ML040120750
| ML040120750 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  (DPR-064) |
| Issue date: | 12/08/2003 |
| From: | Christman R Entergy Nuclear Northeast |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-286/03-303 | |
| Download: ML040120750 (32) | |
Text
2-Sep-2003 Job Performance Measure Exam Submitted By Don Jackson Reviewed By SME Reviewmalidation By Approved By JPMNO.
1 Conduct An RCS Leakrate Surveillance Job Performance Measure Exam 9/20/2003 Date Date Date Page:
1 Date
2-Sep-2003 Job Performance Measure Exam Page:
I JPM Tasks Task ID: Generic-2.1.7
==
Description:==
CONDUCT AN RCS LEAKRATE SURVEILLANCE Trainee:
Evaluator:
Evaluator Signature Date Trainee Performance:
Satisfactory Unsatisfactory Start Time Stop Time:
When I tell you to begin, you are to perform the task listed above. I will describe general conditions standard@), initiating cue(s), and answer any questions you have. I will provide accessto anytools necessary to perform the task. You may use any approved reference material normally available. To satisfactory complete this task, you must perform or simulate each critical element correctly.
You areto inform the examiner when you have completed the task.
General Comments (For Evaluator Use):
Task Conditions:
THERE HAVE BEEN INDICATIONS OF INCREASED RCS LEAKAGE INTO CONTAINMENT BASEL1 01 RADIATION MONITORING EQUIPMENT READINGS. A MANUAL RCS LEAK RATE CALCULATIOh HAS BEEN STARTED FOUR HOURS AGO.
Task Standards :
COMPLETE THE RCS LEAK RATE CALCULATION WITHIN THE REQUIRED ACCURACY.
K&A #: 2.1.7 ABILITY TO EVALUATE PLANT PERFORMANCE AND MAKE OPERATIONAL, JUDGEMENTS BASED ON OPERATING CHARACTERISTICS, REACTOR BEHAVIOR, AND INSTRUMENT INTERPRETATION IMPORTANCE FACTOR: RO=3.7 SR04.4 Applicability: RO & SRO Estimated Completion Time: 20 minutes
2-Sep-2003 Job Performance Measure Exam Page:
I Tools Needed:
CALCULATOR Initiating Cues :
USING THE FINAL VALUES LISTED BELOW, MANUALLY CALCULATE THE RCS LEAK RATE IA V J SOP-RCS-004, BEGIN AT STEP 4.1.3.1.
Final Values:
Time-T+4 hours 0 Pzr Liquid Temp-650 degrees F 0 Boric Acid Integrator-100 gallons Primary Water Integrator-450 gallons VCT Level-24%
e Avg Pzr Level-50%
0 RCS Tavg NR RTD-569 degrees F Last Identified Leak Rate From 3 Days Ago is 1.7 GPM References :
ID SOP RCS-004 Description REACTOR COOLANT LEAKAGE SURVEILLANCE Review Date Ref Flag Safety Considerations :
NONE Consequences of hadequate Performance:
ERRANT LEAK RATE TO BASE PLANT OPERATIONAL DECISIONS FROM Performance Checklist :
Element :
Standards :
Conditions :
2-Sep-2003 Job Performance Measure Exam Page:
1 1
RECORD FINAL DATA PLACE DATA FROM CUE Cue: Hand Out The Final Readings, and Initial Data SHEET IN THE APPROPRIATE PLACE ON Attl OnAtt. 1 Comments :
Critical Task?
N Satisfactory Unsatisfactory Element :
Standards :
Conditions :
THE LEAK RATE DATA COLLECTION IS COMPLETE Comments :
2 NOTIFY CHEMISTRY THAT MAKES NOTIFICATION Cue: State That Notification Is Received and Understood IN PERSON OR VIA PHONE Critical Task?
N Satisfactory Unsatisfactory Element :
Standards :
BETWEEN INITIAL AND CORRECTLY FINAL DATA 3
CALCULATE DIFFERENCES PERFORMS CALCULATIONS Conditions :
Comments :
Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
LEVEL CONVERSION FACTOR ON ATT 2 4
PERFORM PRESSURIZER REFERS TO ATT 2, AND ENTERS DATA BASED ON PRESSURIZER TEMPERATURE Comments :
Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
5 PERFORM RCS TEMPERATURE REFER TO ATT 2 AND ENTER
2-Sep-2003 Job Performance Measure Exam Page:
I CONVERSION FACTOR CALC ON ATT 2 Comments :
DATA BASED ON RCS AVG.
TEMPERATURE IN APPROPRIATE BLOCK Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
VALUES BASED ON CORRECTLY CONVERSION FACTOR 6
CALCULATE CORRECTED PERFORMS CALCULATION Comments :
Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
LEAKAGE IN GALLONS CORRECTLY BY ADDING CORRECTED VALUE COLUMN Comments :
7 CALCULATE TOTAL PERFORMS CALCULATIONS Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
BY DIVIDING TOTAL LEAKAGE BY ELAPSED TIME 8
CALCULATE RCS LEAK RATE PERFORMS CALCULATIONS CORRECTLY WITHIN 0.1 GPM Comments :
Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
RATE REVIEW AND WITHIN 0.1 GPM Accept-.75-.95 gpm APPROVAL FORM 9
COMPLETE ATT 3, RCS CALCULATION CORRECT Actual-Mgpm
2-Sep-2003 Job Performance Measure Exam Page:
I Comments :
Critical Task?
Y Satisfactory Unsatisfactory Terminating Cues :
THE CRS IS REVIEWING THE LEAK RATE CALCULATION-THIS JPM IS COMPLETE
2-Sep-2003 Job Performance Measure Exam Parameter ime RZR Liquid emp.
oric Acid rimary Water CT Level vg PRZR eve[*
CS Tavg NR TD mperature 547 OF)
CSTavgWR TD mperature 547 O F )
ATTACHMENT 1 RCS Leakrate Calculation (Page 1 of 1)
Date NOTE IF CFMS is NOT available, THEN alternate CCR indications may be used, document indications used in applicable comment section of Attachment 3.
Computer Indicator (Step 4.1.2) (Step 4.1.3) (Step 4.1.4) Conversion (Step 4.1.9)
Point Initial Final Difference Factor Corrected Valuf Control (Final-Initial)
Room Clock (Final-Initial) 650°F "F
Tl-453 (Final-Initial)
Integrator 80.0gal gal gal gal (Final-Initial)
Integrator 29.3gal gal gal LO1 12A LT-112 (Initial-Final) gal 22.0%
Yi 19.3 gal/%
gal U0483 (Initial-Final) (Step 4.1.5)
L0480A LO481 A T0499A CFMS (Final-Initial) (Step 4.1.7) or or U0484 3TR-412 TAVG Recorder gall%
gal 570°F "F
gall O F gal LO4824 47.0%
"F KTAVG CFMS (Final-Initial) (Step 4.1.7)
O F "F
gall O F gal "F
Page:
I
.1.10) (add column) gal I
RCS Leakrate (Step 4.1.I I)
(total leakage/ elapsed time) gPm
2-Sep-2003 Job Performance Measure Exam Page:
I ATTACHMENT 2 PRZR And RCS Correction Calculation (Page 1 of 1)
ZR Level Conversion Factor (Step 4.1.5) 125 aa1/%x0.01613 (specific volume for saturated liquid at I 0 0 OF)
(specific volume for saturated liquid at average P E R liquid temperature)
CS Temperature Conversion Factor (Step 4.1.7) 11 8 gal/ O F x 0.0161 3 (specific volume for saturated liquid at 100 O F )
(specific volume for saturated liquid at average RCS temperature)
2-Sep-2003 Job Performance Measure Exam ATTACHMENT 3 RCS Leakage Review And Approval (Page 1 of 1)
Page:
I NOTE The value of 0.9 gpm used below is used, as a conservatism to ensure an unidentified leakrate of I
.O gpm is NOT exceeded without taking actions as required by Technical Specifications. LCO 3.4.13 may apply.
.o
.o
.o
.o
.o RCS leakrate (Attachment I )
gpm WHEN required for SR 3.4.13.1, THEN PERFORM SOP-RCS-005, Reactor Coolant Leakage Evaluation, to obtain value for ldentifien Leak rate.
Last Reactor Coolant Leakage Evaluation performed on (date)
Identified leak rate of gpm DETERMINE unidentified RCS Leakrate (RCS leakrate - Identified leakrate)
Does unidentified RCS Leakrate exceed 0.9 gpm?
Yes No IF Step 4.0 was answered yes, THEN PERFORM SOP-RCS-005, Reactor Coolant Leakage Evaluation.
alculation Performed by:
Signature Date Time omments:
eviewed by:
Shift Manager Date Time
2-Sep-2003 Job Performance Measure Exam JPMNO.
2 CONDUCT A VALVE LINEUP VERIFICATION Job Performance Measure Exam Submitted By : Don Jackson-9/20/2003 Date Reviewed By Date SME ReviewNalidation By Approved By Date Date Page:
I
2-Sep-2003 Job Performance Measure Exam Page:
I JPM Tasks Task ID: 2.1.29
==
Description:==
CONDUCT A VALVE LINEUP VERIFICATION AND SYSTEM STATUS CONTROL OD-35, COMPONENT VERIFICATION Trainee:
Evaluator:
Evaluator Signature Date Trainee Performance:
Satisfactory Unsatisfactory Start Time Stop Time:
When I tell you to begin, you are to perform the task listed above. I will describe general conditions standard(s), initiating cue@), and answer any questions you have. I will provide accessto anytools necessary to perform the task. You may use any approved reference material normally available. To satisfactory complete this task, you must perform or simulate each critical element correctly.
You areto inform the examiner when you have completed the task.
General Comments (For Evaluator Use):
Task Conditions:
THE CREW IS PREPARING TO DRAIN THE 32 FWST WITH THE ELECTRIC FIRE PUMP IN ACCORDANCE WITH SOP-FP-001 SECTION 4.12. THE SHIFT MANAGER HAS DIRECTED YOU TO PERFORM STEP 4.12.15 OF SOP-FP-001 TO VERIFY TO THE CORRECT ALIGNMENT OF SELECTED FIRE PROTECTION SYSTEM VALVES.
Task Standards :
ONDUCT A VALVE LINEUP VEFUFICATION PER OD-35, COMPONENT VERIFICATION AND SYSTEM TATUS CONTROL K&A #: 2.1.29 Knowledge of How To Conduct and Veri@ A Valve Lineup IMPORTANCE FACTORS: SR0=3.3
2-Sep-2003 Job Performance Measure Exam Page:
I Tools Needed:
None Initiating Cues :
THE CREW IS PREPARING TO DRAIN THE 32 FWST WITH THE ELECTRIC FIRE PUMP IN ACCORDANCE WITH SOP-FP-001 SECTION 4.12. THE SHIFT MANAGER HAS DIRECTED YOU TO PERFORM STEP 4.12.15 OF SOP-FP-001 TO VERIFY TO THE CORRECT ALIGNMENT OF SELECTED FIRE PROTECTION SYSTEM VALVES.
Safety Considerations :
PERSONNEL PROTECTIVE EQUIPMENT REQUIRED Consequences of Inadequate Performance:
LOSS OF PLANT STATUS CONTROL IF NOT PERFORMED CORRECTLY
2-Sep-2003 Job Performance Measure Exam Performance Checklist :
Element :
Standards :
Conditions :
1 OBTAIN A COPY OF SOP-FP-001 OBTAINS AND REVIEWS THE AND REVIEW STEP 4.12.15 SOP-FP-001 AND PREPARES FOR THE LINEUP ACTIVITY Comments :
Critical Task?
N Satisfactory Unsatisfactory Element :
Standards :
2 PERFORMLINEUP PERFORM LINEUP VERIFICATION OF VERIFICATION OF VALVES IN STEP 4.12.15 OF SOP-FP-001 STEP 4.12.15 OF SOP-FP-001 Comments :
Critical Task?
Y Satisfactory Element :
z VERIFY POSITION OF FP-46 Comments :
Critical Task?
Y Satisfactory Element :
VERIFY POSITION OF FP-6 1 omments :
Unsatisfactory Conditions :
Standards :
Conditions :
VERIFICATION AND SYSTEM STATUS CONTROL PER OD-35, COMPONENT Unsatisfactory Standards :
Conditions :
VERIFICATION AND SYSTEM STATUS CONTROL PER OD-35, COMPONENT Page:
I Critical Task?
Y Satisfactory Unsatisfactory
2-Sep-2003 Job Performance Measure Exam Page:
I Element :
Standards :
Conditions :
FP-48 VERIFICATION AND SYSTEM 5
VERIFY POSITION OF PER OD-35, COMPONENT STATUS CONTROL Comments :
Critical Task?
Y Satisfactory Element :
6 VERIFY POSITION OF FP-39-1 Comments :
Critical Task?
Y Satisfactory Element :
7 VERIFY POSITION OF FP-28-3 Comments :
Critical Task?
Y Satisfactory Unsatisfactory Standards :
Conditions :
PER OD-35, COMPONENT VERIFICATION AND SYSTEM STATUS CONTROL Unsatisfactory Standards :
Conditions :
VERIFICATION AND SYSTEM STATUS CONTROL PER OD-35, COMPONENT Unsatisfactory Terminating Cues :
JPM IS COMPLETE WHEN ALL 5 VALVES HAVE BEEN VENFIED IN THE PROPER POSITION
2-Sep-2003 Job Performance Measure Exam JPMNO.
3 RESPOND TO LOWERING REFUELING CAVITY LEVEL WITH THE TRANSFER TUBE GATE VALVE OPEN DURING REFUELING OPERATIONS Job Performance Measure Exam Submitted By : Don Jackson-9l20l2003 Date Reviewed By Date SME ReviewNalidation By Approved By Date Date Page:
1
2-Sep-2003 JPM Tasks Task ID: 2.2.27 Job Performance Measure Exam Page:
1
==
Description:==
ACTIONS FOR LOWERING REFUELING POOL LEVEL DURING REFUELING PER ONOP-RP-3 Trainee:
Evaluator:
Evaluator Signature Date Trainee Performance:
Satisfactory Unsatisfactory Start Time Stop Time:
When I tell you to begin, you are to perform the task listed above. I will describe general conditions standard@), initiating cue(s), and answer any questions you have. I will provide access to any tools necessary to perform the task. You may use any approved reference material normally available. To satisfactory complete this task, you must perform or simulate each critical element correctly.
You areto inform the examiner when you have completed the task.
General Comments (For Evaluator Use):
Task Conditions:
REFUELING ACTIVITIES ARE IN PROGRESS. THE CORE IS CURRENTLY BEING FULLY OFFLOADEI)
OR RHR MAINTENANCE. 42 ASSEMBLIES HAVE BEEN MOVED TO THE SPENT FUEL PIT. THERE IS URRENTLY AN IRRADIATED FUEL ASSEMBLY IN THE REFUELING BRIDGE MAST. FUEL TRANSFER ART IS IN THE SPENT FUEL HANDLING BUILDING WITH AN IRRADIATED FUAL ASSEMBLY ON BOAR I S THE FUEL HANDLING SUPERVISOR, YOU NOTICE THAT REFUELING CAVITY LEVEL HAS VISIBLY OWERED OVER A 5 MINUTE PERIOD. YOU RECEIVE A REPORT FROM THE CONTROL ROOM THAT ASED ON CONTAINMENT SUMP LEVEL AND REPORTS FROM THE LOWER LEVELS OF CONTAINMENI HAT THERE IS A LEAK FROM THE REFUELING CAVITY.
Task Standards :
ACTIONS FOR LOSS OF REFUELING CAVITY LEVEL PER ONOP-RP-3 K&A #: 2.2.27 KNOWLEDGE OF THE REFUELING PROCESS IMPORTANCE FACTORS: SRO=3.5
2-Sep-2003 Job Performance Measure Exam Page:
I Tools Needed:
Initiating Cues :
REFUELING ACTIVITIES ARE IN PROGRESS. THE CORE IS CURRENTLY BEING FULLY OFFLOAO r D OR RHR MAINTENANCE. 42 ASSEMBLIES HAVE BEEN MOVED TO THE SPENT FUEL PIT. THERE IS URRENTLY AN IRRADIATED FUEL ASSEMBLY IN THE REFUELING BRIDGE MAST. FUEL TRANSFER ART IS IN THE SPENT FUEL HANDLING BUILDING WITH AN IRRADIATED FUAL ASSEMBLY ON BOAltD S THE FUEL HANDLING SUPERVISOR, YOU NOTICE THAT REFUELING CAVITY LEVEL HAS VISIBLY OWERED OVER A 5 MINUTE PERIOD. YOU RECEIVE A REPORT FROM THE CONTROL ROOM THAT ASED ON CONTAINMENT SUMP LEVEL AND REPORTS FROM THE LOWER LEVELS OF CONTAINMEN /I_
HAT THERE IS A LEAK FROM THE REFUELING CAVITY. YOU ARE TO RESPOND TO THE LOSS OF THE FUEL HANDING BUILDING, AND APPROPRIATE CUES WILL BE GIVEN BY THE EXAMINER.
EFUELNG CAVITY WATER LEVEL PER ONOP-RP-3. DISCUSSION OF THE ACTIONS WILL TAKE PLACE, Safety Considerations :
NONE Consequences of Inadequate Performance:
FUEL DAMAGE AND HIGH LEVELS OF RADIATION IN CONTAINMENT
2-Sep-2003 Job Performance Measure Exam Page:
I Performance Checklist :
Element :
Standards :
Conditions :
OBTAIN AND REVIEW Comments :
Critical Task?
N OBTAINS AND REVIEWS ONOP-RP-3 ONOP-RP-3 Satisfactory Unsatisfactory Element :
Standards :
Conditions :
ENSURE AUTO ACTIONS Comments :
DETERMINE CONDITION OF Cue: R-5 Has Not Annunciated HAVE OCCURRED R-5, FSB AREA RAD MONITOR Critical Task?
N Satisfactory Unsatisfactory Element :
Standards :
Conditions :
ORDERS CONTAINMENT CONTAINMENT EVAC ALARM Cue: Containment Evac Alarm EVACUATION ALARM AND CONTAINMENT AND Cont. Vent Is01 AND CONTAINMENT VENTILATION ISOLATION Have Been Initiated VENTILATION ISOLATION ARE ORDERED TO CONT RM Comments :
Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
ORDERS NON-ESSENTIAL SELECTS WHO IS NON Consider: Needs Reheling Machine PERSONNEL TO EVACUATE ESSENTIAL AND HAS Operator, Upender Operator CONTAINMENT AND FSB THEM EVACUATE CONTAINMENT AND FSB Gate Valve Operator (Cont, and FSB), Transfer Tub:
omments :
Critical Task?
Y Satisfactory Unsatisfactory
Z-Sep-2003 Job Performance Measure Exam Page:
1 Element :
Standards :
Conditions :
ISOLATION GATE, AND APPLY AIR TO GATE SEAL 5
CLOSE SPENT FUEL POOL ORDERS SPENT FUEL POOL Cue: Spent Fuel Pool Isolation ISOLATION GATE SHUT, AND Gate Is Shut, and Air Is Applied To ODERS STATION AIR APPLIED The Seal TO THE SEAL Comments :
Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
CONVEYER TO THE CONVEYER MOVED TO THE CONTAINMENT CONTAINMENT, AND ORDERS and the Fuel Transfer Tube AND CLOSE THE FUEL THE FUEL TRANSFER TUBE GATE TRANSFER TUBE GATE VALVE CLOSED VALVE 6
SEND THE FUEL TRANSFER ORDERS THE FUEL TRANSFER Cue: The Conveyer Has Been Moved To The Containment Gate Valve Is Shut Comments :
Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
7 DIRECT HEALTH PHYSICS DIRECTS HEALTH PHYSICS Cue: Rad Levels Are Currently Nom TO CONSTANTLY MONITOR TO CONSTANTLY MONITOR Monitoring Will Be Continuous AND REPORT RAD LEVELS AND REPORT RAD LEVELS TO THE REFUELING SRO TO HIMSELF, FOR THE FOR THE CONTAINME" CONTAINMENT AND FSB AND FSB Comments :
Critical Task?
N Satisfactory Unsatisfactory
8 9
10 11 2-Sep-2003 Job Performance Meusure Exam Page:
1 Element :
Standards :
Conditions :
IF THE LEAK IS SMALL THEN INITIATE BLENDED MAKE UP OF THE RCS Comments :
DETERMINES THAT BLENDED Cue: Blended Make Up Is Started MAKEUP IS APPROPRIATE AND ORDERS IT STARTED Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
PLACE THE IRRADIATED FUEL ASSEMBLY INTO ANY ACCESSIBLE CORE PLACED BACK INTO THE CORE Toward The Upender LOCATION, UNLATCH AND RAISE MAST Comments :
BASED ON CUE, RECOGNIZES Cue: Motion Has Just Been Initiated THAT ASSEMBLY SHOULD BE By The Bridgeflrolley From The C01.i PER STEP 5.2.1,AND UNLATCH AND RAISE THE MAST Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
CHECK THAT THERE IS NO ASSEMBLY IN THE RCC CHANGE FIXTURE UPON CUE, RECOGNIZES THE STEP IS N/A Cue: There Is No Assembly In The RCC Change Fixture Comments :
Critical Task?
N Satisfactory Unsatisfactory Element :
Standards :
Conditions :
CHECK THAT THERE IS NO ASSEMBLY IN THE THE STEP IS N/A Upender UPENDER (EITHER SIDE).
Comments :
UPON CUE, RECOGNIZES Cue: There Is No Assembly In Either Critical Task?
N Satisfactory Unsatisfactory
2-Sep-2003 Job Performawe Measure Exam Page:
I Element :
Standards :
Conditions :
NO ASSEMBLY SUSPENDED FROM THE SPENT FUEL HANDLING TOOL Comments :
12 CHECK THAT THERE IS UPON CUE, RECOGNIZES Cue: There Is No Assembly Suspend I:d THE STEP IS N/A From The Spent Fuel Handling Too1 Terminating Cues :
MITIGATING ACTIONS ARE COMPLETE FOR THE LOSS OF REFUELING POOL LEVEL, THIS JPM 1,:;
COMPLETE
2-Sep-2003 Job Performance Measure Exam Page:
I JPMNO.
4 PERFORM CALCULATIONS FOR A GASEOUS RADIOACTIVE RELEASE PERMIT Job Performance Measure Exam Submitted By : Don Jackson-Reviewed By SME ReviewNalidation By Approved By 9/20/2003 Date Date Date Date
2-Sep-2003 Job Performance Measure Exam Page:
I JPM Tasks TaskID: 2.3.8
==
Description:==
PERFORM CALCULATIONS FOR A GASEOUS RADIOACTIVE RELEASE PERMIT Trainee:
Evaluator:
Evaluator Signature Date Trainee Performance:
Satisfactory Unsatisfactory Start Time Stop Time:
When I tell you to begin, you are to perform the task listed above. I will describe general conditions standard(s), initiating cue@), and answer any questions you have. I will provide access to any tools necessary to perform the task. You may use any approved reference material normally available. To satisfactory complete this task, you must perform or simulate each critical element correctly.
You areto inform the examiner when you have completed the task.
General Comments (For Evaluator Use):
Task Conditions:
THE CALCUALTIONS FOR THE GDT CURIE CONTENT, PLANT VENT RELEASE RATE, ALLOWAT iL ACTUAL VALUES.
GDT RELEASE RATE, RELEASE TIME, AND R-44 ALARM SETPOINT ARE DONE WITHIN 25% OF Task Standards :
PERFORM CALCULATIONS FOR A GASEOUS RADIOACTIVE RELEASE PERMIT IN ACCORDANC 3 K&A #: SYSTEM GENERIC 2.3.8 KNOWLEDGE OF THE PROCESS FOR PERFORMING A PLANNE; GASEOUS RADIOACTIVITY RELEASE IMPORTANCE FACTORS: SR0=3.2 VALIDATION TIME 20 MINUTES WITH SOP-WDS-013
2-Sep-2003 Job Performance Measure Exam Page:
1 Tools Needed:
CALCULATOR Initiating Cues :
USING THE APPROPRIATE SECTION OF SOP-WDS-013, GASEOUS WASTE RELEASES, PERFON, 1 INDEPENDENT VERIFICATION OF THE CALCULATIONS PERFORMED FOR ATTACHEMNT 1,
GASEOUS WASTE RELEASE PERMIT FOR 33 LARGE GAS DECAY TANK.
33 LGDT PRESSURE IS 87PSIG THE 33 LGDT HAS BEEN ISOLATED AND SAMPLED BY CHEMISTRY 0 A GASEOUS WASTE RELESE PERMIT IS BEING PREPARED TO DISCHARGE THE DECAY TANK 0
DATA NECESSARY TO SUPPORT THE RELEASE PERMIT HAS BEEN COLLECTED AND RECORD]! 1 0
THE CCR PERSONAL COMPUTER IS NOT AVAILABLE, AND THE SOFTWARE CAN NOT BE USEI::
THE PABNC EXHAUST FANS ARE IN SERVICE AND DISCHARGING AT 30,000SCFM ON ATT.l OF SOP-WDS-013 Safety Considerations :
NONE Consequences of Inadequate Performance:
INACCURATE RELEASE LIMITING SETPOINTS, POSSIBLE RELEASE RATE ABOVE LEVEL PERMISSIBLE
2-Sep-2003 Job Performance Measure Exam Page:
1 Performance Checklist :
Element :
SOP-WDS-0 13 1
OBTAINANDREVIEW Comments :
Critical Task?
N Satisfactory Element :
CONTENT 2
DETERMINE GDT CURIE Comments :
Critical Task?
Y Satisfactory Element :
RELEASE RATE (D), IN Ucihec 3
DETERMINE AVAILABLE Comments :
Critical Task?
Y Satisfactory Standards :
Conditions :
OBTAINS AND REVIEWS STEP 4.2.10 APPLIES SOP-WDS-0 13, DETERMINES Unsatisfactory Standards :
Conditions :
PERFORMS THE FOLLOWING CALCULATION AND RECORDS ONATT. 1 A=(l.93E+03)*C*V*P Unsatisfactory Standards :
Conditions :
WITH R-27, CHAN 4 IN SERVICE, DETERMINE (D)
BY SUBTRACTING THE Calculation CURRENT READING FROM THE ALARM SETPOINT Note: Determines Error Was Made In The Original Unsatisfactory
2-Sep-2003 Job Performance Measure Exam Page:
1 Element :
4 RECORD N/A ON ATT. 1 CALCULATED ALARM SETPOINT, CALCULATED FOR I-13 1 ACTIVITY, R-12 AUTO CLOSURE SETPOINT, ACTUAL R-12 AUTO CLOSURE SETPOINT omments :
Critical Task?
N Satisfactory Element :
MONITOR AND ACTUAL ALARM SETPOINT FOR DISCHARGE MONITOR ONATT. 1 Comments :
5 RECORD DISCHARGE Critical Task?
N Satisfactory Element :
6 DETERMINE MAX ALLOWED RELEASE RATE IN SCFM,
USING EMAX= D/(C*472)
Comments :
Critical Task?
Y Satisfactory Terminating Cues :
Standards :
RECORDS N/A ON ATT. 1 CALCULATED ALARM SETPOINT, CALCULATED FOR 1-13 1 ACTIVITY, R-12 AUTO CLOSURE SETPOINT, ACTUAL R-12 AUTO CLOSURE SETPOINT Unsatisfactory Conditions :
Standards :
Conditions :
RECORDS MONITOR AND SETPOINT Unsatisfactory Standards :
Conditions :
PERFORMS CALCULATION AND RECORDS ON ATT. 1 EMAX= D/(C*472)
Note: This Calculation Is Also In Error On Supplied Form Unsatisfactory TERMINATE THE JPM ONCE BOTH ERRORS HAVE BEEN IDENTIFIED
2-Sep-2003 Job Performance Measure Exam JPMNO. 5 Emergency Plan Classification For General Emergency Including PAR Job Performance Measure Exam Submitted By Don Jackson Reviewed By SME ReviewNalidation By Approved By 9/20/2003 Date Date Date Date Page:
I
2-Sep-2003 Job Performame Measure Exam Page:
I JPM Tasks 2.4.41
==
Description:==
GENERAL EMERGENCY CLASSIFICATION AND PAR Trainee:
Evaluator:
Evaluator Signature Date Trainee Performance:
Satisfactory Unsatisfactory Start Time Stop Time:
When I tell you to begin, you are to perform the task listed above. I will describe general conditions standard(s), initiating cue(s), and answer any questions you have. I will provide access to any tools necessary to perform the task. You may use any approved reference material normally available. To satisfactory complete this task, you must perform or simulate each critical element correctly.
You areto inform the examiner when you have completed the task.
General Comments (For Evaluator Use):
Task Conditions:
A REACTOR TRIP AND SAFETY INJECTION HAVE OCCURRED, E-0 REACTOR TRIP OR SAFETY JECTION IS COMPLETE AND A TRANSITION TO E-3, STEAM GENERATOR TUBE RUPTURE HAS CCURRED. UPON ENTRY INTO E-3, STEAM GENERATOR TUBE RUPTURE, THE STA REPORTS THA I A ED PATH EXISTS ON HEAT SINK, THE CREW TRANSITIONS TO FR-H.l RESPONSE TO LOSS OF ECONDARY HEAT SINK. IT IS DETERMINED THAT A 300 GPM SGTR EXISTS ON 32 SIG, IN ADDITION i
/G SAFETY IS STUCK OPEN ON 32 S/G. WHILE IN FR-H. 1 IT IS DETERMINED THAT DE-I 13 1 IS 475UCUC: :,
-25 IS READING 20 UHR, AND R-26 IS READING 16 R/HR. WIND IS 7 METERS PER SECOND FROM 220 EGREES. AN AFW PUMP IS QUICKLY RECOVERED AND FR-H.l IS EXITED. AS THE SHIFT MANAGER, AKE THE E-PLAN CLASSIFCATION AND ANY PROTECTIVE ACTION RECOMMENDATIONS IF ECESSARY.
2-Sep-2003 Job Performance Measure Exam Page:
1 ask Standards :
K&A #: ADMIN-2.4.41-KNOWLEDGE OF THE EMERGENCY ACTION LEVELS THRESHOLDS AND CLASSIFICATIONS Applicability: SRO INCLUDING THE ASSOCIATED PROTECTIVE ACTION RECOMMENDATION Estimated Completion Time: 30 minutes A GENERAL EMERGENCY IS DECLARED, AND ACTIONS PER IP-2001 HAVE BEEN COMPLETED Tools Needed:
None Initiating Cues :
A REACTOR TRIP AND SAFETY INJECTION HAVE OCCURRED, E-0 REACTOR TRIP OR SAFETY JECTION IS COMPLETE AND A TRANSITION TO E-3, STEAM GENERATOR TUBE RUPTURE HAS CCURRED. UPON ENTRY INTO E-3, STEAM GENERATOR TUBE RUPTURE, THE STA REPORTS THK ED PATH EXISTS ON HEAT SINK, THE CREW TRANSITIONS TO FR-H.1 RESPONSE TO LOSS OF ECONDARY HEAT SINK. IT IS DETERMINED THAT A 300 GPM SGTR EXISTS ON 32 S/G, IN ADDITION,\\.
4
/G SAFETY IS STUCK OPEN ON 32 S/G. WHILE IN FR-H. 1 IT IS DETERMINED THAT DE-I 13 1 IS 475UCI/C
-25 IS WADING 20 R/HR, AND R-26 IS READING 16 R/HR. WIND IS 7 METERS PER SECOND FROM 220 EGREES. AN AFW PUMP IS QUICKLY RECOVERED AND FR-H.1 IS EXITED. AS THE SHIFT MANAGER, AKE THE E-PLAN CLASSIFCATION AND ANY PROTECTIVE ACTION RECOMMENDATIONS IF ECESSARY.
References :
ID IP-2001 Description Review Date Ref Flag EMERGENCY PLAN PROCEDURE FOR ED,POM, SM X
EMERGENCY ACTION LEVELS X
Safety Considerations :
None
2-Sep-2003 Job Performance Meastcre Exam Page:
I Consequences of Inadequate Performance:
DELAY OF PROTECTIVE ACTIONS FOR PUBLIC HEALTH AND SAFETY Performance Checklist :
Element :
Standards :
Conditions :
EMERGENCY RESPONSE IS REVIEWED ACTIVATION PROCEDURES 1
OBTAIN & REVIEW IP-3 EMERGENCY RESPONSE PLAN Comments :
Critical Task?
N Satisfactory Unsatisfactory Element :
Standards :
Conditions :
GENERAL EMERGENCY IS DECELARED PER PERCATEGORY4.2.2 CATEGORY4.2.2 2
REVIEW ATT 5.1 TO SELECT GENERAL EMERGENCY MUST COMPLETE IN 15 MINU71 S Comments :
Critical Task?
Y Satisfactory Unsatisfactory Element :
Standards :
Conditions :
ASSUMES ED, AND ENTERS ATT 5.4 3 SM ENTERS IP-2001 AND ENTERS IP-2001 ASSUMES ED MUST COMPLETE IMMEDIATE AND ENTERS ATT 5.4 ACTIONS IN 15 MINUTES THIS INCLUDES EP FORM 1 Comments :
Critical Task?
N Satisfactory Unsatisfactory
2-Sep-2003 Job Performance Measwe Exam Page:
1 Element :
Standards :
Conditions :
CONTROL ROOM NOTIFICATION CHECKLIST CHECKLIST 4
SMED COMPLETES CONTROL ROOM INITIAL, INITIAL NOTIFICATION FORM EP-4 omments :
Critical Task?
N Satisfactory Unsatisfactory Element :
Standards :
Conditions :
NOTIFY SECURITY OF GENER4L EMERGENCY ATT 5.4 CONTACTS SECURITY PER Critical Task?
N Satisfactory Element :
BEGIN SITE ACCOUNTABILITY Unsatisfactory Standards :
Conditions :
SM TAKES ACTION PER ATT 5.4 CUE: SIMULATE SOUNDING ALARMS AND ANNOUNCEMENTS Comments :
Critical Task?
N Satisfactory Unsatisfactory Element :
Standards :
Conditions :
COMPLETE PART 1-DATA FORM EP FORM 1 PART 1 IS COMPLETED CUE: STABILITY CLASS NYS RADIOLOGICAL EMER PER ATTACHED EXAMPLE IS C Comments :
Critical Task?
Y Satisfactory Unsatisfactory
7 2-Sep-2003 Job Performance Measure Exam Page:
1 Element :
Standards :
Conditions :
PROTECTIVE ACTION EVACUATE AND IMPLEMENT RECOMMENDATION MADE PER IP-EP-410 PROTECTIVE KJ ALL ERPAS 0-2 MILES (1,2,3,4, 7,29,30,38,39,42,43,44,45,46), AND 2-5 MILES ACTION DOWNWIND (8,9,16,18,49), RECOMMEND RECOMMENDATIONS SHELTERING NON-EVACUATED ERPAS Comments :
Critical Task?
N Satisfactory Unsatisfactory Terminating Cues :
THIS JPM IS TERMINATED ONCE THE EP FORM 1 NYS RADIOLOGICAL EMERGENCY DATA FO i 1.1 IS COMPLETED WITH THE APPROPRIATE EVENT CLASSIFICATION AND PAR