ML22186A133
| ML22186A133 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/29/2017 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | FirstEnergy Nuclear Operating Co |
| Baker R | |
| Shared Package | |
| ML17068A444 | List: |
| References | |
| Download: ML22186A133 (91) | |
Text
Davis-Besse NRC Exam 2018 Admin JPM RO A1.1
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet NRC JPM RO A1.1 Page 1 of 10 Facility: Davis-Besse Task No:
115-016-01-0100 Task
Title:
Manually Calculate a Shutdown Value K/A
Reference:
2.1.37 (4.3)
Job Performance Measure No: RO A1.1 (JPM 259)
Examinee:
NRC Examiner:
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.
Initial Conditions:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Task Standard:
Manually Calculate a Shutdown Value between -6.5 and -7.5 %K/K Required Materials:
DB-NE-06202, Reactivity Balance Calculations Rev 10 DB-NE-06201, Reactor Operator Curve Book Procedure Rev 15 Straight edge, Calculator General
References:
None Initiating Cue:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Time Critical Task:
No Alternate Path:
No Validation Time:
29 minutes
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.1 Page 2 of 10 EVALUATOR COPY The plant is in Mode 3 with a reactor startup in progress.
All systems are in their normal lineup.
The START program is not available.
The following conditions exist:
Burnup: 60 EFPD Xenon:
No Xenon Boron Conc: 1875 ppmB Tave: 520°F APSRs at 29.5%
Control Rod Group 1 at 100%
The Reactor Engineer reports values for the following:
Transient poison worth is -1.5% K/K Correction factor for boron 10 depletion is 0.96 Reactivity Anomaly is zero.
INITIATING CUES:
The Unit Supervisor directs you to manually calculate a shutdown value per DB-NE-06202, Reactivity Balance Calculations, and DB-NE-06201, Reactor Operator Curve Book.
(Provide examinee a copy of DB-NE-06202 and DB-NE-06201)
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.1 Page 3 of 10 CANDIDATE COPY The plant is in Mode 3 with a reactor startup in progress.
All systems are in their normal lineup.
The START program is not available.
The following conditions exist:
Burnup: 60 EFPD Xenon:
No Xenon Boron Conc: 1875 ppmB Tave: 520°F APSRs at 29.5%
Control Rod Group 1 at 100%
The Reactor Engineer reports values for the following:
Transient poison worth is -1.5% K/K Correction factor for boron 10 depletion is 0.96 Reactivity Anomaly is zero.
INITIATING CUES:
The Unit Supervisor directs you to manually calculate a shutdown value per DB-NE-06202, Reactivity Balance Calculations, and DB-NE-06201, Reactor Operator Curve Book.
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.1 Page 4 of 10 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT required unless denoted in the "Comments".
START TIME:
- 1.
PERFORMANCE STEP: Locate correct procedure section.
STANDARD:
Identifies Section 9 and Attachment 5 of DB-NE-06202, Reactivity Balance Calculations, as the correct section/attachment and enters the data from the initial conditions.
CUE:
None SAT UNSAT
- 2.
PERFORMANCE STEP: Determine reactivity worth of the fuel.
........C........
STANDARD: From Figure 2, determine value of 12.1 to 12.2 %K/K and enter this value on Attachment 5.
COMMENT: Actual value is 12.13 %K/K.
CUE:
None.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.1 Page 5 of 10
- 3.
PERFORMANCE STEP: Determine the reactivity worth due to boron.
........C........
STANDARD: From Figure 3, determine value Boron Worth %K/K for boron based on B10 correction factor of 0.96.
Multiply RCS boron by correction factor and by uncertainty, 1875 x 0.96 x 0.99 = 1782 ppm B (ROCB)
From Figure 4 determine value of 0.997 to 0.999 for the BCF.
From Figure 3 determine (BBOL). Value should be between -12.15 and
-12.25%K/K.
Multiply these two values to obtain between -12.11 and -12.24 %K/K.
COMMENT:
Actual values: Boron is -12.22 %K/K, BCF is 0.9978 and total boron reactivity worth is -12.193 %K/K.
CUE:
None.
SAT UNSAT
- 4.
PERFORMANCE STEP: Utilize the reactivity worth due to transient poisons.
STANDARD: Determine from initial conditions (-1.5 %K/K).
CUE:
None.
SAT UNSAT
- 5.
PERFORMANCE STEP: Determine the reactivity worth due to excess Pu-239.
........C........
STANDARD: From Figure 20B, determine value of 0.1465 to 0.1475 %K/K for maximum excess Pu-239 worth.
COMMENT: Actual value: 0.1469 %K/K.
CUE:
None.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.1 Page 6 of 10
- 6.
PERFORMANCE STEP: Determine the reactivity worth due to temperature.
........C........
STANDARD: From Figure 12, determine value of -0.0075 to -0.0085 %K/K/°F for temperature coefficient.
T = -12 Multiply these two values to obtain between 0.09 and 0.102 %K/K.
COMMENT: Actual values: temperature coefficient is -0.0078 (%K/K)/°F; T is -12°F; temperature reactivity worth is 0.0936 %K/K.
CUE:
None.
SAT UNSAT
- 7.
PERFORMANCE: STEP: Determine Safety Rod worth.
........C........
STANDARD: From Table 1, determine Safety worth of -2.624 %K/K.
COMMENT: Actual value is -2.624 %K/K.
CUE:
None.
SAT UNSAT
- 8.
PERFORMANCE STEP: Determine Control Rod 5-7 worth.
........C........
STANDARD: From Figure 9A, determine Regulating Rod worth of -2.8 to -2.95 %K/K.
COMMENT: Actual value is -2.877 %K/K.
CUE:
None.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.1 Page 7 of 10
- 9.
PERFORMANCE STEP: Determine Total Rod worth.
........C........
STANDARD: Add Safety Rod worth and Control Rod worth. Range from -5.424 to
-5.594%K/K.
COMMENT: Actual value is -5.501%K/K.
CUE:
None.
SAT UNSAT
- 10. PERFORMANCE STEP: Determine APSR worth.
........C........
STANDARD: From Figure 11A, determine APSR worth of -0.084 to -0.094 %K/K.
COMMENT: Actual value is -0.085 %K/K.
CUE:
None.
SAT UNSAT
- 11. PERFORMANCE STEP: Determine reactivity anomaly worth.
STANDARD: Determine zero from Initial Conditions.
CUE:
None.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.1 Page 8 of 10
- 12.
PERFORMANCE STEP: Determine the value for shutdown value.
........C........
STANDARD: Determine that shutdown value is a value between -6.50 and -7.50%K/K.
COMMENT:
Actual value is -6.9085 %K/K.
CUE:
None.
SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by examinee). See next page for Answer Key.
END TIME: ____________
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.1 Page 9 of 10 ATTACHMENT 5:
SHUTDOWN VALUE (SDV) CALCULATION WITH Tave 500°F - SECTION 9.0 Page 1 of 2 ANSWER KEY EFPD=__60____
CF(B10) =_0.96__
B(RCS)=_1875_ppmB Tave=__520_°F Rod Index=__0___RI APSR=_29.5__%wd Data: Date_today_ Time__now_
Is Control Rod Group 1 withdrawn? _____No ____Yes Use the critical reference condition for all data.
This calculation is valid only with the reactor subcritical and Tave 500°F.
If a stuck rod exists contact a Reactor Engineer.
Shutdown Value (SDV)
_12.13__+__-12.193__+__-1.5___+__0.1469_+ _ 0.0936__+ __-5.501___+_-0.085__+___0_ = _-6.9085%k/k (fuel) (boron) (tp) (Pu-max) (temp) (CRG 1-7) (APSR) (anom) SDV Where:
(fuel) is fuel Worth from Figure 2 based on EFPD (boron) is Boron Worth = __-12.22____ x __0.9978___ = __-12.193___%k/k (BBOL) CF(FBU) (boron)
Where:
(BBOL) is Boron Worth at Beginning of Life from Figure 3 based on B(ROCB)
(Critical curve)
__1875___ x __0.96___ x (1 -.01) = __1782___ppmB B(RCS) CF(B10) B(ROCB)
Where:.01 is the Boron Concentration Measurement Uncertainty (1 -.01) is the Boron Concentration Measurement Correction Factor CF(FBU) is Correction Factor for Fuel Burnup from Figure 4 based on EFPD (Critical curve)
(tp) is Transient Poison Worth from START program for time of data (Pu-max) is Maximum Excess Pu-239 Worth from Figure 20B based on EFPD (temp) is Temperature Reactivity = _-0.0078__ x __-12___ = _0.0936___%k/k T T (temp)
Where:
T is Temperature Coefficient from Figure 12 based on EFPD and B(ROCB)
T = Tave - 532°F
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.1 Page 10 of 10 ATTACHMENT 5:
SHUTDOWN VALUE (SDV) CALCULATION WITH Tave 500°F -
SECTION 9.0 Page 2 of 2 ANSWER KEY (CRG 1-7) is Control Rod Groups 1-7 Worth = ___-2.624___ + ___-2.877___ = __-5.501____%k/k (CRG 1-4) (CRG 5-7) (CRG 1-7)
Where:
(CRG 1-4) is Safety Rod Worth from Table 1 of ROCB based on Control Rod Group 1 position (CRG 5-7) is Control Rod Groups 5-7 Worth from Figure 9* based on EFPD, (tp),
and Rod Index (APSR) is APSR Worth from Figure 11A based on EFPD and APSR position (anom) is Reactivity Worth of HFP Anomaly from the Reactor Operating Guidance (For conservatism, a value of 0 may be used in place of a negative HFP anomaly for calculations of Shutdown Value. See Step 4.2.8.)
- Use Figure 9A if the absolute value of (tp) < 2.0%k/k.
Use Figure 9B if the absolute value of (tp) 2.0%k/k.
Calculated by Candidate Date Today Time Now Checked by Date
Davis-Besse NRC Exam 2018 Admin JPM RO A1.2
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet NRC JPM RO A1.2 r1 Page 1 of 5 Facility: Davis-Besse Task No:
115-033-01-0100 Task
Title:
Perform 1/M Plot K/A
Reference:
2.1.43 (4.1)
Job Performance Measure No: RO A1.2 (JPM 276)
Examinee:
NRC Examiner:
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.
Initial Conditions:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Task Standard:
Perform the calculations and 1/M Plot and recommend no further rod withdrawal Required Materials:
DB-OP-06912, Approach to Criticality Rev 19 Straight edge, Calculator General
References:
None Initiating Cue:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Time Critical Task:
No Alternate Path:
No Validation Time:
15 minutes
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.2 r1 Page 2 of 5 EVALUATOR COPY INITIAL CONDITIONS:
The Plant is in Mode 2.
A reactor startup is in progress.
Group 1-4 rods are withdrawn Regulating Rods are pulled to 100 index INITIATION CUE:
The Shift Manager directs you to perform a peer check of the Reactor Engineer performing the 1/M Plot by performing a separate 1/M Plot using the Source Range count rate data provided on of DB-OP-06912, Approach to Criticality. Compare the 1/M data with the predicted ECP data and make a recommendation for further rod withdrawal.
Document recommendation below.
(Hand Candidate a copy of DB-OP-06912, Approach to Criticality, Calculator and a Straight Edge)
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.2 r1 Page 3 of 5 CANDIDATE COPY INITIAL CONDITIONS:
The Plant is in Mode 2.
A reactor startup is in progress.
Group 1-4 rods are withdrawn Regulating Rods are pulled to 100 index INITIATION CUE:
The Shift Manager directs you to perform a peer check of the Reactor Engineer performing the 1/M Plot by performing a separate 1/M Plot using the Source Range count rate data provided on of DB-OP-06912, Approach to Criticality. Compare the 1/M data with the predicted ECP data and make a recommendation for further rod withdrawal.
Document recommendation below:
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.2 r1 Page 4 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT required unless denoted in the "Comments".
START TIME: _______
- 1.
PERFORMANCE STEP: Refer to data on Attachment 1 STANDARD: Refer to data on Attachment 1 for count rate data CUE: None SAT UNSAT
- 2.
PERFORMANCE STEP:
_____C____
Plots data SR data on 1/M Plot STANDARD: Evaluates count rate data on attachment 1 and plots this data on the 1/M Plot for 25, 50, 75, and 100 Rod Index COMMENTS: See attached answer key for 1/M plot values CUE: None SAT UNSAT
- 3.
PERFORMANCE STEP:
_____C____
Evaluate 1/M Plot data STANDARD: Determines that the 1/M Plot predicts criticality before reaching the Lower Rod Index limit of the ECP listed as 121.7 (- 0.5%k/k)
CUE: None - Verify that the candidate makes the recommendation for no further rod withdrawal or ask a follow-up question.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A1.2 r1 Page 5 of 5
- 4.
PERFORMANCE STEP:
_____C____
Notify SRO that the 1/M Plot predicts criticality before reaching the Lower Rod Index limit of the ECP and recommend no further rod withdrawal.
STANDARD: Notify SRO that the 1/M Plot predicts criticality before reaching the Lower Rod Index limit of the ECP and recommend no further rod withdrawal.
CUE: None SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by examinee). See next page for Answer Key.
END TIME: ____________
Davis-Besse NRC Exam 2018 Admin JPM RO-A2
Appendix C Rev 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO-A2 r1 1 of 5 Facility: Davis-Besse Task No:
119-016-03-0100 Task
Title:
Review a safety clearance for CC210 with eSOMS unavailable K/A
Reference:
2.2.13 (4.1)
Job Performance Measure No: RO-A2 Examinee:
NRC Examiner:
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.
Initial Conditions:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Task Standard:
Review clearance and identify errors Required Materials:
NOP-OP-1001, Clearance/Tagging Program, Rev 24 NOBP-OP-1001, Manual Clearance Generation, Rev 4 Forms NOP-OP-1001-07, Rev 5 and NOP-OP-1001-09, Rev 2 Operations Schematic, OS-21, SH2 (Component Cooling Water System)
General
References:
None Initiating Cue:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Time Critical Task: No Alternate Path: No Validation Time: 16 minutes
Appendix C Rev 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO-A2 r1 2 of 5 EXAMINER COPY INITIAL CONDITIONS:
The plant is currently operating at 100%.
eSOMS is currently out of service and return to service is indeterminate.
CC211, CCW to Make-Up Pump Lube Oil Cooler 2 Supply Header Drain, is leaking and requires replacement.
INITIATION CUE:
A manual clearance has been generated. The Shift Manager directs you review the copy of manual clearance per NOBP-OP-1001, step 4.1.6 for tagging points (4.1.6.1), tag type (4.1.6.5),
placement configuration (4.1.6.6) and placement sequence (4.1.6.7) only. An SRO will complete the formal review and has the original clearance package including preparation checklist and prepared tags. Review of the tags is not required.
Return to Shift Manger with concurrence or list any deficiencies identified below on this sheet.
(Provide Candidate a copy of NOP-OP-1001 Clearance Tagging Program, NOBP-OP-1001, Manual Clearance Generation, and copies of the Clearance Package Form NOP-OP-1001-07, Form NOP-OP-1001-09 and OS-21 SH 2, Component Cooling Water)
Appendix C Rev 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO-A2 r1 3 of 5 CANDIDATE COPY INITIAL CONDITIONS:
The plant is currently operating at 100%.
eSOMS is currently out of service and return to service is indeterminate.
CC211, CCW to Make-Up Pump Lube Oil Cooler 2 Supply Header Drain, is leaking and requires replacement.
INITIATION CUE:
A manual clearance has been generated. The Shift Manager directs you review the copy of manual clearance per NOBP-OP-1001, step 4.1.6 for tagging points (4.1.6.1), tag type (4.1.6.5),
placement configuration (4.1.6.6) and placement sequence (4.1.6.7) only. An SRO will complete the formal review and has the original clearance package including preparation checklist and prepared tags. Review of the tags is not required.
Return to Shift Manger with concurrence or list any deficiencies identified below on this sheet.
Appendix C Rev 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO-A2 r1 4 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT critical unless denoted in the "Comments".
START TIME: _______
- 1.
PERFORMANCE STEP: Review provided material STANDARD: Reviews provided material COMMENT: Step sequence not required for this JPM CUE:
(Provide Candidate a copy of NOP-OP-1001 Clearance Tagging Program, NOBP-OP-1001, Manual Clearance Generation, and copies of the Clearance Package Form NOP-OP-1001-07, Form NOP-OP-1001-09 and OS-21 SH 2, Component Cooling Water)
SAT UNSAT
- 2.
PERFORMANCE STEP: Review Manual Clearance Tag List, NOP-OP-1001-9 STANDARD: Identifies Makeup Pump 2 should be cleared since lube oil cooling will be isolated COMMENT: Step sequence not required for this JPM It is acceptable if the candidate identifies that the makeup pump lube oil cooling is isolated and provides feedback to the SM that per system procedure guidance a makeup pump may be in service for up to one hour without CCW cooling flow.
CUE:
None SAT UNSAT
- 3.
PERFORMANCE STEP: Review Manual Clearance Tag List, NOP-OP-1001-9
........C........
STANDARD: Identifies CC211 hang sequence is out of order and should not be opened until boundary is established COMMENT:
CUE:
None SAT UNSAT
Appendix C Rev 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO-A2 r1 5 of 5
- 4.
PERFORMANCE STEP: Review Manual Clearance Tag List, NOP-OP-1001-9
........C........
STANDARD: Identifies CC211 should not have a tag since it will be removed from system COMMENT: Step sequence not required for this JPM CUE:
None SAT UNSAT
- 5.
PERFORMANCE STEP: Review Manual Clearance Tag List, NOP-OP-1001-9
........C........
STANDARD: Identifies CC221 is incorrect and should be CC212 COMMENT: Step sequence not required for this JPM CUE:
None SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by the examinee)
END TIME
Manual Clearance Tag List NOP-OP-1001-09 Rev. 02 Sheet 1
Of 1 CLEARANCE No.
DB 016-01-001 Equipment ID Equipment Description Equipment Location Tag #
Tag Type Placement Configuration Hang order 1st Verify 2nd Verify Restoration Configuration Clear Order 1st Remove 2nd Remove Notes CC128 MUP 2 CCW Inlet Stop Check to Lube Oil Clr MUP Pmp RM 1
D CLOSED 1
OPEN 2
CC263 CCW Essential Line 2 to MUP 2 Supply Stop Check DH Cooler Rm 2
D CLOSED 1
OPEN 2
CC130 MUP 2 CCW Outlet from Lube Oil Clr MUP Pmp RM 3
D CLOSED 2
Throttled 3
CC211 CCW to MUP Lube Oil Clr 2 Supply Hdr Drain MUP Pmp RM 4
D OPEN 2
CLOSED 1
CC221 CCW to MUP Lube Oil Clr 2 Supply Hdr Vent MUP Pmp RM 5
D OPEN 3
CLOSED 1
CC262 CCW Essential Line 2 to MUP 2 Supply Header Drain DH Cooler Rm 6
D OPEN 3
CLOSED 1
MANUAL CLEARANCE COVER SHEET NOP-OP-1001-07 Rev. 05 Manual Clearance DB-017-01 -001 Date Today / /
Time Now Equipment ID / Asset Number :
CC211
/ CCW to Make-Up Pump Lube Oil Cooler 2 Supply Header Drain Description / Reason Replace CC211, CCW to Make-Up Pump Lube Oil Cooler 2 Supply Header Drain Placement Notes OS-021 SH2 Refer to DB-OP-06006, Section 3.6 for pump swap Isolate/Vent and drain work area Cautions Contact RP about draining radioactive fluids. CC211 will drain the CCW header for the work that needs to be done.
Monitor CCW Surge Tank level.
Completion Notes Consult chemistry for makeup water chemical addition requirements.
Fill and vent as directed by Field Supervisor Order Number FLOC Description 200456789 CC211 CCW to Make-Up Pump Lube Oil Cooler 2 Supply Header Drain Clearance Holder Acceptance
/
Print/Sign Date Notes Clearance Holder Release
/
Print/Sign Date Status Name (Print / Sign)
Date / Time Prepared By Bob Plant/ Bob Plant Today/
Reviewed By
/
/
Approved by
/
/
Issued for Work by
/
/
Removal Authorized by
/
/
Clearance Closed by
/
/
DT DT DT DT DT DT
ANSWER KEY Manual Clearance Tag List NOP-OP-1001-09 Rev. 02 Sheet 1
Of 1 CLEARANCE No.
DB 016-01-001 Equipment ID Equipment Description Equipment Location Tag #
Tag Type Placement Configuration Hang order 1st Verify 2nd Verify Restoration Configuration Clear Order 1st Remove 2nd Remove Notes CC128 MUP 2 CCW Inlet Stop Check to Lube Oil Clr MUP Pmp RM 1
D CLOSED 1
OPEN 2
CC263 CCW Essential Line 2 to MUP 2 Supply Stop Check DH Cooler Rm 2
D CLOSED 1
OPEN 2
CC130 MUP 2 CCW Outlet from Lube Oil Clr MUP Pmp RM 3
D CLOSED 2
Throttled 3
CC211 CCW to MUP Lube Oil Clr 2 Supply Hdr Drain MUP Pmp RM 4
NT OPEN 3
CLOSED 1
CC212 CCW to MUP Lube Oil Clr 2 Supply Hdr Vent MUP Pmp RM 5
D OPEN 3
CLOSED 1
CC262 CCW Essential Line 2 to MUP 2 Supply Header Drain DH Cooler Rm 6
D OPEN 3
CLOSED 1
Davis-Besse NRC Exam 2018 Admin JPM RO A3
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A3 r1 Page 1 of 5 Facility: Davis-Besse Task No:
115-035-01-0100 Task
Title:
Stay Time Calculation K/A
Reference:
2.3.7 (3.5)
Job Performance Measure No: RO A3 (JPM New)
Examinee:
NRC Examiner:
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.
Initial Conditions:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Task Standard:
Determine the total dose received and the time required to receive an EAD Dose Alarm.
Required Materials:
RAD Pro Survey Map DB-M-2018-TRG Calculator General
References:
None Initiating Cue:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Time Critical Task:
No Alternate Path:
No Validation Time:
20 minutes
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A3 r1 Page 2 of 5 EVALUATOR COPY INITIAL CONDITIONS:
The plant is in procedure DB-OP-02527 Loss of Decay Heat Removal Refer to the Decay Heat Pump area Rad Pro Survey Map.
You are to stage yourself inside the radiologically controlled area where you can minimize your dose while awaiting directions. You are to remain in an area identified on the survey map with the lowest possible dose during the wait period.
Your task will be to vent Decay Heat Pump 2 using vent valve DH56, DH PUMP 2 CASING VENT Your RWP has the following limits:
o Dose Rate Alarm = 75 mrem/hr o Dose Alarm = 40 mrem Aux Building 545 ECCS Room 2 is posted as a Radiation Area Time Line:
0800 - You enter the Aux Building 545 ECCS Room 2 room 0830 - You are directed to start venting Decay Heat Pump 2 0855 - Venting complete. You immediately exit the room and report back to the Control Room.
INITIATING CUE:
Based upon the above timeline, the information from your RWP and the Aux Building 545 ECCS Room 2 survey map:
- 1.
Determine the total amount of dose that was received from room entry to exit. Use the highest potential dose rate in the area of the pump in determining your dose for the actual venting portion of the entry.
- 2.
Assuming no dose was received until you entered the Aux Building 545 ECCS Room 2, determine the MAXIMUM time (including the wait time) you could take to vent the Decay Heat Pump 2 until you would receive an EAD Dose Alarm.
You do not have to include any dose received while transiting from the waiting area through the room to and from the pump.
(Provide examinee a copy of Survey Map DB-M-2018-TRG)
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A3 r1 Page 3 of 5 CANDIDATE COPY INITIAL CONDITIONS:
The plant is in procedure DB-OP-02527 Loss of Decay Heat Removal Refer to the Decay Heat Pump area Rad Pro Survey Map.
You are to stage yourself inside the radiologically controlled area where you can minimize your dose while awaiting directions. You are to remain in an area identified on the survey map with the lowest possible dose during the wait period.
Your task will be to vent Decay Heat Pump 2 using vent valve DH56, DH PUMP 2 CASING VENT Your RWP has the following limits:
o Dose Rate Alarm = 75 mrem/hr o Dose Alarm = 40 mrem Aux Building 545 ECCS Room 2 is posted as a Radiation Area Time Line:
0800 - You enter the Aux Building 545 ECCS Room 2 room 0830 - You are directed to start venting Decay Heat Pump 2 0855 - Venting complete. You immediately exit the room and report back to the Control Room.
INITIATING CUE:
Based upon the above timeline, the information from your RWP and the Aux Building 545 ECCS Room 2 survey map:
- 1.
Determine the total amount of dose that was received from room entry to exit. Use the highest potential dose rate in the area of the pump in determining your dose for the actual venting portion of the entry.
- 2.
Assuming no dose was received until you entered the Aux Building 545 ECCS Room 2, determine the MAXIMUM time (including the wait time) you could take to vent the Decay Heat Pump 2 until you would receive an EAD Dose Alarm.
You do not have to include any dose received while transiting from the waiting area through the room to and from the pump.
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A3 r1 Page 4 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT required unless denoted in the "Comments".
START TIME:
- 1.
PERFORMANCE STEP: Determine the dose that will be received while waiting in the lowest dose waiting area in the radiologically controlled area.
STANDARD:
Calculates the dose received for the duration of the time in the low dose area.
Based on a 30 minute wait at the area with a dose rate of 5 mrem/hr:
Low Dose Wait Area Dose: 5 mrem/hr X 0.5 hr = 2.5 mrem COMMENT: Acceptable range is 2.4 to 2.6 mrem CUE:
None SAT UNSAT
- 2.
PERFORMANCE STEP: Determine the dose that will be received while venting the pump.
C STANDARD:
Calculates the dose received for the duration of the time venting the pump. Per the Survey Map location DR10 has the highest dose at 50 mrem/hr.
Based on a 25 minute task duration at the pump with a dose rate of 50 mrem/hr:
Pump Venting Dose: 50 mrem/hr X (25/60) hr = 20.83 mrem COMMENT: Acceptable range is 20 to 21 mrem.
CUE:
None SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM RO A3 r1 Page 5 of 5
- 3. PERFORMANCE STEP: Determine the Total dose that will be received while in the area performing the task.
C STANDARD:
Calculate the dose received for the duration of the task.
TOTAL Dose: 2.5 mrem + 20.83 mrem = 23.3 mrem COMMENT: Acceptable range is 22.4 to 23.6 mrem CUE:
None SAT UNSAT
- 4.
PERFORMANCE STEP: Determine the maximum time to complete the task before reaching the EAD Dose Alarm setpoint.
C STANDARD:
Calculates the maximum time until Dose Alarm.
The RWP Dose Alarm setpoint is 40 mrem.
Subtract the low dose waiting area dose from the total allowed:
40 mrem - 2.5 mrem = 37.5 mrem Vent Time Dose Rate is 50 mrem / hr:
37.5 mrem/ 50 mrem / hr = 0.75 hrs or 45 minutes TOTAL Time is 45 minutes COMMENT: Acceptable range is 44 to 46 minutes.
CUE:
None SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by examinee)
END TIME: ____________
FOR TRAINING USE ONLY VSDS Standard Map Survey Report Survey DB-M-2018-TRG
FOR TRAINING USE ONLY VSDS Standard Map Survey Report Survey DB-M-2018-TRG Cooler 1-2 DH HPI Cooler 1-1 CS Sump ALARA RA Catwalk CA DR 2 15 DR 1 12 CA DR 10 50 DR 9 22 DR 3 20 DR 4 60 DR 5 70 DR 7 10 DR 6 20 DR 8 10 DR 12 5
4 1
2 3
5 7
6 8
DR 11 HS* 540 11
FOR TRAINING USE ONLY VSDS Standard Map Survey Report Survey DB-M-2018-TRG Type Inst.
Value Units Position Notes 1
DR N/A 12 mrem/hr 2
DR N/A 15 mrem/hr 3
DR N/A 20 mrem/hr 4
DR N/A 60 mrem/hr 5
DR N/A 70 mrem/hr 6
DR N/A 20 mrem/hr 7
DR N/A 10 mrem/hr 8
DR N/A 10 mrem/hr 9
DR N/A 22 mrem/hr 10 DR N/A 50 mrem/hr 11 DR HS N/A HS
- 540 mrem/hr Hot Spot # 1 Elbow, placard reads *540 /11/@ 30 CM N/A
+11 mrem/hr 12 DR N/A 5
mrem/hr Type Inst.
Value Units Position Notes 1
Smear N/A
/ 22 DPM/100 cm2 floor N/A
< MDA DPM/100 cm2 2
Smear N/A
/ 47 DPM/100 cm2 floor N/A
< MDA DPM/100 cm2 3
Smear N/A
/ 62 DPM/100 cm2 floor N/A
< MDA DPM/100 cm2 4
Smear N/A
/ <MDA DPM/100 cm2 floor N/A
< MDA DPM/100 cm2 5
Smear N/A
/ 38 DPM/100 cm2 floor N/A
< MDA DPM/100 cm2 6
Smear N/A
/ 38 DPM/100 cm2 floor N/A
< MDA DPM/100 cm2 7
Smear N/A
/ 587 DPM/100 cm2 floor N/A
< MDA DPM/100 cm2 8
Smear N/A
/ MDA DPM/100 cm2 floor N/A
< MDA DPM/100 cm2
Davis-Besse NRC Exam 2018 Admin JPM SRO A1.1
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet NRC JPM SRO A1.1 Page 1 of 12 Facility: Davis-Besse Task No:
333-014-01-0300 Task
Title:
Review a Calculated Shutdown Value K/A
Reference:
2.1.37 (4.6)
Job Performance Measure No: SRO A1.1 (JPM 262)
Examinee:
NRC Examiner:
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.
Initial Conditions:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Task Standard:
Reviews and corrects the Shutdown Value calculation to between -1.55%K/K and -1.65%K/K, identify errors in the shutdown value calculation.
Required Materials:
DB-NE-06202, Reactivity Balance Calculations Rev 10 DB-NE-06201, Reactor Operator Curve Book Procedure Rev 15 Straight edge, Calculator General
References:
None Initiating Cue:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Time Critical Task:
No Alternate Path:
No Validation Time:
29 minutes
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 2 of 12 EXAMINER COPY INITIAL CONDITIONS:
The plant is in Mode 3 with a reactor startup in progress.
All systems are in their normal lineup.
The START program is not available.
The following conditions exist:
Burnup:
60 EFPD Xenon:
1035 ppmB Tave:
520°F APSRs at 29.5%
Control Rod Group 1 100%
The Reactor Engineer reports values for the following:
Transient poisons is -1.5% K/K Correction factor for Boron 10 depletion is 0.96 Reactivity Anomaly is zero.
INITIATING CUES:
As the Unit Supervisor review a shutdown value calculation per DB-NE-06202, Reactivity Balance Calculations, and DB-NE-06201, Reactor Operator Curve Book. Identify any discrepancies below.
(Provide examinee completed SDV calculation and DB-NE-06202 and DB-NE-06201)
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 3 of 12 CANDIDATE COPY INITIAL CONDITIONS:
The plant is in Mode 3 with a reactor startup in progress.
All systems are in their normal lineup.
The START program is not available.
The following conditions exist:
Burnup:
60 EFPD Xenon:
1035 ppmB Tave:
520°F APSRs at 29.5%
Control Rod Group 1 100%
The Reactor Engineer reports values for the following:
Transient poisons is -1.5% K/K Correction factor for Boron 10 depletion is 0.96 Reactivity Anomaly is zero.
INITIATING CUES:
As the Unit Supervisor review a shutdown value calculation per DB-NE-06202, Reactivity Balance Calculations, and DB-NE-06201, Reactor Operator Curve Book. Identify any discrepancies below.
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 4 of 12 ATTACHMENT 5:
SHUTDOWN VALUE (SDV) CALCULATION WITH Tave 500°F - SECTION 9.0 Page 1 of 2 EFPD=__60____
CF(B10)=_0.96__
B(RCS)=_1035_ppmB Tave=__520_°F Rod Index=__0___RI APSR=_29.5__%wd Data: Date_today_ Time__now_
Is Control Rod Group 1 withdrawn? _____No _____Yes Use the critical reference condition for all data.
This calculation is valid only with the reactor subcritical and Tave 500°F.
If a stuck rod exists contact a Reactor Engineer.
Shutdown Value (SDV)
_12.13__+__-6.89__+__-1.5___+__0.1469_+ _-0.1776__+ __-6.127___+_-0.085__+___0_ = _-2.5027%k/k (fuel) (boron) (tp) (Pu-max) (temp) (CRG 1-7) (APSR) (anom) SDV Where:
(fuel) is fuel Worth from Figure 2 based on EFPD (boron) is Boron Worth = __-6.9____ x __0.998___ = __-6.89___%k/k (BBOL) CF(FBU) (boron)
Where:
(BBOL) is Boron Worth at Beginning of Life from Figure 3 based on B(ROCB)
(Critical curve)
__1035___ x __0.96___ x (1 -.01) = __ 984___ppmB B(RCS) CF(B10) B(ROCB)
Where:.01 is the Boron Concentration Measurement Uncertainty (1 -.01) is the Boron Concentration Measurement Correction Factor CF(FBU) is Correction Factor for Fuel Burnup from Figure 4 based on EFPD (Critical curve)
(tp) is Transient Poison Worth from START program for time of data (Pu-max) is Maximum Excess Pu-239 Worth from Figure 20B based on EFPD (temp) is Temperature Reactivity = _-0.0148__ x __-12___ = _ 0.1776___%k/k T T (temp)
Where:
T is Temperature Coefficient from Figure 12 based on EFPD and B(ROCB)
T = Tave - 532°F
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 5 of 12 ATTACHMENT 5:
SHUTDOWN VALUE (SDV) CALCULATION WITH Tave 500°F -
SECTION 9.0 Page 2 of 2 (CRG 1-7) is Control Rod Groups 1-7 Worth = ___-3.25___ + ___-2.877___ = __-6.127____%k/k (CRG 1-4) (CRG 5-7) (CRG 1-7)
Where:
(CRG 1-4) is Safety Rod Worth from Table 1 of ROCB based on Control Rod Group 1 position (CRG 5-7) is Control Rod Groups 5-7 Worth from Figure 9* based on EFPD, (tp),
and Rod Index (APSR) is APSR Worth from Figure 11A based on EFPD and APSR position (anom) is Reactivity Worth of HFP Anomaly from the Reactor Operating Guidance (For conservatism, a value of 0 may be used in place of a negative HFP anomaly for calculations of Shutdown Value. See Step 4.2.8.)
- Use Figure 9A if the absolute value of (tp) < 2.0%k/k.
Use Figure 9B if the absolute value of (tp) 2.0%k/k.
Calculated by Candidate Date Today Time Now Checked by Date
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 6 of 12 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT required unless denoted in the "Comments".
START TIME:
- 1.
PERFORMANCE STEP: Locate correct procedure section.
STANDARD:
Identifies Section 9 or Attachment 5 of DB-NE-06202, Reactivity Balance Calculations, as the correct section and reviews the data from the initial conditions.
CUE:
None SAT UNSAT
- 2.
PERFORMANCE STEP: Determine reactivity worth of the fuel.
........C........
STANDARD: From Figure 2, determine value of 12.1 to 12.2 %K/K and enter this value on Attachment 5.
COMMENT: Actual value is 12.13 %K/K.
CUE:
None.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 7 of 12
- 3.
PERFORMANCE STEP: Determine the reactivity worth due to boron.
........C........
STANDARD: From Figure 3, determine value Boron Worth %K/K for boron based on B10 correction factor of 0.96.
Multiply RCS boron by correction factor and by uncertainty, 1035 x 0.96 x 0.99 = 984 ppmB B(ROCB)
From Figure 4 determine value of 0.997 to 0.999 for the BCF.
From Figure 3 determine (BBOL). Value should be between -6.8 and
-7.0%K/K.
Multiply these two values to obtain between -6.78 and -6.99 %K/K.
COMMENT:
Actual values: Boron is -6.9 %K/K, BCF is 0.998 and total boron reactivity worth is -6.89 %K/K.
CUE:
None.
SAT UNSAT
- 4.
PERFORMANCE STEP: Utilize the reactivity worth due to transient poisons.
STANDARD: Determine from initial conditions (-1.5 %K/K).
CUE:
None.
SAT UNSAT
- 5.
PERFORMANCE STEP: Determine the reactivity worth due to excess Pu-239.
........C........
STANDARD: From Figure 20B, determine value of 0.1465 to 0.1475 %K/K for maximum excess Pu-239 worth.
COMMENT: Actual value: 0.1469 %K/K.
CUE:
None.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 8 of 12
- 6.
PERFORMANCE STEP: Determine the reactivity worth due to temperature.
........C........
STANDARD: From Figure 12, determine value of -0.0145 to -0.0155 %K/K/°F for temperature coefficient.
T = -12 Multiply these two values to obtain between 0.1740 and 0.1860 %K/K.
COMMENT: Actual values: temperature coefficient is -0.0148 (%K/K)/°F; T is -12°F; temperature reactivity worth is 0.1776 %K/K.
INCORRECT VALUE ENTERED: Incorrect sign results in entering -0.1776 CUE:
None.
SAT UNSAT
- 7.
PERFORMANCE: STEP: Determine Safety Rod worth.
........C........
STANDARD: From Table 1, determine Safety worth of -2.624 %K/K.
COMMENT: Actual value is -2.624 %K/K.
INCORRECT VALUE ENTERED: Using Group 1-4 inserted value instead of Group 1 withdrawn value results in entering -3.25%K/K.
CUE:
None.
SAT UNSAT
- 8.
PERFORMANCE STEP: Determine Control Rod 5-7 worth.
........C........
STANDARD: From Figure 9A, determine Regulating Rod worth of -2.8 to -2.95 %K/K.
COMMENT: Actual value is -2.877 %K/K.
CUE:
None.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 9 of 12
- 9.
PERFORMANCE STEP: Determine Total Rod worth.
........C........
STANDARD: Add Safety Rod worth and Control Rod worth. Range from -5.424 to
-5.574 %K/K.
COMMENT: Actual value is -5.501%K/K.
INCORRECT VALUE: -6.127 was entered due to using the all Safety Rods inserted value in step 7.
CUE:
None.
SAT UNSAT
- 10. PERFORMANCE STEP: Determine APSR worth.
........C........
STANDARD: From Figure 11A, determine APSR worth of -0.084 to -0.087 %K/K.
COMMENT: Actual value is -0.085 %K/K.
CUE:
None.
SAT UNSAT
- 11. PERFORMANCE STEP: Determine reactivity anomaly worth.
STANDARD: Determine zero from Initial Conditions.
CUE:
None.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 10 of 12
- 12. PERFORMANCE STEP: Determine the correct value for shutdown value.
........C........
STANDARD: Determine that shutdown value is a value between -1.50 and -1.55%K/K.
COMMENT:
Actual value is -1.5215 %K/K.
CUE:
None.
SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by examinee). See next page for Answer Key.
END TIME: ____________
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 11 of 12 ATTACHMENT 5:
SHUTDOWN VALUE (SDV) CALCULATION WITH Tave 500°F - SECTION 9.0 Page 1 of 2 ANSWER KEY EFPD=__60____
CF(B10)=_0.96__
B(RCS)=_1035_ppmB Tave=__520_°F Rod Index=__0___RI APSR=_29.5__%wd Data: Date_today_ Time__now_
Is Control Rod Group 1 withdrawn? _____No _____Yes Use the critical reference condition for all data.
This calculation is valid only with the reactor subcritical and Tave 500°F.
If a stuck rod exists contact a Reactor Engineer.
Shutdown Value (SDV)
_12.13__+__-6.89__+__-1.5___+__0.1469_+ _0.1776__+ __-5.501___+_-0.085__+___0_ = _-1.5215%k/k (fuel) (boron) (tp) (Pu-max) (temp) (CRG 1-7) (APSR) (anom) SDV Where:
(fuel) is fuel Worth from Figure 2 based on EFPD (boron) is Boron Worth = __-6.9____ x __0.998___ = __-6.89___%k/k (BBOL) CF(FBU) (boron)
Where:
(BBOL) is Boron Worth at Beginning of Life from Figure 3 based on B(ROCB)
(Critical curve)
__1035___ x __0.96___ x (1 -.01) = __ 984___ppmB B(RCS) CF(B10) B(ROCB)
Where:.01 is the Boron Concentration Measurement Uncertainty (1 -.01) is the Boron Concentration Measurement Correction Factor CF(FBU) is Correction Factor for Fuel Burnup from Figure 4 based on EFPD (Critical curve)
(tp) is Transient Poison Worth from START program for time of data (Pu-max) is Maximum Excess Pu-239 Worth from Figure 20B based on EFPD (temp) is Temperature Reactivity = _-0.0148__ x __-12___ = _ 0.1776___%k/k T T (temp)
Where:
T is Temperature Coefficient from Figure 12 based on EFPD and B(ROCB)
T = Tave - 532°F
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A1.1 Page 12 of 12 ATTACHMENT 5:
SHUTDOWN VALUE (SDV) CALCULATION WITH Tave 500°F -
SECTION 9.0 Page 2 of 2 ANSWER KEY (CRG 1-7) is Control Rod Groups 1-7 Worth = ___-2.624___ + ___-2.877___ = __-5.501____%k/k (CRG 1-4) (CRG 5-7) (CRG 1-7)
Where:
(CRG 1-4) is Safety Rod Worth from Table 1 of ROCB based on Control Rod Group 1 position (CRG 5-7) is Control Rod Groups 5-7 Worth from Figure 9* based on EFPD, (tp),
and Rod Index (APSR) is APSR Worth from Figure 11A based on EFPD and APSR position (anom) is Reactivity Worth of HFP Anomaly from the Reactor Operating Guidance (For conservatism, a value of 0 may be used in place of a negative HFP anomaly for calculations of Shutdown Value. See Step 4.2.8.)
- Use Figure 9A if the absolute value of (tp) < 2.0%k/k.
Use Figure 9B if the absolute value of (tp) 2.0%k/k.
Calculated by Candidate Date Today Time Now Checked by Date
Davis-Besse NRC Exam 2018 Admin JPM SRO A2
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A2 r1 Facility: Davis-Besse Task No:
333-040-01-0300 Task
Title:
Review Shutdown Safety Assessment K/A
Reference:
2.2.18 (3.9)
Job Performance Measure No: SRO A2 (JPM NEW)
Examinee:
NRC Examiner:
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.
Initial Conditions:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Task Standard:
Reviews the provided Defense in Depth Turnover Checklist and identifies the errors in the DID calculations and status indications.
Required Materials:
NOP-OP-1005, Shutdown Defense in Depth, Rev 15 NOP-OP-1005-02 Davis Besse Key Shutdown Defense in Depth Turnover Checklist, Rev 10 NOP-OP-1005-04 Key Shutdown Defense in Depth Function Status, Rev 8 NG-DB-00117, Shutdown Defense in Depth Assessment General
References:
None Initiating Cue:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Time Critical Task:
No Alternate Path:
No Validation Time:
15 minutes
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A2 r1 EVALUATOR COPY INITIAL CONDITIONS:
A Refueling Outage is in progress, the core has been offloaded to the Spent Fuel Pool RCS Temperature is 102 F as indicated on computer point T532 RCS Pressure is 0 PSIG as indicated on computer point P723 Spent Fuel Pool Temperature is 100 F as indicated on computer point T874 Refueling cavity level is 23.5 feet RCS Boron concentration is 2350 PPM Train 1 Decay Heat Pump and Cooler is available Train 2 Decay Heat Pump and Cooler is on clearance Emergency Diesel Generator 1 is Operable Emergency Diesel Generator 2 is in Clearance Station Blackout Diesel Generator is Operable Startup Transformer X01 is energized Startup Transformer X02 is not available Backfeed through the Aux Transformer is not available All four Off-site power sources are available (Beaver, Lemoyne, Bayshore, Hayes)
There are no Severe Weather warnings or Grid stability issues Train A Spent Fuel Pool Cooling pump is in service Train B Spent Fuel Pool Cooling pump is in standby.
Makeup to the Spent Fuel pool is available
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A2 r1 INITIATING CUE:
You are to perform the SRO review of the provided Shutdown Safety Defense in Depth Turnover Checklist. The Safety Functions that are identified as N/A do not need to be reviewed since the core is offloaded. Use the plant status information provided in the Initial Conditions to support your review.
You do not need to verify the Time to Boiling Calculations, they have been verified as accurate.
Document the results of your review below.
(Provide examinee a copy of NOP-OP-1005, Shutdown Defense in Depth, completed Forms NOP-OP-1005-02 and NOP-OP-1005-04, and NG-DB-00117, Shutdown Defense in Depth Assessment)
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A2 r1 CANDIDATE COPY INITIAL CONDITIONS:
A Refueling Outage is in progress, the core has been offloaded to the Spent Fuel Pool RCS Temperature is 102 F as indicated on computer point T532 RCS Pressure is 0 PSIG as indicated on computer point P723 Spent Fuel Pool Temperature is 100 F as indicated on computer point T874 Refueling cavity level is 23.5 feet RCS Boron concentration is 2350 PPM Train 1 Decay Heat Pump and Cooler is available Train 2 Decay Heat Pump and Cooler is on clearance Emergency Diesel Generator 1 is Operable Emergency Diesel Generator 2 is in Clearance Station Blackout Diesel Generator is Operable Startup Transformer X01 is energized Startup Transformer X02 is not available Backfeed through the Aux Transformer is not available All four Off-site power sources are available (Beaver, Lemoyne, Bayshore, Hayes)
There are no Severe Weather warnings or Grid stability issues Train A Spent Fuel Pool Cooling pump is in service Train B Spent Fuel Pool Cooling pump is in standby.
Makeup to the Spent Fuel pool is available
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A2 r1 INITIATING CUE:
You are to perform the SRO review of the provided Shutdown Safety Defense in Depth Turnover Checklist. The Safety Functions that are identified as N/A do not need to be reviewed since the core is offloaded. Use the plant status information provided in the Initial Conditions to support your review.
You do not need to verify the Time to Boiling Calculations, they have been verified as accurate.
Document the results of your review below.
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A2 r1 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT required unless denoted in the "Comments".
START TIME:
- 1.
PERFORMANCE STEP: Reviews the forms and Attachment 1 and 2 of NG-DG-00117.
STANDARD:
Reviews the provided documents.
CUE:
None SAT UNSAT
- 2.
PERFORMANCE STEP: Identifies that the number of credited EDGs is correct and 2 are credited.
STANDARD:
Determines that EDG 1 and the SBO EDG are available.
CUE:
None SAT UNSAT
- 3.
PERFORMANCE STEP: Identifies that the number of credited Startup Transformers is correct as 1.
STANDARD:
Recognizes that the X01 Startup Transformer is energized, X02 is denergized.
CUE:
None SAT UNSAT
- 4.
PERFORMANCE STEP: Identifies that the Backfeed is not available through the Aux Transformer so the source is correct and credited as 0.
STANDARD:
Recognizes that Backfeed is not available.
CUE:
None SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A2 r1
- 5.
PERFORMANCE STEP: Identifies that the number of credited Offsite Sources is incorrect as 4 it should be 2.
C STANDARD:
Recognizes the maximum credit for Offsite sources is 2, not 4.
CUE:
None SAT UNSAT
- 6.
PERFORMANCE STEP: Identifies that the No Severe Weather or Grid Stability should be credited as a 1 not a T for True.
STANDARD:
Recognizes the credit for Weather and Grid should be a 1 not a T.
CUE:
None SAT UNSAT
- 7.
PERFORMANCE STEP:
Identifies that Total Status for the Electrical Power Availability should be 6 not 7.
C STANDARD:
Recognizes the error in calculating the total credit and corrects to be a
- 6.
CUE:
None SAT UNSAT
- 8.
PERFORMANCE STEP: Recognizes that the status for Electrical Power Availability remains Green with 6 sources credited.
STANDARD:
Determines that Electrical status remains Green.
CUE:
None SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A2 r1
- 9.
PERFORMANCE STEP: Identifies that the number of credited Spent Fuel Pool Cooling trains is correct as 2.
STANDARD:
Recognizes that SFP cooling has two trains available.
CUE:
None SAT UNSAT
- 10. PERFORMANCE STEP: Identifies that the number of credited Standby Decay Heat trains is correct as 1 for SFP cooling.
STANDARD:
Recognizes that Decay Heat cooling has one train available.
CUE:
None SAT UNSAT
- 11. PERFORMANCE STEP: Identifies that the credited Second train of Decay Heat trains is incorrect as F should be a 0.
STANDARD:
Recognizes that Second Decay Heat cooling train is misidentified as a F versus a 0.
CUE:
None SAT UNSAT
- 12. PERFORMANCE STEP: Identifies that the credited Spent Fuel Pool Makeup is incorrect as T should be a 1.
STANDARD:
Recognizes that Spent Fuel Pool Makeup is misidentified as a T versus a 1.
CUE:
None SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A2 r1
- 13. PERFORMANCE STEP: Identifies that Total Status for the Spent Fuel Pool Cooling should be 4 not 3.
C STANDARD:
Recognizes the error in calculating the total credit and corrects to be a
- 4.
CUE:
None SAT UNSAT
- 14. PERFORMANCE STEP: Recognizes that the status for Spent Fuel Pool Cooling should be Green and not Yellow with 4 sources credited.
C STANDARD:
Changes the Spent Fuel Pool status to Green.
CUE:
None SAT UNSAT
- 15. PERFORMANCE STEP: Recognizes that the Overall Shutdown status is Green not Yellow.
C STANDARD:
Changes the overall status to Green.
CUE:
None SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by examinee)
END TIME: ____________
KEY SHUTDOWN DEFENSE IN DEPTH FUNCTION STATUS NOP-OP-1005-04 Rev. 08 Page 1 of 1 Date/Time: Today / Now Mode: Defueled Protected Train/Division: Train 1 Overall Key Shutdown Defense in Depth Function Status (Yellow)
Shutdown Defense in Depth Function Description Status RCS Decay Heat Removal Not applicable with the Core Offloaded N/A RCS Inventory Control Not applicable with the Core Offloaded N/A Power Availability EDG 1, SBODG, S/U Xfrmr X01, Beaver, Lemoyne, Bayshore, Hayes Green Reactivity Control Not applicable with the Core Offloaded N/A Containment Closure Not applicable with the Core Offloaded N/A Spent Fuel Pool Cooling Spent Fuel pool Cooling Trains 1 & 2, Decay Heat Train 1 Yellow Green: Full S/D Defense in Depth Yellow: Adequate S/D Defense in Depth Orange: Marginal S/D Defense in Depth Red: Unacceptable S/D Defense in Depth RCS Pressure: 0 psig RCS Temp: 102 F RCS Time to Boil:15 hours RCS Temp at which Time to Boil less than 60 minutes:
212F Switchyard Work: None Time to Uncover: > 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> SFP Temp:
100 F SFP Time to Boil:
25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> Shutdown Defense in Depth Advisor: Ima Did SRO Peer Review:
Davis-Besse Initial License NRC Exam 2018 ADMIN JPM SRO A1.2
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet JPM SRO A1.2 r1 Page 1 of 5 Facility: Davis-Besse Task No:
332-002-02-0300 Task
Title:
Review DB-OP-03006, Miscellaneous Shift Check K/A
Reference:
2.1.31 (4.3)
Job Performance Measure No: SRO A1.2__
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance ___
Actual Performance _X_
Classroom _X__
Simulator ___
Plant ___
Read to the examinee:
Initial Conditions:
The plant is in Mode 1.
Initiating Cue:
You are to review DB-OP-03006, Attachment 1, Miscellaneous Instrument Shift Check and notify the SM if you identify any problems.
Determine if there are any Technical Specification entry requirements and if so, determine the associated actions.
Task Standard:
Identify errors in the performance of DB-OP-03006, Attachment 1, Miscellaneous Instrument Shift Check, and determine Technical Specification entry requirements and associated actions.
Required Materials:
Completed surveillance of DB-OP-03006, Miscellaneous Instrument Shift Check DB-OP-03006, Miscellaneous Instrument Shift Check DB-OP-03006, Miscellaneous Instrument Shift Check, Attachment 6 with current data entered Technical Specifications Core Operating Limits Report General
References:
None Time Critical Task: No Validation Time: 33 minutes
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet JPM SRO A1.2 r1 Page 2 of 5 EXAMINER COPY INITIAL CONDITIONS:
The plant is in Mode 1.
INITIATING CUES:
You are to review DB-OP-03006, Attachment 1, Miscellaneous Instrument Shift Check and notify the SM if you identify any problems.
Determine if there are any Technical Specification entry requirements and if so, any associated actions.
(Provide completed surveillance of DB-OP-03006, Miscellaneous Instrument Shift Check including Attachment 6 data, a copy of DB-OP-03006, Miscellaneous Instrument Shift Check, and a copy of Technical Specifications)
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet JPM SRO A1.2 r1 Page 3 of 5 CANDIDATE COPY INITIAL CONDITIONS:
The plant is in Mode 1.
INITIATING CUES:
You are to review DB-OP-03006, Attachment 1, Miscellaneous Instrument Shift Check and notify the SM if you identify any problems.
Determine if there are any Technical Specification entry requirements and if so, any associated actions.
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet JPM SRO A1.2 r1 Page 4 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT required unless denoted in the "Comments".
START TIME: _______
- 1.
PERFORMANCE STEP: Reviews completed surveillance DB-OP-03006, Miscellaneous Instrument Shift Check.
STANDARD: Reviews information provided in completed surveillance DB-OP-03006, Miscellaneous Instrument Shift Check.
SAT UNSAT
- 2.
PERFORMANCE STEP: Step 4.2, BWST Level, calculated Maximum Difference should
____C_____
be 2.5 feet not 2.0 feet Should declare LI1525B inoperable and enter TS 3.3.5, Cond. A and place channel in Trip in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. (TS 3.3.17 may also be referenced for Information Only)
STANDARD: Should identify that maximum difference in logged should be 2.5 feet not 2.0 feet. Step NOT met, (YES incorrectly circled). Should declare LI1525B inoperable and enter TS 3.3.5 and trip BWST level indicator LI1525B within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. May refer to TS 3.3.17 but not critical.
COMMENT: Critical step is to enter TS 3.3.5 and identify action to place LI1525B in trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
CUE: As SM, acknowledge error and continue with surveillance.
If necessary provide candidate with computer point L063 is also reading 42.5 feet.
SAT UNSAT
- 3.
PERFORMANCE STEP: Step 4.3, CTMT to Annulus Diff Pressure, Shift Manager should be notified of degraded condition as required by Note a.
STANDARD:
Notifies Shift Manager that CTMT to Annulus Diff Pressure needs to be addressed.
COMMENT:
Not critical, no TS entry.
CUE: As SRO, acknowledge error and continue with surveillance.
SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet JPM SRO A1.2 r1 Page 5 of 5
- 4.
PERFORMANCE STEP: Step 4.9, CST Level, levels should be added together.
STANDARD: Identifies that Step 4.9, CST Levels were not added together. Notifies shift manager of error.
COMMENT:
Not critical since no TS entry.
CUE: As SRO, acknowledge error and continue with surveillance.
SAT UNSAT
- 5.
PERFORMANCE STEP: Step 4.18, Missed circling YES for PWR Range flux.
STANDARD:
Identifies that Step 4.18 not circled.
CUE: As SRO, acknowledge error and continue with surveillance.
SAT UNSAT
- 6.
PERFORMANCE STEP: Step 4.20, Missed RCS Loop flow data entry.
____C_____
STANDARD:
Identifies that Step 4.20 data entry is missing.
CUE: As SRO, acknowledge error and if necessary provide the following information FIRC1B is 74 MPPH FIRC1A is 76 MPPH.
SAT UNSAT
- 7.
PERFORMANCE STEP: Step 4.2, BWST Level on SFAS Cabinets page 6 of 8, calculated maximum difference in error. (Similar to BWST level error on page 1 of 8).
STANDARD:
Informs Shift Manager that BWST Level indicator is out of tolerance.
Requires entry into TS 3.3.5, Condition A. Must place channel in trip < 1hr.
CUE: As SRO, acknowledge error and continue with surveillance.
SAT UNSAT TERMINATING CUES: This JPM is complete. (Terminated by the applicant) __________
END TIME
Davis-Besse NRC Exam 2018 Admin JPM SRO-A3
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A3 r1 1 of 5 Facility: Davis-Besse Task No:
334-005-05-0300 Task
Title:
Emergency Dose Authorization K/A
Reference:
2.3.4 (3.7)
Job Performance Measure No: SRO-A3 Examinee:
NRC Examiner:
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.
Initial Conditions:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Task Standard:
Select the three mechanic method and authorize Emergency dose for mechanic 1, 2, and 4 only Required Materials:
RA-EP-02620, Emergency Dose Control and Potassium Iodide Distribution Emergency Dose Authorization form for each mechanic Calculator General
References:
None Initiating Cue:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Time Critical Task: No Alternate Path: No Validation Time: 21 minutes
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A3 r1 2 of 5 EXAMINER COPY INITIAL CONDITIONS:
The Plant has experienced a Loss of Coolant Accident and fuel damage. Emergency Core Cooling Train (ECCS) 1 is in operation at full flow. Low Pressure Injection Pump (LPI) 2 is out of service for maintenance. Just before the accident it was determined LPI Pump 1 was losing oil through a loose bearing housing. Plans were being made to tighten the housing and add oil. It is determined that this task is required to be performed immediately to maintain core cooling and prevent core damage.
INITIATION CUE:
You are an extra SRO on shift. The ERO is not yet activated. The Shift Manager, acting as the Emergency Director, has directed you to prepare an emergency dose authorization using the information below.
Select the method that results in the lowest accumulated dose per mechanic and acceptable mechanics to perform this task. Document your recommendations on this page.
Prepare the Emergency Dose Authorization form(s) per RA-EP-02620, Emergency Dose Control and Potassium Iodide Distribution up to the authorization signatures.
Radiation levels in ECCS Room 1 are indicating 40 Rem/hr These two tasks (tighten the housing and add oil) can be performed by the mechanic(s) working in series or multiple mechanics working in parallel.
One mechanic would obtain 48 minutes of exposure Two mechanics simultaneously would obtain 24 minutes of exposure each Three mechanics in rotation would obtain 15 minutes of exposure each Four mechanics in rotation would obtain 10 minutes of exposure each Four Mechanics have volunteered to perform this work:
- Mechanic 1 is a 52 year old male with 10 Rem lifetime dose and no dose for current year.
- Mechanic 2 is a 47 year old male with 600 mrem lifetime dose and 5 mrem for current year
- Mechanic 3 is a 34 year old female, who has a declared pregnancy, with 125 mrem lifetime dose and no dose for current year
- Mechanic 4 is a 49 year old male with 4.2 mrem lifetime and 700 mrem for the current year (Hand Candidate a copy of RA-EP-02620, Emergency Dose Control and Potassium Iodide Distribution and the four Emergency Dose Authorization Forms)
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A3 r1 3 of 5 CANDIDATE COPY INITIAL CONDITIONS:
The Plant has experienced a Loss of Coolant Accident and fuel damage. Emergency Core Cooling Train (ECCS) 1 is in operation at full flow. Low Pressure Injection Pump (LPI) 2 is out of service for maintenance. Just before the accident it was determined LPI Pump 1 was losing oil through a loose bearing housing. Plans were being made to tighten the housing and add oil. It is determined that this task is required to be performed immediately to maintain core cooling and prevent core damage.
INITIATION CUE:
You are an extra SRO on shift. The ERO is not yet activated. The Shift Manager, acting as the Emergency Director, has directed you to prepare an emergency dose authorization using the information below.
Select the method that results in the lowest accumulated dose per mechanic and acceptable mechanics to perform this task. Document your recommendations on this page.
Prepare the Emergency Dose Authorization form(s) per RA-EP-02620, Emergency Dose Control and Potassium Iodide Distribution up to the authorization signatures.
Radiation levels in ECCS Room 1 are indicating 40 Rem/hr These two tasks (tighten the housing and add oil) can be performed by the mechanic(s) working in series or multiple mechanics working in parallel.
One mechanic would obtain 48 minutes of exposure Two mechanics simultaneously would obtain 24 minutes of exposure each Three mechanics in rotation would obtain 15 minutes of exposure each Four mechanics in rotation would obtain 10 minutes of exposure each Four Mechanics have volunteered to perform this work:
- Mechanic 1 is a 52 year old male with 10 Rem lifetime dose and no dose for current year.
- Mechanic 2 is a 47 year old male with 600 mrem lifetime dose and 5 mrem for current year
- Mechanic 3 is a 34 year old female, who has a declared pregnancy, with 125 mrem lifetime dose and no dose for current year
- Mechanic 4 is a 49 year old male with 4.2 mrem lifetime and 700 mrem for the current year
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A3 r1 4 of 5 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT critical unless denoted in the "Comments".
START TIME: _______
- 1.
PERFORMANCE STEP: Evaluate the dose that would be received for each method STANDARD: One mechanic would obtain 32 Rem, which exceeds the 25 Rem limit Two mechanics simultaneously would obtain 16 Rem each Three mechanics in rotation would obtain 10 Rem each Four mechanics in rotation would obtain 6.7 Rem each COMMENT: JPM step sequence not critical. May evaluate mechanics and select method first in which case only the method selected will need dose evaluated CUE: None SAT UNSAT
- 2.
PERFORMANCE STEP: Evaluate Mechanic 1 acceptability for receiving Emergency Dose STANDARD:. Determines Mechanic 1 can be authorized to receive emergency dose CUE:
If asked - have never received emergency dose SAT UNSAT
- 3.
PERFORMANCE STEP: Evaluate Mechanic 2 acceptability for receiving Emergency Dose STANDARD: Determines Mechanic 2 can be authorized for Emergency Dose CUE: If asked - have never received emergency dose SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A3 r1 5 of 5
- 4.
PERFORMANCE STEP: Evaluate Mechanic 3 acceptability for receiving Emergency Dose STANDARD: Determines Mechanic 3 SHALL NOT be authorized to receive emergency dose. Since mechanic is female, and is a declared pregnant worker CUE: If asked - have never received emergency dose If asked - have just found out is pregnant SAT UNSAT
- 5.
PERFORMANCE STEP: Evaluate Mechanic 4 acceptability for receiving Emergency Dose STANDARD: Determines Mechanic 4 can be authorized for Emergency Dose CUE: If asked - have never received emergency dose SAT UNSAT
- 6.
PERFORMANCE STEP: Determine method for repair
........C........
STANDARD: Determines 3 mechanics in rotation is proper method due to condition in RA-EP-02620, step 6.1.3.b 25,000 mrem TEDE CUE:
None SAT UNSAT
- 7.
PERFORMANCE STEP: Select Mechanic 1, Mechanic 2 and Mechanic 4 to perform work
........C........
STANDARD: Recommend Emergency Dose for Mechanic 1, Mechanic 2 and Mechanic 4 CUE:
None SAT UNSAT TERMINATING CUES: This JPM is complete (Terminated by the examiner)
END TIME
EMERGENCY DOSE AUTHORIZATION DBEP-204-01 INDIVIDUAL (Last, First, Middle)
Mechanic 1 SOCIAL SECURITY NUMBER 111-11-1111 DATE Today TLD NO.
1 EMPLOYER FENOC BRIEF DESCRIPTION OF TASK Enter ECCS Room 1 to add oil and tighten the bearing housing for Low Pressure Injection Pump 1 RECOMMENDED EMERGENCY DOSE AUTHORIZATION YES NO RECOMMENDED EMERGENCY DOSE LIMIT REM { TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) }
COMMENTS EMERGENCY RP MANAGER RECOMMENDATION (Signature)
EMERGENCY DIRECTOR APPROVAL (Signature)
AUTHORIZATION DATE AUTHORIZATION LIMIT REM { TEDE }
I have been briefed on the radiological consequences and hazards associated with the authorized emergency dose and I have volunteered to perform the above described task.
INDIVIDUAL (Signature)
DATE BRIEFED BY (Signature)
DATE (TOTAL DOSE - TEDE) =
(EXTERNAL - DDE)
PLUS (INTERNAL - CEDE)
RADIOBIOASSAY RESULTS EMERGENCY RP MANAGER REVIEW (Signature)
DATE EMERGENCY DIRECTOR REVIEW (Signature)
DATE
EMERGENCY DOSE AUTHORIZATION DBEP-204-01 INDIVIDUAL (Last, First, Middle)
Mechanic 2 SOCIAL SECURITY NUMBER 222-22-2222 DATE Today TLD NO.
2 EMPLOYER FENOC BRIEF DESCRIPTION OF TASK Enter ECCS Room 1 to add oil and tighten the bearing housing for Low Pressure Injection Pump 1 RECOMMENDED EMERGENCY DOSE AUTHORIZATION YES NO RECOMMENDED EMERGENCY DOSE LIMIT REM { TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) }
COMMENTS EMERGENCY RP MANAGER RECOMMENDATION (Signature)
EMERGENCY DIRECTOR APPROVAL (Signature)
AUTHORIZATION DATE AUTHORIZATION LIMIT REM { TEDE }
I have been briefed on the radiological consequences and hazards associated with the authorized emergency dose and I have volunteered to perform the above described task.
INDIVIDUAL (Signature)
DATE BRIEFED BY (Signature)
DATE (TOTAL DOSE - TEDE) =
(EXTERNAL - DDE)
PLUS (INTERNAL - CEDE)
RADIOBIOASSAY RESULTS EMERGENCY RP MANAGER REVIEW (Signature)
DATE EMERGENCY DIRECTOR REVIEW (Signature)
DATE
EMERGENCY DOSE AUTHORIZATION DBEP-204-01 INDIVIDUAL (Last, First, Middle)
Mechanic 3 SOCIAL SECURITY NUMBER 333-33-3333 DATE Today TLD NO.
3 EMPLOYER FENOC BRIEF DESCRIPTION OF TASK Enter ECCS Room 1 to add oil and tighten the bearing housing for Low Pressure Injection Pump 1 RECOMMENDED EMERGENCY DOSE AUTHORIZATION YES NO RECOMMENDED EMERGENCY DOSE LIMIT REM { TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) }
COMMENTS EMERGENCY RP MANAGER RECOMMENDATION (Signature)
EMERGENCY DIRECTOR APPROVAL (Signature)
AUTHORIZATION DATE AUTHORIZATION LIMIT REM { TEDE }
I have been briefed on the radiological consequences and hazards associated with the authorized emergency dose and I have volunteered to perform the above described task.
INDIVIDUAL (Signature)
DATE BRIEFED BY (Signature)
DATE (TOTAL DOSE - TEDE) =
(EXTERNAL - DDE)
PLUS (INTERNAL - CEDE)
RADIOBIOASSAY RESULTS EMERGENCY RP MANAGER REVIEW (Signature)
DATE EMERGENCY DIRECTOR REVIEW (Signature)
DATE
EMERGENCY DOSE AUTHORIZATION DBEP-204-01 INDIVIDUAL (Last, First, Middle)
Mechanic 4 SOCIAL SECURITY NUMBER 444-44-4444 DATE Today TLD NO.
4 EMPLOYER FENOC BRIEF DESCRIPTION OF TASK Enter ECCS Room 1 to add oil and tighten the bearing housing for Low Pressure Injection Pump 1 RECOMMENDED EMERGENCY DOSE AUTHORIZATION YES NO RECOMMENDED EMERGENCY DOSE LIMIT REM { TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) }
COMMENTS EMERGENCY RP MANAGER RECOMMENDATION (Signature)
EMERGENCY DIRECTOR APPROVAL (Signature)
AUTHORIZATION DATE AUTHORIZATION LIMIT REM { TEDE }
I have been briefed on the radiological consequences and hazards associated with the authorized emergency dose and I have volunteered to perform the above described task.
INDIVIDUAL (Signature)
DATE BRIEFED BY (Signature)
DATE (TOTAL DOSE - TEDE) =
(EXTERNAL - DDE)
PLUS (INTERNAL - CEDE)
RADIOBIOASSAY RESULTS EMERGENCY RP MANAGER REVIEW (Signature)
DATE EMERGENCY DIRECTOR REVIEW (Signature)
DATE
Davis-Besse Initial License NRC Exam 2018 Admin JPM SRO-A4
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A4 r1 1 of 6 Facility: Davis-Besse Task No:
334-004-05-0300 Task
Title:
Determine the off-site PAR K/A
Reference:
2.4.44 (4.4)
Job Performance Measure No: SRO-A4 (JPM 150)
Examinee:
NRC Examiner:
Date:
Method of testing:
Simulated Performance ___
Actual Performance _X_
Classroom _X_
Simulator __X_
Plant ___
Read to the examinee:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Task Standard:
Determine the off-site protective action recommendations and make all required offsite notifications.
Required Materials:
RA-EP-01900, General Emergency, Rev 9 RA-EP-02110, Emergency Notification, Rev 15 RA-EP-02245, Protective Action Guidelines, Rev 6 RA-EP-02240, Offsite Dose Assessment, Rev 9 RA-EP-01500, Emergency Classification, Rev 16 E-Plan Implementation Forms envelope General
References:
None Initiating Cue:
The plant conditions are specified in the Initial Conditions and Initiating Cues.
Time Critical Task:
Yes Alternate Path:
No Validation Time: 12 Minutes
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A4 r1 2 of 6 SIMULATOR INSTRUCTIONS INITIAL CONDITION:
This JPM is not dependent on any specific simulator initial conditions since the task is administrative in nature.
The plant conditions are specified in the Initial Conditions and Initiating Cues.
ADDITIONAL SETUP/DEVIATION FROM INITIAL CONDITION:
If this JPM is not conducted in the simulator, the following references need to be available to the examinee:
RA-EP-01500, Emergency Classification RA-EP-01900, General Emergency RA-EP-02240, Offsite Dose Assessment RA-EP-02110, Emergency Notification RA-EP-02245, Protective Action Guidelines E-Plan Implementation Forms envelope MALFUNCTIONS/FAILURE TO INSERT:
None.
ACTION/CUES:
See body of JPM
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A4 r1 3 of 6 EXAMINER COPY INITIAL CONDITIONS:
A large break LOCA is in progress with no indications of a core melt sequence.
A Containment-to-Annulus leak has resulted in a release from the Station Vent.
A General Emergency has been declared (3 minutes ago) per EAL RG1.
Information reviewed for the General Emergency declaration determined that there is no Loss or Potential Loss of the CTMT Fission Product Barrier. There is no Hostile Action or Evacuation Impediments reported by the state or counties.
The Emergency Response Organization is being notified of the General Emergency.
Due to a power failure, MIDAS is unavailable and the current wind direction is unknown.
INITIATING CUES:
You are the Emergency Director.
The following off-site dose assessment data is provided.
TEDE RATE X 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> estimated release duration TOTAL TEDE RELEASE 3.0 Rem/hr at 0.75 Miles 6.0 Rem at 0.75 Miles 0.6 Rem/hr at 2 Miles 1.2 Rem at 2 Miles 0.2 Rem/hr at 5 Miles 0.4 Rem at 5 Miles 0.075 Rem/hr at 10 Miles 0.15 Rem at 10 Miles This is a Time Critical JPM. The instructor will inform when the clock begins and stops.
Determine the off-site protective action recommendations starting with step 6.1.1.i of RA-EP-01900, General Emergency. Use the TEDE values only (Child Thyroid dose equivalent values not yet available) AND make required offsite notifications.
Provide copy of in progress RA-EP-01900, General Emergency, and have available the following procedures:
RA-EP-01500, Emergency Classification RA-EP-02240, Offsite Dose Assessment RA-EP-02110, Emergency Notification RA-EP-02245, Protective Action Guidelines E-Plan Implementation Forms envelope
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A4 r1 4 of 6 CANDIDATE COPY INITIAL CONDITIONS:
A large break LOCA is in progress with no indications of a core melt sequence.
A Containment-to-Annulus leak has resulted in a release from the Station Vent.
A General Emergency has been declared (3 minutes ago) per EAL RG1.
Information reviewed for the General Emergency declaration determined that there is no Loss or Potential Loss of the CTMT Fission Product Barrier. There is no Hostile Action or Evacuation Impediments reported by the state or counties.
The Emergency Response Organization is being notified of the General Emergency.
Due to a power failure, MIDAS is unavailable and the current wind direction is unknown.
INITIATING CUES:
You are the Emergency Director.
The following off-site dose assessment data is provided.
TEDE RATE X 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> estimated release duration TOTAL TEDE RELEASE 3.0 Rem/hr at 0.75 Miles 6.0 Rem at 0.75 Miles 0.6 Rem/hr at 2 Miles 1.2 Rem at 2 Miles 0.2 Rem/hr at 5 Miles 0.4 Rem at 5 Miles 0.075 Rem/hr at 10 Miles 0.15 Rem at 10 Miles This is a Time Critical JPM. The instructor will inform when the clock begins and stops.
Determine the off-site protective action recommendations starting with step 6.1.1.i of RA-EP-01900, General Emergency. Use the TEDE values only (Child Thyroid dose equivalent values not yet available) AND make required offsite notifications.
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A4 r1 5 of 6 PERFORMANCE INFORMATION NOTE: Critical steps denoted with a "C". Failure to meet any one of these standards for this item constitutes failure. Sequence is NOT critical unless denoted in the "Comments".
START TIME: _______
- 1.
PERFORMANCE STEP: Refer to RA-EP-02245, Protective Action Guidelines and refer to STANDARD: Obtains RA-EP-02245 and refers to Attachment 1.
CUE:
Time Critical clock begins (Record Time)
SAT UNSAT
- 2.
PERFORMANCE STEP: Determine PAR using page 1 of Attachment 1.
STANDARD: Determines a General Emergency IS declared Determines this is the Initial PAR Determines Rapidly Progressing Severe Accident NOT in progress (NOTE1)
Determines Hostile Action or Impediment to Evacuation NOT in progress Determines a release IS in progress Determines the release is NOT terminable by operator action Determines TEDE projected doses are < 1 Rem at 5 miles CUE: None SAT UNSAT
- 3.
PERFORMANCE STEP: Determine PAR using page 2 of Attachment 1.
........C........
STANDARD: Uses Column A on Page 2 of Attachment 1.
Using the unknown wind direction, determines the affected subareas for 2 mile radius and 5 miles down wind are 1, 2, 6, 10 and 12.
CUE: None SAT UNSAT
Appendix C Rev. 11 Job Performance Measure Form ES-C-1 Worksheet Admin JPM SRO A4 r1 6 of 6
- 4.
PERFORMANCE STEP: Make notifications to offsite agencies STANDARD: Refers to RA-EP-02110, Emergency Notification.
CUE: None SAT UNSAT
- 5.
PERFORMANCE STEP: Complete an Initial Notification Form (DBEP-010) and a Davis-
........C........
Besse Notification Cover Sheet (DBEP-012).
STANDARD: Completes items 1 through 5 on the Initial Notification form and the header information on the Cover Sheet then signs the Cover Sheet.
CUE: If asked, provide an independent check of the data entered and sign the Davis-Besse Notification Cover Sheet.
SAT UNSAT
- 6.
PERFORMANCE STEP: Make Initial Notification using the 4-Way Ring-Down Circuit.
........C........
STANDARD: Picks up the 4-Way Ring-Down phone in the Control Room. When all parties answer, reads the Initial Notification information.
COMMENT: Notification must be made within 15 minutes of the event declaration time; the clock stops when the 4-Way Ring-Down phone is picked up.
CUE (when the 4-Way Ring-Down phone is picked up Time Critical clock stops)
Critical Time is less than 12 minutes from start time since declaration of General Emergency was 3 minutes ago by initial conditions.
(Record Time)
CUE:
(I/S or classroom instructor CUE) Ottawa Country Sheriff's Dispatcher, Lucas County Sheriff's Dispatcher, and Ohio State Highway Patrol Dispatcher answer the phone.
(I/S or classroom instructor CUE) Repeat back the information as it is communicated.
Time: __________
SAT UNSAT TERMINATING CUES: This JPM is complete. (Terminated by the evaluator).
END TIME