ML051320295
| ML051320295 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/28/2004 |
| From: | Hynes C FirstEnergy Nuclear Operating Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-334/01-302, ES-C-1 50-334/05-301 | |
| Download: ML051320295 (38) | |
Text
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
BVPS Unit 1 Task No.: 0481 -01 4-03-01 3 Task
Title:
Perform RCS Cooldown Verification JPM No.:
2005 NRC RO Admin No. 1 WA
Reference:
2.1.25 (2.8)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testinq Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
A plant shutdown to Mode 5 is in progress.
Current RCS wide range temperature and pressure are 238°F and 1,220 psig respectively.
Data Sheet 3: RCS Cooldown Determination is in effect to track RCS cooldown limits per 1 OM-52.4.NR.l.F, Non-Refueling Station Shutdown From 100% Power To Mode 5.
Task Standard:
RCS cooldown rate calculated and verified NOT to be within acceptable limits.
Required Materials:
Calculator General
References:
1 OM-52.4.NR.1.F, Non-Refueling Station Shutdown From 100% Power To Mode 5, Rev. 6 Handouts:
Data Sheet 3: RCS Cooldown Determination (Modified with entries) 1 OM-52.4.NR.1.F, Attachment 13: RCS/PRZR COOLDOWN SURVEILLANCE Figure 51 -2, Beaver Valley Unit 1 Reactor Coolant System Cooldown Limitations Initiating Cue:
The Unit Supervisor directs you to complete the information required for the 1 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> entry of Data Sheet 3, RCS Cooldown Determination and verify the RCS cooldown is within acceptable limits using Attachment 13, RCS/PRZR Cooldown Surveillance. Report your results when finished.
Time Critical Task:
No Validation Time:
9 minutes BVPS-1 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Page 2 of 5 Form ES-C-1 2005 NRC ADMIN NO. 1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
4 Performance Step: 1 Calculate the RCS cooldown rate at least once per 30 minutes during system cooldown using the following equation AND Record the results on Data Sheet 3:
COOLDOWN RATE = [TEMPf -TEMPI) X 60 MIN/HR (Step 1)
CHANGE IN TIME Standard:
Candidate correctly calculates current RCS cooldown rate as SOF/hr 1238°F - 263°F) x 60 = - 50°F 30 Comment :
Performance Step: 2 Verify the RCS cooldown rate is I 100 WHR at least once per 30 minutes during system cooldown.
W P
- 1)
Standard:
Com men t :
BVPS-1 NRC ADMIN NO. 1 Candidate determines RCS cooldown rate is within the acceptable limit of less than or equal to 1 OOG/hr.
NUREG 1021, Revision 9
Appendix C Page 3 of 5 Form ES-C-1 2005 NRC ADMIN NO. 1 PERFORMANCE INFORMATION
,/
Performance Step: 3 Verify temperature [TR-1 RC-4101 OR (T0406A, T0426A, T0446A) AND
[PR-1 RC-4031, RCS Pressure (P0499A) are WITHIN the Acceptable Operation region of 1 OM-51.5, Figure 51 -2, "Beaver Valley Unit 1 Reactor Coolant System Cooldown Limitations", at least once per 30 minutes during system cooldown AND Record the results on Data Sheet 3.
Candidate determines that current RCS temperature and pressure are NOT within the acceptable region of Figure 51 -2.
Candidate reports the results to the Unit Supervisor.
(Step 1)
Standard:
Standard:
Comment:
Terminating Cue:
When the Candidate reports the results of the cooldown determination, the evaluation for this JPM is complete.
STOP TIME:
BVPS-1 NRC ADMlN NO. 1 NUREG 1021, Revision 9
Appendix C Page 4 of 5 Form ES-C-1 2005 NRC ADMIN NO. 1 VERIFICATION OF COMPLETION JPM No.:
2005 NRC RO No. 1 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's Signature:
Date:
BVPS-1 NRCADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Page 5 of 5 Form ES-C-1 2005 NRC ADMIN NO. 1 JPM CUE SHEET INITIAL CONDITIONS:
. A plant shutdown to Mode 5 is in progress Current RCS wide range temperature and pressure are 238°F and 1,220 psig respectively.
Data Sheet 3: RCS Cooldown Determination is in effect to track RCS cooldown limits per 1 OM-52.4.NR.1.F, Non-Refueling Station Shutdown From 100% Power To Mode 5.
INITIATING CUE:
The Unit Supervisor directs you to complete the information required for the 1100 hour0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> entry of Data Sheet 3, RCS Cooldown Determination and verify the RCS cooldown is within acceptable limits using Attachment 13, RCS/PRZR Cooldown Surveillance. Report your results when finished.
BVPS-1 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
BVPS Unit 1 Task No.: 001 1-003-01-013 Task
Title:
Perform an Estimated Critical Position JPM No.:
2005 NRC RO Calculation Admin No. 2 WA
Reference:
192008 K1.07 (3.5) 2.1.23 (3.9)
NRC Examiner:
Date:
Examinee:
Facility Evaluator:
Method of testinq:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
Genera I References :
Handouts:
Initiating Cue:
Time Critical Task:
Validation Time:
A plant startup is being performed 5 days after a reactor trip from 100% power.
Core burnup is 1,000 MWDIMTU.
RCS boron concentration is 1337 ppm.
The plant computer is NOT available.
Estimated critical boron concentration calculated within the specified tolerance and error(s) identified.
Calculator; Evaluator ECP Answer Sheet 1 OM-50.4.F, Performing An Estimated Critical Position Calculation, Rev. 3 BV-1 Curve Book 10M-50.4.F, with Critical Data recorded in DATA SHEET 1 BV-1 Curves CB-I 2, 21, 22, 23, 24A - C, 29 The Unit Supervisor directs you to perform a review of an ECP calculation and determine that the critical boron concentration is correct using 1 OM-50.4.F, Performing An Estimated Critical Position Calculation.
No 15 minutes BVPS-1 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 2005 NRC ADMIN NO. 2 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
.(
Performance Step: 1 Calculate ECP.
(Data Sheet 1)
Standard:
Candidate correctly determines critical boron concentration using 1 OM-50.4.F within f 5 ppm.
Standard:
Candidate correctly identifies errors as noted on Evaluator's ECP Answer Sheet.
Comment:
Terminating Cue:
When the Candidate completes the calculation, the evaluation for this JPM is complete.
STOP TIME:
BVPS-1 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Page 3 of 4 Form ES-C-1 2005 NRC ADMIN NO. 2 VERIFICATION OF COMPLETION JPM No.:
Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
2005 NRC RO No. 2
Response
~~
~
~
~~~
~
Result: SatisfactoryAJnsatisfactory Examiner's Signature:
Date:
BVPS-1 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Page 4 of 4 Form ES-C-1 2005 NRC ADMIN NO 2 JPM CUE SHEET INITIAL CONDITIONS:
A plant startup is being performed 5 days after a reactor trip from 100% power.
Core bumup is 1,000 MWD/MTU.
RCS boron concentration is 1337 ppm.
The plant computer is NOT available.
INITIATING CUE:
The Unit Supervisor directs you to perform a review of an ECP calculation and determine that the critical boron concentration is correct using 1 OM-50.4.F, Performing An Estimated Critical Position Calculation.
BVPS-1 NRC ADMIN NO. 2 NUREG 1021. Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
BVPS Unit 1 Task
Title:
Review a Taaaina Request WA
Reference:
2.2.1 3 (3.8)
Examinee:
Facility Evaluator:
Task No.: 0481 -020-03-01 3 JPM No.:
2005 NRC RO Admin No. 3 NRC Examiner:
Date:
Method of testinq:
Simulated Performance:
Actual Performance:
X Class room X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
The plant is operating at 100% power with all systems in their normal operating alignment. A tagout section has been prepared to isolate and drain [l QS-P-ZB], RWST Recirculating Pump for maintenance.
Task Standard:
Correctly review a clearance tagout section and identify errors.
Required Materials:
None General
References:
NOP-OP-1001, Clearanceflagging Program, Rev. 4 Handouts:
Tagging Section with errors 1 OM-l3.3.B.1, Valve List - 1 QS, Rev. 12 1 OM-l3.3.C, Power Supply And Control Switch List, Issue 4, Rev. 4, OP Manual Fig. No. 13-1, Containment Depressurization System, Rev. 18 NOP-OP-1001, Clearance/Tagging Program, Rev. 4 Initiating Cue:
The Unit Supervisor directs you to conduct a review of the attached tagout section that is being prepared for use and determine its completeness and accuracy. Report your results when finished.
Time Critical Task:
Yes Validation Time:
10 minutes BVPS-1 NRC ADMIN NO. 3 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 2005 NRC ADMIN NO. 3 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
NOTE:
This task is normally performed using the eSOMS clearance computer and signed electronically. If necessary, for the purpose of this JPM, inform the Candidate to review a hardcopy of the tagout for approval in place of performing an electronic review.
.I Performance Step: 1 Review the tagout section for accuracy and completeness.
Standard:
Standard:
Candidate verifies tagout section is appropriate for the task.
Candidate identifies and reports the following tagout errors:
. Valve 1 QS-20 is not the correct discharge isolation point.
(1 QS-P-2A vs. 28). The correct valve is 1 QS-21.
Valve QS-16 is not a correct discharge isolation point.
(1 QS-P-2A vs. 26). The correct valve is 1 QS-17.
CUE:
If the Candidate asks for direction following identification of the first error, direct the Candidate to review the remainder of the tagout section.
NOTE:
If questioned by the Candidate, confirm that valve 1QS-83-3 is not shown on the attached print; however, it is an appropriate drain point.
Comment:
I Terminating Cue:
When the Candidate reports the results of the review, the evaluation for this JPM is complete.
STOP TIME:
BVPS-1 NRC ADMIN NO. 3 NUREG 1021, Revision 9
Appendix C Page 3 of 4 Form ES-C-1 2005 NRC ADMIN NO 3 VERIFICATION OF COMPLETION JPM No.:
Examinee's Name:
Examiner's Name:
Date Performed:
Facility Eva1 u ato r:
Number of Attempts:
Time to Complete:
Question Documentation:
2005 NRC RO No. 3
Response
Resu I t: Satisfactory/Unsatisfactory Examiner's Signature:
BVPS-1 NRC ADMIN NO. 3 Date:
NUREG 1021, Revision 9
Appendix C Page 4 of 4 Form ES-C-1 2005 NRC ADMlN NO. 3 JPM CUE SHEET INITIAL CONDITIONS:
The plant is operating at 100°/o power with all systems in their normal operating alignment. A tagout section has been prepared to isolate and drain [l QS-P-281, RWST Recirculating Pump for maintenance.
INITIATING CUE:
The Unit Supervisor directs you to conduct a review of the attached tagout section that is being prepared for use and determine its completeness and accuracy. Report your results when finished.
BVPS-1 NRC ADMIN NO. 3 NUREG 1021. Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
BVPS Unit 1 Task No.:
Task
Title:
Determine Maximum Allowable Stav Time JPM No.: 2005 NRC RO Admin No. 4 WA
Reference:
2.3.10 (2.9)
Examinee:
Facility Evaluator:
NRC Examiner:
Date:
Method of testina:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
General
References:
Handouts:
initiating Cue:
Time Critical Task:
Validation Time:
Both Units are operating at 100% power. A void has developed in the suction line to 1 CH-P-1 A, Charging Pump at Unit 1. You are NOT currently signed on to fill any operator positions. Your current TEDE dose for the quarter is 150 mR.
Determine the correct RWP and the maximum stay time according to the survey map dose rates.
None 1/2-ADM-1630, Radiation Worker Practices, Rev. 8 Set of RWPs Radiation Survey Map 1021 82 You are to assist a QC Inspector in performing an ultrasonic examination of the void. This requires selecting the correct RWP to enter the RCA, and calculating your MAXIMUM stay time in the charging pump room based on the radiation readings from a survey map. Report your results when finished.
NO 7 minutes BVPS-1 NRC ADMIN NO. 4 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 2005 NRC ADMIN NO. 4 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
.(
Performance Step: 1 Select correct RWP.
Standard:
Candidate correctly determines to log in under RWP 104-1003 based on < 100 mR/hr. General Area Range and EAD dose alarm setpoints of 100 mR.
CUE:
Provide the Candidate with the set of RWPs.
Comment:
NOTE:
After selecting an RWP, provide the Candidate with the attached Survey Map to comdete the followincl step.
.j Performance Step: 2 Calculate maximum stay time.
Standard:
Corn men t :
Candidate correctly calculates maximum stay time as 2 hrs 100 mR 50 mWhr.
2 hrs.
(EAD dose limit)
(highest dose rate)
(Stay time)
~
~~~~
~
Terminating Cue:
When the Candidate reports the results, the evaluation for this JPM is complete.
STOP TIME:
BVPS-1 NRC ADMIN NO. 4 NUREG 1021, Revision 9
Appendix C Page 3 of 4 Form ES-C-1 2005 NRC ADMIN NO. 4 VERIFICATION OF COMPLETION JPM No.:
2005 NRC RO No. 4 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Result: Satisfactory/Unsatisfactory Examiner's Signature:
Date:
BVPS-1 NRC ADMIN NO. 4 NUREG 1021, Revision 9
Appendix C Page 4 of 4 Form ES-C-1 2005 NRC ADMIN NO. 4 JPM CUE SHEET INITIAL CONDITIONS:
Both Units are operating at 100% power. A void has developed in the suction line to 1 CH-P-1 A, Charging Pump at Unit 1. You are NOT currently signed on to fill any operator positions. Your current TEDE dose for the quarter is 150 mR.
INITIATING CUE:
BVPS-1 NRC ADMIN NO. 4 You are to assist a QC Inspector in performing an ultrasonic examination of the void. This requires selecting the correct RWP to enter the RCA, and calculating your MAXIMUM stay time in the charging pump room based on the radiation readings from a survey map. Report your results when finished.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
BVPS Unit 1 Task No. :
1 320-008-03-023 Task
Title:
Determine Action Rewired For Failed AC JPM No.:
2005 NRC SRO Sources Surveillance Adrnin No 1 WA
Reference:
2.2.12 (3.4)
Examinee:
Facility Evaluator:
NRC Examiner:
Date:
Method of testina:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
General Ref e rences :
Handouts:
Initiating Cue:
Time Critical Task:
Validation Time:
The plant is operating at 100% power with all systems in their normal operating alignment. The No. 1 EDG was declared inoperable and removed from service 30 minutes ago due to a ruptured engine cylinder. The PO has completed 1 OST-36.7, Offsite to Onsite Power Distribution System Breaker Alignment Verification.
Procedure errors are identified and Technical Specification action requirements are determined for a failed surveillance test.
None 1 OST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification, Rev. 8 BVPS Unit 1 Technical Specifications LCO 3.8.1.1 1 OST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification, Rev. 8 (marked up copy)
BVPS Unit 1 Technical Specifications LCO 3.8.1.1 The Shift Manager directs you to review the completed 1 OST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification for completeness. Report your results when finished.
No 10 minutes BVPS-1 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Page 2 of 5 Form ES-C-1 2005 NRC ADMIN NO. 1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
4 Performance Step: 1 Review the Initial Conditions section for completeness.
Standard:
Candidate determines that signoffs are missing for the following steps:
111.1.b (power via USSTs or SSSTs) 111.3 (operators have reviewed procedure)
Corn men t :
4 Performance Step: 2 Review Data Sheet 1 for completeness.
Standard:
Candidate determines that the white light for 4KV breaker ACB-341 B is marked as OFF.
NOTE:
This lineup is required to satisfy the requirement for physically independent offsite circuits indicated by the white light being ON.
Corn men t :
BVPS-1 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Page 3 of 5 Form ES-C-1 2005 NRC ADMlN NO. 1 PERFORMANCE INFORMATION Performance Step: 3 Determine Technical Specification Action Statement requirements.
Standard:
Standard:
Candidate determines that OST does not satisfy the Acceptance Criteria.
Candidate identifies applicability of T.S. Action Statement 3.8.1.I.c with one offsite circuit and one diesel generator inoperable.
NOTE:
Provide the Candidate with a copy of the T.S.
handout.
NOTE:
Refer to attached Technical Specification LCO 3.8.1.1 Action c for applicable requirements for an inoperable offsite circuit and diesel generator.
Comment:
Terminating Cue:
When the Candidate identifies the Technical Specification action statement requirement, the evaluation for this JPM is complete.
STOP TIME:
BVPS-1 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Page 4 of 5 Form ES-C-1 2005 NRC ADMIN NO. 1 VERIFICATION OF COMPLETION JPM No.:
2005 NRC SRO No. 1 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's Signature:
Date:
BVPS-1 NRC ADMIN NO. 1 NUREG 1021, Revision 9
Appendix C Page 5 of 5 Form ES-C-1 2005 NRC ADMIN NO. 1 JPM CUE SHEET IN IT1 AL CONDITIONS:
The plant is operating at 100% power with all systems in their normal operating alignment. The No. 1 EDG was declared inoperable and removed from service 30 minutes ago due to a ruptured engine cylinder. The PO has completed 1 OST-36.7, Offsite to Onsite Power Distribution System Breaker Alignment Verification.
INITIATING CUE:
BVPS-1 NRC ADMIN NO. 1 The Shift Manager directs you to review the completed 1 OST-36.7, Offsite To Onsite Power Distribution System Breaker Alignment Verification for completeness. Report your results when finished.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
BVPS Unit 1 Task No.: 001 1-003-01 -01 3 Task
Title:
Review an Estimated Critical Position JPM No.:
2005 NRC SRO Calculation Admin No. 2 WA
Reference:
192008 K1.07 (3.5) 2.1.23 (3.9)
Examinee:
Facility Evaluator:
Method of testing:
NRC Examiner:
Date:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Req u i red Mate rials:
General Ref e rences:
Handouts:
Initiating Cue:
Time Critical Task:
Validation Time:
A plant startup is being performed 5 days after a reactor trip.
Core burnup is 1,000 MWD/MTU.
The plant computer is NOT available.
Estimated critical boron concentration calculated within the specified tolerance and error(s) identified.
Calculator; Evaluator ECP Answer Sheet 1 OM-50.4. F, Performing An Estimated Critical Position Calculation, Rev. 3 BV-1 Curve Book 1 OM-50.4.F, with Critical Data recorded in DATA SHEET 1 BV-1 Curves CB-l2,21,22,23,24A - C, 29 The Shift Manager directs you to review an ECP calculation and determine the boron concentration for startup in accordance with 1 OM-50.4. F, Performing An Estimated Critical Position Calculation.
No 12 minutes BVPS-1 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 2005 NRC ADMIN NO. 2 PERFORMANCE 1 NFORMATION (Denote Critical Steps with a check mark)
START TIME:
4 Performance Step: 1 Review the ECP calculation.
(Data Sheet 1)
Standard:
Standard:
Candidate correctly determines the critical boron concentration required for startup within ? 5 ppm.
Candidate correctly identifies errors as noted on Evaluator's ECP Answer Sheet.
Comment:
I Terminating Cue:
When the Candidate completes the calculation, the evaluation for this JPM is complete.
STOP TIME:
BVPS-1 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Page 3 of 4 Form ES-C-1 2005 NRC ADMIN NO. 2 VERI FI CAT IO N 0 F C 0 M P L ET IO N JPM No.:
2005 NRC SRO No. 2 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's Signature:
Date:
BVPS-1 NRC ADMIN NO. 2 NUREG 1021, Revision 9
Appendix C Page 4 of 4 Form ES-C-1 2005 NRC ADMIN NO. 2 JPM CUE SHEET INITIAL CONDITIONS:...
A plant startup is being performed 5 days after a reactor trip.
Core burnup is 1,000 MWD/MTU.
The plant computer is NOT available.
INITIATING CUE:
BVPS-1 NRC ADMIN NO. 2 The Shift Manager directs you to review an ECP calculation and determine the boron concentration for startup in accordance with 1 OM-50.4. F, Performing An Estimated Critical Position Calculation.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
BVPS Unit 1 Task No.: 1300-023-03-023 Task
Title:
ADgrove a Tacminq Reauest JPM No.:
2005 NRC SRO Admin No. 3 WA
Reference:
2.2.13 (3.8)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testinq:
Simulated Performance:
Actual Pe rf o rm ance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
The plant is operating at 100% power with all systems in their normal operating alignment. A tagout section has been prepared to isolate and drain [ l QS-P-ZB], RWST Recirculating Pump for maintenance.
Task Standard:
Review a clearance tagout section and identify errors.
Required Materials:
None General
References:
NOP-OP-1001, Clearancenagging Program, Rev. 4 Handouts:
Modified Tagging Request 1OM-13.3.8.1, Valve List - IQS, Rev. 12 1 OM-l3.3.C, Power Supply And Control Switch List, Issue 4, Rev. 4, OP Manual Fig. No. 13-1, Containment Depressurization System, Rev. 18 NOP-OP-1001, Clearancenagging Program, Rev. 4 Initiating Cue:
The Shift Manager directs you to conduct a review of the attached tagout section that is ready for approval for completeness and accuracy. Report your results when finished.
Time Critical Task:
Yes Validation Time:
10 minutes BVPS-1 NRC ADMIN NO. 3 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 2005 NRC ADMIN NO. 3 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
NOTE:
This task is normally performed using the eSOMS clearance computer and signed electronically. If necessary, for the purpose of this JPM, inform the Candidate to review a hardcopy of the tagout for approval in place of performing an electronic review.
.I Performance Step: 1 Review the tagout section for accuracy and completeness.
Standard:
Candidate verifies tagout section is appropriate for the task Standard:
Candidate identifies and reports the following tagout errors:
Breaker MCC1-19-G is tagged in the On position. The correct position is Off.
Valve 1 QS-20 is not a correct discharge isolation point (1 QS-P-2A vs. 2B). The correct valve is 1 QS-21.
Valve 1 QS-16 is not a correct discharge isolation point (1 QS-P-2A vs. 2B). The correct valve is 1 QS-17.
CUE:
NOTE:
If the Candidate asks for direction following identification of the first error, direct the Candidate to review the remainder of the tagout section.
If questioned by the Candidate, confirm that valve 1QS-83-3 is not shown on the attached print:
however, it is an appropriate drain point.
Comment:
Terminating Cue:
When the Candidate reports the results of the review, the evaluation for this JPM is complete.
STOP TIME:
BVPS-1 NRC ADMIN NO. 3 NUREG 1021, Revision 9
Appendix C Page 3 of 4 Form ES-C-1 2005 NRC ADMIN NO. 3 VERIFICATION OF COMPLETION JPM No.:
2005 NRC SRO No. 3 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's Signature:
Date:
BVPS-1 NRC ADMIN NO. 3 NUREG 1021, Revision 9
INITIATING CUE:
Appendix C Page 4 of 4 Form ES-C-1 2005 NRC ADMlN NO. 3 JPM CUE SHEET INITIAL CONDITIONS:
The plant is operating at 100% power with all systems in their normal operating alignment. A tagout section has been prepared to isolate and drain [ l QS-P-2B1, RWST Recirculating Pump for maintenance.
BVPS-1 NRC ADMIN NO. 3 The Shift Manager directs you to conduct a review of the attached tagout section that is ready for approval for completeness and accuracy. Report your results when finished.
NUREG 1021, Revision 9
Appendix C Job Performance Measure ES-C-1 Worksheet Faci I i t y :
BVPS Unit 1 Task No.: 1300-009-03-023 Task
Title:
Review a Gaseous Waste Discharae JPM No.:
2005 NRC SRO Authorization Admin No. 4 WA
Reference:
2.3.8 (3.2)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testina:
Simulated Performance:
Actual Performance:
X Class room X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
The plant is in Mode 1 at 100% power. A gaseous waste discharge has been performed from [l GW-TK-1 A], Decay Tank on the previous shift.
Task Standard:
RWDA-G reviewed and errors identified Required Materials:
None General
References:
1 OM-l9.4.E, Decay Tank Discharge, Rev. 6 Handouts:
1 OM-l9.4.E, Decay Tank Discharge, Rev. 6 1/2-HPP-3.006.F011 Gaseous Radioactive Waste Discharge Authorization (Modified)
Initiating Cue:
As the Unit Supervisor, you are to perform a post-release review of the attached RWDA-G to verify that all of the data entered is complete and correct. Report your results when finished.
Time Critical Task:
No Validation Time:
10 minutes BVPS-I NRC ADMIN NO. 4 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 2005 NRC ADMIN NO. 4 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
4 Performance Step: 1 Review the RWDA-G for correct entries and completeness.
Standard:
(Step 1Il.F. Note)
(Step IV.A.6 Note)
Candidate identifies the following errors:
. Chemistry signature is missing in the pre-discharge authorization section.
Discharge Start date exceeds the effective date (greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).
NOTE:
Candidate may refer to 1 OM-l9.4.E, Decay Tank Discharge procedure in order to verify accuracy and completeness of the RWDA-G.
Corn men t :
I I Terminating Cue:
When the Candidate identifies the errors contained in the RWDA-G, the evaluation for this JPM is complete.
STOP TIME:
BVPS-1 NRC ADMIN NO. 4 NUREG 1021, Revision 9
Appendix C Page 3 of 4 Form ES-C-1 2005 NRC ADMIN NO. 4 VERIFICATION OF COMPLETION JPM No.:
2005 NRC SRO No 4 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
~
~~
Result: SatisfactoqdUnsatisfactory Examiner's Signature:
Date:
BVPS-1 NRC ADMIN NO. 4 NUREG 1021 Revision 9
Appendix C Page 4 of 4 Form ES-C-1 2005 NRC ADMIN NO. 4 JPM CUE SHEET INITIAL CONDITIONS:
The plant is in Mode 1 at 100% power. A gaseous waste discharge has been performed from [l GW-TK-1 A], Decay Tank on the previous shift.
INITIATING CUE:
BVPS-1 NRC ADMIN NO. 4 As the Unit Supervisor, you are to perform a post-release review of the attached RWDA-G to verify that all of the data entered is complete and correct. Report your results when finished.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
BVPS Unit 1 Task No.: 1350-004-03-023 Task
Title:
Terminate an Emeraencv Classification JPM No.:
2005 NRC SRO Admin No. 5 WA
Reference:
2.4.40 (4.0)
Examinee:
Facility Evaluator:
NRC Examiner:
Date:
Method of testina:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
An Unusual Event was declared at Unit 1 due to indications of an RCS leak inside containment.
The unidentified leak rate was estimated to be between 12 and 20 gpm based on charging/letdown mismatch.
A plant shutdown was initiated at 2% per minute.
The shutdown was completed and the plant is currently in Mode 5 with the RCS depressurized.
Task Standard:
Emergency Plan EALs reviewed and classification level terminated Required Materials:
None General
References:
EPP/I-1 a, Unit 1 - Recognition And Classification Of Emergency Conditions, Rev. 5 1/2-EPP-1-2, Unusual Event, Rev. 20 Handouts:
EPP/I-1 a, Unit 1 - Recognition And Classification Of Emergency Conditions, Rev. 5 1/2-EPP-I-2, Unusual Event, Rev. 20 Initiating Cue:
As the Emergency Director, you are to perform a review of the Emergency Plan EALs and determine the current status of the Emergency Plan classification level. Report your results when finished.
Time Critical Task:
No Validation Time:
5 minutes BVPS-1 NRC ADMIN NO. 5 NUREG 1021, Revision 9
Appendix C Page 2 of 4 Form ES-C-1 2005 NRC ADMIN NO. 5 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
.(
Performance Step: 1 Review the EALs.
Standard:
Standard:
Candidate locates TAB 2.5, RCS Unidentified Leakage.
Candidate determines that the Unusual Event can be terminated based on Mode 5 and RCS depressurized.
NOTE:
Candidate may also refer to 1/2-EPP-I-2, Unusual Event for guidance. If requested provide the Candidate with a copy of the procedure.
If asked, inform the Candidate that it will not be necessary to refer to the event termination procedure, once the determination has been made that the event conditions no longer exist.
NOTE:
Comment:
Terminating Cue:
When the Candidate determines the Unusual Event can be terminated, the evaluation for this JPM is complete.
STOP TIME:
BVPS-1 NRC ADMIN NO. 5 NUREG 1021, Revision 9
Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION 2005 NRC ADMIN NO. 5 JPM No.:
2005 NRC SRO No. 5 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: Satisfactory/Unsatisfactory Examiner's Signature:
BVPS-1 NRC ADMIN NO. 5 Date:
NUREG 1021, Revision 9
Appendix C Page 4 of 4 Form ES-C-1 2005 NRC ADMIN NO. 1 JPM CUE SHEET IN !TI AL C 0 N DlTlO NS :.
I An Unusual Event was declared at Unit 1 due to indications of an RCS leak inside containment.
The unidentified leak rate was estimated to be between 12 and 20 gpm based on charging/letdown mismatch.
A plant shutdown was initiated at 2% per minute.
The shutdown was completed and the plant is currently in Mode 5 with the RCS depressurized.
INITIATING CUE:
BVPS-1 NRC ADMIN NO. 5 As the Emergency Director, you are to perform a review of the Emergency Plan EALs and determine the current status of the Emergency Plan classification level. Report your results when finished.
NUREG 1021, Revision 9