ML070610466
| ML070610466 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/11/2006 |
| From: | NRC Region 1 |
| To: | Entergy Nuclear Operations |
| Sykes, Marvin D. | |
| Shared Package | |
| ML060800104 | List: |
| References | |
| Download: ML070610466 (54) | |
Text
Appendix C Job Performance Measure Form ES-C-1 Worksheet
'L-., Facility:
PILGRIM Task No.:
356-01 004 Task
Title:
Perform a Short Form Heat Balance JPM No.:
2007 NRC JPM RO/SRO A I a WA
Reference:
292008 K I 21 2.9 / 3.0 Examinee:
NRC Examiner:
Faci I i ty Eva I ua tor:
Method of testinq:
Date:
Simulated Performance:
Actual Performance:
X Classroom 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.
I
---/-'
Initial Conditions:
Task Standard:
Note:
Required Materials:
General
References:
Initiating Cue:
Plant conditions are as follows:
0 The plant is at 50% power.
0 Plant conditions are stable.
0 The plant process computer is out of service. of PNPS 2.1. I O is completed with no errors. The system procedure shall be followed without failure of critical tasks. Critical steps must be performed in order. Other steps may be performed out of sequence.
PNPS 9.3 Attachment 3 is an alternate method for performing a short form heat balance and provides the same results.
Steam Tables PNPS 21.10, revision 31 Perform a Short Form Heat Balance per PNPS 2.1.I
- 0.
2007 NRC JPM RO/SRO Ala NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task:
NO ii Validation Time:
5 minutes 2007 NRC JPM RO/SRO Ala NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Initialize simulator to a 50% power IC.
2007 NRC JPM RO/SRO Ala NUREG 1021, Revision 9
Appendix C Page 4 of 8 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with a check mark) u START TIME:
Performance Step: 1 Standard:
Operator reviews the applicable sections of the procedure.
Operator reviews the applicable sections of the procedure.
Comment:
Performance Step: 2 Standard:
Operator fills out datehime and performed by on Attachment 4.
Datehime and performed by recorded on Attachment 4.
Comment:
Performance Step: 3 Standard:
FI-6240-24A reading recorded.
Find and record reading for Feedwater Flow A from Fl-640-24A on Panel C905.
Comment:
Approximately I
.8 Mlb/hr.
Performance Step: 4 Standard:
FI-640-24B reading recorded.
Find and record reading for Feedwater Flow B from FI-640-24B on Panel C905.
Comment:
Approximately 1.9 Mlblhr.
2007 NRC JPM RO/SRO Ala NUREG 1021, Revision 9
Appendix C Page 5 of 8 PERFORMANCE INFORMATION Form ES-C-I
+---.-
Performance Step: 5 Standard:
Find and record reading for Feedwater Temperature A from TR-3496A on Panel C1.
TR-3496A reading recorded (RED pen).
Comment:
Approximately 310°F.
Performance Step: 6 Standard:
Find and record reading for Feedwater Temperature B from TR-3496B on Panel C1.
TR-3496B reading recorded (BLUE pen).
Comment:
Approximately 31 0°F.
Performance Step: 7 Calculate Total Feedwater flow by adding the A and B Feedwater Flows.
4 Standard:
Total Feedwater flow calculated.
Comment:
Approximately 3.7 Mlb/hr.
Performance Step: 8 Average the A and B Feedwater Temperatures loops together.
1, Standard:
Average Feedwater temperature calculated.
Comment:
Approximately 31 0°F.
Performance Step: 9 Using steam tables, determine Feedwater enthalpy.
1, Standard:
Feedwater enthalpy is recorded.
Comment:
Hf 365°F 280 BTU/lb.
2007 NRC JPM RO/SRO Ala NUREG 1021, Revision 9
Appendix C Page 6 of 8 PERFORMANCE INFORMATION Form ES-C-1 iJ
.I Performance Step: 10 Determine Core Thermal Power by subtracting Feedwater enthalpy from 1 189.6 and dividing by 3.4.13, multiply by Total feedwater flow and add 9.02.
Core Thermal Power is calculated [995 MWth (+/- 50 mw)].
Standard:
Comment:
Terminating Cue:
STOP TIME:
When the candidate has completed the core thermal power calculation, the examiner shall inform himlher that the task is complete.
TIME CRITICAL STOP TIME:
2007 NRC JPM ROfSRO Ala NUREG 1021, Revision 9
Appendix C Page 7 of 8 Form ES-C-I VERIFICATION OF COMPLETION Job Performance Measure No.:
2007 NRC JPM ROlSRO Ala
,%L.l Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
.-/
Response
Result:
Examiners Signature:
Date:
2007 NRC JPM ROlSRO Ala NUREG 1021, Revision 9 SAT UNSAT
Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET IN lTlAL CONDITIONS:
Plant conditions are as follows:
0 The plant is at 100% power.
0 Plant conditions are stable.
0 The plant process computer is out of service.
ii' INITIATING CUE:
Perform a Short Form Heat Balance per PNPS 2.1.IO.
2007 NRC JPM ROlSRO Ala NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
PI LGRl M Task No.:
- d Task
Title:
Verifv Recombiner ODeration JPM No.:
2007 NRC RO/SRO JPM A.l.b K/A
Reference:
2.1.25 2.8 / 3.1 Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testins:
Simulated Performance:
Actual Pe tfo rmance:
X Classroom 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 is operating at 50% power.
Task Standard:
Determines recombiner delta-temperature indicates recombiner is overheated.
Required Materials:
N/A General
References:
PNPS 2.4.141 Initiating Cue:
You have been directed to verify AOG recombiner operation IAW PNPS 2.4.141, section 4.2.
Time Critical Task:
NO Validation Time:
2007 NRC JPM RO/SRO A.1.b NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Initialize simulator to a 50% power IC.
Override simulator indications to give the indications as stated in the task.
2007 NRC JPM RO/SRO A.l.b NUREG 1021, Revision 9
Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)
START TIME:
4 Performance Step: I Standard:
Comment:
.I Performance Step: 2 Standard:
Determines recombiner outlet temperature.
Determines recombiner outlet temperature is approximately 575°F.
Evaluate recombiner outlet temperature utilizing Attachment 2 of PNPS 2.4.141.
Determines recombiner outlet temperature (575°F) is between the high and low limits at 50% power.
Comment:
4 Performance Step: 3 Determines recombiner inlet temperature Standard:
Determines recombiner inlet temperature is approximately 300°F.
Comment:
4 Performance Step: 4 Evaluate recombiner delta-temperature utilizing Attachment 1 of PNPS 2.4.141.
Standard:
Comment:
2007 NRC JPM RO/SRO A.l.b Determines recombiner delta-temperature is approximately 275°F. Determines recombiner is overheated.
NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue:
This JPM is complete.
d STOP TIME:
TIME CRITICAL STOP TIME:
2007 NRC JPM RO/SRO A.l.b NUREG 1021, Revision 9
Appendix C Page 5 of 6 VERI F I CAT I 0 N 0 F CO M P L ET I ON Form ES-C-I 4 Job Performance Measure No.:
2007 NRC JPM RO/SRO A.l.b Examineels Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
2007 NRC JPM RO/SRO A.l.b NUREG 1021 Revision 9
Appendix C Page 6 of 6 JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS:
The plant is operating at 50% power.
iJ INITIATING CUE:
You have been directed to verify AOG recombiner operation IAW PNPS 2.4.141.
2007 NRC JPM ROlSRO A.1.b NUREG 1021, Revision 9
Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:
PI LGRlM Task No.:
k J Task
Title:
Prepare a Danqer Taqout JPM No.:
Reference:
2.2.13 3.6 Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testinq:
Simulated Performance:
Actual Performance:
Classroom 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.
V Initial Conditions:
Maintenance has determined that the VAC-1068 heating coil must be replaced.
Task Standard:
All VAC-106B heating coil tagging points identified.
Required Materials:
General
References:
PNPS 2.2.44 revision 14 EN-OP-102 Initiating Cue:
You have been directed to verify VAC-106A is running IAW PNPS 2.2.44 and prepare a tagout for replacement of the VAC-106B heating coil using SOMS.
Time Critical Task:
NO Validation Time:
25 minutes
,e.
2007 NRC JPM RO A2 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet N/A 2007 NRC JPM RO A2 SIMULATOR SETUP NUREG 1021, Revision 9
Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION L/*
(Denote Critical Steps with a check mark)
START TIME:
NOTE:
Performance Step: 1 Standard:
Comment:
Performance Step: 2 Standard:
Comment:
Performance Step: 3 Standard:
Comment:
2007 NRC JPM RO A2 Provide operator with a copy of PNPS 2.2.44.
Review the applicable sections of PNPS 2.2.44.
Review section 7.2.2 of PNPS 2.2.44.
STARTNERIFY that the unit to remain in service is running.
Verifies VAC-106A is running.
Review the applicable sections of the tagout procedure.
LOCATE and review EN-OP-102.
NUREG 1021, Revision 9
Appendix C Page 4 of 6 PERFORMANCE INFORMATION Form ES-C--l
.-\\-;
Performance Step: 4 Standard:
4 4
4 4
Comment:
Terminating Cue:
I STOP TIME:
Develop a tagout in SOMS which isolates the VAC-106B heating coil.
Operator develops a tagout in SOMS which isolates the VAC-106B heating coil. Isolation points should be:
0 24-HO-429 - Closed 0
24-HO-427 - Closed 0
VAC-1O6B Control Switch - Off VRC-1028 Control Switch - Off B19116B-Off Bl9114-Off TIME CRITICAL STOP TIME:
2007 NRC JPM RO A2 NUREG 1021, Revision 9
Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION 4
2007 NRC JPM RO A2 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
v
Response
Result:
SAT UNSAT Examiners Signature:
Date:
2007 NRC JPM RO A2 NUREG 1021, Revision 9
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
Maintenance has determined that the VAC-106B heating coil must be replaced.
INITIATING CUE:
2007 NRC JPM RO A2 You have been directed to verify VAC-106A is running IAW PNPS 2.2.44 and prepare a tagout for replacement of the VAC-1066 heating coil using SOMS.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
PILGRIM
.u' Task No.:
299-03-04-010 Task
Title:
Conduct a Danqer Taqout /
JPM No.:
2007 NRC JPM SRO Ternporarilv Lift Taqs A2 K/A
Reference:
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testinq:
Simulated Performance:
Actual Performance:
X Classroom 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:
Maintenance has determined that the spectacle flange on the RHR suction piping from the Fuel Pool Cooling system requires repair.
.e' Task Standard:
The operator shall prepare a tagout properly isolating the spectacle flange on the RHR suction piping from the Fuel Pool Cooling system with an isolation valve. Following this task, the operator will prepare a temporary lift allowing manual cycling of 19-HO-167.
Required Materials:
N/A General
References:
PNPS 1.4.5 Revision 74 EN-OP-I 02 Initiating Cue:
Prepare a tagout using SOMS to isolate the spectacle flange on the RHR suction piping from the Fuel Pool Cooling System.
Time Critical Task:
NO Validation Time:
~- '-.-'
2007 NRC JPM SRO A2 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet N/A 2007 NRC JPM SRO A2 SIMULATOR SETUP NUREG 1021, Revision 9
Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION d
(Denofe Crifical Steps with a check mark)
START TIME:
Performance Step: I Standard:
Review the applicable sections of the procedure.
Operator reviews the applicable section of the procedure.
Evaluators Note:
Comment:
This task is covered in 1.4.5 and EN-OP-102.
Performance Step: 2 Develop a tagout using SOMS which isolates the spectacle flange.
d Standard:
Operator develops tagout in SOMS which isolates the spectacle flange. Isolation points should be 1001-1 03, 19-HO-167 and 19-HO-186 (or equivalent isolation).
Evaluators Cue:
When the operator has prepared the tagout, cue him/her that the tagout is hung, the spectacle flange has been cut out and maintenance has installed blank flanges per their MR.
19-HO-167 now needs to be manually cycled for another MR.
They are to temporary lift tags on 19-HO-I67 to allow cycling the valve and also ad tags on any other components to ensure that the RHR or FPC system cannot be pumped out the opening.
Comment:
Performance Step: 3 Add tags to the blank flange on the FPC side of the flange fitting.
Standard:
Standard:
Operator uses SOMS to generate a new tag out which includes the previous boundaries plus the flanges.
Operator uses SOMS to write a temporary lift for the Tag on 19-HO-167.
Comment:
2007 NRC JPM SRO A2 NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION
'-/
Terminating Cue:
STOP TIME:
This JPM is complete.
TIME CRITICAL STOP TIME:
2007 NRC JPM SRO A2 NUREG 1021, Revision 9
Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2007 NRC JPM SRO A2 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
2007 NRC JPM SRO A2 NUREG 1021, Revision 9
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
Maintenance has determined that the spectacle flange on the RHR suction piping from the Fuel Pool Cooling system requires repair.
INITIATING CUE:
2007 NRC JPM SRO A2 Prepare a tagout using SOMS to isolate the spectacle flange on the RHR suction piping from the Fuel Pool Cooling System.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-I Worksheet Facility:
PILGRIM Task No.:
Ll Task
Title:
Determine Stay time for Work to be JPM No.:
2007 NRC JPM Performed RO/SRO A3 WA
Reference:
G2.3.10 2.9 13.3 Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testina:
Simulated Performance:
Actual Performance:
Classroom 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:
You have been directed to perform vent and fill operations in the RWCU Heat Exchanger Room.
Task Standard:
Determine Stay Time.
Required Materials:
General
References:
C-GT-01-02 PNPS 1.3.114 Initiating Cue:
The Work Control Supervisor directs you to select the appropriate RWP for the work to be performed, select the appropriate Survey Map, and determine stay time in the general work area.
Time Critical Task:
NO Validation Time:
10 minutes 2007 NRC JPM ROfSRO A3 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-7 Worksheet SIMULATOR SETUP Provide examinee with three (3) survey maps and four (4) RWPs to choose from.
2007 NRC JPM RO/SRO A3 NUREG 1021, Revision 9
Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark) ii START TIME:
Evaluators Note:
Evaluators Cue:
Provide applicant with Survey Maps to choose from.
Direct examinee to assume all radiation exposure received is in the general area.
LOCATE survey map for the task to be performed. (Map #56).
.( Performance Step: I Determine applicable survey map.
Standard:
Comment:
.( Performance Step: 2 Determine RWP that provides coverage of the task performed.
Standard:
LOCATE and REVIEW RWP #06-0015, which allows vent and fill activities.
Comment:
.( Performance Step: 3 Determine Stay Time in work area.
Standard:
Based upon general area radiation levels in the RWCU Heat Exchanger Room and the required setpoint of alarming dosimeter, DETERMINE that stay time will be 80 minutes based on 90 mWhr general area radiation and 120 mR dose alarm.
Comment:
Terminating Cue:
This JPM is complete.
STOP TIME:
TIME CRITICAL STOP TIME:
J 2007 NRC JPM RO/SRO A3 NUREG 1021, Revision 9
Page 4 of 5 Form ES-C-I Appendix C VERIFICATION OF COMPLETION
- LJ Job Performance Measure No.:
2007 NRC JPM RO/SRO A3 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
I
\\---
Response
Result:
SAT UNSAT Examiners Signature:
Date:
2007 NRC JPM RO/SRO A3 NUREG 1021, Revision 9
Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET
...J INITIAL CONDITIONS:
You have been directed to perform vent and fill operations in the RWCU Heat Exchanger Room.
INITIATING CUE:
The Work Control Supervisor directs you to select the appropriate RWP for the work to be performed, select the appropriate Survey Map & determine stay time in the general work area.
2007 NRC JPM RO/SRO A3 NUREG 1021, Revision 9
PILGFUM NUCLEAR POWER STATION RADIOLOGICAL WORK PERMIT 06-5006 Rev. 01 RWP
Title:
PROCESS BLDG MECH / ELECT MAINT ON EQUIP W/
LOW RADIOLOGICAL IMPACT.
?equesting Department::
AAINT
!06-5006!
NRC Code:
MAINT RWP Type: Start Date Closed Date Review Datr Routine 01/01/07 12/31/07 JobLocation:VARIOUS RADIOLOGICAL CONDITIONS I
LIMITING I===
- EE SURVEY OR MAPS
<.3DAC GENERAL REQUIREMENTS Pre-job Briefing: NOT Required I Post Job Review: NOT Required ACTIVITY REQUIREMENTS 0 1 MECHIELEC CORRECTIVE MAINT. ROUTINE PMS &SURVEILLANCES WORK HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None 02 MANAGEMENT TOURS AND INSPECTION HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 10, Rate Alarm: 85, Chirp Rate: None 03 PLANNERS INSPECTION HIGH RAD.AREAS: N Rp Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None 04 TURBINE DECK CRANE PM HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 40, Rate Alarm: 85, Chirp Rate: None 05 A & B RHR QUADS HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None 06 A RHR VALVE ROOM HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None 07 TOP OF THE EAST & WEST HCU MEZZANINES HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None 08 REACTOR WATER SAMPLE SINK HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None 09 REACTOR WATER CLEANUP PUMP ROOMS HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None
.O CONDENSATE PUMP PIT RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None HIGH RAD.AREAS: N T
(12/00)
i PILGRIM NUCLEAR POWER STATION RADIOLOGICAL WORK PERMIT 06-5006 Rev. 01 RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None
~ I G H RAD.AREAS: N 12 TURBINE BUILDING VENTILATION DUCT PLATFORM ON TURBINE DECK 5 1 ACROSS FROM THE A RFP RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, C h q Rate: None HIGH RAD.AREAS: N 13 CONDENSER BAY SOUTHEAST DOOR HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None 14 RADWASTE -1 NON HIGH RADIATION AREAS TANK & PUMP ROOMS RP Coverage: Periodic, Dose A l a m 20, Rate Alarm: 85, Chirp Rate: None HIGH RAD.AREAS: N 15 AOG FOYER TO THE OLD CONDENSER BAY DOOR 23 HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chirp Rate: None 16 RADWASTE TRUCKLOCK HIGH RAD.AREAS: N RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 85, Chip Rate: None WORKER SPECIAL INSTRUCTIONS (SI)
PERFORM A FRISK IMMEDIATELY UPON EXITING A CONTAMINATED AREA AT THE NEAREST FRSIKER.
VISUALLY CHECK DOSIMETER AT LEAST EVERY 10 TO 15 MINUTES IN HIGH RADIATION AREAS AND AT PERIODIC OR CONSTANT COVERAGE IS EQUIVALENT TO INTERMITTENT OR CONTINUOUS COVERAGE, SKULL CAP IN LIEU OF HOOD FOR LOW RISK WORK AS DET. BY RP ONOBLE GAS AREAS ALLOWED ON THIS RWP UNO BREACHES ON THIS RWP WITHOUT RP PERMISSION DWORK AREAS TO BE SURVEYED ROUTINELY EVERY 30 DAYS OR AT THE INTERVAL SPECIFIED IN ROUTINE MATRIX
,EAST EVERY 60 MINUTES IN NON-HIGH RADIATION AREAS.
RESPECTIVELY, AS FOUND IN EN-RP-141.
- SEE ALARA REQUIREMENT SHEET**
MOVE COMPONENTS TO LOW DOSE AREA FOR WORK WHEN PRACTICAL.
WORKERS REQUIRED TO REVIEW APPROPRIATE SURVEY MAP FOR CURRENT RAD. CONDITIONS.
CATCH CONTAINMENT AND ABSORBENT MATERIAL REQUIRED TO CONTAIN ALL LIQUIDS.
CONTACT RP FOR SURVEY PRIOR TO ENTEFUNG AREAS ABOVE 8.
NO ENTRY TO AREAS AVERAGING >50K DPM/100 CM2.
NO ENTRY TO POSTED HIGH RADIATION AREAS.
SURVEY REQUIRED WHEN CHANGES IN RADIOLOGICAL CONDITIONS ARE EXPECTED.
CONTACT RP FOR SURVEY WHEN EXPOSING PREVIOUSLY INACCESSIBLE SURFACES.
NO DRESS REQUIREMENTS FOR CLEAN AREAS.
FULL PCS FOR WORK IN CAS PER RP.
PARTIAL PCs FOR WORK W/NO KNEELING, SITTING, OR CLIMBING UNLESS BRIEFED BY RP.
~~~~
~
RP TECHNICIAN SPECIAL INSTRUCTIONS (4/99)
Page 2 of 2
PILGRIM NUCLEAR POWER STATION RADIOLOGICAL WORK PERMIT NRC Code:
Title:
PROCESS BLDG MECH / ELECT MAINT ON EQUIP W/
LOW RADIOLOGICAL IMPACT.
MAINT I
32.1 Ia026e5vO.dot RWP Number 06-5006 Rev. 01
!06-5006!
(4199)
Page 3 of 2
'2 Technician RP Supervisor TETZLMF, THOMAS A i,
IRANCH, RICHARD S WK Supervisor
PILGRIM NUCLEAR POWER STATION RADIOLOGICAL WORK PERMIT 06-5002 Rev. 0 1 R
e
Title:
ROUTINE OPERATIONS AND RADWASTE OPERATIONS SURVEILLANCES.
?equesting Department: :
)PS
! 06-5002!
NRC Code:
OP/SuR RWP Type: Start Date Closed Date Review Datl Routine 0 110 1/07 0 110 1 /OS RADIOLOGICAL CONDITIONS
- EE CURRENT SURVEYS GENERAL REQUIREMENTS LIMITING CONDITIONS
<lo00 MR/HR Pre-job Briefing: NOT Required I Post Job Review: NOT Required ACTIVITY REQUIREMENTS 01 ROUTINE WORK OR SURVEILLANCES RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 20, Rate Alarm: 350, Chirp Rate: None HIGH RAD.AREAS: Y 02 OPS SUPPORT LLRT,IST,ILRT INCLUDES HRA HIGH RAD.AREAS: Y RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 100, Rate Alarm: 500, Chirp Rate: None WORKER SPECIAL INSTRUCTIONS (SI)
PERFORM A FRISK IMMEDIATELY UPON EXITING A CONTAMINATED AREA AT THE NEAREST FRSIKER.
VISUALLY CHECK DOSIMETER AT LEAST EVERY 10 TO 15 MINUTES IN HIGH RADIATION AREAS AND AT PERIODIC OR CONSTANT COVERAGE IS EQUIVALENT TO INTERMITTENT OR CONTINUOUS COVERAGE, CRD FILTERS CHANGED OUT ON RWP 0010. WORK AREAS TO BE SURVEYED EVERY 30 DAYS OR AT THE INTERVAL SPECIFIED IN THE ROUTINE MATRIX.
OEACH INDIVIDUAL ENTERING A HIGH RADIATION AREA WILL REQUIRE A BRIEFING FROM RP AND A SURVEY METER OR A BRIEFING FROM RF AND PLACED ON A STAY TIME SHEET.
OENTRY TO HIGH NOISE HIGH RAD AREAS REQUIRES ONE OF THE FOLLOWING, A SCREAMER ATTACHMENT TO THE ED, AN LED, OR PAMS LEAST EVERY 60 MINUTES IN NON-HIGH RADIATION AREAS.
RESPECTIVELY, AS FOUND IN EN-RP-141.
OCHECK DOSIMETER EVERY 10-15 MINUTES
- SEE ALARA REQUIREMENT SHEET**
MOVE COMPONENTS TO LOW DOSE AREA FOR WORK WHEN PRACTICAL.
WORKERS REQUIRED TO REVIEW APPROPRIATE SURVEY MAP FOR CURRENT RAD. CONDITIONS.
CONTACT RP FOR SURVEY PRIOR TO ENTERING AREAS ABOVE 8.
SURVEY REQUIRED WHEN CHANGES IN RADIOLOGICAL CONDITIONS ARE EXPECTED.
NO DRESS REQUIREMENTS FOR CLEAN AREAS.
FULL PCS FOR WORK IN CAS PER RP.
JORK GROUP IS TO CONTACT RP UPON EXITING HRAS-VERIFY HRA BOUNDARY IS IN PLACE.
32.1 la026e5vO.dot (1 2/00)
PILGRIM NUCLEAR POWER STATION RADIOLOGICAL WORK PERMIT 06-5002 Rev. 01
! 06-5 002!
RWJ?
Title:
ROUTINE OPERATIONS AND RADWASTE OPERATIONS NRC Code:
SURVEILLANCES.
OP/SUR RP Technician BRANCH, RICHARD S RP Supervisor FOREAKER, LOUIS C WK Supervisor
~-L-='
32.lIa026e5vO.dot (4199)
Page 2 of 2
PILGRIM NUCLEAR POWER STATION RADIOLOGICAL WORK PERMIT RWP
Title:
NMCA - INST. NEW VALVE ASSEMBLY -
NRC Code:
MAINT Pequesting Department::
RWP Type:
/IAINT.
I Job Spec5cl 09/13/06 I 9/03/07 I Job
Description:
CUT OUT OLD VALVE ASEMBLY - SOCKET WELDS, WELD IN NEW PREFABBED ASSEMBLY -
RWP Number 06-0104 Rev. 00
!06-0104!
Start Date I Closed Date IReview Datc RADIOLOGICAL CONDITIONS
- EE RP FOR BRIEFING AND REVIEW OF CONDITIONS GENERAL REQUIREMENTS Pre-job Briefing
- NOT Required I Post Job Review: NOT Required ACTIVITY REQUIREMENTS RP Coverage: Periodic, Dose Alarm: 250, Rate Alarm: 500, Chirp Rate: None 01 NMCA - INSTALL NEW 4 VALVE ASSEMBLY AND SUPPORT, SCAFF HIGH RAD.AREAS: Y LIMITING CONDITIONS WORKER SPECIAL INSTRUCTIONS (SI)
PERFORM A FRISK IMMEDIATELY UPON EXITING A CONTAMINATED AREA AT THE NEAREST FRSIKER.
VISUALLY CHECK DOSIMETER AT LEAST EVERY 10 TO 15 MINUTES IN HIGH RADIATION AREAS AND AT PERIODIC OR CONSTANT COVERAGE IS EQUIVALENT TO INTERMITTENT OR CONTINUOUS COVERAGE, ENSURE ALL TOOLS AND EQUIPMENT TAKEN INTO THE RWCU HEAT EXCHANGER ROOM ARE REMOVED AFTER THE WORK HAS BEEN COMPLETED 3DOUBLE PCS WITH FACE SHIELD WHEN BUILDING SCAFFOLD AND WORKING VALVE.
OSINGLE PCS FOR WALKDOWNS AND INSPECTIONS ONLY AS PER RP.
LEAST EVERY 60 MINUTES IN NON-HIGH RADIATION AREAS.
RESPECTIVELY, AS FOUND IN EN-RP-141.
RP TO ESTABLISH LOW DOSE WAITING AREA.
- SEE ALARA REQUIREMENT SHEET**
USE REMOTE COMMUNICATIONS AND CCTV WHEN PRACTICAL.
WORKERS REQUIRED TO REVIEW APPROPRIATE SURVEY MAP FOR CURRENT RAD. CONDITIONS.
RP TO ESCORT ANY MATERIAL >OR = 100 M W R CONTACT OR 50 MR/HR AT 30 CM.
CONTACT RP FOR SURVEY WHEN EXPOSING PREVIOUSLY INACCESSIBLE SURFACES.
CONTACT RP PRIOR TO EACH ENTRY TO DISCUSS WORK SCOPE & OBTAIN RP BRIEFING SPARE GLOVES FOR EXCHANGE REQUIRED FOR ENTRY.
d 32.1 Ia026e5vO.dot (12/00)
PILGRIM NUCLEAR POWER STATION RADIOLOGICAL WORK PERMIT NRC Code:
MAINT RWP
Title:
NMCA - INST. NEW VALVE ASSEMBLY -
(4199)
Page 2 of 2 RwP Number 06-0104 Rev. 00
!06-0 104!
W Technician VARMETTE, EDWARD J W Supervisor FITZSIMMONS, JAMES B WK Supervisor WKSUPER, SIGNATURE
PILGRIM NUCLEAR POWER STATION RADIOLOGICAL WORK PERMIT RWP
Title:
OPERATIONSRP SURVALIANCES,PMS & TOURS AND NRC Code:
EMERGENT REPAIRS IN LHRAS OP/SUR Yequesting Department::
RWP Type:
PS Job Specific I
I RWP Number 06-0015 Rev. 00
!06-00 15!
Start Date Closed Date Review Datc 01/01/07 01/01/08 I
c I
<0.3 DAC GENERAL REQUIREMENTS Pre-job Briefing: NOT Required I Post Job Review: NOT Required ACTIVITY REQUIREMENTS 01 LHRA NON-STEAM AFFECTED AREAS HIGH RAD.AREAS: Y RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose Alarm: 120, Rate Alarm: 2000, Chirp Rate: None 02 LHRA-STEAM AFFECTED AREAS RP Coverage: Periodic, Dosimetry: DLR AND SRD REQUIRED, Dose AIarm: 150, Rate Alarm: 4000, Chirp Rate: None HIGH RAD.AREAS: Y Job
Description:
SUR,PMS & TOURS - EMERGENT REPAIRS Job Location:LOCKED HIGH RAD AREAS INCLUDING STEAM EFFECTED AREAS.
RADIOLOGICAL CONDITIONS LIMITING CONDITIONS SEE RP FOR SURVEY NO DRESS REQUIREMENTS FOR CLEAN AREAS.
FULL PCS FOR WORK IN CAS PER RP.
ENSURE BOUNDARY IS RESTORED WHEN LEAVING WORK AREA.
WORKER SPECIAL INSTRUCTIONS (SI)
PERFORM A FRISK IMMEDIATELY UPON EXITING A CONTAMINATED AREA AT THE NEAREST FRSIKER.
VISUALLY CHECK DOSIMETER AT LEAST EVERY 10 TO 15 MINUTES IN HIGH RADIATION AREAS AND AT PERIODIC OR CONSTANT COVERAGE IS EQUIVALENT TO INTERMITTENT OR CONTINUOUS COVERAGE, SKULL CAPS IN LIEU OF HOODS FOR LOW RISK WORK PER RP.
0 SURGEONS GLOVES IN LIEU OF RUBBER GLOVES PER RP, BASED ON SURVEY RESULTS AND JOB EVOLUTION.
LEAST EVERY 60 MINUTES IN NON-HIGH RADIATION AREAS.
RESPECTIVELY, AS FOUND IN EN-RP-141.
RP TO ESTABLISH LOW DOSE WAITING AREA.
- SEE ALARA REQUIREMENT SHEET**
MOVE COMPONENTS TO LOW DOSE AREA FOR WORK WHEN PRACTICAL.
USE REMOTE COMMUNICATIONS AND CCTV WHEN PRACTICAL.
WORKERS REQUIRED TO REVIEW APPROPRIATE SURVEY MAP FOR CURRENT RAD. CONDITIONS.
CATCH CONTAINMENT AND ABSORBENT MATERIAL REQUIRED TO CONTAIN ALL LIQUIDS.
CONTACT RP FOR SURVEY PRIOR TO ENTERING AREAS ABOVE 8.
RP TO ESCORT ANY MATERIAL >OR = 100 MR/HR CONTACT OR 50 MR/HR AT 30 CM.
SURVEY REQUIRED WHEN CHANGES IN RADIOLOGICAL CONDITIONS ARE EXPECTED.
CONTACT Rp FOR SURVEY WHEN EXPOSING PREVIOUSLY INACCESSIBLE SURFACES.
?p TO SURVEY SPECIFIC JOB LOCATION UPON ENTRY.
PILGRIM NUCLEAR POWER STATION RADIOLOGICAL WORK PERMIT NRC Code:
Title:
OPERATIONS/RP SURVALIANCES,PMS & TOURS AND EMERGENT REPAIRS IN LHRAS OP/SuR
~
~
RP TECHNICIAN SPECIAL INSTRUCTIONS JANY REPAIRS WILL REQUIRE ROS/ALARA REVIEW FOR SEPERATE ALARA REQUIREMENT SHEET AND/OR DIFFERENT RWP.
RWP Number 06-0015 Rev. 00
!06-0015!
EVALUATE DLWSRD PLACEMENT.
IN LIEU OF STAY TIMES, LINE OF SIGHT COVERAGE MAY BE PROVIDED.
SURVEY REQUIRED WHEN CHANGES IN RADIOLOGICAL CONDITIONS ARE EXPECTED.
RP TO SURVEY SPECIFIC JOB LOCATION UPON ENTRY.
DOSE RATES AND SMEARS EVERY 7 DAYS.
RP COVERAGE EVERY 4 HOURS.
WORK AREA A/S FOR AIRBORNE GENERATING WORK PER 6.3-061 UNLESS INSTRUCTED BY ROS.
~
RP Technician BRANCH, RICHARD S RP Supervisor CHRISTOPHER, MICHAEL L WK Supervisor
-4 32.1 Ia026e5vO.dot (4199)
Page 2 of 2
Serial No.:
Ti74 7 9-7-07 Specific RWPR 06-5°s(
Dose: -A I
mrem Cal Due:
RWCU Pump Rooms
/
7 6
6 5k MDA:
H2 Level:
%a SCFM Status Map Updated Initial:.-A Time:
/ S Y 0 Serial NO.: -22? 7 Probe No.. -
Cal Due: 11-3 7 __
Collimated Probe%/
Serial No.: ___ /A/
/ a 3 Cal Due:
1-7 Cal Due:
Rx Power:
Cal Due:
nact u p c / s / r o ( + +
(Reactor Building 51')
RUNNING B SECUREDO RUNNING 0 A SECURED ra' I AIRBORNE = /t/A DAC
/--
I Reactor Water Sample Sink Reactor Building 51 u
COMMENl Peercheck: I/v HPS Rnvinw- &
I I
0 I
I I I I I 10 I
r I
/
/
6 /
I
Status Map Updated Initial:.&C-I'
' \\\\\\I\\
AIRBORNE -3J.f DAC 1
181 B
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility :
PILGRIM
~----/
Task No.:
015-05-05-003 Task
Title:
Perform Dose Assessment Usinq JPM No.:
2007 NRC JPM SRO Dapar Software A4 WA
Reference:
EK1.02 4.2 14.4 Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testinq:
Simulated Performance:
Actual Performance:
X Classroom 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:
A LOCA has occurred. The Emergency Plan is activated. Today is Wednesday July 7*h. Weather is sunny and there is no chance of rain.
The operator is required to perform a Dose Assessment and make Protective Action Recommendations.
Task Standard:
Protective Action Recommendations shall be completed without assistance using the DAPAR software. The dose assessment shall be accomplished in accordance with EP-IP-300. There shall be no failure of any critical elements.
Required Materials:
General
References:
EP-IP-300, Revision 2B Initiating Cue:
Perform an offsite dose assessment using the DAPAR computer software in accordance with EP-IP-300. Utilize the available Met tower and Main Stack high range effluent monitor data from panel C170 to perform your dose assessment. Inform me when you have determined if any additional subareas are required to be evacuated based on the dose assessment.
2007 NRC JPM SRO A4 NUREG 1021, Revision 9
Appendix C Job Performance Measure Worksheet Form ES-C-I Time Critical Task:
NO i j Validation Time:
I O minutes 2007 NRC JPM SRO A4 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP 0
0 0
Any IC with the reactor shutdown.
A General Emergency has been declared following a LOCA.
Insert I/Os for Meteorological and Radiological Data as shown on Attachment 1.
2007 NRC JPM SRO A4 NUREG 1021, Revision 9
Appendix C Page 4 of I 1 PERFORMANCE INFORMATION Form ES-C-I (Denote Crifical Steps with a check mark)
\\d START TIME:
Performance Step: I Standard:
Review the applicable sections of the procedure Operator reviews the applicable section of the procedure.
Evaluators Note:
0 0
This task is covered in EP-IP-300 section 5.0.
All functions are located on the control room dose assessment computer unless noted.
All critical steps must be performed in order unless otherwise noted.
0 Comment:
Performance Step: 2 If the computer is OFF, turn the computer ON. After the initial diagnostic checks the Windows Program Manager window will appear with the DAPARI.I program group open on the workspace. DAPAR can be chosen from the Window DAPARI.I program group by double clicking the mouse on the 1 DAPARI icon.
0 Operator turns the computer ON, if it is not already on.
0 Operator double-clicks the mouse on the I DAPARI icon.
Standard:
Evaluators Note:
Evaluators Note:
Comment:
Computer is ON.
DAPAR is started.
2007 NRC JPM SRO A4 NUREG 1021, Revision 9
Appendix C Page 5 of 11 PERFORMANCE INFORMATION Form ES-C-1
~ L. l Performance Step: 3 If the computer is on and DAPAR is not running, or another program is being run, quit to the Windows Program Manager screen. Open the DAPAR.1 program group by double clicking the mouse on the program group icon if necessary. Choose 1 DAPARI from the DAPARI.I program group by double clicking the mouse on the IDAPAR1 icon. This step may be bypassed by restarting the computer.
Standard:
Evaluators Note:
Standard:
Evaluators Note:
4 Standard:
Eva1 uators Note:
Comment:
Operator navigates to the Windows Program Manger screen, if the computer is already ON, or restarts the computer.
Windows Program Manager is running.
Operator double-clicks the mouse on the DAPARI.I program group icon.
DAPARI.I program group is OPEN. (N/A if computer was restarted in a.)
Operator double-clicks the mouse on the DAPARI.
DPAR is started.
Performance Step: 4 The introduction screen shows the application version and directs program flow to the desired assessment method. The Quick Assessment option is designed for use in the control room. The Full Assessment option is designed for use by a qualified dose assessment engineer. Four methods of dose assessment are available; monitored release, containment leakage/failure, field team analysis, and release point sample analysis. In the case of Full Assessment, multiple assessments can be performed simultaneously during a session. Once an assessment option is selected, the introduction screen cannot be recalled without quitting the application and beginning a new session.
Standard:
Eva1 uators Note:
Comment:
Operator selects Quick Assessment option.
Quick Assessment screen appears.
2007 NRC JPM SRO A4 NUREG 1021, Revision 9
Appendix C Page 6 of 11 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 5 Quick assessment operation and calculation is identical to the full 4 Standard:
Evaluators Note:
Evaluators Note:
Standard:
Evaluators Note:
Standard:
Evaluators Note:
Standard:
Evaluators Note:
Standard:
Evaluators Cue:
Standard:
Evaluators Cue:
Standard:
Evaluators Note:
assessment method.for a monitored release, but utilizes default release path and core damage assumptions for the determination of offsite doses. Default values incorporating a design basis LOCA accident are applied to allow a rapid assessment from within the control room during situations involving a monitored release. The quick assessment option takes monitor release and meteorological information inputs to determine a protective action recommendation. Information is entered directly into the appropriate text box or by selecting a choice from a group of option buttons. The quick assessment option window also contains an area for main application functions called the command bar. Base information is grouped into areas, release information and meteorological data.
Operator enters the following information to complete the Quick Assessment screen:
This data is collected from panel C170 and the Met tower.
DAPAR accepts the following information until the PARS Command Button is enabled.
0 Monitor Main Stack indication on C170 SAT / UNSAT 0
Range High Range SAT / UNSAT 0
Monitor Reading 1000 Rlhr SAT I UNSAT 0
Vent Flow Rate Provide 4000 scfm SAT / UNSAT 0
Hours After S/D Provide: I
.I 5
SAT / UNSAT 0
Towerused 220 SAT / UNSAT 2007 NRC JPM SRO A4 NUREG 1021, Revision 9
Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION Standard:
,e Evaluators Note:
Standard:
Evaluators Note:
Standard:
Evaluators Note:
Standard:
Evaluators Note:
Standard:
Evaluators Note:
Standard:
Standard:
Eva1 uato rs Cues:
Standard:
Evaluators Note:
0 TowerUsed 220 SAT / UNSAT 0
Wind Speed 6 MPH SAT / UNSAT 0
Wind Direction From 90 SAT / UNSAT 0
Delta T 1.5 Degrees F SAT / UNSAT 0
Stability Class F
SAT / UNSAT 0
Weather Conditions 0
TimeofYear 0
Timeofweek 0
Timeof Day 0
Conditions Weather conditions are given as part of the initiating cue.
0 Release Duration Provide: 5.55 SAT / UNSAT Operator clicks on the PARS Command Button.
Protective Action Recommendation screen appears.
SAT / UNSAT Comments:
2007 NRC JPM SRO A4 NUREG 1021, Revision 9
Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 The Protective Action Recommendation window evaluates the downwind dose estimate in relation to the protective action guides. The window is divided into three sections; key information, geographic evacuation illustration, and downwind radiological conditions. The key information section shows the assessment method utilized to generate the PARS, the current offsite evacuation conditions, meteorological data, and the release duration. The geographic evacuation illustration outlines the subareas within the ten mile EPZ. Subareas in which the projected dose exceeds the protective action guides are shaded to indicate an evacuation recommendation. Downwind radiological conditions provides information in tabular format.
Affected subareas and projected doses are given for the three rings surrounding the site. Dose information is color coded to indicate the projected exposure for whole body and thyroid under unprotected and sheltered conditions. A value highlighted in red indicates a whole body dose in excess of 5 Rem and a thyroid dose in excess of 25 Rem. A value highlighted in yellow indicates a whole body dose from 1 to 5 Rem and a thyroid doses from 5 to 25 Rem. Green values indicate whole body doses less than 1 Rem and thyroid doses less than 5 Rem. A command options section is available to allow movement and provide functions within the PAR window.
Operator determines subareas 6, 7, 8, and 11 require evacuation in addition to subareas 1, 3 and 12.
Subareas 6,7,8, and I 1 are recommended for evacuation by DPAR program.
Operator informs evaluator that the assigned task is complete.
4 Standard:
Evaluators Note:
Standard:
Comment:
Terminating Cue:
This JPM is complete.
STOP TIME:
TIME CRITICAL STOP TIME:
2007 NRC JPM SRO A4 NUREG 1021, Revision 9
Appendix C Page 9 of 11 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.:
2007 NRC JPM SRO A4 L--l Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
2007 NRC JPM SRO A4 NUREG 1021, Revision 9
Appendix C Page 10 of 11 Form ES-C-I JPM CUE SHEET L-INITIAL CONDITIONS:
A LOCA has occurred. The Emergency Plan is activated. Today is Wednesday July 7h. Weather is sunny and there is no chance of rain. The operator is required to perform a Dose Assessment and make Protective Action Recommendations.
INITIATING CUE:
Perform an offsite dose assessment using the DAPAR computer software in accordance with EP-IP-300. Utilize the available Met tower and Main Stack high range effluent monitor data from panel C170 to perform your dose assessment. Inform me when you have determined if any additional subareas are required to be evacuated based on the dose assessment.
2007 NRC JPM SRO A4 NUREG 1021, Revision 9
4 e
e e
e e
e e
e e
w ATTACHMENT 1 METEOROLOGICAL AND RADIOLOGICAL DATA FOR DOSE ASSESSMENT RR-I 001-608, Main Stack Effluent Recorder ((370)
RI-I 001 -608, Main Stack Effluent Indicator (C170)
- Vent Flow Rate
- Hours After S/D Tower Used Wind Speed Wind Direction MTI Temp Recorder Point 1 (Delta T)
MTI Temp Recorder Point 2
- Weather Conditions:
- Time of Year
- Time of Week
- Timeof Day 0
- Conditions
- Release Duration I/O:
110:
CUE:
CUE:
I/O:
110:
I/O:
110:
I/O:
CUES:
0 0
0 0
CUE:
2.93 3.00 4000 scfm 1:15 220 6 MPH 90 at 220 I
.6F 78°F IS u m mer Midweek All Day Good 5.55 Will be provided by the evaluator when operator requests data