ML110140191
| ML110140191 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/19/2010 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-390/10-301 | |
| Download: ML110140191 (58) | |
Text
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO&SRO 201 0-08 NRC Exam A.1-1 RO&SRO Calculation of values required to raise RWST level.
PA(P I OF II
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO&SRO 201 0-08 NRC Exam EVALUATION SHEET Task:
Calculation of values required to raise RWST level.
Alternate Path:
None Facility JPM #:
Modified Safety Function:
n/a
Title:
Conduct of Operations KIA 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Rating(s):
4.3/4.4 CFR:
41.10/43.5/45.2/45.6 Evaluation Method:
Simulator In-Plant Classroom X
References:
S0I-62.02, Boron Concentration Control, Rev. 50 Task Number:
RO-062-SOl-62-018
Title:
Makeup to the RWST using the blender.
Task Standard:
The applicant performs SOl-62.02, Boron Concentration Control, Appendix B, Blending Greater Than 2500 ppm, and calculates:
1.) The amount of primary water to be entered into the PW integrator to be 1637 +/- 5 gallons.
2.) The amount of boric acid solution to be entered into the BA integrator to be 1363 +/- 5 gallons.
Validation Time:
10 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMMENTS DA(21
)Iz.14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC Exam ToolslEguipmentlProcedures Needed:
The latest revision of SOl-62.02, Boron Concentration ControL Calculator NOTE:
This JPM is designed to be performed in a classroom with procedures available to the applicant.
PAGE 3 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 201 0-08 NRC Exam READ TO APPLICANT 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
1.
RWST level has been reported to be at 371,000 gallons.
- 3. A problem in the makeup control circuit is currently limiting the maximum boric acid flow rate to 30 gpm.
- 4. You are an extra operator assigned to the shift.
INITIATING CUES:
- 1. The Unit Supervisor directs you to determine the amount of primary water and the amount of boric acid needed to raise RWST level to 374,000 gallons while maintaining the current boron concentration.
- 2. You are to notify Unit Supervisor when you have completed your determination of the amount of primary water and the amount of boric acid needed.
LDf2IZ A (
1 I
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 201 0-08 NRC Exam STEP/STANDARD SAT/UNSAT START TIME:
STEP 1: Obtain a copy of the procedure.
SAT STANDARD: A copy of S0I-62.02, Boron Concentration Control, Section UNSAT 8.1 is located by the applicant.
EXAMINERS CUE:After the applicant has demonstrated the method of obtaining the correct instruction, the examiner will provide a copy of the instruction.
NOTE Performance of this Section should be coordinated with performance of I -TRI-62-3, Boric Acid Flow Paths: Valve Position Verification.
STEP 2:
[1] REFER TO one of the following methods to determine amount SAT of Primary Water (PW) & Boric Acid (BA) needed: (NIA method NOT used)
UNSAT
[1.11 IF blending at less than 2500 ppm, THEN USE Tl-59.
[1.2] IF blending at 2500 ppm or greater, THEN USE Appendix B.
STANDARD:
Applicant determines from the INITIAL CONDITIONS that the blended solution is greater than 2500 ppm, and enters an N/A in Step 1.1.
Applicant locates Appendix B to continue the calculation.
COMMENTS:
Page 5 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO&SRO 201 0-08 NRC Exam
[
STEP/STANDARD I
SAT/UNSAT NOTE This Appendix should only be used in conjunction with Sections 6.5 or 8.1. Primary water flow must be varied to blend at concentrations greater than 2500 ppm; therefore, blending is only possible when 1-HS-62-140B, VCT MAKEUP MODE is in MANUAL.
STEP 3: From the Table on Page 2 of 2, the applicant locates the row SAT which contains the Desired Blend Concentration of 3100 ppm, and determines Primary Water flow rate to be 48 gpm.
UNSAT STANDARD:
Applicant reads the primary flow rate to be 48 gpm from the row for 3100 ppm.
COMMENTS:
Page 6 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 201 0-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: Calculates Required PW flow rate using the formula provided at SAT the bottom of Page 2 of 2 of Appendix B.
UNSAT STANDARD:
Applicant performs the calculation at the bottom of Page 2 of 2, and determines that the Required PW Flow Rate to be used with 30 gpm of Boric Acid Flow rate is 36 gpm.
For Boric Acid flow rates other than 40 gpm the following formula may be used:
Actual BA flow rate Required PW flow rate 40 PW flow rate from Table OR Actual BA flow rate X
PW flow rate from Table
=
Required PW flow rate 40 X
46
=
36gpm 40 COMMENTS:
Page 7 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO&SRO 201 0-08_NRC_Exam STEPISTAN DARD SATIUN SAT STEP 5: Calculates the amount of primary water to be entered into the PW CRITICAL integrator, by using the ratio of the primary water flow rate to the STEP total flow rate.
SAT STANDARD:
UNSAT Applicant determines the Total Flow rate to be 66 gpm by adding the primary water and boric acid flow rates together.
Applicant determines the total amount of primary water to be added by first calculating the percentage of flow due to primary water by dividing the primary water flow by the total flow, then multiplying the 3000 gallon change by that percentage. This results in 1637 gallons of primary water to be placed in the PW integrator.
Acceptable value: 1637 +/- 5 gallons.
Total Flow Rate
=
36 gprn
+
30 gprri
=
66 gprn 36 gpni
=
68 gpm 4154545 X 3000=1637ga. PW Could also perform calculation:
3000 gal.166 gpm = 45.45 minutes 36 gpm x 45.45 mm.
1636 gal. of PW Step is critical since the proper adjustment in primary flow rate is required to ensure proper blended solution is delivered to the RWST.
COMMENTS:
Page 8 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO&SRO 201 0-08_NRC_Exam STEP/STANDARD SAT/UNSAT STEP 6: Calculates the amount of boric acid to be entered into the BA CRITICAL integrator, by using the ratio of the boric acid rate to the total flow STEP rate.
SAT STANDARD:
UNSAT Applicant determines the total amount of boric acid to be added by first calculating the percentage of flow due to boric acid by dividing the boric acid flow by the total flow, then multiplying the 3000 gallon change by that percentage. This results in 1363 gallons of boric acid to be placed in the BA integrator.
Acceptable values: 1363 +/- 5 gallons.
Total Flow Rate
=
36 gpm
+
30 gprn
=
6 gprn 30 gpr
=
045455 6 gprn 0.4545 X 3000 = 1:363 gal. BA Could also perform calculation:
3000 gal.166 gpm 45.45 minutes 30 gpm x 45.45 mm. = 1364 gal. of PW Step is critical since the proper adjustment in boric acid flow rate is required to ensure proper blended solution is delivered to the RWST.
COMMENTS:
Page 9 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.l-l RO&SRO 2010-08 NRC Exam STEP/STANDARD SATIUNSAT STEP 10:
Notify the Unit Supervisor that the primary water flow rate, SAT amount of boric acid and primary water have been determined.
UNSAT STANDARD:
Applicant informs the Unit Supervisor of the results of the calculations.
COMMENTS:
END OF TASK STOP TIME Page 10 of 11
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. RWST level has been reported to be at 371,000 gallons.
2.
RWST boron concentration is currently 3100 ppm.
- 3. A problem in the makeup control circuit is currently limiting the maximum boric acid flow rate to 30 gpm.
- 4. You are an extra operator assigned to the shift.
INITIATING CUES:
I. The Unit Supervisor directs you to determine the amount of primary water and the amount of boric acid needed to raise RWST level to 374,000 gallons while maintaining the current boron concentration.
- 2. You are to notify Unit Supervisor when you have completed your determination.
A.1-1 RO&SRO
WBN Boron Concentration Control SOl-6202 Unit I Rev. 0050 Page49ofG2 Appendix B (Pagelof2)
Blending Greater Than 2500 ppm NOTE This Appendix should only be used in conjunction with Sections 6.5 or 8.1. Primary water flow must be varied to blend at concentrations greater than 2500 ppm therefore blending is only possible when 1-HS-62-140B VCT MAKEUP MODE is in MANUAL (Table is continued on next page)
Desired Blend Boric Acid flow rate I-FC-62-139 BA to Primary Concentration gpm*
Blender [I-M-6] %
Water Flow ppm rate gpm 2500 40 100 69 2550 40 100 67 2600 40 100 65 2650 40 100 63 2700 40 100 61 2750 40 100 59 2800 40 100 57 For Boric Acid flow rates other than 40 gpm the following formula may be used:
Actual BA flow rate
=
Required PW flow rate 40 PW flow rate from Table OR Actual BA flow rate X
PW flow rate from Table
=
Required PW flow rate 40
WBN Boron Concentration Control SOl-62.02 Unit I Rev. 0050 Page 50 of 62 Appendix B (Page 2 of 2)
(Table is continued from previous page)
Desired Blend Boric Acid flow rate I-FC-62-139 BA to Primary Concentration gpm*
Blender [I-M-6] %
Water Flow ppm.
rate gpm 2850 40 100 56 2900 40 100 54 2950 40 100 52 3000 40 100 51 3050 40 100 49 E
3100 40 100 48 3150 40 100 47 3200 40 100 45 3300 40 100 43 For Boric Acid flow rates other than 40 gpm the following formula may be used Actual BA flow rate
=
Required PW flow rate 40 PW flow rate from Table OR Actual BA flow rate X
PW flow rate from Table
=
Required PW flow rate 40 Required PW flow rate = (30 / 40) X 48 = 36 gpm Total flow rate 30 gpm ÷ 36 gpm 66 gpm Primary Water integrator setting
= (36 gpm I 66 gpm) = 0.54545
= 0.54545 x 3000 gallons = 1637 gallons of primary water Acceptable value: 1637 +1-5 gallons.
Boric Acid integrator setting
= (30 gpm / 66 gpm) 0.45455
= 0.45455 x 3000 gallons = 1364 gallons of boric acid solution Acceptable value: 1364 +1-5 gallons.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO/SRO 201 0-08 NRC Exam A.1-2 RO/SRO Determine RCP Start Requirements
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 ROISRO 2010-08 NRC Exam Task:
Alternate Path:
n/a Facility JPM #:
New Safety Function:
n/a K/A Rating(s):
Evaluation Method:
Simulator In-Plant SOl-68.02, Reactor Coolant Pumps, Rev. 33.
Title:
Start a Reactor Coolant Pump.
The applicant determines that RCP #2 should be started first, and the earliest time to start the pump is 1742.
10 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMMENTS
Title:
EVALUATION SHEET Determine RCP Start Requirements.
Conduct of Operations.
Ability to explain and apply system limits and precautions.
CFR:
41.10/43.2/45.12 2.1.32 2.7/3.5
References:
Task Number:
RO-068-SOl-68-007 Task Standard:
Classroom IIi,I,tiri 1 Time:
x
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 ROISRO 2010-08 NRC Exam DIRECTIONS TO APPLICANT 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
Reactor Coolant System sweeps and vents is in progress per GO-b, Reactor Coolant System Drain and Fill Operations, Section 5.4.2, RCP Sweeps and Vents.
The following is the run history for RCP #1 and RCP #2:
Pump Start Time Shutdown Time Run Time 1
1456 1456 30 seconds 1535 1536 1 minute 1650 1659 9 minutes 2
1502 1502 30 seconds 1602 1603 1 minute 1704 1712 8 minutes Current time is 1725.
INITIATING CUE:
You have been assigned to determine which of these pumps can be started first, and the earliest time that the selected pump may be started.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO-SRO 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT START TIME:
STEP 1:
Applicant determines the number of starts for each of the CRITICAL RCPs in the previous two hours.
STEP STANDARD:
SAT The applicant determines that RCP #1 has been started 3 times in the UNSAT previous two hours, and RCP #2 has been started two times in the past two hours.
Step is critical to evaluate the starting duty limits for the RCPs.
COMMENTS:
PAGE 4 OF 7
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO-SRO 201 0-08 NRC Exam STEP/STANDARD I
SAT/UNSAT STEP 2:
Applicant determines how much idle time is required prior to CRITICAL each pumps restart.
STEP STANDARD:
SAT From SOI-68.02, Reactor Coolant Pumps, PRECAUTIONS AND UNSAT LIMITATIONS:
E. RCP Maximum Starting Duty limits:
- 1. For Restart after any period running or attempted start where motor failed to achieve full speed before it is stopped: Motor must be idle at least 30 mm before restart.
- 2. Consecutive Starts: In any 2 hr period: Maximum of 3 starts with minimum 30 mm idle period before each restart. When 3 starts (or attempted starts) are made in 2 hrs, then a fourth start should NOT be made until motor is idle at least 1 hr.
The applicant determines that RCP #1 must be idle for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and that RCP #2 must be idle for 30 minutes.
Step is critical to determine the required idle period for each RCP.
COMMENTS:
PAGE 5 OF 7
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO-SRO 201 0-08 NRC Exam STEP/STANDARD I
SAT/UNSAT STEP 3:
Applicant calculates the earliest start time for each pump.
CRITICAL STEP STANDARD:
SAT Applicant determines the earliest start time for RCP #1 is 1659 plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or 1759.
UNSAT Applicant determines the earliest start time for RCP #2 is 1712 plus 30 minutes, or 1742.
Step is critical to ensure the correct RCP is started without violating starting duty limits.
COMMENTS:
END OF TASK STOP TIME PAGE 6 OF 7
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Reactor Coolant System sweeps and vents is in progress per GO-b, Reactor Coolant System Drain and Fill Operations, Section 5.4.2, RCP Sweeps and Vents.
The following is the run history for RCP #1 and RCP #2:
Pump Start Time Shutdown Time Run Time 1
1456 1456 30 seconds 1535 1536 1 minute 1650 1659 9 minutes 2
1502 1502 30 seconds 1602 1603 1 minute 1704 1712 8 minutes Current time is 1725.
INITIATING CUE:
You have been assigned to determine which of these pumps can be started first, and the earliest time that the selected pump may be started.
A.1-2 RO-SRO
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 201 0-08 NRC Exam A.2 RO Review 1-Sl-O-4, Monthly Surveillances.
PAGE 1 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 201 0-08 NRC Exam EVALUATION SHEET Task:
Review 1-Sl-0-4, Monthly Surveillances.
Alternate Path:
N/A Facility JPM #:
Modified Safety Function:
Title:
K/A 2.2.12 Knowledge of surveillance procedures.
Rating(s):
3.7/4.1 CFR:
45.10/45.13 Evaluation Method:
Simulator In-Plant Classroom X
References:
1-Sl-0-4, Monthly Surveillances, Rev. 24.
Task Number:
RO-1 1 3-GEN-004
Title:
Perform surveillance tests.
Task Standard:
The applicant reviews a completed 0-Sl-4, Monthly Surveillance, and determines that the following 5 items require the indicated actions:
1.
AFW PMP B-B SG4 LEVEL instrument loop is reading outside the channel check MCD value, requiring the SM/Unit SRO to be notified and a Work Order (or Service Request to be initiated.
2.
1-PI-68-336C PZR PRESS is exceeding its MCD value, requiring the requiring the SM/Unit SRO to be notified and a Work Order (or Service Request to be initiated.
3.
1-Pl-68-70 LOOP 4 HL PRESS is exceeding its MCD value, requiring the requiring the SM/Unit SRO to be notified and a Work Order (or Service Request to be initiated.
Also requires MIG notification to perform 1-S1 88.
4.
1-Fl-62-93C CHARGING FLOW is within its MCD value, but exceeding the 20 gpm limit of NOTE (32) requiring the requiring the SM/Unit SRO to be notified and a Work Order (or Service Request to be initiated.
Also requires calibration of the flow instrumentation.
5.
1-PI-62-81C LP LETDOWN PRESS is exceeding its MCD value, requiring the requiring the SM/Unit SRO to be notified and a Work Order (or Service Request to be initiated.
Validation Time:
10 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMMENTS PAGE 2 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 201 0-08 NRC Exam DIRECTIONS TO APPLICANT 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. The Unit is in Mode 1, with no LCO entries at this time.
- 2. You are the Unit Operator responsible for the review of a partial performance of 1-SI-0-4, Monthly Surveillances, Appendix 0, Remote Shutdown and PAM Channel Check Data Sheet, pages 42 through 44, 47 and 54.
INITIATING CUES:
You are to review the data entered on pages provided to you from Appendix D, list the actions required to be taken to address any deviations found, and notify the Unit Supervisor that you have completed your task.
PAGE 3 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2010-08 NRC Exam STEP/STANDARD I
SAT/UNSAT START TIME:
EXAMINERS CUE: 1-Sl-0-4, Appendix D, pages 42 through 44, 47 and 54 are attached as the key to this JPM. Values which fall outside the MCD are circled on the key, and actions to be taken for each item are listed STEP 1:
Item 3 (Page 44) values for AFW PMP B-B SG 4 LEVEL.
CRITICAL STEP STANDARD:
SAT Applicant evaluates data provided and determines that the readings in the Main Control Room (1-M-3) and the Auxiliary Control Room (1-L-1O) for 1-UNSAT Ll-3-1 71 and I -Ll-3-1 71 C are outside the channel check MCD of 6%.
The applicant indicates that the following actions are required (in no particular order):
I.
SM/Unit SRO must be notified.
2.
A Work Order (WO) must be prepared for SG 4 LEVEL loop.
COMMENTS:
PAGE4OF9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2.
Item 7 (Page 47) value for 1-PI-68-336C PZR PRESS.
CRITICAL STEP STANDARD:
SAT Applicant evaluates data provided and determines that the reading for 1-PI-68-336C in the Auxiliary Control Room (1-L-10) is outside the channel UNSAT check MCD of 50 psig.
The applicant indicates that the following actions are required (in no particular order):
- 1. SM/Unit SRO must be notified of 1-Pl-68-336C exceeding its MCD limit.
2.
A Work Order (WO) or Service Request (SR) must be prepared for 1-Pl-68-336C.
COMMENTS:
PAGE 5 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 201 0-08 NRC Exam STEPISTANDARD SATIUNSAT STEP 3.
Item 7 (Page 47) values for 1-PI-68-70 LOOP 4 HL PRESS.
CRITICAL STEP STANDARD:
SAT Applicant evaluates data provided and determines that the reading for 1-PI-68-70 in the Main Control Room (1-L-10) is outside the channel check MCD UNSAT of 50 psig.
The applicant indicates that the following actions are required (in no particular order):
3.
SM/Unit SRO must be notified of 1-Pl-68-70 exceeding its MCD limits.
4.
A Work Order (WO) or Service Request (SR) must be prepared for 1-PI-68-70 LOOP 4 HL PRESS.
- 5. Per Note (10), MIG must be notified to perform 1-S1-68-88 since 1-Pl-68-70 is out-of-tolerance.
COMMENTS:
PAGE 6 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 201 0-08 NRC Exam STEP/STANDARD
[
SAT/UNSAT STEP 4:
Item 25 (Page 54) value for 1-Fl-62-93A CHARGING FLOW.
CRITICAL STEP STANDARD:
SAT Applicant evaluates data provided and determines that the reading for 1-Fl-62-93C in the Auxiliary Control Room (1-L-10) is within the channel check UNSAT MCD of 40 psig, but exceeds the 20 gpm value given in NOTE (32).
The applicant indicates that the following actions are required (in no particular order):
1.
SM/Unit SRO must be notified.
- 2. The Work Order (WO) or Service Request (SR) number must be included in REMARKS.
Per Note (32) If channel deviation is greater than 20 gpm, action shall be initiated to calibrate the flow instrumentation W.O. number shall be recorded in REMARKS.
COMMENTS:
PAGE 7 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 201 0-08 NRC Exam STEPISTANDARD SAT/UNSAT STEP 5:
Item 29 (Page 54) value for 1-Pl-62-81C LP LETDOWN CRITICAL PRESS.
STEP STANDARD:
SAT Applicant evaluates data provided and determines that the reading for 1-PI-UNSAT 62-81C in the Auxiliary Control Room (1-L-10) exceeds the 30 gpm MCD vs Iue.
The applicant indicates that the following actions are required (in no particular order):
1.
SM/Unit SRO must be notified.
2.
A Work Order (WO) or Service Request (SR) must be prepared for 1-PI-62-81 C.
COMMENTS:
STOP TIME PAGE 8 OF 9
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. The Unit is in Mode 1, with no LCO entries at this time.
- 2. You are the Unit Operator responsible for the review of a partial performance of 1-SI-O-4, Monthly Surveillances, Appendix D, Remote Shutdown and PAM Channel Check Data Sheet, pages 42 through 44, 47 and 54.
INITIATING CUES:
You are to review the data entered on pages provided to you from Appendix D, list the actions required to be taken to address any deviations found, and notify the Unit Supervisor that you have completed your task.
A.2 RO
WBN Monthly Surveillances 1-Sl-0-4 Unit I Rev. 0024 Page 42 of 74 Appendix D (Page 1 of 15)
Remote Shutdown and PAM Channel Check Data Sheet Data Package: Page of Date TODAY Mode 1.0 REMOTE SHUTDOWN AND PAM CHANNEL CHECKLIST ITEM REFERENCE REQUIRED NOTES DESCRIPTION LOC INST NO READING LOC INST NO READING DATA MCD NO.
NUMBER MODE UNITS SR 3.3.3.1-22 1, 2, 3 (1)
AFWTO SG 1 FLOW 1-M-3 1-Fl-3-163A 0
1-L-10 1-FI-3-163C 0
gpm 60 gpm SR p3.3.4.1-4.d AFWTO SG 2 FLOW 1-M-3 1-FI-3-1558 0
1-FI-3-155C 0
AFWTO SG 3 FLOW 1-M-3 1-FI-3-147A 0
1-FI-3-147C 0
AFWTO SG 4 FLOW 1-M-3 1-FI-3-170B 0
1-FI-3-170C 0
AFWTO SG 1 FLOW 1-M-3 1-FI-3-163B 0
N/A N/A AFWTO S02 FLOW 1-M-3 1-F[-3-155A 0
N/A N/A AFWTO SG 3 FLOW 1-M-3 1-FI-3-147B 10 N/A N/A AFWTOSG4FLOW 1-M-3 1-FI-3-170A 0
N/A N/A AFW PUMP A DIFF 1-PDIC-3-122A 1200 1-PDIC-3-122C 1200 psid 99 psid 1 -M-4 PRESSURE AFW PUMP B DIFF 1-PDIC-3-132A 1-M-4 1200 1-PDIC-3-132C 1200 PRESSURE Operators Initials DAH Operators Initials DAH (1)
The following pairs of indicators are to be channel checked against each other to satisfy the surveillance requirement: 1-FI-3-163A and -163C; 1-FI-3-155B and -155C; 1-FI-3-147A and -147C; 1-FI-3-170B and -170C; 1-PDIC-3-122A and -122C; 1-PDIC-3-132A and -132C. All AFW flow indicators on 1-M-3 are to be channel checked against each other.
/
/
/
Remarks:
WBN Monthly Surveillances 1-SI-0-4 Unit I Rev. 0024 Page 43 of 74 Appendix D (Page 2 of 15)
Remote Shutdown and PAM Channel Check Data Sheet Data Package: Page 2
of Date TODAY 1.0 REMOTE SHUTDOWN AND PAM CHANNEL CHECKLIST (continued)
Mode 1
ITEM REFERENCE REQUIRED NOTES DESCRIPTION LOC INST NO READING LOC INST NO READING DATA MCD NO.
NUMBER MODE UNITS 2
SR 3.3.3.1-17 1, 2, 3 N/A ERCWTO AFWP A-A CLOSED 21 N/A N/A 1-FCV-3-116A N/A N/A SUCT FRM HDR A 1 M 3 OPEN U N/A
- FCV-3-116A & B CLOSED 1-FCV-3-116B N/A N/A OPEN U
ERCW TO AFWP B-B CLOSED 1-FCV-3-126A N/A N/A SUCT FRM HDR B 1 M 3 OPEN U
N/A
-FCV-3-126A&B CLOSED 1-FCV-3-126B N/A N/A OPEN U
ERCW TO T-D AFWP CLOSED I 1-FCV-3-136A N/A N/A SUCTFRMHDRA-1M3 OPEN U
N/A FCV-3-136A&B CLOSED 1-FCV-3-136B N/A N/A OPEN U
ERCW TO T-D AFWP CLOSED J 1-FCV-3-179A N/A N/A SUCT FRM HDR B 1 M 3 OPEN U
N/A
- FCV-3-179A & B CLOSED 1-FCV-3-179B N/A N/A OPEN U
Operators Initials DAH Operators Initials N/A Remarks:
[,
WBN Monthly Surveillances 1-Sl-0-4
(
Unit I Rev. 0024 L
Page44of74 Appendix D (Page 3 of 15)
Remote Shutdown and PAM Channel Check Data Sheet T-D AFW PMP 1-M-3 1-LI-3-173 60 SG_2_LEVEL T-D AFW PMP 1-M-3 1-Ll-3-172 58 SG_3_LEVEL (2)
The indicators on 1-M-3 and 1-L-10 listed for AFW PMP A-A and B-B are in the same loop and are NOT to be channel checked against each other to satisfy the surveillance requirement, but should be reading within the channel check MCD value.
ITEM NO.
3 TODAY Data Package: Page of Date 1.0 REMOTE SHUTDOWN AND PAM CHANNEL CHECKLIST (continued)
Mode 3
REFERENCE REQUIRED NUMBER MODE NOTES SR 3.3.3.1-16 SR 3.3.4.1-4.
d 1,2,3 DESCRIPTION LOC Per 6.1. G.
SM/Unit SRO is to be notified that the loop is reading outside the channel check MCD value.
A Work Order (WO) is to be initiated to have the suspect loops calibrated.
T-D AFW PMP SG 1 LEVEL INST NO 1-M-3 READING LOC 1-LI-3-1 74 IINI PIU 57 T-D AFW PMP SG 4 LEVEL 7I_1 LJIIflJ (2)
N/A LJk I M UNITS 1-M-3 AFW PMP A-A SG I LEVEL ivic.u N/A N/A 1-LI-3-1 75 1-M-3 6.0%
60 N/A /
N/A N/A/
N/A 1 -LI-3-1 64 60 N
1 -L-1 0 AFW PMP B-B SG 4 LEVEL N/A 1 -L,/-1 64C AFW PMP A-A 1-M-3 1-LI-3-156 58 1-L-10 1/I3156C 61 SG_2_LEVEL AFW PMP B-B 1-M-3 1-LI-3-148 59 1-L-10
/-LI_3-148C 59 SG_3_LEVEL 1-M-3 60 1 -LI-3-1 71 Operators Initials
-.-------.-- _iZE° 1 -LI-3-171C DAH Operators Initials DAH Remarks:
WBN Monthly Surveillances 1-Sl-0-4 Unit I Rev. 0024 Page47of74 Otors Initials (8)
Remote Shutdown requires PZR PRESS or RCS WR RANGE PRESS, but both are NOT required to satisfy SR4.1-2.a.
(9)
PZR COLD CAL PRESS is to be considered the same as RCS WR RANGE PRESS.
(10)
If 1-PI-68-70 is out-of-tolerance, MIG is to be notified to perform i-SI-68-88.
DAH Appendix D (Page 6 of 15)
Remote Shutdown and PAM Channel Check Data Sheet Data Package: Page of Date TODAY 1.0 REMOTE SHUTDOWN AND PAM CHANNEL CHECKLIST (continued)
Mode 1
Exceeds MCD Limit.
SM/Unit SRO is to be notified that an MCD value has been exceeded.
A Work Order (WO) is to be initiated to have the suspect indicator(s (loops(s)) calibrated.
/
ITEM REFERENCE REQUIRED NOTES DESCRIPTION LOC INST NO READING LOC INST NO READING DATA / MCD NO.
NUMBER MODE UNIT 6
SR 3.3.3.1-14 1, 2, 3 N/A 1-Ll-68-339A 60 1-Ll-68-325C 58 PZR LEVEL 1-M4 1-Ll-68-335A 59 1-L-10 1-Ll-68-326C 60 6.0%
SR 3.3.4.1-3.a I -Ll-68-320 N/A N/A /
7 SR 3.3.3.1-5 1, 2, 3 (8) 1-Pl-68-340A 1-Pl-68-336C SR 3.3.4.1-2.a 1-Pl-68-334 2240 PZRPRESS 1-M-5 1-L-10 psig 5opsig 1-Pl-68-323 2225 1-Pl-68-337C 2235 1-Pl-68-322 2240 (9)
PZR-COLD CAL 1-M-5 1-Pl-68-342A 2250 1-L-10 1-Pl-68-342C 2250 PRESS psig 200 psig (10)
LOOP 4 HL PRESS 1-Pl-68-70 N/A N/A LOOP 3 HL PRESS 1-M-6 1-Pl-68-64 2250 N/A N/A N/A LOOP 1 HL PRESS 1-Pl-68-63 2300 N/A N/A Ooerators Initials DAH lExceeds MCD Limit.
Requires performance of 1-Sl-68-88by MIG, per Note (10)
ISM/Unit SRO is to be notified.
/
/ork Order (WO) is to be initiated.
WBN Monthly Surveillances.
1-Sl-0-4 Unit I Rev. 0024 Page54of74 1.0 Appendix D (Page 13 of 15)
Remote Shutdown and PAM Channel Check Data Sheet Data Package: Page of Date TODAY REMOTE SHUTDOWN AND PAM CHANNEL CHECKLIST (continued)
Mode Exceeds MCD Limit.
SM/Unit SRO is to be notified.
A Work Order (WO) is to be initiated.
ITEM REFERENCE REQUIRED NOTES DESCRIPTION LOC INST NO READING LOC INST NO READING DATA MCD NO.
NUMBER MODE
UNITS!
24 SR 3.3.3.1-26 1,2, 3 N/A AB PASSIVE 1-M-15 0-LI-77-134 12.5
N/A N/A N/A
./
4.8 SUMP LEVEL 0-LI-77-135 12.5 N/A N/A in. WC 120 m
4ogpm 25 SR p3.3.4.1-3.b 1,2,3 (32)
CHARGING FLOW 1-M-5 1-FI-62-93A C
1-L-10 1-FI-62-93C 150 26 LCO 3.3.4 1,2, 3 (32)
CHARGING 1-M-5 HDR PRESS 1-Pl-62-92A /
2475 1-L-10 1-PI-62-92C 2450
/psig psig
/
27 LCO 3.3.4 1, 2,3 (32)
EMERG BORATE 1-M-5 1-Fl-62-137 7
0 1-L-10 1-FI-62-137C 0
gpm 7.5 gpm FLOW 28 SR p3.3.4.1-3.b 1,2, 3 (32)
LETDOWN HX 1-M-6 1TI627y 91 1-L-10 1-TI-62-80C 93 F
6F OUTLET TEMP 29 LCO 3.3.4 1, 2, 3 (32)
LP LETDOWN 1-M-6 1-Pl-62/1 1-L-10 1-Pl-62-81C ZQ._
psig 30 psig PRESS 30 LCO 3.3.4 1,2, 3 (32)
VCT LEVEL 1-M-6 1-Ll-6/-129A 62 1-L-10 1-Ll-62-129C 61 6%
31 LCO3.3.4 1,2,3 (32) 1AERCWSUP 0-M-27A 1 Fl 67-61 2500 1-L-10 1-FI-67-61C 2000 (33)
HDR FLOW 1/6762 1000 1-L-10 1-Fl-67-62C 1250 lB ERCW SUP 0-M-27A HDR FLOW 1000 gp 2A ERCW SUP m
0-M-27A
.1I6761 8500 2-L-10 2-FI-67-61C 8000 HDR FLOW 2B ERCW SUP OM27A/ 2-Fl-67-62 9500 2-L-10 2-FI-67-62C 9250 HDR FLOW Ooerat rs Initials DAH Onerators Initials DAH (32)
MCR indications are recorded for comparison purposes only. The following requir/ment is applicable to Item 25 (Charging Flow) ONLY:
If channel deviation is greater than 20 gpm, action shall be initiated to calibrate the flow instrumentation. WO no. shall be recorded in RMARKS.
(33)
Descriptions for the Remote Shutdown board instruments:
/
/
A. 1-TI-67-61C, SUP HDR A FLOW.
B. 1-Tl-67-62C, SUP HDR B FLOW. /
C. 2-TI-67-61C, SUP HDR A FLOW..
D. 2-TI-67-62C, SUP HDR B FLOW.
Remarks:
/
Per Note (32) If channel deviation is greater than 20 gpm, action shall be, initiated to calibrate the flow instrumentation W.O. number shall be recorded in REMARKS.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 201 0-08 NRC Exam A.2 SRO Determine a Technical Specification Completion Time Extension Page 1 of 5
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2010-08 NRC Exam Task:
Alternate Path:
Facility JPM #:
EVALUATION SHEET Determine a Technical Specification Completion Time Extension.
n/a New Safety Function:
n/a K/A 2.2.42 Rating(s):
3.1/4.6 Evaluation Method:
Simulator
Title:
Equipment Control Ability to track Technical Specification limiting conditions for operations.
CFR:
41.10/43.2/45.13 In-Plant Classroom x
References:
Watts Bar Nuclear Plant Technical Specifications, All Amendments through Amendment 81. 1.3, Completion Times. LCO 3.5.2, ECCS
- Operating.
Task Number:
SRO-1 1 9-SSP-1 2.56-005
Title:
Evaluate status changes for Tech. Spec.
equipment to determine if LCO action statement entry is required.
Task Standard:
The applicant determines the LATEST date and time that Unit must be placed in Mode 4 if the 1 B-B Safety Injection pump cannot be restored to OPERABLE STATUS to be 1900 on 7/6/201 0.
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMM ENTS IIit4tirn Time:
10 minutes Time Critical:
Yes No X
Page 2 of 5
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 201 0-08 NRC Exam DIRECTIONS TO APPLICANT 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. The unit is at 100% power.
- 2. Todays date is July 4, 2010. The time is 0700.
- 3. On July 2, 2010 at 0700, the 1 A-A Safety Injection pump was declared INOPERABLE.
4.
LCO Action Statement 3.5.2.A, One or more trains inoperable AND at least 100%
of the ECCS flow equivalent to a single OPERABLE ECCS train available, was entered at that time.
- 5. The 1 B-B Safety Injection pump was declared INOPERABLE today at 0700, and LCO 3.0.3 was entered.
- 6. At 0900 on July 4, 2010, the lA-A Safety Injection pump was declared OPERABLE.
INITIATING CUE:
You are to determine the LATEST date and time that Unit must be placed in Mode 4 if the 1 B-B Safety Injection pump cannot be restored to OPERABLE STATUS.
Page 3 of 5
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 201 0-08 NRC Exam STEP/STANDARD SAT/UNSAT START TIME:
STEP 1:
Application of Technical Specifications 1.3, Completion Times, CRITICAL to the return of the lA-A Safety Injection pump to service at STEP 0900 on July 4, 2010.
SAT Application of Technical Specifications 3.5.2.B, Required Action and Completion Time not met, and determination of UNSAT time to place the Unit in Mode 4.
STANDARD:
Applicant determines that LCO 3.0.3 can be exited at 0900 on 7/4/2010.
Applicant determines from the second INITIATING CUE that the conditions described in Tech Spec Section 1.3,Completion Times have been met.
Applicant determines that the total Completion Time is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> added to the initial entry into LCO 3.5.2 Condition A. Initial entry July 2, 2010 at 0700. Thel B-B SI pump must be restored to OPERABLE status before 0700 on 7/6/2010.
Applicant determines LCO 3.5.2 Condition B cannot be met, and that the Unit must be placed in Mode 4 within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, with the time starting at 0700 on 7/6/2010. Therefore, the Unit must be in Mode 4 by 1900 on 7/6/2010.
Step is critical to ensure equipment is returned to service within the times allowed in Technical Specifications.
COMMENTS:
END OF TASK STOP TIME
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. The unit is at 100% power.
- 2. Todays date is July 4, 2010. The time is 0700.
- 3. On July 2, 2010 at 0700, the lA-A Safety Injection pump was declared INOPERABLE.
4.
LCO Action Statement 3.5.2.A, One or more trains inoperable AND at least 100%
of the ECCS flow equivalent to a single OPERABLE ECCS train available, was entered at that time.
- 5. The 1 B-B Safety Injection pump was declared INOPERABLE today at 0700, and LCO 3.0.3 was entered.
- 6. At 0900 on July 4, 2010, the lA-A Safety Injection pump was declared OPERABLE.
INITIATING CUE:
You to determine the LATEST date and time that Unit must be placed in Mode 4 if the 1 B-B Safety Injection pump cannot be restored to OPERABLE STATUS.
A.2SRO
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 201 0-08 NRC Exam A.3R0&SRO Calculate Maximum Permissible Stay Time within Emergency Dose Limits PAGE 1 0F7
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 201 0-08 NRC Exam EVALUATION SHEET Task:
Calculate Maximum Permissible Stay Time Within Emergency Dose Limits Alternate Path:
n/a Facility JPM #:
Modified Safety Function:
n/a
Title:
Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
Rating(s):
3.2/3.7 CFR:
41.12/43.4/45.10 Evaluation Method:
Simulator In-Plant Classroom X
References:
EPIP-15, Emergency Exposure Guidelines, Rev. 13.
AUO-1 1 9-SSP-5.O1 -001
Title:
Control personnel radiation exposure.
The applicant:
1.
Calculates the total dose received performing the assigned tasks to be 23.3 Rem.
2.
Determines that personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance K/A Task Number:
Task Standard:
VIirIt.nn Time:
10 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMMENTS PAGE2OF7
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 2010-08 NRC Exam Tools/Equipment/Procedures Needed:
EPIP-15, EMERGENCY EXPOSURE GUIDELINES.
Calculator NOTE:
This JPM is designed to be performed in a classroom with procedures available to the applicant.
PAGE 3 OF 7
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 201 0-08 NRC Exam READ TO APPLICANT 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
1.
A loss of coolant accident is in progress.
2.
ECA-1.1, Loss of RHR Sump Recirculation, has been entered.
- 3. Automatic swap over to the containment sump has failed to occur.
- 4. The Auxiliary Building AUO has been dispatched to perform the following tasks:
TASK TIME DOSE RATE 1
Go to task performance area.
12 minutes 0.5 R/hr 2
Remove cover from enclosure for 1-FCV 54 minutes 9 R/hr 72, CNTMT SUMP TO RHR PMP A SUCT.
3 Manually open 1-FCV-63-72, CNTMT SUMP TO 45 minutes 20 RIhr RHR PMP A SUCT.
4 Return from task performance area.
12 minutes 0.5 R/hr
- 5. Authorization to exceed occupational dose limits to restore critical safety functions has been approved by the Shift Manager (SED) for the Auxiliary Building AUO.
INITIATING CUES:
The Auxiliary Building AUO has completed Tasks 1 and 2 in the time listed. You are to determine:
PAGE4OF7
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 201 0-08 NRC Exam STEP 1: Applicant reviews EPIP-15, Emergency Exposure Guidelines, SAT Appendix A, Watts Bar Emergency Exposure Reference, and determines that the exposure limit to be 25 Rem.
UNSAT STANDARD: A STEP 2:
Determine dose received performing Tasks lthrough 4.
CRITICAL STEP STANDARD:
SAT Applicant calculates dose to complete Task 1 as:
12 mm. /60 mm/hr x 0.5 Rem/hr = 0.1 Rem UNSAT Applicant calculates dose to complete Task 2 as:
54 mm. /60 mm/hr. x 9 Rem/hr = 8.lRem Applicant calculates dose to complete Task 3 as:
45 min./60 mm/hr. X 20 Rem/hr 15 Rem Applicant calculates dose to complete Task 4 as:
(SAME CALCULATION AND DOSE AS Task 1, or 0.1 Rem.
Total for Tasks 1, 2, 3 and 4 is 23.3 Rem Step is critical to determine the total dose for the assigned tasks, and to determine that the Emergency Dose Limit is NOT exceeded.
COMMENTS:
STEPISTANDARD START TIME:
Page 5 of 7
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 201 0-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: Determine the restrictions, if any, that are imposed on the AB CRITICAL AUO after receipt of the emergency exposure.
TASK STANDARD:
SAT From EPIP-15.
UNSAT 3.1.4 POST-EXPOSURE EVALUATIONS A. Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance.
Step is critical to determine the restrictions associated with the dose received, even though the Emergency Dose limit of 25 Rem is not exceeded.
COMMENTS:
END OF TASK STOP TIME Page 6 of 7
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. A loss of coolant accident is in progress.
2.
ECA-1.1, Loss of RHR Sump Recirculation, has been entered.
- 3. Automatic swap over to the containment sump has failed to occur.
- 4. The Auxiliary Building AUO has been dispatched to perform the following tasks:
TASK TIME DOSE RATE 1
Go to task performance area.
12 minutes 0.5 RIhr 2
Remove cover from enclosure for 1-FCV 54 minutes 9 RIhr 72, CNTMT SUMP TO RHR PMP A SUCT.
3 Manually open 1-FCV-63-72, CNTMT SUMP TO 45 minutes 20 RIhr RHRPMPASUCT.
4 Return from task performance area.
12 minutes 0.5 Rlhr
- 5. Authorization to exceed occupational dose limité to restore critical safety functions has been approved by the Shift Manager (SED) for the Auxiliary Building AUG.
INITIATING CUES:
The Auxiliary Building AUO has completed Tasks 1 and 2 in the time listed. You are to determine:
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 2010-08 NRC Exam A.4-SRO Determine if conditions warrant a Follow-up Report or Upgrade to General Emergency based on changing conditions.
Pin I nf
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 201 0-08 NRC Exam EVALUATION SHEET Task:
Determine if conditions warrant a Follow-up Report or Upgrade to General Emergency based on changing conditions.
Alternate Path:
n/a Facility JPM #:
Modified Safety Function:
n/a
Title:
K/A 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.
Rating(s):
2.7/4.5 CFR:
41.10 / 43.5 / 45.11 Evaluation Method:
Simulator In-Plant Classroom X
References:
EPIP-1 Emergency Plan Classification Flowpath, Rev. 31.
EPIP-5 GENERAL EMERGENCY, Rev. 37.
Task Number:
SRO-1 1 3-EPIP-001
Title:
Classify emergency events requiring Emergency Plan Implementation.
Task Standard:
The applicant:
1)
Determines that an upgrade from a Site Area Emergency to a General Emergency is required.
2)
Prepares forms for emergency notification as indicated on the attached key.
3)
Initiates Protective Action Recommendations, Recommendation 2.
Validation Time:
15 minutes Time Critical:
Yes X
No Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMMENTS PwiA 2 of R
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A4 SRO 201 0-08 NRC Exam THIS JPM IS PERFORMED IN A CLASSROOM SETTING.
REQUIRED MATERIALS:
EPIP-1 through EPIP-5 Tools/Equipment/Procedures Needed:
Copies of the WBN EPIPs for each applicant.
f R
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 201 0-08 NRC Exam READ TO APPLICANT 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. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
1.
Unit I was at 100% power when a loss of reactor coolant event occurred.
2.
A Site Area Emergency has been declared 30 minutes ago for Unit 1, based on a Loss or Potential Loss of any two barriers:
a.
1.1 Fuel Clad Barrier - Loss (1.1.2, Primary Coolant Activity Level, RCS sample activity is Greater Than 300 j.Ci/gm dose equivalent iodine
- 131).
- b. 1.2 RCS Barrier - Loss (1.2.2, RCS Leakage/LOCA, RCS Leak results in Loss of subcooling (<65°F indicated) [85°F ADV].
3.
EPIP-4, SITE AREA EMERGENCY, has been performed through Step 15.
- 4. The Shift Technical Advisor now reports the following conditions exist on Unit 1:
a.
RVLIS level is 30%, with no RCP5 running.
- b. RCS subcooling is 15°F.
- c. Containment Radiation monitors 1-RE-90-273 and 1-RE-90-274 both indicate 9ORIhr and are slowly trending up.
- d. Initial wind direction was from 165 and has now shifted to from 180 degrees.
- e. Wind speed has increased from 5 mph to 12 mph.
INITIATING CUES:
- 1. As the SED, you are to evaluate current plant conditions and decide the appropriate actions.
- 2. Once your decision is made, fill out the appropriate forms to make notifications to appropriate personnel.
- 3. This JPM contains time critical elements.
4 rif R
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 2010-08 NRC Exam START TIME:
STEP 1:
Refers to EPIP-1 to determine level of event.
CRITICAL STEP STANDARD:
Applicant refers to EPIP-1, Section 1, andFission Product Barrier Matrix.
SAT Applicant determines that the following conditions exist:
1.1.2 Loss, RCS sample activity is greater than 300 Ci/gm dose UNSAT equivalent 1131 1.2.2 Loss, RCS Leakage/LOCA, RCS Leak results in Loss of subcooling
(<65°F indicated) [85°F ADV].
1.3.5 Potential Loss, Significant Radioactivity in Containment, VALID Reading increase of Greater Than 108 R/hron 1-RE-90-271 and 1-RE-90-272 OR 86 Rlhron 1-RE-90-273 and 1-RE-90-274.
Based on Emergency Class Criteria, the applicant determines the need to declare a General Emergency, based on Loss of two barriers and potential loss of the third barrier.
Criteria to meet the critical step is for the EALs to be correctly identified and the declaration made within 15 minutes.
NOTE TO EXAMINER:
RECORD time that declaration was made:
COMMENTS:
Pn of R
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 201 0-08 NRC Exam STEP 2:
Implements EPIP-5, GENERAL EMERGENCY.
SAT STANDARD:
EPIP-5, GENERAL EMERGENCY, is implemented.
COMMENTS:
UNSAT The following steps are from EPIP-5 STEP 3:
[1] IF the onsite emergency centers are not staffed, THEN SAT DIRECT Shift Personnel to activate the Emergency Paging System (EPS) to staff the Technical Support Center (TSC) and Operations Support Center (OSC). Shift Personnel should confirm activation and provide the 20 minute printed UNSAT report to the SM for review.
- a. IF the EPS system fails, call the ODS, ringdown or (5-751-1 700) and DIRECT him to activate the EPS.
- b. IF the above methods of activating the EPS fail, THEN DIRECT Shift Personnel to use the Watts Bar Nuclear Plant Emergency Response Call-List to staff the TSC and OSC. (This list is located in the EPS Manual near the terminal.)
STANDARD:
Shift Personnel are directed to activate the Emergency Paging System (EPS)
CUE: When directed state Emergency paging has been activated.
COMMENTS:
PnA S of R
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 2010-08 NRC Exam STEP 4:
[2] IF the TSC has not been activated, THEN CRITICAL
- a. INITIATE Appendix A and B, Initial Notification Form for STEP GENERAL EMERGENCY and Protective Action Recommendations.
STANDARD:
Applicant completes Appendix A and Appendix B, SAT determines Recommendation 2.
NOTE TO EVALUATOR:
UNSAT Completed copies of Appendix A and B for this JPM are included and marked EXAM MATERIAL
- KEY.
COMMENTS:
End of JPM TIME STOP:
Paae 7 of 8
APPLICANT HANDOUT SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
1.
Unit I was at 100% power when a loss of reactor coolant event occurred.
- 2. A Site Area Emergency has been declared 30 minutes ago for Unit 1, based on a Loss or Potential Loss of any two barriers:
a.
1.1 Fuel Clad Barrier - Loss (1.1.2, Primary Coolant Activity Level, RCS sample activity is Greater Than 300 Ci!gm dose equivalent iodine 131).
- b. 1.2 RCS Barrier - Loss (1.2.2, RCS Leakage/LOCA, RCS Leak results in Loss of subcooling (<65°F indicated) [85°F ADV].
3.
EPIP-4, SITE AREA EMERGENCY, has been performed through Step 15.
- 4. The Shift Technical Advisor now reports the following conditions exist on Unit 1:
a.
RVLIS level is 30%, with no RCPs running.
- b. RCS subcooling is 15°F.
- c. Containment Radiation monitors 1-RE-90-273 and 1-RE-90-274 both indicate 9ORIhr and are slowly trending up.
- d. Wind direction has shifted from 165 to 180 degrees.
- e. Wind speed has increased from 5 mph to 12 mph.
INITIATING CUES:
- 1. As the SED, you are to evaluate current plant conditions and decide the appropriate actions.
- 2. Once your decision is made, fill out the appropriate forms to make notifications to appropriate personnel.
- 3. This JPM contains time critical elements.
A.4-SRO
EXAM MATERIAL KEY Revision 31 Page 9A of 47 1.1._ Fuel Clad Barrier 1.
Critical Safety Function Status I 2._ RCS Barrier Potential LOSS y.1*
Core Cooling Red Core Cooling Orange (FR-Cl)
(FR-C.2)
OR Heat Sink Red (FR-H.1)
(RHR Not in Service)
-OR-1.
Critical Safety Function Status Potential LOSS 9_c.
(
/
t Activity Level Potential LOSS RCS sample activity is Greater Than 300 pCi/gm Not applicable dose equivalent iodine-131 j
-OR 3.
Incore TCs Hi Quad Average Potential_LOSS Greater Than 1200°F Greater Than 727°F
-OR-
- 4. Reactor Vessel Water Level LOSS LOSS
--L.
Not Applicable Pressurized Thermal Shock Red (FR-P.1)
OR Heat Sink Red (FR-Hi)
(RHR Not in Service)
-OR-2.
e/LOCA Potential LOSS RCS Leak results in Non Isolatable RCS Leak Loss of subcooling xceeding The Capacity of
(<65°F Indicated),
Qn Charging Pump (CCP) theNorrnaiCharging RCS Leakage Results In Entry Into E-1
-OR-
- 3. Steam Generator Tube Rupture Potential_LOSS I l-t that results in a Not Applicable safety injection actuation OR Entry into E-3
-OR-
- 4. Reactor Vessel Water Level Potential_LOSS VALID RVLIS level Not Applicable
<33%
(No RCP Running)
-OR-
- 5. Site Emergency Director Judgment LOSS Potential LOSS Not Applicable VALID RVLIS level <33%
(No RCP running)
-OR-
- 5. Containment Radiation Monitors Potential_LOSS Not Applicable LOSS LOSS VALID readin increase 9Jearrhane 74 R/hr On 1-RE-90-271 and 272 (see instruction note 5)
-OR-
- 6. Site Emergency Director Judgment Any condition that, in the Judgment of the SM/SED, Indicates Loss or Potential Loss of the Fuel Clad Barrier Comparable to the Conditions Listed Above.
Any condition that, in the Judgment of the SM/SED, Indicates Loss or Potential Loss of the RCS Barrier Comparable to the Conditions Listed Above.
EXAM MATERIAL
- KEY I.3._ CNTMT Barrier 1.
Critical Safety Function Status LOSS Potential LOSS Containment (FR-Z.1) Red OR Actions of FR-C.1 (Red Path) are INEFFECTIVE (i.e.: core TCs trendina UD
-OR-
- 2. Containment Pressure/Hydrogen Potential LOSS Rapid unexplained decrease Containment Hydrogen following initial increase Increases to >4% by volume E
Containment pressure or Pressure >2.8 PSIG (Phase Sump level N2 increasing B) with < One full train of (with LOCA in progress)
-OR-3.
Containment Isolation Status Potential LOSS Containment Isolation is Not Applicable Incomplete (when required)
AND a Release Path to the Environment Exists
-OR-4.
Containment Potential LOSS RUPTURED S/G is also Unexplained VALID increase FAULTED outside CNTMT in area or ventilation RAD OR monitors in areas adjacent to Prolonged (>4 Hours)
CNTMT (with LOCA in Secondary Side release progress) outside CNTMT from a SIG with a SGTL > T/S Limits
-OR-5.
Significant Radioactivity in Containment Poten1al LOSS Not Applicable VAJ.iWRading increas
,eater Than:
108 R/hron 1-RE-90-271 and
/
1-RE-90-272 1\\
OR 8, R/hron 1-RE-90-273 and 14 (see instructtrtmtr
-OR-6.
Site Emergency Director Judgment Any condition that, in the Judgment of the SM/SED, Indicates Loss or Potential Loss of the CNTMT Barrier Comparable to the Conditions Listed Above.
Modes: 1,2,3,4 EPIP-1 Revision 31 Page 9B of 47 INSTRUCTIONS NOTE: A condition is considered to be MET i in the judgment of the Site Emergency Director the condition will be MET imminently (i.e., within Ito 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in the absence of a viable success path).
The classification shall be made a soon as this determination is made.
1.
In the matrix to the left, review the INITIATING CONDITIONS in all columns and identify which, if any, INITIATING CONDITIONS are MET.
Circle these CONDITIONS.
- 2. For each of the three barriers, identify if any LOSS or Potential LOSS INITIATING CONDITIONS have been MET.
3.
If a CSF is listed as an INITIATING CONDITION; the respective status tree criteria will be monitored and used to determine the EVENT classification for the Modes listed on the classification flowchart.
- 4. Compare the barrier losses and potential losses to the EVENTS below and make the appropriate declaration.
5.
Containment Radiation Monitors are temperature sensitive and can be affected by temperature induced currents. Following a rapid increase or decrease in containment temperature, testing has shown rad monitors to give unreliable indication for up to 2 minutes.
Any LOSS Potential LOSS of RCS barrier Not Applicable LOSS LOSS LOSS F
I S
S I
0 N
P R
0 D
U C
T B
A R
R I
E R
M A
T R
I x
U 1
UNUSUAL EVENT Loss or Potential LOSS of Containment Barrier EVENTS ALERT Any LOSS Potential LOSS of Fuel Clad barrier OR SITE AREA EMERGENCY LOSS or Potential LOSS of any two barriers EEMERGEY LOSS of any two barrier Potential LOSS of third r
EXAM MATERIAL
- KEY
(
WBN GENERALEMERGENCY EPIP-5 APPENDIX A (Page 1 of 1)
TVA INITIAL NOTIFCATION FORM FOR GENERAL EMERGENCY X This is a Drill LI This is an Actual Event - Repeat
- This is an Actual Event 2., jhis is Applicants Name Watts Bar has declared a GENERAL EMERGENCY affecting Unit 1
,EAL Designator(s):
1.1.2 LOR 1.1.5 L, 1.2.2 L, 1.3.5 PL (j)Brief Description of the Event:
- Loss of Coolant accident with failed fuel, and significant radiation in c.
containment. (or words to this effect) i)adioIogicaI Conditions:
(Check one under both Airborne and Liquid column.)
Airborne Releases Offsite Liquid Releases Offsite LI Minor releases within federally approved limits 1
El Minor releases within federally approved limits 1
El Releases above federally approved limits 1
LI Releases above federally approved limits 1
[.J Release information not known Release information not known
(
1 Tech Specs)
(
1 Tech Specs)
Event Declared:
Time: Applicant ENTRY Date:
Today C he Meteorological Conditions are:
(Use 46 meter data from the Met Tower)
Wind Direction is FROM:
180 degrees Wind Speed:
12 m.p.h rovide Protective Action Recommendation:
(Check eithe2 or 3, and mark wind direction.)
El Recommendation I R WIND FROM EVACUATE LISTED SECTORS E
(Mark)
E EVACUATE LISTED SECTORS (2 mile Radius and 10 miles downwind)
C C
(2 mile radius and 5 mile downwind)
=SHELTER remainder of 10 mile EPZ.
=SHELTER remainder of 10 mile EPZ.
=CONSlDER issuance of Potassium Iodide in
=CONSIDER issuance of Potassium accordance with the State Plan.
2 Iodide in accordance with the State Plan.
A-i, B-i, C-i, D-i, 26-68 A-i, B-i, C-i, D-i, C-7, -9, 0-2, -4, -5, -6, -7, -8, -9
C-7, D-2, -4, -5 Ai, Bi
, Ci, Di 69i 1 0 Ai, Bi
, Ci, D1 A-3, -4, D-2, -3, -4, -5, -6, -7, -8, -9
A-3, D-2, -4, -5 A-lB-iC-iD-i, 111-170 A-i,B-1,C-1,D-i, A-2, -3, -4, -5, -6, -7, D-2, -3, -5, -6 A-2, -3, D-2, -5 A-i, B-i, C-i, D-i, t712 B-i, A-2, -3, -5, -6, -7, B-2, -3, -4, -5, C-2
A-i, B-i, C-i, D-i, 231-270
A-i, B-i, C-i, D-i, B-2, -3, -4, -5, C-2, -3,
B-2, -4, C-2 A-i, B-i, C-i, D-i, 271-325 A-i, B-i, C-i, D-i, B-2,-3,C-2,-3,-4,-5,-6,-ii
B-2,C-2,-4,-5, A-i, B-i, C-i, D-i, 326-25
A-i, B-i, C-i, D-i, C-2, -4, -5, -6, -7, -8, -9, -10, -ii, D-4, -9
C-2, -4, -5, -7, -8, D-4 El Recommendation 3 Sj1ELTER all sectors.
=CONSlDER issuance of Potassium Iodide in accordance with the State Plan.
. iNease repeat the information you have received to ensure accuracy.
[i,1me and Date this information was provided.
Time:. Applicant ENTRY Date Today A%ion: When notification complete, FAX form as prescribed in this instruction.
N
(
PAGE i3ofi7 REVISION 37
EXAM MATERIAL
- KEY WBN GENERALEMERGENCY EPIP-5 APPENDIX B (Page 1 of 1)
PROTECTIVE ACTION RECOMMENDATIONS Note 1:
If conditions are unknown utilizing the flowchart, then answer is NO.
Note 2: A short term release is defined as a release that does not exceed a 15 minute duration.
GENERAL EMERGENCY DECLARED 1
.1 TABLE 1 Protective Action Guides (PAG)
TYPE LIMIT Measured 3.9 E-6 micro Cl/cc of Iodine 131 or 1 REM per hour External Dose Projected 1 REM TEDE or 5 REM Thyroid CDE CONTINUE ASSESSMENT Modify protective actions based on available plant and field monitoring information.
Locate and evaluate localized hot spots.
/
Istherea
/short term conti
/7 release whereas near c(
plant areas cannot be N
evacuated before /
N plume arrival? /
YES SHELTER 10 mile EPZ YES 1
RECOMMENDATION I
-j EVACUATE 2 miles radius and 10 miles downwind AND SHELTER remainder of 10 mile EPZ
çRECO EVACUATE 2 miles radius and 5 miles downwind AND SHELTER remainder of 10 mile EPZ PAGE 14 of 17 REVISION 37