ML112430553
| ML112430553 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/08/2011 |
| From: | Kelly Clayton Operations Branch IV |
| To: | Entergy Operations |
| References | |
| 50-382/11-302 | |
| Download: ML112430553 (227) | |
Text
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE A1 Calculation of Containment Pressure Applicant:
Examiner:
JPM A1 JOB PERFORMANCE MEASURE DATA PAGE Task: Calculate Containment pressure Task Standard: Calculates Containment pressure in accordance with OP-903-001, Technical Specification Surveillance Logs.
References:
OP-903-001, Technical Specification Surveillance Logs Time Critical: No Validation Time: 15 mins.
K/A 2.1.19 Ability to use plant computers to Importance Rating 3.9 evaluate system or component status RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 6 2011 NRC Walk Through Exam
JPM A1 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-903-001, Technical Specification Surveillance Logs
==
Description:==
Applicant uses SDS terminal to obtain barometric pressure and Containment pressure and then calculates corrected Containment pressure for Technical Specification logs.
READ TO APPLICANT DIRECTION TO APPLICANT:
Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.
Provide all answers on the sheets provided.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 6 2011 NRC Walk Through Exam
JPM A1 TASK ELEMENT 1 STANDARD Containment pressure is Calculate Containment pressure calculated in accordance with the key.
Comment: Critical When completed, ask applicant if the final value mets Technical Specification limits. The final value, 14.33 PSIA, is above the Tech Spec SAT / UNSAT limit of 14.275 END OF TASK Revision 0 Page 4 of 6 2011 NRC Walk Through Exam
JPM A1 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-192 Revision 0 Page 5 of 6 2011 NRC Walk Through Exam
JPM A1 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Containment pressure reduction was secured during the previous shift.
INITIATING CUES:
- Calculate Containment pressure using OP-903-001, Technical Specification Surveillance Logs.
- Use the Plant Monitoring Computer for data collection.
Revision 0 Page 6 of 6 2011 NRC Walk Through Exam
A1 KEY 11.15 CONTAINMENT PRESSURE CALCULATION 11.15.1 Barometric Pressure as measured by PMC (PID C48516).
If local reading used, then add 0.05 INHG to obtain a value equivalent to Met Tower PMC point. BP = ____29.75___ INHG 11.15.1.2 Record M&TE data on TS Logs Remarks and WR, if applicable.
11.15.2 Containment to Ambient Differential Pressure (PMC PID-A51000). C/A = ___-7.7_____ INWC 11.15.3 Convert Barometric Pressure (BP) from INHG to PSIA by performing the following:
BP(PSIA) = [BP (INHG) X 0.4912 PSIA/INHG]
BP(PSIA) = [ ____29.75_________ INHG X 0.4912 PSIA/INHG]
BP(PSIA) = ____14.61_________ PSIA 11.15.4 Convert Containment to Ambient Differential Pressure (C/A) from INWC to PSIA by performing the following:
C/A(PSIA) = [C/A (INWC) X 0.0361 PSIA/INWC]
C/A(PSIA) = [ _____-7.7__________ INWC X 0.0361 PSIA/INWC]
C/A(PSIA) = ______-0.278_______ PSIA 11.15.5 Calculate Absolute Containment Internal Pressure (CP) by performing the following:
CP(PSIA) = BP(PSIA) + C/A(PSIA)
CP(PSIA) = _____14.61__________ PSIA + ____-0.278__________ PSIA CP(PSIA) = ______14.332_________ PSIA 11.15.6 Attach this Attachment to Attachment 11.1, Mode 1-4 Technical Specification Surveillance Log.
A1 KEY OP-903-001 Revision 043 Attachment 11.15 (1 of 1) 139
20.0 Individual CEA positions can be obtained by one of the following methods:
(NA if not in Mode 1 or 2)
PMC hard copy printout Attachment 11.8, Technical Specification Addendum Logsheet Satisfactory indication of CEA positions via the Excel spreadsheet (Att. 11.20)
If one of the above methods is not available, then record all CEA positions from all three indicating channels on Attachment 11.5, CEA Positions.
21.0 In Modes 1 and 2, two of the three CEA position indicator channels are required to be Operable. Verify all CEA Position Indicator channels are Operable by verifying that for the same CEA, the position indicator channels agree within 5 inches of each other.
Position Indicator channels are the RSPT #1 and #2 (CEACs) and the CEA Pulse Counting position indicator channel (PMC). NA if not in Mode 1 or 2.
22.0 N/A if not in Modes 1 or 2. Verify the position of each CEA within 7 inches (indicated position) of all CEAs in its group. If either or both CEACs are Inoperable then verify individual CEA positions at least once per 4 Hours. If both CEACs are Inoperable, then comply with T.S. 3.2.4.b or T.S. 3.2.4.d.
23.0 N/A if not in Modes 1 or 2. Verify each S/D CEA is withdrawn to 145 inches.
24.0 N/A if not in Modes 1 or 2. Verify CEA Group P withdrawal within the Transient Insertion Limits of the COLR when in Mode 1, or Mode 2 with Keff once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or with PDIL alarm Inoperable once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Per the COLR, Group P CEA position is unrestricted at <20% power. If withdrawn between the Long Term Steady State and Transient Insertion Limits, then document per Attachment 11.7, Regulating Group and Group P Insertion Limits. [TS 3.1.3.6]
25.0 N/A if not in Modes 1 or 2. Verify CEA group withdrawal within the Transient Insertion Limits of the COLR when in Mode 1, or Mode 2 with Keff 1 once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or with PDIL alarm Inoperable once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. In Mode 2 with Keff < 1, verify Estimated Critical Position is within the limits of the COLR within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving Reactor Criticality. If withdrawn between the Long Term Steady State and Transient Insertion Limits, then document per Attachment 11.7, Regulating Group and Group P CEA Insertion Limits. [TS 3.1.3.6]
26.0 Verify Containment Pressure within the limits of 0 to <24.2 INWC in Modes 1-4. If Containment to Ambient Differential Pressure is <0 INWC, then refer to Note 26.1 and N/A this reading.
26.1 Perform Attachment 11.15, Containment Pressure Calculation. (NA if Containment to Ambient Differential Pressure is 0 INWC.)
27.0 Verify Containment Purge Isolation Valves Open <90 Hours in the previous 365 Days, while in Modes 1-4.
OP-903-001 Revision 043 Attachment 11.1 (27 of 37) 44
11.15 CONTAINMENT PRESSURE CALCULATION 11.15.1 Barometric Pressure as measured by PMC (PID C48516).
If local reading used, then add 0.05 INHG to obtain a value equivalent to Met Tower PMC point. BP = ____________ INHG 11.15.1.2 Record M&TE data on TS Logs Remarks and WR, if applicable.
11.15.2 Containment to Ambient Differential Pressure (PMC PID-A51000). C/A = ___________ INWC 11.15.3 Convert Barometric Pressure (BP) from INHG to PSIA by performing the following:
BP(PSIA) = [BP (INHG) X 0.4912 PSIA/INHG]
BP(PSIA) = [ __________________ INHG X 0.4912 PSIA/INHG]
BP(PSIA) = __________________ PSIA 11.15.4 Convert Containment to Ambient Differential Pressure (C/A) from INWC to PSIA by performing the following:
C/A(PSIA) = [C/A (INWC) X 0.0361 PSIA/INWC]
C/A(PSIA) = [ __________________ INWC X 0.0361 PSIA/INWC]
C/A(PSIA) = __________________ PSIA 11.15.5 Calculate Absolute Containment Internal Pressure (CP) by performing the following:
CP(PSIA) = BP(PSIA) + C/A(PSIA)
CP(PSIA) = ____________________ PSIA + ___________________ PSIA CP(PSIA) = ____________________ PSIA 11.15.6 Attach this Attachment to Attachment 11.1, Mode 1-4 Technical Specification Surveillance Log.
OP-903-001 Revision 043 Attachment 11.15 (1 of 1) 139
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE A2 Determine Time to Place Shutdown Cooling in Service Applicant:
Examiner:
JPM A2 JOB PERFORMANCE MEASURE DATA PAGE Task: Calculate the time remaining to place Shutdown Cooling in service.
Task Standard: Applicant calculates the remaining time to place Shutdown Cooling in service in accordance with OP-902-009, Standard Appendices, and answer key.
References:
OP-902-009, Standard Appendices Time Critical: No Validation Time: 15 mins.
K/A 2.1.25, Ability to interpret reference Importance Rating 3.9 materials, such as graphs, curves, tables, etc RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 7 2011 NRC Walk Through Exam
JPM A2 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-902-009, Standard Appendices
==
Description:==
Applicant will be required to calculate the time remaining to get on Shutdown Cooling. Appendix 2 of OP-902-009, Standard Appendices, will be required. All other data will be given in the question initial conditions.
READ TO APPLICANT DIRECTION TO APPLICANT:
Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.
Provide all answers on the sheets provided.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 7 2011 NRC Walk Through Exam
JPM A2 TASK ELEMENT 1 STANDARD Determine DWST volume Volume = 127,000 gallons.
Comment: Critical SAT / UNSAT TASK ELEMENT 2 STANDARD Determine CSP volume Volume = 62,830 gallons.
Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD Determine Total Feedwater Volume = 189,830 gallons.
Comment: Critical SAT / UNSAT TASK ELEMENT 4 STANDARD Volume = 30,000 - 30,500 Determine Feedwater Required from 2 - G gallons.
Comment: Critical Band for graph reading.
SAT / UNSAT Revision 0 Page 4 of 7 2011 NRC Walk Through Exam
JPM A2 TASK ELEMENT 5 STANDARD Volume = 159,830 -
Determine Available Feedwater 159,330 gallons.
Comment: Critical SAT / UNSAT TASK ELEMENT 6 STANDARD Determine maximum time to place Shutdown Cooling in Service Time = 10.5 - 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
Comment: Critical SAT / UNSAT END OF TASK Revision 0 Page 5 of 7 2011 NRC Walk Through Exam
JPM A2 SIMULATOR OPERATOR INSTRUCTIONS There is no Simulator setup for this JPM Revision 0 Page 6 of 7 2011 NRC Walk Through Exam
JPM A2 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
Do not use Simulator data for this JPM INITIAL CONDITIONS:
The plant tripped due to a Main Steam Line Break inside containment. All actions of OP-902-004 are complete up to starting a cooldown to SDC entry conditions. All Reactor Coolant Pumps are secured.
The following plant conditions exist:
The plant tripped one hour ago.
DWST Volume - 37%
CSP Volume - 55%
THOT - 520 °F INITIATING CUES:
- The CRS directs you to calculate time to place SDC in service based upon Condensate Inventory in accordance with OP-902-009, Attachment 2-G, Feedwater for Sensible Heat Removal.
Revision 0 Page 7 of 7 2011 NRC Walk Through Exam
WATERFORD 3 SES OP-902-009 Revision 301 Page 12 of 195 STANDARD APPENDICES Appendix 2 Page 7 of 10 Figures Attachment 2-G: Feedwater for Sensible Heat Removal 650 450 °F T h ot 600 550 40 0 °F T h ot 500 350 °F T hot 450 400 30 0 °F T hot 350 300 250 0 .0 1 0 .0 2 0 .0 3 0 .0 4 0 .0 5 0 .0 6 0 .0 7 0 .0 8 0 .0 F e e d w a te r R e q u ire d ( g a l x 1 0 0 0 )
D W S T V o l u m e = 5 0 0 0 g a l / % x _ _ _ _ _ _ % - 5 8 ,0 0 0 g a l = _ _ _ _ _ _ _ _ _ _ g a l C S P V o lu m e = 2 1 0 6 g a l / % x _ _ _ _ _ _ % -5 3 ,0 0 0 g a l = _ _ _ _ _ _ _ _ _ _ _ _ g a l T o ta l F ee d w a te r = D W S T V o lu m e + C S P V o lu m e = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ g a l A v a ila b le F e e d w a te r = T o ta l F e e d w a te r F e e d w a te r R e q u ire d fro m A tt. 2 -G
= _ _ _ _ _ _ _ _ _ _ _ _ _ _ T o ta l - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ R e q u ire d = _ _ _ _ _ _ _ _ _ _ _ g a l End of Attachment 2-G
WATERFORD 3 SES OP-902-009 Revision 301 Page 13 of 195 STANDARD APPENDICES Appendix 2 Page 8 of 10 Figures End of Attachment 2-H: Condensate Inventory Curve Four RCPs Operating 750.0 Time After Shutdown 700.0 0 Hour 1 Hour 2 Hours 650.0 3 Hours 4 Hours 8 Hours 600.0 10 Hours 12 Hours 16 Hours 550.0 500.0 450.0 400.0 350.0 300.0 250.0 200.0 150.0 100.0 50.0 0.0 0 4 8 12 16 20 24 28 32 Maximum Time Remaining to Place Shutdown Cooling System in Service (Hrs)
End of Attachment 2-H
WATERFORD 3 SES OP-902-009 Revision 301 Page 14 of 195 STANDARD APPENDICES Appendix 2 Page 9 of 10 Figures Attachment 2-I: Condensate Inventory Curve Two RCPs Operating 600.0 Time After Shutdown 0 Hour 1 Hour 500.0 2 Hours 3 Hours 4 Hours 8 Hours 10 Hours 12 Hours 16 Hours 400.0 300.0 200.0 100.0 0.0 0 4 8 12 16 20 24 28 32 Maximum Time Remaining to Place Shutdown Cooling System in Service (Hrs)
End of Attachment 2-I
WATERFORD 3 SES OP-902-009 Revision 301 Page 15 of 195 STANDARD APPENDICES Appendix 2 Page 10 of 10 Figures Attachment 2-J: Condensate Inventory Curve NO RCPs Operating 450.0 Time After 400.0 Shutdown 0 Hour 1 Hour 2 Hours 350.0 3 Hours 4 Hours 8 Hours 10 Hours 12 Hours 300.0 16 Hours 250.0 200.0 150.0 100.0 50.0 0.0 0 4 8 12 16 20 24 28 32 Maximum Time Remaining to Place Shutdown Cooling System in Service (Hrs)
End of Attachment 2-J
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE A3 Complete Assessment of Heated and Unheated Junction Thermocouples Applicant:
Examiner:
JPM A3 JOB PERFORMANCE MEASURE DATA PAGE Task: Complete Assessment of Heated and Unheated Junction Thermocouples in accordance with OP-903-013, Monthly Channel Checks.
Task Standard: Completes OP-903-013, Monthly Channel Checks, Attachment 10.3 for Heated and Unheated Thermocouples according to answer key.
References:
OP-903-013, Monthly Channel Checks.
Alternate Path: No Time Critical: No Validation Time: 10 mins.
K/A 2.2.12 - Knowledge of surveillance Importance Rating 3.7 procedures.
Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 7 2011 NRC Walk Through Exam
JPM A3 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-903-013, Monthly Channel Checks
==
Description:==
Applicant will use data provided to complete assessment of the heated and unheated junction thermocouples using OP-903-013. Position 1 of Channel 1 will be inoperable.
All other positions will meet the requirements of the procedure.
READ TO APPLICANT DIRECTION TO APPLICANT:
Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.
Provide all answers on the sheets provided.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 7 2011 NRC Walk Through Exam
JPM A3 TASK ELEMENT 1 STANDARD Complete OP-903-013, Monthly Channel Checks, for the Heated and See answer key.
Unheated Junction Thermocouples.
Comment: Critical Position 1 of QSPDS Channel 1 should be declared inoperable.
There is a > 25 F difference between position 6 and position 8 unheated SAT / UNSAT readings on QSPDS 2.
END OF TASK Revision 0 Page 4 of 7 2011 NRC Walk Through Exam
JPM A3 SIMULATOR OPERATOR INSTRUCTIONS There is no Simulator setup for this JPM Revision 0 Page 5 of 7 2011 NRC Walk Through Exam
JPM A3 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
Do not use Simulator data for this JPM INITIAL CONDITIONS:
- Data sheet provided.
INITIATING CUES:
- The CRS directs you to complete OP-903-013, Monthly Channel Checks, Attachment Revision 0 Page 6 of 7 2011 NRC Walk Through Exam
JPM A3 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
QSPDS Datasheet QSPDS 1 UHJTC Zone 1 = 605 °F QSPDS 1 UHJTC Zone 2 = 603 °F QSPDS 1 UHJTC Zone 3 = 608 °F QSPDS 1 UHJTC Zone 4 = 609 °F QSPDS 1 UHJTC Zone 5 = 611 °F QSPDS 1 UHJTC Zone 6 = 607 °F QSPDS 1 UHJTC Zone 7 = 610 °F QSPDS 1 UHJTC Zone 8 = 610 °F QSPDS 1 HJTC Zone 1 = 626 °F QSPDS 1 HJTC Zone 2 = 645 °F QSPDS 1 HJTC Zone 3 = 647 °F QSPDS 1 HJTC Zone 4 = 650 °F QSPDS 1 HJTC Zone 5 = 660 °F QSPDS 1 HJTC Zone 6 = 650 °F QSPDS 1 HJTC Zone 7 = 655 °F QSPDS 1 HJTC Zone 8 = 660 °F QSPDS 2 UHJTC Zone 1 = 595 °F QSPDS 2 UHJTC Zone 2 = 600 °F QSPDS 2 UHJTC Zone 3 = 607 °F QSPDS 2 UHJTC Zone 4 = 610 °F QSPDS 2 UHJTC Zone 5 = 606 °F QSPDS 2 UHJTC Zone 6 = 586 °F QSPDS 2 UHJTC Zone 7 = 609 °F QSPDS 2 UHJTC Zone 8 = 612 °F QSPDS 2 HJTC Zone 1 = 650 °F QSPDS 2 HJTC Zone 2 = 647 °F QSPDS 2 HJTC Zone 3 = 652 °F QSPDS 2 HJTC Zone 4 = 655 °F QSPDS 2 HJTC Zone 5 = 636 °F QSPDS 2 HJTC Zone 6 = 657 °F QSPDS 2 HJTC Zone 7 = 660 °F QSPDS 2 HJTC Zone 8 = 655 °F Revision 0 Page 7 of 7 2011 NRC Walk Through Exam
KEY A3 ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECK (CONTD)
Reactor Vessel Level Monitoring System HJTC Temperatures
[P-15406]
QSPDS1 QSPDS2 REGION ZONE UNHEATED HEATED T OPERABLE UNHEATED HEATED T OPERABLE YES NO YES NO 1 605 626 21 (check one) 595 650 55 (check one)
YES NO YES NO Head 2 603 645 42 (check one) 600 647 47 (check one)
YES NO YES NO 3 608 647 39 (check one) 607 652 45 (check one)
YES NO YES NO 4 609 650 41 (check one) 610 655 45 (check one)
YES NO YES NO 5 611 660 49 (check one) 606 636 30 (check one)
YES NO YES NO Plenum 6 607 650 43 (check one) 586 657 71 (check one)
YES NO YES NO 7 610 655 45 (check one) 609 660 51 (check one)
YES NO YES NO 8 610 660 50 (check one) 612 655 43 (check one)
AVG HJTC AVG HJTC TEMP CH 1 649.13 TEMP CH 2 651.5 OPERABILITY:
(1) HJTC and UHJTC temperatures are >32°F and <2300°F.
(2) HJTC temperature is greater than UHJTC temperature by more than 25°F.
OP-903-013 Revision 016 Attachment 10.3 (4 of 14)
KEY A3
KEY A3 ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECK (CONTD)
ACCEPTANCE CRITERIA AND TEST ACCEPTANCE At least the REQUIRED NUMBER OF CHANNELS requirement for the Instruments and Containment Isolation Valves is satisfied except as allowed by T.S. Table 3.3-10.
If an Action of T.S. 3.3.3.6 is entered due to the Minimum Channels Operable requirements not being met, then alternate means of indication selected from Attachment 10.4, Alternate Accident Monitoring Instruments must be verified to be available for the Allowed Outage Time. If no alternate means are available, then see section 7.3 and T.S. 3.3.3.6 for required action.
Acceptance Criteria Met: YES / NO (Circle One)
REMARKS: Work Request written for QSPDS 1 Zone 1. Sensor is inoperable due to HJTC-UHJTC Delta T not exceeding 25 °F.
Work Request written for QSPDS 2 position 6 being > 25 °F lower than position 8.
Performed by:
(Signature) (Date)
Calculations Verified by:
(Signature) (Date)
SM/CRS Review:
(Signature) (Date/Time)
KEY A3 2011 NRC Walk Through Exam OP-903-013 Revision 016 [LAST PAGE] Attachment 10.3 (14 of 14)
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE A4 Complete Waste Condensate Tank Release Applicant:
Examiner:
JPM A4 JOB PERFORMANCE MEASURE DATA PAGE Task: Complete the release permit for a Waste Condensate Tank release.
Task Standard: Applicant correctly completes the provided release permit in accordance with the answer key. Release is completed with no errors related to flow rate or volume of water discharged.
References:
OP-007-004, Liquid Waste Management System EC-M84-001, Tank Volume vs. Level Time Critical: No Validation Time: 15 mins.
K/A 2.3.11 Ability to control radiation releases Importance Rating 3.8 RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 6 2011 NRC Walk Through Exam
JPM A4 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-007-004, Liquid Waste Management System EC-M84-001, Tank Volume vs. Level
==
Description:==
The applicant will be required to calculate the volume of water discharged and the average flow rates for a Waste Condensate Tank release. The cue sheet will provide the necessary information. The applicant will be required to calculate flow rate for the control Panel flow integrator and the change in volume of the tank using the tank volume calculation. The simulator is not required for this admin JPM.
READ TO APPLICANT DIRECTION TO APPLICANT:
Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk.
Provide all answers on the sheets provided.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 6 2011 NRC Walk Through Exam
JPM A4 TASK ELEMENT 1 STANDARD Release is completed with Applicant completes the provided release permit in accordance with the no errors related to flow key. rate or volume of water discharged.
Comment: Critical Items the applicant must correctly calculate are:
Release time: 285 minutes SAT / UNSAT Release rate using flow integrator: 47.35 gpm Gallons discharged from Data Book 13,544.7 gallons Release rate using Data Book 47.5 gpm END OF TASK Revision 0 Page 4 of 6 2011 NRC Walk Through Exam
JPM A4 SIMULATOR OPERATOR INSTRUCTIONS There is no Simulator setup for this JPM Revision 0 Page 5 of 6 2011 NRC Walk Through Exam
JPM A4 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
Do not use Simulator data for this JPM INITIAL CONDITIONS:
- The release of Waste Condensate Tank A was completed at 1300 on 8/12/2011.
- The final tank level was 5.5 %.
- The flow integrator reading is 13,498.
INITIATING CUES:
- Complete the release permit for Waste Condensate Tank A.
Revision 0 Page 6 of 6 2011 NRC Walk Through Exam
R Type K2.33 Liquid Waste batch Release Permit Permit Number: LB2011-0082 Entergy Operations, Inc. Waterford Steam Electric Station Unit III Release Point (1) : Waste Condensate Tank A Waste Volume : 15,497 gal Maximum Waste Flow: 50.00 gpm Minimum Dilution Flow : 5.00 e+5 gpm (2 Circ Water Pumps) Total Gamma Conc. : 1.04e-05 uCi/ml SINGLE Release Setpoint for PRM-IRE-0647 8.00e-02 uCi/ml *** ADJUST ***
- Concurrent with Permit Number LC2009-0043 : (22) Dry Cooling Tower Sump #1 to Circ Water
- Concurrent with Permit Number LC2009-0044 : (23) Dry Cooling Tower Sump #21 to Circ Water
- Concurrent with Permit Number LC2009-0045 : (24) TGB Industrial Waste Sump to Circ Water Estimated Maximum Organ Dose: 0.00 mrem for the Adult Thyroid Estimated Cumulative Maximum Organ Doses - Including this release.
31 Day Quarter - To - Date Year - To - Date Limit 0.06 mrem 1.50 mrem 3.00 mrem Organ Total Body Total Body Total Body 0.000 mrem 0.00 mrem 0.0029 mrem Special Conditions : Adjust PRM-IRE-0647 radiation monitor setpoint to 8.00 e-02 uCi/ml prior to release.
PRM-IRE-0647 setpoint to 6.50 e-01 uCi/ml after release permit is closed.
Prepared By: Reviewed By: Approved By:
S. Chemist C. Supervisor C.R. Supervisor Date: 8/12/2011 Date: 8/12/2011 Date: 8/12/2011 PRM-IRE-0647 Radiation Monitor Source Check: JVS Channel Check: JVS Circ. Water Flowrate: 1,000,000 gpm Date Time Tank Level % Flow Integrator (gal)
Release Start 8 / 12 / 11 0815 95.7 0 Release Finish
- NET
- min.
gal / min = gpm = Average Waste Flow Rate (Flow Integrator) (Release Time) gal / min = gpm = Average Waste Flow Rate (Plant Data Book) (Release Time)
Radiation Monitor Readings for PRM-IRE-0647 10 minutes into release: 6.04 e-5 uCi/m l After Flush: 1.42 e-5 uCi/ml Remarks:
Release Completed By: Date / Time Operations Release Reviewed By: Date / Time CRS / SM Release Reviewed By: Date / Time HP Forman / Designee Revision 0 JPM A4 2011 NRC Walk Through Exam
- ANSWER KEY ***
R Type K2.33 Liquid Waste batch Release Permit Permit Number: LB2011-0082 Entergy Operations, Inc. Waterford Steam Electric Station Unit III Release Point (1) : Waste Condensate Tank A Waste Volume : 15,497 gal Maximum Waste Flow: 50.00 gpm Minimum Dilution Flow : 5.00 e+5 gpm (2 Circ Water Pumps) Total Gamma Conc. : 1.04e-05 uCi/ml SINGLE Release Setpoint for PRM-IRE-0647 8.00e-02 uCi/ml *** ADJUST ***
- Concurrent with Permit Number LC2009-0043 : (22) Dry Cooling Tower Sump #1 to Circ Water
- Concurrent with Permit Number LC2009-0044 : (23) Dry Cooling Tower Sump #21 to Circ Water
- Concurrent with Permit Number LC2009-0045 : (24) TGB Industrial Waste Sump to Circ Water Estimated Maximum Organ Dose: 0.00 mrem for the Adult Thyroid Estimated Cumulative Maximum Organ Doses - Including this release.
31 Day Quarter - To - Date Year - To - Date Limit 0.06 mrem 1.50 mrem 3.00 mrem Organ Total Body Total Body Total Body 0.000 mrem 0.00 mrem 0.0029 mrem Special Conditions : Adjust PRM-IRE-0647 radiation monitor setpoint to 8.00 e-02 uCi/ml prior to release.
PRM-IRE-0647 setpoint to 6.50 e-01 uCi/ml after release permit is closed.
Prepared By: Reviewed By: Approved By:
S. Chemist C. Supervisor C.R. Supervisor Date: 8/12/2011 Date: 8/12/2011 Date: 8/12/2011 PRM-IRE-0647 Radiation Monitor Source Check: JVS Channel Check: JVS Circ. Water Flowrate: 1,000,000 gpm Date Time Tank Level % Flow Integrator (gal)
Release Start 8 / 12 / 11 0815 95.7 0 Release Finish 8 / 12 / 11 1300 5.5 13,495
- NET
- 285 min. 90.2 13,495 13,495 gal / 285 min = 47.35 gpm = Average Waste Flow Rate (Flow Integrator) (Release Time) 13,544.7 gal / 285 min = 47.5 gpm = Average Waste Flow Rate (Plant Data Book) (Release Time)
Radiation Monitor Readings for PRM-IRE-0647 10 minutes into release: 6.04 e-5 uCi/m l After Flush: 1.42 e-5 uCi/ml Remarks:
Release Completed By: Date / Time Operations Release Reviewed By: Date / Time CRS / SM Release Reviewed By: Date / Time HP Forman / Designee Revision 0 JPM A4 2011 NRC Walk Through Exam
JPM A4 Tank Level Gallons Gallons per percent 95.0 15482.6 96.0 15632.8 150.2 105.14 15587.74 0.70% 95.70%
5.0 1967.9 6.0 2118.1 150.2 75.1 2043 0.50% 5.50%
13544.74 95.70% 15587.7 gallons 5.50% 2043.0 gallons Total Discharged 13544.7 gallons Discharge Time 285 minutes Flow Rate 47.53 gallons/minute Flow Integrator 13495.0 gallons Discharge Time 285.0 minutes Flow Rate 47.35 gallons/minute
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE S1 OP-903-096, Boron Flow Rate Verification Applicant:
Examiner:
JPM S1 JOB PERFORMANCE MEASURE DATA PAGE Task: Perform OP-903-096, Boron Flow Rate Verification.
Task Standard: Applicant completes OP-903-096 without tripping the running Charging Pump on low suction pressure.
References:
OP-903-096, Boron Flow Rate Verification Alternate Path: No Time Critical: No Validation Time: 15 mins.
K/A A4.07 Boration/Dilution Importance Rating 3.9 RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 12 2011 NRC Walk Through Exam
JPM S1 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-903-096, Boron Flow Rate Verification
==
Description:==
The applicant will perform OP-903-096, Boron Flow Rate Verification. This task rotates the Charging Pump suction sources through the various combinations. All manipulations occur at CP-4. If an applicant does not follow the procedure sequence properly and trips the running Charging Pump, then that applicant would fail this task.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 12 2011 NRC Walk Through Exam
JPM S1 Evaluator Note Cue the Simulator Operator to place the Simulator in RUN.
TASK ELEMENT 1 STANDARD 7.1.1 Verify one Charging Pump is operating, and document on Documentation complete. 0.1, Boron Flow Rate Verification.
Comment:
SAT / UNSAT TASK ELEMENT 2 STANDARD 7.1.2 If the RCS is depressurized, then perform the following for accurate flow measurements:
Not applicable 7.1.2.1 Close Charging Line 1A Shutoff Valve, CVC-218A 7.1.2.2 Close Charging Line 2A Shutoff Valve, CVC-218B.
Comment:
SAT / UNSAT TASK ELEMENT 3 STANDARD This switch will already be 7.1.3 Place Makeup Mode selector switch in Manual.
in manual.
Comment:
SAT / UNSAT TASK ELEMENT 4 STANDARD 7.1.4 Open Gravity Feed Valves Tank A, BAM-113A. Valve open.
Comment: Critical SAT / UNSAT Revision 0 Page 4 of 12 2011 NRC Walk Through Exam
JPM S1 TASK ELEMENT 5 STANDARD 7.1.5 Verify the following valves Closed:
- CVC-183 VCT Disch Valve CVC-183 is closed.
- CVC-507 RWSP to Charging Pump Suction Isolation Comment: Critical CVC-507 will already be closed. The applicant will be required to close CVC-183. SAT / UNSAT TASK ELEMENT 6 STANDARD 7.1.6 Verify Charging Header Flow, using ultrasonic flow meter, indicates 40 GPM. Record and document on Attachment 10.1, Boron Flow Rate Information requested.
Verification.
Comment:
Cue: Acknowledge communication and direct applicant to use Charging flow indication on CP-4. SAT / UNSAT TASK ELEMENT 7 STANDARD 7.1.7 Start Boric Acid Pump A. Pump running.
Comment: Critical SAT / UNSAT TASK ELEMENT 8 STANDARD 7.1.7.1 Close Boric Acid Makeup Pump A Recirc Valve, BAM-126A. Valve closed.
Comment: Critical SAT / UNSAT Revision 0 Page 5 of 12 2011 NRC Walk Through Exam
JPM S1 TASK ELEMENT 9 STANDARD 7.1.8 Open Emergency Boration Valve, BAM-133. Valve open.
Comment: Critical SAT / UNSAT TASK ELEMENT 10 STANDARD 7.1.9 Close Gravity Feed Valves Tank A, BAM-113A, and document on Valve closed. 0.1, Boron Flow Rate Verification.
Comment: Critical SAT / UNSAT TASK ELEMENT 11 STANDARD 7.1.10 Verify Charging Header Flow, using ultrasonic flow meter, indicates 40 GPM. Record and document on Attachment 10.1, Boron Information requested.
Flow Rate Verification.
Comment:
Cue: Acknowledge communication and direct applicant to use Charging flow indication on CP-4. SAT / UNSAT TASK ELEMENT 12 STANDARD 7.1.11 Start Boric Acid Pump B. Pump running.
Comment: Critical SAT / UNSAT Revision 0 Page 6 of 12 2011 NRC Walk Through Exam
JPM S1 TASK ELEMENT 13 STANDARD 7.1.11.1 Close Boric Acid Makeup Pump B Recirc Valve, BAM-126B. Valve closed.
Comment: Critical SAT / UNSAT TASK ELEMENT 14 STANDARD 7.1.12 Stop Boric Acid Pump A. Pump secured.
Comment: Critical SAT / UNSAT TASK ELEMENT 15 STANDARD 7.1.12.1 Open Boric Acid Makeup Pump A Recirc Valve, BAM-126A, and Valve open.
document on Attachment 10.1, Boron Flow Rate Verification.
Comment:
SAT / UNSAT TASK ELEMENT 16 STANDARD 7.1.13 Verify Charging Header Flow, using ultrasonic flow meter, indicates flow 40 GPM. Record and document on Attachment 10.1, Information requested.
Boron Flow Rate Verification.
Comment:
Cue: Acknowledge communication and direct applicant to use Charging flow indication on CP-4. SAT / UNSAT Revision 0 Page 7 of 12 2011 NRC Walk Through Exam
JPM S1 TASK ELEMENT 17 STANDARD 7.1.14 Open Gravity Feed Valves Tank B, BAM-113B. Valve open.
Comment: Critical SAT / UNSAT TASK ELEMENT 18 STANDARD 7.1.15 Close Emergency Boration Valve, BAM-133, and document on Valve closed. 0.1, Boron Flow Rate Verification.
Comment: Critical SAT / UNSAT TASK ELEMENT 19 STANDARD 7.1.16 Stop Boric Acid Pump B. Pump secured.
Comment: Critical SAT / UNSAT TASK ELEMENT 20 STANDARD 7.1.16.1 Open Boric Acid Makeup Pump B Recirc Valve, BAM-126B, and Valve open.
document on Attachment 10.1, Boron Flow Rate Verification.
Comment:
SAT / UNSAT Revision 0 Page 8 of 12 2011 NRC Walk Through Exam
JPM S1 TASK ELEMENT 21 STANDARD 7.1.17 Verify Charging Header Flow, using ultrasonic flow meter, indicates 40 GPM. Record and document on Attachment 10.1, Boron Information requested.
Flow Rate Verification.
Comment:
Cue: Acknowledge communication and direct applicant to use Charging flow indication on CP-4. SAT / UNSAT TASK ELEMENT 22 STANDARD 7.1.18 Align Charging Pump suction source by performing either of the following at SM/CRS discretion and document on Attachment 10.1, Boron Flow Rate Verification:
- Open VCT Disch Valve, CVC-183 CVC-183 open or
- Open RWSP to Charging Pump Suction Isolation, CVC-507 Comment: Critical Cue: CRS directs that the Charging suction be aligned to the Volume Control Tank. SAT / UNSAT TASK ELEMENT 23 STANDARD 7.1.19 Close Gravity Feed Valves Tank B, BAM-113B, and document on Valve closed. 0.1, Boron Flow Rate Verification.
Comment: Critical SAT / UNSAT Revision 0 Page 9 of 12 2011 NRC Walk Through Exam
JPM S1 TASK ELEMENT 24 STANDARD 7.1.20 If Charging Line Shutoff Valves, CVC-218A and CVC-218B, were Not applicable.
closed, then Open CVC-218A and CVC-218B.
Comment:
SAT / UNSAT TASK ELEMENT 25 STANDARD 7.1.21 Restore CVCS normal operations, as directed by SM/CRS.
7.1.22 Submit for Independent Review. None 7.1.23 Submit copy to Programs Engineering for review.
Comment:
Task is complete at this point.
SAT / UNSAT END OF TASK Revision 0 Page 10 of 12 2011 NRC Walk Through Exam
JPM S1 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-190 There are no malfunctions or overrides for this JPM.
Revision 0 Page 11 of 12 2011 NRC Walk Through Exam
JPM S1 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- The plant is shutdown, entering a refueling outage.
INITIATING CUES:
Revision 0 Page 12 of 12 2011 NRC Walk Through Exam
REQUESTIAPPROVAL PAGE Normal Review Class (check one):
SAFETY RELATED OSRC QUALIFIED PROCEDURE REVIEWER PROCEDURE NUMBER: OP-903-096 REVISION: 007 TITLE: Boron Flow Rate Verification PROCEDURE OWNER lPosition Title): Assistant Operations Manager (Support)
TERM (check one): v Permanent Temporary Effective Date / Milestone (if applicable): 8/26/2008 Expiration Date / Milestone (if applicable): N/A PROCEDURE ACTION (Check one):
. Revision Deletion New Procedure DESCRIPTION AND JUSTIFICATION:
In Attachment 10.1 changed the order of review signoffs to provide for SM/CRS review following the Independent Reviewer signature. This change affects presentation and meets Editorial Correction criteria.
Request/Approval Page Continuation Sheet(s) attached.
REVIEW PROCESS Editorial Correction Technical Verification (CHECK ONE):
Normal ..
(Revisions Only) (Revisions Only)
REVIEW AND APPROVAL ACTIVITIES PRINT NAME OR SIGNATURE DATE PREPARER Perry Rodrigue 8/24/2008 EC SUPERVISOR Administrative Review and Approval (sign)
Ø-,-r N/A N/A CROSS-DISCIPLINE N/A N/A and INTERNAL N/A N/A REVIEWS (List Groups or N/A N/A Functions)
N/A N/A PROCESS APPLICABILITY N/A Performed PA Exclusfon V
DETERMINATION TECHNICAL Review Verification N/A QUALIFIED REVIEWER Review N/A GROUP/DEPT. HEAD Review Approval (sign,i N/A GM. PLANT OPERATIONS Review Approval (sign)
N/A VICE PRESIDENT, OPERATiONS Approval (sign) N/A C:eGacorr V2C
Surveillance Procedure OP-903-096 Boron Flow Rate Verification Revision 007 3M PRECAUTIONS AND LIMITATIONS 3.1 PREcAUTIoNs 3.1.1 If at any point in this procedure, charging flow to RCS is lost, then discontinue use of this procedure and return CVCS to normal operation.
3.2 LIMITATIoNs 3.2.1 When changing RCS boron concentration, then a minimum of one Reactor Coolant Pump one Shutdown Cooling Train shall be in service with a flow rate 2,000 GPM to provide adequate mixing.
3.2.2 This procedure is intended to be performed in conjunction with shutdown for refueling operations.
4
Surveillance Procedure OP903-096 Boron Flow Rate Verification Revision 007 7O PROCEDURE 7.1 BORON FLOW RATE VERIFIcATIoN 7.1 1 Verify one Charging Pump is operating, and document on Attachment 10.1 Boron Flow Rate Verification.
7.1.2 If the RCS is depressurized, then perform the following for accurate flow measurements:
7.1.2.1 Close Charging Line 1A Shutoff Valve, CVC-218A 7.1.2.2 Close Charging Line 2A Shutoff Valve, CVC-218B.
7.1.3 Place Makeup Mode selector switch in Manual.
7.1.4 Open Gravity Feed Valves TankA, BAM-113A.
7.1.5 Verify the following valves Closed:
- CVC-183 VCT Disch Valve
- CVC-507 RWSP to Charging Pump Suction Isolation 7.1.6 Verify Charging Header Flow, using ultrasonic flow meter, indicates 40 GPM.
Record and document on Attachment 10.1, Boron Flow Rate Verification.
7.1.7 Start Boric Acid Pump A.
7.1.7.1 Close Boric Acid Makeup Pump A Recirc Valve, BAM-126A.
7.1.8 Open Emergency Boration Valve, BAM-133, 7.1.9 Close Gravity Feed Valves Tank A, BAM-1 1 3A, and document on Attachment 10.1, Boron Flow Rate Verification.
7.1 .10 Verify Charging Header Flow, using ultrasonic flow meter, indicates 40 GPM.
Record and document on Attachment 10.1, Boron Flow Rate Verification.
7.1 .11 Start Boric Acid Pump B.
7.1.11.1 Close Boric Acid Makeup Pump B Recirc Valve, BAM-126B, 7.1 .12 Stop Boric Acid Pump A.
7.1 .12.1 Open Boric Acid Makeup Pump A Recirc Valve, BAM-1 26A, and document on Attachment 10.1, Boron Flow Rate Verification.
7.1 .13 Verify Charging Header Flow, using ultrasonic flow meter, indicates flow 40 GPM.
Record and document on Attachment 10.1, Boron Flow Rate Verification.
8
Surveillance Procedure OP-903-096 Boron Flow Rate Verification Revision 007 7.1.14 Open Gravity Feed Valves Tank B, BAM-113B.
7.1.15 Close Emergency Boration Valve, BAM-1 33, g document on Attachment 10.1, Boron Flow Rate Verification.
7.1.16 Stop Boric Acid Pump B.
7.1.16.1 Open Boric Acid Makeup Pump B Recirc Valve, BAM-126B, and document on Attachment 10.1, Boron Flow Rate Verification.
7.1.17 Verify Charging Header Flow, using ultrasonic flow meter, indicates 40 GPM.
Record and document on Attachment 10.1, Boron Flow Rate Verification.
7.1.18 Align Charging Pump suction source by performing either of the following at SM/CRS discretion and document on Attachment 10.1, Boron Flow Rate Verification:
- Open VCT Disch Valve, CVC-183 or
- Open RWSP to Charging Pump Suction Isolation, CVC-507 7.1 19 Close Gravity Feed Valves Tank 8, BAM-1 1 3B, and document on Attachment 10.1, Boron Flow Rate Verification.
7.1.20 If Charging Line Shutoff Valves, CVC218A and CVC-218B, were closed, then Open CVC-218A and CVC-218B.
7.1.21 Restore CVCS normal operations, as directed by SM/CRS.
7.1.22 Submit for Independent Review.
7.1.23 Submit copy to Programs Engineering for review.
9
10.1 BORON FLOW RATE VERIFICATION Permission:
SM/CR) date/Time Performed Verified STEP DESCRIPTION (Initials) (lnitiaI1 71.1 Charging Pump in operation A. AB, B (circle)
Flow Path Tank A Gravity Feed 71.6 Flowrate 7.1.9 Valve BAM-113A, Closed Flow Path Boric Acid Pump A 7.1.10 Flowrate 7.1.12.1 Valve BAM-126A, Open Flow Path Boric Acid Pump B 7.1.13 Flow rate 7.1.15 Valve BAM-133, Closed 7.1.16.1 Valve BAM-126B, Open Flow Path Tank B Gravity Feed 7.1.17 Flow rate Open*
7.1.18 CVC-183, CVC-507, Open*
71.19 Valve BAM-113B, Closed
- One of these valves may be NA OP-903-096 Revision 007 Attachment 10.1 (lof 2) 13
BORON FLOW RATE VERIFICATION (C0NTD)
M&TE Number Calibration Date Due Date (if used)
Test Accertance:
Each flow path tested delivers 40 GPM to Reactor Coolant System:
(initials)
Copy submitted to Programs Engineering for review:
(initials)
REMARKS:
Performed by:
(Signature) (Date)
Verified by:
(Signature) (Date)
Independent Reviewer: I (Signature) (Date/Time)
SM/CRS Review: I (Signature) (Date/Time)
OP-903-096 Revision 007 [LAST PAGE] Attachment 101 (2 of 2) 14
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE S2 Hot and Cold Leg Safety Injection Applicant:
Examiner:
JPM S2 JOB PERFORMANCE MEASURE DATA PAGE Task: Align Hot and Cold Leg Safety Injection for Trains A and B Task Standard: Applicant aligns Hot and Cold Leg Safety Injection in accordance with OP-902-009, Standard Appendices, Appendix 15.
References:
OP-902-002, Loss of Coolant Accident Recovery OP-902-009, Standard Appendices Alternate Path: Yes Time Critical: No Validation Time: 20 mins.
K/A 006 A4.07, ECCS pumps and valves Importance Rating 4.4 RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 8 2011 NRC Walk Through Exam
JPM S2 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-902-009, Standard Appendices, Appendix 15, Hot and Cold Leg Injection.
==
Description:==
This JPM occurs during a Loss of Coolant Accident. The applicant will receive direction to align simultaneous Hot and Cold Leg Safety Injection. SI-225 B will be closed, contrary to its Safety Injection Actuation position. The applicant should notice this difference and open SI-225 B when balancing the Hot and Cold Leg flows. All manipulations will occur at CP-8.
Applicant must obtain keys for the valves manipulated in this JPM.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 8 2011 NRC Walk Through Exam
JPM S2 Evaluator Note SI-225 B, HPSI Hdr B to RC Loop 1A Flow Control Valve, will be closed when this JPM is started. The applicant may notice this condition and open it at any time during the JPM. The task element for performing this action is Task Element 7.
1.1 Establish simultaneous Hot and Cold leg injection for Train A by performing the following:
TASK ELEMENT 1 STANDARD 1.1.a Close SI-219A, HPSI HEADER ORIFICE BYPASS valve. SI-219 A is closed.
Comment: Critical SAT / UNSAT TASK ELEMENT 2 STANDARD 1.1.b Open SI-502A, HOT LEG 1 INJECTION ISOLATION valve. SI-502 A is open.
Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD 1.1.c Open SI-506A, HOT LEG 1 INJECTION FLOW CONTROL valve. SI-506 A is open.
Comment: Critical SAT / UNSAT Revision 0 Page 4 of 8 2011 NRC Walk Through Exam
JPM S2 1.2 Establish simultaneous Hot and Cold leg injection for Train B by performing the following:
TASK ELEMENT 4 STANDARD 1.2.a Close SI-219B, HPSI HEADER ORIFICE BYPASS valve. SI-219 B is closed.
Comment: Critical SAT / UNSAT TASK ELEMENT 5 STANDARD 1.2.b Open SI-502B, HOT LEG 2 INJECTION ISOLATION valve. SI-502 B is open.
Comment: Critical SAT / UNSAT TASK ELEMENT 6 STANDARD 1.2.c Open SI-506B, HOT LEG 2 INJECTION FLOW CONTROL valve. SI-506 B is open.
Comment: Critical SAT / UNSAT Revision 0 Page 5 of 8 2011 NRC Walk Through Exam
JPM S2 Evaluator Note The applicant may report to the CRS that SI-225 B is open. If he asks for direction, request a recommendation from applicant. The applicant should open SI-225 B without a prompt.
TASK ELEMENT 7 STANDARD Open SI-225 B, HPSI Hdr B to RC Loop 1A Flow Control Valve. SI-225 B is open.
Comment: Critical Applicant may have discovered this valve alignment prior to this step and opened it. SAT / UNSAT With SI-225 B closed, the SI flow to Loop 1A will be half that of the other loops.
TASK ELEMENT 7 STANDARD The sum of all cold leg 1.3 WHEN hot and cold leg injection has been established, THEN adjust flows is approximately SI-506 A and SI-506 B to obtain the sum of ALL cold leg flows equal to equal to the sum of the hot the sum of the hot leg flows.
leg flows.
Comment: Critical Applicant can obtain Hot and Cold Leg flows from either the PMC, the meters on CP-8, or QSPDS. SAT / UNSAT After the initial alignment is complete, Hot Leg flow will be approximately 880 gpm and Cold Leg flow will be approximately 850 gpm. Applicant should throttle SI-506 A and/or B to reduce Hot Leg flow.
END OF TASK Revision 0 Page 6 of 8 2011 NRC Walk Through Exam
JPM S2 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-191 Verify the following Malfunctions:
o RC24 A 3%
o SI16 E True Place the Simulator in Run on the lead examiners cue.
Revision 0 Page 7 of 8 2011 NRC Walk Through Exam
JPM S2 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- A Loss of Coolant Accident occurred 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago.
- The crew has entered OP-902-002, Loss of Coolant Accident Recovery
- All requirements of step 47, Hot and Cold Leg Injection, have been met.
- You are the BOP operator.
INITIATING CUES:
- The Control Room Supervisor directs you to establish Hot and Cold Leg Injection in accordance with OP-902-009, Standard Appendices, Appendix 15.
Revision 0 Page 8 of 8 2011 NRC Walk Through Exam
WATERFORD 3 SES OP-902-002 Revision 013 Page 36 of 66 LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS Hot and Cold Leg Injection
- 47. IF elapsed time from the start of the event is between 2 and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> AND ANY of the following conditions exist:
- Pressurizer level is less than 7%
[23%]
- Reactor vessel level indicates at least one of the following:
- QSPDS REACTOR VESSEL LEVEL 5 is voided
- VESSEL LEVEL PLENUM less than 80%
THEN REFER TO Appendix 15, "Hot and Cold Leg Injection" and establish simultaneous hot and cold leg injection.
Reset Safety Systems
- 48. IF any ESFAS actuations have initiated AND are NO longer needed, THEN REFER TO Appendix 5, "ESFAS Reset" and reset ESFAS actuations as required.
WATERFORD 3 SES OP-902-009 Revision 301 Page 120 of 195 STANDARD APPENDICES Appendix 15 Page 1 of 2 Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS
____ 1.1 Establish simultaneous hot and cold leg injection for Train A by performing the following:
- b. Open SI 502A, HOT LEG 1 INJECTION ISOLATION valve.
- c. Open SI 506A, HOT LEG 1 INJECTION FLOW CONTROL valve.
____ 1.2 Establish simultaneous hot and cold leg injection for Train B by performing the following:
- b. Open SI 502B, HOT LEG 2 INJECTION ISOLATION valve.
- c. Open SI 506B, HOT LEG 2 INJECTION FLOW CONTROL valve.
WATERFORD 3 SES OP-902-009 Revision 301 Page 121 of 195 STANDARD APPENDICES Appendix 15 Page 2 of 2 INSTRUCTIONS CONTINGENCY ACTIONS
____ 1.3 WHEN hot and cold leg injection has been established, THEN adjust SI 506A and SI 506B to obtain the sum of ALL cold leg flows equal to the sum of the hot leg flows.
End of Appendix 15
Operating Instruction OI-038-00 Emergency Operating Procedures Revision 2 Operations Expectations / Guidance 5.2.5 Verify RCS Pressure Control The NPO checks Pressurizer pressure indicators. The NPO should be aware of the status of Pzr heaters. The heater may be deenergized due to low level heater cutout and will require restoration.
The NPO may restore power to Pzr heaters when Pzr level is restored to the normal operating band. The NPO should notify the CRS prior to taking this action.
If Pzr pressure cannot be maintained in the expected post trip band due to a malfunction of the pressurizer pressure controller, then the NPO may operate the PPCS by placing the Pzr Pressure controller in manual and adjusting the output.
The Pzr Spray valve controller may be placed in manual and the spray valve selector switch operated to regain Pzr pressure control.
A stuck open Pzr Spray valve is considered an equipment failure and is not addressed in the EOPs. If during operation of the PPCS, the Spray Valve controller or the Spray valve selector switch does not result in regaining control of the Pzr pressure, then the RCP should be tripped in the loop with the stuck open spray valve (Loop 1A or 1B). If tripping the applicable RCP does not stabilize Pzr pressure, then it may be necessary to continue securing RCPs until Pzr pressure does stabilize. [SEN 230]
Check SIAS initiated by ensuring the Trip Path lights are not illuminated on CP-7 for SIAS and that the SIAS Train Logic Initiated annunciators (CP-2 panel K G-19 & G-20) are in alarm. Other expectations for this step include verifying all Safety Injection pumps running, all SI flow control valves open and all available charging pumps running.
Check CIAS initiated by ensuring the Trip Path lights are not illuminated on CP-7 for CIAS and that the CIAS Train Logic Initiated annunciators (CP-2 panel K E-19 & E-20) are in alarm. Other expectations for this step include verifying all valves closed on the bottom row of CP-8 and CP-4.
Check RCPs operating within the limits of the RCP NPSH curve. The operator should realize that if RCS conditions are at NOP and NOT then the NPSH requirements are satisfied. The RCP NPSH is more conservative than the RCS subcooling curve of 28 F. Satisfying the subcooling requirement does not necessarily mean the NPSH requirement is met. When using the RCP NPSH curve, the operator should use cold leg temperature when available to determine NPSH.
11
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE S3 RCS Vent System Functional Test Applicant:
Examiner:
JPM S3 JOB PERFORMANCE MEASURE DATA PAGE Task: Test RC-1014, 1015, and RC-1017 in accordance with OP-903-098, RCS Vent System Functional Check and Valve Lineup Verification Task Standard: Perform surveillance OP-903-098, RCS Vent System Functional Check and Valve Lineup Verification, section 7.1 for RC-1014, 1015, and 1017.
References:
OP-903-098, RCS Vent System Functional Check and Valve Lineup Verification Alternate Path: No Time Critical: No Validation Time: 20 mins.
K/A 010 K1.05, Pressurizer Relief Tank System Importance Rating 3.4 RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 13 2011 NRC Walk Through Exam
JPM S3 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-903-098, RCS Vent System Functional Check and Valve Lineup Verification
==
Description:==
This task tests the RCS Vent valves to the Quench Tank. The surveillance is written for 6 valves, but the JPM will only be performed on 3 of the 6. Steps 7.1.1 through 7.1.8 setup conditions for the test. Step 7.1.9 tests RC-1014 and step 7.1.10 tests RC-1015 and RC-1017. Steps 7.1.11 and 7.1.12 will not be performed. This task is performed at CP-8 with a Quench Tank pressure verification on CP-2.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 13 2011 NRC Walk Through Exam
JPM S3 TASK ELEMENT 1 STANDARD NOTE This section verifies valve opening and remote position indication. It does not meet the requirements for Post Maintenance Stroke Time Testing. Reviews Note Perform applicable sections of OP-903-033, Cold Shutdown IST Valve Tests for retest following maintenance.
Comment:
SAT / UNSAT TASK ELEMENT 2 STANDARD 7.1.1 Obtain SM/CRS permission to perform this section and document on Attachment 10.1, RCS Vent System Functional Check Data Sheet, Permission is on ATT.10.1 and Attachment 10.2, RCS Vent Path Valve Lineup Verification.
Comment:
SAT / UNSAT TASK ELEMENT 3 STANDARD 7.1.2 Verify RCS pressure is 150 - 392 PSIA. Given in Initial Conditions Comment:
SAT / UNSAT Revision 0 Page 4 of 13 2011 NRC Walk Through Exam
JPM S3 TASK ELEMENT 4 STANDARD NOTE Valves in Attachment 10.2 which are currently inaccessible may be verified Locked Open by alternate means (no existing deviations, tagouts, etc.) to facilitate completion of Section 7.1 testing. However, valves verified by alternate means shall be physically verified Locked Reviews Note Open every 18 months in order to meet Technical Specification Surveillance Requirement 4.4.10.a. Valves that have been verified by alternate means should be physically verified Locked Open as soon as they become accessible and these verifications documented on 0.2.
Comment:
SAT / UNSAT TASK ELEMENT 5 STANDARD Complete per Initial 7.1.3 Complete Attachment 10.2.
Conditions Comment:
SAT / UNSAT TASK ELEMENT 6 STANDARD Control Board Keys 7.1.4 Obtain keys to supply power to Reactor Vent Solenoids.
obtained from key locker Comment: Critical SAT / UNSAT TASK ELEMENT 7 STANDARD Place both Key Switches to 7.1.5 Turn key switches for Reactor Vent Solenoids Power to On.
ON.
Comment: Critical SAT / UNSAT Revision 0 Page 5 of 13 2011 NRC Walk Through Exam
JPM S3 TASK ELEMENT 8 STANDARD Checks Vent Header 7.1.6 Verify RCS Vent Header pressure is approximately equal to Pressure on CP-8 ~ equal Quench Tank pressure. to Quench Tank Pressure on CP-2.
Comment:
SAT / UNSAT TASK ELEMENT 9 STANDARD NOTE The requirements for remote position indication are met by a pressure change in accordance with applicable steps along with position status Reviews Note lights on CP-8 accurately indicating appropriate valve open and closed positions.
Comment:
SAT / UNSAT TASK ELEMENT 10 STANDARD 7.1.7 Verify Green (closed) status lights located on CP-8 Illuminated for the following valves:
- RC-1014 Reactor Vessel Vent To Quench Tank Isolation
- RC-1015 Reactor Vessel Vent To Quench Tank Isolation Verifies Green lights lit as
- RC-3184 Pressurizer Vent To Quench Tank directed in step.
- RC-3183 Pressurizer Vent To Quench Tank
- RC-1017 Reactor/Pressurizer Vents To Quench Tank Header Isolation
- RC-3186 Reactor/Pressurizer Vent To Quench Tank Isolation Comment:
SAT / UNSAT Revision 0 Page 6 of 13 2011 NRC Walk Through Exam
JPM S3 TASK ELEMENT 11 STANDARD 7.1.8 Record RCS Vent Hdr Press, as read from Reactor Vent Lines Checks RC-IPI-0110 and Pressure Indicator, RC-IPI-0110 on Attachment 10.1. records value on ATT. 10.1 Comment: Critical SAT / UNSAT TASK ELEMENT 12 STANDARD Places C/S for RC-1014 to 7.1.9.1 Open Reactor Vessel Vent to Quench Tank Isolation, RC-1014.
OPEN.
Comment: Critical SAT / UNSAT TASK ELEMENT 13 STANDARD Allows pressure to stabilize 7.1.9.2 When RCS Vent Hdr Pressure, as read on RC-IPI-0110, and records value of RC-Stabilizes, record pressure on Attachment 10.1.
IPI-0110 on ATT. 10.1.
Comment: Critical SAT / UNSAT TASK ELEMENT 14 STANDARD 7.1.9.3 Verify Green status light for Reactor Vessel Vent to Quench Tank Verifies OPEN indication for Isolation, RC-1014, Extinguished, and Red light Illuminated. Document RC-1014 and documents on Attachment 10.1. (May be N/A.) on ATT 10.1 Comment:
SAT / UNSAT Revision 0 Page 7 of 13 2011 NRC Walk Through Exam
JPM S3 TASK ELEMENT 15 STANDARD 7.1.9.4 Close Reactor Vessel Vent to Quench Tank Isolation, RC-1014. RC-1014 Closed.
Comment: Critical SAT / UNSAT TASK ELEMENT 16 STANDARD 7.1.9.5 Document Reactor Vessel Vent to Quench Tank Isolation, RC- Document RC-1014 1014, final position on Attachment 10.1. position on ATT 10.1 Comment:
SAT / UNSAT TASK ELEMENT 17 STANDARD 7.1.10.1 Open Reactor/Pressurizer Vents to Quench Tank Header Takes RC-1017 C/S to Isolation, RC-1017. OPEN Comment: Critical SAT / UNSAT TASK ELEMENT 18 STANDARD 7.1.10.2 When RCS Vent Hdr Pressure, as read on RC-IPI-0110, Checks RC-IPI-0110 and stabilizes, record pressure on Attachment 10.1. records value on ATT 10.1 Comment: Critical SAT / UNSAT Revision 0 Page 8 of 13 2011 NRC Walk Through Exam
JPM S3 TASK ELEMENT 19 STANDARD 7.1.10.3 Verify Green status light for Reactor Pressurizer Vents to Verifies open indication for Quench Tank Header Isolation, RC-1017, Extinguished, and Red light RC-1017 and records on Illuminated. Document on Attachment 10.1. (May be N/A.) ATT 10.1 Comment:
SAT / UNSAT TASK ELEMENT 20 STANDARD 7.1.10.4 Close Reactor/Pressurizer Vents to Quench Tank Hdr Isolation, RC-1017 Closed RC-1017.
Comment: Critical SAT / UNSAT TASK ELEMENT 21 STANDARD Takes C/S for RC-1015 to 7.1.10.5 Open Reactor Vessel Vent to Quench Tank Isolation, RC-1015.
OPEN.
Comment: Critical SAT / UNSAT TASK ELEMENT 22 STANDARD Allows RC-IPI-0110 7.1.10.6 When RCS Vent Hdr Pressure, as read on RC-IPI-0110, indication to stabilize and stabilizes, record pressure on Attachment 10.1.
records on ATT 10.1 Comment: Critical SAT / UNSAT Revision 0 Page 9 of 13 2011 NRC Walk Through Exam
JPM S3 TASK ELEMENT 23 STANDARD 7.1.10.7 Verify Green status light for Reactor Vessel Vent to Quench Verifies open indication for Tank Isolation RC-1015, Extinguished, and Red light Illuminated. RC-1015 and records on Document on Attachment 10.1. (May be N/A.) ATT 10.1 Comment:
SAT / UNSAT TASK ELEMENT 24 STANDARD 7.1.10.8 Close Reactor Vessel Vent to Quench Tank Isolation, RC-1015. RC-1015 Closed Comment: Critical SAT / UNSAT TASK ELEMENT 25 STANDARD 7.1.10.9 Document Reactor Vessel Vent to Quench Tank Isolation, RC- Records RC-1015 position 1015, final position on Attachment 10.1. on ATT 10.1 Comment:
SAT / UNSAT TASK ELEMENT 26 STANDARD 7.1.10.10 Lower RCS Vent Header pressure to approximately Quench Cycles RC-1017 to equalize Tank pressure by cycling Reactor/Pressurizer Vents to Quench Tank Hdr pressures Isolation, RC-1017. RC-1017 Closed Comment: Critical SAT / UNSAT Revision 0 Page 10 of 13 2011 NRC Walk Through Exam
JPM S3 TASK ELEMENT 27 STANDARD 7.1.10.11 Document Reactor/Pressurizer Vent to Quench Tank Hdr Document RC-1017 Isolation, RC-1017 final position and RCS Vent Header pressure on position on ATT 10.1 0.1.
Comment:
SAT / UNSAT TASK ELEMENT 28 STANDARD 7.1.13 Turn power Off and remove keys for solenoid power supplies. Both Keyswitches in OFF Document on Attachment 10.1. with keys removed Comment: Critical SAT / UNSAT END OF TASK Revision 0 Page 11 of 13 2011 NRC Walk Through Exam
JPM S3 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-190 There are no malfunctions or overrides for this JPM.
Revision 0 Page 12 of 13 2011 NRC Walk Through Exam
JPM S3 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- The plant is in Mode 5.
- The RCS is filled and vented.
- Work has been completed and tagouts cleared for the following valves:
o RC-1014, Reactor Vessel Vent to Quench Tank Isolation o RC-1015, Reactor/Pressurizer Vents to Quench Tank Header Isolation o RC-1017, Reactor Vessel Vent to Quench Tank Isolation.
- Attachment 10.2, RCS Vent Path Valve Lineup Verification, for OP-903-098 has been completed and reviewed.
INITIATING CUES:
- The CRS directs you to test RC-1014, RC-1015, and RC-1017 in accordance with OP-903-098, RCS Vent System Functional Check and Valve Lineup Verification , section 7.1.
- The CRS has marked steps 7.1.11 and 7.1.12 as not applicable since only RC-1014, RC-1015, and RC-1017 are being tested.
Revision 0 Page 13 of 13 2011 NRC Walk Through Exam
REQUEST/APPROVAL PAGE m&o SA F E TY RE LAT E D V
PROCEDURE PROCEDURE NUMBER: OP-903-098 REVISION: 301 TITLE: RCS Vent System Functional Check and Valve Lineup Verification PROCEDURE OWNERPOSIIIOn Thie): Assistant Operations Manager (Support)
TERM (eck one): V. Pemianent -. Temporary EffDaefr,jstoneOfappiicabIe): 4?eo ExpiraborY Date / Milestone (If applicable): N/A PROCEDURE ACTION (Clack one):
R.b1on Deletion New Procedu, DESCRIPTION AND JUSTIFICATION:
(a) In step 32.3 changed the term Engineering Request to Engineering Change. The terminology change supports the Engineering Change facility that Is currently active in INDUS Access Suite (lAS) and which replaced the This change is a correction of a reference use of the Engineering Request Database at Waterford 3 on 2123/2007.
term only and meets Editonal Correction criteria.
Request/Approval Page ContinuatIon Sheet(s) attached.
REVIEW PROCESS Normal w EC*tDd.I Corctlon Technical V*d&atlOn (CHECK ONE): (Revisions Only) (Revisions Only)
REVIEW AND APPROVAL ACTIVrnES PRINT NAME OR SIGNATURE DATE David R Voisin 12/27/2007 PREPARER EC SUPERViSOR Administrative Review and Approval 144g.
CROSS-DISCIPLINE N/A N/A and INTERNAL N/A N/A REVIEWS (List Groups or N/A N/A FunilonS)
N/A N/A PROCESS APPLICABILITY . N/A Performed PA Exclusion DETERMINATION TECHNICAL Review Verification N/A QUALIFIED REVIEWER Review N/A GROUP/DEPT. HEAD Review Approval (sign) N/A GM, PLANT OPERATIONS Review Approval (sign) N/A ViCE PRESIDENT, OPERATIONS Approval (sign) N/A Ge a Ft.,,, W2 09 09e
Surveillance Procedure OP-903-098 RCS Vent System Functional Check and Valve Lineup Verification Revision 301 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS NONE 3.2 LIMITATIoNs 3.2.1 Section 7.1 of this procedure must be performed at least once every 18 months in order to satisfy Technical Specification Surveillance Requirements 4.4.lOa, 4.4.lOb, and 4.4.lOc.
3.2.2 Section 7.1 of this procedure must be performed in its entirety at least once every two (2) years in order to satisfy the Remote Position Verification surveillance requirement of Technical Specification 6.5.8 and OM-1 0 for valves tested.
3.2.3 Where an instrument specified in this procedure is unavailable, a substitute instrument or M&TE may be used provided Programs Engineering has evaluated the substitution, confirmed that the substitute meets the requirements of OMa 1988 Part 6 Table 1, and that the location of the instrument does not create an unacceptable change in the test data. The evaluation shall be performed as an Engineering Change should document the reason the required instrument is unavailable. The Engineering Change should be included with the completed surveillance.
4
Surveillance Procedure OP-903-098 RCS Vent System Functional Check and Valve Lineup Verification Revision 301 7O PROCEDURE 7.1 REACTOR VENT TEST NOTE This section verifies valve opening and remote position indication. It does not meet the requirements for Post Maintenance Stroke Time Testing. Perform applicable sections of OP 903-033, Cold Shutdown 1ST Valve Tests for retest following maintenance.
7.1.1 Obtain SM/CRS permission to perform this section and document on Attachment 10.1, RCS Vent System Functional Check Data Sheet, and Attachment 10.2, RCS Vent Path Valve Lineup Verification.
7.1.2 Verify RCS pressure is 150 392 PSIA.
NOTE Valves in Attachment 10.2 which are currently inaccessible may be verified Locked Open by alternate means (no existing deviations, tagouts, etc.) to facilitate completion of Section 7.1 testing. However, valves verified by alternate means shall be physically verified Locked Open every 18 months in order to meet Technical Specification Surveillance Requirement 4.4.10.a. Valves that have been verified by alternate means should be physically verified Locked Open as soon as they become accessible and these verifications documented on 0.2.
7.1.3 Complete Attachment 10.2.
7.1.4 Obtain keys to supply power to Reactor Vent Solenoids.
7.1.5 Turn key switches for Reactor Vent Solenoids Power to On.
7.1.6 Verify RCS Vent Header pressure is approximately equal to Quench Tank pressure.
8
Surveillance Procedure OP-903-098 RCS Vent System Functional Check and Valve Lineup Verification Revision 301 NOTE The requirements for remote position indication are met by a pressure change in accordance with applicable steps along with position status lights on CP-8 accurately indicating appropriate valve open and closed positions.
7.1.7 Verify Green (closed) status lights located on CP-8 Illuminated for the following valves:
- RC-1014 Reactor Vessel Vent To Quench Tank Isolation
- RC-1 015 Reactor Vessel Vent To Quench Tank Isolation
- RC-31 84 Pressurizer Vent To Quench Tank
- RC-31 83 Pressurizer Vent To Quench Tank
- RC-1 017 Reactor/Pressurizer Vents To Quench Tank Header Isolation
- RC-3186 Reactor/Pressurizer Vent To Quench Tank Isolation 7.1.8 Record RCS Vent Hdr Press, as read from Reactor Vent Lines Pressure Indicator, RC-lPI-0110 on Attachment 10.1.
7.1.9 Testing Reactor Vessel Vent to Quench Tank Isolation, RC-1014.
7.1.9.1 Open Reactor Vessel Vent to Quench Tank Isolation, RC-1014.
7.1.9.2 When RCS Vent Hdr Pressure, as read on RC-IPI-01 10, Stabilizes, record pressure on Attachment 10.1.
7.1.9.3 Verify Green status light for Reactor Vessel Vent to Quench Tank Isolation, RC-1014, Extinguished, and Red light Illuminated. Document on Attachment 10.1. (MaybeN/A.)
7.1.9.4 Close Reactor Vessel Vent to Quench Tank Isolation, RC-1014.
7.1.9.5 Document Reactor Vessel Vent to Quench Tank Isolation, RC-1 014, final position on Attachment 10.1.
9
Surveillance Procedure OP-903-098 RCS Vent System Functional Check and Valve Lineup Verification Revision 301 7.1.10 Testing Reactor/Pressurizer Vents to Quench Tank Header Isolation, RC-1017, and Reactor Vessel Vent to Quench Tank Isolation, RC-1015.
7.1.10.1 Open Reactor/Pressurizer Vents to Quench Tank Header Isolation, RC-1017.
7.1.10.2 When RCS Vent Hdr Pressure, as read on RC-IPI-01 10, stabilizes, record pressure on Attachment 10.1.
7.1.10.3 Verify Green status light for Reactor Pressunzer Ventsto Quench Tank Header Isolation, RC-1017, Extinguished, and Red light Illuminated.
Document on Attachment 10.1. (May be N/A.)
7.1.10.4 Close Reactor/Pressurizer Vents to Quench Tank Hdr Isolation, RC-1017.
7.1.10.5 Open Reactor Vessel Vent to Quench Tank Isolation, RC-1015.
7.1.10.6 When RCS Vent Hdr Pressure, as read on RC-lPl-0110, stabilizes, record pressure on Attachment 10.1.
7.1.10.7 Verify Green status light for Reactor Vessel Vent to Quench Tank Isolation RC-1015, Extinguished, and Red light Illuminated. Document on Attachment 10.1. (MaybeN/A.)
7.1.10.8 Close Reactor Vessel Vent to Quench Tank Isolation, RC-1015.
7.1.10.9 Document Reactor Vessel Vent to Quench Tank Isolation, RC-1015, final position on Attachment 10.1.
7.1.10.10 Lower RCS Vent Header pressure to approximately Quench Tank pressure by cycling Reactor/Pressurizer Vents to Quench Tank Hdr Isolation, RC-1 017.
7.1.10.11 Document Reactor/Pressurizer Vent to Quench Tank Hdr Isolation, RC-1017 final position and RCS Vent Header pressure on Attachment 10.1.
?+/-t Testing Pressurizer Vent to Quench Tank, RC-3183.
tttt Open Pressurizer Vent to Quench Tank, RC-31 83.
44+2 When RCS Vent Hdr Pressure, as read on RC-lPl-0110, stabilizes, record pressure on Attachment 101.
744+& Verify Green status light for Pressurizer Vent to Quench Tank, RC-31 83, Extinguished, and Red light Illuminated. Document on Attachment 10.1.
(May be N/A.)
jh 01 1+zr Close Pressurizer Vent to Quench Tank, RC-31 83.
J4.4#5 Document Pressurizer Vent to Quench Tank, RC-3183, final position on Attachment 10.1.
10
Surveillance Procedure OP-903-098 RCS Vent System Functional Check and Valve Lineup Verification Revision 301
?ti2 Testing Reactor/Pressurizer Vent to Quench Tank Isolation, RC-31 86, and Pressurizer Vent to Quench Tank, RC-31 84.
.?tT2T Open Reactor/Pressurizer Vent to Quench Tank Isolation, RC-3186.
When RCS Vent Hdr Pressure, as read on RC-IPI-011O, stabilizes, record pressure on Attachment 10.1.
-+tt2 Verify Green status light for Reactor/Pressurizer Vent to Quench Tank Isolation, RC-3186, Extinguished, and Red light Illuminated. Document on Attachment 101. (May be N/A.)
A/J 4+24- Close Reactor/Pressurizer Vent to Quench Tank Isolation, RC-31 86.
4+2&- Open Pressurizer Vent to Quench Tank, RC-31 84.
.4.426 When RCS Vent Hdr Pressure, as read on RC-lPl-0110, stabilizes, record pressure on Attachment 10.1.
Verify Green status light for Pressurizer Vent to Quench Tank, RC-31 84, Extinguished, and Red light Illuminated. Document on Attachment 10.1.
(May be N/A.)
7-tt2fr Close Pressurizer Vent to Quench Tank, RC-3184.
4+29 Document Pressurizer Vent to Quench Tank, RC-31 84, final position on Attachment 10.1.
.4424G. Lower RCS Vent Header pressure to approximately Quench Tank pressure by cycling Reactor/Pressurizer Vent to Quench Tank Isolation, RC-3186.
-++2t Document Reactor/Pressurizer Vent to Quench Tank Isolation, RC-3186 final position and RCS Vent Header pressure on Attachment 10.1.
7.1.13 Turn power Off remove keys for solenoid power supplies. Document on Attachment 10.1.
ii
10.1 RCS VENT SYSTEM FUNCTIONAL CHECK DATA SHEET WO Number: S$/1 )Z3 SM/CRS Permission: / O2o (Signature) (Date/Time)
RCS VENT HDR STATUS STEP VALVE SEE INITIAL INITIAL PREs LIGHT FINAL POSITION ACCEPTANCE CRITERIA No. TESTED NOTE PERF. VERIF.
(RC-IPI-ollo) C 718 1 <15OPSIA 71.9.2 RC-1014 2 150 PSIA 7.1.9.3 RC1014 5 Green Not I .jrnrintxi, Red iIIdrnirlatd 7 1 95 RC-1014 ULOSED 71.10.2 RC-1017 3 <150 PSIA 7.1,10.3 RC-1017 5 Green Not IHum nated, Red IIfUrn:nated 7.1.10.6 RC-1015 2 150 PSIA 7.1.10.7 RC-1015 5 Green Not IIuminated, Red Illuminated 7 1 10 9 RC 1015 2 CLOSED 7,1,10,11 RC-1017 3 CLOSED <150 PSIA
.i A 7.1.11.2 RC-3183 4 pJ/_ 15OPSIA 7.1.11,3 RC-3183 5 ,J/A_. f Green Not IIuniateci. Red lliiiminnted 71 11 5 RC 3183 CLOSED 7.1.12.2 RC-3186 3 <150 PSIA 7.1.12.3 RC-3186 5 Green Noti Iminated, Red IImnated 7.1.12.6 RC-3184 4 15OPSIA 7.1.12.7 RC-3184 5 l Green Not Illuiniriuted, Red Illuminated 7.1,12.9 RC-3184 CLOSED 7.1.12.11 RC-3186 3 <150 PSIA 7.1.13 - KEYS REMOVED OP-903-098 Revision 301 Attachment 10.1 (1 of 2) 20
RCS VENT SYSTEM FUNCTIONAL CHECK DATA SHEET (coNTD)
NOTE 1: Ensures that RCS Vent Header Pressure is less than RCS Pressure so that positive indication of the Opening of Reactor Vessel Vents can be obtained.
NOTE 2: RCS Vent Header Pressure 150 PSIA provides positive indication that Reactor Vessel Vent to Quench Tank, RC-1014 (RC-1015), Opened and Reactor/Pressurizer Vent to Quench Tank Hdr Isolations, RC-3186 and RC-1017, are Closed.
NOTE 3: RCS Vent Header Pressure <150 PSIA provides positive indication that Reactor/Pressurizer Vent to Quench Tank Hdr Isolation, RC-1017 (RC 3186), Opened and Reactor Vessel Vent to Quench Tank Isolations, RC-1012 and RC-1013, and Pressurizer Vents to Quench Tank, RC-3183 and RC-3184, are Closed.
NOTE 4: RCS Vent Header Pressure 150 PSIA provides positive indication that Pressurizer Vent to Quench Tank, RC-3183 (RC-3184), Opened and Reactor/Pressurizer Vent to Quench Tank Hdr Isolations, RC-3186 and RC-1017, are Closed.
NOTE 5: Status light change, Green Closed light Extinguished and Red Open light Illuminated, indicating valve position.
REMARKS:
Performed by:
(Signature) (Date)
Verified by:
(Signature) (Date)
SM/CRS Review: I (Signature) (Date/Time)
OP-9O3O98 Revision 301 Attachment 10.1 (2 of 2) 21
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE S4 Main Feedwater Pump Shutdown at Power Applicant:
Examiner:
JPM S4 JOB PERFORMANCE MEASURE DATA PAGE Task: Secure Main Feedwater Pump B at Power Task Standard: Applicant secures Main Feedwater Pump B in accordance with OP-003-033, Main Feedwater.
References:
OP-003-033, Main Feedwater Alternate Path: No Time Critical: No Validation Time: 20 mins.
K/A 059 A4.03 Feedwater control during power Importance Rating 2.9 increase and decrease RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 9 2011 NRC Walk Through Exam
JPM S4 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-003-033, Main Feedwater
==
Description:==
The applicant will be tasked securing Main Feedwater Pump B with the plant at power in accordance with OP-003-033, Main Feedwater. All manipulations will occur at CP-1. There are no faults in this JPM.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 9 2011 NRC Walk Through Exam
JPM S4 TASK ELEMENT 1 STANDARD NOTE During plant shutdown or load reduction, a Main Feedwater Pump may Note reviewed.
be removed from service when feedwater flow has been reduced to approximately 50%.
Comment:
SAT / UNSAT TASK ELEMENT 2 STANDARD 7.1.1 If one SGFP is being removed when both are in service, then verify Reactor Power Cutback System Auto Actuate Out of Service push-button Verification complete.
is illuminated.
Comment:
SAT / UNSAT TASK ELEMENT 3 STANDARD 7.1.2 Place SGFP A(B) Speed Controller, FW-IHIC-1107(1108), in Controller in Manual.
MANUAL.
Comment: Critical SAT / UNSAT TASK ELEMENT 4 STANDARD NOTE Steam Generator Feed Pump A(B) Recirc Flow Control Valve, FW-111A(B), is rated for 4,600 GPM. Main Feedwater Pump operation at Note reviewed.
flows below approximately 8,000 GPM can result in recirculation of flow and elevated pump vibration. This is acceptable based on the relatively short duration of the high vibration condition. [CR-WF3-2003-2990]
Comment:
SAT / UNSAT Revision 0 Page 4 of 9 2011 NRC Walk Through Exam
JPM S4 TASK ELEMENT 5 STANDARD 7.1.3 Throttle Steam Generator Feed Pump A(B) Recirc Flow Control, FW-111 B throttled.
FW-111A(B), to maintain adequate Steam Generator Feed Pump flow.
Comment: Critical SAT / UNSAT TASK ELEMENT 6 STANDARD NOTE As speed is lowered on SGFP being removed from service, verify speed Note reviewed.
of other SGFP rises to assume load of pump being removed from service.
Comment:
SAT / UNSAT TASK ELEMENT 7 STANDARD 7.1.4 Slowly lower SGFP A(B) speed to minimum (3900 RPM) using Speed lowered to 3800 -
SGFP A(B) Speed Controller, FW-IHIC-1107(1108). 4000 rpm Comment: Critical SAT / UNSAT TASK ELEMENT 8 STANDARD NOTE If SGFP Speed Balance Meter is >"0" on local control panel, then INCREASE FAST push-button is used to lower meter. If SGFP Speed Note reviewed.
Balance Meter is <"0" on local control panel, then DECREASE FAST push-button is used to raise meter. May take several seconds to respond.
Comment:
SAT / UNSAT Revision 0 Page 5 of 9 2011 NRC Walk Through Exam
JPM S4 TASK ELEMENT 9 STANDARD 7.1.5 Adjust SGFP A(B) Speed Balance Meter to "0" on local control Directs TGB Watch to panel using INCREASE FAST and DECREASE FAST push-buttons. place local controls in 7.1.5.1 Place local controls in MANUAL manual.
Comment: Critical SAT / UNSAT TASK ELEMENT 10 STANDARD 7.1.6 Lower SGFP A(B) speed by turning Feedwater Turbine Governor Speed reduced.
Control switch to LESS on CP-1.
Comment: Critical SAT / UNSAT TASK ELEMENT 11 STANDARD 7.1.7 Monitor SGFP A(B) supervisory instruments during SGFP load reduction and verify:
- Rotor vibration <3 mils Parameters monitored.
- Thrust-bearing normal thrust <5 mils
- Thrust-bearing reverse <5 mils Comment:
SAT / UNSAT TASK ELEMENT 12 STANDARD 7.1.8 Maintain bearing drain temperature >100°F. Parameter monitored.
Comment:
SAT / UNSAT Revision 0 Page 6 of 9 2011 NRC Walk Through Exam
JPM S4 TASK ELEMENT 13 STANDARD 7.1.9 When SGFP A(B) speed reaches ~3200 RPM, then verify Open the following:
- RS-319A(B) SGFPT A(B) LP Throttle Above Seat Drain to Verification complete.
Condenser
- MS-220A(B) SGFPT A(B) HP Throttle Valve Drain Comment:
SAT / UNSAT TASK ELEMENT 14 STANDARD When SGFP A(B) speed reaches 3000 RPM, then perform the following:
7.1.10.1 Trip SGFP A(B).
7.1.10.2 Verify Closed the following:
- MS-217A(B) HP Stop Valve
- RS-317A(B) Reheat Steam to FWPT A(B) LP Governor
- FW-118A(B) Stm Generator Feed Pump A(B)
Discharge Comment: Critical Verifications are not critical.
SAT / UNSAT JPM can be terminated after MFW Pump is tripped.
END OF TASK Revision 0 Page 7 of 9 2011 NRC Walk Through Exam
JPM S4 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-195 Assign remote FWR88 to Trigger 1.
There are no Malfunctions for this JPM.
Revision 0 Page 8 of 9 2011 NRC Walk Through Exam
JPM S4 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Main Feedwater Pump B must be secured for repairs.
- The previous shift reduced plant power as directed by the Shift Manger.
INITIATING CUES:
- The Control Room Supervisor directs you to secure Main Feedwater Pump B in accordance with OP-003-033, Main Feedwater.
Revision 0 Page 9 of 9 2011 NRC Walk Through Exam
System Operating Procedure OP-003-033 Main Feedwater Revision 303 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS 3.1.1 Do not start any oil pump if reservoir oil temperature is <70 F.
3.1.2 Main Feedwater Pump Turbine should be accelerated through critical speed of 2500 RPM quickly and smoothly.
3.1.3 Main Feedwater Turbine should remain on turning gear for cooling at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after removing gland-sealing steam.
3.1.4 With no Reactor Coolant Pumps running, the temperature of the Secondary Coolant in the Steam Generator shall be >115 F when pressure in the Steam Generator is >210 PSIG, in accordance with T.S. 3.7.2. If this requirement is not satisfied, then an engineering evaluation must be performed.
3.1.5 Main Feedwater Pump Warming Precautions 3.1.5.1 Pacific Pumps recommends a maximum warm-up rate of 50 F/hr, not to exceed 75 F/hr.
3.1.5.2 The warming process should continue until surface temperature of pump casing near top of volute case is within 50 F of the hot fluid temperature as indicated on the following computer points:
A08105 SGFP A CASE TOP TEMP A08106 SGFP A CASE BOTTOM TEMP A08405 SGFP B CASE TOP TEMP A08406 SGFP B CASE BOTTOM TEMP 3.1.5.3 Oil pressure leaving the Steam Generator Feedwater Pump (SGFP) oil coolers should be >20 PSIG and temperature 120 F.
3.1.5.4 Normal return operating temperatures from the SGFP and pump bearings should be 120 F and 140 F.
3.1.5.5 Normal operating temperatures of the turbine and pump bearing metal should not exceed 185 F.
3.1.5.6 Prior to warming up feed pump, perform the following:
3.1.5.6.1 Verify in AUTO local hand switches for FWPT A(B) Drain Tank Outlet to Condenser A Hotwell, ES-7079A(B).
3.1.5.6.2 Locally verify Open FWPT A(B) Drain Tank Outlet to Condenser A Hotwell, ES-7079A(B).
5
System Operating Procedure OP-003-033 Main Feedwater Revision 303 3.1.5.7 Main Feedwater Pump operation at flows below approximately 8000 GPM can result in recirculation flow and elevated pump vibration.
[CR-WF3-2003-2990]
3.1.6 Do not operate "Overspeed Test Permit" unless directed to by the SM/CRS. This will cause an actual overspeed of the SGFP.
3.1.7 Verify proper communications between Control Room and Auxiliary Operator at SGFP Local Control Panel prior to any SGFP local speed control manipulations.
3.1.8 If Condenser A Hotwell level reaches 60 inches rising, then FWPT A(B) Drain Tank Outlet to Condenser A Hotwell, ES-7079A and ES-7079B, will Close. Water cannot drain to the Condenser Hotwell and may cause Feed Pump Turbine blade damage.
3.1.9 When returning level instruments to service, slowly Open the level column upper isolation valve first, then slowly Open the lower isolation valve. This prevents a surge of water into the level column causing the instrument float to cycle violently up and down. This can knock the instrument out of alignment and/or result in damage to the linkage inside the instrument.
3.2 LIMITATIONS 3.2.1 Prior to filling Main Feedwater System, a sample of demineralized water (Condensate Storage Tank) should be analyzed to verify water quality.
3.2.2 Do not operate Feedwater Line 1(2) to Blowdown Isolation, FW-179A(B) or Emergency Feedwater Hdr A(B) to Blowdown EMF Isolation, EFW-220A(B).
[P-6183, P-6212]
3.2.3 Failure of one of two operating Condensate Pumps may automatically trip one of the two Steam Generator Feedwater Pumps (SGFPs). This trip is only active when both HP Governor Valves are not closed. The plant can generate up to approximately 60% of its rated power with one SGFP.
3.2.4 Feedwater chemistry specifications should be brought within normal operating limits prior to commencing Steam Generator fill.
3.2.5 Do not operate SGFP Local Controls without specific permission from SM/CRS.
3.2.6 If either SGFP trips on Speed Sensing Pickup Failure or loss of power to the speed control cabinet, then the trip must be reset at speed control cabinet (TGB +40 MUX TB4005) by the reset push-button on Card No. 2 upon repair or restoration of power.
3.2.7 Contact Chemistry to sample and analyze any lay-up or flushing water prior to draining.
6
System Operating Procedure OP-003-033 Main Feedwater Revision 303 3.2.8 Prior to depressing the AUTO pushbutton on the SGFP Speed Controller (FW IHIC-1107 or FW-IHIC-1108) to transfer from Manual to Automatic mode, any one of the following three methods can be used to assure the transfer is accomplished with relatively little Main Feedwater flow perturbation:
Slowly adjust the speed controller output (if changes in the parameter will allow) until it matches the auto input.
Adjust the Master Controller output to adjust the speed controller input to match the output.
Adjust the bias control knob of one speed controller until the algebraic sum of the bias signal and the input signal equal the output signal.
Once MFW control is in Automatic mode it may be necessary to adjust the speed controller bias control to establish a delta between the two operating MFW pumps of at least 100 rpm. This delta is only required if MFP speed control is exhibiting oscillations. If necessary, adjust the bias control knob of one speed controller to slightly more positive than the other as such to establish a delta of at least 100 rpm between the two operating MFW pumps.
7
System Operating Procedure OP-003-033 Main Feedwater Revision 303 7.0 SYSTEM SHUTDOWN 7.1 MAIN FEEDWATER PUMP SHUTDOWN NOTE During plant shutdown or load reduction, a Main Feedwater Pump may be removed from service when feedwater flow has been reduced to approximately 50%.
7.1.1 If one SGFP is being removed when both are in service, then verify Reactor Power Cutback System Auto Actuate Out of Service push-button is illuminated.
7.1.2 Place SGFP Speed Controller, FW-IHIC-1107(1108), in MANUAL.
NOTE Steam Generator Feed Pump A(B) Recirc Flow Control Valve, FW-111A(B), is rated for 4,600 GPM. Main Feedwater Pump operation at flows below approximately 8,000 GPM can result in recirculation of flow and elevated pump vibration. This is acceptable based on the relatively short duration of the high vibration condition. [CR-WF3-2003-2990]
7.1.3 Throttle Steam Generator Feed Pump A(B) Recirc Flow Control, FW-111A(B), to maintain adequate Steam Generator Feed Pump flow.
NOTE As speed is lowered on SGFP being removed from service, verify speed of other SGFP rises to assume load of pump being removed from service.
7.1.4 Slowly lower SGFP speed to minimum (3900 RPM) using SGFP Speed Controller, FW-IHIC-1107(1108).
NOTE If SGFP Speed Balance Meter is >"0" on local control panel, then INCREASE FAST push-button is used to lower meter. If SGFP Speed Balance Meter is <"0" on local control panel, then DECREASE FAST push-button is used to raise meter. May take several seconds to respond.
7.1.5 Adjust SGFP Speed Balance Meter to "0" on local control panel using INCREASE FAST and DECREASE FAST push-buttons.
7.1.5.1 Place local controls in MANUAL.
23
System Operating Procedure OP-003-033 Main Feedwater Revision 303 7.1.6 Lower SGFP speed by turning Feedwater Turbine Governor Control switch to LESS on CP-1.
7.1.7 Monitor SGFP supervisory instruments during SGFP load reduction and verify:
Rotor vibration <3 mils Thrust-bearing normal thrust <5 mils Thrust-bearing reverse <5 mils 7.1.8 Maintain bearing drain temperature >100 F.
7.1.9 When SGFP speed reaches ~3200 RPM, then verify Open the following:
RS-319A(B) SGFPT A(B) LP Throttle Above Seat Drain to Condenser MS-220A(B) SGFPT A(B) HP Throttle Valve Drain 7.1.10 When SGFP speed reaches 3000 RPM, then perform the following:
7.1.10.1 Trip SGFP.
7.1.10.2 Verify Closed the following:
MS-217A(B) HP Stop Valve RS-316A(B) Reheat Steam to FWPT A(B) LP Throttle RS-317A(B) Reheat Steam to FWPT A(B) LP Governor FW-118A(B) Stm Generator Feed Pump A(B) Discharge NOTE Main Feedwater Turbine should remain on turning gear for cooling at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after removing gland steam.
7.1.11 When SGFP Turbine coasts down to <2 RPM, then verify turning gear motor starts, engages and rotates SGFP.
7.1.12 When suction temperature as indicated by PMC PID A06002 is 180 F, then isolate gland seal water from SGFPT A(B) by Closing the following valves:
CD-414A(B) SGFP A(B) Gland Seal Water Reg 1 Bypass CD-415A(B) SGFP A(B) Gland Seal Water Reg 2 Bypass CD-408A(B) SGFP A(B) Gland Seal Water Reg 1 Inlet Isol Isolation CD-409A(B) SGFP A(B) Gland Seal Water Reg 2 Inlet Isol Isolation 7.1.13 If the turning gear is secured prior to the 4-hour cooldown period, then rotate the turbine 180 every 15 minutes until the turbine is cooled down.
24
System Operating Procedure OP-003-033 Main Feedwater Revision 303 7.1.14 After all of the following conditions are met:
Steam has been removed from the Turbine Building, and Main Condenser vacuum has been broken in accordance with OP-003-001, Condenser Air Evacuation System, and Gland Steam has been secured to SGFPT A(B) for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, then perform the following:
7.1.14.1 Secure FWPT A(B) turning gear as follows:
7.1.14.1.1 Place FWPT A(B) turning gear control switch on CP-1 to OFF.
7.1.14.1.2 Open FWPT A(B) Turning Gear breaker, FW-EBKR-211A(B)-3M.
7.1.14.2 Secure lube oil to SGFPT A(B) as follows:
7.1.14.2.1 Open FWPT A(B) Emergency Oil Pump (DC) breaker, LOF-EBKR-TGB-9(10).
7.1.14.2.2 Open the breaker for the standby (non-running) main lube oil pump:
LOF-EBKR-211A(212A)-5D FWPT A(B) Main Oil Pump 1 or LOF-EBKR-212B(211B)-5D FWPT A(B) Main Oil Pump 2 7.1.14.2.3 Open the breaker for the operating (running) main lube oil pump:
LOF-EBKR-211A(212A)-5D FWPT A(B) Main Oil Pump 1 or LOF-EBKR-212B(211B)-5D FWPT A(B) Main Oil Pump 2 7.1.15 If SGFP is to remain secured for >7 days, then Open Turbine Console FWPT A(B) Trip (DC), FW-EBKR-TGB-A(B)30.
25
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE S5 Start Reactor Coolant Pump 1A Applicant:
Examiner:
JPM S5 JOB PERFORMANCE MEASURE DATA PAGE Task: Start Reactor Coolant Pump 1A Task Standard: Applicant started Reactor Coolant Pump 1A in accordance with OP-001-002, Reactor Coolant Pump Operation, and secured RCP 1A after receiving high vibration alarms on RCP 1A..
References:
OP-001-002, Reactor Coolant Pump Operation Alternate Path: Yes Time Critical: No Validation Time: 15 mins.
K/A 003 A4.01, HRPS controls Importance Rating 4.0 RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 13 2011 NRC Walk Through Exam
JPM S5 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-001-002, Reactor Coolant Pump Operation
==
Description:==
The applicant will be tasked with starting Reactor Coolant Pump 1A. After the applicant starts the pump, during his check of RCP parameters, high vibration alarms will come in for RCP 1A on CP-2 and on the plant monitoring computer. The severity of the vibration reading will rise until the pump is secured. The applicant must stop RCP 1A.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 13 2011 NRC Walk Through Exam
JPM S5 TASK ELEMENT 1 STANDARD NOTE The following parameters are indicative of RCP seal failure:
- Any seal pressure equal to RCS pressure
- Two or more seal pressures approximately equal to each other
- Controlled Bleedoff flow greater than 2.0 GPM Note reviewed.
- Inability to maintain Seal CCW Cooler Return Temperature <145 F A failed stage is indicated by a differential pressure of less than 100 psid across the stage Comment:
SAT / UNSAT TASK ELEMENT 2 STANDARD 6.1.1 If one or more seals fail, then refer to OP-901-130, Reactor Coolant Step reviewed.
Pump Malfunction.
Comment:
SAT / UNSAT TASK ELEMENT 3 STANDARD 6.1.2 If a diluted pocket of RCS water is suspected in the RCS, then verify OP-901-104, Inadvertent Positive Reactivity Addition, has been Step reviewed.
performed.
Comment:
SAT / UNSAT TASK ELEMENT 4 STANDARD NOTE To monitor the start of an RCP, an Operator should be stationed on the D ring wall, rather than on the pump work platform. Visual monitoring of Note reviewed.
the RCP is not required if Containment access is not in effect or at the SM/CRS discretion for reasons such as precluding impact to off-normal or emergency operations or reducing industrial or radiological safety risk.
Comment:
SAT / UNSAT Revision 0 Page 4 of 13 2011 NRC Walk Through Exam
JPM S5 TASK ELEMENT 5 STANDARD 6.1.3 If personnel are in Containment, then prior to starting the RCP, Step reviewed.
verify that personnel are not on the Reactor Coolant Pump work platform.
Comment:
Cue applicant that verifications have been made and the area is clear.
SAT / UNSAT TASK ELEMENT 6 STANDARD 6.1.4 If at normal RCS Pressure, then verify CBO of 1.2 GPM to 1.8 GPM flow by monitoring applicable RCP mimic or applicable Plant Monitoring N/A Computer (PMC) point in accordance with Attachment 11.2.
Comment:
SAT / UNSAT TASK ELEMENT 7 STANDARD 6.1.5 If not at normal RCS Pressure, then verify approximate CBO flow in Verification complete.
accordance with Attachment 11.4.
Comment:
SAT / UNSAT TASK ELEMENT 8 STANDARD 6.1.6 Verify proper upper oil reservoir level of 65% to 90% on applicable RCP mimic or applicable PMC point per Attachment 11.2, or by using Verification complete.
local level indication.
Comment:
SAT / UNSAT Revision 0 Page 5 of 13 2011 NRC Walk Through Exam
JPM S5 TASK ELEMENT 9 STANDARD 6.1.7 Verify proper lower oil reservoir level of 65% to 90% on applicable RCP mimic or applicable PMC point in accordance with Attachment 11.2, Verification complete.
or by using local level indication.
Comment:
SAT / UNSAT TASK ELEMENT 10 STANDARD 6.1.8 Verify CCW flow at CP-2 to Seal Water Cooler for applicable RCP (1A, 1B, 2A, or 2B) by checking associated inlet and outlet valves indicate Open:
CC-6651A RCP 1A SEAL COOLER CCW INLET ISOLATION CC-679A RCP 1A SEAL COOLER CCW OUTLET ISOLATION CC-6651B RCP 1B SEAL COOLER CCW INLET ISOLATION Verification complete.
CC-679B RCP 1B SEAL COOLER CCW OUTLET ISOLATION CC-666A RCP 2A SEAL COOLER CCW INLET ISOLATION CC-680A RCP 2A SEAL COOLER CCW OUTLET ISOLATION CC-666B RCP 2B SEAL COOLER CCW INLET ISOLATION CC-680B RCP 2B SEAL COOLER CCW OUTLET ISOLATION Comment:
SAT / UNSAT TASK ELEMENT 11 STANDARD 6.1.8.1 At SM/CRS discretion, verify CCW flow on local indicators. Verification complete.
Comment:
Cue the applicant that the local indicators reading are satisfactory.
SAT / UNSAT TASK ELEMENT 12 STANDARD 6.1.9 Test all annunciators on panels CP-2 and CP-18 and verify all Alarms tested.
Reactor Coolant Pump alarms illuminate.
Comment:
SAT / UNSAT Revision 0 Page 6 of 13 2011 NRC Walk Through Exam
JPM S5 TASK ELEMENT 13 STANDARD 6.1.10 Verify applicable RCP (1A, 1B, 2A, or 2B) High Vibration alarm is clear:
REACTOR CLG PUMP 1A HI VIBRATION (A-4, Panel H)
Verification complete.
REACTOR CLG PUMP 1B HI VIBRATION (A-6, Panel H)
REACTOR CLG PUMP 2A HI VIBRATION (A-8, Panel H)
REACTOR CLG PUMP 2B HI VIBRATION (A-10, Panel H)
Comment:
SAT / UNSAT TASK ELEMENT 14 STANDARD 6.1.11 Start RCP Oil Lift Pump A or B for RCP to be started (1A, 1B, 2A, Pump started.
or 2B) by placing associated control switch at CP-2 to ON. [P-15101]
Comment: Critical SAT / UNSAT TASK ELEMENT 15 STANDARD 6.1.12 If a second RCP lift oil pump is required to clear RCP Brg Lift Oil Press Lo annunciators on CP-2, then notify the Operations Manager and N/A Duty Plant Manager prior to starting RCP 1A (1B, 2A, 2B).
Comment:
SAT / UNSAT TASK ELEMENT 16 STANDARD 6.1.13 Verify proper High Pressure Oil Lift System pressure for RCP 1A (1B, 2A, 2B) by observing that applicable annunciator is clear:
RCP 1A BRG LIFT OIL PRESS LO (D-3, Panel H)
Verification complete.
RCP 1B BRG LIFT OIL PRESS LO (D-5, Panel H)
RCP 2A BRG LIFT OIL PRESS LO (D-7, Panel H)
RCP 2B BRG LIFT OIL PRESS LO (D-9, Panel H)
Comment:
SAT / UNSAT Revision 0 Page 7 of 13 2011 NRC Walk Through Exam
JPM S5 TASK ELEMENT 17 STANDARD 6.1.14 Verify RCS pressure and temperature are within limits of Verification complete. 1.1.
Comment:
SAT / UNSAT TASK ELEMENT 18 STANDARD CAUTION LOW TEMPERATURE OVERPRESSURE PROTECTION AND REACTIVITY PROTECTION SHALL BE PROVIDED BY ESTABLISHING A <100 F T BETWEEN RCS COLD LEG (TC) TEMPERATURE AND S/G WATER TEMPERATURE PRIOR TO STARTING THE FIRST RCP ON EACH LOOP. REACTIVITY EXCURSION CONCERNS EXIST ON RCP START IN AN IDLE LOOP IF S/G WATER TEMPERATURE IS Caution reviewed.
>100 F COLDER THAN LOOP TC (WORST CASE NEGATIVE ITC).
ALSO, LOW TEMPERATURE OVERPRESSURE PROTECTION CONCERNS EXIST IF S/G WATER TEMPERATURE IS >100 F HOTTER THAN LOOP TC WHEN LOOP TC IS 272 F. FOR CONSERVATISM AND SIMPLICITY, AN RCP START LIMIT OF 100 F T BETWEEN S/G WATER TEMPERATURE AND LOOP TC IS ESTABLISHED.
Comment:
SAT / UNSAT TASK ELEMENT 19 STANDARD 6.1.15 Verify a <100 F differential temperature ( T) between RCS Cold Leg (Tc) Temperature and Steam Generator Water Temperature prior to starting the first RCP on each RCS Loop (1A or 1B on RCS Loop 1, 2A N/A or 2B on RCS Loop2) to provide low temperature overprotection and reactivity protection.
Comment:
SAT / UNSAT Revision 0 Page 8 of 13 2011 NRC Walk Through Exam
JPM S5 TASK ELEMENT 20 STANDARD 6.1.16 Refer to Attachment 11.3 while performing Steps 6.1.17 through Verification complete.
6.1.27.
Comment:
SAT / UNSAT TASK ELEMENT 21 STANDARD CAUTION (1) RCPS SHALL NOT BE STARTED SIMULTANEOUSLY. PLANT PARAMETERS SHOULD BE ALLOWED TO STABILIZE PRIOR TO STARTING SUBSEQUENT PUMPS.
Caution reviewed.
(2) STARTING THE FIRST RCP IN A REACTOR COOLANT LOOP WITH THE EXISTENCE OF A DILUTED POCKET OF RCS WATER COULD CAUSE A BORON DILUTION EVENT RESULTING IN A REACTIVITY EXCURSION.
Comment:
SAT / UNSAT TASK ELEMENT 22 STANDARD 6.1.17 Verify the associated RCP Oil Lift Pump operating at normal pressure for a minimum of two minutes prior to starting RCP 1A (1B, 2A, Verification complete.
2B).
Comment:
SAT / UNSAT TASK ELEMENT 23 STANDARD 6.1.18 Notify the SM/CRS prior to starting RCP 1A (1B, 2A, 2B). Notification complete.
Comment:
SAT / UNSAT Revision 0 Page 9 of 13 2011 NRC Walk Through Exam
JPM S5 TASK ELEMENT 24 STANDARD NOTE When starting a third RCP during plant startup, upper thrust bearing Note reviewed.
temperatures may exceed alarm limits on the single operating pump in a loop until the fourth RCP is started. [CR-WF3-2005-02745]
Comment:
SAT / UNSAT TASK ELEMENT 25 STANDARD 6.1.19 If excessively high vibration, unusual noises, or sharp rates of bearing temperature rise occur while starting RCP 1A (1B, 2A, 2B), then Step reviewed.
secure RCP 1A (1B, 2A, 2B).
Comment:
SAT / UNSAT TASK ELEMENT 26 STANDARD 6.1.20 Place and Hold selected RCP (1A, 1B, 2A, or 2B) control switch to Pump started.
START until pump starts.
Comment: Critical SAT / UNSAT TASK ELEMENT 27 STANDARD 6.1.21 Verify CCW flow, on CP-2, to Lube Oil Cooler, Air Cooler and Lower Bearing Cooler for applicable RCP (1A, 1B, 2A, or 2B).by verifying associated valve Open: [P-15100]
CC-661A RCP 1A MOTOR COOLERS CCW INLET ISOLATION Verification complete.
CC-661B RCP 1B MOTOR COOLERS CCW INLET ISOLATION CC-660A RCP 2A MOTOR COOLERS CCW INLET ISOLATION CC-660B RCP 2B MOTOR COOLERS CCW INLET ISOLATION Comment:
SAT / UNSAT Revision 0 Page 10 of 13 2011 NRC Walk Through Exam
JPM S5 TASK ELEMENT 28 STANDARD 6.1.22 Verify associated RCP (1A, 1B, 2A, or 2B) alarms clear insuring CCW to RCP Motor Coolers flow:
RCP 1A CCW FLOW LOST (A-1, Panel SA)
RCP 1A CCW FLOW LOST (A-6, Panel SB)
RCP 1B CCW FLOW LOST (A-2, Panel SA)
Verification complete.
RCP 1B CCW FLOW LOST (A-7, Panel SB)
RCP 2A CCW FLOW LOST (A-3, Panel SA)
RCP 2A CCW FLOW LOST (A-8, Panel SB)
RCP 2B CCW FLOW LOST (A-4, Panel SA)
RCP 2B CCW FLOW LOST (A-9, Panel SB)
Comment:
SAT / UNSAT TASK ELEMENT 29 STANDARD Secure Reactor Coolant Pump 1A RCP 1A secured Comment: Critical This faulted step becomes applicable after RCP 1A vibration alarms come in. These alarms may come in before the applicant performs steps SAT / UNSAT 6.1.21 and 6.1.22.
END OF TASK Revision 0 Page 11 of 13 2011 NRC Walk Through Exam
JPM S5 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-194 Verify the following Malfunctions:
o RC07 A with a severity of 20% and a delay of 30 seconds on trigger 1 o RC07 A with a severity of 30% and a delay of 60 seconds on trigger 1 o ZDIRCECS220(2) on Event Trigger 1 Revision 0 Page 12 of 13 2011 NRC Walk Through Exam
JPM S5 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Plant heatup is in progress following a mid cycle forced outage.
INITIATING CUES:
- The Control Room Supervisor directs you to start Reactor Coolant Pump 1A in accordance with OP-001-002, Reactor Coolant Pump Operation.
Revision 0 Page 13 of 13 2011 NRC Walk Through Exam
System Operating Procedure OP-001-002 Reactor Coolant Pump Operation Revision 019 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS 3.1.1 When operating one RCP, no minimum RCS Cold Leg Temperature restrictions exist.
3.1.2 When operating in two pump, opposite loop configuration, no minimum RCS Cold Leg Temperature restrictions exist.
3.1.3 When operating in two pump, same loop configuration using RCP 2A, minimum allowable RCS Cold Leg Temperature for RCP operation is 347 F. This restriction applies to prevent motor load in excess of nameplate HP rating since RCP 2A develops higher head and requires more brake horsepower.
3.1.4 When operating in two pump, same loop configuration, minimum allowable RCS Cold Leg Temperature for RCP operation is 172 F.
3.1.5 When operating in three pump configuration using RCP 2A, minimum allowable RCS Cold Leg Temperature for RCP operation is 347 F. This restriction applies to prevent motor load in excess of nameplate HP rating since RCP 2A develops higher head and requires more brake horsepower.
3.1.6 When operating in three pump configuration, minimum allowable RCS Cold Leg Temperature for RCP operation is 199 F.
3.1.7 With fuel in the core, the fourth RCP shall not be started until RCS Temperature is 382 F. This restriction applies to prevent exceeding fuel assembly uplift limitations.
3.1.8 Low temperature overpressure protection and reactivity protection shall be provided by establishing a <100 F T between RCS Cold Leg (Tc) Temperature and S/G Water Temperature prior to starting the first RCP on each loop.
Reactivity excursion concerns exist on RCP start in an idle loop if S/G Water Temperature is >100 F colder than loop Tc (worst case negative ITC). Also, low temperature overpressure protection concerns exist if S/G Water Temperature is
>100 F hotter than loop Tc when loop Tc is 272 F. For conservatism and simplicity, a RCP start limit of 100 F T between SG Water Temperature and loop Tc is established. [P-22890]
3.1.9 A CCW temperature of 155 F at outlet of RCP Seal Cooler will isolate cooler.
Manual Override exists in Control Room on CP-2. Manual Override is accomplished by first placing control switch in Closed position and then to Open position. If high temperature still exists after isolation valves are Opened, then 100 second time delay will time out and Close isolation valves. If temperature is
<145 F after valves are Opened, they will remain Open.
3.1.10 Do not start RCPs simultaneously.
4
System Operating Procedure OP-001-002 Reactor Coolant Pump Operation Revision 019 3.1.11 During RCP motor operation for oil system cleanup after maintenance, duplex strainer fouling can occur very rapidly. A rapid increase in thrust bearing temperature is an indication of duplex strainer fouling.
3.1.12 Where multiple indications for one parameter exist, more than one instrument should be used to obtain a particular reading.
3.1.13 Starting the first RCP in a Reactor Coolant Loop with the existence of a diluted pocket of RCS water could cause a Boron Dilution Event resulting in a reactivity excursion.
3.1.14 Anytime RCS pressure is greater than VCT pressure, RCP CBO should be unisolated.
3.1.15 RCP seals will exhibit some amount of weepage at low Reactor Coolant System pressures. It is expected that the seals will shut off the weeping with higher pressure in the RCS and that the weepage will stop before reaching RCS normal operating pressure. This weepage will likely result in boric acid residue in the RCP shrouds. [CR-WF3-2005-02712]
3.1.16 To monitor the start of an RCP, an Operator should be stationed on the D ring wall, rather than on the pump work platform. Visual monitoring of the RCP is not required if Containment access is not in effect or at the SM/CRS discretion for reasons such as precluding impact to off-normal or emergency operations or reducing industrial or radiological safety risk.
3.2 LIMITATIONS 3.2.1 When Starting RCP from cold conditions, monitor bearing temperatures for abnormally high rate of rise after reaching normal operating temperatures.
3.2.2 When starting a third RCP during plant startup, upper thrust bearing temperatures may exceed alarm limits on the single operating pump in a loop until the fourth RCP is started. [CR-WF3-2005-02745]
3.2.3 Each RCP Start stresses motor windings both thermally and mechanically. A Start means that motor comes up to rated speed.
3.2.4 With motor at ambient temperature, do not attempt more than two consecutive Starts, allowing motor to coast to a Stop between Starts. For additional Starts, after two consecutive Starts, wait 240 minutes before attempting subsequent Start.
3.2.5 With motor at operating temperature, do not attempt more than one Start at 60 minute intervals.
5
System Operating Procedure OP-001-002 Reactor Coolant Pump Operation Revision 019 3.2.6 Do not exceed more than 6 Starts per day.
3.2.7 The associated RCP Oil Lift Pump must have been operating at normal pressure for a minimum of two minutes prior to Starting RCP.
3.2.8 Do not allow oil level of reservoirs to drop to <37%. An oil level of <37% will cause bearing uncovering and bearing temperature to rise indicating that bearing oil film is deteriorating.
3.2.9 RCP Seals rely upon CBO to maintain a thin film of water for lubrication. During operation, if CBO is lost, seals will run dry and suffer excessive frictional heat and wear.
3.2.10 When starting RCP with RCS temperature >200 F, CBO temperature exiting pump must be 190 F.
3.2.11 Maximum RCP operating time without CCW flow is three minutes. If CCW flow can be restored within 10 minutes, then pump may be restarted. [P-15099]
3.2.12 Fourth stage vapor seal can operate at full system pressure for limited time. This is a severe operating condition and requires that RCP be secured.
3.2.13 Do not operate RCP with system pressure >2500 PSIA.
3.2.14 CBO and CCW flow to seal coolers should be maintained after RCP has been secured until RCS temperature has been lowered to 140 F.
3.2.15 When Starting motor from ambient conditions, bearing temperatures should be watched very closely for minimum of two hours, or until bearing temperatures stabilize. Normal rate of rise from ambient conditions may be as high 27 F/min.
3.2.16 To minimize the effects of RCP seal perturbations, maintain Reactor Coolant Pump Control Bleedoff Pressure 40 PSIG to 65 PSIG when any Reactor Coolant Pumps are running. Reactor Coolant Pump Control Bleedoff Pressure operating band may be expanded to 30 PSIG to 120 PSIG with a 4 PSIG per minute rate of change limit during short periods of operation such as establishing nitrogen or hydrogen blankets on the Volume Control Tank. Refer to Attachment 11.1, RCS Pressure And Temperature Limits Graph.
6
System Operating Procedure OP-001-002 Reactor Coolant Pump Operation Revision 019 6.0 NORMAL OPERATIONS 6.1 STARTING A REACTOR COOLANT PUMP NOTE The following parameters are indicative of RCP seal failure:
Any seal pressure equal to RCS pressure Two or more seal pressures approximately equal to each other Controlled Bleedoff flow greater than 2.0 GPM Inability to maintain Seal CCW Cooler Return Temperature <145 F A failed stage is indicated by a differential pressure of less than 100 psid across the stage 6.1.1 If one or more seals fail, then refer to OP-901-130, Reactor Coolant Pump Malfunction.
6.1.2 If a diluted pocket of RCS water is suspected in the RCS, then verify OP-901-104, Inadvertent Positive Reactivity Addition, has been performed.
NOTE To monitor the start of an RCP, an Operator should be stationed on the D ring wall, rather than on the pump work platform. Visual monitoring of the RCP is not required if Containment access is not in effect or at the SM/CRS discretion for reasons such as precluding impact to off-normal or emergency operations or reducing industrial or radiological safety risk.
6.1.3 If personnel are in Containment, then prior to starting the RCP, verify that personnel are not on the Reactor Coolant Pump work platform.
6.1.4 If at normal RCS Pressure, then verify CBO of 1.2 GPM to 1.8 GPM flow by monitoring applicable RCP mimic or applicable Plant Monitoring Computer (PMC) point in accordance with Attachment 11.2.
6.1.5 If not at normal RCS Pressure, then verify approximate CBO flow in accordance with Attachment 11.4.
6.1.6 Verify proper upper oil reservoir level of 65% to 90% on applicable RCP mimic or applicable PMC point per Attachment 11.2, or by using local level indication.
6.1.7 Verify proper lower oil reservoir level of 65% to 90% on applicable RCP mimic or applicable PMC point in accordance with Attachment 11.2, or by using local level indication.
9
System Operating Procedure OP-001-002 Reactor Coolant Pump Operation Revision 019 6.1.8 Verify CCW flow at CP-2 to Seal Water Cooler for applicable RCP (1A, 1B, 2A, or 2B) by checking associated inlet and outlet valves indicate Open:
CC-6651A RCP 1A SEAL COOLER CCW INLET ISOLATION CC-679A RCP 1A SEAL COOLER CCW OUTLET ISOLATION CC-6651B RCP 1B SEAL COOLER CCW INLET ISOLATION CC-679B RCP 1B SEAL COOLER CCW OUTLET ISOLATION CC-666A RCP 2A SEAL COOLER CCW INLET ISOLATION CC-680A RCP 2A SEAL COOLER CCW OUTLET ISOLATION CC-666B RCP 2B SEAL COOLER CCW INLET ISOLATION CC-680B RCP 2B SEAL COOLER CCW OUTLET ISOLATION 6.1.8.1 At SM/CRS discretion, verify CCW flow on local indicators.
6.1.9 Test all annunciators on panels CP-2 and CP-18 and verify all Reactor Coolant Pump alarms illuminate.
6.1.10 Verify applicable RCP (1A, 1B, 2A, or 2B) High Vibration alarm is clear:
REACTOR CLG PUMP 1A HI VIBRATION (A-4, Panel H)
REACTOR CLG PUMP 1B HI VIBRATION (A-6, Panel H)
REACTOR CLG PUMP 2A HI VIBRATION (A-8, Panel H)
REACTOR CLG PUMP 2B HI VIBRATION (A-10, Panel H) 6.1.11 Start RCP Oil Lift Pump A or B for RCP to be started (1A, 1B, 2A, or 2B) by placing associated control switch at CP-2 to ON. [P-15101]
6.1.12 If a second RCP lift oil pump is required to clear RCP Brg Lift Oil Press Lo annunciators on CP-2, then notify the Operations Manager and Duty Plant Manager prior to starting RCP 1A (1B, 2A, 2B).
6.1.13 Verify proper High Pressure Oil Lift System pressure for RCP 1A (1B, 2A, 2B) by observing that applicable annunciator is clear:
RCP 1A BRG LIFT OIL PRESS LO (D-3, Panel H)
RCP 1B BRG LIFT OIL PRESS LO (D-5, Panel H)
RCP 2A BRG LIFT OIL PRESS LO (D-7, Panel H)
RCP 2B BRG LIFT OIL PRESS LO (D-9, Panel H) 6.1.14 Verify RCS pressure and temperature are within limits of Attachment 11.1.
10
System Operating Procedure OP-001-002 Reactor Coolant Pump Operation Revision 019 CAUTION LOW TEMPERATURE OVERPRESSURE PROTECTION AND REACTIVITY PROTECTION SHALL BE PROVIDED BY ESTABLISHING A <100 F T BETWEEN RCS COLD LEG (TC)
TEMPERATURE AND S/G WATER TEMPERATURE PRIOR TO STARTING THE FIRST RCP ON EACH LOOP. REACTIVITY EXCURSION CONCERNS EXIST ON RCP START IN AN IDLE LOOP IF S/G WATER TEMPERATURE IS >100 F COLDER THAN LOOP TC (WORST CASE NEGATIVE ITC). ALSO, LOW TEMPERATURE OVERPRESSURE PROTECTION CONCERNS EXIST IF S/G WATER TEMPERATURE IS >100 F HOTTER THAN LOOP TC WHEN LOOP TC IS 272 F. FOR CONSERVATISM AND SIMPLICITY, AN RCP START LIMIT OF 100 F T BETWEEN S/G WATER TEMPERATURE AND LOOP T C IS ESTABLISHED.
6.1.15 Verify a <100 F differential temperature ( T) between RCS Cold Leg (Tc)
Temperature and Steam Generator Water Temperature prior to starting the first RCP on each RCS Loop (1A or 1B on RCS Loop 1, 2A or 2B on RCS Loop2) to provide low temperature overprotection and reactivity protection.
6.1.16 Refer to Attachment 11.3 while performing Steps 6.1.17 through 6.1.27.
CAUTION (1) RCPS SHALL NOT BE STARTED SIMULTANEOUSLY. PLANT PARAMETERS SHOULD BE ALLOWED TO STABILIZE PRIOR TO STARTING SUBSEQUENT PUMPS.
(2) STARTING THE FIRST RCP IN A REACTOR COOLANT LOOP WITH THE EXISTENCE OF A DILUTED POCKET OF RCS WATER COULD CAUSE A BORON DILUTION EVENT RESULTING IN A REACTIVITY EXCURSION.
6.1.17 Verify the associated RCP Oil Lift Pump operating at normal pressure for a minimum of two minutes prior to starting RCP 1A (1B, 2A, 2B).
6.1.18 Notify the SM/CRS prior to starting RCP 1A (1B, 2A, 2B).
11
System Operating Procedure OP-001-002 Reactor Coolant Pump Operation Revision 019 NOTE When starting a third RCP during plant startup, upper thrust bearing temperatures may exceed alarm limits on the single operating pump in a loop until the fourth RCP is started.
[CR-WF3-2005-02745]
6.1.19 If excessively high vibration, unusual noises, or sharp rates of bearing temperature rise occur while starting RCP 1A (1B, 2A, 2B), then secure RCP 1A (1B, 2A, 2B).
6.1.20 Place and Hold selected RCP (1A, 1B, 2A, or 2B) control switch to START until pump starts.
6.1.21 Verify CCW flow, on CP-2, to Lube Oil Cooler, Air Cooler and Lower Bearing Cooler for applicable RCP (1A, 1B, 2A, or 2B).by verifying associated valve Open:
[P-15100]
CC-661A RCP 1A MOTOR COOLERS CCW INLET ISOLATION CC-661B RCP 1B MOTOR COOLERS CCW INLET ISOLATION CC-660A RCP 2A MOTOR COOLERS CCW INLET ISOLATION CC-660B RCP 2B MOTOR COOLERS CCW INLET ISOLATION 6.1.22 Verify associated RCP (1A, 1B, 2A, or 2B) alarms clear insuring CCW to RCP Motor Coolers flow:
RCP 1A CCW FLOW LOST (A-1, Panel SA)
RCP 1A CCW FLOW LOST (A-6, Panel SB)
RCP 1B CCW FLOW LOST (A-2, Panel SA)
RCP 1B CCW FLOW LOST (A-7, Panel SB)
RCP 2A CCW FLOW LOST (A-3, Panel SA)
RCP 2A CCW FLOW LOST (A-8, Panel SB)
RCP 2B CCW FLOW LOST (A-4, Panel SA)
RCP 2B CCW FLOW LOST (A-9, Panel SB) 12
System Operating Procedure OP-001-002 Reactor Coolant Pump Operation Revision 019 6.1.23 Verify proper Low Pressure Lube Oil System pressure by observing that annunciator is clear for associated RCP (1A, 1B, 2A, or 2B):
RCP 1A LUBE OIL PRESSURE LO (E-3, Panel H)
RCP 1B LUBE OIL PRESSURE LO (E-5, Panel H)
RCP 2A LUBE OIL PRESSURE LO (E-7, Panel H)
RCP 2B LUBE OIL PRESSURE LO (E-9, Panel H) 6.1.24 If RCP 1A (1B, 2A, 2B) fails to Start or trips during an attempted start, then refer to section 3.2, Limitations, for subsequent starts.
6.1.25 After RCP 1A (1B, 2A, 2B) has been operating for approximately 30 seconds, then place control switches for both associated RCP Oil Lift Pumps to AUTO. [P-15101]
6.1.26 If RCP 1A (1B, 2A, 2B) associated Oil Lift Pumps do not Stop, then leave RCP Oil Lift Pumps control switches in AUTO and investigate cause of problem.
6.1.27 Verify there are no computer alarms associated with the running RCP (1A, 1B, 2A, or 2B) Anti-Reverse Rotation Devices (ARRD's) activated on the associated RCP (1A, 1B, 2A, or 2B) mimic or applicable PMC point in accordance with Attachment 11.2.
6.1.27.1 If any ARRD alarms are activated, then refer to OP-901-130, Reactor Coolant Pump Malfunction, and notify SM/CRS.
6.1.28 The following parameters are indicative of RCP seal degradation at normal operating pressure and temperature. If any of the following parameters are reached, then notify SM/CRS immediately.
Middle Seal Pressure <1237 PSIG or >1815 PSIG Upper Seal Pressure <585 PSIG or >915 PSIG Vapor Seal Pressure <25 PSIG or >45 PSIG Controlled Bleed Off Temp <135 F or >190 F Controlled Bleed Off Flow <1.2 GPM or >1.8 GPM 6.1.28.1 Refer to OP-901-130, Reactor Coolant Pump Malfunction, and inform the System Engineer to evaluate and monitor seal degradation.
6.1.28.2 If RCS is not at normal operating pressure and temperature, then refer to Attachment 11.4 for approximate parameters.
13
System Operating Procedure OP-001-002 Reactor Coolant Pump Operation Revision 019 6.1.29 After RCP 1A (1B, 2A, 2B) has been operating for approximately 5 minutes, verify all secured RCPs (1A, 1B, 2A, 2B) are not rotating in the reverse direction by observing zero speed indicated on the computer points listed in Attachment 11.2.
6.1.29.1 If PMC points indicate any RCP is rotating in the reverse direction, then refer to OP-901-130, Reactor Coolant Pump Malfunction, and notify SM/CRS.
14
RCS PRESSURE AND TEMPERATURE LIMITS GRAPH (CONTD)
(RCS Pressure 0 - 2500 PSIA) 2500 LOWEST SERVICE TEMP (Tcold) 200 ºF (Thot) 217 ºF SUBCOOLING 2000 MINIMUM TEMP.
FOR FOUR RCP OPERATION 382 ºF (Tcold) 1500 LOWEST SERVICE PRESSURE 528 psia 0 ºF (Thot)
RCP OPERATING SUBCOOLING CURVE (Tcold)
ONE, TWO, THREE, THREE RCP* & OR FOUR RCPS 1000 TWO RCP** SAME LOOP OPERATION 403.1 PSIA (120 psig CBO)
THREE RCP * &
TWO RCP** SAME 28 ºF (Thot)
LOOP OPERATION SUBCOOLING 348.1 PSIA (65 psig CBO)
SINGLE & MAXIMUM COOLDOWN RATE TWO RCP 500 (Tcold): 100 ºF/HR (50 ºF/HR on OPPOSITE LOOP OPS Natural Circulation) 339.1 PSIA [for entire temperature range on (120 psig CBO) this chart]
MAX SDC PRESS 392 PSIA SINGLE &
TWO RCP MAX SDC OPPOSITE TEMP LOOP OPS 350 ºF (Thot) 289.1 PSIA (65 psig 0 CBO) 100 200 300 400 500 600 700 RCS TEMPERATURE (DEGF)
- Not allowed below 199°F and RCP 2A operation not allowed below 347°F.
- Not allowed below 172°F and RCP 2A operation not allowed below 347°F OP-001-002 Revision 019 Attachment 11.1 (2 of 2) 23
11.3 RCP NORMAL OPERATING PARAMETERS NOTE (1) Temperatures should be very closely monitored for at least two hours. The rate of rise of the bearing temperature is more an indication of trouble than absolute temperature.
Normal rate of rise from ambient conditions may be as high as 27 F/ minute.
(2) The RCP should be secured if there is excessive vibration, or unusual noise.
(3) The values given assume normal operating RCS pressure and temperature.
Anti-Reverse Rotation Device (ARD) Upper Thrust CCW Outlet <175 F Bearing
<30 F delta 185 F - 205 F CCW Inlet Lower Thrust 105 F - 140 F Bearing 125 F - 160 F CCW Upper Oil Reservoir 65% to 90%
CCW Air Cooler Lube Oil Stator Winding Cooler 266 F Lower Guide CCW Bearing 120 F to 160 F To Containment Sump Lower Oil Reservoir 65% to 90%
CBO to VCT 135 F - 190 F 1.2 - 1.8 GPM Vapor Seal Pressure 25 PSIG - 45 PSIG Upper Seal Pressure 585 PSIG - 915 PSIG Middle Seal Pressure CCW 1237 PSIG - 1815 PSIG OP-001-002 Revision 019 Attachment 11.3 (1 of 1) 26
11.4 RCP UPPER SEAL P VS CBO FLOW RCP SEAL STAGE PRESSURES (PSIG)
RCS PRESSURE CBO FLOW MIDDLE UPPER VAPOR 250 180 110 40 0.46 350 247 143 40 0.56 450 313 177 40 0.65 550 380 210 40 0.72 650 447 243 40 0.79 750 513 277 40 0.85 850 580 310 40 0.91 950 647 343 40 0.96 1050 713 377 40 1.01 1150 780 410 40 1.06 1250 847 443 40 1.11 1350 913 477 40 1.15 1450 980 510 40 1.20 1550 1047 543 40 1.24 1650 1113 577 40 1.28 1750 1180 610 40 1.32 1850 1247 643 40 1.36 1950 1313 677 40 1.39 2050 1380 710 40 1.43 2150 1447 743 40 1.47 OP-001-002 Revision 019 [LAST PAGE] Attachment 11.4 (1 of 1) 27
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE S6 Energize 4.16 KV Safety Bus from Offsite Power Applicant:
Examiner:
JPM S6 JOB PERFORMANCE MEASURE DATA PAGE Task: Energize 4.16 KV Safety Bus from Offsite Power Task Standard: Applicant synchronizes EDG B with in-coming power and secures EDG B.
References:
OP-902-009, Standard Appendices Attachment 12-C: Transfer 4.16 KV Safety Bus from EDG to Offsite Power Alternate Path: No Time Critical: No Validation Time: 15 mins.
K/A 064 A4.07, Transfer ED/G (with load) to grid Importance Rating 3.4 RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 8 2011 NRC Walk Through Exam
JPM S6 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-902-009, Standard Appendices, Attachment 12-C: Transfer 4.16 KV Safety Bus from EDG to Offsite Power
==
Description:==
This task is performed at CP-1. The applicant must synchronize Emergency Diesel Generator B across the 3B to 2B Tie Breaker and secure EDG B. The conditions for the JPM are following a loss of off site power on Train B Safety Bus. All manipulations are at CP-1.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 8 2011 NRC Walk Through Exam
JPM S6 1.2 IF 4.16 KV nonsafety bus B2 is energized AND the 4.16 KV safety bus B3 is energized from the associated EDG, THEN perform the following:
TASK ELEMENT 1 STANDARD 1.2.a: Verify BUS B3S TO B2 TIE BKR open. Verification complete.
Comment:
SAT / UNSAT TASK ELEMENT 2 STANDARD 1.2.b: Close BUS B2 TO B3S TIE Breaker. Breaker is closed.
Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD 1.2.c: Place the SYCHRONIZER key switch in BUS TIE. Key switch is in BUS TIE.
Comment: Critical Key 209 SAT / UNSAT TASK ELEMENT 4 STANDARD Voltages approximately 1.2.d.1: Adjust EDG voltage to equal system voltage.
matched.
Comment:
Voltages are close enough so that if the applicant took no action, the SAT / UNSAT task would be successful, therefore this step is not critical.
Revision 0 Page 4 of 8 2011 NRC Walk Through Exam
JPM S6 TASK ELEMENT 5 STANDARD Synchroscope is rotating 1.2.d.2: Adjust engine speed until synchroscope rotates slowly slowly in the clockwise clockwise.
direction.
Comment: Critical SAT / UNSAT TASK ELEMENT 6 STANDARD 1.2.d.3: Close BUS B3S TO B2 TIE Breaker at 5 minutes to twelve Breaker is closed.
position on the synchroscope.
Comment: Critical SAT / UNSAT TASK ELEMENT 7 STANDARD 1.2.d.4: Place SYNCHRONIZER key switch in OFF. Key switch is in OFF.
Comment:
SAT / UNSAT Evaluator Note Step 1.2.e describes steps for unloading the EDG if SIAS is reset, which for this IC, it is. The steps necessary to unload EDG B follow.
If SIAS was not reset, the EDG B Output breaker would have opened when the 3B to 2B Bus Tie Breaker was closed. Since the EDG B Output breaker will not automatically open, the applicant may or may not take action to make this verification at CP-2 or CP-7.
Revision 0 Page 5 of 8 2011 NRC Walk Through Exam
JPM S6 TASK ELEMENT 8 STANDARD 1.2.e.1: Reduce load on EDG A to 0.1 MW and 0.1 MVARS. Load is reduced.
Comment:
EDG B could reverse power trip at this step if power is reduced too far, or if voltage was raised too high at step 1.2.d.1. SAT / UNSAT TASK ELEMENT 9 STANDARD 1.2.e.2: Open EDG B Output Breaker. Breaker is open.
Comment: Critical SAT / UNSAT TASK ELEMENT 10 STANDARD 1.2.e.3: Stop EDG B. EDG B is off.
Comment: Critical Evaluator: After taking the EDG B control switch to OFF, both the red and green lights will go off on the control switch. The EDG is in SAT / UNSAT cooldown mode at this point. This continues for 5 minutes. After cooldown is complete, the green light comes on.
This task can be terminated when the EDG B control switch is taken to OFF, or after the cooldown cycle is complete, at the examiners discretion.
END OF TASK Revision 0 Page 6 of 8 2011 NRC Walk Through Exam
JPM S6 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-196 There are no malfunctions or overrides for this JPM.
Revision 0 Page 7 of 8 2011 NRC Walk Through Exam
JPM S6 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- A loss of off site power has occurred
- Emergency Diesel Generator B is running in Emergency Mode
- 2B Bus has been restored INITIATING CUES:
- The CRS directs you to energize the 3B Safety Bus from Offsite Power using OP-902-009, Attachment 12-C.
Revision 0 Page 8 of 8 2011 NRC Walk Through Exam
WATERFORD 3 SES OP-902-009 Revision 301 Page 106 of 195 STANDARD APPENDICES Appendix 12 Page 5 of 14 Electrical Restoration Attachment 12-C: Transfer 4.16 KV Safety Bus from EDG to Offsite Power INSTRUCTIONS CONTINGENCY ACTIONS
____ 1.1 IF 4.16 KV nonsafety bus A2 is energized AND the 4.16 KV safety bus A3 is energized from the associated EDG, THEN perform the following:
- a. Verify BUS A3S TO A2 TIE BKR open.
- b. Close BUS A2 TO A3S TIE BKR.
- c. Place the SYCHRONIZER keyswitch in "BUS TIE."
- d. Parallel EDG A as follows:
- 1) Adjust EDG voltage to equal system voltage.
- 2) Adjust engine speed until synchroscope rotates slowly clockwise.
- 3) Close BUS A3S TO A2 TIE BKR at 5 minutes to twelve position on the synchroscope.
- 4) Place SYNCHRONIZER keyswitch in "OFF."
(continue)
WATERFORD 3 SES OP-902-009 Revision 301 Page 107 of 195 STANDARD APPENDICES Appendix 12 Page 6 of 14 INSTRUCTIONS CONTINGENCY ACTIONS
____ 1.1 (continued)
- 2) Open GEN BREAKER.
- 3) Stop EDG A.
____ 1.2 IF 4.16 KV nonsafety bus B2 is energized AND the 4.16 KV safety bus B3 is energized from the associated EDG, THEN perform the following:
- a. Verify BUS B3S TO B2 TIE BKR open.
- b. Close BUS B2 TO B3S TIE BKR.
- c. Place the SYCHRONIZER keyswitch in "BUS TIE."
(continue)
WATERFORD 3 SES OP-902-009 Revision 301 Page 108 of 195 STANDARD APPENDICES Appendix 12 Page 7 of 14 INSTRUCTIONS CONTINGENCY ACTIONS
____ 1.2 (continued)
- d. Parallel EDG B as follows:
- 1) Adjust EDG voltage to equal system voltage.
- 2) Adjust engine speed until synchroscope rotates slowly clockwise.
- 3) Close BUS B3S TO B2 TIE BKR at 5 minutes to twelve position on the sychroscope.
- 4) Place SYNCHRONIZER keyswitch in "OFF."
- 2) Open GEN BREAKER.
- 3) Stop EDG B.
End of Attachment 12-C
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE S7 Restore from Control Room Isolation Applicant:
Examiner:
JPM S7 JOB PERFORMANCE MEASURE DATA PAGE Task: Restore from CR Isolation and start RAB Normal Ventilation Task Standard: Control Room ventilation has been restored from CR Isolation and RAB Normal Ventilation is running in accordance with OP-002-010.
References:
OP-003-014, Control Room Heating and Ventilation (HVC)
OP-002-010, Reactor Auxiliary Building HVAC and Containment Purge Alternate Path: No Time Critical: No Validation Time: 15 mins.
K/A 072 K1.04, Control room ventilation Importance Rating 3.3 RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 12 2011 NRC Walk Through Exam
JPM S7 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-003-014, Control Room Heating and Ventilation (HVC)
OP-002-010, Reactor Auxiliary Building HVAC and Containment Purge
==
Description:==
The initiating cue will describe that an inadvertent Control Room Isolation has occurred and the signal is clear. The applicant will be required to restore from CR Isolation and re-start RAB Normal Ventilation.
The first manipulation is on a mock up panel. The Simulator Booth operator will have to initiate a trigger when the mock up switches are manipulated.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 12 2011 NRC Walk Through Exam
JPM S7 Evaluator Note The first step is performed in a rear Control Room panel that is not installed in the simulator. There is a mock up of the panel. When the applicant operates the mock up switches, then the booth operator should initiate Trigger 1.
TASK ELEMENT 1 STANDARD 8.7.1 Locally at CP-53, place both Control Room Ventilation Manual Switches to RESET.
Isolation switches to RESET.
Comment: Critical Coordinate this step with the Booth Operator.
SAT / UNSAT TASK ELEMENT 2 STANDARD 8.7.2 Verify following valves Open:
HVC-101 CR Norm OAI Dnstrm Isol Verification complete.
HVC-102 CR Norm OAI Upstrm Isol Comment:
SAT / UNSAT TASK ELEMENT 3 STANDARD 8.7.3 Start Toilet Exhaust Fan A(B), HVC-MFAN-0011A(B), then verify following:
Either A or B Fan started.
HVC-304A CR Toilet Exh Fan Bypass Damper.............................. Closed Damper verification is not HVC-304B CR Toilet Exh Fan Bypass Damper.............................. Closed critical.
HVC-306 CR Toilet Exh Fan Upstrm Isol.........................................Open HVC-307 CR Toilet Exh Fan Dnstrm Isol.........................................Open Comment: Critical It does not matter which train the applicant starts.
SAT / UNSAT Revision 0 Page 4 of 12 2011 NRC Walk Through Exam
JPM S7 TASK ELEMENT 4 STANDARD 8.7.4 Start Control Room Kitchen/Conference Exhaust Fan, HVC-MFAN-0012, then verify following:
Fan started.
HVC-312A Kitchen/Conf Rm Exh Fan Bypass Damper ................ Closed Damper verification is not HVC-312B Kitchen/Conf Rm Exh Fan Bypass Damper ................ Closed critical.
HVC-313 Kitchen/Conf Rm Exh Fan Upstream Isol.........................Open HVC-314 Kitchen/Conf Rm Exh Fan Downstream Isol ....................Open Comment: Critical SAT / UNSAT TASK ELEMENT 5 STANDARD 8.7.5 Reset the following valves by taking control switch through CLOSE position:
HVC-201A CR Emerg Fltr Unit N OAI Upstream Isol HVC-201B CR Emerg Fltr Unit N OAI Upstream Isol HVC-203A CR Emerg Fltr Unit S OAI Upstream Isol Dampers reset.
HVC-203B CR Emerg Fltr Unit S OAI Upstream Isol HVC-202A CR Emerg Fltr Unit N OAI Downstream Isol HVC-202B CR Emerg Fltr Unit N OAI Downstream Isol HVC-204A CR Emerg Fltr Unit S OAI Downstream Isol HVC-204B CR Emerg Fltr Unit S OAI Downstream Isol Comment: Critical SAT / UNSAT Revision 0 Page 5 of 12 2011 NRC Walk Through Exam
JPM S7 TASK ELEMENT 6 STANDARD NOTE Note verified.
At discretion of SM/CRS, one set of OAI valves in north or south intakes may be Open.
Comment:
Evaluator cue: Direct the applicant to leave the Outside Air Intake valves directed in step 8.7.7 open. SAT / UNSAT TASK ELEMENT 7 STANDARD 8.7.6 Verify Closed the following valves:
HVC-201A CR Emerg Fltr Unit N OAI Upstream Isol HVC-201B CR Emerg Fltr Unit N OAI Upstream Isol Verification complete.
HVC-203A CR Emerg Fltr Unit S OAI Upstream Isol HVC-203B CR Emerg Fltr Unit S OAI Upstream Isol Comment:
SAT / UNSAT TASK ELEMENT 8 STANDARD 8.7.7 Open the following valves:
HVC-202A CR Emerg Fltr Unit N OAI Downstream Isol HVC-202B CR Emerg Fltr Unit N OAI Downstream Isol Dampers opened.
HVC-204A CR Emerg Fltr Unit S OAI Downstream Isol HVC-204B CR Emerg Fltr Unit S OAI Downstream Isol Comment: Critical SAT / UNSAT Revision 0 Page 6 of 12 2011 NRC Walk Through Exam
JPM S7 TASK ELEMENT 9 STANDARD 8.7.8 If required, then Stop Control Room Emergency Filtration Unit A(B),
HVC-MFAN-0010A(B), and verify following:
Step will not be required.
HVC-205A(B) CR Emerg Fltr Unit A(B) Inlet Damper ................... Closed HVC-213A(B) CR Emerg Fltr Unit A(B) Recirc Damper ................ Closed Comment:
SAT / UNSAT TASK ELEMENT 10 STANDARD 8.7.8.1 When ten minutes have elapsed, then verify the red OFF light on Step will not be required.
the local control panel is Extinguished.
Comment:
SAT / UNSAT The following steps are from OP-002-010, Reactor Auxiliary Building HVAC and Containment Purge. The applicants cue sheet directs re-starting RAB Normal Ventillation.
TASK ELEMENT 11 STANDARD NOTE (1) The +46 HVAC Equipment Room Exhaust Fan, HVR0024A(B),
corresponding to the running +46 HVAC Equipment Room Supply Fan, HVR0022A(B), will automatically Start when HVAC Equipment Room temperature exceeds 90°F and will automatically Stop if temperature drops below 80°F. Note reviewed.
(2) When in Auto, the idle +46 HVAC Equipment Room Supply Fan, HVR0022A(B), and the corresponding +46 HVAC Equipment Room Exhaust Fan, HVR0024A(B), will both automatically Start when HVAC Equipment Room temperature exceeds 100°F and they will both automatically Stop if temperature drops below 90°F.
Comment: SAT / UNSAT Revision 0 Page 7 of 12 2011 NRC Walk Through Exam
JPM S7 TASK ELEMENT 12 STANDARD 6.1.1 Start +46 HVAC Equipment Room Supply Fan, HVR0022A(B), by Fan 22 A is already placing its control switch to Run. running.
Comment:
SAT / UNSAT TASK ELEMENT 13 STANDARD 6.1.2 If RAB ventilation is being started following a Toxic Chemical Monitor Trip, then override the trip by placing RAB Normal Exhaust Fan Override reset.
control switches to Stop.
Comment: Critical SAT / UNSAT TASK ELEMENT 14 STANDARD 6.1.3 Notify Radiation Protection prior to starting RAB Normal Ventilation Notification completed.
Units.
Comment:
SAT / UNSAT TASK ELEMENT 15 STANDARD NOTE Note reviewed.
When RAB Normal Exhaust Fans, HVR0009A(B), are started, HVAC B Radiation Monitor may alarm depending on gas levels in the RAB.
Comment:
SAT / UNSAT Revision 0 Page 8 of 12 2011 NRC Walk Through Exam
JPM S7 TASK ELEMENT 16 STANDARD 6.1.4 Start RAB Normal Exhaust Fan, HVR0009A(B). Fan started.
Comment: Critical There is a Caution Tag on RAB Exhaust Fan A to minimize use. If the applicant asks the CRS which train, direct the operation of train B. SAT / UNSAT TASK ELEMENT 17 STANDARD 6.1.5 Verify Discharge Damper for operating fan is Open:
HVR-122A (D52025) Verification complete.
HVR-122B (D52027)
Comment:
SAT / UNSAT TASK ELEMENT 18 STANDARD 6.1.6 Verify Suction Damper for operating fan is Not Closed:
HVR-121A (D52022) Verification complete.
HVR-121B (D52024)
Comment:
SAT / UNSAT Revision 0 Page 9 of 12 2011 NRC Walk Through Exam
JPM S7 TASK ELEMENT 19 STANDARD 6.1.7 Verify >69,000 SCFM indicated on Pt. ID S52432. Verification complete.
Comment:
SAT / UNSAT TASK ELEMENT 20 STANDARD NOTE Verification complete.
Always Start RAB Normal Supply Fan, HVR0002A(B), of same designation as operating Exhaust Fan, HVR0009A(B).
Comment:
SAT / UNSAT TASK ELEMENT 21 STANDARD Fan of the same Train as 6.1.8 Start RAB Normal Supply Fan, HVR0002A(B).
step 6.1.4 started.
Comment: Critical SAT / UNSAT TASK ELEMENT 22 STANDARD 6.1.9 Evaluate the need to start a Supplementary Chiller. Informs CRS.
Comment:
SAT / UNSAT END OF TASK Revision 0 Page 10 of 12 2011 NRC Walk Through Exam
JPM S7 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-197 Verify HVC-101 and HVC-102 are closed.
Verify the following Remote:
o HVR18 on trigger #1 to a position of RESET.
Revision 0 Page 11 of 12 2011 NRC Walk Through Exam
JPM S7 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- The plant is in Mode 1
- An inadvertent Toxic Gas signal was generated due to I&C maintenance.
- The faulted signal has been cleared.
INITIATING CUES:
The Control Room supervisor directs you to:
- Restore from Control Room Isolation in accordance with OP-003-014, Control Room Heating and Ventilation (HVC)
- Re-start RAB Normal Ventilation in accordance with OP-002-010, Reactor Auxiliary Building HVAC and Containment Purge.
Revision 0 Page 12 of 12 2011 NRC Walk Through Exam
System Operating Procedure OP-003-014 Control Room Heating and Ventilation (HVC) Revision 302 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS 3.1.1 Control Room Emergency Filtration Units should not be operated with painting, fire, or chemical release in progress within Control Room Envelope to prevent damage to charcoal beds.
3.2 LIMITATIONS 3.2.1 If CO2 level reaches 0.3%, then limit Control Room access to thirteen (13) people.
3.2.2 If unable to monitor CO2, then limit Control Room access to thirteen (13) people.
3.2.3 Outside air should not be supplied to the Control Room with the Emergency Filtration Unit operating except during surveillance testing or during Off-Normal or Emergency conditions.
3.2.4 Operability of the ARMs is not effected by the NORM/RECIRC Test Key Switch position.
5
System Operating Procedure OP-003-014 Control Room Heating and Ventilation (HVC) Revision 302 8.7 RESTORATION FROM CONTROL ROOM ISOLATION 8.7.1 Locally at CP-53, place both Control Room Ventilation Manual Isolation switches to RESET.
8.7.2 Verify following valves Open:
HVC-101 CR Norm OAI Dnstrm Isol HVC-102 CR Norm OAI Upstrm Isol 8.7.3 Start Toilet Exhaust Fan A(B), HVC-MFAN-0011A(B), then verify following:
HVC-304A CR Toilet Exh Fan Bypass Damper............................... Closed HVC-304B CR Toilet Exh Fan Bypass Damper............................... Closed HVC-306 CR Toilet Exh Fan Upstrm Isol.........................................Open HVC-307 CR Toilet Exh Fan Dnstrm Isol.........................................Open 8.7.4 Start Control Room Kitchen/Conference Exhaust Fan, HVC-MFAN-0012, then verify following:
HVC-312A Kitchen/Conf Rm Exh Fan Bypass Damper .................. Closed HVC-312B Kitchen/Conf Rm Exh Fan Bypass Damper .................. Closed HVC-313 Kitchen/Conf Rm Exh Fan Upstream Isol.........................Open HVC-314 Kitchen/Conf Rm Exh Fan Downstream Isol ....................Open 8.7.5 Reset the following valves by taking control switch through CLOSE position:
HVC-201A CR Emerg Fltr Unit N OAI Upstream Isol HVC-201B CR Emerg Fltr Unit N OAI Upstream Isol HVC-203A CR Emerg Fltr Unit S OAI Upstream Isol HVC-203B CR Emerg Fltr Unit S OAI Upstream Isol HVC-202A CR Emerg Fltr Unit N OAI Downstream Isol HVC-202B CR Emerg Fltr Unit N OAI Downstream Isol HVC-204A CR Emerg Fltr Unit S OAI Downstream Isol HVC-204B CR Emerg Fltr Unit S OAI Downstream Isol 21
System Operating Procedure OP-003-014 Control Room Heating and Ventilation (HVC) Revision 302 NOTE At discretion of SM/CRS, one set of OAI valves in north or south intakes may be Open.
8.7.6 Verify Closed the following valves:
HVC-201A CR Emerg Fltr Unit N OAI Upstream Isol HVC-201B CR Emerg Fltr Unit N OAI Upstream Isol HVC-203A CR Emerg Fltr Unit S OAI Upstream Isol HVC-203B CR Emerg Fltr Unit S OAI Upstream Isol 8.7.7 Open the following valves:
HVC-202A CR Emerg Fltr Unit N OAI Downstream Isol HVC-202B CR Emerg Fltr Unit N OAI Downstream Isol HVC-204A CR Emerg Fltr Unit S OAI Downstream Isol HVC-204B CR Emerg Fltr Unit S OAI Downstream Isol 8.7.8 If required, then Stop Control Room Emergency Filtration Unit A(B),
HVC-MFAN-0010A(B), and verify following:
HVC-205A(B) CR Emerg Fltr Unit A(B) Inlet Damper .......................... Closed HVC-213A(B) CR Emerg Fltr Unit A(B) Recirc Damper ....................... Closed 8.7.8.1 When ten minutes have elapsed, then verify the red OFF light on the local control panel is Extinguished.
22
System Operating Procedure OP-002-010 Reactor Auxiliary Building HVAC and Containment Purge Revision 303 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS 3.1.1 Containment Purge Supply Isolation valves, CAP-103 and CAP-104, and Containment Purge Exhaust Isolation valves, CAP-203 and CAP-204, may be Open at no greater than the 52 Open position for <90 hours every 365 days while in Modes 1, 2, 3, and 4.
3.1.2 Gas Decay Tank release may be initiated concurrent with Containment Purge provided the following conditions are met:
Containment Purge is in progress and Containment Purge is not on a Batch Release.
If Containment Purge flow is interrupted or Plant Stack flow is changed, then GDT release shall be secured.
3.1.3 If Reactor Auxiliary Building (RAB) Normal Ventilation is to be secured for greater than 30 minutes, then a Controlled Ventilation Area System (CVAS) Filter Train should be started. During the period ventilation is secured, Radiation Protection should monitor the air in any area considered to be an unmonitored release path.
If airborne levels are unacceptable, then RAB normal ventilation should be restored as soon as possible. The normal personnel access paths to the Controlled Access Area (CAA) in their standard configuration are not considered unmonitored release paths.
3.1.4 Do not operate CVAS Filter Units for non-emergency purposes if welding, burning, painting, or chemical cleaning activities are being performed within the CVAS boundary or RAB +46 HVAC room. [CR-WF3-2005-03517]
3.1.5 While in Modes 1 through 4, or during core alterations, or movement of irradiated fuel in containment, at least one containment purge isolation monitor per train must be operable with a setpoint of 40 mR/hr or 2 times background, whichever is higher.
Train A Train B ARMIRE5025 ARMIRE5024 ARMIRE5026 ARMIRE5027 5
System Operating Procedure OP-002-010 Reactor Auxiliary Building HVAC and Containment Purge Revision 303 3.1.6 One of the following Plant Stack Radiation Monitors must be operable in all modes. The operable Plant Stack Radiation Monitor Sample Pump must be operating prior to commencing Containment Purge.
Train A Train B PRMIRE0100-1 PRMIRE0100-2 3.1.7 Containment pressure should be 10 INWC before initiating Containment Purge.
If this cannot be achieved, then in order to ensure that Steam Generator Blowdown Isolation does not occur, one train of CVAS should be started prior to purge operation.
3.1.8 If Met Tower Wind Speed is unavailable when attempting Containment Purge, then obtain a copy of EP-002-050, Offsite Dose Assessment (Manual), Attachment 7.6, Meteorological Data and Calculation of Atmosphere Dispersion Factors, Step 2.1.2, and contact the National Weather Service.
3.1.9 If ambient barometric pressure is <29.7 INHG (14.58 PSIA) during containment purge, then the minimum Technical Specification Containment pressure of 14.275 PSIA could be exceeded.
3.1.10 Containment Purge should not be initiated if meteorological conditions of CE-003-515, Gaseous Radioactive Waste Release Permit (Computer), can not be met.
3.1.11 Containment Purge should not be initiated with the Maintenance Hatch closed and Personnel Airlock Door Interlock defeated. This is a personnel safety risk with persons transiting the airlock.
3.1.12 If the RAB Supply Fan is secured, then the RAB Exhaust Fan shall be Secured for personnel safety.
3.1.13 If Condenser Vacuum Pump Discharge is diverted to the Plant Stack via RAB Normal Exhaust, securing RAB Normal Exhaust can result in a chemical gas build-up (Condensate System Controls) in the +46 HVAC Room as well as the +46 HVAC Penetration Area. This chemical build-up can pose a safety hazard to employees working in the immediate area.
3.1.14 Do not secure RAB Normal Exhaust if Containment Pressure Reduction is in progress, to prevent an unmonitored release from containment into the
+46 HVAC Room as well as the +46 HVAC Penetration Area.
3.1.15 Lowering Containment pressure will cause indicated Containment Spray Riser Level to lower.
6
System Operating Procedure OP-002-010 Reactor Auxiliary Building HVAC and Containment Purge Revision 303 3.2 LIMITATIONS 3.2.1 Always Start HVAC Equipment Room Supply Fan, HVRMAHU0022, of same designation, A or B, as operating Exhaust Fan, HVRMFAN0024.
3.2.2 Always Start RAB Normal Supply Fan, HVRMFAN0002, of same designation, A or B, as operating Exhaust Fan, HVRMFAN0009.
3.2.3 Each time the Containment Purge Supply or Exhaust Dampers are Opened or Closed it shall be logged in the Operator's Log.
3.2.4 Inform Radiation Protection prior to Securing RAB Normal Ventilation. [P-11562]
3.2.5 Prior to securing RAB Normal Ventilation, notify Chemistry to suspend Fume Hood operation and give them an estimated duration that RAB Normal Ventilation will be secured.
3.2.6 CAP heater, CAPEEHC32B-4B, is designed to operate at Full Purge flow only (52 stops removed).
3.2.7 Containment Purge should remain in service as much as practical during outage activities (e.g., Steam Generator primary side activities, Reactor Head disassembly, Reactor Cavity decontamination, Reactor Head inspections, etc.)
Radiation Protection should be notified prior to securing Containment Purge.
7
System Operating Procedure OP-002-010 Reactor Auxiliary Building HVAC and Containment Purge Revision 303 6.0 NORMAL OPERATIONS 6.1 RAB NORMAL VENTILATION STARTUP [R]
NOTE (1) The +46 HVAC Equipment Room Exhaust Fan, HVR0024A(B), corresponding to the running +46 HVAC Equipment Room Supply Fan, HVR0022A(B), will automatically Start when HVAC Equipment Room temperature exceeds 90 F and will automatically Stop if temperature drops below 80 F.
(2) When in Auto, the idle +46 HVAC Equipment Room Supply Fan, HVR0022A(B), and the corresponding +46 HVAC Equipment Room Exhaust Fan, HVR0024A(B), will both automatically Start when HVAC Equipment Room temperature exceeds 100 F and they will both automatically Stop if temperature drops below 90 F.
6.1.1 Start +46 HVAC Equipment Room Supply Fan, HVR0022A(B), by placing its control switch to Run.
6.1.2 If RAB ventilation is being started following a Toxic Chemical Monitor Trip, then override the trip by placing RAB Normal Exhaust Fan control switches to Stop.
6.1.3 Notify Radiation Protection prior to starting RAB Normal Ventilation Units.
NOTE When RAB Normal Exhaust Fans, HVR0009A(B), are started, HVAC B Radiation Monitor may alarm depending on gas levels in the RAB.
6.1.4 Start RAB Normal Exhaust Fan, HVR0009A(B).
6.1.5 Verify Discharge Damper for operating fan is Open:
HVR-122A (D52025)
HVR-122B (D52027) 6.1.6 Verify Suction Damper for operating fan is Not Closed:
HVR-121A (D52022)
HVR-121B (D52024) 6.1.7 Verify >69,000 SCFM indicated on Pt. ID S52432.
10
System Operating Procedure OP-002-010 Reactor Auxiliary Building HVAC and Containment Purge Revision 303 NOTE Always Start RAB Normal Supply Fan, HVR0002A(B), of same designation as operating Exhaust Fan, HVR0009A(B).
6.1.8 Start RAB Normal Supply Fan, HVR0002A(B).
6.1.9 Evaluate the need to start a Supplementary Chiller.
11
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE S8 Waste Condensate Tank Discharge Applicant:
Examiner:
JPM S8 JOB PERFORMANCE MEASURE DATA PAGE Task: Waste Condensate Tank Discharge Task Standard: Applicant initiated Waste Condensate Tank release in accordance with OP-007-004, Liquid Waste Management System, and secured the release after the flow controller failed to maximum output.
References:
OP-007-004, Liquid Waste Management System CE-003-514, Liquid Radioactive Waste Release Permit (Computer)
Alternate Path: Yes Time Critical: No Validation Time: 15 mins.
K/A 068 A4.03, Stoppage of releases if limits Importance Rating 3.9 exceeded RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 7 2011 NRC Walk Through Exam
JPM S8 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-007-004, Liquid Waste Management System Discharge Permit for Waste Condensate Tank A
==
Description:==
The applicant will be tasked with initiating a discharge of Waste Condensate Tank A. The cue will indicate that the operator in the field has completed all required lineups and is standing by. When the applicant initiates flow, the flow controller output will fail high, causing discharge flow to exceed the 50 gpm permit flow limit. The flow controller will not be capable of securing flow. The applicant will stop discharge flow by closing the discharge isolation valves.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 7 2011 NRC Walk Through Exam
JPM S8 TASK ELEMENT 1 STANDARD 6.10.7 On CP-4, Reset Liquid Waste Discharge Flow Integrator to zero. Integrator is reset to zero.
Comment: Critical SAT / UNSAT TASK ELEMENT 2 STANDARD 6.10.8 Record WCT level and Liquid Waste Discharge Integrator Reading is recorded on the reading on Liquid Release Permit. Release Permit.
Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD 6.10.9 Verify Liquid Waste Discharge Flow Controller, LWM-IFIC-0647, Verification complete.
in Manual with 0% output.
Comment:
SAT / UNSAT TASK ELEMENT 4 STANDARD Procedure Caution: If Circulating Water flow is reduced to less than that required by the discharge permit, then discharge shall be secured Caution reviewed.
immediately.
Comment:
SAT / UNSAT Revision 0 Page 4 of 7 2011 NRC Walk Through Exam
JPM S8 Evaluator Note The combined control switch on CP-4 will open LWM-441 and give an open permissive to LWM-442.
LWM-442 is operated using controller LWM-IFIC-0647, also on CP-4.
Evaluator Note When flow rises above the trigger setpoint, the output of the controller will fail in the raise position. Flow will rise above the Permit limit of 50 gpm. The applicant will not be able to secure flow with the controller. The applicant will be required to secure flow by closing LWM-441 and LWM-442 using the control switch.
TASK ELEMENT 5 STANDARD 6.10.10 To start discharging WCT, momentarily position Liquid Waste LWM-441 is opened using Condensate Flow Control handswitch, LWM-441 and LWM-442, to Open control switch.
and adjust flow using Liquid Waste Condensate Flow Controller, LWM- LWM-442 is throttled open IFIC-0647, not to exceed value specified on Liquid Release Permit. using controller.
Comment: Critical The following step is the alternate path.
SAT / UNSAT TASK ELEMENT 6 STANDARD Applicant attempts to lower Attempt to lower release flow using Liquid Waste Condensate Flow flow using the lower Controller, LWM-IFIC-0647.
pushbutton.
Comment: Critical SAT / UNSAT TASK ELEMENT 6 STANDARD Position Liquid Waste Condensate Flow Control Switch for LWM-441 and LWM-441 and LWM-442 LWM-442 to Closed and verify LWM-441 and LWM-442 are closed. are closed.
Comment: Critical SAT / UNSAT END OF TASK Revision 0 Page 5 of 7 2011 NRC Walk Through Exam
JPM S8 SIMULATOR OPERATOR INSTRUCTIONS If there are no gallons indicated on the LWM Flow totalizer, then reset to IC-197, discharge greater than 100 gallons of water, and then proceed with the Simulator setup.
Reset to IC-197 There are no Malfunctions for this JPM.
Verify the following Overrides:
o DI-04A3A12C-3 is overridden to PUSH on Trigger 7 Verify the following Event Trigger settings:
Event Trigger 7 is set as zaowdlwmifif0647(2) > 0.2 Open INSIGHT
- Enter in the Name field
- In the Value field, type 5e-6 and press enter.
- Verify the background reading for the LWM Rad Monitor drops to < 1E-5.
When the JPM is complete, restore RMKNORMBG (P17) to 1.4e-4.
Revision 0 Page 6 of 7 2011 NRC Walk Through Exam
JPM S8 APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Waste Condensate Tank A has been prepared for discharge.
- The RCA Watch reports that he has completed step 6.10.6 in OP-007-004, Liquid Waste Management System, and that Attachment 11.4, Waste Condensate Tank Discharge Checklist, is complete INITIATING CUES:
- The Control Room Supervisor directs you to commence discharging Waste Condensate Tank A, starting at step 6.10.7 of OP-007-004, Liquid Waste Management System.
Revision 0 Page 7 of 7 2011 NRC Walk Through Exam
R Type K2.33 Liquid Waste batch Release Permit Permit Number: LB2011-0082 Entergy Operations, Inc. Waterford Steam Electric Station Unit III Release Point (1) : Waste Condensate Tank A Waste Volume : 15,497 gal Maximum Waste Flow: 50.00 gpm Minimum Dilution Flow : 5.00 e+5 gpm (2 Circ Water Pumps) Total Gamma Conc. : 1.04e-05 uCi/ml SINGLE Release Setpoint for PRM-IRE-0647 8.00e-02 uCi/ml *** ADJUST ***
- Concurrent with Permit Number LC2009-0043 : (22) Dry Cooling Tower Sump #1 to Circ Water
- Concurrent with Permit Number LC2009-0044 : (23) Dry Cooling Tower Sump #21 to Circ Water
- Concurrent with Permit Number LC2009-0045 : (24) TGB Industrial Waste Sump to Circ Water Estimated Maximum Organ Dose: 0.00 mrem for the Adult Thyroid Estimated Cumulative Maximum Organ Doses - Including this release.
31 Day Quarter - To - Date Year - To - Date Limit 0.06 mrem 1.50 mrem 3.00 mrem Organ Total Body Total Body Total Body 0.000 mrem 0.00 mrem 0.0029 mrem Special Conditions : Adjust PRM-IRE-0647 radiation monitor setpoint to 8.00 e-02 uCi/ml prior to release.
PRM-IRE-0647 setpoint to 6.50 e-01 uCi/ml after release permit is closed.
Prepared By: Reviewed By: Approved By:
S. Chemist C. Supervisor C.R. Supervisor Date: 8/12/2011 Date: 8/12/2011 Date: 8/12/2011 PRM-IRE-0647 Radiation Monitor Source Check: JVS Channel Check:
Circ. Water Flowrate: 1,000,000 gpm Date Time Tank Level % Flow Integrator (gal)
Release Start Release Finish
- NET
- min.
gal / min = gpm = Average Waste Flow Rate (Flow Integrator) (Release Time) gal / min = gpm = Average Waste Flow Rate (Plant Data Book) (Release Time)
Radiation Monitor Readings for PRM-IRE-0647 10 minutes into release: uCi/m l After Flush: uCi/ml Remarks:
Release Completed By: Date / Time Operations Release Reviewed By: Date / Time CRS / SM Release Reviewed By: Date / Time HP Forman / Designee Revision 0 JPM S8 2011 NRC Walk Through Exam
System Operating Procedure OP-007-004 Liquid Waste Management System Revision 302 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS 3.1.1 When operating Liquid Waste Management System, prescribed radiological methods shall be followed.
3.1.2 When mixing resin, a face shield should be worn to protect against resin blowback if full-face respirator is not required by Radiation Work Permit.
3.1.3 Tank to be released shall be isolated and shall not receive any influent during recirculation, sampling, or discharge.
3.1.4 Immediately after terminating a discharge, release path shall be secured to prevent unplanned release.
3.1.5 If excessive torque is applied to diaphragm valves when closing, damage may occur.
3.1.6 Prior to performing any evolution that could alter posted radiation levels for affected areas, Radiation Protection should be contacted.
3.1.7 Prior to performing any evolution involving transfer of liquid waste, ion exchanger operations, or liquid waste discharges, Chemistry should be notified.
3.1.8 This procedure contains inactivated equipment. The isolation boundaries are identified in the appropriate Standby Valve Lineup.
5
System Operating Procedure OP-007-004 Liquid Waste Management System Revision 302 3.2 LIMITATIONS 3.2.1 Oil separator is normally bypassed. It is only designed to remove approximately 900 grams of oil.
3.2.2 If discharge activity exceeds alarm setpoint established on LWM Radiation Monitor, PRM-IRE-0647, then immediately go to OP-901-412, Liquid Waste Discharge High Radiation.
3.2.3 If circulating water flow is reduced to less than that required by discharge permit, then immediately secure discharge.
3.2.4 A Batch Radioactive Effluent Release Request Form, HP-001-231, should be used to initiate sampling for liquid effluent release.
3.2.5 Waste Storage Tank (WST) should not be filled more than 50% without specific permission of SM/CRS. Prior to filling tank over 50%, Radiation Protection shall be notified.
3.2.6 Maximum operating DP for the Waste Filter is 25 psid. Waste Filter Bypass may be throttled to maintain Waste Filter DP to 25 psid. Mechanical Maintenance should be informed that the filter element requires change out if throttling is necessary to limit Waste Filter DP.
3.2.7 LWM Radiation Monitor, PRM-IRE-0647, activity level must be less than 2.2E-05 Ci/ml prior to discharging either the Waste Condensate Tanks or the Laundry Tanks to Circulating Water. If activity is greater than 2.2E-05 Ci/ml, then I&C Maintenance should be contacted to decontaminate the sample chamber. If activity is greater than 3.5E-05 Ci/ml, the LWM Radiation Monitor should be declared Inoperable and I&C Maintenance should be contacted to decontaminate the sample chamber. [ER-W3-00-0160-00-00]
6
System Operating Procedure OP-007-004 Liquid Waste Management System Revision 302 6.10 DISCHARGING W ASTE CONDENSATE TANKS TO CIRCULATING W ATER SYSTEM (C)
CAUTION WASTE CONDENSATE TANK A(B) CANNOT BE RECIRCULATED WHILE DISCHARGING WASTE CONDENSATE TANK B(A) DUE TO LWM-308A(B), WCT A(B) OUTLET ISOLATION, BEING CLOSED DURING DISCHARGE TO CIRCULATING WATER.
6.10.1 Verify WCT to be discharged has been recirculated and sampled in accordance with Section 6.9, Recirculating Waste Condensate Tanks for Sample.
6.10.2 Verify one of the following Circulating Water Boxes is in service:
B2 C1 C2 6.10.3 Verify that Liquid Release Permit to discharge WCT to Circulating Water has been issued.
NOTE SM/CRS permission signifies that the plant is in a condition that will allow for the discharge of the appropriate tank. [Commitment P-25084]
6.10.4 Obtain SM/CRS permission to perform Discharge, document on Attachment 11.4, Waste Condensate Tank Discharge Checklist, and Liquid Release Permit.
NOTE Successful performance of Step 6.10.5.3 satisfies TRM Table 4.3-8, Source Check Prior to release.
6.10.5 Perform the following:
6.10.5.1 Verify LWM Radiation Monitor, PRM-IRE-0647, activity is less than or equal to 2.2E-5 Ci/ml per Limitation 3.2.7.
6.10.5.2 Perform a source check for LWM Radiation Monitor, PRM-IRE-0647, on the RM-11 at CP-6 console or locally at the RM-80 by Depressing Check Source (C/S) Pushbutton. [Commitment P-17843]
6.10.5.3 Verify monitor passes source check. If monitor does not pass source check, then contact Chemistry.
20
System Operating Procedure OP-007-004 Liquid Waste Management System Revision 302 6.10.5.4 When a successful source check has been completed, then document on Liquid Release Permit.
6.10.6 Perform Steps 1 through 20 of Attachment 11.4, Waste Condensate Tank Discharge Checklist.
6.10.7 On CP-4, Reset Liquid Waste Discharge Flow Integrator to zero.
6.10.8 Record WCT level and Liquid Waste Discharge Integrator reading on Liquid Release Permit.
6.10.9 Verify Liquid Waste Discharge Flow Controller, LWM-IFIC-0647, in Manual with 0% output.
CAUTION IF CIRCULATING WATER FLOW IS REDUCED TO LESS THAN THAT REQUIRED BY THE DISCHARGE PERMIT, THEN DISCHARGE SHALL BE SECURED IMMEDIATELY.
6.10.10 To start discharging WCT, momentarily position Liquid Waste Condensate Flow Control handswitch, LWM-441 and LWM-442, to Open and adjust flow using Liquid Waste Condensate Flow Controller, LWM-IFIC-0647, not to exceed value specified on Liquid Release Permit.
6.10.10.1 Throttle WCT Pump A(B) Recirc Isolation, LWM-315A(B), as necessary to achieve desired flow.
6.10.11 Record Start date and time on Liquid Release Permit.
NOTE Successful performance of Step 6.10.12 satisfies TRM Table 4.3-8, Channel Check. If the instrument specified is not available, then alternate or local readings may be used to satisfy Channel Check requirements. Note alternate indication used in Remarks section of Liquid Release Permit. [Commitments P-17822, P-17840]
6.10.12 Verify Liquid Waste Management Discharge Flow Recorder, LWM-IFRR-0647, deflects upscale to provide discharge flow indication.
6.10.13 If it is desired to place Liquid Waste Condensate Flow Controller, LWM-IFIC-0647 in Auto, then match Setpoint to process flow and place in Auto.
6.10.13.1 Verify Liquid Waste Condensate Flow less than or equal to value specified on Liquid Release Permit.
6.10.14 On CP-4, periodically monitor discharge flow and activity to verify that they are within limits of Liquid Release Permit.
21
System Operating Procedure OP-007-004 Liquid Waste Management System Revision 302 6.10.15 After discharging for 10 minutes, then record Liquid Waste Discharge Monitor, PRM-IRE-0647, reading on Liquid Release Permit.
6.10.16 When WCT level drops to approximately 5% or at SM/CRS discretion, then perform the following:
6.10.16.1 Verify Waste Condensate Tank Pump A(B) Stops.
6.10.16.2 Close the following valves:
LWM-441 LWM to Circulating Water Shutoff Isol LWM-442 LWM to Circulating Water Control Isol 6.10.17 Verify Liquid Waste Condensate Flow Controller, LWM-IFIC-0647, in Manual with an output of 0%.
6.10.18 Complete Attachment 11.4, Waste Condensate Tank Discharge Checklist.
6.10.19 Complete Liquid Release Permit.
6.10.20 Forward completed Liquid Release Permit to Chemistry.
22
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE P1 Secure Shutdown Cooling Purification Applicant:
Examiner:
JPM P1 JOB PERFORMANCE MEASURE DATA PAGE Task: Secure Shutdown Cooling Purification Task Standard: During Shutdown Cooling alignment, applicant recognizes that SI-423, Shutdown Cooling Purification Supply Isolation, reach rod malfunctions. The applicant must be able to describe how the component position would be verified.
References:
OP-009-005, Shutdown Cooling EN-OP-115-05, Operation of Components Alternate Path: Yes Time Critical: No Validation Time: 15 mins.
K/A 005 A2.04, RHR valve malfunction Importance Rating 2.9 RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 6 2011 NRC Walk Through Exam
JPM P1 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-009-005, Shutdown Cooling
==
Description:==
This task is performed on the -4 level. The applicant will begin to secure Shutdown Cooling Purification. The fourth valve in the task, SI-423 Shutdown Cooling Purification Supply Isolation, a reach rod operated valve, will malfunction. The reach rod pin will bottom out prior to the valve reaching full closed position. The applicant should stop at this point and get shift management involved in the situation. The evaluator will ask the applicant what actions are necessary with the given indications. The applicant must be able to describe how the component position would be verified.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All steps for this JPM will be simulated, do not manipulate any plant components. Make all necessary communications to me. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 6 2011 NRC Walk Through Exam
JPM P1 TASK ELEMENT 1 STANDARD 6.7.1 Adjust Letdown Backpressure controller, CVC-IPIC-0201, output to Contacts Control Room ZERO.
Comment:
Cue the applicant that the output of the letdown Backpressure controller is ZERO. SAT / UNSAT TASK ELEMENT 2 STANDARD 6.7.2 Close and Lock Shutdown Cooling Purification Letdown Ht Ex Valve is closed Bypass, SI-424.
Comment: Critical Provide cue to the applicant of valve position moving from open to closed. SAT / UNSAT Cue that the indicating pin is NOT on the bottom of the indicator and moves freely.
TASK ELEMENT 3 STANDARD 6.7.3 Close and Lock RC Loop 2(1) Shdn Cooling Purification Supply Valve is closed Isol, SI-418A(B).
Comment: Critical Provide cue to the applicant of valve position moving from open to closed. SAT / UNSAT Cue that the indicating pin is NOT on the bottom of the indicator and moves freely.
TASK ELEMENT 4 STANDARD 6.7.4 Close and Lock Letdown to LPSI Pump A(B) Suction Isol, CVC-Valve is closed 1654A(B).
Comment: Critical Provide cue to the applicant of valve position moving from open to closed. SAT / UNSAT Cue that the indicating pin is NOT on the bottom of the indicator and moves freely.
Revision 0 Page 4 of 6 2011 NRC Walk Through Exam
JPM P1 TASK ELEMENT 5 STANDARD Applicant discovers that the position indicating pin for 6.7.5 Close and Lock Shdn Cooling Purification Supply Isol, SI-423.
SI-423 bottoms out before the valve is closed.
Comment: Critical Evaluator: Provide indication that SI-423 is unlocked and travels closed.
Provide cue that the position indicating pin hits the bottom of its travel SAT / UNSAT while the applicant is simulating closing SI-423.
TASK ELEMENT 6 STANDARD From EN-OP-115-05, Operation of Components:
If a valve position indicator pin bottoms out or tops out during repositioning or if a dial indicator is suspected to not be indicating correctly, then perform the following:
- 1. Verify valve position by at least one of the following methods:
- a. Local position indication, or Ask applicant requirements due to these b. Computer point indication, indications.
or
- c. Verification of system parameters (flow, pressure, etc.).
- 2. Generate a Caution Tag for the valve and hang the tag on the remote hand wheel.
- 3. Generate a Work Request on the reach rod post indicator.
- 4. Classify the work request as a Work Around or Burden as appropriate on the valve position verification.
Comment: Critical The applicant must be able to describe how the SAT / UNSAT component position would be verified. Recalling the documentation is not critical.
END OF TASK Revision 0 Page 5 of 6 2011 NRC Walk Through Exam
JPM P1 APPLICANT CUE SHEET Do Not Manipulate Any Plant Components (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Shutdown Cooling Train A is in service.
- Shutdown Cooling Purification is aligned to Train A.
INITIATING CUES:
- The CRS directs you to secure Shutdown Cooling Purification in accordance with OP-009-005, Shutdown Cooling Purification, section 6.7.
Revision 0 Page 6 of 6 2011 NRC Walk Through Exam
System Operating Procedure OP-009-005 Shutdown Cooling Revision 027 6.7 SECURING SHUTDOWN COOLING PURIFICATION 6.7.1 Adjust Letdown Backpressure controller, CVC-IPIC-0201, output to ZERO.
6.7.2 Close and Lock Shutdown Cooling Purification Letdown Htex Bypass, SI-424.
6.7.3 Close and Lock RC Loop 2(1) Shdn Cooling Purification Supply Isol, SI-418A(B).
6.7.4 Close and Lock Letdown to LPSI Pump A(B) Suction Isol, CVC-1654A(B).
6.7.5 Close and Lock Shdn Cooling Purification Supply Isol, SI-423.
6.7.6 Close and Lock Letdown to LPSI Pumps Suction Isol, CVC-164.
6.7.7 Open and Lock Purification Ion Exchs Outlet Header Isolation, CVC-1661.
6.7.8 Place Letdown to Ion Exchangers Inlet/Bypass, CVC-140, control switch to AUTO.
6.7.9 Complete Attachment 11.3 (11.4), Restoration Lineup for SDC Train A(B), for applicable locked valves operated.
41
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE P2 SUPS 014 AB Operation Applicant:
Examiner:
JPM P2 JOB PERFORMANCE MEASURE DATA PAGE Task: Transfer SUPS 014 AB from Alternate to Normal AC power Task Standard: SUPS 014 AB was transferred from Alternate to Normal AC alignment in accordance with OP-006-005, Inverters and Distribution.
References:
OP-006-005, Inverters and Distribution Alternate Path: Yes Time Critical: No Validation Time: 20 mins.
K/A 062 A3.04, Operation of inverter Importance Rating 2.7 / 2.9 RO / SRO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 11 2011 NRC Walk Through Exam
JPM P2 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-006-005, Inverters and Distribution
==
Description:==
SUPS 014 AB will be simulated in the Alternate AC power alignment. Applicant will transfer SUPS 014 AB to the Normal AC alignment. All steps will be simulated in Switchgear Room A. No special PPE will be required for this task.
There is a summary of the initial breaker positions and the initial meter readings before the task elements.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All steps for this JPM will be simulated, do not manipulate any plant components. Make all necessary communications to me. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 11 2011 NRC Walk Through Exam
JPM P2 M1 M2 M3 M4 M6 I-1 I-2 I-3 M5 M7 I-4 I-5 I-6 2 A PB-1 PB-2 PB-3 3 4 1 3 C B 2 5 1 6 STATIC SWITCH RETRANSFER PB-4 S4 PB-5 S1 S2 S3 AUTO INHIBIT TRANSFER TEST CB1 CB2 CB3 CB4 CB5 ALTERNATE OUTPUT BYPASS NORMAL EMERGENCY FEEDER TO PDP FEEDER FEEDER Open / Open / Closed / Open / Open /
Off Off On Off Off Revision 0 Page 4 of 11 2011 NRC Walk Through Exam
JPM P2 Indications METERS Item Designation Comment M1 Inverter Input Voltage Voltage reads zero until AC power is (0-150 VDC) applied to the rectifier at step 6.5.3.1.1.
M2 Inverter Input Current Current reads zero until AC power is (0-400 DC Amps) applied to the rectifier at step 6.5.3.1.1.
M3 Battery Current (400 amps Reads as displayed throughout evolution.
discharge to 400 amps charge)
M4 Battery Recharge Timer Reads as displayed throughout evolution.
(0-30 Hours)
M5 AC Voltage (0-250 VAC) In the Inverter position, Voltage reads zero until step 6.5.3.9.
In the UPS position, voltage reads zero until step 6.5.3.4.
M6 Frequency (57-63 Hz) Frequency reads 60 (center) until step 6.5.3.9.
M7 UPS Output Current System load current reads zero until step (0-150 Amps AC) 6.5.3.6.
INDICATOR LIGHTS Item Designation Indication I-1 Inverter Phase Locked Illuminates at step 6.5.3.9.
I-2 High-Low DC Voltage Illuminated at the start of the JPM, clears at step 6.5.3.1.
I-3 Inverter Output Overload Remains OFF during JPM.
I-4 Over temperature Remains OFF during JPM.
I-5 Static Switch Inhibited Illuminated at the start of the JPM, clears at step 6.5.3.3.
I-6 Static Switch On Reserve Clear at the start of the JPM, illuminates at step 6.5.3.4.
Revision 0 Page 5 of 11 2011 NRC Walk Through Exam
JPM P2 TASK ELEMENT 1 STANDARD 6.5.3.1.1 Place Normal Feeder breaker to ON. Breaker is ON.
Examiner Cue: Breaker will be OFF on arrival, provide cue of breaker being moved from OFF to ON.
Comment: Critical Meters M1 and M2 move to read as is after this step is performed.
SAT / UNSAT TASK ELEMENT 2 STANDARD 6.5.3.1.2 Verify Inverter Input Voltage > 121 VDC, then place Emergency Breaker is ON.
Feeder breaker to ON.
Examiner Cue: Breaker will be OFF on arrival, provide cue of breaker being moved from OFF to ON.
Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD Pushbutton is pressed and 6.5.3.1.3 Depress and release Inverter Operate pushbutton.
released.
Comment: Critical SAT / UNSAT TASK ELEMENT 4 STANDARD 6.5.3.2 Verify SUPS 014AB Static Switch Retransfer toggle switch in Verification complete.
INHIBIT.
Examiner Cue: The Static Switch Retransfer toggle switch will already be in INHIBIT.
Comment:
SAT / UNSAT Revision 0 Page 6 of 11 2011 NRC Walk Through Exam
JPM P2 TASK ELEMENT 5 STANDARD 6.5.3.3 Place SUPS 014AB Alternate Feeder breaker to ON. Breaker is ON.
Examiner Cue: Breaker will be OFF on arrival, provide cue of breaker being moved from OFF to ON.
Comment: Critical The Static Switch Inhibited light goes OFF when this is performed.
SAT / UNSAT TASK ELEMENT 6 STANDARD 6.5.3.4 Depress and release SUPS 014AB Static Switch Transfer Test Test pushbutton depressed pushbutton. and released.
Comment: Critical The Static Switch On Reserve light illuminates when this is performed.
SAT / UNSAT TASK ELEMENT 7 STANDARD 6.5.3.4.1 Verify Static Switch On Reserve light Illuminates. Verification complete.
Comment:
SAT / UNSAT TASK ELEMENT 8 STANDARD Pushbutton depressed and 6.5.3.5 Depress and release SUPS 014AB Lamp Test/Reset pushbutton.
released.
Comment: Critical SAT / UNSAT Revision 0 Page 7 of 11 2011 NRC Walk Through Exam
JPM P2 TASK ELEMENT 9 STANDARD 6.5.3.5.1 Verify Static Switch On Reserve light remains Illuminated. Verification complete.
Comment:
SAT / UNSAT TASK ELEMENT 10 STANDARD 6.5.3.6 Place SUPS 014AB Output To PDP014AB breaker to ON. Breaker is ON.
Examiner Cue: Breaker will be OFF on arrival, provide cue of breaker being moved from OFF to ON.
Comment: Critical SAT / UNSAT TASK ELEMENT 11 STANDARD 6.5.3.7 Place SUPS 014AB Bypass breaker to OFF. Breaker is OFF.
Examiner Cue: Breaker will be ON on arrival, provide cue of breaker being moved from ON to OFF.
Comment: Critical SAT / UNSAT TASK ELEMENT 12 STANDARD Select Switch is verified in 6.5.3.8 Place SUPS 014AB AC Voltage Select Switch to INVERTER.
INVERTER.
Examiner Cue: The AC Voltage Select Switch could be in what ever position the last watch stander left it in.
Comment:
SAT / UNSAT Revision 0 Page 8 of 11 2011 NRC Walk Through Exam
JPM P2 Evaluator Note When applicant observes the SUPS Output Voltage meter, provide indication of zero volts.
If the applicant presses the Operate pushbutton, provide the indications provided in Task Element 13.
If the applicant does not press the Operate pushbutton, then provide the indication that the Static Switch On Reserve light is still illuminated at Task Element 16.
TASK ELEMENT 13 STANDARD 6.5.3.9 If no voltage is indicated, then depress and release SUPS 014AB Inverter Operate pushbutton, and verify the following:
- Inverter Phase Locked light Illuminated Observes no voltage in any Inverter position and
- Inverter Output voltage CN ~120 VAC (118.8 to 121.2 VAC) presses and releases the
- Inverter Output voltage AN ~120 VAC (118.8 to 121.2 VAC)
Operate pushbutton.
- Inverter Output voltage BN ~120 VAC (118.8 to 121.2 VAC)
- Inverter Output frequency ~60 Hz (59.97 to 60.03 Hz)
Comment: Critical The applicant must use the multi-selector switch and move through these positions. SAT / UNSAT There will be no voltage indicated in any Inverter position. If the applicant observes any UPS position, voltage will be as indicated.
TASK ELEMENT 14 STANDARD 6.5.3.10 Place SUPS 014AB Static Switch Retransfer toggle switch to Toggle Switch is in Auto.
AUTO.
Examiner cue: Static Switch Retransfer toggle switch will be in INHIBIT at this point, cue that the switch is moved from INHIBIT to AUTO.
Comment: Critical SAT / UNSAT Revision 0 Page 9 of 11 2011 NRC Walk Through Exam
JPM P2 TASK ELEMENT 15 STANDARD 6.5.3.11 After approximately 30 seconds, depress and release SUPS Pushbutton pressed and 014AB Lamp Test/Reset pushbutton. released.
Examiner cue: 30 seconds have elapsed. After this pushbutton is depressed, the Static Switch On Reserve light will extinguish.
Comment: Critical SAT / UNSAT TASK ELEMENT 16 STANDARD 6.5.3.11.1 Verify Static Switch On Reserve light Extinguished. Verification complete.
Comment:
SAT / UNSAT END OF TASK Revision 0 Page 10 of 11 2011 NRC Walk Through Exam
JPM P2 APPLICANT CUE SHEET Do Not Manipulate Any Plant Components (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- The inverter was isolated in accordance with OP-006-005, Inverters and Distribution, step 6.5.2.7.
INITIATING CUES:
- The CRS directs you to place SUPS 014 AB in the Normal AC alignment in accordance with OP-006-005, Inverters and Distribution, section 6.5.3.
Revision 0 Page 11 of 11 2011 NRC Walk Through Exam
System Operating Procedure OP-006-005 Inverters and Distribution Revision 306 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS 3.1.1 An inverter and its alternate source must be verified in synchronization prior to attempting any transfer operations.
3.1.2 Breaker Lineups are to be used for verification of breaker positions only. All repositioning of breakers should be performed in accordance with the applicable sections of this procedure.
3.1.3 The Computer SUPS and SUPS 014AB should not be operated on the Normal AC supply without the DC input power (emergency DC supply) supplied from the battery. Normal operation without DC input power supplied by the battery may cause damage to the SUPS unit and/or SUPS output loads. The SUPS output should be manually transferred to the Bypass/Alternate AC Supply whenever any of the following are Open:
The local Battery Input breaker The associated DC Input feeder breaker The associated Battery Disconnect 3.1.4 SUPS A, B, AB, MA, MB, MC, and MD may be operated on the normal AC supply without the DC input power (emergency DC supply) supplied from the battery.
The duration operating in this condition should be minimized. [EC-11831]
3.2 LIMITATIONS 3.2.1 An ACC Pump A(B) CCW High Temperature Auto-Start signal may be temporarily generated when opening or closing load circuit #3 breaker for SUPS MA(B).
3.3.2 Technical Specifications 3.8.3.1 and 3.8.3.2 should be reviewed prior to changing status of any Safety SUPS.
3.3.3 Capacitors should be allowed to fully discharge (for at least 60 seconds) prior to re-energizing inverters.
5
System Operating Procedure OP-006-005 Inverters and Distribution Revision 306 6.5 SUPS 014AB NORMAL MANIPULATIONS 6.5.1 Notify Security that operations are being performed on SUPS 014AB.
6.5.2 Transfer SUPS 014AB from Normal to Alternate AC Power as follows:
CAUTION SUPS 014AB SHOULD NOT BE OPERATED ON THE NORMAL AC SUPPLY WITHOUT THE DC INPUT POWER (EMERGENCY DC SUPPLY) SUPPLIED FROM THE BATTERY.
NORMAL OPERATION WITHOUT DC INPUT POWER SUPPLIED BY THE BATTERY MAY CAUSE DAMAGE TO THE SUPS UNIT AND/OR SUPS OUTPUT LOADS. THE SUPS OUTPUT SHOULD BE MANUALLY TRANSFERRED TO THE BYPASS/ALTERNATE AC SUPPLY WHENEVER ANY OF THE FOLLOWING ARE OPEN:
THE LOCAL BATTERY INPUT BREAKER THE ASSOCIATED DC INPUT FEEDER BREAKER THE ASSOCIATED BATTERY DISCONNECT 6.5.2.1 Place SUPS 014AB Static Switch Retransfer toggle switch to INHIBIT.
6.5.2.2 Depress and release SUPS 014AB Static Switch Transfer Test pushbutton, and verify Static Switch On Reserve light Illuminated.
6.5.2.3 Depress and release SUPS 014AB Lamp Test/Reset pushbutton, and verify Static Switch On Reserve light remains Illuminated.
6.5.2.4 Place SUPS 014AB Bypass breaker, ID-EBKR9335-5 to ON.
6.5.2.5 Place SUPS 014AB Output To PDP014AB breaker, ID-EBKR9335-4 to OFF.
6.5.2.6 Place SUPS 014AB Alternate Feeder breaker, ID-EBKR9335-3 to OFF.
6.5.2.7 If SUPS 014AB inverter is to be isolated, then perform the following:
6.5.2.7.1 Depress and release Inverter Standby pushbutton.
6.5.2.7.2 Place Emergency Feeder breaker, ID-EBKR9335-2 to OFF.
6.5.2.7.3 Place Normal Feeder breaker, ID-EBKR9335-1 to OFF.
34
System Operating Procedure OP-006-005 Inverters and Distribution Revision 306 6.5.3 Transfer SUPS 014AB from Alternate to Normal AC Power as follows:
6.5.3.1 If SUPS 014AB inverter has been isolated in accordance with step 6.5.2.7, then perform the following:
6.5.3.1.1 Place Normal Feeder breaker, ID-EBKR9335-1 to ON.
6.5.3.1.2 Verify Inverter Input Voltage > 121 VDC, then place Emergency Feeder breaker, ID-EBKR9335-2 to ON.
6.5.3.1.3 Depress and release Inverter Operate pushbutton.
6.5.3.2 Verify SUPS 014AB Static Switch Retransfer toggle switch in INHIBIT.
6.5.3.3 Place SUPS 014AB Alternate Feeder breaker, ID-EBKR9335-3 to ON.
6.5.3.4 Depress and release SUPS 014AB Static Switch Transfer Test pushbutton.
6.5.3.4.1 Verify Static Switch On Reserve light Illuminates.
6.5.3.5 Depress and release SUPS 014AB Lamp Test/Reset pushbutton.
6.5.3.5.1 Verify Static Switch On Reserve light remains Illuminated.
6.5.3.6 Place SUPS 014AB Output To PDP014AB, ID-EBKR9335-4 breaker to ON.
6.5.3.7 Place SUPS 014AB Bypass breaker, ID-EBKR9335-5 to OFF.
6.5.3.8 Place SUPS 014AB AC Voltage Select Switch to INVERTER.
6.5.3.9 If no voltage is indicated, then depress and release SUPS 014AB Inverter Operate pushbutton, and verify the following:
Inverter Phase Locked light Illuminated Inverter Output voltage CN ~120 VAC (118.8 to 121.2 VAC)
Inverter Output voltage AN ~120 VAC (118.8 to 121.2 VAC)
Inverter Output voltage BN ~120 VAC (118.8 to 121.2 VAC)
Inverter Output frequency ~60 Hz (59.97 to 60.03 Hz) 6.5.3.10 Place SUPS 014AB Static Switch Retransfer toggle switch to AUTO.
6.5.3.11 After approximately 30 seconds, depress and release SUPS 014AB Lamp Test/Reset pushbutton.
6.5.3.11.1 Verify Static Switch On Reserve light Extinguished.
35
Waterford 3 2011 NRC Walk Through Exam JOB PERFORMANCE MEASURE P3 Actions for Main Feedwater Leakage in Emergency Feedwater Applicant:
Examiner:
JPM P3 JOB PERFORMANCE MEASURE DATA PAGE Task: Perform corrective actions for Main Feedwater Leakage into Emergency Feedwater Task Standard: Applicant completes OP-903-001, Technical Specification Surveillance Logs, Attachment 11.12, EFW Steam Binding Corrective Actions, for Emergency Feedwater Pump A.
References:
OP-903-001, Technical Specification Surveillance Logs, Attachment 11.12, EFW Steam Binding Corrective Actions Alternate Path: Yes Time Critical: No Validation Time: 15 mins.
K/A 061 A2.06, Back leakage of MFW Importance Rating 2.7 RO Applicant:
Time Start: Time Finish:
Performance Time: minutes Performance Rating: SAT UNSAT Comments:
Examiner: Date:
Signature Revision 0 Page 2 of 6 2011 NRC Walk Through Exam
JPM P3 EXAMINER COPY ONLY Tools/Equipment/Procedures Needed:
OP-903-001, Technical Specification Surveillance Logs, Attachment 11.12, EFW Steam Binding Corrective Actions
==
Description:==
This task is performed on the -35 level in Emergency Feedwater Pump Room A. The applicant will perform steps to flush cool water from the Condensate Storage Pool through Emergency Feedwater Pump A.
Due to the lack of a power operated relief valve on the Reactor Coolant System and the lack of once through cooling, the Emergency Feedwater System is rated high in the Waterford PRA report.
DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All steps for this JPM will be simulated, do not manipulate any plant components. Make all necessary communications to me. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task.
Read the Initial Condition and Cues from the colored Applicant Cue Sheet, and then give the cue sheet to the applicant.
Revision 0 Page 3 of 6 2011 NRC Walk Through Exam
JPM P3 TASK ELEMENT 1 STANDARD 11.12.5 Unlock and Close the affected EFW Pump Discharge Isolation:
- EFW-211A EFW Pump A Discharge Isolation Comment: Critical SAT / UNSAT TASK ELEMENT 2 STANDARD 11.12.6 Open the affected EFW Pump Discharge Drain/Vent:
- EFW-208A EFW Pump A Discharge Drain Comment: Critical SAT / UNSAT TASK ELEMENT 3 STANDARD 11.12.7 When a solid stream of cool water issues from the affected EFW Pump Discharge Drain/Vent, then Close the affected EFW Pump Discharge Drain/Vent:
- EFW-208A EFW Pump A Discharge Drain Comment: Critical SAT / UNSAT TASK ELEMENT 4 STANDARD 11.12.8 If the affected EFW Pump is EFW Pump AB, then Not applicable Open EFW Pump AB Stop Valve, MS-416.
Comment:
SAT / UNSAT Revision 0 Page 4 of 6 2011 NRC Walk Through Exam
JPM P3 TASK ELEMENT 5 STANDARD 11.12.9 Start the affected EFW Pump in accordance with OP-009-003, Makes report to Control Emergency Feedwater and verify Discharge Pressure is in accordance Room with Technical Specification 4.7.1.2.b.1 or 4.7.1.2.b.2.
Comment:
SAT / UNSAT TASK ELEMENT 6 STANDARD 11.12.10 If the pressure in step 11.12.9 is not satisfactory, then perform Calls Control Room the following:
Comment:
Cue Applicant that the discharge pressure for Emergency Feedwater Pump A is satisfactory. SAT / UNSAT TASK ELEMENT 7 STANDARD 11.12.11.1 Open and Lock the affected EFW Pump Discharge Isolation:
EFW-211A, EFW Pump A Discharge Isolation Comment: Critical SAT / UNSAT TASK ELEMENT 8 STANDARD 11.12.11.2 Stop the affected EFW Pump in accordance with OP-009-Calls Control Room 003, Emergency Feedwater.
Comment:
End JPM when the Control Room is contacted.
SAT / UNSAT END OF TASK Revision 0 Page 5 of 6 2011 NRC Walk Through Exam
JPM P3 APPLICANT CUE SHEET Do Not Manipulate Any Plant Components (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Emergency Feedwater Pump A discharge temperature is 145 °F.
- The control switch for EFW Pump A is in OFF.
INITIATING CUES:
- The CRS directs you to perform the steam binding actions for Emergency Feedwater Pump A in accordance with OP-903-001, Technical Specification Surveillance Logs, Attachment 11.12, EFW Steam Binding Corrective Actions.
Revision 0 Page 6 of 6 2011 NRC Walk Through Exam
11.12 EFW STEAM BINDING CORRECTIVE ACTIONS 11.12.1 SM/CRS Permission to perform: fl ,,3inL Signat re D tefrime rify compliance with Technical Specification 3.7.1.2.
Indicate which EFW Pump corrective action is to be performed on:
EFWPumpA V EFW Pump B EFW Pump AB the affected EFW Pump will not start by performing the following:
(11 the affected EFW Pump is EFW Pump A or B, then place EFW Pump A or B Control Switch to Off.
the affected EFW Pump is EFW Pump AB, then Close EFW Pump AB Stop Valve, MS-416.
11.12.5 Unlock and Close the affected EFW Pump Discharge Isolation:
- EFW-21 1A EFW Pump A Discharge Isolation
- EFW-21 1 B EFW Pump B Discharge Isolation
- EFW-208A EFW Pump A Discharge Drain
- EFW-208B EFW Pump B Discharge Drain
Performed Verified (Initial) (Initial) 11.12.7 When a solid stream of cool water issues from the affected EFW Pump Discharge DrainNent, then Close the affected EFW Pump Discharge DrainNent:
- EFW-208A EFW Pump A Discharge Drain
- EFW-208B EFW Pump B Discharge Drain
Performed Verified (Initial) (Initial) 11.12.8 If the affected EFW Pump is EFW Pump AB, then Open EFW Pump AB Stop Valve, MS-416.
11.12.9 Start the affected EFW Pump in accordance with OP-009-003, Emergency Feedwater and verity Discharge Pressure is in accordance with Technical Specification 4.7.1.2.b.1 94.7.1.2.b.2.
Discharge Pressure: PSIG 11.12.10 Ifthe pressure in step 11.12.9 is not satisfactory, then perform the following:
11.12.10.1 Stop the affected EFW Pump in accordance with OP-009-003, Emergency Feedwater.
11.12.10.2 Repeat steps 11.12.4 through 11.12.9.
11.12.11 Ifthe pressureinstep 11.12.9 is satisfactory, then perform the following:
11.12.11.1 Open and Lockthe affected EFW Pump Discharge Isolation:
EFW-21 1A, EFW Pump A Discharge Isolation EFW-21 1 B, EFW Pump B Discharge Isolation EFW-21 lAB, EFW Pump AB Discharge Isolation 11.12.11.2 Stop the affected EFW Pump in accordance with OP-009-003, Emergency Feedwater.
11.12.11.3 If the affected EFWPumpisEFWPumpA or B, then verity the Control Switch is returned to Neutral. (May be N/A)
OP-903-001 Revision 043 Attachment 11.12(2 of 3) 121
11.12.12 Initiate a WR to correct the check valve back leakage record WR Number.
WR Number:
Performed by:
(Signature) (Date/Time)
Verified by:
(Signature) ( Date/Ti me)
SM/CRS Review: I (Signature) (Date/Ti me)
OP-903-OO1 Revision 043 Attachment 11 12 (3 of 3) 122
11.12 EFW STEAM BINDING CORRECTIVE ACTIONS 11.12.1 SM/CRS Permission to perform: ________________________________
Signature Date/Time 11.12.2 Verify compliance with Technical Specification 3.7.1.2.
11.12.3 Indicate which EFW Pump corrective action is to be performed on:
EFW Pump A __________
EFW Pump B __________
11.12.4 Verify the affected EFW Pump will not start by performing the following:
11.12.4.1 If the affected EFW Pump is EFW Pump A or B, then place EFW Pump A or B Control Switch to Off.
11.12.4.2 If the affected EFW Pump is EFW Pump AB, then Close EFW Pump AB Stop Valve, MS-416.
11.12.5 Unlock and Close the affected EFW Pump Discharge Isolation:
EFW-211A EFW Pump A Discharge Isolation EFW-211B EFW Pump B Discharge Isolation EFW-211AB EFW Pump AB Discharge Isolation 11.12.6 Open the affected EFW Pump Discharge Drain/Vent:
EFW-208A EFW Pump A Discharge Drain EFW-208B EFW Pump B Discharge Drain EFW-209 EFW Pump AB Discharge Line Vent.
Performed Verified (Initial) (Initial) 11.12.7 When a solid stream of cool water issues from the affected EFW Pump Discharge Drain/Vent, then Close the affected EFW Pump Discharge Drain/Vent: _________ _________
EFW-208A EFW Pump A Discharge Drain EFW-208B EFW Pump B Discharge Drain EFW-209 EFW Pump AB Discharge Line Vent OP-903-001 Revision 043 Attachment 11.12 (1 of 3) 120
Performed Verified (Initial) (Initial) 11.12.8 If the affected EFW Pump is EFW Pump AB, then Open EFW Pump AB Stop Valve, MS-416. _________ _________
11.12.9 Start the affected EFW Pump in accordance with OP-009-003, Emergency Feedwater and verify Discharge Pressure is in accordance with Technical Specification 4.7.1.2.b.1 or 4.7.1.2.b.2.
Discharge Pressure: _______________ PSIG _________
11.12.10 If the pressure in step 11.12.9 is not satisfactory, then perform the following:
11.12.10.1 Stop the affected EFW Pump in accordance with OP-009-003, Emergency Feedwater.
11.12.10.2 Repeat steps 11.12.4 through 11.12.9.
11.12.11 If the pressure in step 11.12.9 is satisfactory, then perform the following:
11.12.11.1 Open and Lock the affected EFW Pump Discharge Isolation:
EFW-211A, EFW Pump A Discharge Isolation _________ _________
EFW-211B, EFW Pump B Discharge Isolation _________ _________
EFW-211AB, EFW Pump AB Discharge Isolation _________ _________
11.12.11.2 Stop the affected EFW Pump in accordance with OP-009-003, Emergency Feedwater.
11.12.11.3 If the affected EFW Pump is EFW Pump A or B, then verify the Control Switch is returned to Neutral. (May be N/A) _________ _________
OP-903-001 Revision 043 Attachment 11.12 (2 of 3) 121
11.12.12 Initiate a WR to correct the check valve back leakage and record WR Number.
WR Number: ____________________
Performed by:
(Signature) (Date/Time)
Verified by:
(Signature) (Date/Time)
SM/CRS Review: /
(Signature) (Date/Time)
OP-903-001 Revision 043 Attachment 11.12 (3 of 3) 122