05, verify the following:
- SCRAM GROUP A 1 2 3 4 lights are on.
- SCRAM GROUP B 1 2 3 4 lights are on.
Standard: SCRAM GROUP A 1 2 3 4 lights are on.
SCRAM GROUP B 1 2 3 4 lights are on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 Performance Step: From the STP Prerequisites:
Critical N (SEQ-) At 1C05, verify the following annunciators reset:
- "A" RPS BACK-UP SCRAM HALF SCRAM (1C05A, E-4)
- "B" RPS BACK-UP SCRAM HALF SCRAM (1C05B, E-4)
Standard: All annunciators are reset.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: From the STP Prerequisites:
Critical N (SEQ-) At 1C131A through 1C131H, verify NO blown Scram Pilot solenoid valve fuses.
Standard: Verified that there are no blown fuses.
Performance: SATISFACTORY UNSATISFACTORY Comments: For this step, the candidate will have to call an inplant operator to verify that there are no blown fuses, when he sends the operator to verify, CUE him that there are no blown fuses in 1C131A through H.
Page 5 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 Performance Step: At 1C15, visually confirm the following:
Critical N (SEQ-)
Standard: Contact 5-6 for RPS TRIP SYSTEM A, SCRAM GROUP 1 AND 4 RESET relay C71A-K19A are open.
Performance: SATISFACTORY UNSATISFACTORY Comments: When the candidate goes to the back panel, the relay that he will be looking at will be a picture. See attachment for a picture of the relay and the numbering scheme.
The contacts are the third set from the right. NOTE that all of the contacts of this relay are normally open.
If the Candidate does not specifically identify contacts 5 and 6, CUE him to point out exactly which contacts are the 5 and 6 contacts.
EVALUATOR, when the Candidate first identifies the set of contacts on relay C71A-K19A, point out one of the real HFA relays on 1C15, ask the Candidate the following question:
Using this relay, how would you determine if contacts 5 and 6 are open or closed?
The Candidates answer will consist of the following:
The movable portion of the contact will be in contact with the stationary portion of the contact.
Page 6 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 Performance Step: At 1C15, visually confirm the following:
Critical N (SEQ-)
Standard: Contact 5-6 for RPS TRIP SYSTEM A, SCRAM GROUP 2 AND 3 RESET relay C71A-K19C is open.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE the candidate when he identifies a set of contacts; inform him that those contacts on C71A-K19C are open.
Performance Step: At 1C05, perform the following:
Critical Y (SEQ-)
- Depress and release REACTOR MANUAL SCRAM A pushbutton C71A-S3A.
Standard: REACTOR MANUAL SCRAM A pushbutton C71A-S3A depressed and released.
Performance: SATISFACTORY UNSATISFACTORY Comments: Candidate may use Testing/Maintenance Windows for annunciators 1C05A A-3 and E-4.
If the Candidate states that he is going to post Maintenance Windows, Cue him:
that you understand that this is how you would perform this evolution in the control room, but for the purpose of this JPM, we will simulate posting the borders.
Page 7 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 Performance Step: At 1C05, perform the following:
Critical N (SEQ-)
- Confirm "A" RPS MANUAL SCRAM annunciator (1C05A, A-3) is actuated.
- Confirm "A" RPS BACK-UP SCRAM HALF SCRAM annunciator (1C05A, E-4) is actuated.
Standard: Annunciators (1C05A, A-3) and (1C05A, E-4) are actuated.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C05, perform the following:
Critical N (SEQ-)
- Confirm white SCRAM GROUP A 1 2 3 4 lights are off.
Standard: White SCRAM GROUP A 1 2 3 4 lights are off.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C05, perform the following:
Critical N (SEQ-)
- Confirm red REACTOR MANUAL SCRAM A pushbutton C71A-S3A indicating light is on.
Standard: REACTOR MANUAL SCRAM A pushbutton C71A-S3A indicating light is on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 8 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 Performance Step: Confirm the following computer points type out:
Critical N (SEQ-)
- B657 C71A-K15A1 REACTOR MANUAL SCRAM SCRAM
- D536 MANUAL SCRAM CHNL A TRIP Standard: B657 C71A-K15A1 REACTOR MANUAL SCRAM SCRAM and D536 MANUAL SCRAM CHNL A TRIP confirmed printed out, or verify on Alarm Terminal, or by PVD on the PPC Terminal.
Performance: SATISFACTORY UNSATISFACTORY Comments: The BOP typer will not be working. When the candidate goes to verify that point B657 and D536 have typed out, ACP 101.1, Procedure Use and Adherence, Section 3.19 states the following:
Printed Out/Typed Out/Displayed - When used to direct verification of computer alarms and/or messages, these terms are interchangeable and may be verified by use of either an alarm typer or CRT.
The candidate may use any of the above to verify the computer points, however if it states that he should see B657 and D536 printed out, CUE him that he sees B657 C71A-K15A1 REACTOR MANUAL SCRAM SCRAM and D536 MANUAL SCRAM CHNL A TRIP printed out.
Performance Step: At 1C15, confirm white SCRAM GROUP A 1 2 3 4 lights are off.
Critical N (SEQ-)
Standard: SCRAM GROUP A 1 2 3 4 lights are off.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 9 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 Performance Step: At 1C05, perform the following:
Critical Y (SEQ-)
- Reset Half Scram using REACTOR SCRAM RESET handswitch C71A-S5.
Standard: Half Scram Reset using REACTOR SCRAM RESET handswitch C71A-S5.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C05, perform the following:
Critical N (SEQ-)
- Confirm "A" RPS MANUAL SCRAM annunciator (1C05A, A-3) is reset.
- Confirm "A" RPS BACK-UP SCRAM HALF SCRAM annunciator (1C05A, E-4) is reset.
Standard: Annunciators (1C05A, A-3) and (1C05A, E-4) are reset.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C05, perform the following:
Critical N (SEQ-)
- Confirm white SCRAM GROUP A 1 2 3 4 lights are on.
Standard: SCRAM GROUP A 1 2 3 4 lights are on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 10 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 Performance Step: At 1C05, perform the following:
Critical N (SEQ-)
- Confirm red REACTOR MANUAL SCRAM A pushbutton C71A-S3A indicating light is off.
Standard: REACTOR MANUAL SCRAM A pushbutton C71A-S3A indicating light is off.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Confirm the following computer points type out:
Critical N_(SEQ-)
- B657 C71A-K15A1 REACTOR MANUAL SCRAM RSET
- D536 MANUAL SCRAM CHNL A RSET Standard: B657 C71A-K15A1 REACTOR MANUAL SCRAM SCRAM and D536 MANUAL SCRAM CHNL A TRIP confirmed printed out, or verify on Alarm Terminal, or by PVD on the PPC Terminal.
Performance: SATISFACTORY UNSATISFACTORY Comments: The BOP typer will not be working. When the candidate goes to verify that point B657 and D536 have typed out, ACP 101.1, Procedure Use and Adherence, Section 3.19 states the following:
Printed Out/Typed Out/Displayed - When used to direct verification of computer alarms and/or messages, these terms are interchangeable and may be verified by use of either an alarm typer or CRT.
The candidate may use any of the above to verify the computer points, however if it states that he should see B657 and D536 printed out, CUE him that he sees B657 C71A-K15A1 REACTOR MANUAL SCRAM RESET and D536 MANUAL SCRAM CHNL A RESET printed out.
Page 11 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 Performance Step: At 1C15, confirm white SCRAM GROUP A 1 2 3 4 lights are on.
Critical N (SEQ-)
Standard: White SCRAM GROUP A 1 2 3 4 lights are on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1C15, visually confirm the following:
Critical N (SEQ-)
Standard: Contact 5-6 for RPS TRIP SYSTEM A, SCRAM GROUP 1 AND 4 RESET relay C71A-K19A, and Contact 5-6 for RPS TRIP SYSTEM A, SCRAM GROUP 2 AND 3 RESET relay C71A-K19C are open.
Performance: SATISFACTORY UNSATISFACTORY Comments: When the candidate goes to the back panel, the relay that he will be looking at will be a picture. See attachment for a picture of the relay and the numbering scheme.
The contacts are the third set from the right. NOTE that all of the contacts of this relay are normally open.
CUE the candidate when he identifies a set of contacts; inform him that those contacts on C71A-K19A are open.
Terminating Cues: The JPM is complete when contacts 5-6 on C71A-K19A and C71A-K19C are verified OPEN and the candidate completes Section 8 at the end of the STP.
Stop Time:
Page 12 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 SIMULATOR SET UP:
Reset to any full power IC.
EVENT TRIGGERS:
None.
SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 13 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 INSTRUCTOR ACTIONS:
- 1. Reset the simulator to any power IC.
- 2. Read initial conditions and initiating cues to the operator.
- 3. Place the simulator in run.
Page 14 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
- STP 3.3.1.1-21, Manual Scram Functional Test for the A side is due.
- Plant conditions are stable.
- The STP cover sheet has been signed in by the CRS and for the purpose of this JPM you have also signed it.
INITIATING CUES (IF APPLICABLE):
- As the CRS, I direct you to perform STP 3.3.1.1-21, Manual Scram Functional Test.
Page 15 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 F R O N T V IE W 11 7 5 1 13 9 3 14 10 4 00 12 00 8 6 2 Page 16 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 212000-15, Perform Manual Scram Functional Test STP 3.3.1.1-21, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 17 of 17
OPERATING INSTRUCTION OI 358 REACTOR PROTECTION SYSTEM 6.3 POWER TRANSFER OF ALTERNATE POWER SUPPLY SOURCE FROM 1Y1A TO 1Y2A
[1Y2A TO 1Y1A] ....................................................................................................................
6.3 POWER TRANSFER OF ALTERNATE POWER SUPPLY SOURCE FROM 1Y1A TO 1Y2A [1Y2A TO 1Y1A]
CAUTION Operation with both RPS ALT SUPPLY to 1Y36 circuit breakers 1Y16-10 at 1Y16 and 1Y26-10 at 1Y26 closed is prohibited in order to prevent the possibility of cross-connecting regulating transformers 1Y1A and 1Y2A through a malfunction in manual transfer switch 1Y36.
(1) If either RPS bus is being powered from the alternate power supply source and that bus's associated RPS MG set is available, transfer power to the MG set per Section 6.2. ___________
(2) Verify the Regulating Transformer 1Y2A [1Y1A] is available and in service per OI 317.1. ___________
(3) If an RPS half scram is anticipated because of the RPS bus power supply sources alignment, perform RPS Power Supply Transfer Half Scram Preparation Checklist (Appendix 3). (NA if RPS bus is already deenergized). ___________
CAUTION If either RPS bus is being powered from the alternate power supply source. The following step will cause a reactor half scram and a PCIS Groups 1 through 5 isolation (except MSIVs) signal.
(4) At Panel 1Y30A, open the RPS ALTERNATE FEED XFMR circuit breaker 1Y30A-00. ___________
(5) At the RPS Alternate Source Electrical Protection Assemblies, open the EPA-C2 circuit breaker. ___________
(6) At EPA-C1, open the circuit breaker. ___________
(7) At Panel 1Y26 [1Y16], verify the RPS ALT SUPPLY to 1Y36 circuit breaker 1Y26-10
[1Y16-10] is in the OFF position. ___________
(8) At Panel 1Y16 [1Y26], open the RPS ALT SUPPLY to 1Y36 circuit breaker 1Y16-10
[1Y26-10]. ___________
(9) At 1Y2A [1Y1A], verify circuit breaker 1Y2A02 [1Y1A02] is closed. (REGULATING TRANSFORMER 1Y2A [1Y1A] SUPPLY TO 1Y26 [1Y16]). ___________
(10) At Panel 1Y26 [1Y16], close the RPS ALT SUPPLY to 1Y36 circuit breaker 1Y26-10
[1Y16-10]. ___________
(11) At Panel 1Y36, select 1Y26 [1Y16]. ___________
(a) The manual transfer switch inside 1Y36 rotates counterclockwise only and will "snap" into the desired position.
(12) At EPA-C1, observe that the POWER IN light is ON and the following lights are OFF: ___________
OVER-VOLTAGE UNDER-VOLTAGE UNDER-FREQUENCY POWER OUT (a) If the OVER-VOLTAGE, UNDER-VOLTAGE, and/or UNDER-FREQUENCY trip status light(s) is/are ON, momentarily place the TRIP/RESET keylock switch EPA-C1-S2 in the RESET position and verify the light(s) turn(s) OFF; then place the switch back to the OPER position. ___________
(13) Close the EPA-C1 circuit breaker and observe that the POWER OUT light turns ON. ____
(14) At EPA-C2, observe the POWER IN light is ON and the following lights are OFF: ______
OVER-VOLTAGE UNDER-VOLTAGE UNDER-FREQUENCY POWER OUT (a) If the OVER-VOLTAGE, UNDER-VOLTAGE, and/or UNDER-FREQUENCY trip status light(s) is/are ON, momentarily place the TRIP/RESET keylock switch EPA-C2-S2 in the RESET position and verify the light(s) turn(s) OFF; then place the switch back to the OPER position. ___________
(15) Close the EPA-C2 circuit breaker and observe the POWER OUT light turns ON. _______
(16) At Panel 1Y30A, close the RPS ALTERNATE FEED XFMR circuit breaker 1Y30A-00. ___________
(17) At Panels 1C15 and/or 1C17, verify the white ALT XFMR indicating light(s) above the RPS ALTERNATE POWER TRANSFER switch(es) C71B-S1A (1C15) and/or C71B-S1B (1C17) is/are ON. ___________
NOTE If an RPS bus power supply source was selected to the alternate supply, the white ALT XFMR indicating light above the RPS ALTERNATE POWER TRANSFER switch on the opposite control panel will be OFF. (This is because the two RPS ALTERNATE POWER TRANSFER switches are interlocked so only one RPS bus at a time may be powered from the alternate power supply source.
(18) If an RPS bus was selected to be powered from the alternate power supply source, verify the RPS bus loads were reenergized. ___________
(19) If a half scram occurred as a result of the transfer, complete RPS Power Supply Transfer Half Scram Recovery Checklist (Appendix 4). ___________
OPERATING INSTRUCTION OI 317.1 120 VAC INSTRUMENT CONTROL POWER SYSTEM 5.5 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A [1Y2A]Error! Bookmark not defined.
5.5 SHUTDOWN OF REGULATING TRANSFORMER 1Y1A [1Y2A]
(1) At Panel 1Y36, verify the RPS alternate power supply source is not selected to 1Y16 [1Y26]. ___________
(a) If necessary, transfer the RPS alternate power supply source to 1Y2A [1Y1A]
per OI 358. ___________
(2) If necessary, start up and transfer load to Inverter 1D15 [1D25] per Section 3.5, or transfer loads to an operating inverter per Section 4.2. ___________
(3) At 1D15 [1D25], momentarily depress the LAMP TEST/ALARM RESET pushbutton. ____
(4) At 1D15[1D25] put on electrical safety gear, then open right cabinet door and place inverter ALARM BYPASS SWITCH to BYPASS. ___________
(5) Confirm the FORWARD TRANSFER light is ON. ___________
(6) At 1Y15 [1Y25], confirm switch 1Y1504 [1Y2504] in the INVERTER position.
(1Y15 [1Y25] MAINTENANCE SWITCH) ___________
CAUTION Opening or closing of breaker 1Y1503 [1Y2503] could result in a Reactor Recirc MG Set Scoop Tube lockup due to a problem in the scoop tube positioner circuitry.
(7) Turn circuit breaker 1Y1503 [1Y2503] OFF. (REGULATING TRANSFORMER 1Y1A
[1Y2A] SUPPLY TO JS1501 [JS2501]) ___________
(8) At 1Y1A [1Y2A], turn circuit breaker 1Y1A02 [1Y2A02] OFF.
(REGULATING TRANSFORMER 1Y1A [1Y2A] SUPPLY TO 1Y16 [1Y26]) ___________
(9) Turn circuit breaker 1Y1A01 [1Y2A01] OFF.
(REGULATING TRANSFORMER 1Y1A [1Y2A] INPUT) ___________
(10) At 1B32 [1B42], turn circuit breaker 1B3216A [1B4203A] OFF.
(REGULATING TRANSFORMER 1Y1A [1Y2A] AC SUPPLY) ___________
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Shutdown of Regulating Transformer 1Y1A for maintenance. (AP requiring transfer from 1Y16 to 1Y26)
JPM NUMBER: 262002-04 REV. 0 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 28.10 (NSPEO)
TASK TITLE(S):
K/A NUMBERS: 262002 A4.01 2.8/3.1 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: X Perform:
EVALUATION LOCATION: In-Plant: X Control Room:
Simulator: Other:
Lab:
Time for Completion: 35 Minutes Time Critical: NO Alternate Path / Faulted: Yes TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 JPM Number: 262002-04 JPM
Title:
Shutdown of Regulating Transformer 1Y1A for maintenance. (AP requiring transfer from 1Y16 to 1Y26)
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the plant conditions, assume that the conditions that I read you are the correct plant conditions.
- 1Y1A Regulating Transformer requires maintenance.
- 1D15 Instrument AC Inverter is in operation.
INITIATING CUES (IF APPLICABLE):
- The CRS directs you, IAW OI 317.1, 120 VAC Instrument Control Power System, Section 5.5, to remove 1Y1A, Regulating Transformer, from service in preparation for maintenance.
Page 3 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 JPM PERFORMANCE INFORMATION Required Materials: 1. OI 317.1, Rev. 37
- 2. OI 358, Rev. 46 General
References:
Task Standards:
- Taking 1Y30A breaker 1Y30A-00 to the open position.
- Opening EPA-C2 circuit breaker.
- Opening EPA-C1 circuit breaker.
- At Panel 1Y36, select 1Y26
- Close the EPA-C1
- Close the EPA-C2
- At 1Y15, turn circuit breaker 1Y1503 OFF
- At 1Y1A, turn circuit breaker 1Y1A02 OFF
- At 1Y1A, turn circuit breaker 1Y1A01 OFF
- At 1B32, turn circuit breaker 1B3216A OFF Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Page 4 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At Panel 1Y36, verify the RPS alternate power supply source is not selected to Critical N (SEQ-) 1Y16.
Standard: Verifies that the alternate RPS power supply is selected to 1Y16.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE, if at 1Y36, the alternate power supply is selected to 1Y26, CUE the candidate that the alternate RPS power supply is selected to 1Y16.
NOTE that it is acceptable to open panel 1Y36.
Performance Step: If necessary, transfer the RPS alternate power supply source to 1Y2A per Critical N (SEQ-) OI 358.
Standard: Candidate determines that he must transfer the RPS alternate power supply source to 1Y2A per OI 358.
Performance: SATISFACTORY UNSATISFACTORY Comments:
At this point, the candidate will move to OI 358, RPS and transfer the RPS power supply to 1Y2.
Performance Step: If either RPS bus is being powered from the alternate power supply source and Critical N (SEQ-) that bus's associated RPS MG set is available, transfer power to the MG set per Section 6.2.
Standard: RPS is verified in its normal power line-up.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note: the candidate may simulate calling the control room to verify that the RPS M-G Sets are supplying power to the RPS busses. If he does, CUE him that A and B RPS systems are being power by their respective M-G sets.
NOTE section 6.3 is entered momentarily directing you to section 6.2.
Page 5 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: Verify the Regulating Transformer 1Y2A is available and in service per OI Critical N (SEQ-) 317.1.
Standard: 1Y2A verified available.
Performance: SATISFACTORY UNSATISFACTORY Comments: Candidate will verify that 1Y2A is not tagged out, (the turnover stated that Instrument AC equipment is operable), and he may call the Work Control Center, or Control Room and verify that there is nothing being done to 1Y2A. If he does call either of the above, CUE him that 1Y2A is operable and operating.
Performance Step: If an RPS half scram is anticipated because of the RPS bus power supply Critical N (SEQ-) sources alignment, perform RPS Power Supply Transfer Half Scram Preparation Checklist (Appendix 3). (NA if RPS bus is already deenergized).
Standard: This step will be N/Aed.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE that the evolution we are performing will not de-energize RPS as the alternate is not supplying the RPS system. If the candidate asks the CRS if he can N/A this step, CUE him that the step can be N/Aed.
Page 6 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At Panel 1Y30A, open the RPS ALTERNATE FEED XFMR circuit breaker Critical Y (SEQ-) 1Y30A-00.
Standard: Simulate taking 1Y30A breaker 1Y30A-00 to the open position.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that 1Y30 is a sensitive panel, when the operator goes to 1Y30, show him the attached picture and have him identify 1Y30A-00 and explain how he would open the breaker.
CUE the candidate that 1Y30A-00 is open.
Performance Step: At the RPS Alternate Source Electrical Protection Assemblies, open the Critical Y (SEQ-) EPA-C2 circuit breaker.
Standard: Simulate opening EPA-C2 circuit breaker.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE candidate that EPA-C2 is open.
Performance Step: At EPA-C1, open the circuit breaker.
Critical Y (SEQ-)
Standard: Simulate opening EPA-C1 circuit breaker.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE candidate that EPA-C1 is open.
Page 7 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At Panel 1Y26 [1Y16], verify the RPS ALT SUPPLY to 1Y36 circuit breaker Critical N (SEQ-) 1Y26-10 [1Y16-10] is in the OFF position Standard: Circuit breaker 1Y26-10 is verified in the OFF position Performance: SATISFACTORY UNSATISFACTORY Comments: CUE candidate that 1Y26-10 is OFF.
Note, breaker may be simulated to be repositioned if necessary.
Performance Step: At Panel 1Y16, open the RPS ALT SUPPLY to 1Y36 circuit breaker 1Y16-10.
Critical Y(SEQ-)
Standard: At 1Y36, simulate opening circuit breaker 1Y16-10.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE candidate that circuit breaker 1Y16-10 is open.
NOTE that this breaker should be in the off position.
Performance Step: At 1Y2A, verify circuit breaker 1Y2A02 is closed. (REGULATING Critical N (SEQ-) TRANSFORMER 1Y2A SUPPLY TO 1Y26)
Standard: At 1Y2A, circuit breaker 1Y2A02 is verified closed.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE candidate that circuit breaker 1Y2A02 is closed.
Page 8 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At Panel 1Y26, close the RPS ALT SUPPLY to 1Y36 circuit breaker 1Y26-10.
Critical Y (SEQ-)
Standard: Simulate taking 1Y26-10 to the closed position.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE candidate that circuit breaker 1Y26-10 is closed after the action is simulated.
Performance Step: At Panel 1Y36, select 1Y26.
Critical Y (SEQ-) The manual transfer switch inside 1Y36 rotates counterclockwise only and will "snap" into the desired position.
Standard: Simulate rotating the transfer switch counterclockwise to the 1Y26 position.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE candidate that panel 1Y36 is selected to 1Y26 after the action is simulated.
Page 9 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At EPA-C1, observe that the POWER IN light is ON and the following lights are Critical N (SEQ-) OFF
- OVER-VOLTAGE
- UNDER-VOLTAGE
- UNDER-FREQUENCY
- POWER OUT Standard: OVER-VOLTAGE, UNDER-VOLTAGE, UNDER-FREQUENCY, and POWER OUT lights are verified off.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE the candidate that the POWER IN light is ON, and the OVER-VOLTAGE, UNDER-VOLTAGE, UNDER-FREQUENCY, and POWER OUT lights are off.
The next step is a reset of the EPA if necessary, it is not necessary and these steps will be N/Aed.
Performance Step: Close the EPA-C1 circuit breaker and observe that the POWER OUT light turns Critical Y (SEQ-) ON.
Standard: (Critical) Simulate closing circuit breaker EPA-C1.
(Non-critical) Verifies the POWER OUT light turns ON.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE candidate that circuit breaker EPA-C1 is closed and the POWER OUT light is ON.
Page 10 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At EPA-C2, observe that the POWER IN light is ON and the following lights are Critical N (SEQ-) OFF
- OVER-VOLTAGE
- UNDER-VOLTAGE
- UNDER-FREQUENCY
- POWER OUT Standard: OVER-VOLTAGE, UNDER-VOLTAGE, UNDER-FREQUENCY, and POWER OUT lights are verified off.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE the candidate that the POWER IN light is ON, and the OVER-VOLTAGE, UNDER-VOLTAGE, UNDER-FREQUENCY, and POWER OUT lights are off.
The next step is a reset of the EPA if necessary, it is not necessary and these steps will be N/Aed.
Performance Step: Close the EPA-C2 circuit breaker and observe the POWER OUT light turns ON Critical Y (SEQ-)
Standard: (Critical) Simulate closing circuit breaker EPA-C2.
Non critical) Verifies the POWER OUT light turns ON.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE candidate that circuit breaker EPA-C2 is closed and the POWER OUT light is ON after the action is simulated.
Page 11 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At Panel 1Y30A, close the RPS ALTERNATE FEED XFMR circuit breaker Critical Y (SEQ-) 1Y30A-00.
Standard: Simulate closing circuit breaker1Y30A-00 Performance: SATISFACTORY UNSATISFACTORY Comments: Note that 1Y30 is a sensitive panel, when the operator goes to 1Y30, show him the attached picture and have him identify 1Y30A-00 and explain how he would close the breaker.
CUE candidate that circuit breaker1Y30A-00 is Closed Performance Step: At Panels 1C15 and/or 1C17, verify the white ALT XFMR indicating light(s)
Critical N (SEQ-) above the RPS ALTERNATE POWER TRANSFER switch(es) C71B-S1A (1C15) and/or C71B-S1B (1C17) is/are ON.
Standard: Control Room called and the lights above the RPS ALTERNATE POWER TRANSFER switches C71B-S1A (1C15) and/or C71B-S1B (1C17) are ON.
Performance: SATISFACTORY UNSATISFACTORY Comments: When the candidate calls the Control Room, CUE him that the lights above the RPS ALTERNATE POWER TRANSFER switches C71B-S1A (1C15) and C71B-S1B (1C17) are ON.
Performance Step: If an RPS bus was selected to be powered from the alternate power supply Critical N (SEQ-) source, verify the RPS bus loads were reenergized.
Standard: This step is not applicable.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the candidate calls the Control Room and asks if RPS is to be powered by the alternate power supply, CUE him that RPS is not expected to be powered by the alternate power supply.
Page 12 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: If a half scram occurred as a result of the transfer, complete RPS Power Supply Critical N (SEQ-) Transfer Half Scram Recovery Checklist (Appendix 4).
Standard: This step is not applicable as a half scram has not occurred.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the Control Room is called, CUE the candidate that no half scrams have occurred.
This completes the portion of the JPM to swap alternate RPS power supplies. Now the candidate will transition back to OI 317.1.
Performance Step: If necessary, start up and transfer load to Inverter 1D15 per Critical N (SEQ-) Section 3.5, or transfer loads to an operating inverter per Section 4.2.
Standard: This step is a turnover item. 1D15 is in service.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: At 1D15 [1D25], momentarily depress the LAMP TEST/ALARM RESET Critical N (SEQ-) pushbutton.
Standard: LAMP TEST/ALARM RESET pushbutton being pushed is simulated.
Performance: SATISFACTORY UNSATISFACTORY Comments: If asked what he sees when he pushes the button, CUE him that all of the lights are lit. When he simulates releasing the button, inform the Candidate that the panel is the way he sees it now.
Page 13 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At 1D15 put on electrical safety gear, then open right cabinet door and place Critical N (SEQ-) inverter ALARM BYPASS SWITCH to BYPASS.
Standard: Simulate putting on safety gear and placing the ALARM BYPASS SWITCH to BYPASS.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE The safety gear is located in a locker in the battery room hallway. The Aux man has a key on his ring that gets him into the locker.
To achieve this task, a face shield and gloves are adequate, he may chose to wear more.
Once the gear is pointed out and it is determined what he is going to wear, no further actions are necessary as we are not going to actually open the cabinet.
NOTE the ALARM BYPASS SWITCH is located inside 1D15. For the purposes of this JPM, we do not want to open this panel. The candidate should simulate opening the right cabinet door and state that the bypass switch is on the right side of the cabinet and that he will simulate taking the switch to BYPASS.
CUE him that the ALARM BYPASS SWITCH to BYPASS.
Performance Step: Confirm the FORWARD TRANSFER light is ON.
Critical N (SEQ-)
Standard: FORWARD TRANSFER light is confirmed ON.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE him that the FORWARD TRANSFER light is ON.
Page 14 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At 1Y15, confirm switch 1Y1504 in the INVERTER position.
Critical N (SEQ-) (1Y15 MAINTENANCE SWITCH)
Standard: Switch 1Y1504 confirmed in the INVERTER position.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE him that Switch 1Y1504 confirmed in the INVERTER position.
NOTE, there is a Caution on this page that states that a scoop tube lock-up is possible when closing 1Y1503, the Candidate may call the control room and inform them of the possibility of a scoop tube lock up.
CUE him that you understand that a scoop tube lock up may occur, and that he may continue.
Performance Step: Turn circuit breaker 1Y1503 OFF. (REGULATING TRANSFORMER 1Y1A Critical Y (SEQ-) SUPPLY TO JS1501)
Standard: Simulate turning off circuit breaker 1Y1503, REGULATING TRANSFORMER 1Y1A SUPPLY TO JS1501 by simulating pushing the breaker switch down.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE him that circuit breaker 1Y1503 is in the off position after the action is simulated.
Performance Step: At 1Y1A, turn circuit breaker 1Y1A02 OFF.
Critical Y (SEQ-) (REGULATING TRANSFORMER 1Y1A SUPPLY TO 1Y16)
Standard: Simulate turning off circuit breaker 1Y1A02, REGULATING TRANSFORMER 1Y1A SUPPLY TO 1Y16 by simulating pushing the breaker switch down.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE him that circuit breaker 1Y1A02, REGULATING TRANSFORMER 1Y1A SUPPLY TO 1Y16 is off after the action is simulated.
Page 15 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: Turn circuit breaker 1Y1A01 OFF.
Critical Y (SEQ-) (REGULATING TRANSFORMER 1Y1A INPUT)
Standard: Simulate turning off circuit breaker 1Y1A01, REGULATING TRANSFORMER 1Y1A INPUT by simulating pushing the breaker switch down.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE him that circuit breaker 1Y1A01, REGULATING TRANSFORMER 1Y1A INPUT is off after the action is simulated.
Page 16 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Performance Step: At 1B32, turn circuit breaker 1B3216A OFF.
Critical Y (SEQ-) (REGULATING TRANSFORMER 1Y1A AC SUPPLY)
Standard: Simulate turning off circuit breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY by simulating pushing the breaker switch down.
Performance: SATISFACTORY UNSATISFACTORY Comments: CUE him that breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY, is off after the action is simulated.
NOTE, the operator may state that he will open the cabinet to verify breaker is in the open position. Cue him when he sees the breaker it is in the OPEN position Terminating Cues: When breaker 1B3216A, REGULATING TRANSFORMER 1Y1A AC SUPPLY, is simulated to be off, the JPM is complete.
Stop Time:
Page 17 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None INSTRUCTOR ACTIONS:
- 1. None Page 18 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 TURNOVER SHEET INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the plant conditions, assume that the conditions that I read you are the correct plant conditions.
- 1Y1A Regulating Transformer requires maintenance.
- 1D15 Instrument AC Inverter is in operation.
INITIATING CUES (IF APPLICABLE):
- The CRS directs you, IAW OI 317.1, 120 VAC Instrument Control Power System, Section 5.5, to remove 1Y1A, Regulating Transformer, from service in preparation for maintenance.
Page 19 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 Page 20 of 21
QF-1030-11 Rev. 2 (FP-T-SAT-30) 262002-04, Shutdown of Regulating Transformer 1Y1A for maintenance.
(AP requiring transfer from 1Y16 to 1Y26), Rev. 0 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 21 of 21
ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 1 of 7 Usage Level Information Use Effective Date:
TECHNICAL REVIEW Prepared by: Date:
Validated by: Date:
Operations Staff PROCEDURE APPROVAL I am responsible for the technical content of this procedure.
Verified and Approved by Procedure Owner: Date:
DAEC Plant Manager Concurred by: Date:
Chairman, Operations Committee Reviewed by: Date:
Manager, Regulatory Affairs Approved by: Date:
Site Vice President
ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 2 of 7 1.0 PURPOSE (1) This procedure provides policy guidelines for overtime limits and requirements for personnel working at the Duane Arnold Energy Center (DAEC). These guidelines are provided to prevent situations where fatigue could reduce the mental alertness or decision-making capability of plant personnel.
(2) This procedure applies to salaried, hourly, and union personnel in the Nuclear Division working at the DAEC. (Reference 7) {C002}
(3) This procedure applies to all contractor and vendor personnel working at DAEC.
(4) This procedure does not apply to Security personnel.
2.0 DEFINITIONS The following definition supplements those contained in the Quality Assurance Manual, Appendix B, Glossary of Terms.
(1) Key Maintenance Personnel - Those personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of safety-related structures, systems or components. This includes personnel performing or immediately supervising the performance of such activities.
(2) Shift Turnover - The time frame when an individual assumes the responsibilities from the onshift person. This time will vary depending upon the responsibilities being transferred.
The goal of shift turnover should be to communicate effectively to the oncoming workers to allow them to perform their jobs safely and effectively.
(3) Work Period - The pre-scheduled shift or time slot a worker is assigned to work.
Callouts, downpowers, and/or other emergent work activities may require a worker to return to work or arrive earlier than their pre-scheduled work period. In such cases, authorization for less than the 8-hour break between work periods is not required as long as the remaining overtime limits are met or deviation to those limits is authorized.
However, after the emergent work or unscheduled overtime period is complete, the 8-hour break shall be granted or appropriate authorization obtained.
ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 3 of 7 3.0 INSTRUCTIONS 3.1 RESPONSIBILITIES (1) The Plant Manager and other managers are responsible for authorizing any deviations from the overtime requirements.
(2) The Control Room Supervisor (CRS) is responsible for ensuring shift manning requirements are met.
(3) All supervisors are responsible for assuring that personnel under their supervision do not exceed the overtime requirements of this procedure without prior authorization. If overtime requirements are exceeded due to circumstances beyond the control of the supervisor (e.g., relief overslept or is ill), authorization to exceed the overtime requirement may be granted at the time of the deviation.
(4) The DAEC Administrative Secretary is responsible for maintaining the authorized overtime deviation forms and file for personnel under the Plant Manager. Other departments (e.g.,
Regulatory Affairs, Engineering, Nuclear Oversight, etc.) will maintain their authorized overtime deviation forms.
(5) All project leads are required to discuss this procedure with all contract personnel.
(6) All personnel are responsible for:
- Monitoring their work hours and notifying their supervisor prior to exceeding any overtime limits.
- Informing their supervisor if they believe that fatigue has or will make them unfit for duty.
3.2 REQUIREMENTS (1) When overtime is required, it shall be authorized and controlled in accordance with this procedure.
ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 4 of 7 NOTE Hours worked do not include work breaks such as shift turnover.
(2) An individual shall not be permitted to work more than the following:
- 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight
- 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period
- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period
- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day (168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) period (3) A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, including shift turnover time, shall be allowed between work periods.
(4) The use of overtime shall be considered on an individual basis. During refueling outages, management may provide blanket overtime authorization within the requirements of this procedure.
(5) Deviations from the above requirements shall be documented in writing and authorized by personnel noted in step 3.1(1) using Attachment 1.
(6) The following requirements apply to Operations Department personnel:
(a) If a Reactor Operator (RO) or a Senior Reactor Operator (SRO) has been working more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during periods of extended shutdown (e.g., at duties away from the control board), such individuals shall not be assigned shift duty in the Control Room without at least a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> break preceding such an assignment.
(b) If a Reactor Operator is required to work in excess of 8 continuous hours, he shall be periodically relieved of primary duties at the control board, such that periods of duty at the board do not exceed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at a time.
(c) The Operations Department staffing policy should be developed in a manner that permits licensed Reactor Operators to be periodically assigned to other duties away from the control board during their normal tours of duty.
3.3 GENERAL INSTRUCTIONS (1) Staffing and work assignments should be such that adequate coverage will be maintained without routine or heavy use of overtime.
(2) Overtime shall be considered on an individual basis except for extended outages.
ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 5 of 7 (3) Department supervisors should balance scheduled work activities with resource availability as necessary to maintain a normal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week. When required, overtime work should be scheduled such that the requirements of this procedure are not exceeded without prior authorization.
(4) Due to the inability to pre-schedule all overtime, it is the responsibility of the respective department supervisors to ensure that personnel who are asked to work emergent overtime meet the overtime requirements of this procedure.
3.4 DEVIATIONS (1) When necessary, supervisors may request authorization to deviate from the established overtime limits. The reason for the deviation shall be documented by the person authorizing the overtime on an Overtime Deviation Form (Attachment 1) and submitted to the Plant Manager or authorized alternate for approval. Other managers are considered to be authorized alternates.
(2) Deviations from the working hour guidelines that are solely-related to the transition to/from daylight savings time and standard time are authorized in advance under this procedure based on the limited duration (one hour) and infrequent application. No additional documentation of this deviation beyond that wholly contained in this procedural step is required.
(3) When authorizing deviations, consideration shall be given for the following:
- Reduction in the effectiveness of personnel.
- Utilizing personnel on overtime away from control panel and/or safety-related duties.
(4) A copy of the approved Overtime Deviation Form shall be transmitted to the DAEC Administrative Secretary or appropriate department secretary for record keeping.
(5) This procedure requires an Operations Committee review and DAEC Plant Manager approval per DAEC Technical Specifications. {C001} (References 1 and 8) 4.0 RECORDS (1) Approved Overtime Deviation Forms shall be maintained as non-permanent Quality Assurance records for six (6) months as a minimum.
ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 6 of 7
5.0 REFERENCES
(1) DAEC Technical Specifications, Administrative Controls-Procedures section (2) NUREG-0737, Task Action Plan I.A.1.3, Shift Planning (3) Nuclear Regulatory Commission (NRC) Circular No. 80-02, Nuclear Power Plant Staff Work Hours (4) NRC Generic Letter 82-02, NRC Policy on Factors Causing Fatigue of Operating Personnel at Nuclear Reactors (5) NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours (6) NRC Generic Letter 83-14, Definition of Key Maintenance Personnel (7) {C002} NRC Inspection Report 93-015 (8) {C001} QDR 94-038 (9) AR 98-1930.01 (10) AR 14817 (11) AR 24662
ADMINISTRATIVE CONTROL PROCEDURE ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS Rev. 12 Page 7 of 7 ATTACHMENT 1 OVERTIME DEVIATION FORM OVERTIME DEVIATION FORM INDIVIDUAL:
DEPARTMENT: SAMPLE LENGTH OF DEVIATION: FROM TO Date/Time Date/Time OVERTIME LIMITATION TO BE EXCEEDED:
Work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight Work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24-hour period Work more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48-hour period Work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7-day period (168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />)
Break of less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> between work periods.
JUSTIFICATION FOR EXCEEDING THE LIMITATION:
WORK TO BE PERFORMED:
RECOMMENDED BY: DATE: _______________
Department Supervisor APPROVED BY: DATE: _______________
Plant Manager/Alternate AUTHORIZED APPROVAL ALTERNATES:
Managers of Training, Engineering, Regulatory Affairs, Operations, Maintenance, Radiation Protection, Nuclear Oversight, and Operations Shift Manager.
cc: DAEC Administrative Secretary NG-148K Rev. 10
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Evaluate License Maintenance and Over Time Requirements JPM NUMBER: 2.1.2-01 REV. 0 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 96.05 (Reactor Operator)
TASK TITLE(S):
K/A NUMBERS: Generic 2.1.2 3.0 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.2-01, Evaluate License Maintenance and Over Time Requirements, Rev. 1 JPM Number: 2.1.2-01 JPM
Title:
Evaluate License Maintenance and Over Time Requirements Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.2-01, Evaluate License Maintenance and Over Time Requirements, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
For the purposes of this JPM:
- Todays date is Mar. 31, 2005 and the time is currently 2000.
- The plant is currently operating at 100% capacity.
- You are a Licensed Reactor Operator who has been on loan to the Training Center since January 1, 2005.
- Your new assignment, starting on April 1, 2005, will be at the Work Control Center.
- You have just finished standing a partial watch, (1100 to 1900 on Mar. 31, 2005), for Jim Brown, (ANSOE).
He was called out of the Control Room to Attend a Fact Finding Meeting.
INITIATING CUES (IF APPLICABLE):
You have just received a call from the Control Room Shift Manager that some personal problems have come up for one of the on shift RO licenses. The SM requests you to come back into work tomorrow morning, Tuesday, April 01, 2005, and complete the NSOE watch starting at 0200 and ending at 0700.
What is your response to this request?
Justify your answer.
Page 3 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.2-01, Evaluate License Maintenance and Over Time Requirements, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. ACP 101.4 Rev. 12
- 2. ODI-009 Rev. 19 General
References:
Task Standards:
- Determine that he cannot take the watch based on not getting a 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> break between shifts.
- Per ACP 101.4 in order to stand the watch as a Licensed operator an overtime deviation must be granted.
- Determine that he is not able to assume the watch based on not standing 5 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
For the overtime considerations the candidate will get his information from ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS.
NOTE to the Evaluator; The Candidate may begin the JPM assessing his watchstanding qualifications first. If he does, go to that section of the JPM first.
Performance Step: The Candidate will review his hours worked, then review ACP 101.4 Critical N (SEQ-) OVERTIME LIMITS AND REQUIREMENTS for exceeding any of the following:
- No more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight.
- No more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period.
- No more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period.
- No more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day (168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) period.
Standard: Reviewed and none violated.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.2-01, Evaluate License Maintenance and Over Time Requirements, Rev. 1 Performance Step: Review ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS step 3 of Critical Y (SEQ-) section 3.2 and determine the following:
- A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, including shift turnover time, shall be allowed between work periods.
Standard: Determines that he has not met the 8-hour break requirement of the ACP is not met.
Therefore for per ACP 101.4 HE CANNOT assume the watch in a licensed position.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the Candidate stops here, Cue him that he is the only person available to stand the watch. What if anything can be done to allow him to take the watch.
Performance Step: Review ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS step 5 of Critical Y (SEQ-) section 3.2 and determine the following:
- Determine what is needed to take the watch.
Standard: Per ACP 101.4 in order to stand the watch as a Licensed operator an overtime deviation must be granted.
Performance: SATISFACTORY UNSATISFACTORY Comments: Cue the Candidate that the CRS will work on the Deviation.
If the Candidate does not go further with his assessment of his ability to stand the watch, Cue him to continue by asking the following question; Are there any additional requirements needed before you stand the watch?
For determining whether he is active for standing an ANSOE watch the candidate will use ODI-009, NUCLEAR STATION PLANT EQUIPMENT OPERATOR, REACTOR OPERATOR, SENIOR REACTOR OPERATOR, AND SHIFT TECHNICAL ADVISOR QUALIFICATION REQUIREMENTS, to determine if he is qualified to stand the watch.
Page 5 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.2-01, Evaluate License Maintenance and Over Time Requirements, Rev. 1 Performance Step: Review ODI-009 for requirements of maintaining an active license, and determine Critical Y (SEQ-) the following:
- For ROs to be considered active, they shall stand operating crew watch stations requiring respective qualification for a minimum of five 12-hour shifts per calendar quarter, and no more than four months shall transpire between standing watches.
Standard: ODI-009 requires five 12-hour shifts, based on the above conditions; he has not met the requirements of ODI-009 and cannot assume the watch as ANSOE.
Performance: SATISFACTORY UNSATISFACTORY Comments: When reviewing ODI 009 for determining if his license is active, he will ask for his quarterly watch standing log.
Cue: when asked provide the Candidate with a copy of his watch standing log.
Attachment 7 of ODI-009.
Terminating Cues: When the candidate has determined whether he can stand the watch based on both the overtime and ACTIVE requirements, the JPM is complete.
Stop Time:
Page 6 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.2-01, Evaluate License Maintenance and Over Time Requirements, Rev. 1 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 7 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.2-01, Evaluate License Maintenance and Over Time Requirements, Rev. 1 INSTRUCTOR ACTIONS:
If the JPM is performed somewhere other than the simulator, ensure that there is a copy of:
- Ensure that copies of the current week and last week schedules are copied and available for the candidate.
- ACP 101.4 OVERTIME LIMITS AND REQUIREMENTS.
- ODI-009, NUCLEAR STATION PLANT EQUIPMENT OPERATOR, REACTOR OPERATOR, SENIOR REACTOR OPERATOR, AND SHIFT TECHNICAL ADVISOR QUALIFICATION REQUIREMENTS.
- During the first quarter of 2005 the candidate stood the following watches assigned to the Control Room as the ANSOE. Transfer these numbers to ODI Attachment 7 o January 2 0700 to 1900 o January 17 0700 to 1500 o January 27 1900 to 0700 o January 28 1900 to 0700 o March 17 0700 to 1900 Page 8 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.2-01, Evaluate License Maintenance and Over Time Requirements, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
For the purposes of this JPM:
- Todays date is Mar. 31, 2005 and the time is currently 2000.
- The plant is currently operating at 100% capacity.
- You are a Licensed Reactor Operator who has been on loan to the Training Center since January 1, 2005.
- Your new assignment, starting on April 1, 2005, will be at the Work Control Center.
- You have just finished standing a partial watch, (1100 to 1900 on Mar. 31, 2005), for Jim Brown, (ANSOE).
He was called out of the Control Room to Attend a Fact Finding Meeting.
INITIATING CUES (IF APPLICABLE):
You have just received a call from the Control Room Shift Manager that some personal problems have come up for one of the on shift RO licenses. The SM requests you to come back into work tomorrow morning, Tuesday, April 01, 2005, and complete the NSOE watch starting at 0200 and ending at 0700.
What is your response to this request?
Justify your answer.
Page 9 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.2-01, Evaluate License Maintenance and Over Time Requirements, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 10 of 10
ABNORMAL OPERATING PROCEDURE AOP 149 LOSS OF DECAY HEAT REMOVAL 3.2 Feed and Bleed to the Torus via Safety/Relief Valves
- a. Verify the reactor head is on and tensioned, head vents closed and at least one SRV with N2 supply is available. _______
- b. Evacuate all personnel from the Drywell and Torus areas except personnel assigned to monitor for leakage and/or increased airborne radioactivity levels. _______
- c. To prevent flow down the main steam lines, verify at least one valve in each steam line is closed: _______
Main Steam Line A CV-4412 or CV-4413 Main Steam Line B CV-4415 or CV-4416 Main Steam Line C CV-4418 or CV-4419 Main Steam Line D CV-4420 or CV-4421 HPCI Steam Line MO-2238 or MO-2239 RCIC Steam Line MO-2400 or MO-2401 Steam Line Drains MO-4423 or MO-4424
- d. Place handswitch for one SRV in the open position. _______
- f. Commence and raise injection into the RPV with either a Condensate, Core Spray or RHR pump until the SRV is open and RPV pressure is 50 psig above Torus pressure, but as low as practical. _______
Usage Level - Reference Use CORE SPRAY RAPID START IMMEDIATE ACTIONS (1) Start 1P-99A[B], ESW Pumps A[B]. __________
(2) Start 1P-211A[B], Core Spray Pump A[B]. __________
(3) Open MO-2117[2137], Core Spray Inboard Injection Valve, when reactor pressure is <450 psig. __________
(4) Verify MO-2104[2124], Core Spray Min Flow Bypass Valve, closes when system flow is >600 gpm. __________
FOLLOW-UP ACTIONS (1) Throttle MO-2117[2137], Core Spray Inboard Injection Valve, to maintain system flow <3100 gpm. __________
(2) Verify RHR/CS Pump Room Cooling Units operating. __________
(3) Verify operating Core Spray Pump motors <95 amps. __________
OI 151 QRC 1 Page 1 of 1 Rev. 1
OI 151 QRC 1 CORE SPRAY RAPID START Usage Level Reference Use Effective Date:
TECHNICAL REVIEW Verified by: Date:
Procedures Staff Validated by: Date:
Operations Staff Reviewed by: Date:
Operations Committee PROCEDURE APPROVAL I am responsible for the technical content of this procedure.
Approved by Procedure Owner: Date:
Operations Approved by: Date:
DAEC Plant Manager OI 151 QRC 1 Rev 1
QF-1030-11 Rev. 2 (FP-T-SAT-30)15 JOB PERFORMANCE MEASURE (JPM)
SITE: DAEC JPM TITLE: Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling.
JPM NUMBER: 209001-04 REV. 1 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 4.03 TASK TITLE(S):
K/A NUMBERS: 209001 A4.05 3.8/3.6 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 JPM Number: 209001-04 JPM
Title:
Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
The plant has undergone a transient and the following has occurred:
- The plant was shutdown 5 days ago for a refueling outage.
- Shutdown cooling was lost due to a malfunction of MO 1908, INBD SHUTDOWN CLG ISOL. The valve went closed and will not open.
- AOP 149, LOSS OF DECAY HEAT REMOVAL, was entered. It has been determined that with the current conditions the time to boil has been calculated to be 45 minutes.
- The RPV head is on and tensioned.
- RHR will be started and placed in Torus cooling by another operator.
- People have been evacuated from the Torus and Drywell.
- Based on system availability and plant configuration, it has been determined that the B Core Spray will be used to establish alternate shutdown cooling per section 3.2, Feed and Bleed to the Torus via Safety/Relief Valves.
INITIATING CUES (IF APPLICABLE):
- You are directed to perform section 3.2 of AOP 149 to establish the required conditions of the feed and bleed to the torus via the SRVs.
- You will use the B Core Spray Rapid Start QRC to align the B Core Spray system to fill the RPV.
Page 3 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. Simulator General
References:
- 1. OI 151, QRC, Rev. 1
- 2. AOP 149, Rev. 21 Task Standards:
- Candidate closes either CV-4412 or CV-4413 to isolate Main Steam Line A.
- Candidate closes either CV-4415 or CV-4416 to isolate Main Steam Line B.
- Candidate closes either CV-4418 or CV-4419 to isolate Main Steam Line C.
- Candidate closes either CV-4420 or CV-4421 to isolate Main Steam Line D.
- Closing either MO-4423 or MO-4424 isolates steam Line Drains.
- Candidate places the handswitch for one SRV in the OPEN position.
- B CORE SPRAY PUMP 1P-211B started.
- Candidate verifies that RPV pressure is < 450 and opens MO-2137.
- As necessary throttle MO-2137 to maintain < 3100 gpm on the CS system.
- Injects until one SRV open and RPV pressure is 50 psig above Torus pressure, but as low as practical.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
The following actions will be performed per AOP 149 section 3.2 Performance Step: Verify the reactor head is on and tensioned, head vents closed and at least one Critical N (SEQ-) SRV with N2 supply is available.
Standard: Parameters verified.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 Performance Step: Evacuate all personnel from the Drywell and Torus areas except personnel Critical N (SEQ-) assigned to monitor for leakage and/or increased airborne radioactivity levels Standard: Determine that this is a turnover item.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: To prevent flow down the main steam lines, verify at least one valve in each Critical Y (SEQ-) steam line is closed:
- Main Steam Line A CV-4412 or CV-4413 Standard: Candidate closes either CV-4412 and/or CV-4413 to isolate Main Steam Line A.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: To prevent flow down the main steam lines, verify at least one valve in each Critical Y (SEQ-) steam line is closed:
- Main Steam Line B CV-4415 or CV-4416 Standard: Candidate closes either CV-4415 and/or CV-4416 to isolate Main Steam Line B.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 5 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 Performance Step: To prevent flow down the main steam lines, verify at least one valve in each Critical Y (SEQ-) steam line is closed:
- Main Steam Line C CV-4418 or CV-4419 Standard: Candidate closes either CV-4418 and/or CV-4419 to isolate Main Steam Line C.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: To prevent flow down the main steam lines, verify at least one valve in each Critical Y (SEQ-) steam line is closed:
- Main Steam Line D CV-4420 or CV-4421 Standard: Candidate closes either CV-4420 and/or CV-4421 to isolate Main Steam Line D.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: To prevent flow down the main steam lines, verify at least one valve in each Critical N (SEQ-) steam line is closed:
- HPCI Steam Line MO-2238 or MO-2239 Standard: Verifies either MO-2238 and/or MO-2239 HPCI Steam Line isolations are closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 6 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 Performance Step: To prevent flow down the main steam lines, verify at least one valve in each Critical N (SEQ-) steam line is closed:
- RCIC Steam Line MO-2400 or MO-2401 Standard: Verifies either MO-2400 and/or MO-2401 RCIC Steam Isolations are closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: To prevent flow down the main steam lines, verify at least one valve in each Critical Y (SEQ-) steam line is closed:
- Steam Line Drains MO-4423 or MO-4424 Standard: Closing either MO-4423 and/or MO-4424 isolates steam Line Drains.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Place handswitch for one SRV in the open position.
Critical Y (SEQ-)
Standard: Candidate places the handswitch for one SRV in the OPEN position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 7 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 Performance Step: If available, place RHR in Torus Cooling per OI 149.
Critical N (SEQ-)
Standard: States that this is a turnover item that another operator will place RHR in Torus Cooling.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Commence and raise injection into the RPV with either a Condensate, Core Critical N (SEQ-) Spray or RHR pump until the SRV is open and RPV pressure is 50 psig above Torus pressure, but as low as practical.
Standard: Candidate will determine that here is where he will align CS to inject into the RPV IAW the Core Spray Rapid Start QRC.
Performance: SATISFACTORY UNSATISFACTORY Comments:
The following steps are from the Core Spray Rapid Start QRC.
Performance Step: Start 1P-99B, ESW Pumps B.
Critical N (SEQ-)
Standard: ESW pumps verified running.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that this is a turnover item.
Page 8 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 Performance Step: Start 1P-211B, Core Spray Pump B.
Critical Y (SEQ-)
Standard: B CORE SPRAY PUMP 1P-211B started.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Open MO-2137, Core Spray Inboard Injection Valve, when reactor pressure is Critical Y (SEQ-) <450 psig.
Standard: Candidate verifies that RPV pressure is < 450 and opens MO-2137.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note: to meet this step, the valve can either be throttled or fully opened.
Performance Step: Verify MO-2124, Core Spray Min Flow Bypass Valve, closes when system Critical N (SEQ-) flow is >600 gpm.
Standard: When flow is >600 gpm, MO-2124 closes.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 9 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 Performance Step: Throttle MO-2137, Core Spray Inboard Injection Valve, to maintain system flow Critical Y (SEQ-) <3100 gpm.
Standard: As necessary throttle MO-2137 to maintain < 3100 gpm on the CS system.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Verify RHR/CS Pump Room Cooling Units operating, Critical N (SEQ-) o For 1P-211B: 1V-AC-11.
Standard: B RHR/CS RM CLG UNIT, 1V-AC-11 is verified running.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE, the Candidate may take the handswitch for 1V-AC-11 to the start position.
This is acceptable but not required for the step.
NOTE, if the candidate feels that he must stay and continue to monitor Core Spray flows and adjust to maintain below 3100 gpm.
Cue him that another operator will verify the status 1V-AC-11. Wait 2 min. and inform the Candidate that 1V-AC-11 is running.
Performance Step: Verify operating Core Spray Pump motors <95 amps.
Critical N (SEQ-)
Standard: B Core Spray amps verified lower than 95.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 10 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 Performance Step: Continue to inject until the established conditions of one SRV open and Critical Y (SEQ-) RPV pressure is 50 psig above Torus pressure, but as low as practical.
Standard: Injects until one SRV open and RPV pressure is 50 psig above Torus pressure, but as low as practical.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE, if the candidate completes this JPM with the RPV pressure greater than 100 psig above Torus pressure, the Standard of this Performance Step is Unsat.
Terminating Cues: The JPM is complete when the candidate has established CS flow maintaining RPV pressure 50 psig above torus but as low as practical.
Stop Time:
Page 11 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 SIMULATOR SET UP:
The reactor must be shutdown. The ideal condition is to have the plant in SDC, have SDC be lost, then have the crew inject.
EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
As necessary.
SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 12 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 INSTRUCTOR ACTIONS:
- 1. Place the simulator in run and perform the following:
NOTE: The below setup is suggested as a minimum to create the needed conditions for the JPM, if other JPM setups require these to be altered that is acceptable as long as the intent of this JPM is not changed.
o Any simulator setup that has the reactor shut down and depressurized is acceptable for this JPM.
o The higher RPV level is at the onset, the less time it will take to establish a SRV open. Do not fill the RPV above the main steam lines.
o Ensure that HPCI and RCIC systems have been isolated on low RPV pressure.
o For the JPM your setup should have the following valves open:
All MSIVs.
Both steam line drains.
Page 13 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.
The plant has undergone a transient and the following has occurred:
- The plant was shutdown 5 days ago for a refueling outage.
- Shutdown cooling was lost due to a malfunction of MO 1908, INBD SHUTDOWN CLG ISOL. The valve went closed and will not open.
- AOP 149, LOSS OF DECAY HEAT REMOVAL, was entered. It has been determined that with the current conditions the time to boil has been calculated to be 45 minutes.
- The RPV head is on and tensioned.
- RHR will be started and placed in Torus cooling by another operator.
- People have been evacuated from the Torus and Drywell.
- Based on system availability and plant configuration, it has been determined that the B Core Spray will be used to establish alternate shutdown cooling per section 3.2, Feed and Bleed to the Torus via Safety/Relief Valves.
INITIATING CUES (IF APPLICABLE):
- You are directed to perform section 3.2 of AOP 149 to establish the required conditions of the feed and bleed to the torus via the SRVs.
- You will use the B Core Spray Rapid Start QRC to align the B Core Spray system to fill the RPV.
Page 14 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 209001-04, Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 15 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01 JPM NUMBER: 2.1.7-05 REV. 0 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 1.02 (Senior Reactor Operator)
TASK TITLE(S):
K/A NUMBERS: Generic 2.1.7 4.4 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 JPM Number: 2.1.7-05 JPM
Title:
Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
- It is 0500.
- You are a control room CRS.
- The NSOE has just handed you STP 3.0.0-01 for the end of shift review.
INITIATING CUES (IF APPLICABLE):
- You are to perform the end of shift review for STP 3.0.0-01, Instrument Checks.
Page 3 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 JPM PERFORMANCE INFORMATION Required Materials: 1. STP 3.0.0-01, Attachment 41 & 2, Rev. 50 General
References:
STP 3.0.0-01, Rev. 50 Task Standards:
- Determines that the leak rate is >5 gpm and enter TS 3.4.4 Condition A. This section allows 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to reduce the leakage to within the limits,
- Determines that the leak rate is >2 gpm increase within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and enter TS 3.4.4 Condition B. This section allows 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to reduce the leakage to within the limits, and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, verify the source of unidentified leakage increase is not service sensitive type 304 or type 316 stainless steel.
- Determines that OI 920, section 2.0 must be entered for the rise in leakage.
- CRS will state that he will notify the Operations Manager, Plant Manager, and Maintenance Work Management Supervisor.
- CRS will state that he would inform the ROs that they must pump the Floor Drain Sump every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> until notified differently.
- Notify Chemistry to collect a sample to determine if the Primary System is leaking.
- Determine that TS and also OI 920 require a shutdown.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: On page 8, he will verify that the 0000 and 0400 blanks for the Unidentified and Critical N (SEQ-) Identified leakage, are initialed.
Standard: Page 8 for Unidentified and Identified leakage blanks are initialed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 Performance Step: On page 9, Attachment 1, Unidentified Average Leak Rate Calculation, Critical Y (SEQ-) determine that the 0400 leak rate is at 5.2 gpm. This has gone up from
.07 gpm.
Standard: Determines that the leak rate is >5 gpm and enter TS 3.4.4 Condition A. This section allows 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to reduce the leakage to within the limits, Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: On page 9, Attachment 1, Unidentified Average Leak Rate Calculation, Critical Y (SEQ-) determine that the 0400 leak rate is at 5.2 gpm. This has gone up from
.07 gpm.
Standard: Determines that the leak rate is >2 gpm increase within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and enter TS 3.4.4 Condition B. This section allows 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to reduce the leakage to within the limits, and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, verify the source of unidentified leakage increase is not service sensitive type 304 or type 316 stainless steel.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: On page 10, Attachment 2, Identified Average Leak Rate Calculation, determine Critical N (SEQ-) that the 0000 and 0400 leak rates are at 1.5 gpm.
Standard: Review that identified leakage is currently 1.5 gpm.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 5 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 Performance Step: On page 10, Attachment 2, Identified Average Leak Rate Calculation, determine Critical N (SEQ-) that the 0000 and 0400 Total leak rates are at <25 gpm.
Standard: Review that total identified leakage is < 25 gpm.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Determine that the Unidentified leakage, at 5.2 gpm is above the Critical Y (SEQ-) ACCEPTANCE CRITERIA limit of page 8.
This limits are:
If 1.0 gpm, comply with OI 920, Section 2.0.
Standard: Determines that OI 920, section 2.0 must be entered for the rise in leakage.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Knowing that Unidentified Leakage reached 1.0 gpm, perform the following per OI Critical Y (SEQ-) 920, section 2.0:
- Notify the Operations Manager, Plant Manager, and Maintenance Work Management Supervisor.
Standard: CRS will state that he will notify the Operations Manager, Plant Manager, and Maintenance Work Management Supervisor.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 6 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 Performance Step: Knowing that Unidentified Leakage reached 1.0 gpm, perform the following per OI Critical Y (SEQ-) 920, section 2.0:
- Increase monitoring to every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (Not required if the leakage is known not to be from the Primary Systems, i.e., well water or RBCCW).
Standard: CRS will state that he would inform the ROs that they must pump the Floor Drain Sump every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> until notified differently.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Knowing that Unidentified Leakage reached 1.0 gpm, and determining that after Critical Y (SEQ-) reaching 1 gpm a step jump of greater than .5 gpm has occurred,
- Continue on with section (b) of Section 2 of OI 920.
Standard: Notify Chemistry to collect a sample to determine if the Primary System is leaking.
Performance: SATISFACTORY UNSATISFACTORY Comments: When it is determined that Chemistry is to be notified to collect a sample, cue ask the following question of the Candidate; What will you do if the sample that chemistry collects is reactor water?
Performance Step: If the leak is determined to be reactor water Critical Y (SEQ-)
Standard: Determine that TS and also OI 920 require a shutdown.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 7 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 Terminating Cues: When the requirements TS 3.4.4 have been discussed and the acceptance criteria of STP 3.0.0-01 have been covered, the JPM may be terminated..
Stop Time:
Page 8 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 9 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 INSTRUCTOR ACTIONS:
Find a quiet place that has access to a calculator and OIs.
Give the candidate a marked up copy of the applicable portion of STP 3.0.0-01, INSTRUMENT CHECKS.
This will include the following:
- Copies of pages 1-10.
- Initial the NOTE and the PREREQUISITES blank on page 6.
- On page 8, o Circle MODE 1 in the Reactor MODE section.
o Initial the 0000, and 0400 with a WT, for both the unidentified and identified leakage.
o Initial the Note at the bottom of the page with a WT, and N/A the Date and Time blanks.
- On page 9, o Initial the Note at the top of the page with a WT.
o Fill in the unidentified sump readings through the 0800 time frame. Make the numbers match the ones on page 12 of this JPM and initial them with WT.
o Initial the Note at the bottom of the page with a WT.
- On page 10, o Initial the Note at the top of the page with a WT.
o Fill in the unidentified sump readings through the 0800 time frame. Make the numbers match the ones on page 13 of this JPM and initial them with WT.
- On page 60, Initial step 8.6.1 with LT.
This copy of the STP will be given to the candidate to perform the JPM.
Also have available marked up copies of:
- The Operators working copy of the Sumps graph.
If the candidate asks for the above give them to him to use.
Page 10 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 TURNOVER SHEET INITIAL CONDITIONS:
- It is 0500.
- You are a control room CRS.
- The NSOE has just handed you STP 3.0.0-01 for the end of shift review.
INITIATING CUES (IF APPLICABLE):
- You are to perform the end of shift review for STP 3.0.0-01, Instrument Checks.
Page 11 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 ATTACHMENT 1 UNIDENTIFIED AVERAGE LEAK RATE CALCULATION (Note: Not required in MODE 4 ) WT All readings are to be taken at Panel 1C19.
0000 a. FQ 3707 present reading _____124500___ Time of Reading ____0000___
- b. FQ 3707 previous reading ____124483____ Time of Reading ___ _2000___
- c. Total gallons pumped (a-b) _______17____
- d. Time interval (a-b) ______4_____ hours x 60 = ___240_____ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = ____.07__ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) ________WT_____
Operators Initials 0400 a. FQ 3707 present reading ___ _125750 ____ Time of Reading _____0400__
- b. FQ 3707 previous reading ____124500____ Time of Reading ___ _0000___
- c. Total gallons pumped (a-b) _____1250_____
- d. Time interval (a-b) ) ______4_____ hours x 60 = ___240_____ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = ____5.2___ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) ________WT_____
Operators Initials 0800 a. FQ 3707 present reading _____ __________ Time of Reading ____ _______
- b. FQ 3707 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) _____________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) _________________
Operators Initials 1200 a. FQ 3707 present reading _________ Time of Reading ___________
- b. FQ 3707 previous reading _____ ____ Time of Reading ___________
- c. Total gallons pumped (a-b) _____________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) _______________
Operators Initials 1600 a. FQ 3707 present reading ________________ Time of Reading ___________
- b. FQ 3707 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) ______________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) _______________
Operators Initials 2000 a. FQ 3707 present reading ________________ Time of Reading ___________
- b. FQ 3707 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) ______________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Unidentified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Confirm unidentified average leak rate (e) is 5 gpm (Note 1) _______________
Operators Initials Note 1: May be > 5 gpm if STP 3.4.4-01 in progress to reclassify unidentified leakage. WT Page 12 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 ATTACHMENT 2 IDENTIFIED AVERAGE LEAK RATE CALCULATION (Note: Not required in MODE 4 ) WT All readings are to be taken at Panel 1C19.
0000 a. FQ 3708 present reading ____331785_____ Time of Reading ____0000___
- b. FQ 3708 previous reading ___331425_______ Time of Reading __2000_____
- c. Total gallons pumped (a-b) _____360______
- d. Time interval (a-b) ______4_____ hours x 60 = ____240____ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = __1.50___ gpm
- f. Add identified (e) and unidentified (Att 1, e) =_____1.57___
- g. Confirm total average leak rate (f) is 25 gpm ________WT_____
Operators Initials 0400 a. FQ 3708 present reading _____332145______ Time of Reading ____0400___
- b. FQ 3708 previous reading ____331785_____ Time of Reading _____0000__
- c. Total gallons pumped (a-b) ______360____
- d. Time interval (a-b) ______4_____ hours x 60 = ____240____ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = ___1.50__ gpm
- f. Add identified (e) and unidentified (Att 1, e) =_____6.7__
- g. Confirm total average leak rate (f) is 25 gpm ________WT_____
Operators Initials 0800 a. FQ 3708 present reading ________________ Time of Reading ___________
- b. FQ 3708 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) ______________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Add identified (e) and unidentified (Att 1, e) =____________
- g. Confirm total average leak rate (f) is 25 gpm _________________
Operators Initials 1200 a. FQ 3708 present reading ________________ Time of Reading ___________
- b. FQ 3708 previous reading ________________ Time of Reading ___________
- c. Total gallons pumped (a-b) _____________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = ________ gpm
- f. Add identified (e) and unidentified (Att 1, e) =____________
- g. Confirm total average leak rate (f) is 25 gpm ____________________
Operators Initials 1600 a. FQ 3708 present reading ________________ Time of Reading ___________
- b. FQ 3708 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) ______________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Add identified (e) and unidentified (Att 1, e) =____________
- g. Confirm total average leak rate (f) is 25 gpm ____________________
Operators Initials 2000 a. FQ 3708 present reading ________________ Time of Reading ___________
- b. FQ 3708 previous reading _______________ Time of Reading ___________
- c. Total gallons pumped (a-b) ______________
- d. Time interval (a-b) ____________ hours x 60 = ___________ min.
- e. Identified average leak rate = Total Gallons Pumped (c)
Time Interval (minutes) (d) = _________ gpm
- f. Add identified (e) and unidentified (Att 1, e) =____________
- g. Confirm total average leak rate (f) is 25 gpm ____________________
Operators Initials Page 13 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 This is the portion of the leakage document that can be transferred over to the entire leakage form for the JPM DAY TIME UNIDENTIFIED IDENTIFIED (FLOOR DRAIN) (EQUIPMENT)
FQ3707 GAL GPM FQ3708 GAL GPM 4-HR 24- 4-HR 24- 4-HR 24- 4-HR 24-HR HR HR HR PREVIOUS 0800 2000 2400 124433 10 329624 359 0400 124443 10 .04 329984 360 1.5 SUNDAY 0800 124452 9 60 .04 .04 330345 361 2160 1.5 1.5 1200 124463 11 .04 330705 360 1.5 1600 124473 10 .04 331064 359 1.5 2000 124483 10 61 .04 .04 331425 361 2156 1.5 1.5 2400 124500 17 .07 .04 331785 360 1.5 1.5 0400 125750 1250 5.2 332145 360 1.5 MONDAY 0800 1200 1600 2000 2400 0400 Page 14 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.1.7-05, Interpret REACTOR COOLANT LEAKAGE calculations per STP 3.0.0-01, Rev. 0 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 15 of 15
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State.
JPM NUMBER: 2.4.41-01 REV. 1 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 3.01 (Senior Reactor Operator)
TASK TITLE(S):
K/A NUMBERS: Generic 2.4.41 4.1 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 25 Minutes Time Critical: YES Alternate Path / Faulted: NO TASK APPLICABILITY: SRO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 JPM Number: 2.4.41-01 JPM
Title:
Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The plant had been running at 93% Thermal Power. Last week a small fuel leak was detected. The REs have located the leaker and developed a new rod pattern to shadow the leaking assembly.
- Last night power was lowered with Recirc to perform a control rod pull to adjust load line.
- After the pull power was being raised back up to 89%.
- The crew observed that the Pretreat Radiation Monitor and the Offgas Stack rad monitor were rising steadily.
- The Power rise was stopped.
o About 50 minutes ago the Offgas Stack Rad monitor has gone up to 2.5 E -1 micro curries per cc.
o About 60 minutes ago the Turbine building ventilation rad monitor was, reading 1.34 E -3 micro curries per cc.
o The REs have determined that these rates will continue to rise a little for the next few hours and then stabilize out.
o There are currently no KAMAN alarms.
- Outside air temp is 10 degrees F at 50 meters.
- The wind direction is from 98 degrees at 50 meters.
- The wind speed is at 14 mph at 50 meters.
INITIATING CUES (IF APPLICABLE):
You are the Shift Manager.
Based on the given plant conditions, you are to independently determine the Emergency Action Level, and Complete NOTE 5.
I will act as the STA and fill out NOTE 1 and make the phone notifications.
This JPM is TIME CRITICAL.
Page 3 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. EPIP 1.1, Rev. 24
- 2. EPIP 1.2, Rev. 31
- 3. Note 5, DAEC Emergency Action Level Notification Form, Sheets 1 and 2 Rev. 8 General
References:
Task Standards:
- The following critical tasks are for the AU1 declaration.
- Within 15 minutes of being handed the initial conditions, determine that the EAL is an AU1 Alert. Inform the Shift Manager of his recommendation for an EAL.
- Candidate will circle Unusual Event.
- Candidate will: Place an N/A in both the TIME and DATE blanks for the PAR change, Print A U 1 in the blanks for the EAL. and Circle A in the Category, circle U in the Classification, and circle 1 in the Sequence.
- Candidate will circle Yes and proceed to block 6.
- Candidate will circle Below Federal limits.
- Candidate will circle Radioactive Airborne (filtered), and Radioactive Airborne (unfiltered).
- Candidate will write in 14 mph.
- Candidate will write in 98 degrees.
- Candidate will X the Unusual Event box.
- When filled out, the candidate will offer the note to the SM to sign within the 15 minutes from the declaration of the AU1, and then give the form to the Security Guard to perform the notifications.
- The following critical tasks are for the FA1 declaration.
- Within 15 minutes of being handed Attachment 1, determine that the EAL is a FA1 Alert.
- Inform the Shift Manager of his recommendation for an EAL.
- Candidate will circle Alert.
- Candidate will, Place an N/A in both the TIME and DATE blanks for the PAR change, Print F A 1 in the blanks for the EAL, and Circle F in the Category, circle A in the Classification, and circle 1 in the Sequence.
- Candidate will circle Yes and proceed to block 6.
- Candidate will circle Below Federal limits.
- Candidate will circle Radioactive Airborne (filtered), and Radioactive Airborne (unfiltered).
- Candidate will write in 14 mph.
- Candidate will write in 98 degrees.
- Candidate will X the Alert box.
- When filled out, the candidate will offer the note to the SM to sign within the 15 minutes from the declaration of the FA1, and then give the form to the Security Guard to perform the notifications.
Page 4 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: The Candidate will determine that the proper EAL for the given plant conditions Critical Y (SEQ-) is an AU1. This is based on either of the Turbine building or Offgas Stack radiation readings.
Standard: Within 15 minutes of being handed the initial conditions, determine that the EAL is an AU1 Unusual Event.
Inform the Shift Manager of his recommendation for an EAL.
Performance: SATISFACTORY UNSATISFACTORY Comments: Evaluator, if asked, if the RE expects the release to reach 6.0 E-0, CUE the Candidate it is not expected to reach those levels.
Evaluator, which ever the EAL the Candidate recommends, AGREE with him, then CUE: Hand him a blank copy of NOTE 5 and direct him to fill it out, also inform him that another person will perform NOTE 1, and that you will call Security.
Evaluator, mark the time that the candidate makes his declaration ___________.
The student must finish the Note 5 within 15 minutes of the declaration.
The next portion of this JPM will be the preparation of NOTE 5, DAEC EMERGENCY ACTION LEVEL NOTIFICATION FORM for the UNUSUAL EVENT.
Page 5 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 1 Critical N (SEQ-) Status
- Circle one Actual Drill or Simulator Standard: Candidate will circle DRILL or Simulator.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 2 Critical N (SEQ-) Facility in Command and Control
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 6 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 3 Critical Y (SEQ-) Accident Classification
- Circle one Unusual Event Alert Site Area Emergency General Emergency Recovery Cancellation /Termination Standard: Candidate will circle Unusual Event.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 4 Critical Y (SEQ-) EAL Classified
- Time and date
- EAL letters (write the letters on the blanks)
- Circle the EAL letters Standard: Candidate will:
- Fill in the TIME and DATE blanks for the EAL.
- Print A U 1 in the blanks for the EAL.
- Circle A in the Category, circle U in the Classification, and circle 1 in the Sequence.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 7 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 5 Critical Y (SEQ-) Release in Progress due to this event.
- Circle one o Yes, proceed to 6 o No, proceed to 9 Standard: Candidate will circle Yes and proceed to block 6.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 6 Critical Y (SEQ-) Airborne Release to Environment
- Circle one o Below Federal limits o At or Above Federal limits Standard: Candidate will circle Below Federal limits.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 8 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 7 Critical Y (SEQ-) Type of Release
- Circle one o Radioactive Airborne (filtered) o Radioactive Airborne (unfiltered) o Radioactive Liquid Standard: Candidate will circle Radioactive Airborne (filtered), and Radioactive Airborne (unfiltered).
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 8 Critical N (SEQ-) Projected duration of Release
- Circle one o Unknown (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> default) o 1 Hour or Less o Release Duration _____ hours Standard: Candidate will circle unknown (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> default).
Performance: SATISFACTORY UNSATISFACTORY Comments:
Evaluator, after the Candidate fills out Block 8, give him the below information by handing him New Conditions data sheet (located in the back of this JPM):
- Plant conditions have degraded.
- The crew had to insert a manual scram.
o At the time of the scram a small LOCA occurred.
o RPV level is currently being controlled in the green band by feedwater.
o DW Pressure steady at 4.2 psig.
Page 9 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 All automatic actions that occur on a 2 psig DW signal have occurred as designed.
o Torus water temperature 82 degrees and rising slowly.
- The Offgas Stack Rad monitor has gone up to 3.4 E -1 micro curries per cc.
- The Turbine building ventilation rad monitor has gone up to 1.5 E -3 micro curries per cc.
- Outside air temp is 10 degrees F at 50 meters.
- The wind direction is from 98 degrees at 50 meters.
- The wind speed is at 14 mph at 50 meters.
Evaluator, mark the time that you gave the Candidate the new data, ______________.
From this point the Candidate has to meet the following times:
First:
- 1. The First NOTE 5 must be complete by the declaration time + 15 minutes OR
- 2. If the candidate decides to fill out a new Note 5, the new Note 5 for the FA1 must be filled out within the 15 minutes from the AU1 call, and the AU1 should be noted in the additional information section of Note 5.
If the Candidate chooses this option, the JPM will continue on page 13.
- 3. He can finish the AU1 notifications.
Declare the EAL for the second set of information within the 15 minutes of the threshold being crossed.
Then fill out the Note 5 for the FA1 within 15 minutes of the declaration.
NOTE that if he chooses Option # 2, he does not need to continue in the AU1 Note 5. Therefore, ALL of the Critical tasks for filling out NOTE 5 for the AU1 do not apply anymore. For this option, the critical step is to get the FA1 notification done within the original 15 minutes.
The following steps will be the completion of the AU1 notification if the Candidate chooses to complete the AU1 then go to the determination of the FA1.
Performance Step: NOTE 5 Block 9 Critical Y (SEQ-) Wind Speed Standard: Candidate will write in 14 mph.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 10 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 10 Critical Y (SEQ-) Wind direction Standard: Candidate will write in 98 degrees.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 11 Critical Y (SEQ-) Utility Protective Action Recommendations
- X one of the following:
o Unusual Event o Alert o Site Area Emergency o General [D]
o General [E]
o General [F]
Standard: Candidate will N/A the Par Determination @ time and date blanks, and X the Unusual Event box.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 11 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 12 Critical N (SEQ-) Additional Information Standard: Candidate may list the high points of what has happened.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 13 Critical Y(SEQ-) Approved by Standard: When filled out, the candidate will offer the note to the SM to sign within the 15 minutes from the declaration of the AU1, and then give the form to the Security Guard to perform the notifications.
Performance: SATISFACTORY UNSATISFACTORY Comments: Evaluator, the time from the declaration of the AU1 to the notification of Linn, Benton, and State, must be < 15 minutes.
NOTE that if the Candidate chooses to finish the paper work for the AU1, they should state that because of NOTE 1 being completed for the AU1, that the next message should be sent out on the Alpha Numeric Pager.
The following steps are concerned with the New Conditions Data Sheet.
Page 12 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: The Candidate will determine that the proper EAL for the given plant conditions Critical Y (SEQ-) is a FA1. This is based on a LOSS in the RCS Barrier.
Standard: Within 15 minutes of being handed Attachment 1, determine that the EAL is a FA1 Alert.
Inform the Shift Manager of his recommendation for an EAL.
Performance: SATISFACTORY UNSATISFACTORY Comments: Evaluators, whichever EAL the Candidate recommends, AGREE with him, then CUE him to fill out NOTE 5.
Evaluator, the time from giving the Candidate the Attachment 1 to the time of the declaration must be less than 15 minutes.
Evaluator, mark the time of the declaration ______________.
The remaining portion of this JPM will be the preparation of NOTE 5, DAEC EMERGENCY ACTION LEVEL NOTIFICATION FORM for the FA1 event.
Performance Step: NOTE 5 Block 1 Critical N (SEQ-) Status
- Circle one Actual Drill or Simulator Standard: Candidate will circle Drill or Simulator.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 13 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 2 Critical N (SEQ-) Facility in Command and Control
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 3 Critical Y (SEQ-) Accident Classification
- Circle one Unusual Event Alert Site Area Emergency General Emergency Recovery Cancellation /Termination Standard: Candidate will circle Alert.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 14 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 4 Critical Y (SEQ-) EAL Classified
- Time and date
- EAL letters (write the letters on the blanks)
- Circle the EAL letters Standard: Candidate will:
- Place an N/A in both the TIME and DATE blanks for the PAR change.
- Print F A 1 in the blanks for the EAL.
- Circle F in the Category, circle A in the Classification, and circle 1 in the Sequence.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 5 Critical Y (SEQ-) Release in Progress due to this event.
- Circle one o Yes, proceed to 6 o No, proceed to 9 Standard: Candidate will circle Yes and proceed to block 6.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 15 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 6 Critical Y (SEQ-) Airborne Release to Environment
- Circle one o Below Federal limits o At or Above Federal limits Standard: Candidate will circle Below Federal limits.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 7 Critical Y (SEQ-) Type of Release
- Circle one o Radioactive Airborne (filtered) o Radioactive Airborne (unfiltered) o Radioactive Liquid Standard: Candidate will circle Radioactive Airborne (filtered), and Radioactive Airborne (unfiltered).
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 16 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 8 Critical N (SEQ-) Projected duration of Release
- Circle one o Unknown (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> default) o 1 Hour or Less o Release Duration _____ hours Standard: Candidate will circle unknown (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> default).
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 9 Critical Y (SEQ-) Wind Speed Standard: Candidate will write in 14 mph.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 17 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 10 Critical Y (SEQ-) Wind direction Standard: Candidate will write in 98 degrees.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 11 Critical Y (SEQ-) Utility Protective Action Recommendations
- X one of the following:
o Unusual Event o Alert o Site Area Emergency o General [D]
o General [E]
o General [F]
Standard: Candidate will N/A the Par Determination @ time and date blanks, and X the Alert box.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 18 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01, Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State, Rev. 1 Performance Step: NOTE 5 Block 12 Critical N (SEQ-) Additional Information Standard: If the Candidate did not fill out the complete AU1 paper work, he should state that the plant is currently in an AU1 due to elevated release rates.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: NOTE 5 Block 13 Critical Y(SEQ-) Approved by Standard: When filled out, the candidate will offer the note to the SM to sign within the 15 minutes from the declaration of the FA1, and then give the form to the Security Guard to perform the notifications.
Performance: SATISFACTORY UNSATISFACTORY Comments: Evaluator, the time from the declaration of the FA1 to the notification of Linn, Benton, and State, must be < 15 minutes.
Terminating Cues: When NOTE 5 has been handed to the SM to review and sign, the JPM is complete.
Stop Time:
Page 19 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01 Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn Benton and State, Rev. 1 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 20 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01 Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn Benton and State, Rev. 1 INSTRUCTOR ACTIONS:
If the JPM is performed somewhere other than the simulator, ensure that there is a copy of:
- Copies of NOTE 5, DAEC EMERGENCY ACTION LEVEL NOTIFICATION FORM.
Page 21 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01 Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn Benton and State, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
The plant had been running at 93% Thermal Power. Last week a small fuel leak was detected. The REs have located the leaker and developed a new rod pattern to shadow the leaking assembly.
- Last night power was lowered with Recirc to perform a control rod pull to adjust load line.
- After the pull power was being raised back up to 89%.
- The crew observed that the Pretreat Radiation Monitor and the Offgas Stack rad monitor were rising steadily.
- The Power rise was stopped.
o About 50 minutes ago the Offgas Stack Rad monitor has gone up to 2.5 E -1 micro curries per cc.
o About 60 minutes ago the Turbine building ventilation rad monitor was, reading 1.34 E -3 micro curries per cc.
o The REs have determined that these rates will continue to rise a little for the next few hours and then stabilize out.
o There are currently no KAMAN alarms.
- Outside air temp is 10 degrees F at 50 meters.
- The wind direction is from 98 degrees at 50 meters.
- The wind speed is at 14 mph at 50 meters.
INITIATING CUES (IF APPLICABLE):
You are the Shift Manager.
Based on the given plant conditions, you are to independently determine the Emergency Action Level, and Complete NOTE 5.
I will act as the STA and fill out NOTE 1 and make the phone notifications.
This JPM is TIME CRITICAL.
Page 22 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01 Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn Benton and State, Rev. 1 Attachment 1 New Conditions Data Sheet
- Plant conditions have degraded.
- The crew had to insert a manual scram.
o At the time of the scram a small LOCA occurred.
o RPV level is currently being controlled in the green band by feedwater.
o DW Pressure steady at 4.2 psig.
All automatic actions that occur on a 2 psig DW signal have occurred as designed.
o Torus water temperature 82 degrees and rising slowly.
- The Offgas Stack Rad monitor has gone up to 3.4 E -1 micro curries per cc.
- The Turbine building ventilation rad monitor has gone up to 1.5 E -3 micro curries per cc.
- Outside air temp is 10 degrees F at 50 meters.
- The wind direction is from 98 degrees at 50 meters.
- The wind speed is at 14 mph at 50 meters.
Assess the new conditions and make the necessary adjustments to the EAL declaration and paper work.
Page 23 of 24
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.4.41-01 Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn Benton and State, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 24 of 24
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
1 of 12 2
Usage Level CONTINUOUS Effective Date: __________________
Verified By: Date:
Testing and Surveillance Validated By: Date:
Operations Verified By: Date:
System Engineering Approved By: Date:
Procedures Reviewed By: Date:
Operations Committee Approved By: Date:
DAEC Plant Manager
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
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1.0 PURPOSE 1.1 This STP verifies correct breaker alignment and indicated power availability for each offsite circuit capable of supplying the onsite Class 1E AC Electrical Distribution System.
1.2 This STP is routinely performed with both offsite circuits available, or in response to the condition of one offsite circuit or one diesel generator inoperable.
2.0 BRIEFING INFORMATION 2.1 PERFORMANCE INFORMATION 2.1.1 Personnel recommended to perform this procedure:
1 Operations 2.1.2 Special Test Equipment required:
1 Marking Pen (Do not use light colored hi-lighters or markers. Use only dark colored pens or markers. See General Caution 2.2.1).
2.2 GENERAL CAUTIONS 2.2.1 Do not use light colored hi-lighters or markers to record data, outline configurations on drawings or to initial steps in this STP. Light colored hi-lighters are not dark enough to reproduce adequately when micro-filmed and the micro-filmed copy IS the QA record.
2.3 SPECIAL PRECAUTIONS 2.3.1 None
3.0 REFERENCES
3.1 Applicable drawings:
3.1.1 BECH-E001<1>
3.1.2 BECH-E005 3.1.3 BECH-E023 3.2 Supporting documents:
3.2.1 NG-97-2146
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
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4.0 GENERAL INSTRUCTIONS 4.1 Section 7.0 of this STP contains two (2) sections that cover the anticipated conditions under which this STP will be performed. The STP is organized as follows:
Section Conditions 7.1 Both Offsite Circuits Available 7.2 One Offsite Circuit Available Only one of these sections should need to be performed to satisfy the performance requirements associated with this STP. All steps within a particular section are to be performed in sequence and the STP steps carried through to completion, unless stated otherwise.
4.2 Steps marked with a "TS" immediately to the right of the step sign-off line are required by Technical Specifications. If these steps do not meet their acceptance criteria, or cannot be performed, an NRC reportable condition may exist and shall be reported to the Control Room Supervisor (CRS) immediately.
4.3 If any equipment or components are observed to be in a state of disrepair during the performance of this STP, appropriate corrective maintenance shall be initiated.
4.4 An Action Request (AR) should be completed for any problems encountered with "TS" marked steps during the performance of this test.
4.5 The CRS shall be notified immediately and the appropriate Limiting Conditions for Operation section of Technical Specifications referred to whenever problems are encountered during the performance of this STP.
5.0 APPENDICES 5.1 Appendix A - DAEC OFFSITE POWER CIRCUITS FEEDING ESSENTIAL BUSES
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page 4 of 12 Rev. 2 Appendix - A DAEC OFFSITE POWER CIRCUITS FEEDING ESSENTIAL BUSES Sheet 1 of 1 7510 L3 "C" Dysart Sub Power Source Breaker Transformer Bus 5950 5560 Line "AB" "K" 6th Street Sub Unacceptable path for the purposes of this STP.
4290 161KV 1A 1A "I" West Bus 301 302 345KV West Bus 2820 6780 L6 "S" "F" Hills 1A3 Sub 3110 0220 0710 8490 T1 1X4 1X3 "B" "H" "T" "M" Hazelton Sub 1A4 4730 2690 L7 "R" "D" 345KV East Bus 9180 161KV 1A 1A L1 "G" East Bus 401 402 Hiawatha Sub 8090 5550 L2 "A" "J" Fairfax Sub
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
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Prerequisites Performance Date: ____________________ INITIALS 6.0 PREREQUISITES 6.1 Offsite power is supplying essential buses 1A3 and 1A4 via either the ________
startup transformer (normal source) or the standby transformer (alternate source).
6.2 Evaluate electrical system status and select the STP section which is to be ________
performed:
[ ] Section 7.1 - Both Offsite Circuits Available
[ ] Section 7.2 - One Offsite Circuit Available
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
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Performance Date: ____________________ INITIALS 7.0 PROCEDURE 7.1 BOTH OFFSITE CIRCUITS AVAILABLE NOTE Information from the Load Dispatcher may be needed to complete the following step.
7.1.1 Using the guidance below and Attachment 1, identify two separate circuits available to transmit power from the offsite power sources to the essential buses.
- a. Based on equipment/system lineup and operational status, ________
use a dark marking pen to trace an available circuit from an offsite power source to the Startup Transformer supply breakers, 1A302 and 1A402.
- b. Based on equipment/system lineup and operational status, ________
use a dark marking pen to trace a second circuit from another offsite power source to the Standby Transformer supply breakers, 1A301 and 1A401 such that it does not share any lines, buses, or transformers in common with the circuit to the Startup Transformer supply breakers.
- c. Based on equipment/system lineup and operational status, ________
complete the electrical lineup by using a dark marking pen to trace the connections from each Essential Bus (1A3 and 1A4) to the Startup or Standby Transformer supply breaker currently feeding the bus.
7.1.2 Confirm two (2) independent offsite circuits are available by initialing one of the two sets of statements below and N/Aing the other:
- a. A circuit exists from an offsite power source, through the ________ TS Startup Transformer and its supply breakers to both 1A3 and 1A4 essential buses; AND A second independent circuit exists from a different offsite source, through the Standby Transformer to its supply breakers.
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
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Performance Date: ____________________ INITIALS
- b. A circuit exists from an offsite power source, through the ________ TS Startup Transformer and one of its supply breakers to either the 1A3 or 1A4 essential bus; AND A second independent circuit exists from a different offsite source, through the Standby Transformer and one of its supply breakers to the other essential bus.
Performed by: Date: Time:
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
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Performance Date: ____________________ INITIALS 7.2 ONE OFFSITE CIRCUIT AVAILABLE NOTE Information from the Load Dispatcher may be needed to complete the following step.
7.2.1 Using the guidance below and Attachment 1, identify a circuit available to transmit power from an offsite power source to the essential buses.
- a. Based on equipment/system lineup and operational status, ________
use a dark marking pen to trace an available circuit from an offsite power source to the Startup Transformer supply breakers, 1A302 and 1A402 or Standby Transformer supply breakers, 1A301 and 1A401.
- b. Based on equipment/system lineup and operational status, ________
complete the electrical lineup by using a dark marking pen to trace the connections from the required Essential Bus(es)
(1A3 and/or 1A4) to the Startup or Standby Transformer supply breakers.
7.2.2 If in Mode 1, 2 or 3, mark Step 7.2.4 N/A and proceed with the ________
performance of Step 7.2.3.
OR If in Mode 4 or 5, or during movement of irradiated fuel assemblies in the Secondary Containment, mark Step 7.2.3 N/A and proceed with the performance of Step 7.2.4.
7.2.3 Confirm an offsite circuit exists from an offsite power source, ________ TS through either the Startup or Standby Transformer and its associated supply breakers to both 1A3 and 1A4 essential buses.
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
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Performance Date: ____________________ INITIALS 7.2.4 Confirm an offsite circuit exists from an offsite power source by initialing one of the two statements below and N/Aing the other:
- a. An offsite circuit exists from an offsite power source, through ________ TS either the Startup or Standby Transformer and its associated supply breakers to both 1A3 and 1A4 essential buses.
- b. An offsite circuit exists from an offsite power source, through ________ TS either the Startup or Standby Transformer and one of its associated supply breakers to the required 1A3 or 1A4 essential bus.
Performed by: Date: Time:
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
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Performance Date: ____________________ INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 Indicate the reason for performing the STP:
[ ] Routine with both offsite circuits available
[ ] Routine with one offsite circuit available while in Mode 4 or 5 or during movement of irradiated fuel assemblies in the secondary containment
[ ] Action in response to one offsite circuit inoperable
[ ] Action in response to one diesel generator inoperable
[ ] Other, explain below:
8.2 If a DCF, Procedure Work Request (PWR), or Action Request (AR) was written due to problems encountered with the performance of this procedure, list the applicable number(s) below and attach a copy of each to this procedure. ("N/A" blocks as appropriate.)
DCF No. ________ PWR No. _________ AR No. _________
DCF No. ________ PWR No. _________ AR No. _________
8.3 All Technical Specification required items, as indicated by "TS", have been performed satisfactorily:
8.3.1 Section 7.1 ( ) YES ( ) NO CRS notified ________
8.3.2 Section 7.2 ( ) YES ( ) NO CRS notified ________
8.4 All other items checked in this test have been performed satisfactorily:
8.4.1 Section 7.1 ( ) YES ( ) NO CRS notified ________
8.4.2 Section 7.2 ( ) YES ( ) NO CRS notified ________
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page Rev.
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Performance Date: ____________________ INITIALS 8.5 Indicate any relevant test comments below, otherwise mark this step "N/A":
Operations Date Surveillance Coordinator Date 9.0 ATTACHMENTS 9.1 Attachment 1 - OFFSITE CIRCUIT POWER AVAILABILITY
SURVEILLANCE TEST PROCEDURE STP 3.8.1-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: OFFSITE POWER SOURCES Page 12 of 12 Rev. 2 Attachment 1 OFFSITE CIRCUIT POWER AVAILABILITY Sheet 1 of 1 7510 L3 "C" Dysart Sub Power Source Breaker Transformer Bus 5950 5560 Line "AB" "K" 6th Street Sub Unacceptable path for the purposes of this STP.
4290 161KV 1A 1A "I" West Bus 301 302 345KV West Bus 2820 6780 L6 "S" "F" Hills 1A3 Sub 3110 0220 0710 8490 T1 1X4 1X3 "B" "H" "T" "M" Hazelton Sub 1A4 4730 2690 L7 "R" "D" 345KV East Bus 9180 161KV 1A 1A L1 "G" East Bus 401 402 Hiawatha Sub 8090 5550 L2 "A" "J" Fairfax Sub
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Peer check STP 3.8.1-01, Offsite Power Sources. Determine that the STP was done incorrectly. Re-performs STP.
JPM NUMBER: 2.2.12-02 REV. 0 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 1.07 (Reactor Operator)
TASK TITLE(S):
K/A NUMBERS: Generic 2.2.12 2.9 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 JPM Number: 2.2.12-02 JPM
Title:
Peer check STP 3.8.1-01, Offsite Power Sources. Determine that the STP was done incorrectly. Re-performs STP.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The plant is running at 100% electrical output. The only inoperable piece of equipment is the K Breaker, (5560). It was tagged out for maintenance last Friday.
Today is Sunday, and another operator has just finished the weekly STP 3.8.1-01, Offsite Power Sources.
INITIATING CUES (IF APPLICABLE):
The CRS has directed you to perform an independent review of STP 3.8.1-01, Offsite Power Sources.
Page 3 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 JPM PERFORMANCE INFORMATION Required Materials: 1. A marked up copy of STP 3.8.1-01, Rev. 2.
- 2. Pictures of 1C08, (part of this JPM).
- 3. Three colored pens, (Red, Blue, and Green, preferable), for the filling out of a new offsite circuit power map.
- 4. One filled out offsite circuit power map that is wrong, (Attached).
- 5. A Clean copy of STP 3.8.1-01.
General
References:
Task Standards:
- Determine that Attachment 1 is incorrect. Both off site power sources running through theT1 transformer.
- CRS notified.
- The Candidate will trace offsite power from either, L1, (Hiawatha) or, L2, (Fairfax) or, L3, (Dysart) or, Line, (6th Street), to 1X3, to 1A302 and 1A402, Without going through T1.
- The Candidate will trace offsite power from either, L1, (Hiawatha) or, L2, (Fairfax) or, L3, (Dysart) or, Line, (6th Street), to 1X3, or L6, (Hazelton) or L7, (Hills), to T1, to 1X4, to 1A301 and 1A401.
- The key thing here is that NO lines use the same portion of line at any time.
- Candidate will initial 7.1.2a and N/A 7.1.2b.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Page 4 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 Performance Step: Candidate will review STP 3.8.1-01.
Critical Y (SEQ-)
- Determine that attachment 1 is filled out improperly.
o Both Power Sources Line and L7 go through Transformer T1.
Standard: Determine that attachment 1 is filled out improperly.
Both Power Sources Line and L7 go through Transformer T1.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: The way Attachment 1 is filled out, you are not in compliance with step Critical Y (SEQ-) 7.1.2 and b.
Standard: The Candidate must notify the CRS that the STP was not properly filled out.
Performance: SATISFACTORY UNSATISFACTORY Comments: Evaluator, when the candidate has determined that the current Attachment is incorrect, give him the following:
- Pictures of 1C08
- Switchyard map
- Clean copy of STP 3.8.1-01
- Three colored pens
- Straight edge Then CUE him to re-perform the section 7.1.1 of STP 3.8.1-01.
The following will be steps in STP 3.8.1-01.
Page 5 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 Performance Step: Step 7.1.1 a Critical Y (SEQ-) Trace an available circuit from offsite power source through the Startup transformer, (1X3), to 1A302 and 1A402.
Standard: The Candidate will trace offsite power from either:
- L1, (Hiawatha) or
- L2, (Fairfax) or
- L3, (Dysart) or
- Line, (6th Street),
to 1X3, to 1A302 and 1A402, without going through T1, or without going through the H, (0220), or I, (4290) breakers.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE, some of the breakers on the Attachment are not on 1C08, and if the candidate wants to know the position of any of these breakers he will call the Load Dispatcher.
Evaluator, role play as the Load Dispatcher and inform the candidate that the breakers that he is asking about are closed.
Page 6 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 Performance Step: Step 7.1.1 b Critical Y (SEQ-) Trace an available circuit from another offsite power source through the Standby transformer, (1X4), to 1A301 and 1A401 Standard: The Candidate will trace offsite power from either,
- L1, (Hiawatha) or
- L2, (Fairfax) or
- L3, (Dysart) or
- Line, (6th Street) or
- L6, (Hazelton) or
- L7, (Hills) to T1, to 1X4, to 1A301 and 1A401, or without going through the H, (0220), or I, (4290) breakers.
The key thing here is that NO lines use the same portion of line at any time.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE, some of the breakers on the Attachment are not on 1C08, and if the candidate wants to know the position of any of these breakers he will call the Load Dispatcher.
Evaluator, role play as the Load Dispatcher and inform the candidate that the breakers that he is asking about are closed.
Performance Step: Step 7.1.1 c Critical Y (SEQ-) Trace the connections from each Essential Bus 1A3 and 1A4 to the Startup or Standby Transformer supply breaker currently feeding the bus.
Standard: Lines will be traced from the buses 1A3 and 1A4 to the Startup transformer.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 7 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 Performance Step: Step 7.1.2 Critical Y (SEQ-) Confirm 2 independent offsite circuits are available by initialing one of the two sets of statements below and N/Aing the other.
Standard: Candidate will Initial 7.1.2a and N/A 7.1.2b.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Will sign, Date, and Time the last portion of Section 7.1.2.
Critical N (SEQ-)
Standard: Will sign, Date, and Time the last portion of Section 7.1.2.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 8 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 Performance Step: Will fill out the ACCEPTANCE CRITERIA for Section 8.0:
Critical N (SEQ-)
- 8.1, X the top box, or other and explain why he is re-performing the STP.
- 8.2, N/A.
- 8.3, X the line for 7.1 and N/A the other.
- 8.4 X, the line for 7.1 and N/A the other.
- 8.5, may write that this is a re-do of the STP. Or may leave blank.
Standard: Fill in the following for Section 8:
- 8.1, X the top box, or other and explain why he is re-performing the STP.
- 8.3, X the line for 7.1 and N/A the other.
- 8.4 X, the line for 7.1 and N/A the other.
- 8.5, may write that this is a re-do of the STP. Or may leave blank.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the Candidate states that an AR is required, Cue him that you will write the AR.
Terminating Cues: When the RO finishes with STP 3.8.1-01 and hands it back to the CRS, the JPM is over.
Stop Time:
Page 9 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 10 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 INSTRUCTOR ACTIONS:
Ensure that a copy of STP 3.8.1-01 is marked up as described below:
- General o Mark TODAY in all pages in the Performance Date blanks.
o Initial all notes and cautions in the body of the procedure.
- Prerequisites o Initial steps 6.1 and 6.2.
o X the 7.1 section
- For section 7.1 o Initial steps 7.1.1 a, b, and c.
o Initial step 7.1.2 a o N/A step 7.1.2 b o Sign and initial the Performed by section o Place the Date as SUNDAY o For the time insert 4 Xs
- For section 7.2 o N/A all of the steps
- For section 8.1 o Place an X in the Routine with both offsite circuits available section
- For section 8.2 o N/A all of the steps
- For section 8.3 o 8.3.1 mark YES and initial o 8.3.2 N/A
- For section 8.4 o 8.4.1 mark YES and initial o 8.4.2 N/A
- For section 8.5 o N/A all of the steps
- For Attachment 1 o With a blue pen, trace the lines from Power Supply Line (6th Street Sub), through T1, down through the J breaker, to 1X3 to 1A302 and 402.
o With another color, (green), trace the lines from Power Supply L7 through T1 to 1X4 to 1A 301 and 401.
o With another color, (red), tract the lines from 1A302 and 1A402 to busses 1A3 and 1A4.
Page 11 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 For the second portion of the JPM, have the following ready:
- Pictures of 1C08
- Switchyard map
- Clean copy of Attachment 1
- Three colored pens
- Straight edge Also have a clean copy of STP 3.8.1-01.
Page 12 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 Page 13 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01, Offsite Power Sources.
Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 Page 14 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01. Offsite Power Sources. Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 7510 L3 "C" Dysart Sub Power Source Breaker Transformer Bus 5950 5560 Line "AB" "K" 6th Street Sub Unacceptable path for the purposes of this STP.
4290 161KV 1A 1A "I" West Bus 301 302 345KV West Bus 2820 6780 L6 "S" "F" Hills 1A3 Sub 3110 0220 0710 8490 T1 1X4 1X3 "B" "H" "T" "M" Hazelton Sub 1A4 4730 2690 L7 "R" "D" 345KV East Bus 9180 161KV 1A 1A L1 "G" East Bus 401 402 Hiawatha Sub 8090 5550 L2 "A" "J" Fairfax Sub Page 15 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01. Offsite Power Sources. Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 TURNOVER SHEET INITIAL CONDITIONS:
The plant had been running at 100% electrical output. The 5550, K Breaker was tagged out for maintenance last Friday.
Today is Sunday, and another operator has just finished the weekly STP 3.8.1-01, Offsite Power Sources.
INITIATING CUES (IF APPLICABLE):
The CRS has directed you are to perform an independent review of STP 3.8.1-01, Offsite Power Sources.
Page 16 of 17
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.12-02, Peer check STP 3.8.1-01. Offsite Power Sources. Determine that the STP was done incorrectly. Re-performs STP, Rev. 0 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 17 of 17
3.10 CLOSURE.......................................ERROR! BOOKMARK NOT DEFINED.
3.10.2 OPERATIONS SHIFT SUPERVISOR REVIEW (1)The CRS shall review the testing requirements. If testing requirements are to be changed, obtain concurrence, as appropriate, from affected departments (i.e., Program Engineering for ASME testing and for IST Program for pumps and valves or the Fire Protection System Engineer for fire protection equipment/barriers). Note the changes in the applicable instruction of the WO, and initial and date the changes.
NOTE For Quality Level I Systems/Components, the Operations Shift Supervisor reviewing and performing the operability testing shall be different than the CRS who planned the operability testing in WO instructions.
(2)Complete the required testing and document the results on the WO. If the testing results are unsatisfactory, initiate a new WRC and document the new WRC number on the WO. Document the previous Work Order number on the new WRC. Sign and date the WO.
(3)MWOs shall be signed off coincident with the modification Operational Release. MWOs shall have the applicable Operational Release documentation (partial or full) attached at the time of CRS Review.
Operational Release Packages are prepared in accordance with ACP 109.0, "Engineering Change Packages".
(4)The WO Control Center shall update the Electronic WO System.
(5)The WO Control Center shall forward all Worker Feedback forms to Preventative Maintenance Program personnel for processing.
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS.
JPM NUMBER: 2.2.19-01 REV. 1 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 1.13 (Senior Reactor Operator)
TASK TITLE(S):
K/A NUMBERS: Generic 2.2.19 3.1 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.19-01, Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS, Rev. 1 JPM Number: 2.2.19-01 JPM
Title:
Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.19-01, Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
You are the Shift Manager.
The plant is currently in COLD S/D.
Work Order 1119782C is ready for closure.
INITIATING CUES (IF APPLICABLE):
You are to review Work Order 1119782C for closure.
Page 3 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.19-01, Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. Marked up copy of Work Order 1119782C.
General
References:
ACP 1408.1, Rev. 61 ACP 1407.3, Rev. 12 Task Standards:
- Determines that there are no initials for the QCH step 2.
- Using the ASME valve stroke time book, determines that the MO-2239 did not stroke within the ASME limits in the CLOSE direction.
- Determine that he will not sign the WO as it has not been completed satisfactorily, OR Based on the unsatisfactory stroking of the MO, he will say that he will sign the WO off and write a new WRC to fix the problem. The new WRC number should be written on the closed out WO.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Complete the required testing and document the results on the Work Order and Critical Y (SEQ-) review the following:
- All of the post testing steps are complete and signed off.
Standard: Determines that there are no initials for the QCH step 2.
Performance: SATISFACTORY UNSATISFACTORY Comments: IF the candidate says that the Work Order cannot be closed because of the initial box not being initialed, and he determines that he does not need to go on with the review, Cue him that QC has been contacted and has signed off the step as Sat..
Evaluator at this time place the QC initials, BR, in step 2 and tell the Candidate to continue with the review.
Page 4 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.19-01, Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS, Rev. 1 Performance Step: Complete the required testing and document the results on the Work Order and Critical Y (SEQ-) review the following:
- Reviews the worker comments section of the Work Order.
- Reviews that the valve stroke times are within the ASME stroke limits.
Standard: Using the ASME valve stroke time book, determines that the MO-2239 did not stroke within the ASME limits in the CLOSE direction.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note, the ASME stroke close time is 12.1 seconds. The time in the WO is 12.3.
Performance Step: Complete the required testing and document the results on the Work Order and Critical N (SEQ-) review the following:
- All of the post testing steps are complete and signed off.
Standard: Determines that step 5 should not have been signed off because the valve did not close in that allotted ASME time.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 5 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.19-01, Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS, Rev. 1 Performance Step: Complete the required testing and document the results on the Work Order and Critical Y (SEQ-) review the following:
- Reviews the worker comments section of the Work Order.
Standard: Determine that he will not sign the WO as it has not been completed satisfactorily, OR Based on the unsatisfactory stroking of the MO, he will say that he will sign the WO off and write a new WRC to fix the problem. The new WRC number should be written on the closed out WO.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete when the candidate has reviewed the WO IAW ACP 1408.1, and it is determined that a WO is not complete and MO-2239 did not meet its ASME close times.
Stop Time:
Page 6 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.19-01, Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS, Rev. 1 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 7 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.19-01, Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS, Rev. 1 INSTRUCTOR ACTIONS:
- Ensure the attached Work Order form is accurate with the most current rev of the Work Order ACP.
o When ready hand out the attached copy of the Work Order.
o There is a copy in the Simulator and Control Room.
Page 8 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.19-01, Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
You are the Shift Manager.
The plant is currently in COLD S/D.
Work Order 1119782C is ready for closure.
INITIATING CUES (IF APPLICABLE):
You are to review Work Order 1119782C for closure.
Page 9 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.2.19-01, Review a Work Order for closure IAW ACP 1408.1, WORK ORDERS, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 10 of 10
ANNUNCIATOR PANEL: 1C05A COORDINATES: D-7 REVISION: 7 DATE: 9/5/03 PAGE: 1 of 3 ROD OVERTRAVEL OUT TITLE: CONTROL ROD OVERTRAVEL 1.0 PROBABLE CAUSE(S) / INITIATING DEVICE(S) / SETPOINT(S) 1.1 Any Control Rod Relay C11A-K3A via 3 inches past full out uncoupled from its reed switches Control Rod Drive 2.0 AUTOMATIC ACTIONS 2.1 None.
3.0 OPERATOR ACTIONS 3.1 At 1C05 verify full core display, red Drift light illuminated for affected Control Rod.
3.2 Stop all intentional Control Rod Drive motion.
CAUTION If a Rod is uncoupled, it may be at any elevation in the core. A Rod Drop Accident is possible.
NOTE Because the CRD is out past position 48 for an uncoupled rod, the timer may time out before you get to position 46. It may be necessary to hold the ROD INSERT handswitch in the INSERT position until you see position 46.
3.3 If Rod is uncoupled, attempt to recouple the rod.
- b. Verify Rod Overtravel Out, 1C05A, D-7 alarm clears.
- c. Take the Rod Drift Alarm Reset/Test handswitch to Reset.
- d. Verify Rod Drift, 1C05A, D-6 alarm clears.
- e. Withdraw the associated CRD to Position 48.
(Continued)
ANNUNCIATOR PANEL: 1C05A COORDINATES: D-7 REVISION: 7 DATE: 9/5/03 PAGE: 2 of 3 3.0 OPERATOR ACTIONS (Continued)
NOTE When the Control Rod is recoupled, Rod Position will go blank momentarily, then indicate Position 48 when given a withdraw signal at Position 48.
- f. Give the associated CRD a withdraw signal and observe the CRD remains at position 48 and does not overtravel.
- g. If the Rod still overtravels, repeat Steps a through f at least 2 more times, or as directed by the CRS and Reactor Engineer.
NOTE Technical Specifications for Control Rod Operability require that an uncoupled Control Rod be fully inserted within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and disarmed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If this cannot be accomplished, the Reactor shall be in Mode 3 in the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.4 If the control rod recouples:
- a. Contact the Reactor Engineer.
- b. If in Mode 1 or 2, perform a coupling check and log the results.
- c. If in Mode 3, 4 or 5, perform STP 3.1.3-02, Control Rod Coupling Integrity Check.
- d. Evaluate the need for operational restriction on allowed position for the affected Control Rod and return to normal operation as permitted by the CRS and Operations Manager.
3.5 If the Rod cannot be recoupled:
- a. Contact the Reactor Engineer.
- b. Declare the Control Rod inoperable.
3.6 Adjust the Control Rod pattern per the Reactor Engineer's recommendations.
ANNUNCIATOR PANEL: 1C05A COORDINATES: D-7 REVISION: 7 DATE: 9/5/03 PAGE: 3 of 3 4.0 SUPPLEMENTAL ACTIONS 4.1 If due to a faulty reed switch, initiate a Work Request Card to have the faulty reed switch repaired/replaced as necessary.
4.2 Comply with the Technical Specification requirements for Control Rod Operability.
5.0 REFERENCES
5.1 APED-C11-24 <4,7>
5.2 DAEC Technical Specifications 5.3 MM 134, DCRDR 5.4 DCP 1415
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Usage Level CONTINUOUS Effective Date: __________________
Verified By: Date:
Testing and Surveillance Validated By: Date:
Operations Verified By: Date:
IST Engineer Verified By: Date:
Systems Engineering Approved By: Date:
Procedures Reviewed By: Date:
Operations Committee Approved By: Date:
DAEC Plant Manager
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
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1.0 PURPOSE 1.1 The purpose of this STP is to verify control rod operability by:
1.1.1 Inserting all partially or fully withdrawn operable control rods one notch when reactor power is greater than 10%.
1.1.2 Verifying control rod coupling integrity following insertion and restoration of fully withdrawn control rods.
1.2 This STP FULLY SATISFIES the DAEC Inservice Testing Program requirement for CRD cooling water check valves (closure exercise).
1.3 Obtain stall flows for control rod drive performance trending by System Engineering 2.0 BRIEFING INFORMATION 2.1 PERFORMANCE INFORMATION 2.1.1 Testing within this STP is organized as follows:
Section Control Rod Exercise 7.1 Control Rod Exercise For Partially Withdraw Control Rods 7.2 Control Rod Exercise For Fully Withdraw Control Rods Although these sections are independent, stand-alone procedures, if performing both Sections 7.1 and 7.2, Section 7.1 should be performed first. All steps within a particular section are to be performed in sequence and carried through to completion, unless otherwise stated.
2.1.2 All partially withdrawn operable control rods are to be tested when Section 7.1 is performed.
2.1.3 All fully withdrawn operable control rods are to be tested when Section 7.2 is performed.
2.1.4 For control rod movement associated with this STP, the Rod Worth Minimizer (RWM) is bypassed. STP 3.3.2.1-04, Control Rod Movement Verification, is NOT required to be performed if the RWM is NOT required to be operable per Technical Specifications AND a second Licensed Operator performs control rod positioning peer checking.
2.1.5 For steps confirming control rod position or indication, use of an alternate means (1C05 FULL OUT lights, rod display from computer screen, or RWM screen display) is acceptable if the FOUR ROD DISPLAY is unavailable. If an alternate means is used, the method used shall be documented in Step 8.5.
2.1.6 Personnel recommended to perform this procedure:
2 Operations
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2.2 GENERAL CAUTIONS 2.2.1 None 2.3 SPECIAL PRECAUTIONS 2.3.1 Neutron monitoring instrumentation shall be monitored during any control rod movement.
2.3.2 When exercising a rod, the time the rod is out of its AS FOUND ROD POSITION should be minimized to minimize local xenon transients which may cause unnecessary stress on the fuel clad.
3.0 REFERENCES
3.1 Applicable drawing:
3.1.1 BECH-M118 4.0 GENERAL INSTRUCTIONS 4.1 Steps marked with "TS" immediately to the right of the step number are required by Technical Specifications. If these steps do not meet their acceptance criteria or cannot be performed, a NRC reportable condition may exist and shall be reported to the Control Room Supervisor (CRS) immediately.
4.2 The CRS shall be notified immediately and the appropriate Limiting Condition for Operation section of Technical Specifications referred to whenever problems are encountered during the performance of this STP.
4.3 An Action Request (AR) should be completed for any problems encountered during the performance of TS marked items.
4.4 If any equipment or components are observed to be in a state of disrepair during the performance of this STP, appropriate corrective maintenance shall be initiated.
4.5 Proper control rod operation during control rod exercise will meet ASME requirements for CRD Cooling Water Check valve V-18-0919 (CRD-**-**) exercise test to the closed position in accordance with NRC Generic Letter 89-04, Position 7.
4.6 Prerequisite steps of this STP provide for independent verification (IV) for the identification of all withdrawn operable control rods on applicable attachments. Refer to guidelines contained in ACP 101.2, Verification Process and Self/Peer Checking Practices.
5.0 APPENDICES 5.1 None
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Prerequisites Performance Date: ____________________ INITIALS 6.0 PREREQUISITES 6.1 The following checked STP Sections are to be performed: ________
Surveillance Section 7.2 Control Rod Exercise For Fully Withdrawn Control Rods Coordinator (Perform Step 7.2.6. Do not perform Step 7.2.7 to obtain CRD stall flows.) [ ]
Section 7.2 Control Rod Exercise For Fully Withdrawn Control Rods (Perform Step 7.2.7 to obtain CRD stall flows. Do not perform Step 7.2.6.)
AND Section 7.1 Control Rod Exercise For Partially Withdrawn Control Rods [ ]
6.2 Using the Plant Process Computer, obtain an Official 3D Case Periodic Log ________
and verify that the most limiting node's MFLPD is 0.962. N/A this step if < (OPS) 20% power and 3D Monicore is not in service.
6.3 Using the Plant Process Computer, obtain an Official 3D Case Periodic Log ________
and verify that the most limiting node's MAPRAT is 0.962. N/A this step if (OPS)
< 20% power and 3D Monicore is not in service.
6.4 Using the Plant Process Computer, obtain a Rod Position Log and attach to ________
this procedure. If computer is not available, record AS FOUND ROD (OPS)
POSITION for each control rod on Attachment 1, Pre-Test Control Rod Positions.
6.5 Based on control rod positions obtained in Prerequisite 6.4, mark N/A all ________
steps on Attachment 3 for control rods that are NOT fully withdrawn and (OPS) operable.
6.6 If Section 7.1 is to be performed, based on control rod positions obtained in ________
Prerequisite 6.4, on Attachment 2 list grid coordinates and position of all (OPS) partially withdrawn operable control rods.
(IV) 6.7 Verify compensatory measures in place for RWM inoperability by one of the following (mark compensatory measure not performed as N/A):
6.7.1 STP 3.3.2.1-04, Control Rod Movement Verification, has been ________
signed on to be performed in parallel with this STP. (OPS)
OR 6.7.2 2nd Licensed Operator is assigned to perform control rod ________
positioning peer checking. (OPS)
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Performance Date: ____________________ INITIALS 7.0 PROCEDURE 7.1 CONTROL ROD EXERCISE FOR PARTIALLY WITHDRAWN CONTROL RODS NOTE All steps in this procedure are performed at 1C05 unless stated otherwise. Confirmation of step completion for each rod tested shall be indicated by placing a checkmark (for Satisfactory or Completed) or "U" (for Unsatisfactory) in the appropriate column of Attachment 2 - Step Confirmation.
7.1.1 Place the RWM Operator's Display (RWM-OD) keylock MODE ________
switch in the BYPASS position.
7.1.2 At the RWM-OD, verify the MODE display changes to BYPASS. ________
NOTE If any individual rod position is jumpered out due to an inoperable reed switch, the jumper will need to be temporarily lifted (or jumper switch opened) before exercising rod.
7.1.3 Select a partially withdrawn control rod by depressing the appropriate rod select pushbutton on ROD SELECT MATRIX and ensure white light is on for selected rod.
CAUTION Neutron monitoring instrumentation shall be monitored during any control rod movement.
CAUTION When exercising a rod, the time the rod is out of its AS FOUND ROD POSITION should be minimized to minimize local xenon transients which may cause unnecessary stress on the fuel clad.
7.1.4 Insert the selected control rod one notch and confirm the following:
- a. Rod position for the selected control rod on the FOUR ROD DISPLAY changes to the next lower latch position.
- b. Computer (if available) acknowledges the selected control rod position has changed.
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Performance Date: ____________________ INITIALS 7.1.5 Withdraw the selected control rod one notch to its AS FOUND ROD POSITION and confirm the following:
- a. Rod position for the selected control rod on the FOUR ROD DISPLAY changes to the next higher latch position.
- b. Computer (if available) acknowledges the selected control rod position has returned to AS FOUND ROD POSITION. If computer is not available, or if an individual position is unavailable due to an inoperable reed switch, have a second Licensed Operator confirm selected control rod position returned to AS FOUND ROD POSITION by comparing current position against position recorded on Attachment 1 or Rod Position Log.
7.1.6 Repeat Steps 7.1.3 through 7.1.5 for all operable partially withdrawn control rods.
7.1.7 Using the Plant Process Computer, obtain a Rod Position Log ________
and attach to this procedure OR If the computer is not available, write N/A for Steps 7.1.8 and 7.1.9 and proceed to Step 7.1.10.
7.1.8 Compare the data obtained in this scan to the scan obtained in ________
Prerequisite 6.4 and confirm that all rods are at their respective AS FOUND ROD POSITION.
7.1.9 If the computer recorded position scan check was unsatisfactory, ________
immediately notify the Control Room Supervisor and take appropriate steps to correct the discrepancy. (N/A this step if computer check was satisfactory.)
7.1.10 If the computer is not available, have a second Licensed Operator ________
confirm final rod positions are the same as the AS FOUND ROD POSITION recorded on Attachment 1 or Rod Position Log. If the check is unsatisfactory, immediately notify the Control Room Supervisor and take appropriate steps to correct the discrepancy.
(N/A step if computer is available.)
7.1.11 Place the RWM-OD keylock MODE switch in the OPERATE ________
position. (May be marked N/A if Section 7.2 is to be performed immediately after Section 7.1.)
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Performance Date: ____________________ INITIALS 7.1.12 At the RWM-OD, verify the MODE display changes to OPERATE. ________
(May be marked N/A if Section 7.2 is to be performed immediately after Section 7.1.)
Performed by Date Time Initials
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Performance Date: ____________________ INITIALS 7.2 CONTROL ROD EXERCISE FOR FULLY WITHDRAWN CONTROL RODS NOTE All steps in this procedure are performed at 1C05 unless stated otherwise. Confirmation of step completion for each rod tested shall be indicated by placing a checkmark (for Satisfactory or Completed) or "U" (for Unsatisfactory) in the appropriate column of Attachment 3 - Step Confirmation.
7.2.1 Verify the RWM Operator's Display (RWM-OD) keylock MODE ________
switch in the BYPASS position.
7.2.2 At the RWM-OD, verify the MODE display changes to BYPASS. ________
NOTE If any individual rod position is jumpered out due to an inoperable reed switch, the jumper will need to be temporarily lifted (or jumper switch opened) before exercising rod.
7.2.3 Select a fully withdrawn control rod by depressing the appropriate rod select pushbutton on ROD SELECT MATRIX and ensure white light is on for selected rod.
CAUTION Neutron monitoring instrumentation shall be monitored during any control rod movement.
CAUTION When exercising a rod, the time the rod is out of its AS FOUND ROD POSITION should be minimized to minimize local xenon transients which may cause unnecessary stress on the fuel clad.
7.2.4 Insert the selected control rod one notch and confirm the following:
- a. Rod position for the selected control rod on the FOUR ROD DISPLAY changes to position 46.
- b. Computer (if available) acknowledges the selected control rod position has changed.
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Performance Date: ____________________ INITIALS 7.2.5 Withdraw the selected control rod one notch to position 48 and confirm the following:
- a. Rod position for the selected control rod on the FOUR ROD DISPLAY changes to position 48.
- b. Computer (if available) acknowledges the selected control rod position has returned to position 48. If computer is not available, or if an individual position is unavailable due to an inoperable reed switch, have a second Licensed Operator confirm selected control rod position returned to position 48.
7.2.6 Perform a coupling check of the selected rod by applying a withdrawal signal with the ROD MOVEMENT CONTROL switch and complete the following: (Mark this step N/A if CRD stall flows are to be obtained (refer to Prerequisite 6.1).)
- a. Verify ROD OVERTRAVEL OUT annunciator (1C05A, D-7) is not activated.
- b. Confirm ROD DRIFT annunciator (1C05A, D-6) is not activated.
- c. Confirm FOUR ROD DISPLAY indication remains at position 48 (indication may go blank momentarily but should return to indicate position 48).
7.2.7 Obtain CRD stall flow by performing the following: (Mark this step N/A if CRD stall flows are NOT to be obtained (refer to Prerequisite 6.1).)
- a. Place and hold EMERGENCY IN/NOTCH OVERRIDE SELECT switch in NOTCH OVERRIDE position.
- b. Place and hold ROD MOVEMENT CONTROL switch in the ROD OUT position.
- c. Record stall flow as indicated at 1C05 on FI-1829A, DRIVE WATER FLOW.
- d. Release EMERGENCY IN/NOTCH OVERRIDE SELECT switch.
- e. Release ROD MOVEMENT CONTROL switch.
- f. Verify ROD OVERTRAVEL OUT annunciator (1C05A, D-7) is not activated.
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Performance Date: ____________________ INITIALS
- g. Confirm ROD DRIFT annunciator (1C05A, D-6) is not activated.
- h. Confirm FOUR ROD DISPLAY indication remains at position 48 (indication may go blank momentarily but should return to indicate position 48).
7.2.8 Repeat Steps 7.2.3 through 7.2.7 for all operable fully withdrawn control rods.
7.2.9 Using the Plant Process Computer, obtain a Rod Position Log ________
and attach to this procedure OR If the computer is not available, write N/A for Steps 7.2.10 and 7.2.11 and proceed to Step 7.2.12.
7.2.10 Compare the data obtained in this scan to the scan obtained in ________
Prerequisite 6.4 and confirm that all rods are at their respective AS FOUND ROD POSITION.
7.2.11 If the computer recorded position scan check was unsatisfactory, ________
immediately notify the Control Room Supervisor and take appropriate steps to correct the discrepancy. (N/A this step if computer check was satisfactory.)
7.2.12 If the computer is not available, have a second Licensed Operator ________
confirm final rod positions are the same as the AS FOUND ROD POSITION recorded on Attachment 1 or Rod Position Log. If the check is unsatisfactory, immediately notify the Control Room Supervisor and take appropriate steps to correct the discrepancy.
(N/A step if computer is available.)
7.2.13 Place the RWM-OD keylock MODE switch in the OPERATE ________
position.
7.2.14 At the RWM-OD, verify the MODE display changes to OPERATE. ________
Performed by Date Time Initials
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
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Performance Date: ____________________ INITIALS
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
12 of 20 7
Performance Date: ____________________ INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 If this STP is performed for any reason other than for satisfying the PURPOSE as stated in Section 1.0, indicate below (otherwise mark this step "N/A"):
8.2 If a DCF, Procedure Work Request (PWR), or Action Request (AR) was written due to problems encountered with the performance of this procedure, list the applicable number(s) below and attach a copy of each to this procedure. ("N/A" blocks as appropriate.)
DCF No. ___________ PWR No. ___________ AR No. __________
DCF No. ___________ PWR No. ___________ AR No. __________
8.3 All Technical-Specification-required items (as indicated by "TS") have been performed satisfactorily.
Section 7.1 ( ) YES ( ) NO CRS notified ________
Section 7.2 ( ) YES ( ) NO CRS notified ________
8.4 All other items checked in this test have been performed satisfactorily.
Section 7.1 ( ) YES ( ) NO CRS notified ________
Section 7.2 ( ) YES ( ) NO CRS notified ________
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
13 of 20 7
Performance Date: ____________________ INITIALS 8.5 Indicate any relevant test comments below (otherwise mark this step "N/A"):
Operations Date Surveillance Coordinator Date 9.0 ATTACHMENTS 9.1 Attachment 1 - Pre-Test Control Rod Positions 9.2 Attachment 2 - Step Confirmation - Partially Withdrawn Control Rods 9.3 Attachment 3 - Step Confirmation - Fully Withdrawn Control Rods
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
14 of 20 7
Attachment - 1 PRE-TEST CONTROL ROD POSITIONS Sheet 1 of 1 AS FOUND AS FOUND AS FOUND AS FOUND GRID GRID GRID GRID ROD ROD ROD ROD COORDINATE COORDINATE COORDINATE COORDINATE POSITION POSITION POSITION POSITION 18 - 03 22 - 15 30 - 23 38 - 31 22 - 03 26 - 15 34 - 23 06 - 35 26 - 03 30 - 15 38 - 23 10 - 35 10 - 07 34 - 15 42 - 23 14 - 35 14 - 07 38 - 15 02 - 27 18 - 35 18 - 07 02 - 19 06 - 27 22 - 35 22 - 07 06 - 19 10 - 27 26 - 35 26 - 07 10 - 19 14 - 27 30 - 35 30 - 07 14 - 19 18 - 27 34 - 35 34 - 07 18 - 19 22 - 27 38 - 35 06 - 11 22 - 19 26 - 27 10 - 39 10 - 11 26 - 19 30 - 27 14 - 39 14 - 11 30 - 19 34 - 27 18 - 39 18 - 11 34 - 19 38 - 27 22 - 39 22 - 11 38 - 19 42 - 27 26 - 39 26 - 11 42 - 19 06 - 31 30 - 39 30 - 11 02 - 23 10 - 31 34 - 39 34 - 11 06 - 23 14 - 31 18 - 43 38 - 11 10 - 23 18 - 31 22 - 43 06 - 15 14 - 23 22 - 31 26 - 43 10 - 15 18 - 23 26 - 31 14 - 15 22 - 23 30 - 31 18 - 15 26 - 23 34 - 31
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
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STEP CONFIRMATION - PARTIALLY Attachment - 2 Sheet 1 of 1 WITHDRAWN CONTROL RODS AS FOUND 7.1.3 7.1.4 7.1.5 GRID ROD a a INITIALS COORDINATE b b POSITION TS TS
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
16 of 20 7
Attachment - 3 STEP CONFIRMATION - FULLY WITHDRAWN CONTROL RODS Sheet 1 of 5 7.2.3 7.2.4 7.2.5 7.2.6 7.2.7 INITIALS GRID COORDINATE a a a f b b b c a b c d e g h TS TS TS TS 18 - 03 22 - 03 26 - 03 10 - 07 14 - 07 18 - 07 22 - 07 26 - 07 30 - 07 34 - 07 06 - 11 10 - 11 14 - 11 18 - 11 22 - 11 26 - 11 30 - 11 34 - 11 38 - 11
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
17 of 20 7
Attachment - 3 STEP CONFIRMATION - FULLY WITHDRAWN CONTROL RODS Sheet 2 of 5 7.2.3 7.2.4 7.2.5 7.2.6 7.2.7 INITIALS GRID COORDINATE a a a f b b b c a b c d e g h TS TS TS TS 06 - 15 10 - 15 14 - 15 18 - 15 22 - 15 26 - 15 30 - 15 34 - 15 38 - 15 02 - 19 06 - 19 10 - 19 14 - 19 18 - 19 22 - 19 26 - 19 30 - 19 34 - 19 38 - 19 42 - 19
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
18 of 20 7
Attachment - 3 STEP CONFIRMATION - FULLY WITHDRAWN CONTROL RODS Sheet 3 of 5 7.2.3 7.2.4 7.2.5 7.2.6 7.2.7 INITIALS GRID COORDINATE a a a f b b b c a b c d e g h TS TS TS TS 02 - 23 06 - 23 10 - 23 14 - 23 18 - 23 22 - 23 26 - 23 30 - 23 34 - 23 38 - 23 42 - 23 02 - 27 06 - 27 10 - 27 14 - 27 18 - 27 22 - 27 26 - 27 30 - 27 34 - 27 38 - 27 42 - 27
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
19 of 20 7
Attachment - 3 STEP CONFIRMATION - FULLY WITHDRAWN CONTROL RODS Sheet 4 of 5 7.2.3 7.2.4 7.2.5 7.2.6 7.2.7 INITIALS GRID COORDINATE a a a f b b b c a b c d e g h TS TS TS TS 06 - 31 10 - 31 14 - 31 18 - 31 22 - 31 26 - 31 30 - 31 34 - 31 38 - 31 06 - 35 10 - 35 14 - 35 18 - 35 22 - 35 26 - 35 30 - 35 34 - 35 38 - 35
SURVEILLANCE TEST PROCEDURE STP 3.1.3-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: CONTROL ROD EXERCISE Page Rev.
20 of 20 7
Attachment - 3 STEP CONFIRMATION - FULLY WITHDRAWN CONTROL RODS Sheet 5 of 5 7.2.3 7.2.4 7.2.5 7.2.6 7.2.7 INITIALS GRID COORDINATE a a a f b b b c a b c d e g h TS TS TS TS 10 - 39 14 - 39 18 - 39 22 - 39 26 - 39 30 - 39 34 - 39 18 - 43 22 - 43 26 - 43
QF-1030-11 Rev. 1 (FP-T-SAT-30)
SITE: DAEC TASK TITLE: Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD.
JPM NUMBER: 201003-06 REV. 1 RELATED PRA INFORMATION:
TASK NUMBERS: 99.14 K/A NUMBERS: 201003 A2.02 (3.7/3.8)
APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 30 Minutes Time Critical: NO Alternate Path / Faulted: YES TASK APPLICABILITY: SRO/RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 JPM Number: 201003-06 JPM
Title:
Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
- The reactor is at power.
- STP 3.1.3-01, CONTROL ROD EXERCISE, for Section 7.2 is due.
- All of the prerequisites are signed for the performance of section 7.2, CONTROL ROD EXERCISE FOR FULLY WITHDRAWN CONTROL RODS.
- Further, in section 7.2, you will not perform step 7.2.7 as stall flows are not required.
- The crew has started the STP and has completed the first two rods, 18-03 and 22-03.
- You are an extra Licensed Operator that the WCC has sent to the control room to continue with the STP so the crew can carry out other responsibilities.
INITIATING CUES (IF APPLICABLE):
- For this JPM assume the following:
o All of the Prerequisites are CORRECT and COMPLETE.
o You have been given a full pre-job brief and rod movement brief IAW IPOI 3.
o The RWM is bypassed.
- For this JPM, I will be performing the task as Peer Checker and RWM, however it must be stated that I will only repeat your statement. This is a test of your ability to carry out this task.
- The CRS directs you to perform section 7.2 of STP starting with Rod 26-03 and continuing through rod 22-07. (5 control rods)
NOTE: If the student does not feel comfortable performing this evolution without a rod movement brief, then give the following brief from IPOI 3 P & L 15, Rev. 66.
- The Operations SM/CRS and Control Room Operator shall review the rod group and their insert/withdraw limit. For this event, the insert is 46 and the withdraw is 48.
Page 3 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1
- The Operations SM/CRS shall conduct a pre-rod movement briefing which should include discussion about:
o Operations SM/CRSs responsibility and authority with respect to control of the reactor core and reactivity changes.
o Purpose of the rod movement is to perform STP 3.1.3-01, Control Rod Exercise.
o Monitoring thermal limits; if the rods are moved IAW the STP, the thermal limits will not be challenged.
o Rod Worth Minimizer will be bypassed for this event. A second licensed operator will be assigned to peer check you. This will be performed by the evaluator for this event.
o In the simulator, Feedwater Correction Factor Status (FWFLAG, FWCF A[B], and FWALM) is not in service.
o Maintain attention to detail.
o Causes of previous rod mispositioning events. Discuss that during a previous rod pull two pages of the pull sheet stuck together. This led to control rods being withdrawn out of sequence.
o Operator alertness, if you get tired inform the CRS.
o Inform the CRS of Expected alarms and proper responses.
o Approval of changes to evolutions, if needed must go through the CRS and an RE.
o Communications from Reactor Engineers regarding the reactor core shall not explicitly direct Operations actions. Operator actions shall be directed by Operations SM/CRS. {C003}
Page 4 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. Copy of marked up STP 3.1.3-01, CONTROL ROD EXRECISE.
- 2. NOTE to Driver. When control rod 10-07 is moved to position 46, event trigger 1 will go to true. This will cause the rod over travel Malfunction for rod 10-07.
General
References:
IPOI 3, Rev. 66 ARP 1C05A [D-7], Rev. 7 STP 3.1.3-01, Rev. 7 Task Standards:
- The operator selects rod 10-07 and white light is on.
- Rod 10-07 is driven in to position 46 and 4-rod display and the computer indicates 46.
- Rod 10-07 is withdrawn one notch to position 48.
- Per ARP, the control rod is inserted to position 46.
- Inform the CRS that the ARP says to declare the control rod inoperable.
- Candidate inserts rod 10-07 form over travel to full in.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Note: There are no expected actions for ARP 1C05A (D-6).
If the candidate states that he will place borders on the expected annunciators, inform the Candidate that you understand that this is an expected action at DAEC, but for the purposes of this JPM. Simulate hanging the borders.
Page 5 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 Performance Step: At Panel 1C05 select a fully withdrawn control rod by depressing the Critical N (SEQ-) appropriate rod select pushbutton on ROD SELECT MATRIX, 26-03, and ensure white light is on for selected rod.
Standard: The operator selects rod 26-03 and white light is on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Insert the selected control rod one notch and confirm the following:
Critical N (SEQ-)
- Rod position for the selected control rod on the FOUR ROD DISPLAY changes to position 46.
- Computer (if available) acknowledges the selected control rod position has changed.
Standard: Rod 26-03 is driven in to position 46 and 4 rod display and the computer indicates 46.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Withdraw the selected control rod one notch to position 48 and confirm the Critical N (SEQ-) following:
- Rod position for the selected control rod on the FOUR ROD DISPLAY changes to position 48.
- Computer (if available) acknowledges the selected control rod position has returned to position 48.
Standard: Rod 26-03 is withdrawn to position 48 and 4 rod display and the computer indicates 48.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that when the control rod is at position 48, the computer indication is blank.
Page 6 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 Performance Step: Perform a coupling check by applying a withdrawal signal to the selected Critical N (SEQ-) control rod and perform the following:
- Verify ROD OVERTRAVEL OUT annunciator (1C05A, D-7) is not activated.
- Confirm ROD DRIFT annunciator (1C05A, D-6) is not activated.
- Confirm FOUR ROD DISPLAY indication remains at position 48 (indication may go blank momentarily but should return to indicate position 48).
Standard:
- ROD OVERTRAVEL OUT annunciator (1C05A, D-7) does not activate.
- ROD DRIFT annunciator (1C05A, D-6) does not activate.
- FOUR ROD DISPLAY indication remains at position 48.
Performance: SATISFACTORY UNSATISFACTORY Comments: At this point the student will finish signing Attachment 3 and move on to rod 10-07.
Performance Step: At Panel 1C05 select a fully withdrawn control rod by depressing the Critical Y (SEQ-) appropriate rod select pushbutton on ROD SELECT MATRIX, 10-07, and ensure white light is on for selected rod.
Standard: The operator selects rod 10-07 and white light is on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 7 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 Performance Step: Insert the selected control rod one notch and confirm the following:
Critical Y (SEQ-)
- Rod position for the selected control rod on the FOUR ROD DISPLAY changes to position 46.
- Computer (if available) acknowledges the selected control rod position has changed.
Standard: Rod 10-07 is driven in to position 46 and 4-rod display and the computer indicates 46.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Note to driver:
When 10-07 is moved to position 46, you must verify the following:
Verify that event trigger 1 goes true and IMF RD-31007 goes active.
This will cause rod 10-07 to over travel when it returns to position 48.
Performance Step: Withdraw the selected control rod one notch to position 48 and confirm the Critical Y (SEQ-) following:
Note - rod will not stop at 48.
Standard: The Candidate will apply a Notch Out signal to rod 10-07.
Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE to Evaluator.
With the over travel malfunction in, Control Rod 10-07 will not stop at position 48, it will pass through 48 to the over travel position.
NOTE to Evaluator:
The next steps will be based on the Rod Overtravel Out alarm.
Page 8 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 Performance Step: The Candidate will acknowledge to the following alarms:
Critical N (SEQ-)
- ROD OVERTRAVEL OUT annunciator (1C05A, D-7).
- ROD DRIFT annunciator (1C05A, D-6).
Standard: Candidate will respond to the following alarms:
- ROD OVERTRAVEL OUT annunciator (1C05A, D-7).
- ROD DRIFT annunciator (1C05A, D-6).
Performance: SATISFACTORY UNSATISFACTORY Comments: When the over travel annunciator annunciates, the student should report that there is an over travel alarm on rod 10-07.
When reported, and if asked, tell the student to stop the STP and to perform the appropriate ARPs.
Performance Step: The operator will review ARP 1C05A [D-6], ROD DRIFT and determine that Critical N (SEQ-) there are no applicable actions from this ARP.
Standard: ARP 1C05A [D-6], ROD DRIFT is reviewed and determined that no applicable actions are required.
Performance: SATISFACTORY UNSATISFACTORY The operator may state that the ROD DRIFT is caused by the ROD Comments: OVERTRAVEL OUT. This is satisfactory for completion of this step.
If the student states that the ARP says we must enter AOP 255.1, Cue him that another operator will enter the AOP and perform the applicable actions, and he is to carry-on with his ARP actions.
Performance Step: Per ARP 1C05A [D-7], Rod OVERTRAVEL OUT, Critical N (SEQ-) At Panel 1C05 verify full core display, red Drift light illuminated for affected Control Rod.
Standard: The operator determines that the drift light is on.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 9 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 Performance Step: Stop all intentional control rod movement.
Critical N (SEQ-)
Standard: The operator has stopped all intentional control rod movement.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: If Rod is uncoupled, attempt to re-couple the rod by performing the following:
Critical Y (SEQ-)
Standard: The CRD is inserted to Position 46.
Performance: SATISFACTORY UNSATISFACTORY Cue: The RE and CRS concur with inserting the control rod to Position 46, if Comments: asked.
Performance Step: If Rod is uncoupled, attempt to re-couple the rod by performing the following:
Critical N (SEQ-)
- Verify Rod Overtravel Out, 1C05A, D-7 alarm clears.
- Take the Rod Drift Alarm Reset/Test handswitch to Reset.
- Verify Rod Drift, 1C05A, D-6 alarm clears.
Standard: Rod Overtravel Out, 1C05A, D-7 alarm is verified cleared and the rod drift alarm is reset and clears.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 10 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 Performance Step: Withdraw the CRD to position 48.
Critical Y (SEQ-)
Standard: The Candidate will apply a Notch Out signal to rod 10-07.
Performance: SATISFACTORY UNSATISFACTORY The control rod will not settle at Position 48 and the over travel alarm will Comments: annunciate.
Performance Step: If the rod still overtravels, repeat Steps a through f at least two more times, or Critical N (SEQ-) as directed by the CRS and Reactor Engineer.
Standard: The operator repeats Steps a through f two more times.
Performance: SATISFACTORY UNSATISFACTORY Cue: The RE and CRS direct that Steps a through f be repeated one more Comments: time. [The Rod should not re-couple.]
The following steps are the repeating of steps a through f from the above step.
Performance Step: If the rod is uncoupled, attempt to insert the associated CRD to Position 46 or Critical Y (SEQ-) as directed by the CRS and Reactor Engineer.
Standard: The CRD is inserted to Position 46.
Performance: SATISFACTORY UNSATISFACTORY Cue: The RE and CRS concur with inserting the control rod to Position 46, if Comments: asked.
Page 11 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 Performance Step: If Rod is uncoupled, attempt to re-couple the rod by performing the following:
Critical N (SEQ-)
- Verify Rod Overtravel Out, 1C05A, D-7 alarm clears.
- Take the Rod Drift Alarm Reset/Test handswitch to Reset.
- Verify Rod Drift, 1C05A, D-6 alarm clears.
Standard: Rod Overtravel Out, 1C05A, D-7 alarm is verified cleared and the rod drift alarm is reset and clears.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Withdraw the CRD to position 48.
Critical Y (SEQ-)
Standard: The Candidate will apply a Notch Out signal to rod 10-07.
Performance: SATISFACTORY UNSATISFACTORY The control rod will not settle at Position 48 and the over travel alarm will Comments: annunciate.
Performance Step: If the rod cannot be recoupled:
Critical N (SEQ-)
- Contact the Reactor Engineer.
Standard: Inform the CRS to contact the RE.
Performance: SATISFACTORY UNSATISFACTORY Comments: Cue the Candidate that you will contact the RE.
Page 12 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 Performance Step: If the rod cannot be recoupled:
Critical Y (SEQ-)
- Declare the control rod inoperable.
Standard: Inform the CRS that the ARP says to declare the control rod inoperable.
Performance: SATISFACTORY UNSATISFACTORY Comments: When informed that the rod must be declared inoperable, Cue the candidate that you will work on declaring the control rod inoperable.
Performance Step: If the rod cannot be recoupled:
Critical N (SEQ-)
Standard: Candidate will inform the CRS that the ARP states to fully insert the control rod.
Performance: SATISFACTORY UNSATISFACTORY Comments: When informed that the ARP directs that the control rod be fully inserted, Cue: The candidate that the RE and you agree the control rod be fully inserted.
Cue him that the RE has determined that this rod is to be driven in using the Continuous In method of driving control rods.
Performance Step: IAW ARP. The Candidate will fully insert the associated CRD Critical Y (SEQ-)
Standard: Candidate inserts rod 10-07 from over travel to full in.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 13 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 Performance Step: If the rod cannot be recoupled:
Critical N (SEQ-)
Standard: The following either performed or stated:
- Direction to disarm the affected CRD.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Cue: The candidate that another operator will perform the Actions of OI 255 to electrically disarm the control rod.
Terminating Cues: The affected rod is fully inserted and, associated indications properly reflect the rod status.
Stop Time:
Page 14 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 SIMULATOR SET UP: IC-2 EVENT TRIGGERS:
Trigger Number Trigger Logic Statement Trigger Word Description 1 rdsblpos(4) .le. 184 Control rod 10-07 at position 46 SIMULATOR MALFUNCTIONS:
TIME MALFUNCTION MALFUNCTION ET DELAY F. SEV. RAMP I. SEV.
No. TITLE 0 RD031007 Rod uncoupled 1 SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None SIMULATOR PREPARATIONS:
- Have a Rod Display, (DR), up on one of the CRTs.
- Bypass the RWM.
- Select control rod 22-03 on the Rod Select Matrix to coincide with the last control rod tested.
INSTRUCTOR ACTIONS:
- 1. Mark up STP 3.1.3-01, Control Rod Exercise, as follows,
- Prerequisites filled out for the performance of Section 7.2 only.
- Section 7.1 for Partially Withdrawn Control Rods is N/Aed.
- In Section 7.2 perform the following:
o Initial steps 7.2.1 and 7.2.2.
- N/A Attachments 1 and 2
- For Attachment 3 perform the following:
o For control rods 18-03 and 22-03 perform the following:
Check of boxes for 7.2.3, 7.2.4, 7.2.5, and 7.2.6.
N/A the boxes for 7.2.7.
Initial the INITIALS box for rods 18-03 and 22-03.
N/A the entire row for rods 18-11 and 26-11.
Page 15 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1
- Have the simulator in run and type in run3d at a terminal.
- 3. Print out a Control Rod Positions sheet.
- Have the simulator in run and type in rodlog at the terminal.
- 4. Read initial conditions and initiating cues to the operator.
Page 16 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
- The reactor is at power.
- STP 3.1.3-01, CONTROL ROD EXERCISE, for Section 7.2 is due.
- All of the prerequisites are signed for the performance of section 7.2, CONTROL ROD EXERCISE FOR FULLY WITHDRAWN CONTROL RODS.
- Further, in section 7.2, you will not perform step 7.2.7 as stall flows are not required.
- The crew has started the STP and has completed the first two rods, 18-03 and 22-03.
- You are an extra Licensed Operator that the WCC has sent to the control room to continue with the STP so the crew can carry out other responsibilities.
INITIATING CUES (IF APPLICABLE):
- For this JPM assume the following:
o All of the Prerequisites are CORRECT and COMPLETE.
o You have been given a full pre-job brief and rod movement brief IAW IPOI 3.
o The RWM is bypassed.
- For this JPM, I will be performing the task as Peer Checker and RWM, however it must be stated that I will only repeat your statement. This is a test of your ability to carry out this task.
- The CRS directs you to perform section 7.2 of STP starting with Rod 26-03 and continuing through rod 22-07. (5 control rods)
Page 17 of 18
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 201003-06, Perform A CONTROL ROD DRIVE EXERCISE, Alternate Path to CARRY OUT REQUIRED ACTIONS FOR AN UNCOUPLED CONTROL ROD, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 18 of 18
QF-1030-11 Rev. 2 (FP-T-SAT-30)
SITE: DAEC JPM TITLE: Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job.
JPM NUMBER: 2.3.10-01 REV. 1 RELATED PRA INFORMATION:
TASK NUMBER(S)/ 96.05 (Reactor Operator)
TASK TITLE(S):
K/A NUMBERS: Generic 2.3.10 2.9 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 25 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: RO Additional signatures may be added as needed.
Developed by:
Wayne Render, Instructor Date Validated by:
Validation Instructor Date (See JPM Validation Checklist, Attachment 1)
Approved by:
Training Supervisor-Operations Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.3.10-01, Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job, Rev. 1 JPM Number: 2.3.10-01 JPM
Title:
Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: UNSAT:
COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.3.10-01, Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job, Rev. 1 JPM BRIEFING/TURNOVER Use OTI 105 Attachment 6, DAEC Walkthrough Exam Briefing Checklist, to conduct the JPM Briefing.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The plant is operating at about 60% power.
You have 2 tasks to perform in the heater bay.
- The first job is to close 3 valves to isolate LT1065B, level transmitter to the drain valve of 1T93A Moisture Separator Drain Tank that controls the Drain to the 1E-05A heater, and 2 valves to vent and drain the LT line.
- Scaffolding has been erected around the work site to allow access to the valves.
- The Scaffolding has been erected at location 5 on Survey Map 05-023.
- The decision has been made to go in and isolate Level Transmitter 1065B.
- You are the RO who will hang the tags to isolate LT 1065B.
- There are 5 valves to manipulate. Assume that each valve will take about 5 minutes to reposition and tag.
- A hose has been attached to the drain line of LT 1065B.
- The second job is to check the outer Steam Tunnel access door.
- A work request card was put in on the door because it was hard to open.
- The door has been fixed and you are to enter the Steam tunnel air lock and exit the air lock a couple of times to verify that the door opens easily and closes fully.
- The job duration is expected to take 7 minutes.
INITIATING CUES (IF APPLICABLE):
Given a Duane Arnold survey map and the applicable RWP, the Shift Manager wants you to determine the following:
- The specific dose for each job in the Heater Bay.
- Show your work on the Survey Map.
Page 3 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.3.10-01, Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job, Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: 1. RWP 10 Job step 7
- 2. Survey map of the Heater Bay at 61% power.
- 3. Section tagout for LT1065B-RO
- 4. Calculator General
References:
Task Standards:
- Determines that the total dose for the first job is 87.5 mrem.
- Determines that the total dose for the second job is 28 mrem.
- Determine that dose of 110 mrem is too low for the job.
- Determine that the Dose Rate on the RWP is not set too low.
Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).
NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.
Performance Step: Calculates the dose for hanging the tags to isolate LT-1065B. (Job #1)
Critical Y (SEQ-)
Standard: Determines that the total dose for the job is 87.5 mrem (plus or minus 1 mrem).
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that this dose is calculated from area 5 on the survey map, (210).
Note that the Candidate may add some additional dose for transient to and from the work area.
Page 4 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.3.10-01, Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job, Rev. 1 Performance Step: Calculates the dose for exercising the Steam Tunnel air lock. (Job #2)
Critical Y (SEQ-)
Standard: Determines that the total dose for the job is 28 mrem.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that this dose is calculated from area 2 on the survey map, (240).
Note that the Candidate may add some additional dose for transient to and from the work area.
Performance Step: Compares the total dose for the job, [115.5] to the RWP ED alarm set point, Critical Y (SEQ-) [110].
Standard: Determines that the job dose is not high enough to complete the job.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that the Candidate may add additional dose on to the totals for traveling to and from job site. This is good but not necessary to determine that the dose amount on the RWP is not enough to cover the job.
Performance Step: Reviews the Dose Rate for the jobs to be done.
Critical Y (SEQ-)
Standard: Determines that the dose rate is adequate for the working areas.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note that the Candidate may discuss that the HP will state that he can expect to get High Dose Rate alarms while going to and from the job.
Failure criteria for this step is if the Candidate states that the Dose Rate set at 400 is too low based on going through areas with readings of 720 mrem.
Page 5 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.3.10-01, Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job, Rev. 1 Terminating Cues: The JPM is complete when the candidate has determined the dose at each job, determined that the dose on the RWP is too low, and determined that the Dose rate setting is satisfactory.
Stop Time:
Page 6 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.3.10-01, Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job, Rev. 1 SIMULATOR SET UP:
None EVENT TRIGGERS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 7 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.3.10-01, Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job, Rev. 1 INSTRUCTOR ACTIONS:
- Ensure that there is a copy of RWP 10 with the following:
o Dose filled in at 110 mrem.
o Dose Rate filled in at 400 mrem/hr.
o There is a copy attached to the JPM.
- Ensure that there is a copy a Duane Arnold Energy Center HP Survey map of the Heater Bay.
- Ensure that a copy of the Tag out sheet for LT-1065B is attached.
At the time of the JPM hand out the RWP 10, the HP Survey Map, and the tag out sheet for LT-1065B.
Page 8 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.3.10-01, Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job, Rev. 1 TURNOVER SHEET The plant is operating at about 60% power.
You have 2 tasks to perform in the heater bay.
- The first job is to close 3 valves to isolate LT1065B, level transmitter to the drain valve of 1T93A Moisture Separator Drain Tank that controls the Drain to the 1E-05A heater, and 2 valves to vent and drain the LT line.
- Scaffolding has been erected around the work site to allow access to the valves.
- The Scaffolding has been erected at location 5 on Survey Map 05-023.
- The decision has been made to go in and isolate Level Transmitter 1065B.
- You are the RO who will hang the tags to isolate LT 1065B.
- There are 5 valves to manipulate. Assume that each valve will take about 5 minutes to reposition and tag.
- A hose has been attached to the drain line of LT 1065B.
- The second job is to check the outer Steam Tunnel access door.
- A work request card was put in on the door because it was hard to open.
- The door has been fixed and you are to enter the Steam tunnel air lock and exit the air lock a couple of times to verify that the door opens easily and closes fully.
- The job duration is expected to take 7 minutes.
INITIATING CUES (IF APPLICABLE):
Given a Duane Arnold survey map and the applicable RWP, the Shift Manager wants you to determine the following:
- The specific dose for each job in the Heater Bay.
- Show your work on the Survey Map.
Page 9 of 10
QF-1030-11 Rev. 2 (FP-T-SAT-30) 2.3.10-01, Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job, Rev. 1 ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date.
Validation Personnel /Date Validation Personnel/Date Page 10 of 10