ML110110571
| ML110110571 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/20/2010 |
| From: | Constellation Energy Nuclear Group |
| To: | David Silk Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML103200039 | List: |
| References | |
| TAC U01839 | |
| Download: ML110110571 (107) | |
Text
I APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-1
Job Performance Measure Form ES-C-l Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-l (Alt Path)
Task
Title:
Verify Reactivity Control safety function is satisfied.
Task Number: 201.009 KIA
Reference:
004 A2.14 (4.4,4.7)
Method of testing:
Simulated Performance: D Actual Performance: C8J Classroom: D Simulator: C8J Plant: D READ TO THE APPLICANT:
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:
- 1. Unit 1 was in Mode 1 at 100% power.
- 2. A significant electrical transient and Unit-l trip have occurred.
- 3. You are the Reactor Operator Initiating Cue:
The CRS directs you to Perform Reactivity Safety Function per EOP-O Task Standard:
The candidate will initiate Emergency Boratilon per EOP-O.
Appendix C Job Performance Measure Form ES-C-l Worksheet 1.
Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
- 1. EOP-O, Post-Trip Immediate Actions Time Critical Task:
No Validation Time:
20 minutes Simulator Setup:
- 1. Reset to IC-24 (both units at 100%)
- 2. Enter malfunctions:
- a. 4KVOOl_03, fault on 13 4kv bus on Fl
- b. 4KVOOl_04, fault on 14 4kv bus on F2
- 3. Place simulator in run
- 4. Initiate Fl and F2
- 5. Manually trip the reactor when 11 and 12 SGFPs trip on low suction pressure
- 6. Freeze the simulator.
Job Performance Measure Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start:
CUE: The CRS directs you perform Reactivity Control safety function per EOP-O Locates the reactivity control plaque Same as element.
- 1. Depress ONE set of Manual REACTOR TRIP Same as element.
buttons.
- 2. Check the Reactor has tripped by the following:
The candidate determines the
- Prompt drop in NI power reactor has tripped and alternate action step 2.1 is NOT applicable.
- Negative SUR
- 3. Check that NO more than ONE CEA is NOT fully The candidate determines that inserted. CEA positions CANNOT be determined and alternate action step 3.1 is required.
3.1 IF more than ONE CEA fails to fully insert, THEN borate the RCS to at least 2300 ppm as The candidate places the follows: handswitch for l-CVC-512-CV in close.
- a. Shut the VCT M/U valve, 1-CVC-512-CV.
- b. Open the SA DIRECT M/U valve, 1-CVC-514- The candidate may place l-CVC MOV. 514-MOV hand switch in open.
514-MOV is deenergized so this step is NOT critical
- c. Open the BAST GRAVITY FD valves:
Candidate opens l-CVC-508
- 1-CVC-508-MOV MOV
- 1-CVC-509-MOV Candidate opens l-CVC-509 MOV
- d. Verify the M/U MODE SEL SW, 1-HS-210, is The candidate veritIes I-HS-21O in MANUAL. in manual.
- e. Start a SA PP. The candidate starts 11 BA pump.
(12 BA pump is deenergized due to loss of power affects)
Job Performancie Measure Form ES-C-I ELEMENT STANDARD The candidate places I-CVC-501
The candidate verifies 11
- charging pump running.
9 Start ALL available CHG PPs The Ioss 0 f144kv bus startsaII available charging pumps so NOT
- critical.
- 4. Verify demineralized water makeup to the ReS is secured as follows: Candidate verifies II and 12 RCMU pumps are secured.
- 11 and 12 RC M/U PPs are secured
- VCT M/U valve, 1-CVC-512-CV, is shut Candidate verifies l-CVC-512 CV is shut.
- IF RCS Makeup is in Direct Lineup, THEN the RWT CHG PP SUCT, 1-CVC-504-MOV, The candidate determines this step is shut is NOT applicable The candidate reports 'Reactivity Control is Complete' (or met)
Note: The candidate may provide additional information for valves and pumps not operating due to loss of power. This additional information is not critical.
Terminating Cue: This IPM is complete when the candidate reports the status of the Reactivity Control safety function. No further actions are required. The evaluator is expected to end the IPM.
Time Stop:
Job Performance Measure Form ES-C-l Verification of Completion Job Performance Measure Number: SIM-l Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ UNSAT --------
Examiner's Signature and Date: ---------------------------------------
Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1. Unit 1 was in Mode 1 at 100% power.
- 2. A significant electrical transient and Unit-l trip have occurred.
- 3. You are the Reactor Operator Initiating Cue:
The eRS directs you to Perform Reactivity Safety Function per EOP-O
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-2
Appendix C Job Perfonnance Measure Fonn ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-2 (Alt Path)
Task
Title:
Respond to RCS leakage exceeding one charging pump in modes 1 and 2 Task Number: 202.015 K.I A
Reference:
002 A2.01 (4.3, 4.4)
Method of testing:
Simulated Performance: Actual Perfonnance: [ZJ Classroom: D Simulator: [ZJ Plant: D READ TO THE APPLICANT:
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:
- 1. Unit 1 is in Mode 1 at 100% power.
- 2. An RCS leak has occurred.
- 4. You are the Control Room Operator Initiating Cue:
The CRS directs you to perform AOP-2A step VI.E, 'Attempt to isolate the leak' Task Standard:
The candidate will attempt to isolate letdown. The leak will remain greater than the capacity of a charging pump requiring a Reactor Trip.
Job Perfonnanc(~ Measure Form ES-C-I Evaluation Criteria:
I. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals nonnally available in the plant General
References:
- 1. AOP-2A, EXCESSIVE REACTOR COOLANT LEAKAGE Time Critical Task:
No Validation Time:
10 minutes Simulator Setup:
- 1. Reset to IC-24 (both units at 100%)
- 2. Enter malfunctions:
___ a. RCS003, RCS Leak, at 75 gpm
- 3. Place simulator in run
- 4. Open I-PS-5464, plant sample isolation valve
- 5. Place an off-nonnal pink ring on I-PS-5464
- 6. Freeze the simulator when a second charging pump starts (about 4 minutes)
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start: - - - -
CUE: The CRS directs you to perform AOP-2A step VI.E, 'Attempt to isolate the leak' Locates AOP-2A section VLE on page 35 Same as element
- 1. Verify that the UD CNTMT ISOL valves are shut:
Candidate will place hand
- 1-CVC-515-CV switches for l-CVC-515-CV in close.
- 1-CVC-516-CV Candidate will place hand switches for l-CVC-516-CV in close.
- 2. Check there is NO PORV leakage by following indications: Candidate will determine there is
- Quench Tank Parameters no PORV leakage due to
- PORV discharge piping temperatures, computer points T1 07 and T108
- Acoustic Monitor indication
- 3. Verify that RCS SAMPLE ISOL valve, 1-PS-The candidate closes l-CV-5464 5464-CV, is shut.
- 4. Verify that the Reactor Vessel Vent valves are shut: The candidate verifies the RCS
- 1-RC-103-SV vent valves closed
- l-RC-104-SV
- 5. Verify that the PZR Vent valves are shut:
The candidate verifies the PZR
- 1-RC-105-SV vent valves closed
- 1-RC-106-SV
Job Performance Measure Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
NOTE A leak on the Charging header which exceeds the capacity of the charging pumps can be identified by Charging header pressure indicating less than RCS pressure.
Identification of the leak may be missed if more than one charging pump is running.
- 6. Determine if the leak is on the Charging header by performing the following actions:
Same as element
- a. Stop all but ONE CHG PP.
- b. IF Charging header pressure is less than RCS Pressure, THEN assume the leak is The candidate determines the leak is NOT on the charging header.
on the Charging header.
- c. IF the leak is NOT on the Charging The candidate starts charging header, THEN start any CHG PPs that pumps turned off in step 6.a.
were stopped.
- 7. IF the leak is on the Charging header, THEN Candidate determines the step is perform the following actions: not applicable
- 8. IF the leak is determined to be occurring inside Containment by checking the following indications:
- Rise in Containment temperature, pressure, humidity or sump level alarm frequency The candidate determines the leak is inside the containment based on
- Rise in Containment gaseous or particulate Containment sump level alarm activity and containment humidity
- "U-1 WR NOBLE GAS RAD MON" and "UNIT 1 MAIN VENT GASEOUS" alarms clear THEN perform the following actions:
- a. Start ALL available CNTMT AIR CLRs in HIGH.
Job Performance Measure Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
- b. Open the CNTMT CLR EMER OUT valves for Same as element the operating CNTMT AIR CLRs.
- 9. IF the leak is NOT occurring inside of Candidate determines the step is Containment. THEN perform the following not applicable actions:
- 10. Determine that NO leakage into the Component The candidate determines there is Cooling System is indicated by: NO leakage into the component cooling system
- NO rising trends on Component Cooling Radiation Monitor. 1-RI-3819
CUE: Acknowledge step E is complete CUE: Perform block AOP-2A step F, DETERMINE THE APPROPRIATE ACTIONS FOR RCS LEAKAGE, ON PAGE 42
- 1. Check that the leak has been isolated. Candidate will determine the leak has not been isolated. Candidate will perform alternate step F.1.1 1.1 IF the leak has NOT been isolated AND the leak is greater than the capacity of ONE Charging Pump. THEN. with the approval of the SM/CRS.
The candidate will recommend perform the following actions:
tripping the reactor and
- a. Trip the Reactor. implementing EOP-O
- b. IMPLEMENT EOP-O. POST TRIP IMMEDIATE ACTIONS.
Terminating Cue: This JPM is complete when the candidate recommends a manual reactor trip. No further actions are required. Th(: evaluator is expected to end the JPM.
- Time Stop:
Job Performance Measure Form ES-C-l Verification of Completion Job Performance Measure Number: SIM-2 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
Examiner's Signature and Date: __________~_. . . . . . _ _ _ _ _ _ _ __
Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1. Unit 1 is in Mode 1 at 100% power.
- 2. An RCS leak has occurred.
- 4. You are the Control Room Operator Initiating Cue:
The CRS directs you to perform AOP-2A step VI.E, 'Attempt to isolate the leak'
I APPLICANT, _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-3
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-3 (Alt Path)
Task
Title:
Notes failure of an operating HPSI pump and establishes safety injection using 12 HPSI pump prior to exiting EOP-O Task Number: 201.132 KIA
Reference:
006 A2.02 (3.9, 4.3)
Method of testing:
Simulated Performance: Actual Performance: ~
Classroom: D Simulator: ~
Plant: D READ TO THE APPLICANT:
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:
- 1. 11 HPSI pump is tagged out for maintenance
- 2. Unit 1 was in Mode 1 at 100% power.
- 3. A plant transient and Unit trip occurred
- 5. You are the Reactor Operator Initiating Cue:
The CRS directs you to perform EOP-5 block step D, 'Monitor RCS Depressurization' Task Standard:
The candidate determines that there is insufficient HPSI flow from 13 HPSI pump.
The candidate will starts 12 HPSI pump aligned to the 13 HPSI pump flow path.
...."ri-"x,........, Measure Fonn ES-C-l Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals nonnally available in the plant General
References:
- 1. EOP-5, LOSS OF COOLANT ACCIDENT Time Critical Task:
No Validation Time:
20 minutes Simulator Setup:
_ _ 1. Reset to IC-24 (both units at 100%)
- 2. Enter malfunctions:
_ _ a. FI: RCS002, RCS leak @ 1200 gpm
- 3. Enter Overrides
_ _ a. I-SI-406, 13 HPSI pump discharge valve, open @ .07
_ _ 4. Tag 11 HPSI PP HS in PTL
_ _ 5. Tag I-S1-656 in close
- - 6. Place simulator in run
- - 7. Initiate FI
_ _ 8. Close I-CV-515 and I-CV-5I6
_ _ 9. Stop IIA and 12B RCPs
-- 10. Freeze simulator 5 minutes after SIAS actuates
_ _ 11. Acknowledge all alanns
Perionmruncle Measure Fonm ES-C-l ELEMENT STANDARD
(* = CRITICAL STEP)
'-'tart: - - -
- CUE: The CRS directs you to perform EOP*-5 block step D, 'Monitor ReS Depressurization' Locates EOP-5 block step D on page 8 Srume as element.
Candidate will determine that
- 1. IF pressurizer pressure is less than or equal to SIAS has actuated by checking 1725 PSIA OR containment pressure is greater SIAS alarm, 13 HPSI pp has than or equal to 2.8 PSIG, THEN verify SIAS started, rund HPSI MOVs have actuation. opened.
- 2. IF pressurizer pressure is greater than 1725 PSIA AND containment pressure is less than 2.8 PSIG, Crundidate will detenmine the step THEN perform the following actions to block is NOT applicable SIAS:
- 3. IF SIAS has actuated, THEN perform the following actions:
- a. Verify the following pumps are running:
- 11 HPSI PP
- 11 LPSI PP
- 12 LPSI PP
- ALL available CHG PPs Crundidate locates EOP
- b. Verify safety injection flow: attachments, refers to ATTACHMENT (10), and
- HPSI flow PER ATTACHMENT(10), detenmines 13 HPSI flow is less HIGH PRESSURE SAFETY than the minimum required based IN"IECTION FLOW, when pressure is on addition of the 4 loop flow below 1270 PSIA indicators rundJor the HPSI total flow indication.
b.1 Perform the following actions as necessary:
Candidate detenmines 11 HPSI
Job Perfonnancle Measure Fonn ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
- IF 13 HPSI PP failed, THEN align 12 HPSI Candidate detennines 13 HPSI PP as follows: pump has failed due to its low flow (1) Start 12 HPSI PP Candidate starts 12 HPSI pump (2) Open HPSI HDR XCONN valve, 1-SI 653-MOV. Candidate opens I-S1-653 (3) Shut HPSI HDR XCONN valve, 1-SI-655 Candidate closes I-S1-655 MOV.
- Ensure electrical power is available to Same as element valves and ~um~s.
CUE: Another operator will verify Safety Injection lineup per attachment 2.
- Verify safety injection system lineup PER ATTACHMENT (2), SIAS VERIFICATION CHECKLIST.
Tenninating Cue: This JPM is complete when the 12 HPSI pump is injecting into the RCS per step b.I second bullet. No further actions are required. The evaluator is expected to end the JPM.
Appendix C Job Performanc1e Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: SIM-3 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: __________________
Time to Complete:
Follow up Question: __________________________
Applicant Response: __________________________
Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
Examiner's Signature and Date:
IJvU......,. C Job Perfonnancj; Measure Fonn ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1. 11 HPSI pump is tagged out for maiutenauce
- 2. Unit 1 was in Mode 1 at 100% power.
- 3. A plant transient and Unit trip occurred
S. You are the Reactor Operator Initiating Cue:
The CRS directs you to perform EOP-S block step D, 'Monitor RCS Depressurization'
I APPLICANT: _ __
CALVERl' CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-4
Appendix C Job Performance Measure Form ES-C-l Form ES-C-l Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-4 (Alt Path)
Task
Title:
Takes alternate actions for turbine stop and control valve failure by shutting MSIVs, or if SOlS actuates notes an MSIV failed to shut on SOlS and shuts the MSIVs.
Task Number: 093.002 KIA
Reference:
045 A3.04 (3.4, 3.6)
Method of testing:
Simulated Performance: 0 Actual Performance: [gJ Classroom: Simulator: [gJ Plant:
o READ TO THE APPLICANT:
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:
- 1. Unit 1 was in Mode 1 at 100% power.
- 2. A Switchyard Fault has occurred
- 3. The reactor has tripped
- 4. You are performing duties as the Control Room Operator Initiating Cue:
The CRS directs you to perform Turbine Trip per EOP-O Task Standard:
A main turbine stop valve and control valve have failed to automatically close on the plant trip. This will cause the Main Turbine to overspeed and steam generator pressures to lower rapidly. SGIS will not actuate to protect the plant. The candidate will shut the Main Steam Isolation Valves and secure the Main Generator Exciter.
Job Performance Measure Form ES-C-l Form ES-C-l Worksheet Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
- 1. 01-28, OPERATION OF THE 500 KV SWITCHYARD
- 2. EOP-O, POST-TRIP IMMEDIATE ACTIONS Time Critical Task:
No Validation Time:
5 minutes Simulator Setup:
- 1. Reset to I C-24 (both units at 100%)
- - 2. Enter malfunctions:
- a. SWYDOOI_02, Breaker 552-22 failure
___ b. TG005 _01, Main Turbine Stop Valve and Control Valve 1 failed as-is
- c. ESFAXXXX, SGIS auto failure
- - 3. Place simulator in run
- 4. Place breaker 552-22 in open
- 5. Freeze simulator
Job Perfonnance Measure Fonn ES-C-I Fonn ES-C-l ELEMENT STANDARD Time Start:
CUE: The RO announces 'The reactor is tripped', the CRS announces 'Perform EOP-O'
- 1. Check the Reactor has tripped. Candidate verifies the reactor has tripped
- 2. Ensure the Turbine has tripped by performing the following actions: Candidate depresses both turbine trip buttons
- a. Depress BOTH TURBINE TRIP buttons.
- b. Check the Turbine Main Stop Valves shut:
- MSV1 Candidate detennines MSV I did
- MSV2 not shut and alternate step b.l is required
- MSV3
- MSV4 Note: The candidate may report 'Taking alternate actions for (stop valve open)'. This report is not critical.
CUE: Acknowledge alternate actions b.1 IF ANY Turbine Main Stop Valve failed to Candidate will shut both Main shut, THEN shut BOTH MSIVs. Steam Isolation Valves
- c. Check Turbine Speed drops. Candidate detennines turbine speed is lowering
- d. IF the Turbine was paralleled to the grid, The candidate detennines breaker THEN verify the Turbine Generator Output 552-22 did not open and takes its breakers open: handswitch to open.
- 11 GEN BUS BKR, O-CS-552-22
- 11 GEN TIE BKR, O-CS-552-23 Same as element
- e. Verify 11 GEN FIELD BKR, 1-CS-41, is c)pen. Same as element
Job Perfonnance Measure Fonn ES-C-l Fonn ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
The candidate will open the
- f. Verify 11 EXCITER FIELD BKR, 1-CS-41 E, is exciter field breaker open. The exciter field breaker will not automatically open
- 3. Ensure BOTH MSR 2ND STG STM SOURCE MOVS are shut: Detennines the valves have not shut due to loss of power and
- 1-MS-4025-MOV (11 MSR) alternate action step 3.1 IS
- 1-MS-4026-MOV (12 MSR) required.
3.1 IF EITHER MSR 2ND STG STM SOURCE Same as element.
MOV failed to shut, THEN perform the foliowin~1 actions:
- a. Verify the MSR 2ND STG HIGH LOAD MOV (Not critical since Main Steam is shut: Isolation Valves were closed in
- (11 MSR) 1-MS-4018-MOV step b.l)
- (12 MSR) 1-MS-4017-MOV
- b. Dispatch an operator to verify the MSR 2ND STAGE BYPASS CONTROL VALVE panel Same as element loader in MANUAL with panel loader output at zero.
The Candidate will report 'Turbine Trip is complete' or similar Tenninating Cue: This JPM is complete when the candidate reports the Turbine Trip safety function. No further actions are required. The evaluator is expected to end the JPM.
Time Stop:
~el*tolTIl,mc:e Measure Form ES-C-l Form ES-C-l Worksheet Verification of Completion Job Perform;mce Measure Number: SIM-4 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT - - - - - - - UNSAT _ _ _ _ _ ___
Examiner's Signature ;md Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Job Performance Measure Form ES-C-l Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1. Unit 1 was in Mode 1 at 100% power.
- 2. A Switchyard Fault has occurred
- 3. The reactor has tripped
- 4. You are performing duties as the Control Room Operator Initiating Cue:
The CRS directs you to perform Turbine Trip per EOP-O
I APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2011 NRC ITIAL LICENSED OPERATOR EXAM JPM #: SIM-5
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: SIM-5 (Alt Path)
Task
Title:
Detennine whether a RCP seal has failed.
Task Number: 064.013 KJA
Reference:
003 A2.01 (3.4,3.9)
Method of testing:
Simulated Performance: 0 Actual Perfonnance: ~
Classroom: 0 Simulator: ~
Plant: 0 READ TO THE APPLICANT:
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:
- 1. Unit 1 was in Mode 1 at 100% power.
- 2. The overhead annunciator alarm E55 "llB RCP SEAL TEMP HIIPRESS" has come in
- 3. You are performing the duties of the Unit 1 RO.
Initiating Cue:
Initiating Cue: The CRS directs you to respond to alarm window E55.
Task Standard:
This JPM is complete when the operator detennines that two seals have failed on lIB RCP and recommends an expeditious shutdown. The evaluator is expected to end this JPM.
Appendix C Job Perfonnance Measure Fonn ES-C-l Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals nonnally available in the plant
- 1. Alann Manual 1C06
- 2. OI-1A, Reactor Coolant System and Pump Operations No Validation Time:
10 minutes Simulator Setup:
_ _ 1. Reset to IC-24 (both units at 100%)
- - 2. Enter malfunctions:
- - a. Insert RCSOll_02, lIB Rep middle seal failure
b. Insert RCSO 12 02. 11 BRep lower seal failure
- - 3. Place simulator in run
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start: - - - -
CUE: The CRS directs you to respond to the RCP alarm.
Identify and locate Alarm Response Manual for I C06 window E-55. Same as element.
CAUTION There is a potential for heat checking of seal faces if RCP seal limits have been exceeded. This heat damage may cause seal degradation/failure during RCS depressurization (compressive forces removed) or subsequent RCP starts (centrifugal forces).
CUE: Middle seal press indicated on I-PIA-I62 is approximately 2220 PSIA. Upper Seal Press indicated on I-PIA-I63 is approximately 2220 PSIA.
Checks Input Devices for alanns.
Detennines that high middle seal pressure alann and high upper Checks validity of alann. seal pressure alann exist.
Checks alanns against setpoints and detennines alanns are valid.
Note to Evaluator: The operator may reference OI-1A to try to determine how many seals have failed.
Checks POSSIBLE CAUSES and detennines that the abnonnal Reviews POSSIBLE CAUSES.
conditions are caused by a seal failure.
- 1. 11 B Rep seal high temperature. Candidate detennines step is N/A
- 2. lIB Rep seal high or low pressure. Candidate detennines this step is applicable.
RCP bleed-off flow indicates approximately 2.5 gpm.
Checks Bleed-off flow on Plant Computer and
- a. CHECK RCP seal bleed-off flow nonnal. detennines the vapor seal is not failed.
Appendix C Job Performancl;! Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
NOTE: If RCP seal bleed-off is less than normal (or zero) with normal seal pressure, the vapor seal may bl~ failed.
- IF the vapor seal is determined to be failed, THEN IMPLEMENT AOP**2A, Excessive Reactor Coolant Leakage CAUTION Debris from a failed seal may propagate 1to remaining seal stages, eventually leading to complete seal failure.
CUE: CRS will contact System Engineer.
- b. IF alarm is due to the failure of ONE seal, THEN closely monitor and trend the remaining seals for an increased rate of degradation AND CONTACT the System Engineer immediately to provide Determines step is NIA.
an evaluation of continued operability PER CNG-OP-1.01-1002, Conduct of Operability Determinations/Functionality Assessments.
- c. IF alarm is due to the failure of TWO or more seals, Determines 11 B RCP lower THEN, and middle seals have failed (1). COMMENCE an expeditious plant shutdown PER OP-3 Normal Power Candidate recommends plant Operation, and OP-4, Plant Shutdown shutdown to CRS due to two from Power Operation to Hot failed seals on 11 B RCP Standby.
TIME STOP --
TERMINATING CUE: This JPM is complete when the operator has determined that 11 B RCP has two failed seals and recommends an expeditious shutdown. The evaluator is expected to end this JPM.
Appendix C Job Performancl~ Measure Form ES-C-l Worksheet Verification of Completion Job Performance Measure Number: SIM-S Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _________________
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT ------- UNSAT --------
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions:
- 1. Unit 1 was in Mode 1 at 100% power.
- 2. The overhead annunciator alarm E55 "lIB RCP SEAL TEMP HIIPRESS" has come in
- 3. You are performing the duties ofthe Unit 1 RO.
Initiating Cue:
Initiating Cue: The CRS directs you to respond to alarm window E55.
I APPLICANT: _ __
CALVERl' CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-6
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-6 Task
Title:
Respond to the loss of a 120 volt vital AC bus Task Number: 202.100 KIA
Reference:
006 A2.01 (3.4, 3.9)
Method of testing:
Simulated Performance: D Actual Performance: ~
Classroom: D Simulator: ~
Plant: D READ TO THE APPLICANT:
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:
- 1. Unit 1 was in Mode 1 at 100% power.
- 2. An electrical transient has occurred.
- 3. You are the Control Room Operator Initiating Cue:
The CRS directs you to Perform block step IV.A of AOP-7J.
Task Standard:
The candidate will use AOP-7J to diagnose llioss of 1YO 1. The candidate will restore pressurizer pressure and level instrUlments affected by the bus loss. The candidate will protect the pressurizer by securing charging pumps before exceeding 225 inches. The cllndidate will protect RCPs by placing 12 CC HX in service.
Appendix C Job Performance Measure Form ES-C-l Worksheet Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
No Validation Time:
20 minutes Simulator Setup:
_ _ 1. Reset to IC-24 (both units at 100%)
- - 2. Enter malfunctions:
- a. Loss of 1YOI on Fl
- 3. Place simulator in run
- - 5. Initiate the loss of 1YOI
_ _ 6. Freeze simulator when pressuriz(~r level or pressure alarm annunciates
Job Perfonnance Measure Fonn ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start: - - -
CUE: The CRS directs you to Perform block step IV.A of AOP-7J.
Locates the AOP-7J Same as element.
CUE: The CRS will perform step 1 1, Perform the following immediate actions:
- a. Confirm with the Fuel Handling Supervisor that any fuel assembly being handled has been placed in a safe location.
- b. Suspend movement of irradiated fuel.
N/A
- c. Suspend movement of heavy loads over irradiated fuel.
- d. IF in Modes 5 or 6, THEN suspend operations involving positive reactivity additions that could result in loss of required SDM or boron i concentration.
- 12. GO TO 1C24A. Same as element.
. 3. IF 11 120 Volt Vital AC Instrument Bus (1YO'1) is The candidate reviews indications deenergized, AND 11 125 Volt DC Bus is on I C24A for 1YO 1 and 11 DC energized, THEN PROCEED to Section V., '11 Bus then detennines the a loss of 120 VOLT VITAL AC I NSTRUMENT BUS only IYOI has occurred and (1Y01). proceeds to section V on page 9.
Cue: Acknowledge recommendation, continue with the procedure I
- 1. Verify that the PRZR PRESS CH SEL Switch is in The candidate places PRZR the Y position. PRESS CH SEL Switch in Y.
- 2. Verify that the RRS CH SEL Switch is in the The candidate places RRS CH RRS-Y position. SEL Switch in Y.
- 3. Verify that the PRZR LVL CH SEL Switch is in the Same as element.
11 OY ~osition.
- 4. Verify that the PZR HTR LO LVL CUT-OFF SEL The candidate places PZR HTR Switch is in the Y position. LO LVL CUT-OFF SEL Switch in Y.
Appendix C Job Performance Measure ELEMENT STANDARD (SHADED = CRITICAL STEP)
CUE: Another operator will place switch 81 in OFF, continue
- 6. Shut the UD CNTMT ISOL valves:
Candidate shuts l-CV -515
- 1-CVC-515-CV
- 1-CVC-516-CV Candidate shuts 1-CV -516 Note: If pressurizer level reaches 225 prior to c~mdidate performing step 7, the candidate should stop all charging pumps.
- 7. Operate the selected charging pump as Candidate will secure the running necessary to maintain.PZR level within 15 inches charging pump(s).
of programmed level, NOT to exceed 225 inches.
- 8. Operate Pressurizer HTRs and PRZR SPRAY VLVs as necessary to maintain RCS pressure Same as element.
between 2225 and 2275 PSIA.
Note: The candidate may perform the following step from memory or by using 01-16 section 6.4.
- opening l-CC-3826-CV
- throttle open 12 CC HX SW FLOW CONTR, 1 HIC-5208 Terminating Cue: This JPM is complete when the candidate places 12 CC HX in service.
No further actions are required. The evaluator is expected to end the JPM.
Time Stop:
Appendix C Job Performanc(~ Measure Form ES-C-l Worksht:et Verification of Completion Job Performance Measure Number: SIM-6 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT - - - - - - - UNSAT _ _ _ _ _ __
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1. Unit 1 was in Mode 1 at 100% power.
- 2. An electrical transient has occurred.
- 3. You are the Control Room Operator Initiating Cue:
The CRS directs you to Perform block step IV.A of AOP-7J.
I APPLICANT: _ _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-7
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-7 (Alt Path)
Task
Title:
Override shut a PORV Task Number: 064.035 KIA
Reference:
007.A2.01 (3.9,4.2)
Method of testing:
Simulated Performance: D Actual Performance: [g]
Classroom: D Simulator: [g] Plant: D READ TO THE APPLICANT:
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:
- 1. Unit 1 is stable in Mode 4 at 250F and 225 psia
- 2. You are performing duties as the Reador Operator
- 3. Alarm E-21, PORV ENERGIZED, ahlrm has been received Initiating Cue:
The CRS directs you to respond to alarm window E-21 Task Standard:
The candidate will diagnose that the PORV is open due to equipment malfunction and shut the associated PORV block valve.
Appendix C Job PerformanCE! Measure Form ES-C-l Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
- 1. ALM-IC06, RCS Control Alarm Manual Time Critical Task:
No Validation Time:
10 minutes Simulator Setup:
- 1. Resetto IC-1
- 2. Enter malfunctions:
- a. Override 1-PI-103-1 to 1533#
- 3. Place simulator in run
- 4. Override PORV 402 to "manopen"
- 5. Freeze the simulator when pressurizer pressure lowers to 225 psia.
Appendix C Job PerformanCE~ Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
- Time Start:
CUE: The CRS directs you to respond to alarm window E-21 Locates the 1C06 alarm manual and refers to E-21 Same as element.
The candidate determines the step
- 1. PERFORM the following:
The candidate determines the
- a. IF reactor trip occurs, THEN IMPLEMENT reactor is shut down and step is EOP-O, Post-Trip Immediate Actions. NOT applicable.
CUE: The shift manager will contact the electric shop
- b. NOTIFY the electric shop to verify the trip status of the PORV thermal overloads to ensure PORV operability. [80034]
The candidate determines PORVs
- c. IF the PORVs are in NORMAL, THEN: ...
are in variable MPT and step is NOT applicable
- d. IF the PORVs are in MPT ENABLE, THEN: The candidate determines PORVs are in variable MPT and step is applicable (1) TRIP any RCPs operating in the NON- Candidate refers to RCP curve for OPERATING AREA of the RCP curve current lineup and determines RCP are in the non-operating area of the curve.
Candidate secures 11 A and 12B RCPs
Appendix C Job Performance Measure Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
(2) WHEN the cause of the high pressure Candidate determines the PORV condition has been corrected, THEN: is open due to equipment
[B0064]
malfunction and not high RCS pressure.
Determines step is NIA (3) IF a PORV fails to shut or is open due to The candidate determines PORV a failed transmitter, THEN SHUT the 402 is open due to a failed applicable PORV Block, 1-RC-403-MOV transmitter and closes the PORV or 1-RC-405-MOV. 402 block valve l-RC-403-MOV CUE: The CRO will perform step l.d.(4)
(4) DRAIN the PORV discharge piping to the N/A Quench Tank as follows:
- e. MONITOR computer points T106, T107, and Candidate uses plant computer to T1 08 for leak-off temperatures. monitor leak-off temperatures Terminating Cue: This JPM is complete when the candidate isolates the open PORV flow path. No further actions are required. The evaluator is expected to end the JPM.
Time Stop:
Appendix C Job Performanc~ Measure Form ES-C-l Verification of CI)mpletion Job Performance Measure Number: SIM-7 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _._ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
- 1. Unit 1 is stable in Mode 4 at 250F and 225 psia
- 2. You are performing duties as the Reactor Operator
- 3. Alarm E-21, PORV ENERGIZED, alarm has been received Initiating Cue:
The CRS directs you to respond to alarm window E-21
I APPLICANT: _ __
CALVER1~ CLIFFS NUCLEAR POW RPLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-1
PertorJmaJl1ce Measure Form ES-C-l Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-l Task
Title:
Fill the SRW and CC head tanks during a loss of AC power Task Number: 011.025, 015.008 KJA
Reference:
008 A4.07 (2.9, 2.9)
Method of testing:
Simulated Performance: fZ] Actual Performance:
Classroom: D Simulator:
Plant: fZ]
READ TO THE APPLICANT:
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:
- 1. A severe fire has resulted in Control Room evacuation. AOP-9A has been implemented.
- 2. You are performing the duties of the Unit:-2 ABO.
Initiating Cue:
You have just completed Step CG, ESTABLISH SALTWATER FLOW THROUGH THE COMPONENT COOLING HEAT EXCHANGERS which directs you to "Go to the 69' Aux Building to perform Step CH".
Task Standard:
This JPM is complete when makeup has been restored to the Service Water and Component Cooling Head Tanks.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
- 1. AOP-9A, CONTROL ROOM EV ACUA nON AND SAFE SHUTDOWN DUE TO A SEVERE CONTROL ROOM FIRE.
Time Critical Task:
No Validation Time:
20 minutes Simulator Setup:
- 1. None
Appendix C Job Perfonnance Measure Fonn ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start:
CUE: You have just completed Step CG, ESTABLISH SALTWATER FLOW THROUGH THE COMPONENT COOLING HEAT EXCHANGERS which directs you to "Go to the 69' Aux Building to perform Step CH".
Locate AOP-9A, Step CH. Same as element.
Candidate proceeds to the Unit-2 69' Same as element I
CUE: 2C43 notifies you that makeup has been restored to fill the Service Water and Component Cooling Head Tanks
- 1. WHEN notified that makeup has been restored to fill the Service Water and Component Cooling Head i Tanks, THEN: Same as element
- Open Component Cooling Head Tank Condensate Supply, 2-CD-145.
- Open SRW Head Tank Condensate Supply, Same as element 2-CD-144.
CUE: The component cooling head tank level is below the sight glass
- 2. Operate, as necessary, to maintain level indication for the Component Cooling and Service Water Head Tanks:
Same as element
- a. Component Cooling Head Tank:
(1) Open Component Cooling Head Tank Makeup Bypass, 2-CC-108 (2) Shut 2-CC-3820-CV Inlet Isol, 2-CC-107 Same as element i CUE: The component cooling head tank level is normal by sight glass CUE: 21 SRW head tank is normal, 22 SRW head tank level is below the sight glass
- b. 21 Service Water Head Tank: I Candidate detennines step is NOT applicable
Job Performance Measure Form ES-C-l ELEMENT STANDARD (SHADED= CRITICAL STEP)
- c. 22 Service Water Head Tank:
(1) Open 22 Service Water Head Tank Makeup Bypass, 2-SRW-114 Same as element (2) Shut 22 Service Water Head Tank LCV Same as element Inlet Isol, 2-SRW-112 CUE: 22 SRW head tank level is level is normal by sight glass
- 3. Periodically monitor Component Cooling and Service Water Head Tanks levels and fill as Same as element necessary.
Terminating Cue: This JPM is complete when the Component Cooling and 22 Service Water Head Tanks are in the normal band. No further actions are required. The evaluator is expected to end the JPM.
Time Stop:
Job Performance Measure Form ES-C-I Verification of Completion Job Performance Measure Number: PLANT-l Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _________________
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
Examiner's Signature and Date: ______________________
Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
- 3. A severe fire has resulted in Control Room evacuation. AOP-9A has been implemented.
- 4. You are performing the duties of the Unit-2 ABO.
Initiating Cue:
You have just completed Step CG, ESTABLISH SAL TWATER FLOW THROUGH THE COMPONENT COOLING HEAT EXCHANGERS which directs you to "Go to the 69' Aux Building to perform Step CH".
CALVER1' CLIFFS NUCLEAR PO'WER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-2
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-2 Task
Title:
Shutdown/Return and AF AS sensor cabinet to/from service Task Number: 036.005 KIA
Reference:
013 A2.06 (3.7, 4.0)
Method of testing:
Simulated Performance: ~ Actual Performance: D Classroom: D Simulator: D Plant: ~
READ TO THE APPLICANT:
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:
- 2. Shift Manager approval has been obtaim~d.
- 3. You are performing the duties of the Unilt-2 CRO.
Initiating Cue:
The CRS directs you to shutdown AF AS Sensor Cabinet ZE Task Standard:
This JPM is complete when AF AS ZE sensor cabinet is shutdown.
Form ES-C-l Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
No Validation Time:
20 minutes Simulator Setup:
- 1. None
Appendix C Job Performanc1e Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start: - - - -
CUE: The CRS directs you to shutdown AFAS Sensor Cabinet ZE Locate OI-32B Section 6.3. Same as element.
CUE: The CRS has reviewed Tech Specs 3.3.4 and 3.3.5 Candidate proceeds to the Unit-2 cable spreading Same as element room
- 1. UNLOCK AND OPEN the Sensor Cabinet front Candidate notifies control room, door for the Sensor Cabinet to be shutdown. then unlocks Unit 2 AF AS sensor cabinet ZE
- 2. CHECK that NO trips are present on any other Sensor Cabinets for SG Low Level or for SG Same as element Differential Pressure.
- 3. CHECK that NO trips are present on either of the Same as element Logic Cabinets. [B0068]
- 4. PLACE the circuit breaker on the Sensor Cabinet Same as element to be shutdown to the OFF position. (FIGURE 1)
- 5. PLACE the 120 volt breaker for the Sensor Cabinet to be shutdown to the OFF position: Same as element Sensor Cabinet ZE ....... Panel 2Y02-1, Breaker 22
- 6. CLEAR all AFAS alarms that will reset. Same as element
- 7. CLOSE AND LOCK the Sensor Cabinet front Same as element door.
Terminating Cue: This JPM is complete when AF AS ZE Sensor cabinet is de energized with door locked. No further actions are required. The evaluator is expected to end the JPM.
Time Stop:
Appendix C Job Performance Measure Form ES-C-I Worksheet Verification of Completion Job Performance Measure Number: PLANT-2 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _,_ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT ________ UNSAT ______________
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1. Maintenance is scheduled to be performed on AFAS channel ZE
- 2. Shift Manager approval has been obtained.
- 3. You are performing the duties of the Unit-2 CRO.
Initiating Cue:
The CRS directs you to shutdown AFAS Sensor Cabinet ZE
APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PJLANT-3
Fonn ES-C-l Facility: Calvert Cliffs 1 & 2 Job Perfonnance Measure No.: PLANT-3 Task
Title:
Manually override Saltwater valves using hand transfer valves Task Number: 012.019 KIA
Reference:
076 A4.02 (2.6, 2.6)
Method of testing:
Simulated Performance: cg] Actual Perfonnance: D Classroom: D Simulator: D Plant: cg]
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task !mccessfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1. A severe fire has resulted in Control Room evacuation. AOP~9A has been implemented.
- 2. You are performing the duties of the Unit 1 TBO.
Initiating Cue:
The CRS directs you to perform step AP, Override Saltwater to the Service Water Heat Exchangers Task Standard:
This JPM is complete when Salt Water valve:s to the Service Water Heat Exchangers are manually overridden.
Fonn ES-C-l Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals nonnally available in the plant General
References:
- 1. AOP-9A, CONTROL ROOM EVACUATION AND SAFE SHUTDOWN DUE TO A SEVERE CONTROL ROOM FIRE.
Time Critical Task:
No Validation Time:
20 minutes Simulator Setup:
- 1. None
Job Performance Measure Form ES-C-I ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start:
CUE: The CRS directs you to perform step AP, Override Saltwater to the Service Water Heat Exchangers
- 1. WHEN notified to override Saltwater to the Service Water Heat Exchangers, THEN insert the Key into 1-HS-5149 and place the Saltwater System Emergency Same as element
- Overboard, 1-CV-5149, to OVERRIDE TO CLOSE.
- 2. Place the following Handvalves to OVERRIDE
{from left to right}:
Same as element
Job Performance Measure Form ES-C-l
- 3. Perform the next TBO assigned step.
Terminating Cue: This JPM is complete when Saltwater to the Service Water Heat Exchangers is overridden. No further actions are re q uired. The evaluator is exp ected to end thelPM.
Form ES-C-l Verification of Completion Job Performance Measure Number: PLANT-3 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT - - - - - - - UNSAT _ _ _ _ _ __
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Job Performanc'e Measure Form ES-C-I Workshl~et APPLICANT'S CUE SHEET Initial Conditions:
- 1. A severe fire has resulted in Control Room evacuation. AOP-9A has been implemented.
- 2. You are performing the duties of the Unit 1 TBO.
Initiating Cue:
The CRS directs you to perform step AP, Override Saltwater to the Service Water Heat Exchangers
I APPLICANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-1
Job Performance Measure Form ES-C-I Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-1 Task
Title:
Initiate, ensure performance of, and review Operational Test Documents.
Task Number: 204.035 KJA
Reference:
2.1.7 (4.4, 4.7)
Method of testing:
Simulated Performance: D ActuaIPerformance:[3J Classroom: [3J Simulator:
Plant: D READ TO THE APPLICANT:
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:
- 1) Unit-1 is at 100% reactor power.
- 2) STP O-SA-l, AUXILIARY FEEDWATER SYSTEM QUARTERLY SURVEILLANCE TEST, Section 6.1 has just been performed.
- 3) You are performing the duties of the CRS.
Initiating Cue:
The Shift Manager directs you to perform Step 6.1.31 ofSTP O-SA-l Section 6.1 Task Standard:
The candidate conducts a level 2 review ofSTP O-SA-l section 6.1. The candidate determines 11 AFW pump to be inoperable, and TS 3.7.3.A is entered. The evaluator is expected to end the JPM.
Appendix C Job Performance Measure Form ES-C-l Worksheet Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
- 1. STP O-SA-l, Auxiliary Feedwater System Quarterly Surveillance Test.
- 2. Technical Specifications Time Critical Task:
No Validation Time:
30 minutes Simulator Setup:
None
Appendix C Job Performancl~ Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start:
CUE: The Shift Manager directs you to perform Step 6.1.31 of STP O-SA-l Section 6.1 Steps 6.1.31.1-13 The candidate will review 11 AFW Checks YES or NI A in accordance pump collected test data against the acceptance with the answer key in steps 6.1.31.1 criteria through 6.1.31.13 Determines 11 AFW pump Step 6.1.31.14 Did 11 AFW Pump develop a DIP of at differential pressure is less than the least 1210 PSID and no greater than required in step 6.1.31.14.
1295.2 PSID in Step 6.1.20?
Checks NO Determines 11 AFW pump Steps 6.1.31.15 Did 11 AFW Pump develop a TDH developed head is less than the greater than or equal to 2800 feet in required in step 6.1.31.15.
Step 6.1.21 Checks NO in accordance with the key in steps 6.1.31.15 Step 6.1.31.16 This test section is considered satisfactory Determines 11 AFW pump testing is if YES or NIA was answered in all steps UNSAT in step 6.1.31.16 above. Checks UNSAT Step 6.1.31.16.a. IF unsat THEN: Notifies the SM 11 AFW pump has failed the testing.
- Notify the SM CUE: The SM directs the CRS to determine 'IS actions required Step 6.1.31.16.a Declare the affected equipment inoperable Determines that TS 3.7.3.A should Take action as required by Te,ehnical be entered Specifications and administrative actions stated in EN-4-104 Terminating Cue: This JPM is complete when it is determined 11 AFW pumps is inoperable and TS 3.7.3.A is entered.
The evaluator is expected to end the JPM.
Time Stop:
Appendix C Job Performance Measure Form ES-C-l Worksh~~et Verification of Completion Job Performance Measure Number: SRO-ADMIN-l Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _________________
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT -------
UNSAT --------
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1) Unit-l is at 100% reactor power.
- 2) STP O-SA-l, AUXILIARY FEEDWATER SYSTEM QUARTERLY SURVEILLANCE TEST, Section 6.1 has just been performed.
- 3) You are performing the duties of the CRS.
Initiating Cue:
The Shift Manager directs you to perform Step 6.1.31 ofSTP O-SA-l Section 6.1
I APPLlCANT: _ __
CALVERT CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-2
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-2 Task
Title:
Evaluate the need for plant cooldlown.
Task Number: 201.005 KIA
Reference:
2.1.25 (3.9, 4.2)
Method of testing:
Simulated Performance: D Actual Performance: IZI Classroom: IZI Simulator: D Plant: D READ TO THE APPLICANT:
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:
- 1) Unit-l and Unit-2 were at 100% reactor pow(~r.
- 2) A loss of offsite power occurred at 0800. SME:CO is unavailable.
- 3) The OC DG is unavailable, the lA DG failed to start, 14 4kv bus is deenergized due to a ground fault.
- 4) The plant has been stabilized per EOP-7 with the following parameters:
a) It is now 0900.
b) Unit 1 RCS Temperature is 532F and ste~ldy. Unit 2 RCS temperature is 532F and steady.
c) 11 CST level is 27 feet, 12 CST level is 22 feet, 21 CST level is 26 feet
- 5) You are performing the duties of the Unit 1 CRS.
Initiating Cue:
The Shift Manager directs you to perform EOP-7 step AB, EVALUATE THE NEED FOR PLANT COOLDOWN.
Task Standard:
The candidate will assess condensate inventOlry using EOP attachment (9) and determine there is insufficient water to cooldown, the plant must be maintained in hot standby, and the plant can be maintained in hot standby for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The evaluator is expected to end the JPM.
Job Performance Measure Form ES-C-l Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
- 1. EOP-7, Station Blackout
- 2. EOP Attachments Time Critical Task:
No Validation Time:
30 minutes Simulator Setup:
- - a. None
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start:
CUE: The Shift Manager directs you to perform EOP-7 step AB, EVALUATE THE NEED FOR PLANT COOLDOWN Locate EOP-7, Step AB. Same as element.
- 1. WHEN the RCS parameters have been stabilized, THEN evaluate the need for a plant cooldown based on:
Candidate will determine
- Plant Status Attachment (9) completion is
- Auxiliary systems availability required
- Condensate inventory PERATIACHMENT (9),
MAKEUP WATER REQUIRED FOR RCS COOLDOWN Locate EOP Attachment (9) Same as element.
- 1. Determine the amount of makeup water required Candidate enters uses table to perform an ADV cooldown and a TBV 'INVENTORY REQUIRED TO cooldown, based on the time after shutdown: COOL DOWN TO 300F' and determines 625067 gallons are
- a. ADV cooldown and time after shutdown required.
Candidate enters uses table
'INVENTORY REQUIRED TO
- b. TBV cooldown and time after shutdown COOL DOWN TO 300F' and determines 94828 gallons are required.
- 2. Determine the amount of makeup water available in the CSTs:
- a. Record the level in 11 CST. The candidate determines the tank levels from the initiating cue
- b. Record the level in 12 CST.
- c. Record the level in 21 CST.
- d. Determine the status of Unit 2 (check ()ne):
Candidate checks d.2.
(1) _ Mode 1, 2 or 3 and does NOT require AFWoperation. The loss of offsite power has caused (2) _ Mode 1, 2 or 3 and does require AFW a dual unit trip. Main feed water is NOT available to either unit on a operation.
loss of offsite power.
(3) Mode 4, 5, 6 or defueled.
Job Performance Measure Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
NOTE: Calculated negative values should be entered as zero.
- e. Determine the amount of makeup watE~r available to Unit 1 using one of the following formulas, based on the status checked in step 2.d above:
(1) IF step d.(1) is checked, THEN correct CST Candidate determines step is NOT levels for usable volume: applicable (2) IF step d.(2) is checked, THEN correct CST Candidate determines step IS levels for usable volume: applicable Candidate enters 27 and calculates (a) step 2.a ft-2.75ft= 24.25 for step 2(a)
(b) step 2.b ft - 2.5 ft= Candidate enters 22 and calculates 9.75 for step 2(b) 2 Candidate enters 24.25 and 9.75, and (c) step(a) + step(b) ft = calculates 34 for step 2( c)
(3) IF step d.(3) is checked, THEN cornect CST Candidate determines step is NOT levels for usable volume: applicable
- f. Convert the amount of CST level into gallons.
Candidate enters 34 and calculates (ft available) x 9636.78 gal/ft = approximately 327650 for step 2.f NOTE The nominal capacity of a Well Water pump is 300 GPM.
The nominal capacity of a Demineralized Water Transfer pump is 300 GPM.
The Fire System can fill the CST via fire hoses at greater than 500 GPM.
CAUTION I The status of both units should be considered when evaluating a makeup source.
Candidate determines there is NOT
- 3. IF adequate inventory exists to perform adequate inventory to perform a cooldown, THEN determine if an adequate cooldown.
makeup source exists to maintain hot statndby. Water required is 625067, inventory !
available is 327650
Job Performance Measure Form ES-C-l CUE: The shift manager requests the candidate to determine how long hot standby can be maintained with the current inventory.
- 4. IF adequate inventory does NOT exist to perform cooldown, THEN evaluate the following:
The candidate uses ATTACHMENT (9) MAKEUP WATER REQUIRED
- Maintaining hot standby conditions TO MAINTAIN HOT STANDBY.
- Time to restore an adequate makeup source If the chart is NOT interpolated, the
- Restoration of other plant systems (TBVs, value would be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of hot standby.
main feedwater system, etc.)
If chart is interpolated, the value would
- Performing partial cooldown while restoring be approximately 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> 34 minutes.
plant systems Terminating Cue: This JPM is complete when it is determined how long hot standby can be maintained.
The evaluator is expected to end the JPM.
Time Stop:
Job Performance Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
Verification of Completion Job Performance Measure Number: SRO-ADMIN-2 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __
Examiner's Signature and Date: _ _ _ _ _,_ _ _ _ _ _ _ _ _ _ _ _ __
Appendix C Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1) Unit-l and Unit-2 were at 100% reactor power.
- 2) A loss of offsite power occurred at 0800. SMECO is unavailable.
- 3) The OC DG is unavailable, the lA DG failed to start, 14 4kv bus is deenergized due to a ground fault.
- 4) The plant has been stabilized per EOP-7 with the following parameters:
a) It is now 0900.
b) Unit 1 RCS Temperature is 532F and steady. Unit 2 RCS temperature is 532F and steady.
c) 11 CST level is 27 feet, 12 CST level is 22 feet, 21 CST level is 26 feet
- 5) You are performing the duties of the Unit 1 CRS.
Initiating Cue:
The Shift Manager directs you to perform EOP-7 step AB, EVALUATE THE NEED FOR PLANT COOLDOWN.
I APPLICANT: _ __
CALVERl' CLIFFS NUCLEAR PO~WER PLANT 2011 ~~RC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-3
Appendix C Job Performance Measure Form ES-C-l Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-3 Task
Title:
Establish initial plant conditions for and approve performance of an STP.
Task Number: 210.001 KIA
Reference:
2.2.40 (3.4, 4.7)
Method of testing:
Simulated Performance: Actual Performance: ~
Classroom: [gJ Simulator: 0 Plant: 0 READ TO THE APPLICANT:
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:
- 1) Unit-l is at 100% reactor power.
- 2) STP O-SA-1 is scheduled today.
- 3) No maintenance was performed on the lA DG
- 4) You are performing the duties of the CRS.
Initiating Cue:
The Shift Manager directs you to prepare STP O-SA-l for performance by completing SRO portions of step 4.0.
Task Standard:
The candidate correctly completes the SRO portion of the STP preliminary section using the plan of the day and Technical Specifications.
The evaluator is expected to end the JPM.
Appendix C Job Performancj~ Measure Form ES-C-1 Worksheet Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
- 2. Technical Specifications Time Critical Task:
No Validation Time:
30 minutes Simulator Setup:
- a. None
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP)
Time Start:
CUE: The Shift Manager directs you to prepare STP O-SA-l for performance by completing SRO portions of section 4.0 CUE: The candidate is given a partial copy ofthe Plan ofthe Day and STP O-SA-l CUE: STP M-6S1C-IA is not required.
A. PERFORM the following determinations:
Candidate checks Scheduled
- 1. IF STP M-651 C-1A is to be performed concurrently Surveillance' based on the initiating with this test THEN NOTIFY E&C to perform STP cue.
M-651 C-1A prerequisites.
CUE: The candidate is given the plan of the day NOTE
- LOCI Sequencer testing is required monthly in Modes 1-4 .
- SIAS A-10 Logic, Channel Functional test is required quarterly in Modes 1-3 .
- 2. INDICATE ESFAS test requirements:
Candidate checks this checkbox 0 SIAS/UV OR LOCI SEQ test required: (check based on the preceding note required tests)
Candidate checks this checkbox D PERFORM Section 6.5, MONTHLY 11 based on the preceding note 4KV BUS LOCI SEQUENCER TEST D PERFORM Section 6.4, QUARTERLY Candidate checks this checkbox SIAS A-1 0 LOGIC AND UV A-4 LOGIC based on the preceding note TEST Candidate DOES NOT check this checkbox based on the preceding D ESFAS testing NOT required:
note NOTE Taking 1A DG to LOCAL makes the DG inoperable. This minimizes unloaded run time during ESFAS testing AND is the preferred alignment.
- 3. IF performing ESFAS testing, THEN REVIEW equipment availability AND INDICATE 1A DG Candidate checks this checkbox alignment during test: (N/A if NOT testing ESFAS) based on the preceding note D 1A DG in LOCAL during ESFAS te!~t:
Job Performance Measure Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
Candidate DOES NOT check this checkbox based on the preceding D 1A DG in AUTO during ESFAS test: note NOTE 1A DG remains operable when performing a Slow Speed start from 1C18A.
~
- 4. REVIEW PMT requirements, Surveillance Schedule I Candidate checks this checkbox AND INDICATE 1A DG start requirements: based on the surveillance requirements (Non-fast speed start)
[J Slow start of 1A DG:
Candidate does not check this checkbox based on the surveillance D Emergency start of 1A DG:
requirements.
Candidate does not check this Start of 1A DG NOT required checkbox based on the surveillance requirements.
'.."::H~' "ine YES - Performance of Sect. 6.1 is required Candidate checks these checkboxes
- based on the surveillance Monthly FO TRANSFER PP Automatic requirements.
Start test reQuired.
Candidate checks this checkbox Quarterly 1ST FO TRANSFER PP based on the surveillance Performance Capacity test required. requirements.
Candidate does not check this NO - Performance is NOT required; LEAVE checkbox based on the surveillance Sect. 6.1 blank reqUlrements.
Candidate checks this checkbox DYES - Performance of Sect. 6.9 is required based on the surveillance requirements Candidate does not check this D NO - Performance is NOT required; LEAVE checkbox based on the surveillance Sect. 6.9 blank requirements.
Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
NOTE FSTC-OPS OR System Engineer may be contacted to make the determination.
CUE: No maintenance was performed on the diesel
- 6. IF this is the first performance of this test after EDG- I . . . . ..
13 has been performed on 1A DG, THEN INDICATE
- Candidate determines the step is minimum 1A DG loaded run time for Sect. 6.8: (N/A if NOT Applicable NOT first test after EDG-13) [80273]
- 7. REVIEW the Surveillance Schedule OR PMT to determine if Quarterly air receiver check valve testing is required.
Candidate checks yes based on D YES - Quarterly air receiver check valve surveillance requirements.
testing is required.
NO ~ Quarterly air receiver check valve testing is NOT required.
Terminating Cue: This JPM is complete when all SRO steps are complete in section 4.0.
The evaluator is expected to end the JPM.
I
Job Performancl~ Measure Form ES-C-l Verification of Completion Job Performance Measure Number: SRO-ADMIN-3 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ UN SAT --------
Examiner's Signature and Date:
Form ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1) Unit-1 is at 100% reactor power.
- 2) STP O-SA-1 is scheduled today.
- 3) No maintenance was performed on the 1A DG
- 4) You are performing the duties of the CRS.
Initiating Cue:
The Shift Manager directs you to prepare STP O-SA-l for performance by completing SRO portions of step 4.0.
I APPLICANT: - -
CALVERl' CLIFFS NUCLEAR POWER PLANT 2011 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-4
Appendix C Job Performance Measure Form ES-C-l Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.SRO-ADMIN-4 Task
Title:
Determine radiological conditions for personnel exposure Task Number: No equivalent task at CCNPP KIA
Reference:
2.3.7 (3.5, 3.6)
Method oftesting:
Simulated Performance: Actual Performance: _::1_
Classroom: _~ Simulator: Plant:
READ TO THE APPLICANT:
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:
- 1. Unit 2 is at 100% power.
- 2. 12 SFP coolers is in service. 11 SF]) cooler is isolated for maintenance on 0-SFP-196,11 PP SUCT FR 11 SFP DRN. Maintenance is complete.
- 3. Maintenance needs you to observe for any binding while cycling the valve a number of times before its return to service.
Initiating Cue:
You have been directed to cycle 0-SFP-196, 11 PP SUCT FR 11 SFP DRN multiple times to observe for binding, and then stand by to clear tags and open the downstream isolation valve. Task time is estimated to take 10 minutes.
State the radiological requirements for lentering this area. Include in your discussion:
- 1. Protective clothing required in the work area
- 2. Highest radiation level in the work area
- 3. Expected dose for this assignment
- 4. Dose rate alarm
- 5. Low dose waiting area What is the definition of a Locked High Radiation Area?
Task Standard:
Determine radiological conditions for p,ersonnel exposure NRC-17 Page 2 of6 NUREG-1 021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria:
- 1. All critical steps completed.
- 2. All sequential steps completed in order.
- 3. All time-critical steps completed within allotted time.
- 4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Spent Fuel Cooling Room Survey Map
- 2. RWP 106 task 2, "Operations Activities in High Radiation Areas (HRAs)"
- 3. RP-l-100, "Radiation Protection", Revision 8 General
References:
RP-I-I00, "Radiation Protection", Revision 8 (Pages 14,31)
Time Critical Task:
No Validation Time:
10 minutes Simulator Setup:
None NRC-17 Page 3 of6 NUREG-1 021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Review survey map and R WP. Same as element.
- 1. State protective clothing Determines that R WP specifies requirements. Anti-Cs and conferring with RST (Radiation Safety Technician).
- 2. Identify highest radiation level in Determines that highest radiation the area. level in the area is 350 mRlhr 0 SFP-196.
- 3. Calculate expected dose for this Determines that expected dose in 10 assignment. minutes is 1/6
- 350mRlhr = 58.3 mR
- 4. Identifies dose rate alarm setpoint. Determines from R WP that dose rate alarm will be set at 950 mRlhr.
- 5. Locates low dose waiting area. Identifies from R WP room low dose waiting area is by the room door, or identifies lowest general area is by the door (.4 mRlhr), or states would wait outside of the room in the hallway.
- 6. Explains the radiation classification States that Locked HRA is an area of a Locked High Radiation Area. where dose could exceed 1RIhr at 30cm.
TIME STOP Examiner Note: The task is complete when the applicant has provided requested radiological informatilon.
NRC-17 Page 4 of6 NUREG-l 021, Revision 9
Appendix C Job Performance Measure Form ES-C-l Verification of Completion Job Performance Measure Number: ADMIN-4 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT ------- UNSAT - - - - - - - -
Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
NRC-17 Page 50f6 NUREG-l 021, Revision 9
Appendix C Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions:
- 1. Unit 2 is at 1000/0 power.
- 2. 12 SFP coolers is in service. 11 SFP cooler is isolated for maintenance on 0-SFP-196, 11 PP SUCT FR 11 SFP DRN.
Maintenance is complete.
- 3. Maintenance needs you to observe for any binding while cycling the valve a number of times before its return to service.
Initiating Cue:
You have been directed to cycle 0-SFP-196, 11 PP SUCT FR 11 SFP DRN multiple times to observe for binding. Once cycling is complete, stand by to clear tags and open the downstream isolation valve. Task time is estimated to take 10 minutes.
State the radiological requirements for entering this area. Include in your discussion:
- 1. Protective clothing required in the work area
- 2. Highest radiation level in the work area
- 3. Expected dose for this assignment
- 4. Dose rate alarm
- 5. Low dose waiting area What is the definition of a Locked High Radiation Area?
NRC-I? Page 6 of6 NUREG-l 021, Revision 9
I APPLICANT: _ __
CALVERT~ CLIFFS NUCLEAR POWER PLANT 2011 ~~RC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-5
Job Performance Measure Form ES-C-l Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADlVIIN-5 Task
Title:
Determine appropriate emergency response actions per the ERPIP Task Number: 204.097 KJA
Reference:
2.4.38 (2.4, 4.4)
Method of testing:
Simulated Performance: D Actual Performance: [?5J Classroom: [?5J Simulator: D Plant:
READ TO THE APPLICANT:
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:
- 1) Unit-l is at 100% reactor power.
- 2) An unisolable RCS leak has developed.
- 3) 13 Charging pump is tagged out for maintenance.
- 4) Chemistry reports no activity in Steam Generators
- 5) You are performing the duties of the CRS.
Initiating Cue:
The Shift Manager directs you to determine the RCS leak Rate per AOP-2A Task Standard:
The candidate determines the RCS leak rate. Once the leak rate is calculated, the candidate will correctly classify the event and complete the initial notification form within 15 minutes.
Job Performance Measure Form ES-C-l Evaluation Criteria:
- 1. All critical steps completed (denoted by shading).
- 2. All sequential steps completed in order.
- 3. All time-critical steps (denoted by an asterisk) completed within allotted time.
- 4. JPM completed within validated tiffil~. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1. Procedures and manuals normally available in the plant General
References:
- 2. ERPIP, Emergency Response Plan Implementation Procedure Time Critical Task:
No Validation Time:
30 minutes Simulator Setup:
- a. None
Job Performanc(~ Measure Form ES-C-l ELEMENT STANDARD
- Time Start: - - - -
CUE: The Shift Manager directs you to determine the RCS leak Rate per AOP-2A The candidate locates AOP-2A Same as element CUE: The STA has collected plant information on attachment 1 of AOP-2A Determine Factors:
The candidate determines 18.9
- k. Estimate PZR volume factor based on ReS Pressure Step g.
I. Estimate ReS expansion factor based on ReS The candidate determines 86.2 Temp., TAVEStep e.
i Calculate Leak Rate: The candidate calculates m.PZR Level approximately 264 The candidate calculates
- n. ReS Temperature approximately 86 I
I The candidate calculates
- o. ReS change approximately 17 The candidate calculates
- p. Calculate Leak Rate approximately 100 gpm aluate the ERPIP based on the calculated RCS leak rate P Call Time Start:
The candidate locates ERPIP 3.0, IMMEDIATE Same as element ACTIONS Refers to Immediate Actions, identifies the category from Determines ATTACHMENT 2 is the listing and goes to the appropriate Attachment. applicable
Job Performance Measure Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP)
AfTACHMENT 2, EMERGENCY CLASSIFICATION A. CLASSIFY the Event
- 1. WHEN an event is in progress potentially requiring emergency response, THEN CONDUCT the following actions in parallel:
CUE: The Unit 2 CRS will perform step A.1.a
- .........- - - - - - - - - - - - - - - - - - - - - , - - - - - - - - - - - - - - - - - - i
- a. DETERMINE if existing conditions warrant implementation of one of emergency response attachments:
- Personnel Emergency, Att 15
- Fire, Att 16,17,18
- Radiological Event, Att 19
- Severe Weather, Att 20,21
- Hazardous Material Release, Att 22
- Containment Evacuation, Att 23
- Security, Att 24
- Large Area Loss, Att 25
- Large Steam Leak, Att 26
- Extensive Damage Mitigation Guidelines, Att27
- S/G Level Monitoring During Extensive Damage Mitigation, Att 28 Determines an ALERT classification is warranted under FISSION
- b. EVALUATE the existing conditions against PRODUCT BARRIER Attachment I, Emergency ActionLt:~vel DEGRADATION, based on a potential loss of RCS barrier.
(EAL) Criteria, to determine if an EAL threshold has been met. RCS Barrier- Unisolable ReS Leakage> 50 gpm.
Form ES-C-I ELEMENT STANDARD (SHADED = CRITICAL STEP)
B. IMPLEMENT Emergency Response Actions
- 1. IF existing conditions warrant implementation of an emergency response attachment, in parallel, Determines step is NOT applicable THEN GO TO that attachment AND begin response actions.
- 2. IF an EAL condition is met, THEN OBTAIN an Attachment 3, Initial Notification Form, AND GO TO the appropriate EAL Declaration attachment: Determines from previous evaluation that an EAL is satisfied and obtains
- General Emergency Actions, Att 4 an Initial Notification form.
Identifies ALERT Actions as the
- Site Area Emergency Actions, Att 9 appropriate declaration attachment and goes to Attachment 11.
- Alert Actions, Art 11
- Unusual Event Actions, Art 13 Candidate commences actions per Attachment 3, ALERT A.I COMPLETE Attachment 3, Initial Notification Refers to Attachment 3, Initial Form. Notification Form.
NOTE TO EVALUATOR:
Page 2 of ATTACHMENT 3 contains instrudions for completing the form and mayor may
. not be referred to as the applicant completes page 1.
CUE: Candidate completes Attachment 3 Initial Notification Form, following instructions provided on the back of the form Attachment 3, Initial Notification Form; Page-l Section-A CI Complete Item A I. Checks "is" a drill CI Complete Item A2.
- Checks "Unit 1" CJ Complete Item A3. Checks "ALERT" CJ Complete Item A4. Enters "H.A. 5 .1. 2" CI Complete Item A5. Checks "Yes"
Appendix C Job Performance Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP) 0 Complete Item A5a Checks "Yes" 0 Complete Item A5b Checks "Airborne" 0 Complete Item A6. Checks 6.a "None" Completes A. 7 only after items 1 through 6 are completed, and within o Complete Item A 7.
15 minutes of determining an EAL is met.
ATTACHMENT 3, Page 1, Section B Selects blocks for:
Drill, ALERT, and Staff Normal o B. Complete Section B.
Emergency Response Facilities.
Prints name and signs.
CUE: The request for an STA peer check is acknowledged Terminating Cue: Terminating Cue: This JPM is complete when an EAL classification is determined based on given plant conditions ~md the Initial Notification Form is completed.
No further actions are required.
Time Stop:
ERPIP Call Time Start - Time Stop = <<15 Minutes)
Job Performance Measure Form ES-C-l Verification of Completion Job Performance Measure Number: SRO-ADMIN-5 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Time to Complete:
Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Result: SAT _ _ _ _ __ UNSAT ---------
Examiner's Signature and Date: - - - - - - - - - - - - - - - - - - - - -
Job Perfonnanc(:! Measure Fonn ES-C-l APPLICANT'S CUE SHEET Initial Conditions:
- 1) Unit-l is at 100% reactor power.
- 2) An unisolable RCS leak has developed.
- 3) 13 Charging pump is tagged out for maintenance.
- 4) Chemistry reports no activity in Steam Generators
- 5) You are performiug the duties of the CRS.
Initiating Cue:
The Shift Manager directs you to determine the RCS leak Rate per AOP-2A