ML14028A168
| ML14028A168 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 01/28/2014 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| 50-369/13-301, 50-370/13-301 | |
| Download: ML14028A168 (89) | |
Text
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Ala RO 2013 Admin JPM Ala RO (REV_111113)
- NUREG 1021, Revision 9
Appendix C Page 2 of 8 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:
Task Title: Determine Boric Acid Addition to JPM No.: 2013 Admin JPM Ala
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FWST K/A
Reference:
2.1.25 (3.9)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinQ:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-3.
Initial Conditions:
- The plant was at 100% power when a leak developed on the FWST.
- FWST Level dropped to 440 inches before leak was isolated.
- Enclosure 4.4, FWST Makeup Using the RFIT, of OP/1/A16200/014, Refueling Water System is in progress and completed through Step 3.10.
- Chemistry has provided the following information:
- BAT Boron Conc. = 7311 ppm
- RHT Boron Conc.= 826 ppm
- FWST Make up Boron Concentration: Use COLR Minimum Initiating Cue: The CRS has directed you to determine the amount of Boric Acid needed to raise the FWST level to 480 using the RHT in accordance with Step 3.11 of Enclosure 4.4 of 0P111A16200/0i 4, Refueling Water System 2013 Admin JPM Ala RO
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NUREG 1021, Revision 9
Appendix C Page 3 of 8 Form ES-C-i Job Performance Measure Worksheet Task Standard: The operator will calculate the amount of Boric Acid that must be added from the BAT to refill the FWST is between 8654 and 9247 gallons.
Required Materials: Calculator OPIi/A16100/022 (Unit 1 Data Book Cycle 23) available to Operator
MCEI-0400-261 (Unit 1 Cycle 23 Core Operating Limits Report) available to Operator General
References:
OP/i/A16200/0i4 (Refueling Water System), Rev 91 OP/i /A/6i 00/022 (Unit 1 Data Book Cycle 23), Rev 480
MCEI-0400-261 (Unit 1 Cycle 23 Core Operating Limits Report), Rev 0 McGuire Technical Specifications LCO 3.5.4, Refueling Water Storage Tank (RWST), Amendment 184/i 66 Handouts: Handout 1: Enclosure 4.4 (FWST Makeup Using RHT) of OP/i/A16200/0i4 (Refueling Water System) marked up for place keeping through Step 3.10.
Handout 2: McGuire Cycle 23 Core Operating Limits Report, Page 26.
Handout 3: OP/i/A16i00/22, Enclosure 4.3, Curve 7.7; Refueling Water Storage Tank Level (Volume vs. Tank Level).
Time Critical Task: NO Validation Time: 25 minutes 2013 Admin JPM Ala RO
- NUREG 1021, Revision 9
Appendix C Page 4 of 8 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-3.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 (Step 3.11) Determine the The operator refers to the amount of Boric Acid COLR, Section 2.13.1 on needed to raise makeup Page 26 of 32 and water to the limits specified determines that the in the Core Operating Limits minimum boron Report (COLR). concentration to be used in the calculation is 2675 ppm.
The operator records 2675 ppm in the first line (Desired Boron Concentration of Addition from COLR) of the Doer Calculation in Step 3.11 of Enclosure 4.4.
- 2 (ist Bullet) Desired Boron The operator adds an Concentration of Addition additional 25 ppm and from COLR + 25 ppmB determines Desired Boron margin = Desired Boron Concentration to be 2700 Concentration ppm.
The operator records 2700 ppm in the 2nd line (Desired Boron Conc) of the Doer Calculation in Step 3.1 1 of Enclosure 4.4.
- 3 (2 Bullet) The operator identifies Desired Cb 2700 from previous Step and records.
{(Desired Cb) (RHT Cb)}
-
(BAT Cb) (RHT Cb) The operator recognizes that RHT Cb = 826 ppm x {Desired Total and records (InWal Makeup Volume to Conditions).
FWST}
The operator recognizes
= Desired BAT Volume that BAT Cb = 7311 ppm and records (Initial Conditions).
- NUREG 1021, Revision 9
Appendix C Page 5 of 8 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 3 The operator addresses (CONTD)
OP/i /A161 00/22, Enclosure 4.3, Curve 7.7, and determines from graph that total makeup volume is 31,000+/- by comparing 480 volume of 390,000 gallons to the 440 volume of 360,000 gallons.
The operator records 31,000 (+1000/-1050) gallons.
The operator calculates the Desired BAT Volume to be added to be between 8654 and 9247 gallons.
The operator records between 8654 and 9247 gallons as the Desired BAT Volume in the Doer Calculation.
Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
- NUREG 1021, Revision 9
Appendix C Page 6 of 8 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin JPM Ala RO
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Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result: SAT UNSAT Examiners Signature: Date:
- NUREG 1021, Revision 9
Appendix C Page 7 of 8 Form ES-C-i VERIFICATION OF COMPLETION KEY:
Desired Boron Concentration from COLR + 25 ppmB = Desired Boron Concentration 2675 ppm (From COLA) + 25 ppmB = 2700 ppm
{(Desired Cb) (RHT Cb)} x {Desired Total Makeup Volume to FWST}
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= Desired BAT Volume (BAT Cb) (RHT Cb)
-
Given:
RHT Cb 826 ppm BAT Cb=7311 ppm Desired Total Makeup Volume to FWST = Overflow volume Present volume
(From Enclosure 4.3, Curve 7.7 of Unit 1 Core Data Book:)
- 390,000 gallons 360,000 gallons (440) = 30,000 gallons#
- If the operator uses develops a gallons/inch volume from the information block on Curve 7,7, the operator will determine the makeup volume to be 31,277 gallons.
If the operator uses an interpolation of the graph they could determine the level at 490 inches to be between 30,000 and 32,000 gallons.
Volume at 484 inches = 394,089 gallons Volume at 0 inches = 15,638 gallons (394089 gallons 15,638 gallons)1484 inches = 781.92 gallons/inch OR Volume at 455,88 inches = 372,100 gallons Volume at 0 inches = 15,638 gallons (372,100 gallons 15, 638 gallons)/455.88 inches = 781.92 gallonslinch Therefore, 781.92 gallons/inch x 40 inches = 31,276.80 gallons (This may be used as the makeup volume instead of 30,000 gallons).
If this volume is used, the calculation will result in a Desired BAT Volume below of 9038 gallons So:
{(Desired Cb)-(RHT Cb)} x {Desired Total Makeup Volume to FWST) = Desired BAT Volume (BAT Cb)-(RHT Cb)
{(2700)-(826fl x (30000) = Desired BAT Volume (7311 )-(826)
{j,4J x (30000) = Desired BAT Volume 6485
.28897 x {29950) = Desired BAT Volume or 8654 gallons, Where $=50 gallons is allowance
.28897 x {32000) = Desired BAT Volume or 9247 gallons between 8654 and 9247 gallons 2013 Admin JPM Ala RO
- NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET initial Conditions:
- The plant was at 100% power when a leak developed on the FWST.
- FWST Level dropped to 440 inches before leak was isolated.
- Enclosure 4.4, FWST Makeup Using the RHT, of OP/1/A/6200/014, Refueling Water System is in progress and completed through Step 3.10.
- Chemistry has provided the following information:
- BAT Boron Conc. = 7311 ppm
- RHT Boron Conc.= 826 ppm
- FWST Make up Boron Concentration: Use COLR Minimum INITIATING CUE: The CRS has directed you to determine the amount of Boric Acid needed to raise the FWST level to 480 using the RHT in accordance with Step 3.11 of Enclosure 4.4 of OP/i /A162001014, Refueling Water System.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Aib RO 2013 Admin JPM Aib PC (REVJ11113)
- NUREG 1021, Revision 9
Appendix C Page 2 of ii Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:
Task Title: Manual AFD Calculation JPM No.: 2013 Admin JPM Aib
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RO K/A
Reference:
GKIA 2.1.7 (4.4)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinQ:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handouts 1-3.
Initial Conditions: Unit 1 is at 94% power.
The OAC has been out of service for 30 minutes.
PT/1/A14600/021 A (Loss of Operator Aid Computer While in Mode 1) is being performed.
The Main Control Board AFD meters are INOPERABLE.
The following are the present current values for the Power Range upper and lower detectors:
- PR-41 A = 342 MicroAmps PR-41 B = 418 MicroAmps
- PR-42 A = 359 MicroAmps PR-42 B = 433 MicroAmps
- PR-43 A = 341 MicroAmps PR-43 B = 418 MicroAmps
- NUREG 1021, Revision 9
Appendix C Page 3 of 11 Form ES-C-i Job Performance Measure Worksheet Initiating Cue: The CRS has directed you to calculate AFD per PT111A146001021 A (Loss of Operator Aid Computer while in Mode 1), Step 12.12 for current plant conditions and verify that AFO is within the limits specified in the COLR.
Task Standard: AFD is determined to be within (+/-) 0.2% of the following values: (error band based on rounding numbers)
PR-41 = -20.38%
PR-42 = -20.99%
PR-43 = -17.86%
PR-44 = -17.48%
The operator determines the AFD associated with N41 and N42 exceeds the COLR limit of (-20.16%) at 94% RTP and informs the CRS.
Required Materials: Calculator General
References:
PT/i/A14600/021 A (Loss of Operator Aid Computer While in Mode 1),
Rev 38 OP/1/A16100/022 (Unit 1 Data Book Cycle 23), Rev 480
MCEI-0400-261 (Unit 1 Cycle 23 Core Operating Limits Report), Rev 0 McGuire Technical Specifications LCO 3.2.3, Axial Flux Difference (AFD), Amendment 261/241 Handouts: Handout 1: PT/i/A14600/021 A (Loss of Operator Aid Computer While in Model) marked up through Step 12.11.
Handout 2: OP/1/AJ6100/022, Enclosure 4.3, Table 2.2; Excore Currents and Voltages Correlated to 100% Full Power at Various Axial Offsets.
Handout 3: McGuire 1 Cycle 23 Core Operating Limits Report, Figure 5, Percent of Rated Thermal Power Versus Percent Axial Offset Difference Limits.
Time Critical Task: NO Validation Time: 25 minutes 2013 Admin JPM Ala RO
- NUREG 1021, Revision 9
Appendix C Page 4 of 1 1 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handouts 1-3.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Step 12.12) IF AFD The operator recognizes Monitor Alarm inoperable that the AFD Monitor is AND greater than or equal inoperable, and that present to 50% RTP, perform the power is greater than 50%
following: RTP.
(Step 12.12.1) IF MCB AFD gauges operable.....
The operator recognizes that the MCB AFD gauges are inoperable and places an NA in this step.
2 (Step 12.12.2) IF MCB AFD The operator refers to gauges inoperable, perform PT/1/A/4600/021 A the following: Enclosure 13.2 Part B (Step 12.12.2.1) Check AFD by performing Enclosure 13.2 (Axial Flux Difference Monitoring) Part B within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every hour thereafter until OAC AFD Monitor Alarm or MOB AFD gauges operable.
- NUREG 1021, Revision 9
Appendix C Page 5 of ii Form ES-C-i PERFORMANCE INFORMATION 3 (Notes prior to Enclosure The operator reads the 13.2 Part B) Notes and proceeds.
Manual AFD calculations using PR detector currents will provide a means to check AFD is within the limits as specified in the COLR. A difference may exist between manual AFD calculations and functioning OAC calculated values and functioning Control Board AFD gauges due to accuracy of readings and calibration of PR current meters.
IF more accurate Power Range (PR) detector current readings are desired or required, SPOC should be contacted to obtain PR detector current readings with a digital voltmeter (DVM) per Reactor Engineering procedure PTIO/A14600/002 G (Incore and NIS Recalibration) 2013 Admin JPM Ala RO
- NUREG 1021, Revision 9
Appendix C Page 6 of 1 1 Form ES-C-i PERFORMANCE INFORMATION 4 (Enclosure 13.2 Part B, The operator obtains Column A) From most OP/i/AJ6100/022, recent calibration data using Enclosure 4.3, Table 2.2 0 Incore Axial Offset and uses the Full Power current in Data Book, Table Detector Currents 2.2 (T for Detector A and (Microamps) Corresponding B for Detector B). to Various Incore Axial Offsets Chart, and an Incore Axial Offset of 0, records the following in Column A of Enclosure 13.2 Part B:
PR-41A = 119.1 PR-41B = 131.1 PR-42A = 125.7 PR-42B = 136.1 PR-43A = 121.5 PR-43B = 136.0 PR-44A = 115.8 PR-44B = 132.5 5 (Enclosure 13.2 Part B, The operator, using the Column B) From M information provided in the cabinets current meters initial conditions, records (located on respective PR A the following in Column B of and B Drawers). Ensure Enclosure 13.2 Part B:
Detector Milliamp range switches are in 0.5 PR-41A = 342 position and read from 0- PR-41B =418 500 microamp scale.
Readings should be to PR-42A = 359 nearest microamp for PR-42B = 433 accuracy.
PR-43A = 341 PR-43B = 418 PR-44A = 333 PR-44B =417 2013 Admin JPM Ala RO
- NUREG 1021, Revision 9
Appendix C Page 7 of ii Form ES-C-i PERFORMANCE INFORMATION 6 (Enclosure 13.2 Part B, The operator divides Column C) Column B Column B by Column A for Measured Current divided each detector, and by Column A Axial Offset multiplies the quotient by Current for each detector 100, and then records the multiplied by 100. following in Column C of Enclosure 13.2 Part B:
PR-41A = 287.15 PR-41 B = 318.84 PR-42A = 285.60 PR-42B = 318.15 PR-43A = 280.66 PR-43B = 307.35 PR-44A 287.56 PR-44B = 314.72 7 (Enclosure 13.2 Part B, The operator subtracts Column D) Column C Detector B from Detector A Detector A minus Column C for each PR, and divides Detector B for each PR the remainder by 2, and channel divided by 2. then records the following in Column D of Enclosure 13.2 Part B:
PR-41 =-15.85 PR-42 = -16.28 PR-43 = -13.35 PR-44 = -13.58 8 (Enclosure 13.2 Part B, The operator obtains Column E) M Factor from OP/l/A16100/022, Data Book Table 2.2 AFD Enclosure 4.3, Table 2.2 Incore/Excore Ratios for and uses the AFD Quadrants 1-4. Incore/Excore Ratios for Quadrants 1-4 Chart, and records the following in Column E of Enclosure 13.2 Part B:
PR-41 =1.286 PR-42= 1.290 PR-43 = 1.338 PR-44 = 1.287 2013 Admin JPM Al a RO
- NUREG 1021, Revision 9
Appendix C Page 8 of 1 1 Form ES-C-i PERFORMANCE INFORMATION
- 9 (Enclosure 13.2 Part B, The operator multiplies Column F) Column D Column D by Column E for multiplied by Column E will each PR and records the provide AFD value for each following in Column F of PR channel. Enclosure 13.2 Part B:
PR-41 = -20.38 PR-42 -20.99 PR-43 = -17.86 PR-44 = -17.48
- 10 Verify calculated AFD is The operator uses Figure 5 within limits specified in (Percent of Rated Thermal COLR. Power Versus Percent Axial Flux Difference Limits) of the COLR and determines that AFD limits for 94%
power are -20.16.
The operator compares the calculated AFD values to Figure 5 (Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits) of the COLR and determines that AFD for N41 and N42 exceeds the COLR limit of
(-20.16%).
11 The operator informs the CRS that N41 and N42 Cue:
exceeds the COLR limit for AFD. The CRS acknowledges.
Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
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NUREG 1021, Revision 9
Appendix C Page 9 of 11 Form ES-C1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin JPM Alb RO
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Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result: SAT UNSAT Examiners Signature: Date:
- NUREG 1021, Revision 9
Appendix C Page 10 of ii Form ES-C-i VERIFICATION OF COMPLETION KEY:
(A) (B) (C) (D) (E) (F) 0% Axial Measured (Ccl B/Cal A (Det ADet B) M Factor AFD Detectors Offset Currents x 100) 2 (COl D x Col E)
Currents PR-41A 119.1 342 287.15
-15.85 1.286 -20.38 PR-41B 131.1 H8 318.84 PR-42A PD.
1 7 39 285.60 16.28 1.290 -0.99 PR-42B 136.1 318.15 PR-43A i2i. 341 280.66
-13.35 i.38 17.36 PR-43B 136.0 418 307.35 PR-44A 115.8 333 287.6 13.58 1.287 17.8 PR-44B R2.3 417 314.72 2013 Admin - JPM Ala RO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions: Unit 1 is at 94% power.
The OAC has been out of service for 30 minutes.
PT/i/A14600/021 A (Loss of Operator Aid Computer While in Mode 1) is being performed.
The Main Control Board AFD meters are INOPERABLE.
The following are the present current values for the Power Range upper and lower detectors:
- PR-41 A = 342 MicroAmps PR-41 B = 418 MicroAmps
- PR-42 A 359 MicroAmps PR-42 B = 433 MicroAmps
- PR-43 A 341 MicroAmps PR-43 B = 418 MicroAmps
- PR-44 A = 333 MicroAmps PR-44 B = 417 MicroAmps INITIATING CUE: The CRS has directed you to calculate AFD per PT/1/A14600/021A (Loss of Operator Aid Computer while in Mode 1), Step 12.12 for current plant conditions and verify that AFD is within the limits specified in the COLR.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM A2 RO 2013 Admin JPM A2 RO (REV_111113) NUREG 1021, Revision 9
Appendix C Page 2 of 7 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:
Task Title: Partial Loss of Annunciators JPM No.: 2013 Admin JPM A2 RO K/A
Reference:
GK/A 2.2.43 (3.0)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinci:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and Handouts 1 and 2.
Initial Conditions:
- Unit 1 is operating at 100% power.
- Due to a lightning strike several of the Unit 1 Control Room Annunciators have failed.
- The crew entered PT/i /A4600/033 (Loss of Control Room Annunciators), and has completed Enclosure 13.2 (Partial Loss of Annunciator Panels) through Step 3.3.
- The failed Annunciators have been identified (Marked in YELLOW on Attached Handout).
- Another operator is reviewing the Annunciator Response Procedures for each failed annunciator.
- All other annunciators have been tested satisfactorily.
- The IAE Supervisor has been notified and is investigating.
Initiating Cue: The CRS has directed you to perform steps 3.4 through 3.11 of Enclosure 13.2 of PT/i/A4600/033 (Loss of Control Room Annunciators), and identify the affected Annunciators, if any, that have an Alternate Method for Surveillance that are applicable.
2013 Admin JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 3 of 7 Form ES-C-i Job Performance Measure Worksheet Task Standard: The operator will determine that 11% of the Annunciators have failed in accordance with the attached Key, and identify five (5) specific annunciators that have an identified Alternative Method for Surveillance.
Required Materials: None General
References:
PT/i /A/4600/033 (Loss of Control Room Annunciators), Rev 5 Handouts: Handout 1: PT/i/A4600/033 (Loss of Control Room Annunciators) marked up for place-keeping.
Handout 2: Failed Annunciators Time Critical Task: NO Validation Time: 13 minutes NOTE: An Answer KEY is provided as a separate document.
2013 Admin JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 4 of 7 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1 and 2.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 (Step 3.4) Perform The operator reviews Enclosure 13.3 (Loss of Handout 2 (Failed Annunciators Annunciators) and Determination), determines that the following Panels are affected:
1AD-7 (16) 1AD-8 (10) 1AD-9 (12) 1AD-10(3) 1AD-12 (6) 1AD-13 (15)
And completes Enclosure 13.3 in accordance with the attached Key.
- 2 (Step 3.5) Record total The operator records 1 1%
percentage of annunciators and continues.
affected.
NOTE: Critical nature of Step is that the operator determines that 1 1% of the Annunciators have been affected.
3 (Step 3.6) IF greater than The operator recognizes 50% of annunciators are that 50% of the affected annunciators are NOT affected and continues.
(Step 3.7) IF in Mode The operator recognizes 6 that the plant is NOT in Mode 6 and continues.
2013 Admin JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 5 of 7 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5 (Step 3.8) IF annunciator The operator recognizes panel 1AD-14 or 1AD-15 that panel 1AD-14 or lAD-failed to generate an 15 did NOT fail to generate audible alarm or an audible alarm or illuminate,..... illuminate.
6 (Step 3.9) Notify l&E to The operator recognizes investigate affected that the l&E Supervisor has annunciator panel(s) or been notified and is window(s), investigating; and continues.
7 (Step 3.10) Review The operator recognizes associated annunciator that another operator is response procedures for reviewing the ARP5 panel(s) or windows associated with the failed affected. Annunciators.
- 8 (Step 3.11) Perform The operator addresses Enclosure 13.4 Enclosure 13.4 and (Annunciator Panel identifies that the following Reference) to evaluate the Alarms have an identified following: Alternate Method for Su rveil lance:
. Alternate indications available for affected 1AD-7 F2 alarms 1AD-7
. lmpacttoOpsPTs (Semi Daily, Daily, etc.) 1AD8 C4 lAD-b Cl 1AD-13 Ci Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
2013 Admin JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 6 of 7 Form ES-C-i VERIFICATION OF COMPLEflON Job Performance Measure No.: 2013 Admin JPM A2 RO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result: SAT UNSAT Examiners Signature: Date:
2013 Admin JPM A2 RO NUREG 1021, Revision 9
Form ES-C-i Appendix C JPM CUE SHEET Initial Conditions:
- Unit 1 is operating at 100% power.
- Due to a lightning strike several of the Unit 1 Control Room Annunciators have failed.
- The crew entered PTI1/A46001033 (Loss of Control Room Annunciators), and has completed Enclosure 13.2 (Partial Loss of Annunciator Panels) through Step 3.3.
- The failed Annunciators have been identified (Marked in YELLOW on Attached Handout).
- Another operator is reviewing the Annunciator Response Procedures for each failed annunciator.
- All other annunciators have been tested satisfactorily.
- The IAE Supervisor has been notified and is investigating.
INITIATING CUE: The CRS has directed you to perform steps 3.4 through 3.11 of Enclosure 13.2 of PT/1/A4600/033 (Loss of Control Room Annunciators), and identify the affected Annunciators, if any, that have an Alternate Method for Surveillance that are applicable.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM A3 RO 2013 Admin JPM A3 RO (REV_111113)
- NUREG 1021, Revision 9
Appendix C Page 2 of 9 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:
Task Title: Predict Radiation Levels While JPM No.: 2013 Admin JPM A3
-
Resrondina to a Damacied Scent EQ Fuel Pool K/A
Reference:
GK/A 2.3.14 (3.4)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testincu Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1 Initial Conditions:
- Due to an Earthquake, Unit 2 tripped from 100% power.
- Unit 1 is 11 days into a Refueling Outage and a full core off-load has just been completed.
- A Loss of Offsite Power has occurred, and only one EDG is running on each unit.
- The Unit 1 Spent Fuel Pool has sustained damage, and is leaking.
- The crew is implementing several EPs/AP5 simultaneously including AP/1/A15500/41 (Loss of Spent Fuel Pool Cooling or Level).
- The TSC is manned.
- All attempts to add makeup water to the Unit 1 Spent Fuel Pool have been unsuccessful.
- The Control Room Spent Fuel Pool Level and Temperature instrumentation are unavailable.
- It is expected that the ability to add makeup water to the Spent Fuel Pool will be regained within four hours.
2013 Admin JPM A3 RD
- NUREG 1021, Revision 9
Appendix C Page 3 of 9 Form ES-C-i Job Performance Measure Worksheet
- An operator who has just left the Spent Fuel Pool Area has reported that during the 12 minutes that he was in the Spent Fuel Pool Area, the Aztec Level Gauge dropped about 1 foot, and the present level is 23 feet above the top of the Spent Fuel.
Initiating Cue: The OSC Coordinator has directed you to refer to Enclosure 13 (Spent Fuel Pool Radiation Level vs. Water level Above Fuel) of AP/11A15500/41 (Loss of Spent Fuel Pool Cooling or Level), and determine the expected radiation levels one hour, two hours, three hours and four hours from now, based on the last known leak rate.
Assume Dose Rate rises linearly as level drops between 20 and 15 feet Assume initial leakrate remains constant.
Task Standard: The operator will use Enclosure 13 of AP/i/A15500/41 and determine that the expected radiation levels will be as follows:
One hour 0.38 mr/hr (+/-50%)
Two hours 13.2 mr/hr Three hours 8.73 R/hr Four hours 5790 R/hr Required Materials: Calculator General
References:
AP/i/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), Rev 11 EP/1/A15000/G-1 (Generic Enclosures), Enclosure 32 (Monitoring Unit 1 SFP Level and Temperature), Rev 34 McGuire Selected Licensee Commitments 16.9.21 (Water Level Spent Fuel Storage Pool), Rev 0 Handouts: Handout 1: Enclosure 13 (Loss of Spent Fuel Pool Cooling or Level) of AP/1/A15500/41 (Loss of Spent Fuel Pool Cooling or Level)
Time Critical Task: NO Validation Time: 15 minutes 2013 Admin JPM A3 RO
- NUREG 1021, Revision 9
Appendix C Page 4 of 9 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1 START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 (Enclosure 13) Determine The operator recognizes expected radiation levels in that the present level of the Spent Fuel Pool area in 1 Spent Fuel Pool hour. approximates the SLC Limit of 23 feet above the Fuel, and uses this as a reference.
The operator recognizes that the Spent Fuel Pool is lowering at a rate of 5 feet per hour, and will be approximately 18 feet above the Spent Fuel Pool in one hour.
The Operator uses Enclosure 13, locates the Dose Rate at 20 feet and 15 feet, and then approximates between these two values for 18 feet.
When this is accomplished the operator will determine that the expected Dose Rate in one hour is approximately 0.38 mremlhr (+/-50%) See Key on Page 81.
- NUREG 1021, Revision 9
Appendix C Page 5 of 9 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 2 (Enclosure 13) Determine The operator recognizes expected radiation levels in that the Spent Fuel Pool is Spent Fuel Pool area in 2 lowering at a rate of 5 feet hours. per hour, and will be approximately 13 feet above the Spent Fuel Pool in two hours.
The Operator uses Enclosure 13, locates the Dose Rate at 13 feet, and determines that the expected Dose Rate in two hours is approximately mrem)hr [See Key on Page 81.
- 3 (Enclosure 13) Determine The operator recognizes expected radiation levels in that the Spent Fuel Pool is Spent Fuel Pool area in 3 lowering at a rate of 5 feet hours. per hour, and will be approximately 8 feet above the Spent Fuel Pool in three hours.
The Operator uses Enclosure 13, locates the Dose Rate at 8 feet, and determines that the expected Dose Rate in three hours is approximately 8.73 Rem/hr
[See Key on Page 81.
- NUREG 1021, Revision 9
Appendix C Page 6 of 9 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 4 (Enclosure 13) Determine The operator recognizes expected radiation levels in that the Spent Fuel Pool is Spent Fuel Pool area in 4 lowering at a rate of 5 feet hours. per hour, and will be approximately 3 feet above the Spent Fuel Pool in four hours.
The Operator uses Enclosure 13, locates the Dose Rate at 3 feet, and determines that the expected Dose Rate in four hours is approximately 5790 Rem/hr rsee Key on Page Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
- NUREG 1021, Revision 9
Appendix C Page 7 of 9 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin JPM A3 RO
-
Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result: SAT UNSAT Examiners Signature: Date:
- NUREG 1021, Revision 9
Appendix C Page 8 of 9 Form ES-C-i VERIFICATION OF COMPLETION KEY:
1 Hour Dose rate at 20 feet 1.21 xi 0 R/hr x 1 O mrem/hr/R/hr = .001 mrem/hr 3
Dose rate at 15 feet 9.51 xi 0 R/hr x 1 Omrem/hr/R/hr = .951 mrem/hr 3
Assume Dose Rate rises linearly as level drops between 20 and 15 feet.
.951 mrem/hr .001 mrem/hr / 5 feet= .19 mrem/hr/ft
-
Since the rise in radiation level from level dropping one foot from 20 feet is 0.19 mrem/hr, the expected Dose Rate at 18 feet is .38 mrem/hr higher than the Dose Rate at 20 feet; or .38 rnrem/hr, (.19 -.57 mrem/hr) 2 Hours This is a direct read from the Table.
Dose rate at 13 feet 1.32 x10 2 R/Hr x io mrem/hr/R/Hr 3 = 13.2 mrem/hr 3 Hours This is a direct read from the Table.
Dose rate at 8 feet 8.73R/Hr 4 Hours This is a direct read from the Table.
Dose rate at 3 feet 5790 R/Hr 2013 Admin JPM A3 RO
- NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions:
- Due to an Earthquake, Unit 2 tripped from 100% power.
- Unit 1 is ii days into a Refueling Outage and a full core off-load has just been completed.
- A Loss of Offsite Power has occurred, and only one EDG is running on each unit.
- The Unit 1 Spent Fuel Pool has sustained damage, and is leaking.
- The crew is implementing several EPs/APs simultaneously including AP/i/A15500/41 (Loss of Spent Fuel Pool Cooling or Level).
- The TSC is manned.
- All attempts to add makeup water to the Unit 1 Spent Fuel Pool have been unsuccessful.
- The Control Room Spent Fuel Pool Level and Temperature instrumentation are unavailable.
- It is expected that the ability to add makeup water to the Spent Fuel Pool will be regained within four hours.
- An operator who has just left the Spent Fuel Pool Area has reported that during the 12 minutes that he was in the Spent Fuel Pool Area, the Aztec Level Gauge dropped about 1 foot, and the present level is 23 feet above the top of the Spent Fuel.
INITIATING CUE: The OSC Coordinator has directed you to refer to Enclosure 13 (Spent Fuel Pool Radiation Level vs. Water level Above Fuel) of AP/i/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), and determine the expected radiation levels one hour, two hours, three hours and four hours from now, based on the last known leak rate.
Assume Dose Rate rises linearly as level drops between 20 and 15 feet.
Assume initial leakrate remains constant.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Ala SRO 2013 Admin JPM Ala SRO (REV_111213)
- NUREG 1021, Revision 9
Appendix C Page 2 of 9 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:
Task Title: Determine Boric Acid Addition to JPM No.: 2013 Admin JPM Ala
-
FWST SRO K/A
Reference:
GK!A 2.1.25 (4.2)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinQ:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-3.
Initial Conditions:
- The plant was at 100% power when a leak developed on the FWST.
- FWST Level dropped to 440 inches before leak was isolated.
- Enclosure 4.4, FWST Makeup Using the RHT, of OP/1/A16200/014, Refueling Water System is in progress and completed through Step 3.10.
- Chemistry has provided the following information:
- BAT Boron Conc. = 7311 ppm
- RHT Boron Conc.= 826 ppm
- The BOP has just completed the Doer Calculation of Step 3.11 of Enclosure 4.4, FWST Makeup Using the RHT, and has asked you to perform an Independent Verification on the calculation.
Initiating Cue: Perform the Independent Verification (IV) of the calculation in Step 3.11 of Enclosure 4.4 to confirm the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480 using the RHT.
- NUREG 1021, Revision 9
Appendix C Page 3 of 9 Form ES-C-i Job Performance Measure Worksheet AFTER the calculations have been completed and verified in the FWST make up procedure, an 80 gpm Makeup is started to the FWST, and continues for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
At the end of this 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period what is the status of compliance with LCO 3.5.4; and what additional ACTION, if any, is required?
FWST Temperature =85 Deg FWST [B] = 2775 ppm Task Standard: The operator will calculate the amount of Boric Acid that must be added from the BAT to refill the FWST is between 8654 and 9247 gallons, determine that the BOP made two errors in the original calculation, and identify that Technical Specification ACTION C is now applicable.
Required Materials: Calculator OP/l/A16100/022 (Unit 1 Data Book Cycle 23) available to Operator
MCEI-0400-261 (Unit 1 Cycle 23 Core Operating Limits Report) available to Operator General
References:
OP/i/A16200/014 (Refueling Water System), Rev 91 OP/11A16100/022 (Unit 1 Data Book Cycle 23), Rev 480
MCEI-0400-261 (Unit 1 Cycle 23 Core Operating Limits Report), Rev 0 McGuire Technical Specifications LCO 3.5.4, Refueling Water Storage Tank (RWST), Amendment 184/i 66 Handouts: Handout 1: Enclosure 4.4 (FWST Makeup Using RHT) of OP/1/A/6200/014 (Refueling Water System) marked up for place keeping through the Doer Calculation of Step 3.11.
Handout 2: McGuire Cycle 23 Core Operating Limits Report, Page 26.
Handout 3: OP/1/A16100/22, Enclosure 4.3, Curve 7.7; Refueling Water Storage Tank Level (Volume vs. Tank Level).
Time Critical Task: NO Validation Time: 25 minutes 2013 Admin JPM Al a SRO
- NUREG 1021, Revision 9
Appendix C Page 4 of 9 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-3.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT i (Step 3.11) Determine the The operator refers to the amount of Boric Acid COLR, Section 2.13.1 on needed to raise makeup Page 26 of 32 and water to the limits specified determines that the in the Core Operating Limits minimum boron Report (COLR). concentration to be used in the calculation is 2675 ppm, and NOT 2775 ppm used by BOP (jSt Error).
The operator records 2675 ppm in the first line (Desired Boron Concentration of Addition from COLR) of the IV calculation in Step 3.11 of Enclosure 4.4.
- 2 St 1
(
Bullet) Desired Boron The operator adds an Concentration of Addition additional 25 ppm and from COLR + 25 ppmB determines Desired Boron margin = Desired Boron Concentration to be 2700 Concentration ppm.
The operator records 2700 ppm in the 2nd line (Desired Boron Conc) of the IV calculation in Step 3.1 1 of Enclosure 4.4.
- 3 (2 Bullet) The operator identifies Desired Cb = 2700 from
((Desired Cb) (RHT Cb)}
-
previous Step and records.
(BAT Cb) (RHT Cb)
-
The operator recognizes x (Desired Total that RHT Cb = 826 ppm Makeup Volume to and records Initial FWST} Conditions).
= Desired BAT Volume The operator recognizes that BAT Cb = 7311 ppm and records (Initial 2013 Admin JPM Ala SRO
- NUREG 1021, Revision 9
Appendix C Page 5 of 9 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 3 Conditions).
(C0NTD) The operator addresses OP/i /AJ61 00/22, Enclosure 4.3, Curve 7.7, and determines from graph that total makeup volume is 30,000 by comparing 480 volume of 390,000 gallons to the 440 volume of 360,000 gallons.
The operator records 31,000 (+1000/-1050) gallons; and NOT 20,000 gallons used by the BOP (2 Error).
The operator records 31,000 (+1000/-1050) gallons in the IV Calculation.
The operator calculates the Desired BAT Volume to be added to be between 8654 and 9247 gallons.
The operator records between 8654 and 9247 gallons as the Desired BAT Volume in the Doer Calculation.
- NUREG 1021, Revision 9
Appendix C Page 6 of 9 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 4 (Technical Specification The operator observes TS LCO 3.5.4) The RWST shall LCO 3.5.4 and determines be OPERABLE. that ACTION B was entered at the start of the JPM and action was necessary within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore volume.
The operator determines that the FWST Volume TS Limit is 372,100 gallons.
The operator determines that 12,100 gallons must be added to the FWST to comply with this ACTION Statement, and that in one hour 4800 gallons will be added.
The operator identifies that ACTION C is now applicable.
Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
- NUREG 1021, Revision 9
Appendix C Page 7 of 9 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin JPM Ala SRO
-
Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result: SAT UNSAT Examiners Signature: Date:
- NUREG 1021, Revision 9
Appendix C Page 8 of 9 Form ES-C-i VERIFICATION OF COMPLETION KEY:
Desired Boron Concentration from COLR + 25 ppmB = Desired Boron Concentration 2675 ppm (From COLA) ÷ 25 ppmB = 2700 ppm
((Desired Cb) (RHT Cb)) x (Desired Total Makeup Volume to FWST}
- = Desired BAT Volume (BAT Cb) (RHT Cb)
-
Given:
RHT Cb = 826 ppm BAT Cb=7311 ppm Desired Total Makeup Volume to FWST = Overflow volume Present volume
(From Enclosure 4.3, Curve 7.7 of Unit 1 Core Data Book:)
- 390,000 gallons 360,000 gallons (440) = 30,000 gallons#
4: If the operator uses develops a gallons/inch volume from the information block on Curve 7.7, the operator will determine the makeup volume to be 31,277 gallons.
- If the operator uses an interpolation of the graph they could determine the leveJ at 490 inches to be between 30,000 and 32,000 gallons.
Volume at 484 Inches = 394,089 gallons Volume at 0 inches = 15,638 gallons (394,089 gallons 15,638 gallons)/484 inches = 781.92 gallons/inch OR Volume at 455.88 inches = 372,100 gallons Volume at 0 inches = 15,638 gallons (372,100 gallons 15, 638 gallons)/455.88 inches = 781.92 gallons/inch Therefore, 781.92 gallons/inch x 40 inches = 31,276.80 gallons (This may be used as the makeup volume instead of 30,000 gallons).
If this volume is used, the calculation will result in a Desired BAT Volume below of 9038 gallons So:
{(Desired Cb-(RHT Cb)} x {Desired Total Makeup Volume to FWST) = Desired BAT Volume (BAT Cb)-(RHT Cb)
{(2700)-(826l} x (30000) = Desired BAT Volume (731 1)-(826)
{i} x (30000) = Desired BAT Volume 6485
.28897 x {29950) = Desired BAT Volume or 8654 gallons, Where $=50 gallons is allowance 28897 x {32000} = Desired BAT Volume or 9247 gallons OR between 8654 and 9247 gallons 2013 Admin JPM Al a SRO
- NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions:
- The plant was at 100% power when a leak developed on the FWST.
- FWST Level dropped to 440 inches before leak was isolated.
- Enclosure 4.4, FWST Makeup Using the RHT, of OP/i /A/6200/01 4, Refueling Water System is in progress and completed through Step 3.10.
- Chemistry has provided the following information:
- BAT Boron Conc. = 7311 ppm
- RHT Boron Conc.= 826 ppm
- The BOP has just completed the Doer Calculation of Step 3.11 of Enclosure 4.4, FWST Makeup Using the RHT, and has asked you to perform an Independent Verification on the calculation.
INITIATING CUE: Perform the Independent Verification (IV) of the calculation in Step 3.11 of Enclosure 4.4 to confirm the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480 using the RHT.
AFTER the calculations have been completed and verified in the FWST make up procedure, an 80 gpm Makeup is started to the FNST, and continues for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
At the end of this 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period what is the status of compliance with LCO 3.5.4; and what additional ACTION, if any, is required?
FWST Temperature = 85 Deg FWST [B] = 2775 ppm NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Aib SRO 2013 Admin JPM Aib SRO (REV_111213)
- NUREG 1021, Revision 9
Appendix C Page 2 of 17 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:
Task Title: Perform an ECP JPM No.: 2013 Admin JPM Aib
-
SRO K/A
Reference:
GKIA 2.1.37 (4.6)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-10.
Initial Conditions: Unit 1 startup in progress per OP/1/A16i00/00i (Controlling Procedure for Unit Startup).
All steps are complete up to determining the desired estimated critical rod height.
The Unit tripped from 30% power, 143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br /> ago.
Prior to that the Unit had operated at 25 EFPD since the previous plant trip, which resulted in a shutdown lasting 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The following Cycle 23 conditions exist:
- EFPD=200
- NCBoron=1694PPM
- Xenon Worth =0
- Samarium = -150 PCM It is intended to pull rods to criticality with criticality achieved in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Reactor Engineer has been contacted earlier today and has reported that there have been no unusual trends on ECPs.
The OAC and REACT Program are unavailable.
- NUREG 1021, Revision 9
Appendix C Page 3 of 17 Form ES-C-i Job Performance Measure Worksheet nitiating Cue: The CRS has directed you to perform an ECP per Enclosure 4.2 (Estimated Critical Rod Position (ECP)) of OP/0/A161 00/006 (Reactivity Balance Calculation).
Task Standard: The Actual Estimated Critical Rod Position Bank for No and Peak Xenon at time of Criticality agrees with the attached KEY.
Required Materials: Calculator General
References:
OP/11A161001003 (Controlling Procedure for Unit Operation), Rev 184 OP/0/A16100/006 (Reactivity Balance Calculation), Rev 74 OP/i/A16100/022 (Unit 1 Data Book Cycle 23), Rev 480
MCEI-0400-261 (Unit 1 Cycle 23 Core Operating Limits Report), Rev 0 SOMP 01-02 (Reactivity Management), Rev 8 Handouts: Handout 1: OP/0/A/61 00/006 (Reactivity Balance Calculation) Enclosure 4.2 (Estimated Critical Rod Position (ECP)
Handout 2: OP/0/A16100/006 (Reactivity Balance Calculation) Enclosure 4.8 (Fission Product Correction Calculation)
Handout 3: OP/i/A16100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.7, Shutdown Fission Product Correction Handout 4: OP/1/A16100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 6.1, Critical Boron Concentration HZP, ARO, NO XENON, EQ Sm.
Handout 5: OP/1/A16100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 6.8, Differential Boron Worth, HZP, ARO, NO XENON, EQ Sm.
Handout 6: OP/1/A16100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.9, Xenon and Samarium Worths.
Handout 7: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.3.A, Integral Rod Worth in Overlap, HZP, NO XENON.
Handout 8: OP/i/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.3.B, Integral Rod Worth in Overlap, HZP, PEAK XENON.
Handout 9: OP/1/A16100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 1 .2, Control Rod Insertion Limit as a Function of Power.
Handout 10: OP/i/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 2.8, Rod Withdrawal Limits.
Time Critical Task: NO Validation Time: 30 minutes 2013 Admin JPM Aib SRO
- NUREG 1021, Revision 9
Appendix C Page 4 of 17 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-10.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Note prior to Step 3.1) All The operator reads the curves/tables used in this Note and proceeds.
procedure are found in OP/i (2)/A/61 00/022 (Unit One (Two) Core Data Book). These procedures will be referred to as the Data Book.
2 (Step 3.1) Record the following:
The operator records Unit 1 (Step 3.1.1)
Unit_____ Cycle The operator records Cycle 23.
(Step 3.1 .2) Recent trends The operator recognizes 3
on ECP that Chad Adams has been
- contacted.
Reactor Engineer contacted Date The operator records RE name () and todays date.
4 (Step 3.1.3) Date/Time of The operator records Shutdown. DatelTime (143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br /> ago) from current Date/Time.
5 (Step 3.1.4) Anticipated The operator records Date/Time of Criticality todays date and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the time calculation 7 is started as the time of criticality.
-
NUREG 1021, Revision 9
Appendix C Page 5 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Step 3.1.5) Burnup:
(P1457) The operator records 200 EFPD.
7 (Step 3.1.6) NC System Boron Concentration:
(Step 3.1.6.1) If pulling rods The operator recognizes to Criticality: from initial conditions that (Step 3.1 .6.1A) If OAC is OAC is unavailable and it is unavailable, record the intended to pull rods to current NC System boron criticality. The operator concentration. records 1694 in Step 3.1 .6.iA.
OR (Step 3.1 .6.1 B) If OAC is The operator places f in available Step 3.1.6.iB.
8 (Step 3.1 .6.2) If dilution to The operator places in Criticality Step 3.1.6.2.
9 (Step 3.1.6.3) Record the Effective Boron Concentration:
(Step 3.1.6.iA or Step 3.1.6.1 B3 or 3.1.6.2) The operator records 1694 ppm from Step 3.i.6.iA.
10 (Step 3.1.7) Xenon worth at The operator records Q from anticipated time of Criticality initial conditions.
(From OAC program Xenon Samarium XESM or
REACT Program).
11 (Step 3.1 .8) If burnup from The operator recognizes Step 3.1.5 is > 0 EFPD, that burnup is > 0 EFPD record the difference and records -150 from initial between equilibrium and conditions.
present samarium worth (P1 475, Samarium program on OAC or REACT).
- NUREG 1021, Revision 9
Appendix C Page 6 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 12 (Step 3.1.9) If burnup from The operator recognizes Step 3.1.5 is> 12 EFPD, that burnup is> 12 EFPD perform Enclosure 4.8 to and that fission product determine the fission correction is needed, and product correction. proceeds to Enclosure 4.8.
13 (Enclosure 4.8/Notes prior The operator reads Notes, to Step 3.1) All curves and proceeds.
/tables used in this procedure are found in OP/i (2)/A161 00/022 (Unit One (Two) Core Data Book). These procedures will be referred to as the Data Book.
Number of hours shutdown is the difference in time between the time the reactor went subcritical and the expected time of criticality.
- 14 (Step 3.1) Shutdown The operator reviews power Fission Product Correction history and recognizes that Calculation: the Unit did operate > 3
. EFPD from previous (Step 3.1 .1) If Unit operated shutdown to current
> 3 EFPD from previous shutdown shutdown to current shutdown: The operator records 144 in (Step 3.1.1.1) Use Data Step 3.1.1.2, and proceeds Book Table 6.7 to to Step 3.1.1.3.
determine the shutdown The operator uses Data fission product correction: Book Table 6, and determines that the (Step 3.1 .1 .2) Number of Shutdown Fission Product hours shutdown Correction for 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> is 41 PPM, and records this in (Step 3.1 .1 .3) Shutdown Step 3.1.1.3.
Fission Product Correction:
- NUREG 1021, Revision 9
Appendix C Page 7 of 17 Form ES-C1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 15 (Step 3.1.2) If Unit operated The operator reviews power
< 1 EFPD from previous history and recognizes that shutdown to current the Unit operated> 1 EFPD shutdown...... from previous shutdown to current shutdown.
Operator records an in Step 3.1.2, and proceeds to Step 3.1.3.
16 (Step 3.1.3) If Unit operated The operator reviews power between 1 EFPD and 3 history and recognizes that EFPD from previous the Unit did NOT operate shutdown to current between 1 and 3 EFPD shutdown from previous shutdown to current shutdown.
Operator records an NA in Step 3.1 .3, and proceeds to Step 3.1.4.
17 (Step 3.1.4) If Unit The operator reviews power operated between 1 EFPD history and recognizes that and 3 EFPD from previous the Unit did NOT operate shutdown to current between 1 and 3 EFPD shutdown from previous shutdown to current shutdown.
Operator records an NA in Step 3.1.4.
Operator records that the Shutdown Fission Product Correction factor is 41 in Enclosure 4.2, Step 3.1.9.
- NUREG 1021, Revision 9
Appendix C Page 8 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 18 (Enclosure 4.2/Step 3.2) If The operator recognizes desired, perform automated from initial conditions that calculations using REACT is NOT available REACT and proceeds to Step 3.3.
- 19 (Step 3.3) Manual Calculations:
(Step 3.3.1) Boron Concentration:
(Step 3.3.1.1) Determine The operator addresses the all rods out (ARO), hot Data Book Graph 6.1.
zero power (HZP), no (NOTE: The operator xenon, equilibrium should use chart at bottom, samarium, boron and NO interpolation is concentration for present needed).
burnup from Step 3.1.5 (Data Book Graph 6.1)
(Step 3.3.1.2) Record value The operator records 1793 in Table 4.2.1 Line A. in Table 4.2.1 Line A.
- 20 (Step 3.3.2) Differential The operator addresses Boron Worth: Data Book Graph 6.8.
(Step 3.3.2.1) Determine (NOTE: Operator should the ARO differential boron use chart at bottom, and worth for present burnup of NO interpolation is needed).
step 3.1.5 (Data Book Graph 6.8)
(Step 3.3.2.2) Record value The operator records -6.52 in Table 4.2.1 Line B in Table 4.2.1 Line B.
- NUREG 1021, Revision 9
Appendix C Page 9 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 21 (Step 3.3.3) Determine the The operator records values Rod Inserted Worth: from steps 3.1 .6 3.1.9 in
-
Step (3.3.3.1) Record Table 4.2.1 as follows:
values from Steps 3.1.6 - C. Present Effective Boron 3.1.9 in Table 4.2.1. Concentration: 1694 D. Xenon Worth: 0 E. Diff from Eq Sm Worth:
-150 F. Fission Product Correction: 41 22 (Step 3.3.3.2) Complete The operator records Table 4.2.1, recording 0 for remaining values in Table any N/Ad Reference Steps. 4.2.1, as follows:
G. Reactivity Equivalent of Boron Difference (C A) x B
-
= (645.5).
(1694 -1793)x-6.52=-
645.5 pcm H. Reactivity Equivalent of Fission Product Correction FxB = -267.3 41 x -6.52 = -267.3 Reactivity of Inserted Rods:
(D+E+G)H=762.8 (0 + -150 + (645.5))
(-267.3) = 762.8 23 (Step 3.3.4) If result from The operator recognizes Table 4.2.1 < 0 result from Table 4.2.1 > 0 and records in Step 3.3.4.
-
NUREG 1021, Revision 9
Appendix C Page 10 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 24 (Step 3.3.5) Peak xenon The operator addresses worth: Data Book Table 6.9.
(Step 3.3.5.1) Determine the peak xenon worth for present burnup from step 3.1.5 (Data Book Table 6.9)
(Step 3.3.5.2) Record value The operator records 3985 in Table 4.2.2 Line C. in Table 4.2.2 Line C.
25 (Step 3.3.6) Calculate the The operator records values Estimated Critical Rod in Table 4.2.2 as follows:
Positions: A. Xenon Worth: 0 (Step 3.3.6.1) Record B. Reactivity of inserted values from Step 3.1.7 and rods: 762.8 Table 4.2.1 in Table 4.2.2.
C. Peak Xenon Worth: 3985 D. Lower Band Reactivity Worth: 1512.8 E. Upper Band Reactivity Worth: 12.8 2013 Admin JPM Al b SRO
- NUREG 1021, Revision 9
Appendix C Page 11 of 17 Form ESC..1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 26 (Step 3.3.6.2) Complete The operator completes Table 4.2.2. Table 4.2.2 as follows:
The operator addresses Table 6.3.Aof the Data Book and determines:
F. No Xenon Rod Position for Reactivity of B Bank D
-
@ 55 steps, +0/-5 steps.
G. No Xenon Rod Position for Reactivity of D Bank C
-
@ 66 steps, +4/-i steps.
H. No Xenon Rod Position for Reactivity of E Bank D
@ 217 steps, +3/-2 steps.
The operator addresses Table 6.3.B of the Data Book and determines:
I. Peak Xenon Rod Position for Reactivity of B Bank D
-
@ 74 steps, +11-4 steps.
J. Peak Xenon Rod Position for Reactivity of D Bank C
-
@ 90 steps, +0/-5 steps.
K. Peak Xenon Rod Position for Reactivity of E Bank D @ 220 steps, +0/-S steps.
- 27 (Table 4.2.2) Estimated The operator records Bank Critical Position D @ 55 steps, +0/-S steps.
[(I F) x (A ÷ C)] + F.
-
- NUREG 1021, Revision 9
Appendix C Page 12 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 28 (Table 4.2.2) Lower Limit of The operator records Bank Band C @ 66 steps. +4/-i steps.
{(J G) x (A ÷ C)]
- + G
- 29 (Table 4.2.2) Upper Limit of The operator records Bank Band D @ 217 steps, +3/-2 steps.
[(K- H)x(A÷C)]+H
- 30 (Step 3.4) Check the The operator addresses following: Graph 1.2 and determines (Step 3.4.1) Rod Positions rod positions are greater of Table 4.2.2 or REACT than insertion limits.
output are greater than insertion limits per Data The operator addresses Book Graph 1.2. Table 2.8 and determines that there are no rod (Step 3.4.2) Rod positions withdrawal limits.
of Table 4.2.2 or REACT Output are less than rod withdrawal limits per Data Book Table 2.8.
31 (Step 3.5) If Step 3.4 The operator recognizes CANNOT be met that reactor Engineering does NOT need to be contacted.
- NUREG 1021, Revision 9
Appendix C Page 13 of 17 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 32 Calculations performed By: The operator records Name (RO) and date.
Date Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
2013 Admin -JPMA1bSRO NUREG 1021, Revision 9
Appendix C Page 14 of 17 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin JPM Aib SRO
-
Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result: SAT UNSAT Examiners Signature: Date:
- NUREG 1021, Revision 9
Appendix C Page 15 of 17 Form ES-C-i VERIFICATION OF COMPLETION KEY:
Table 4.2.1: Rod Inserted Worth Calculation Description Reference Value A. ARO, HZP, No Xenon, Eq. Step 3.3.1 1793ppm Samarium Boron B. ARO/DBW Step 3.3.2 652pcm/ppm C. Present Effective Boron Step 3.1.6.3 1694ppm Concentration D. Xenon Worth Step 3.1.7 Opcm E. Diff from Eq Sm Worth Step 3.1.8 -1 5Opcm Step 3.1 .9 41 ppm F. Fission Product Correction G. Reactivity Equivalent of (C-A) x B 645.5pcm Boron Difference (1694 1793)
-
x -6.52 H. Reactivity Equivalent of FxB -267.3pcm Fission Product CorrecUon 41 x -6.52 Reactivity of Inserted Rods ( D + E + G) H 762.8pcm (0 + -150
+ 645.5) (-267.3)
-
NUREG 1021, Revision 9
Appendix C Page 16 of 17 Form ES-C-i VERIFICATION OF COMPLETION KEY01t Table 4.2.2: Estimated Critical Rod Positions Description Reference Value A. Xenon Worth Step 3.1.7 Opcm B. Reactivity of inserted rods Table 4.2.1 762.8pcm C. Peak Xenon Worth Step 3.3.5 - 3985pcm D. Lower Band Reactivity B + 750 1512.8pcm Worth E. Upper Band Reactivity B - 750 128pcm Worth F. No Xenon Rod Position for Data Book Table 6.3.A BankD 55+5/-Osteps w/d Reactivity of B G. No Xenon Rod Position for Data Book Table 6.3.A BankC 66+4/-Isteps w/d Reactivity of D H. No Xenon Rod Position for Data Book Table 6.3.A BankD 21 7+3!-2steps w/d Reactivity of E I. Peak Xenon Rod Position Data Book Table 6.3.B BankD 74+1/-4steps w/d for Reactivity of B J. Peak Xenon Rod Position Data Book Table 6.3.B BankC 90+1/-4steps w/d for Reactivity of D K. Peak Xenon Rod Position Data Book Table 6.3.B Bank D 220+0/-5 steps w/d for Reactivity of E Estimated Critical Position [(I - F) x (NC)] + F BankD 55+5/-0 steps w/d
[(D74 D55)
x (0/3985)]
+ D55 Lower Limit of Band [(J - G) x (NC)] + G BankC 66+4/-isteps w/d
[(090 066)
x (0/3985)]
+ 066 Upper Limit of Band [(K - H) x (NC)] + H BankD 217+3/-2 steps w/d
[(D220 D21 7)
x (0/3985)]
+_D217 2013 Admin - JPM Aib SRO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions: Unit 1 startup in progress per OPI1/AJ6100IOO1 (Controlling Procedure for Unit Startup).
All steps are complete up to determining the desired estimated critical rod height.
The Unit tripped from 30% power, 143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br /> ago.
Prior to that the Unit had operated at 25 EFPD since the previous plant trip, which resulted in a shutdown lasting 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The following Cycle 23 conditions exist:
- EFPD=200
- XenonWorth=O
- Samarium = -150 PCM It is intended to pull rods to criticality with criticality achieved in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Reactor Engineer has been contacted earlier today and has reported that there have been no unusual trends on ECPs.
The OAC and REACT Program are unavailable.
INITIATING CUE: The CRS has directed you to perform an ECP per Enclosure 4.2 (Estimated Critical Rod Position (ECP)) of OP/0/A16100/006 (Reactivity Balance Calculation).
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM A2 SRO 2013 Admin JPM A2 SRO (REV_111213) NUREG 1021, Revision 9
Appendix C Page 2 of 8 Form ESC-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task Title: Determine Procedure Sections that JPM No.: 2013 Admin Audit
Must be Performed JPM A2 SRO K/A
Reference:
GKIA 2.2.12 (4.1)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testinci:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1.
Initial Conditions:
- A plant startup is in progress in accordance with OP/1/A16100/003 (Controlling Procedure for Unit Operation).
- The crew has just stabilized the plant at 3.6% power and is in a 10 minute hold.
- The BOP reports that the following OAC points have changed from Green to Magenta on the OAC Display Screen:
- Mi Li 470, Xenon/Samarium Calcs Program Status
- Mi P1555, Max Rod Deviation Shutdown Bank E
- MiAi234, Lower Cont Ambient Air Temp B
- All other equipment is operating normally.
- No unexpected alarms have occurred.
Initiating Cue: The CRS has directed you to assess the OAC Points using PT/i /A/4600/021 B (Loss of Operator Aid Computer while in Mode 2).
Identify the following below:
- Procedure sections that must be performed.
- Personnel and/or organizations that must be notified.
- Procedure Enclosures or other procedures that must be performed.
2013 Admin JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 3 of 8 Form ES-C-i Job Performance Measure Worksheet Task Standard: The operator will identify the five procedure Sections that must be performed as 12.2, 12.5,12.9,12.10 and 12.13; identifythatthe Engineering OAC Group must be notified, and that Enclosure 13.2 Part A needs to be performed.
Required Materials: None General
References:
OPI1IAI6100/003 (Controlling Procedure for Unit Operation), Rev 184 PT/i /A/4600/021 B (Loss of Operator Aid Computer while in Mode 2),
Rev 26 Handouts: Handout 1: Blank Copy of PT/i/A14600/021 B (Loss of Operator Aid Computer while in Mode 2)
Time Critical Task: NO Validation Time: 15 minutes 2013 Admin JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 4 of 8 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1.
START TIME:
STEPS ELEM ENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Notes prior to Step 12.1) A The operator reads the magenta OAC point NOTES and proceeds.
indicates Failed or Bad Quality. Some of these also indicate a partial loss of OAC.
Turn On Code GD OAC may be used to find OAC points in Enclosure 13.5 (OAC Point List For Partial Loss Of OAC).
- 2 (Step 12.1) IF this The operator proceeds to procedure is entered due to Enclosure 13.5.
a Failed OR Bad Quality OAC point, go to Enclosure 13.5 (OAC Point List For Partial Loss Of OAC) to determine applicable sections of procedure to perform. All other sections of procedure may be marked NA.
- 3 (Enclosure 13.5) Determine applicable sections of The operator determines procedure to perform due to that procedure sections Bad Quality on Ml Li 470, 12.2 and 12.13 need to be Max Rod Deviation performed.
Shutdown Bank E
- 4 (Enclosure 13.5) Determine The operator determines applicable sections of that procedure sections procedure to perform due to 12.2, 12.5 and 12.9 need to Bad Quality on Mi P1555, be performed.
SWBD Application Active Flag 2013 Admin JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 5 of 8 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 5 (Enclosure 13.5) Determine The operator determines applicable sections of that procedure sections procedure to perform due to 12.2 and 12.10 need to be Bad Quality on M1A1 234, performed.
Lower Cont Ambient Air Temp B
- 6 Identify procedure sections The operator identifies that that must be performed. procedure sections 12.2, 12.5, 12.9, 12.10 and 12.13 need to be performed.
- 7 Identify personnel and/or The operator reviews organizations that must be procedure sections 12.2, notified. 12.5, 12.9, 12.10 and 12.13, and determines that the Engineering OAC Group must be notified (Section 12.2).
- 8 Identify procedure The operator reviews Enclosures that must be procedure sections 12.2, performed. 12.5, 12.9, 12.10 and 12.13, and determines that Enclosure 13.2 Part A needs to be performed (Section 12.9).
Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
2013 Admin JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 6 of 8 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin JPM A2 SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result: SAT UNSAT Examiners Signature: Date:
2013 Admin JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 7 of 8 Form ES-C-i VERIFICATION OF COMPLETION KEY:
- 1. Procedure sections that must be performed Sections 122, 125, 129, 1210 and 1213.
- 2. Personnel and/or organizations that must be notified Engineering OAC Group
- 3. Procedure Enclosures or other procedures that must be performed as power is raised Enclosure 132 Part A 2013 AdminJPM A2 SRO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions:
- A plant startup is in progress in accordance with OP/i /A/61 00/003 (Controlling Procedure for Unit Operation).
- The crew has just stabilized the plant at 3.6% power and is in a 10 minute hold.
- The BOP reports that the following OAC points have changed from Green to Magenta on the OAC Display Screen:
- Mi Li 470, Xenon/Samarium Calcs Program Status
- MiPi555, Max Rod Deviation Shutdown Bank E
- MiAi 234, Lower Cont Ambient Air Temp B
- All other equipment is operating normally.
- No unexpected alarms have occurred.
INITIATING CUE: The CRS has directed you to assess the OAC Points using PT/i/A/4600/O2iB (Loss of Operator Aid Computer while in Mode 2).
Identify the following below:
- Procedure sections that must be performed.
- Personnel and/or organizations that must be notified.
- Procedure Enclosures or other procedures that must be performed.
- 1. Procedure sections that must be performed
- 2. Personnel and/or organizations that must be notified
- 3. Procedure Enclosures or other procedures that must be performed NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPM A3 SRO 2013 Admin JPM A3 SRO (REV_111213)
- NUREG 1021, Revision 9
Appendix C Page 2 of 9 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:
Task Title: Calculate Spent Fuel Pool Boiloff JPM No.: 2013 Admin JPM A3
-
rate and predict when Spent Fuel SRO Pool Radiation levels will exceed 100 mrem/hour K/A
Reference:
GK/A 2.3.14 (3.8)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testing:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handouts 1-2.
Initial Conditions:
- Due to an Earthquake, Unit 2 tripped from 100% power.
- Unit 1 was shutdown 24 days ago and a full core off-load has just been completed.
- A loss of Offsite Power has occurred, and only one EDG is running on each unit.
- The Unit 1 Spent Fuel Pool cooling has been lost.
- The crew is implementing several EPs/APs simultaneously including AP/1/A15500/41 (Loss of Spent Fuel Pool Cooling or Level).
h
- The earrnquake Iowewci me Unit 1 spent t-uel l-uul level to 23 feet above the top of the Spent Fuel due to wave action.
- All attempts to add makeup water to the Unit 1 Spent Fuel Pool have been unsuccessful.
- The Unit 1 Spent Fuel Pool has just started to boil.
- NUREG 1021, Revision 9
Appendix C Page 3 of 9 Form ES-C-i Job Performance Measure Worksheet Initiating Cue: The OSC Coordinator has directed you to use Enclosure 5 (Spent Fuel Pool Boiloff rate) of AP/11A15500/41 (Loss of Spent Fuel Pool Cooling or Level), and estimate how fast the Unit 1 Spent Fuel Pool level will go down as the pool boils.
THEN Use this boiloff rate and Enclosure 13 (Spent Fuel Pool Radiation Level vs. Water level Above Fuel> of API1IAI5500/41 (Loss of Spent Fuel Pool Cooling or Level), and predict when the radiation levels in the Unit 1 Spent Fuel Pool area will be greater than 100 mrem/hour if no makeup water is added.
Assume Dose Rate rises linearly as level drops Task Standard: The operator will determine that the Spent Fuel Pool level will go down at a rate of 3.1 inches/hour, and that the expected time that the Dose Rate in the Spent Fuel Area exceeds 100 mrem/hour is 41.8+/-2 hours.
Required Materials: Calculator General
References:
AP/i/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), Rev 11 EP/1/A15000/G-i (Generic Enclosures), Enclosure 32 (Monitoring Unit 1 SFP Level and Temperature), Rev 34 McGuire Selected Licensee Commitments 16.9.21 (Water Level Spent Fuel Storage Pool), Rev 0 Handouts: Handout 1: Enclosure 5 (Spent Fuel Pool Boiloff rate) of AP/1/A15500/4i (Loss of Spent Fuel Pool Cooling or Level)
Handout 2: Enclosure 13 (Loss of Spent Fuel Pool Cooling or Level) of AP/i/A15500/41 (Loss of Spent Fuel Pool Cooling or Level)
Time Critical Task: NO Validation Time: 15 minutes 2013 Admin JPM A3 SRO
- NUREG 1021, Revision 9
Appendix C Page 4 of 9 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handouts 1-2.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Enclosure 5, Note prior to The operator reads the Step 1) The following step Note and proceeds.
calculates Time After Shutdown. This value is used to determine how much decay heat exists in the pool and will be used in subsequent steps to calculate boiloff rate.
2 (Step 1) Determine Time The operator recognizes After Shutdown as follows: that this Step is NA and proceeds to Step 1 .a.2.
(Step 1.a) IF Unit 1 is currently shutdown for a refueling outage, THEN perform the following:
(Step 1.a.1) IF core offload has not occurred
- 3 (Step 1 .a.2) IF less than The operator recognizes 193 fuel assemblies are that Unit 1 was shut down currently in the reactor, 24 days ago (Initial THEN perform the Conditions), and proceeds following: to Step 2.
Use number of days since reactor was shutdown as Time After Shutdown.
Observe Notes prior to Step 2 and GO TO Step 2.
- NUREG 1021, Revision 9
Appendix C Page 5 of 9 Form ES.C1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Notes prior to Step 2) The operator reads the Notes and proceeds.
. Tables assume complete core off load has occurred. For partial off load, tables are conservative.
. If Spent Fuel Pool makeup has occurred, tables are conservative.
. There is approximately 940 gallons of water per inch of Spent Fuel Pool level.
. Table does not consider additional inventory loss if Standby Makeup pump is on (approximately 2 inches/hr).
- 5 (Step 2) IF less than 193 The operator recognizes fuel assemblies are that the core has been currently in the reactor, offloaded, and that the THEN use the following following Table applies.
tables to estimate Spent The operator locates 24 Fuel Pool boiloff rate: days since shutdown and determines the boiloff rate of 49 gpm and a level decrease rate of 3.1 inches/hour.
- NUREG 1021, Revision 9
Appendix C Page 6 of 9 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 6 (Enclosure 13) REFER TO The Operator uses the table below to Enclosure 13, and determine estimated Spent determines that an Fuel Pool radiation levels, estimated Dose rate of 100 mrem/hour will occur with a SFP Level between 12.5 and 10 feet above the Spent Fuel.
The operator calculates/approximates the water depth above the Spent Fuel yielding Dose Rates of 100 mrem/hour to be 12 feet, 2.5 inches.
(See Key on Page 8)
The operator calculates/approximates the Time that the water level will drop to the point at which the Dose Rate will exceed 100 mrem/hour to be 41.8+/-2 hours. (See Key on Page 8)
Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
- NUREG 1021, Revision 9
Appendix C Page 7 of 9 Form ES-C-i VERIFICATION OF COMPLETiON Job Performance Measure No.: 2013 Admin JPM A3 SRO
-
Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result: SAT UNSAT Examiners Signature: Date:
- NUREG 1021, Revision 9
Appendix C Page 8 of 9 Form ES-C-i VERIFICATION OF COMPLETION KEY:
Depth of Spent Fuel Pool water that will yield a Dose Rate in the Spent Fuel area of 100 mremlhour:
Dose rate at 12.5 feet 2 R/Hr x 3 2.52 x10 io m rem/hr/R/Hr = 25.2 mrem/hr Dose rate at 10 feet 1 R/Hr x 3 6.49 x10 io m rem/hr/R/Hr = 649 mrem/hr Assume Dose Rate rises linearly as level drops between 12.5 and 10 feet.
649 mrem/hr 25.2 mrem/hr /2.5 feet x 1 footJi2 inches= 20.8 mrem/hr/inch Since the rise in radiation level from level dropping one inch from 12.5 feet is 20.8 mrem, the amount in inches that the level must drop to yield a Dose rate of 100 mrem/hour can be calculated as follows:
(100 mrem/hr-25.2 mrem/hr)/20.8 mrem/hr/inch = 3.6 inches.
Consequently, the operator can estimate that the level in the Spent Fuel Pool that (Above the top of the fuel) that the water must drop to, which will result in a Dose Rate in the Spent Fuel area of 1 Rem/hour is [12.5 feet 3.5 inches] or 12 feet, 2.5 inches.
Time that the water level will drop to the point at which the Dose Rate will exceed 100 mremlhour:
[Present Level in inches Level inches when DR i0omrem/hr/3.i inches/hour
[(23ft x i2in/ft) (i2ft x l2in/ft + 2.4in)]/3.iin/hour
[(276in) (i46.4in)j/3.i in/hour = 41.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> NOTE: If the operator conservatively used the 12.5 foot level to estimate time this would be acceptable. However, if the operator used the 10 foot level, which is not conservative, this would not be acceptable
[Present Level in inches Level inches when DR 100 mrem/hrj/3.1 inches/hour
[(23ft x l2in/ft) (12.5ft x l2in/ft ]/3.1 in/hour
[(276in) (isoin)]/3.1 in/hour = 40,7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. (12.5 foot level used)
[(23ft x i2in/ft) (lOft x i2in/ft ]/3.lin/hour
[(276in) (i2Oin)j/3.1 in/hour = 50.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. (10 foot level used)
Consequently, if the acceptable range were +/-2 hour, and the operator used the conservative value (i.e. the 12.5 foot Dose Rate), rather than extrapolating between 12.5 and 10 feet, the operator would still be correct.
-
NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions:
- Due to an Earthquake, Unit 2 tripped from 100% power.
- Unit 1 was shutdown 24 days ago and a full core off-load has just been completed.
- A loss of Offsite Power has occurred, and only one EDG is running on each unit.
- The Unit 1 Spent Fuel Pool cooling has been lost.
- The crew is implementing several EPs/APs simultaneously including AP/i/A/5500/4i (Loss of Spent Fuel Pool Cooling or Level).
- The TSC is manned.
- The earthquake lowered the Unit 1 Spent Fuel Pool level to 23 feet above the top of the Spent Fuel due to wave action.
- All attempts to add makeup water to the Unit 1 Spent Fuel Pool have been unsuccessful.
- The Unit 1 Spent Fuel Pool has just started to boil.
INITIATING CUE: The OSC Coordinator has directed you to use Enclosure 5 (Spent Fuel Pool Boiloff rate) of AP/1/A15500/41 (Loss of Spent Fuel Pool Cooling or Level), and estimate how fast the Unit 1 Spent Fuel Pool level will go down as the pool boils.
THEN Use this boiloff rate and Enclosure 13 (Spent Fuel Pool Radiation Level vs. Water level Above Fuel) of AP/1/A15500/4i (Loss of Spent Fuel Pool Cooling or Level), and predict when the radiation levels in the Unit 1 Spent Fuel Pool area will be greater than 100 mrem/hour if no makeup water is added.
Assume Dose Rate rises linearly as level drops.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-i Worksheet JPMA4SRO 2013 Admin JPM A4 SRO (REV_111213)
-
NUREG 1021, Revision 9
Appendix C Page 2 of 11 Form ES-C-i Job Performance Measure Worksheet Facility: McGuire Task No.:
Task Title: Provide an urdated PAR JPM No.: 2013 Admin JPM A4
-
SRO K/A
Reference:
GKIA 2.4.44 (4.4)
Examinee: NRC Examiner:
Facility Evaluator: Date:
Method of testin:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-3.
Initial Conditions: Unit 2 is at 100% power.
A LOCA inside containment has occurred on Unit 1.
The crew implemented EP/1/A15000/ECA-1.1 (Loss of Emergency Coolant Recirc) due to multiple ECCS component failures.
A Containment Red Path and a Core Cooling Red Path have occurred.
The Emergency Coordinator declared a General Emergency per RP/0/A15700/000, Enclosure 4.1, EAL # 4.1 .G.2 (Loss of Any two Barriers AND Potential loss of the third).
An Emergency Notification Form, along with the initial PAR was sent at the appropriate time.
The following conditions exist 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the start of the event:
- The radioactive release is still on-going.
- The wind speed is 7 mph.
- The wind direction is 110.7°.
- EMF51 A and B reading is 850 R/hr.
A Radioactive Release is still in progress above normal limits.
The OAC is NOT available.
-
NUREG 1021, Revision 9
Appendix C Page 3 of ii Form ES-C-i Job Performance Measure Worksheet RP Dose Assessment has indicated that dose projections indicate that Thyroid Dose for Members of the Public in Sector M, within 1 mile of the site, will be 7 Rem. However, no PARs will be needed beyond 10 miles.
Initiating Cue: Based on the present conditions, the OSM directs you to update the PAR by completing steps 2 through 12 of Enclosure 4.4 (Offsite Protective Action Recommendation) of RP101B157001029 (Notifications to Offsite Agencies from the Control Room).
Then complete the Emergency Power Plant Emergency Notification Form.
Task Standard: The operator will determine the PAR for the current conditions and complete the Emergency Power Plant Emergency Notification Form as reflected on the provided KEY.
Required Materials: None General
References:
RPIOIAJ5700/000 (Classification of Emergency), Rev 20 RPIOIBI5700/029 (Notifications to Offsite Agencies from the Control Room), Rev 10 Handouts: Handout 1: Initial Emergency Notification Form Handout 2: RPIO/B157001029 (Notifications to Offsite Agencies from the Control Room).
Handout 3: Pre-printed Emergency Notification Form for EAL # 4.1 .G.2.
Time Critical Task: NO Validation Time: 10 minutes 2013 Admin JPM A4 SRO
- NUREG 1021, Revision 9
Appendix C Page 4 of ii Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-3.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (Enclosure 4.4, Step 1) If a The operator recognizes General Emergency is per the initial conditions this declared, determine initial step is already complete, Protective Action and proceeds.
Recommendations
- 2 (Step 2) If Wind Speed is The operator recognizes less than or equal to that Wind Speed is greater than 5 mph, and proceeds to Step 3.
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NUREG 1021, Revision 9
Appendix C Page 5 of 1 1 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 3 (Step 3) If Wind Speed is The operator uses the greater than 5 mph, Table and determines that evacuate and shelter zones the applicable Wind as shown in the table below Direction range is 90.1-based on wind direction 112.5°.
Caution 1: Once a zone is The operator observes that selected for evacuation, it Sectors B, C, L, M, N, 0 should not be removed. and R are recommended to be evacuated for a 2 mile radius, and 5 miles Caution 2: A short term downwind.
release is any release that can be projected to be 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or less in duration. The operator observes that An example would be a Sectors A, D, E, F, G, H, I, puff release. A controlled J, K, P, Q and S are release is one that can be recommended to be started or stopped at the sheltered.
licensees discretion, such as the venting of Containment for pressure The operator applies control. If a release is short Caution 1, and recognizes term and controlled, then that Sector A has previously sheltering in lieu of been evacuated, and evacuation should be although the Table considered. recommends that it be sheltered, Sector A must remain evacuated.
The operator recognizes that Caution 2 does NOT apply.
The operator recommends that Sectors A, B, C, L, M, N, 0 and R remain evacuated for a 2 mile radius, and 5 miles downwind; and that Sectors D, E, F, G, H, I, J, K, P, Q, and S remain sheltered.
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Appendix C Page 6 of 1 1 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 4 (Step 4) If notified by RP The operator recognizes Dose Assessment that dose that RP Dose Assessments projections or field indicate that thyroid dose measurements indicate that will be greater than 5 Rem, thyroid dose will be greater and recommends that KI than 5 Rem, KI use by the use by the General Public General Public must be be administered in recommended in accordance with State accordance with State Plans and Policy.
Plans and Policy.
5 (Step 5) For any other The operator recognizes Protective Action that there are no other Recommendation, Check E PARs, and proceeds to (Other), and record Step 6.
information
- 6 (Step 6) After the initial PARS are transmitted to offsite agencies, check for large fission product inventory in Containment as follows:
The operator recognizes (Step 6.1) If the OAC is that the OAC is NOT available..., available and proceeds.
(Step 6.2) If the OAC is The operator recognizes unavailable, use the that 1 EMF51 A and B following EMFs: 1 EMF51 A, readings must be used.
1EMF51B (Step 6.3) Check if The operator uses the table Containment radiation level in the Time after Shutdown exceeds the following limits column of 0-2 hours, and based on time after compares the 1 EMF51A shutdown: and B readings of 850 R/hr to the established limit of 864 R/hr determining that the Large Fission Product Inventory in Containment has NOT been met.
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Appendix C Page 7 of 11 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 7 (Step 7) If Containment The operator recognizes radiation level exceeds that the radiation levels are limits in Step 6.3 NOT exceeded, and proceeds to Step 8.
8 (Step 8) A McGuire EPZ The operator acknowledges Map is located on Page 8 of and proceeds to Step 9.
8, if it is desired to visually see zones evacuated or sheltered.
9 (Step 9) If notified by RP The operator recognizes Dose Assessment that dose that RP Dose Assessments projections or field indicate that thyroid dose measurements indicate that will be greater than 5 Rem, thyroid dose will be greater and recommends that KI than 5 Rem, KI use by the use by the General Public General Public must be be administered in recommended in accordance with State accordance with State Plans and Policy.
Plans and Policy.
10 (Step 10) On a continuing The operator acknowledges basis, evaluate specific and proceeds to Step 11.
plant conditions including:
large fission product inventory in Containment, EMF 51 A/B readings, offsite dose projections, wind speed and wind direction, field monitoring team data, and assess the need to update Protective Action Recommendations made to the states and counties in the previous notification.
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Appendix C Page 8 of 1 1 Form ES-C-i PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 11 (Step 1 1) Review dose The operator recognizes projections with the on-shift that RP Dose Assessments dose assessor (if available) has indicated that no PARs to determine if Protective beyond 10 miles will be Action Recommendations needed, and proceeds to are required beyond the 10- Step 12.
mile radius.
12 (Step 12) If Protective The operator recognizes Action Recommendations that RP Dose Assessments are required beyond 10 has indicated that no PARs miles.... beyond 10 miles will be needed, and returns the completed PAR marked up as established on the KEY.
- 13 Complete the Emergency The operator completes the Power Plant Emergency form in accordance with the Notification Form attached KEY.
(Enclosure 4.2)
Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
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Appendix C Page 9 of ii Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No: 2013 Admin JPM A4 SRO
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Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result: SAT UNSAT Examiners Signature: Date:
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NUREG 1021, Revision 9
Appendix C Page 10 of 11 Form ES-C-i VERIFICATION OF COMPLETION KEY:
Enclosure 4.2 Block How Completed Step #
2.1.1 Drill/Actual Event Operator checks A (Drill) is already shaded in.
2.1.2 Message # The operator enters 02 (or equivalent)
Note prior to Notification Time Left Blank Step 2.2 Note prior to Notification Date Left Blank Step 2.2 Note prior to Authentication # Left Blank Step 2.2 2.2 Initial/Follow-Up The operator checks B (Follow-Up).
2.3.1 Site McGuire Nuclear Site is pre-recorded 2.3.2 Confirmation Phone # (704) 875-6044 is pre-recorded 2.4.1 Emergency Classification Operator checks D (General Emergency) is already shaded in.
2.4.2 EAL # Operator checks 4.1.G.2 is already written in.
2.4.3 EAL Description Operator checks that the following statement is written in: Loss of Any Two Fission Product Barriers and Potential Loss of the Third.
2.5.1 Protective Action Operator checks in 8, C and D.
Recommendations Evacuate: A, B, C, L, M, N, 0 and R remain evacuated for a 2 mile radius, and 5 miles downwind Shelter: D, E, F, G, H, I, J, K, P, 0, and S KI Use: YES 2.6.1 Emergency Release The operator checks B (Is occurring) 2.7.3 Release Significance The operator checks C (Above Normal Limits).
2.8 Event Prognosis The operator checks B (Stable) or C Degrading.
2.9.1 Wind Direction The operator records 110.7 degrees 2.9.2 Wind Speed The operator records 7 mph 2.9.3 Precipitation The operator records None, OR leaves Blank 2.9.4 Stability Class Left Blank 2.10.1 DeclarationiTermination Operator checks A (Declaration) is shaded in.
2.10.2 Time/Date The operator records the Time, and todays date.
2.11 Affected Unit(s) The operator checks Ui ONLY.
2.12 Unit Status The operator records that Unit 1 is at 0%
power, and shutdown at T-1 0, Today. The operator records that Unit 2 is at 100%
power.
2.13 Remarks Left Blank RED denotes CrticaI information 2013 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Form ES-C-i JPM CUE SHEET Initial Conditions: Unit 2 is at 100% power.
A LOCA inside containment has occurred on Unit 1 The crew implemented EPI1IAI5000IECA-l.l (Loss of Emergency Coolant Recirc) due to multiple ECCS component failures.
A Containment Red Path and a Core Cooling Red Path have occurred.
The Emergency Coordinator declared a General Emergency per RPIOIAI5700I000, Enclosure 4.1, EAL # 4.1 .G.2 (Loss of Any two Barriers AND Potential loss of the third).
An Emergency Notification Form, along with the initial PAR was sent at the appropriate time.
The following conditions exist 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the start of the event:
- The radioactive release is still on-going.
- The wind speed is 7 mph.
- The wind direction is 110.7°.
- EMF51 A and B reading is 850 R/hr.
A Radioactive Release is still in progress above normal limits.
The OAC is NOT available.
RP Dose Assessment has indicated that dose projections indicate that Thyroid Dose for Members of the Public in Sector M, within 1 mile of the site, will be 7 Rem. However, no PARs will be needed beyond 10 miles.
INITIATING CUE: Based on the present conditions, the OSM directs you to update the PAR by completing steps 2 through 12 of Enclosure 4.4 (Offsite Protective Action Recommendation) of RP/0/B/5700/029 (Notifications to Offsite Agencies from the Control Room).
Then complete the Emergency Power Plant Emergency Notification Form.
NUREG 1021, Revision 9