ML13032A571
| ML13032A571 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/29/2013 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| 50-324/324, 50-325/12-301, LOT-ADM-JP-201-D13 | |
| Download: ML13032A571 (77) | |
Text
L1IIII1IIIIIPF DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC Coo1 LESSON TITLE:
LESSON NUMBER:
Evaluate Status of Operator Licenses LOT-ADM-JP-201-D1 3 REVISION NO:
Concurred By Validated By:
Approved By:
0 erations Instructor 6-2-2 Date Nuclear Operations Instruc or Date Prepared By:
Date Facility Representative /
ii Dte
JIL;1IIILL LLiil LAILIIIIIIIIII Evaluate Status of Operator Licenses SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
- 1. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
- 2. A yearly calendar will be provided to the candidate.
- 3. A copy of 001-01.05, License Activation and Maintenance, may be provided if requested by the candidate.
4.
If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
- 5. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
LOT-ADM-JP-201-D13 Page 2 of 10 REV. 0
- iIWL___ r Evaluate Status of Operator Licenses Read the following to JPM performer.
TASK CONDITIONS:
Three operators have been performing off-shift duties and are now returning to licensed operator duties on shift.
The following conditions apply for operators 1 and 2:
Operator 1: license was active as of December 31, 2011.
Operator 2: license was active as of December 31, 2011.
The following conditions apply for all three operators:
All required training is complete.
Respirator qualifications are current.
Emergency response organization qualifications are current.
All required plant tours have been conducted by the Shift Manager within the required time frame.
Shifts worked were full 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts, including turnovers.
When required, shifts were worked under the direction of an active license holder.
The Unit CRS has reviewed PQD and ensured each licensed watchstander meets qualification requirements.
No-Solo restrictions do not apply.
Operator I (SRO):
Shifts worked in 2012:
Day shift, March 24 through March 26 Night Shift, March 30 Watch position:
Shifts worked in 2012:
Night shift, March 30 through April 3 Watch position:
Unit CRS Operator 3 (Newly licensed RO):
Shifts worked in 2012:
Day shift, March 29, 2012 through March 31, 2012 Watch position:
OAC LOT-ADM-JP-201-D13 Page 3 of 10 REV. 0
- !Z
Evaluate Status of Operator Licenses INITIATING CUE:
For Operator 1: Determine and circle whether the operators license is active or inactive as of April 4, 2012.
Active I Inactive For Operator 2: Determine and circle whether the operators license is active or inactive as of April 4, 2012.
Active I Inactive For Operator 3: Determine and circle whether the operators license has been properly activated as of April 4, 2012.
Active! Inactive LOT-ADM-JP-201-D13 Page 4 of 10 REV. 0
Evaluate Status of Operator Licenses PERFORMANCE CHECKLIST Ii NOTE: Sequence of the following actions is NOT critical.
I START TIME:
Step I Review data for Operator I and determine status of license activation and maintenance criteria.
Determined that license activation and maintenance criteria are NOT met for Operator I (License still active on return to shift but will be inactive March 31; five 12-hour shifts in a calendar quarter NOT completed to maintain active status through the following quarter.)
- CRITICAL STEP** SATIUNSAT*
Step 2 Review data for Operator 2 and determine status of license activation and maintenance criteria.
Determined that license activation and maintenance criteria are NOT met for Operator 2. 1 (License still active on return to shift but will be inactive March 31; five 12-hour shifts in a calendar quarter NOT completed to maintain active status through the following quarter; March 311s NOT counted for maintaining license active since it spans a calendar quarter.)
- CRITICAL STEP** SATIUNSAT*
Step 3 Review data for Operator 3 and determine status of license activation and maintenance criteria.
Determined that ilcense activation and maintenance criteria are met for Operator 3. (Three 12-hour shifts required for initial activation are met as of March 31)
- CRITICAL STEP** SATIUNSAT*
LOT-ADM-JP-201-D13 Page 5 of 10 REV. 0
JI1I!I1!IIIIIIIIY Evaluate Status of Operator Licenses TERMINATING CUE: When the examinee has completed a determination of Operator License status, this JPM is complete.
TIME COMPLETED
- Comments required for any step evaluated as UNSAT.
LOT-ADM-JP.-201-D13 Page 6 of 10 REV. 0
J$IIIII1IWJ!V Evaluate Status of Operator Licenses RELATED TASKS:
None KJA REFERENCE AND IMPORTANCE RATING:
GEN2.1.4 3.3/3.8 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
REFERENCES:
001-01.05, License Activation and Maintenance TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin
- Conduct of Operations REASON FOR REVISION:
New JPM for HLC 2012 LOT-ADM-JP-201-D13 Page 7 of 10 REV. 0
Evaluate Status of Operator Licenses Validation Time:
20 Minutes (approximate)
Time Taken:
LOT-ADM-JP-201 -Dl 3 Page 8 of 10 REV. 0 L
APPLICABLE METHOD OF TESTING Performance:
Simulate
Actual X
Unit:
0 Setting:
In-Plant Simulator Admin X
Time Critical:
Yes
No X
Time Limit N/A Alternate Path:
Yes
No X
EVALUATION Trainee:_______________________________
JPM:
Pass Fail Remedial Training Required: Yes No (Reference TAP-41 1 for evaluation guidance)
Comments:
Comments reviewed with Student Evaluator Signature:
Date:__________
.__:A Evaluate Status of Operator Licenses TASK CONDITIONS:
Three operators have been performing off-shift duties and are now returning to licensed operator duties on shift.
The following conditions apply for operators I and 2:
Operator 1: license was active as of December 31, 2011.
Operator 2: license was active as of December 31, 2011.
The following conditions apply for all three operators:
All required training is complete.
Respirator qualifications are current.
Emergency response organization qualifications are current.
All required plant tours have been conducted by the Shift Manager within the required time frame.
Shifts worked were full 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts, including turnovers.
When required, shifts were worked under the direction of an active license holder.
The Unit CRS has reviewed PQD and ensured each licensed watchstander meets qualification requirements.
No-Solo restrictions do not apply.
Operator 1 (SRO):
Shifts worked in 2012:
Day shift, March 24 through March 26 Night Shift, March 30 Watch position:
Shifts worked in 2012:
Night shift, March 30 through April 3 Watch position:
Unit CRS Operator 3 (Newly licensed RO):
Shifts worked in 2012:
Day shift, March 29, 2012 through March 31, 2012 Watch position:
OAC
IINIfI1NiL&
If7IIIIt Evaluate Status of Operator Licenses INITIATING CUE:
For Operator 1: Determine and circle whether the operators license is active or inactive as of April 4, 2012.
Active I Inactive For Operator 2: Determine and circle whether the operators license is active or inactive as of April 4, 2012.
Active I Inactive For Operator 3: Determine and circle whether the operators license has been properly activated as of April 4, 2012.
Active I Inactive
i DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC C002 (SRO)
LESSON TITLE:
NRC Event Notification LESSON NUMBER:
SOT-ADM-JP-200-BO1 REVISION NO:
0 Dan Arhelger Nuclear Operations Instructor Nude Operations Instructor Prepared By:
Concurred By Validated By:
Approved By:
Date
//.-zt, //
Date
) 1l Date 2i fZOiL I
ate
NRC Event Notification SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to performer)
- 1. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
- 2. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
3.
A copy of Technical Specifications will be provided.
4.
A copy of 001-01.07, Notifications, and any Plant Emergency Procedure (PEPs) will be provided if requested by the candidate.
5.
If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
SPECIAL INSTRUCTIONS:
None SOT-ADM-JP-200-B01 Page 2 of 11 REV. 00
NRC Event Notification Read the following to the JPM Performer TASK CONDITIONS:
Unit Two was performing a normal Reactor Startup in accordance with OGP-03, Unit Startup and Synchronization with the following initial conditions:
Reactor Power 5%
Reactor Mode Switch in Startup Reactor pressure 928 psig Core flow 9.5% of rated core flow A feedwater transient subsequently occurs with the following observations:
When Reactor power reached 28% RTP the RO inserted a manual reactor scram.
Reactor pressure was maintained at 928 psig.
Core Flow peaked at 9.6% of rated flow.
INITIATING CUE:
You are directed by the Shift Manager to evaluate these plant conditions and determine:
(1) any required Technical Specification actions and (2) the earliest required NRC notification.
SOT-ADM-JP-200-BO1 Page 3 of 11 REV. 00
NRC Event Notification PERFORMANCE CHECKLIST NOTE: Sequence of the following actions is NOT critical.
I START TIME:
Step I Reviews Technical Specifications, section 2.1, SLs.
2.1 SLs 2.1.1 Reactor Core SLs 2.11.1 With the reactor steam dome pressure <785 psig or core flow < 10%
rated core flow:
THERMAL POWER shall be 23% RTP.
2.1.1.2 With the reactor steam dome pressure 785 psig and core flow 1 0%
rated core flow:
MCPR shall be 1.11 for two recirculation loop operation or 1.13 for single recirculaflon loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
Determines that Safety Limit 2.1.1.1 has been exceeded (With Reactor steam dome pressure <785 psig or core flow <10% rated core flow, THERMAL POWER shall be 23% RTP).
- CRITICAL STEP
- SATIUNSAT*
Step 2 Reviews Technical Specifications, section 2.2, SL Violations.
2.2 SL Violations With any SL violation, the following actions shall he completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SL.s; and 2.2.2 Insert all insertable control rods.
Determines that with any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1, Restore compliance with all SLs; and 2.2.2, Insert all insertable control rods.
- CRITICAL STEP
- SATIIJNSAT*
SOT-ADM-JP-200-BO1 Page 4 of 11 REV. 00
NRC Event Notification Step 3 Reviews 001-01.07, Notifications, Attachment 1, Reportability Evaluation Checklist, for NRC notification requirements.
NOTE:
Reporting of events that result in the declaration of an emergency classification in accordance with the Emergency Plan will be in accordance with OPEP-02.&21, Emergency Communicator. Events reported per DPEP-02.6.21 satisty the correspondent notification requirements of this procedure for the reporting of the event classification ONLY. All other notifications shall be made in accordance Mth this procedure.
2.0 FOUR-HOUR REPORTABILITY ITEM #
YES NO DESCRIPTIVE QUESTION 2.1 NOTE:
Includes any Safety Limit violation (Tech Spec 2.2),
Is p.ant shutdown required by technical spacificaitans being initiated?
[10 CFR 50.72b)2)(i)]
2.2 Has the event resulted in or should have resuited in an Emergency Core CooIng System (ECCS) discharge into the Reactor Cooant System as a resut of a va!id sinaI, except when the actuation resulted from and was part of a pre-planned sequence durina testing or reactor operation?
[10 CFR 5o.72i:b:I2)(JxA)I 2.3 Did the event or condition resu t in actuation of the reactor protection stem (RPS) when the reactor was critical, except when the actuafion resulted from and was part of a pre-panned sequence during tesng or reactor operation?
[10 CFR 50.72(bX2Xiv}(5)
May determine that a FOUR-HOUR REPORTABILITY notification to the NRC is required lAW 001-01.07 for the Safety Limit violation and that OPEP-02.6.21 needs to be reviewed.
SAT/U NSAT*
SOT-ADM-JP-200-B01 Page 5 of 11 REV. 00
NRC Event Notification Step 4 Reviews OPEP-02.1, Brunswick Nuclear Plant Initial Emergency Actions.
S42 Automatic Scram fal1s to shutdo the reactor arid the manual actions taken from the reactor control console are successFul in shuttir down the reactor.
1112 I
SA2.1 Automatic scram fails :o reduce reactor power < 2%
{APRM downscale)
AND Manual scram actions taken at the reactor control console ManuaI PBs. Mode Switch. ARI) successfully shutdown the reactor as indicated by reactor power < 2%
(APRM downscale)
May determThe that the conditions require a declaration of an Alert.
SATIU NSAT*
SOT-ADM-JP-200-B01 Page 6 of 11 REV. 00 4LERT
NRC Event Notification Step 5 Reviews Plant Emergency Procedures (PEP) for NRC notification requirements for an Alert.
OPEP-02.1.1, Emergency Control
- Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency states:
6.3.3 In accordance with OPEP-02.6.21, notify, or direct notification to, the Nuclear Regulatory Commission (NRC) of the emergency condition following the notification to State and local governments. NRC notification must not exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the emergency classification.
OPEP-02.1.1, Emergency Control
- Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency, Attachment 1:
F I
ALRT L_ 13 LdG NOTIFY CUN1T%
TO ACTI VML ULN IOk NOTIFICATION OF ERO WITHIN S MIlLrrES or OICLAEATION ASSI1N AF1 E ERGNCY VOMAUNICATOR rANMr FVFNT WITHIN IS MINUTES IER apEp-DLG.I r4ri OPEP-02.6.21, Emergency Communicator, states:
4.6.1 For an emergency declaration, reclassification or event termination, initiate an Initial Notification to state and counties within 15 minutes, and notity the NRC immediatety following state and counties, but no later than 60 minutes.
Determines that a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notification to the NRC is required for the EAL Classification.
- CRITICAL STEP
- SATIUNSAT*
SOT-ADM-JP-200-BO1 Page 7 of 11 REV. 00
NRC Event Notification TERMINATING CUE: When the examinee has completed Tech Spec determination and NRC Reportability this JPM is complete.
- Comments required for any step evaluated as UNSAT.
SOT-ADM-JP-200-BO1 Page 8 of 11 REV. 00
NRC Event Notification RELATED TASKS:
341225B102, Direct actions required for a Safety Limit Violation.
KIA REFERENCE AND IMPORTANCE RATING:
GEN2.1.18 3.6/3.8 Ability to make accurate, clear, and concise logs, records, status boards, and reports.
REFERENCES:
001-01.07 Technical Specifications TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin
- Conduct of Operations REASON FOR REVISION:
New JPM for 2012 NRC Exam.
SOT-ADM-JP-200-B01 Page 9 of 11 REV. 00
NRC Event Notification Validation Time:
15 Minutes Time Taken:______
APPLICABLE METHOD OF TESTING Performance:
Simulate
Actual X
Unit:
2 Setting:
Control Room
Simulator Admin X
Time Critical:
Yes
No X
Time Limit N/A Alternate Path:
Yes
No X
EVALUATION Trainee:_______________________________
JPM:
Pass Fail Remedial Training Required: Yes No (Reference TAP-41 I for evaluation guidance)
Comments:
Comments reviewed with performer Evaluator Signature:
Date:__________
SOT-ADM-JP-200-BO1 Page 10 of 11 REV. 00
TASK CONDITIONS:
Unit Two was performing a normal Reactor Startup in accordance with OGP-03, Unit Startup and Synchronization with the following initial conditions:
Reactor Power 5%
Reactor Mode Switch in Startup Reactor pressure 928 psig Core flow 9.5% of rated core flow A feedwater transient subsequently occurs with the following observations:
When Reactor power reached 28% RTP the RO inserted a manual reactor scram.
Reactor pressure was maintained at 928 psig.
Core Flow peaked at 9.6% of rated flow.
INITIATING CUE:
You are directed by the Shift Manager to evaluate these plant conditions and determine:
(1) any required Technical Specification actions and (2) the earliest required NRC notification.
1IZhffUt1ktAIL DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC C004 (RO)
LESSON TITLE:
LESSON NUMBER:
Determine Primary Containment Water Level and Evaluate PCPL-A.
SOT-ADM-JP-200-B0 I REVISION NO:
01 Prepared By:
Concurred By Validated By:
Approved By:
Dan Arhelger Nuclear Operations Instructor 1/
Nuclear Operations Instructor
/,
ions Department Representative Facility
JLJ$LLt LLIII Determine Primary Containment Water Level and Evaluate PCPL-A.
SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to trainee)
- 1. The applicable procedure section WILL be provided to the trainee.
- 2. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
3.
If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
Read the following to trainee.
TASK CONDITIONS:
TASK CONDITIONS:
1.
An accident is in progress on Unit Two. The Unit SCO is directing actions of EOP RVCP and EOP-02-PCCP.
2.
480 VAC Substation E7 is de-energized due to a fault. All other electrical buses are energized.
3.
ERFIS is unavailable.
4.
See Attachment I for the Containment parameter readings that are available on the RTGB.
INITIATING CUE:
You are directed to determine Primary Containment water level per EOP-01-UG, 1. Determine the current region of operation (Safe/Unsafe) on Primary Containment Pressure Limit A (PCPL-A).
LOT-ADM-JP-300-B01 Page 2 of 11 REV. 0
,1 LIiL JYJIWtZJII!Itk Determine Primary Containment Water Level and Evaluate PCPL-A.
PERFORMANCE CHECKLIST START TIME:
Step I
- Obtain a current revision of EOP-01-UG and AOP-36.1.
Current Revision of EOP-O1-UG and AOP-36. I obtained.
SATIU NSAT*
Step 2 Determine suppression pool water level instruments cannot be used to determine primary containment water level since CAC-LI-2601-1 is above +2 feet and CAC-LR 2602 is powered from E7 and is de-energized.
Determine suppression pooi water level instruments cannot be used to determine prima!) containment water.
SATIUNSAT*
Step 3 Determine suppression chamber pressure instruments cannot be used to determine primary containment water level since CAC-Pl-1257-2B is not less than 75 psig and CAC-Pl-1257-2A is powered from E7 and is de-energized Determine suppression chamber pressure instruments cannot be used to determine primary containment water.
SATIUNSAT*
LOT-ADM-JP-300-B01 Page 3 of 11 REV. 0
h1tIiiIIIIIiI?
Determine Primary Containment Water Level and Evaluate PCPL-A.
Step 4 Determine primary containment water level should be calculated using CAC-Pl-1 230 and CAC-Pl-4176 since both instruments have power and suppression chamber pressure is not less than 75 psig, determine CAC-PR-1257-1 is powered from E7 and should not be used.
Determine primaiy containment water level should be calculated using CAC-PI 1230 and CAC-PI-4176 SATIUNSAT*
Step 5 Calculate primary containment water level to be 2.3 ft/psi (72.5 67.5) + 28.5 ft.
Primary containment water level calculated to be 40 feet.
- CRITICAL STEP
- SATIUNSAT*
Step 6 Determine operation to be in the safe region of PCPL-A using the PCPL-A graph, calculated primary containment water level and CAC-Pl-41 76 for drywell pressure, (or by using CAC-Pl-1230 reading <70 psig).
Determine PCPL-A is in the Safe region.
- CRITICAL STEP
- SATIUNSAT*
COMPLETION TIME:
TERMINATING CUE: When primary containment water level is calculated, and PCPL-A is determined to be in the Safe region, this JPM is complete.
- Comments required for any step evaluated as UNSAT.
LOT-ADM-JP-300-B01 Page 4 of 11 REV. 0 ir
!LYJILJIIIII1IIII Determine Primary Containment Water Level and Evaluate PCPL-A.
RELATED TASKS:
200602B501, Determine Primary Containment water level per EOP-O1-UG KIA REFERENCE AND IMPORTANCE RATING:
GEN2.l.7 44/4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
REFERENCES:
OEOP-O1 -UG OAOP-36. I TOOLS AND EQUIPMENT:
Student may use calculator.
SAFETY FUNCTION (from NUREG 1123):
Administrative Conduct Of Operations REASON FOR REVISION:
Revised JPM to support 2012 NRC Exam.
LOT-ADM-JP-300-B01 Page 5 of 11 REV. 0
/
v W IW J
Determine Primary Containment Water Level and Evaluate PCPL-A.
Validation Time:
15 Minutes APPLICABLE METHOD OF TESTING Performance:
Simulate
Actual x
Unit:
2 Setting:
Control Room
Simulator____ (N/A for Admin or In-Plant JPMs)
Time Critical:
Yes
No x
Time Limit N/A Alternate Path:
Yes
No x
EVALUATION Trainee:_______________________________
JPM:
Pass Fail Remedial Training Required: Yes No Did Trainee Verify Procedure as Authorized Copy?:
Yes No Comments:
Comments reviewed with Student Evaluator Signature:
Date:__________
r REV.O LOT-ADM--J P-300-BO 1 Page 6 of 11
Ji!IiLiIr TASK CONDITIONS:
1.
An accident is in progress on Unit Two. The Unit SCO is directing actions of EOP-O1-RVCP and EOP-02-PCCP.
2.
480 VAC Substation E7 is de-energized due to a fault. All other electrical buses are energized.
3.
ERFIS is unavailable.
4.
See Attachment 1 for the Containment parameter readings that are available on the RTGB.
INITIATING CUE:
You are directed to determine Primary Containment water level per EOP-01-UG, Attachment II. Determine the current region of operation (Safe/Unsafe) on Primary Containment Pressure Limit A (PCPL-A).
4-E C.)
4-Q
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E
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LEEL IcAC-U2601 1 L
E4E8 DREU PRESSURE CAC P14176 E4 su pp POOL PRES3URE CkC-PI12572A E3-E7 iIItdø Attachment I c
U p
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[1 B
6 4
2
.7 4
6 8
10 50 25 245 145 45 L
E F
E E
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65 63
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GAUGE ZERO Attachment I 71 R
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E L
L F
E E
T 75 50 25 75 50 0
P G
P C
25 P
R E
S S
U R
E I
cX DRYELL [1 DRTVELL SUPRESSION IATER LEVEL INDKI PRESS IN[IIDITK)N OL PRESSURE I CPCLI121 I
I CP112572B UPS E4-E8
IIIIIIIIIIIJLJILA £i!L JrdJUA!AAh1UIIIII1I PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC EC LESSON TITLE:
LESSON NUMBER:
Develop a Clearance Boundary
- RBCCW Pump 2C.
LOT-ADM-JP-201 -E04 REVISION NO:
02 Depament Representative Date Prepared By:
Concurred By Validated By:
Nuclea_perations Instructor Date
,h-e Nuclear Operations Instructor Date Approved By:
Develop a Clearance Boundary
- RBCCW Pump 2C SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to performer)
- 1. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
2.
An answer key is provided to the evaluator.
3.
If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
4.
If desired, the evaluator may provide the examinee with a copy of OPS-NGGC-1 301, 20P-21, and the referenced prints.
- 5. The evaluator should have available copies of prints D-02538 Sheets 1 & 2 and LL-09241 sheets 8 & 24 to support performance of JPM, or perform JPM in a location where a print machine is available.
- 6. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
LOT-ADM-JP-201-E04 Page 2 of 11 REV. 02
Develop a Clearance Boundary
- RBCCW Pump 2C Read the following to the JPM performers TASK CONDITIONS:
- 1. You are an operator in the Work Control Center. PASSPORT (Equipment Tag Out) is not available for use. No historical clearances are available for review.
2.
A Clearance has been requested by maintenance to place RBCCW Pump 2C under clearance for pump packing replacement.
3.
RBCCW Pumps 2A and 2B will remain running.
4.
Hanging the clearance will not result in any radiation dose.
INITIATING CUE:
The WCC SRO directs you to propose a Clearance Boundary for RBCCW Pump 2C by completing Attachment 4 of OPS-NGGC-1 301, Equipment Clearance procedure and determine if any second verification is required to hang the clearance.
LOT-ADM-JP-201-E04 Page 3 of 11 REV. 02
Develop a Clearance Boundary - RBCCW Pump 2C ANSWER KEY ATTACHMENT 4 Page 1 of I EQUIPMENT CLEARANCE CHECKLIST Clearance No.
N/A Page of Checklist Type:
Hang LiLift LiBoundary Change (Check one)
INT Passport Short Name (PRINT)
INT Passport Short Name (PRINT)
- Independent/Concurrent Verification Required?QLaQ If NO, N/A the Blocks Seq Action Type Tag Id Position Equipment/Component Completed By Verified By*
I N/A No Tag 2-RCC-OFF or RBCCW Pump 2C or CIT CS-449 HUNG Control Switch 2
N/A RED 2-2XE-OPEN or RBCCW Pump 2C EA7-52 OFF Circuit Breaker 3
N/A RED 2-RCC-CLOSED RBCCW Pump C V34 Discharge Valve 3
N/A RED 2-RCC-CLOSED RBCCW Pump C V30 Suction Valve 4
N/A No Tag 2-RCC-OPEN RBCCW Pump C Suction or RED V128 Drain Valve 4
N/A No Tag 2-RCC-OPEN RBCCW Pump C Discharge or RED V129 Drain Valve 4
N/A No Tag 2-RCC-OPEN RBCCW Pump C Casing or RED V301 Vent Valve Sequence must have the breaker first, the discharge/suction valves second, and operating drain/vent valves last.
If the control switch is included it must be before the breaker.
- Minimum requirements for satisfactory boundary are breaker, discharge valve, suction valve, at least one drain valve, and vent valve.
LOT-ADM-JP-201 -E04 Page 4 of II REV. 02
Develop a Clearance Boundary - RBCCW Pump 2C PERFORMANCE CHECKLIST NOTE:
If desired, the examiner may provide a copy OPS-NGGC-1 301 to the examinee.
START TIME NOTE:
If desired, the examiner may provide a copy of the required prints to the examinee (D-02538, Sheets I & 2, LL-9241, Sheets 8 & 24) and 20P-21 lineups.
NOTE:
CITs can have position OFF or In-Place I HUNG Step I
- Obtain copies of required prints (D-02538, Sheets I & 2, LL-09241, Sheets 8 & 24).
Drawings D-02538, Sheets I & 2, LL-09241, Sheets 8 & 24 obtained.
SATIU NSAT*
Step 2
- Identify control switch 2-RCC-CS-449 should be placed to OFF.
Determine 2-RCC-CS-449 should be placed to OFF.
SATIU NSAT*
Step 3
- Identify breaker 2XE Compt EA7 should be RED tagged to OFF.
Determine 2XE Compt EA 7 should be RED tagged to OFF.
- CRITICAL STEP
- SAT/UNSAT*
LOT-ADM-JP-201-E04 Page 5 of 11 REV. 02
Develop a Clearance Boundary
- RBCCW Pump 2C NOTE:
Sequence of suction or discharge valve closing is not critical so long as the pump motor is de-energized.
Step 4
- Identify discharge valve 2-RCC-V34 should be RED tagged closed.
Determine 2-RCC-V34 should be RED tagged closed.
- CRITICAL STEP
- SAT/UNSAT*
Step 5
- Identify suction valve 2-RCC-V30 should be RED tagged closed.
Determine 2-RCC-V30 should be RED tagged closed.
CRITICAL STEP
- SATIUNSAT*
NOTE:
Either 2-RCC-V128 or 2-RCC-V129 is critical. Both are not required to meet critical task standards.
NOTE:
Sequence of drain or vent valve opening is not critical.
Step 6
- Identify drain valve 2-RCC-V128 should be open.
Determine 2-RCC-V1 28 should be open.
- CRITICAL STEP
- SAT/UNSAT*
Step 7
- Identify drain valve 2-RCC-V129 should be open.
Determine 2-RCC-V1 29 should be open.
- CRITICAL STEP
- SATIUNSAT*
Step 8
- Identify vent valve 2-RCC-V301 should be open.
Determine 2-RCC-V301 should be open.
- CRITICAL STEP
- SAT/UNSAT*
LOT-ADM-JP-201-E04 Page 6 of 11 REV. 02
Develop a Clearance Boundary
- RBCCW Pump 2C Step 9 Determines that an Independent Verification is required for the Clearance Hang.
NOTE:
A I arg ctM:ies equire Verification.
Identifies that the clearance hang has to be independently verified.
- CRITICAL STEP SATIUNSAT*
Step 10 Submit proposed boundary to WCC SRO.
Proposed boundary submitted to WCC SRO.
SATIUNSAT*
TERMINATING CUE: When the proposed boundary has been submitted, this JPM is complete.
TIME COMPLETED
- Comments required for any step evaluated as UNSAT.
LOT-ADM-JP-201-E04 Page 7 of 11 REV. 02
Develop a Clearance Boundary - RBCCW Pump 2C RELATED TASKS:
299020B301, Develop A Clearance per OPS-NGGC-1 301 KIA REFERENCE AND IMPORTANCE RATING:
2.2.13 (4.1/4.3)
Knowledge of tagging and clearance procedures
REFERENCES:
OPS-NGGC-1 301 20P-21 D-02538, Sheets I & 2 LL-09241, Sheets 8 & 24 TOOLS AND EQUIPMENT:
Referenced prints and procedures.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin
- Equipment Control REASON FOR REVISION:
Revised to support HLC 2012 NRC exam.
Changed NGGC-1 301, Attachment 4 to latest revision (rev 29). Corrected JPM number in footer (ADM vs OJT). Added signature page.
LOT-ADM-JP-201-E04 Page 8 of 11 REV. 02
Develop a Clearance Boundary
- RBCCW Pump 2C Validation Time:
20 Minutes (approximate).
Time Taken:
APPLICABLE METHOD OF TESTING Performance:
Simulate
Actual X
Unit:
2 Setting:
In-Plant
Simulator Admin X
Time Critical:
Yes
No X
Time Limit N/A Alternate Path:
Yes
No X
EVALUATION Performer:
JPM:
Pass Fail Remedial Training Required: Yes No (Reference TAP-41 I for evaluation guidance)
Comments:
Comments reviewed with Student Evaluator Signature:
Date:__________
LOT-ADM-JP-201-E04 Page 9 of 11 REV. 02
TASK CONDITIONS:
- 1. You are an operator in the Work Control Center. PASSPORT (Equipment Tag Out) is not available for use. No historical clearances are available for review.
- 2. A Clearance has been requested by maintenance to place RBCCW Pump 2C under clearance for pump packing replacement.
3.
RBCCW Pumps 2A and 2B will remain running.
4.
Hanging the clearance will not result in any radiation dose.
INITIATING CUE:
The WCC SRO directs you to propose a Clearance Boundary for RBCCW Pump 2C by completing Attachment 4 of OPS-NGGC-1 301, Equipment Clearance procedure and determine if any second verification is required to hang the clearance.
ATTACHMENT 4 Page 1 of 1 EQUIPMENT CLEARANCE CHECKLIST Clearance No.
N/A Page of Checklist Type:
LiHang EJLift LiBoundary Change (Check one)
INT Passport Short Name (PRINT)
INT Passport Short Name (PRINT)
- Independent/Concurrent Verification Required? YES / NO If NO, N/A the Blocks Seq Action Type Tag Id Position Equipment/Component Completed Verified By*
By N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Continued Y/N Vital Record until information is entered into the computer program.
-,_j&
DUKE ENERGY CAROLINAS BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC EC (SRO)
LESSON TITLE:
LESSON NUMBER:
Determine Protected Equipment Actions SOT-ADM-JP-201 -DOl REVISION NO:
00 Prepared By:
Concurred By Validated By:
Approved By:
Dan Arhelger Nuclear Operations Instructor Date i41a-
/2 Nuclear Operations Instructor Date A
)
Oprations Department Representative Date 11/2 9/1 Facili y Representative
/ Date
Determine Protected Equipment Actions SAFETY CONSIDERATIONS:
None EVALUATOR NOTES: (Do not read to performer)
- 1. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
2.
If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
3.
A copy of Technical Specifications, TRM, 001-01.01, OPS-NGGC-1 311, OP lineups, and OAP-25 will be provided if requested.
- 4. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
SOT-ADM-JP-201-D01 Page 2 of 11 REV. 00
Determine Protected Equipment Actions Read the following to the JPM performers TASK CONDITIONS:
2.
An emergent clearance is being developed for the Control Building Standby Instrument Air Compressor 2-VA-2A-AC-CB.
3.
Both Units are operating at rated power.
- 4. The expected return of the equipment is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
INITIATING CUE:
The Shift Manager directs you to determine the following:
(1) Any required Technical SpecificationlTRM actions and (2) Identify the specific component name, identification number and location for any equipment that is required to be protected.
SOT-ADM-JP-201-DO1 Page 3 of 11 REV. 00
Determine Protected Equipment Actions PERFORMANCE CHECKLIST START TIME NOTE:
Sequence of step performance is not critical.
Step I Determines TS LCO 3.7.3 applies.
P.CTIONS COMP+/-TIDN COI DIllON REQUIRED ACTION TI1E k
One CREY subsystem Al Restoe CREV subjstern 7 days iriupeibI fui ieaur.Lhe Lu OPERABLE sLatus.
than Conlition B.
Determines that LCO 3.7.3, Condition A. I applies:
Step 2
- Determines TS LCO 3.7.4 applies.
ACTIONS CONDITION REQUIRED AOTtON COMPLETION TlIE A.
One conft room AC Al Rstore cotrd room AC 30 days subsystei inoperable, subsystem to OPERABLE stitu.
Determines that LCO 3.7.4, Condition A.i applies:
- CRITICAL STEP
- SATIUNSAT*
- CR!TICAL STEP
- SATIUNSAT*
SOT.-ADM-JP-201 -DOl Page 4 of II REV. 00
Determine Protected Equipment Actions Step 3 Determines TRM 3.18 applies.
REQUIRED COMPENSATORY COMPLETIOSJ CCJND1T4ON MEASURE TIME A
One contro room A.i Restore cortrol rom 7 days emergencj filtration emergency liltraton subsstern inoperable.
subsvsten, t OPERABLE status.
OR A2. 1 Prepare a plan to return 7 days thc control room emergency filtraton subsysi.ein b OPERABLE status and assign a responsible indiidual to ensure the restoration plan is carried out.
AND A2.2 Inkiate a condition report.
7day Determines that TRM 3.18, Required Compensatory Measure A. I OR A.2. I and A2.2 applies.
- CRITICAL STEP
- SATIUNSAT*
SOT-ADM-JP-201-DO1 Page 5 of 11 REV. 00
Determine Protected Equipment Actions Ii NOTE:
The site no longer maintains a Chlorine tank car in the exclusion area.
Step 4Determines TRM 3.19 applies.
REQUIRED COMPENSATORY COMPLETION COD[TiDN MEA.3URE TIME A.
Chlorine protection node of k 1 Remove the chlorine tank 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> the CREV Systm carfrorr the xcIusian inopeable for reascns other ar.
than iioperable chlorine isolatbn irstrumantation.
Q 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> k2 1 Prepare a plan to return the chlotne protection mode of the CREJ System to OPERABLE sta:us and assan a responsible hdiviiual to ensure the restoration pan is carried out.
AND A22
NOTE-----------
Conditicn report need not be generated when inoerabil[tv s due sdely to planned maintenance or sur.eilbnce testing.
8hours Initate a condition report.
Determines that TRM 3.19, Required Compensatory Measure A. I OR A.2. I and A.2.2 applies.
- CRITICAL STEP
- SATIUNSAT*
SOT-ADM-JP-201-DO1 Page 6 of 11 REV. 00
Determine Protected Equipment Actions Step 5 Evaluates the following step in OAP-25 for applicability:
- 1) Equipment will be posted as Protected if:
a) Removal of a single SSC elevates the overall risk greater than a Yellow risk condition (Orange or Red) b) Inadvertent equipment manipulation that if lost concurrently with other SSCs OR concurrent with a loss of a SSC, servicing the same mitigation function, being unavailable would cause:
i)
An unplanned increase in the overall station risk greater than a Yellow risk condition (Orange or Red) ii)
Entry into a limiting condition of operation (LCO) action statement with less than or equal to a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> completion time AND, if required action and associated completion time not met, requires changing operation mode. When the scope of the schedule test or maintenance provides assurance that the SSC under the initial LCO can have its LCO canceled prior to the newly cascaded LCO completion time, this requirement need not apply iii)
A plant transient requiring manipulation of reactor power to stabilize event.
(i.e. loss of only available LHC pump or Stator Cooling Pump)
Determines that 1)b)ii) applies which will require the other Control Building Standby Air Compressor to be protected. (Loss of the opposite division air compressor would require entry into TS 3.7.3, Required Action C. I Be in Mode 3 I2hours)
- CRITICAL STEP
- SATIUNSAT*
Step 6 Determines the required equipment components that must be logged lAW OAP 25, Attachment 6, for the minimum requirements.
7)
To ensure consistency in applying protective barriers and to maintain general awareness and component level identification, the following devices/components will be tagged at a minimum:
a Main Power Supply breaker (4 KV or 480 V).
b) Primary mover and/or component (i.e. pump motor, motor operated valve).
It is acceptable to post general areas or access/egress locations.
Determines that the B air compressor breaker and the compressor area must be protected SAT/U NSAT*
SOT-ADM-JP-201-DO1 Page 7 of 11 REV. 00
Determine Protected Equipment Actions Step 7
- Identifies the Control Building Standby Air Compressor 2B (2-VA-2B-AC-CB) located in the Mechanical Equipment Room on the 70 Turbine Building and its associated breaker C16 on 480V MCC ICA in the Cable Spread Room (23 Control Building) is the minimum required protected equipment.
Identifies Control Building Standby Air Compressor 2-VA-2B-A C-CB Breaker Cl 6 on 480V MCC I CA with a location of 23 foot (Cable Spread Room) OR may conseivatively identify the whole MCC I CA in the Cable Spread Room.
Identifies the Control Building Standby Air Compressor 2-VA-2B-AC-CB area with a location of 70 Control Building OR Mechanical Equipment Room.
May conservatively protect a train of CREV, but is not required.
- CRITICAL STEP
- SATIUNSAT*
Step 8 Notifies the Shift Manager of the Tech Spec and identified protected equipment.
Shift Manager notified of Tech Spec and protected equipment requirements.
SATIU NSAT*
TERMINATING CUE: When the TS and protective equipment requirements have been provided to the Shift Manager, this JPM is complete.
TIME COMPLETED
- Comments required for any step evaluated as UNSAT.
SOT-ADM-JP-201-D01 Page 8 of 11 REV. 00
Determine Protected Equipment Actions RELATED TASKS:
341004B102, Determine actions required for Limiting Conditions for Operation per 001-01.01 and Technical Specifications.
KIA REFERENCE AND IMPORTANCE RATING:
2.2.14 (3.9/4.3)
Knowledge of the process for controlling equipment configuration or status.
REFERENCES:
001-01.01 Technical Specifications TRM OOP-37 OAP-25 OPS-NGGC-1 311 TOOLS AND EQUIPMENT:
None SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin
- Equipment Control REASON FOR REVISION:
New JPM for 2012 NRC exam.
SOT-ADM-JP-201-D01 Page 9 of 11 REV. 00
Determine Protected Equipment Actions Validation Time:
20 Minutes (approximate).
Time Taken:
APPLICABLE METHOD OF TESTING Performance:
Simulate
Actual X
Unit:
2 Setting:
In-Plant Simulator Admin X
Time Critical:
Yes No X
Time Limit N/A Alternate Path:
Yes
No X
EVALUATION Performer:________________________________
JPM:
Pass Fail Remedial Training Required: Yes No (Reference TAP-41 I for evaluation guidance)
Comments:
Comments reviewed with Student Evaluator Signature:
Date:__________
SOT-ADM-JP-201-D01 Page 10 of 11 REV. 00
TASK CONDITIONS:
- 2. An emergent clearance is being developed for the Control Building Standby Instrument Air Compressor 2-VA-2AAC-CB.
3.
Both Units are operating at rated power.
- 4. The expected return of the equipment is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
INITIATING CUE:
The Shift Manager directs you to determine the following:
(1) Any required Technical SpecificationlTRM actions and (2) Identify the specific component name, identification number and location for any equipment that is required to be protected.
iiiriiii fzirwi Aiiiirn DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC RC LESSON TITLE:
LESSON NUMBER:
Determine Total Dose For ALARA.
LOT-ADM-JP-1 02-AOl REVISION NO:
01 Prepared By:
ations Instructor Date Concurred By Nuclear Operations Instructor Date Validated By:
Approved By:
64-:
6 perions Department Representative Date
-Th Facityepresentative 3
I Date
IIIIIIPIIV*ALsd A 1
IiIIIIF Determine Total Dose for ALARA SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
- 1. This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
- 2. A calculator may be given to Trainee.
- 3. A copy of OPS-NGGC-1 301 or OPS-NGGC-1 303 will be provided if requested.
4.
If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Appendix E, or similar to the trainee.
- 5. Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
LOT-ADM-JP-1 02-AOl Page 2 of 9 REV. 01
I1L1JIt Determine Total Dose for ALARA Read the following to the JPM performer TASK CONDITIONS:
Work is to be performed on the 2E1 1-FOO6D valve in the Unit Two Reactor Building -17 ft elevation. The workers must acquire the proper tools and travel to the job area. Three potential paths to the work area have been identified as detailed below:
Dose Path Dose Path 2 Dose Path 3 Rate Rate Rate 8 mr/hr Transit time 8 mr/hr Transit time 8 mr/hr Transit time 6 minutes 3 minutes 6 minutes 9 mr/hr Transit time 8 mr/hr Transit time 9 mr/hr Transit time 3 minutes 3 minutes 3 minutes 1 mr/hr Transit time 9 mr/hr Transit time 1 mr/hr Transit time 6 minutes 6 minutes 6 minutes 1 mr/hr Transit time 9 mr/hr Transit time 3 minutes 3 minutes 1 mr/hr Transit time 6 minutes Total Total Total Dose Dose Dose Temperature in the work area is 100°F.
Following work completion, the clearance on the valve will be removed.
It is anticipated that Independent Verification activities in contact with the valve will take 15 minutes.
INITIATING CUE:
(1)
Determine the dose received for each path the work area and identify which path maintains dose ALARA.
(2)
Determine if Independent Verification of clearance removal can I cannot be waived lAW BNP administrative procedures. (circle correct answer)
LOT-ADM-JP-1 02-AOl Page 3 of 9 REV. 01
I1IIIIII1tI!1IL1JI&
1L iiIr Determine Total Dose for ALARA PERFORMANCE CHECKLIST START TIME:
Step 1Determine dose for Path I is 1.5 mr. (8 x 0.1 + 9 xO.05 + 1 x 0.1 + lx 0.05 + 1 x 0.1)
Dose for Path I determined to be 1.5 mr.
CRITICAL STEP
- SATIUNSAT*
Step 2-Determine dose for Path 2 is 1.7 mr. (8 x 0.05 + 8 x 0.05 + 9 x 0.1)
Dose for Path 2 determined to be 1.7 mr.
CRITICAL STEP
- SAT/UNSAT*
Step 3-Determine dose for Path 3 is 1.8 mr. (8 X 0.1 + 9 X 0.05 + 1 X 0.1 ÷ 9 X 0.05)
Dose for Path 3 determined to be 1.8 mr.
- CRITICAL STEP
- SATIUNSAT*
Step 4 Determine Path 1 provides lowest overall dose.
Determined Path I provides lowest overall dose.
- CRITICAL STEP
- SATIUNSAT*
Step 5 Determine dose received for Independent Verification activity.
Uses survey map to read the top number with an asterisk at the El 1-FOO6D valve is 60 mr/hr. Determines 15 mr dose for IV activity.
- CRITICAL STEP
- SATIUNSAT*
LOT-ADM-JP-l 02-AOl Page 4 of 9 REV. 01 f V
Determine Total Dose for ALARA Step 6
- Determine that Independent Verification CAN be waived.
Determined Independent Verification CAN be waived due to estimated dose of 15 mr (15 minutes in a 60 mr/hr field).
OPS-NGGC-1303, Step 9.5.3.1 allows waiving of independent verification if exposure of greater than 10 mrem would be received or if the presence of extreme temperatures (greater than 120°F) exist.
- CRITICAL STEP
- SATIUNSAT*
COMPLETION TIME:
TERMINATING CUE: (1) Dose for the three Paths is determined and (2) Lowest dose path is determined, and (3) Independent Verification requirements are determined, this JPM is complete.
- Comments required for any step evaluated as UNSAT.
LOT-ADM-JP-1 02-AOl Page 5 of 9 REV. 01 rviw
Determine Total Dose for ALARA RELATED TASKS:
None KIA REFERENCE AND IMPORTANCE RATING:
Gen2.3.7 3.5/3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
REFERENCES:
OPS-NGGC-1 301 OPS-NGGC-1 303 TOOLS AND EQUIPMENT:
Examinee may use calculator.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin Radiation Control REASON FOR REVISION:
Revised to support HLC 2012 NRC Exam. Added determination of waiver of independent verification. Added survey map. Reformatted for consistency. Added signature page.
LOT-ADM-JP-1 02-AOl Page 6 of 9 REV. 01
Determine Total Dose for ALARA Validation Time:
10 Minutes Time Taken:
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual X
Unit:
0 Setting:
In-Plant Simulator Admin X
Time Critical:
Yes No X
Time Limit N/A Alternate Path:
Yes No X
EVALUATION Trainee:___________________________________
JPM:
Pass Fail Remedial Training Required: Yes No (Reference TAP-41 1 for evaluation guidance)
Comments:
Comments reviewed with Student Evaluator Signature:
Date:
LOT-ADM-JP-1 02-AOl Page 7 of 9 REV. 01
rJrLAiáI1RIitII!IM1I1Wit TASK CONDITIONS:
Work is to be performed on the 2E11-FOO6D valve in the Unit Two Reactor Building -17 ft elevation.
The workers must acquire the proper tools and travel to the job area. Three potential paths to the work area have been identified as detailed below:
Dose Path I Dose Path 2 Dose Path 3 Rate Rate Rate 8 mr/hr Transit time 8 mr/hr Transit time 8 mr/hr Transit time 6 minutes 3 minutes 6 minutes 9 mr/hr Transit time 8 mr/hr Transit time 9 mr/hr Transit time 3 minutes 3 minutes 3 minutes 1 mr/hr Transit time 9 mr/hr Transit time 1 mr/hr Transit time 6 minutes 6 minutes 6 minutes 1 mr/hr Transit time 9 mr/hr Transit time 3 minutes 3 minutes 1 mr/hr Transit time 6 minutes Total Total Total Dose Dose Dose Temperature in the work area is 100°F.
Following work completion, the clearance on the valve will be removed.
It is anticipated that Independent Verification activities in contact with the valve will take 15 minutes.
INITIATING CUE:
(1)
Determine the dose received for each path to the work area and identify which path maintains dose ALARA.
(2)
Determine if Independent Verification of clearance removal can I cannot be waived lAW BNP administrative procedures. (circle correct answer)
COMPONENT OR TAG NO.
NM WORK PERFORMED Qurter1v Routine Survey BRUNSWICK NUCLEAR PLANT RADIOLOGICAL SURVEY 1 R77 SURVEY NO, 09201]
OO DATE:
09/2012011 TIME DOSERATE CONTAMINATION INTS. TYPE R020 0
SURVEYOR L0ovd [1rri!
SERIAL ND.
2418 SIGNATURE FACTOR INST/SN 130311/247841 RM-1414-440 RX POw 100 EFF 27.2 010 REVIEWED H2SCFM BKCD.
BLDG RB EL-I7 AREA South RHR RWP ND.
4600-01 HP EXPOSURE WRIJO NA 3
rnrrn Smears I thr 5 counted for Iph Results <MDA RBEDT Roof It) 140 DRAIN RA-RADIATION AREA RItA NIGh RMIIATION AREA NRA LOCKED HIGh RADiATION AREA DIArION CONTROL AREA ON CONTAC 3D CM C IL - CONTAMRAJION ARFA RMA RAD1OACTIVE MATERIALS AF1FA AR-AiRMJRIE AREA x
ROPE EQUNDARY DOSE RATES IN rrREMMR n DncEA NFUTRON ftREW1IR]
DUKE ENERGY BRUNSWICK TRAINING SECTION JOB PERFORMANCE MEASURE ADMINISTRATIVE 2012 NRC EP LESSON TITLE:
LESSON NUMBER:
Determine Off-Site Release Per PEP-03.47 SOT-ADM-JP-301 -AOl REVISION NO:
03 Prepared By:
Date Concurred By Validated By:
Approved By:
Nuclear Operations Instructor Date Date
y Determine Off-Site Release per PEP-03.4.7 SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee) 1.
This is an administrative JPM designed to be administered in any setting and may be administered to multiple candidates simultaneously in a classroom setting.
2.
This JPM may be performed in any location with a computer loaded with the RASCAL Dose program 3.
The applicable procedure section WILL be provided to the trainee.
4.
An answer key is provided for the evaluator.
5.
If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021, Append ix E, or similar to the trainee.
6.
Ensure any case files saved by candidates have candidates first name attached for ease of identification (this is in addition to PEP-03.4.7 i.d. requirements).
7.
Provide filled out OPEP-03.4.7, Attachment 5 of this JPM to Trainee following INITIATING CUE delivery, with the CURRENT TIME (JPM START TIME ) AND minus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time hand written on form. Ensure all candidates have the same (specific) times entered on the form.
8.
Task standards (i.e. pass/fail criteria) for each JPM step are ITALICIZED below the step.
9.
Ensure Saved case files (dates with first Names) ARE DELETED prior to administering JPM to successive candidates. Instructions to perform this are contained in a note at the end of the JPM.
SOT-ADM-JP-301-A01 Page 2 of 14 REV. 03
Determine Off-Site Release per PEP-03.4.7 Read the following to the JPM Performer TASK CONDITIONS:
- 1. A General Emergency has been declared due to a steam line break in the Unit 1 Turbine Building which is at a positive pressure.
2.
Main Steam Line B MSIVs have failed to close and there are indications of fuel failure.
- 3. A release is in progress and the Duty Dose Projection Coordinator is on site.
- 4. The operating crew is currently executing the RRCP and RVCP with one CRD pump providing the only RPV injection source.
- 5. The Unit One reactor was shutdown 30 minutes ago.
6.
RPV level dropped below TAF 15 minutes ago and is being maintained between TAF and LL4.
- 7. There is no rain on plant site and Attachment 5 of PEP-3.4.7 has been filled out to support Actual Observation MET data entry.
INITIATING CUE:
You are directed by the Shift Manager (SEC) to:
1.
Perform an initial dose calculation per PEP 03.4.7, Automation of Off-Site Dose Projection procedure using default data where required.
2.
Determine whether projected TEDE dose at the Site Boundary exceeds Protective Action Guides (PAGs) and the Total Activity Released.
3.
Notify the Shift Manager (SEC) of the results of your projection.
SOT-ADM-JP-301-A01 Page 3 of 14 REV. 03
OPEP-03.4.7 Rev. 21 Page 26 of 31 H
CD Cl)
CD CD CD0 (I)
CD CD1
-iJm D
0 c)
ATTACHMENT 5 Page 1 of 1 Data Sheet for Dose Projection Inputs CHARACTERISTIC TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago TART i[ME Core Uncovered Time (1) Iostl (2) Returned 15 mm ago Drywell High Range Radiation Monitor Readings (RThr) flop mop Effective Filtration Yes / No NO Release Height Ground Elevated Release Duration Anticipated Length of Time S sours Shutdown Date oday Time 3Gmmnago Met Data Wind Speed Lower 2
22 Met Data Direction Lower 5
5 Stability Class 5
5 Seabreeze Yes / No O
NO
>z Cl) m m
III1LgLI Determine Off-Site Release per PEP-03.4.7 PERFORMANCE CHECKLIST Ii NOTE: Sequence is assumed unless otherwise denoted.
START TIME (Write this time for the current time and subtract 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for previous time prior to giving Attachment 5 to Trainee)
NOTE:
Trainee should calculate Shutdown and Core Uncovered times from the START TIME provided on Attachment 5.
Step I
- Obtain a current revision of PEP-03.4.7.
Current Revision of PEP-03.4. 7 obtained.
SATIUNSAT*
Step 2
- Access RASCAL 3.0.5 program.
Start the RASCAL program from the desktop screen by selecting:
Start>Programs>Emergency Preparedness >RASCAL>RASCAL 3.0.5 Shell.
SAT/UNSAT*
Step 3
- Selects the OK button (lower right) on the screen to initiate projection process.
Selects OK button (lower right) to initiate projection process.
SATIU NSAT*
NOTE:
SRO responsibilities are limited to providing dose projections using the following source terms: 1) Containment Rad Monitor; 2) Time Core is uncovered 3) Spent Fuel Events.
Step 4 Selects the model to be used (STDose).
Selects the Source Term to Dose model.
SAT!UNSAT*
SOT-ADM-JP-301-A01 Page 5 of 14 REV. 03
Determine Off-Site Release per PEP-03.4.7 NOTE:
A / mark will appear in front of each Step Location when the step is complete.
Step 5Selects EVENT TYPE and chooses NUCLEAR POWER PLANT event type selection and proceeds with the case development by selecting OK in the lower right corner of the Event Type Selection window.
NUCLEAR POWER PLANT event type selected.
SATIU NSAT*
NOTE:
Trainee should verify Plant Parameters in the program match PEP-03.4.7 default parameters.
Step 6 Selects EVENT LOCATION and chooses Brunswick Unit 1, and then clicking on OK button (lower right) on the screen.
Brunswick Unit I event location selected.
SAT/UNSAT*
Step 7Selects SOURCE TERM. and chooses TIME CORE UNCOVERED and selects OK.
TIME CORE UNCOVERED selected as Source Term.
SATIUNSAT*
Step 8 Enters the date/time the reactor was shut down.
Enters todays date and TIME START minus 30 minutes for time reactor was shutdown.
SATIUNSAT*
Step 9 Selects YES Core uncovered and enters date/time the Core was uncovered.
Core uncovered selected YES and enters todays date and TIME START minus 15 minutes for time uncovered.
SATIUNSAT*
SOT-ADM-.JP-301-AO1 Page 6 of 14 REV. 03
Determine Off-Site Release er PEP-03.4.7 Ii PROMPT:
Level remains below TAF.
ii Step 10 Selects NO for Core recovered and selects OK.
Core recovered selected NO and selects OK.
SATIUNSAT*
Step 11Selects Release Path and chooses Bypass secondary containment and selects OK.
Bypass secondaiy containment release path selected.
SATIUNSAT*
Step 12 Selects not an isolated stack, enters 0 meters for release height, and selects YES for Building Wake effects.
Not an isolated stack selected at 0 meters and Building Wake YES selected SATIUNSAT*
Step 13Verifies/enters current date and time the core was uncovered.
Core uncovered date and time verified at TIME START minus 15 minutes SATIUNSAT*
PROMPT Inform Trainee to use the default leak rate.
Step 14 Under Event - selects Leak Rate Under Event Setting
- enters the estimated flow for the coolant bypassing containmentthe default is 100 gal/mm.
Leak Rate with Leak Rate setting of 100 gal/mm SATIUNSAT*
SOT-ADM-JP-301 -AOl Page 7 of 14 REV. 03
iL+/- rI ZJIIII Determine Off-Site Release per PEP-03.4.7 PROMPT Inform Trainee the Turbine Building is positive.
Step 15 Under Event
- selects Filters Under Event Setting selects OFF selects OK.
Filters OFF and OK selected SAT!UNSAT*
Step 16Selects Meteorology and chooses ACTUAL OBSERVATION AND FORECASTS and selects CREATE NEW.
Create New under Actual Obseivation and Forecasts selected for Meteorology.
SAT!UNSAT*
NOTE:
The Minimum Met data required for dose projection model is wind speed and direction.
Air Temperature, Air Pressure, and Dew Point are all OPTIONAL.
NOTE:
Time entered for MET data must be before release start time. When Calculate Dose is performed, RASCAL will prompt the candidate to adjust this time if input was Ii PROMPT:
Inform Trainee that it is not raining.
Step 17 Selects ENTER DATA and inputs the Attachment 5 data o
Selects CBS for observed data o
Date/Time of met data o
Direction From in degrees. (75 deg) Use lower direction if available.
o Speed in mph. (22 mph) Use lower Wind Speed if available.
o Stability class (B) (Using dropdown listing, select determined classification).
o Precipitation (No Precip) (Using dropdown listing, select condition)
Met data entered with correct date and time at START TIME.
SATIUNSAT*
fi NOTE:
Trainee may elect to input both current & 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> earlier MET data.
SOT-ADM-JP-301-AO1 Page 8 of 14 REV. 03 IIIII1WiII TE
Determine Off-Site Release per PEP-03.4.7 NOTE:
The Name is the current date and time. (Example: 0213101500). This allows for repeated update of new met data saved under different names for future retrieval.
PROMPT: Have Trainee add their first name to the end (for exam retrieval) i.e. 0213101500TED First Names will follow all case file names for the remainder.
Step 18 Selects the SAVE AND PROCESS DATA button on the screen.
Enters a name for the met data set just entered and selects Return.
SAVE AND PROCESS DATA selected with todays date and START TIME as the Name and selects Return.
SAT!UNSAT*
Step 19 Ensures the saved file is highlighted and selects OK.
Saved file highlighted and selects OK.
SATIU NSAT*
Step 20Selects Calculate Doses and specifies the options and descriptions for this set of calculations.
Calculate Doses selected with close in + out 10 miles with default for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> duration.
SAT/UNSAT*
Step 21Assigns a Case Description of BNP and the current time and selects OK.
Case Description provided as BNP + current time + first name (BNPI53OTED) and OK selected.
SATIUNSAT*
Step 22 Determines projected TEDE dose at the Site Boundary (0.5 mile) exceeds PAGs.
TEDE dose at Site Boundary is ABOVE PAGs.
- CRITICAL STEP
- SATIUNSAT*
SOT-ADM-JP-301-A01 Page 9 of 14 REV. 03 IF£!!
1IIILJTh1L!iUIL1INII!tI11I1titIf Determine Off-Site Release per PEP-03.4.7 Step 23Determines Total activity released is 3.2E+08 Ci.
Total activity released is 3. 2E+08 Cl
- CRITICAL STEP
- SAT!UNSAT*
Step 24 Notifies Shift Manager of results.
Shift Manager notified of off-site dose projection results.
SATIUNSAT*
TERMINATING CUE: When the offsite dose projection has been performed, and the SM informed of results, this JPM is complete.
NOTE:
Examiner to delete any saved case files by performing the following:
On the computer used by the candidate:
Open Explore (Right click Start button and select Explore)
Navigate to C:\\Program Files\\RASCAL 3.O.5\\Save Case Delete any saved files in the Save Case folder Close Explore
- Comments required for any step evaluated as UNSAT.
TIME STOP SOT-ADM-JP-301-AO1 Page 10 of 14 REV. 03
I11ULt f3 Determine Off-Site Release per PEP-03.4.7 RELATED TASKS:
344 058 B3 02 Perform Initial Dose Projection Calculation Using Computer per PEP-03.4.7 KIA REFERENCE AND IMPORTANCE RATING:
GEN 2.4.40 2.7/4.5 Knowledge of SRO responsibilities in emergency plan implementation.
REFERENCES:
OPEP-03.4.7 TOOLS AND EQUIPMENT:
Computer loaded with RASCAL.
SAFETY FUNCTION (from NUREG 1123, Rev. 2, Supp. 1):
Admin Emergency Procedures/Plan REASON FOR REVISION:
Revised to support HLC 2012. Reformatted and corrected minor typographical errors.
Deleted unused references.
SOT-ADM-JP-301-A01 Page 11 of 14 REV. 03
Determine Off-Site Release per PEP-03.4.7 Time Required for Completion:
30 Minutes (approximate)
Time Taken:
APPLICABLE METHOD OF TESTING Performance:
Simulate Actual X
Unit:
Setting:
In-Plant
Simulator Admin X
Time Critical:
Yes
No X
Time Limit N/A Alternate Path:
Yes
No X
EVALUATION Trainee:
JPM:
Pass Fail Remedial Training Required: Yes No (Reference TAP-41 1 for evaluation guidance)
Comments:
Comments reviewed with Student Evaluator Signature:
Date:___________
SOT-ADM-JP-301-A01 Page 12 of 14 REV. 03
ATTACHMENT 5 Page i ot 1 Data Sheet for Dose Projection Inputs CHARACTERISTIC TIME Core Uncovered Time (1) Iost/ (2) Returned 13 mm go Drywell High Range Radiation Monitor Readings (RThr)
Effective Filtration Yes No NO Release Height Ground Elevated Release Duration Anticipated Length of Time 3
Shutdown Date Time c mm go Met Data Wind Speed Lower 22 Met Data Directmon Lower 75 Stability Class B
5 Seabreeze Yes / No NO NO OPEP-D3.4.7 Rev. 21 Page 26 of 31
L KM TASK CONDITIONS:
- 1. A General Emergency has been declared due to a steam line break in the Unit 1 Turbine Building which is at a positive pressure.
2.
Main Steam Line B MSIVs have failed to close and there are indications of fuel failure.
- 3. The operating crew is currently executing the RRCP and RVCP with one CRD pump providing the only RPV injection source.
4.
RPV level dropped below TAF 15 minutes ago and is being maintained between TAF and LL4.
- 5. The Unit One reactor was shutdown 30 minutes ago.
- 6. There is no rain on plant site and Attachment 5 of PEP-3.4.7 has been filled out to support Actual Observation MET data entry.
INITIATING CUE:
You are directed by the Shift Manager (SEC) to:
1.
Perform an initial dose calculation per PEP 03.4.7, Automation of Off-Site Dose Projection procedure using default data where required.
- 2. Determine whether projected TEDE dose at the Site Boundary exceeds Protective Action Guides (PAG5) and the Total Activity Released.
3.
Notify the Shift Manager (SEC) of the results of your projection.
TOTAL ACTIVITY RELEASED SITE BOUNDARY DOSE (Curies)
(Circle Choice)
Above PAGs or Below PAG5