ML110110571

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Calvert Cliffs, Operator Licensing Retake Exam - Draft Operating Exam (Sections a and B) (Folder 2)
ML110110571
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 12/20/2010
From:
Constellation Energy Nuclear Group
To: Silk D M
Operations Branch I
Hansell S
Shared Package
ML103200039 List:
References
TAC U01839
Download: ML110110571 (107)
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Text

I APPLICANT:

__CALVERT NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

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 Method of Simulated Performance:

D Actual Performance: 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 The CRS directs you to Perform Reactivity Safety Function per Task The candidate will initiate Emergency Boratilon per Appendix Job Performance Measure Form ES-C-l Worksheet
1. Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. 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: Reset to IC-24 (both units at 100%) Enter malfunctions: 4KVOOl_03, fault on 13 4kv bus on Fl 4KVOOl_04, fault on 14 4kv bus on F2 Place simulator in run Initiate Fl and F2 Manually trip the reactor when 11 and 12 SGFPs trip on low suction pressure Freeze the simulator.

Job Performance 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 Same as element. 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 Check that NO more than ONE CEA is NOT fully The candidate determines that CEA positions CANNOT be determined and alternate action step 3.1 is required.

3.1 IF more than ONE CEA fails to fully insert, The candidate places the THEN borate the RCS to at least 2300 ppm as handswitch for l-CVC-512-CV in follows: close. a. Shut the VCT M/U valve, 1-CVC-512-CV. Open the SA DIRECT M/U valve, 1-CVC-514-The candidate may place 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 1-CVC-508-MOV MOV Candidate opens

  • MOV 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 The candidate starts 11 BA pump. (12 BA pump is deenergized due to loss of power affects)

Job Performancie Form ES-C-I STANDARD The candidate places

f. Shut the VCT OUT valve, 1-CVC-501-MOV.

MOV in close. The candidate verifies 11

  • charging pump 9 Start ALL available CHG Th e I oss 0 f144k v b us s tart sa II available charging pumps so NOT
  • critical.
4. Verify demineralized water makeup to the ReS is Candidate verifies II and 12 secured as follows: 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 CV is shut.
  • IF RCS Makeup is in Direct Lineup, THEN The candidate determines this step the RWT CHG PP SUCT, 1-CVC-504-MOV, is NOT applicable is shut 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 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 The eRS directs you to Perform Reactivity Safety Function per APPLICANT:

__CALVERT NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

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, Method of Simulated Performance:

Actual Perfonnance: 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.
3. The ST A has calculated the RCS leak rate to be 75 gpm. 4. You are the Control Room Operator Initiating The CRS directs you to perform AOP-2A step VI.E, 'Attempt to isolate the 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 Form ES-C-I Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. 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: Reset to I C-24 (both units at 100%) Enter

___ a. RCS003, RCS Leak, at 75 Place simulator in run Open I-PS-5464, plant sample isolation valve Place an off-nonnal pink ring on I-PS-5464 Freeze the simulator when a second charging pump starts (about 4 minutes)

Appendix 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 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.

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 computer points T1 07 and 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 vent valves closed 1-RC-103-SV 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 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 The candidate determines the leak RCS Pressure, THEN assume the leak is 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 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" "UNIT 1 MAIN VENT GASEOUS" THEN perform the following actions: a. Start ALL available CNTMT AIR CLRs Job Performance 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. 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 Radiation Monitor. CC HEAD TK LVL" high alarm clear The candidate reports AOP-2A block step E is complete.

CUE: Acknowledge step E is complete CUE: Perform block AOP-2A step F, DETERMINE THE ACTIONS FOR RCS LEAKAGE, ON PAGE 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 is greater than the capacity of ONE Pump. THEN. with the approval of the The candidate will recommend perform the following actions: tripping the reactor and a. Trip the implementing EOP-O b. IMPLEMENT EOP-O. POST IMMEDIATE 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 -_* 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 Initial Conditions:

1. Unit 1 is in Mode 1 at 100% power. 2. An RCS leak has occurred.
3. The ST A has calculated the RCS leak rate to be 75 gpm. 4. You are the Control Room Operator Initiating The CRS directs you to perform AOP-2A step VI.E, 'Attempt to isolate the I APPLICANT, __CALVERT NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

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: READ TO THE I will explain the initial conditions, which steps to simulate or discuss, and initiating cues. When you complete the task successfully, the objective for this performance measure will be Initial

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 4. EOP-O has been completed, EOP-5 has implemented.
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,........, Fonn Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made. Required Materials: Procedures and manuals nonnally available in the plant General

References:

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%) Enter

__a. FI: RCS002, RCS leak @ 1200 3. Enter Overrides

__a. I-SI-406, 13 HPSI pump discharge valve, open @ __4. Tag 11 HPSI PP HS in __5. Tag I-S1-656 in 6. Place simulator in run 7. Initiate __8. Close I-CV-515 and

__9. Stop IIA and 12B 10. Freeze simulator 5 minutes after SIAS

__ 11. Acknowledge all

---Perionmruncle 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 1. IF pressurizer pressure is less than or equal to 1725 PSIA OR containment pressure is greater than or equal to 2.8 PSIG, THEN verify SIAS actuation.
2. IF pressurizer pressure is greater than 1725 PSIA AND containment pressure is less than 2.8 PSIG, THEN perform the following actions to block SIAS: 3. IF SIAS has actuated, THEN perform the following actions: a. Verify the following pumps are running: 11 HPSI PP 13 HPSI PP 11 LPSI PP 12 LPSI PP ALL available CHG PPs b. Verify safety injection flow: HPSI flow PER ATTACHMENT(10), HIGH PRESSURE SAFETY IN"IECTION FLOW, when pressure is below 1270 PSIA Perform the following actions as necessary: IF 11 HPSI PP failed, THEN start 12 HPSI PP. Srume as element. Candidate will determine that SIAS has actuated by checking SIAS alarm, 13 HPSI pp has started, rund HPSI MOVs have opened. Crundidate will detenmine the step is NOT applicable Detenmines 11 HPSI is not running due to a tagout Crundidate locates EOP attachments, refers to ATTACHMENT (10), and detenmines 13 HPSI flow is less than the minimum required based on addition of the 4 loop flow indicators rundJor the HPSI total flow indication.

Candidate detenmines 11 HPSI pump did not fail, it is tagged out Job Perfonnancle 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, 653-MOV. Candidate opens I-S1-653 (3) Shut HPSI HDR XCONN valve, Candidate closes I-S1-655 MOV. Ensure electrical power is available to Same as element valves and CUE: Another operator will verify Safety Injection lineup per attachment
2. Verify safety injection system PER ATTACHMENT (2), VERIFICATION 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 Number of Attempts:

_________________Time to 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 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 4. EOP-O has been completed, EOP-S has been implemented.

S. You are the Reactor Operator Initiating Cue: The CRS directs you to perform EOP-S block step D, 'Monitor RCS Depressurization' I APPLICANT:

__CAL VER l' NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

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 Simulated Performance:

0 Actual Performance: Classroom:

Simulator:

[gJ 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 Form ES-C-l Form Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. 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:

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 Fonn ES-C-I Fonn ES-C-l ELEMENT STANDARD Time CUE: The RO announces

'The reactor is tripped', the CRS announces EOP-O' 1. Check the Reactor has tripped. 2. Ensure the Turbine has tripped by performing the following actions: a. Depress BOTH TURBINE TRIP buttons. b. Check the Turbine Main Stop Valves shut:

  • MSV1
  • MSV2
  • MSV3
  • MSV4 Candidate verifies the reactor has tripped Candidate depresses both turbine trip buttons Candidate detennines MSV I did not shut and alternate step b.l is required Note: The candidate may report 'Taking alternate actions for (stop valve open)'. This report is not critical.

CUE: Acknowledge alternate actions IF ANY Turbine Main Stop Valve failed to shut, THEN shut BOTH MSIVs. c. Check Turbine Speed drops. d. IF the Turbine was paralleled to the grid, THEN verify the Turbine Generator Output breakers open:

  • 11 GEN BUS BKR, O-CS-552-22
  • 11 GEN TIE BKR, O-CS-552-23
e. Verify 11 GEN FIELD BKR, 1-CS-41, is c)pen. Candidate will shut both Main Steam Isolation Valves Candidate detennines turbine speed is lowering The candidate detennines breaker 552-22 did not open and takes its handswitch to open. Same as element Same as element Job Perfonnance Fonn ES-C-l Fonn ES-C-l (SHADED = CRITICAL Verify 11 EXCITER FIELD BKR, 1-CS-41 E, is open. Ensure BOTH MSR 2ND STG STM SOURCE MOVS are shut:
  • 1-MS-4025-MOV (11 MSR)
  • 1-MS-4026-MOV (12 MSR) 3.1 IF EITHER MSR 2ND STG STM SOURCE MOV failed to shut, THEN perform the actions: a. Verify the MSR 2ND STG HIGH LOAD MOV is shut: * (11 MSR) 1-MS-4018-MOV
  • (12 MSR) 1-MS-4017-MOV Dispatch an operator to verify the MSR 2ND STAGE BYPASS CONTROL VALVE panel loader in MANUAL with panel loader output at zero. STANDARD The candidate will open the exciter field breaker The exciter field breaker will not automatically open Detennines the valves have not shut due to loss of power and alternate action step 3.1 IS required.

Same as element. (Not critical since Main Steam Isolation Valves were closed in step b.l) Same as element 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: *

Measure Form ES-C-l Form 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 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 The CRS directs you to perform Turbine Trip per I APPLICANT:

__CALVERT CLIFFS NUCLEAR POWER PLANT 2011 NRC ITIAL LICENSED OPERATOR EXAM JPM #:

Appendix 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: 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: Unit 1 was in Mode 1 at 100% power. The overhead annunciator alarm E55 "llB RCP SEAL TEMP HIIPRESS" has come in 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 Job Perfonnance Measure Fonn ES-C-l Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made. Required Materials: Procedures and manuals nonnally available in the plant 1. Alann Manual 1 C06 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 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 Same as element. I C06 window E-55. There is a potential for heat checking of seal faces if RCP seal limits have exceeded.

This heat damage may cause seal degradation/failure during depressurization (compressive forces removed) or subsequent RCP (centrifugal 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 seal pressure alann exist. Checks validity of alann. 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 Candidate detennines step is N/A 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 Job Performancl;!

Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP) If RCP seal bleed-off is less than normal (or zero) with normal seal pressure, the vapor seal may failed. IF the vapor seal is determined to be failed, THEN IMPLEMENT AOP**2A, Excessive Reactor Coolant Leakage Debris from a failed seal may propagate 1to remaining seal stages, leading to complete seal CUE: CRS will contact System Engineer. 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 NI A. 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 shutdown to CRS due to two Operation, and OP-4, Plant Shutdown failed seals on 11 B RCP from Power Operation to 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 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 Examiner's Signature and Date: ____________________

Appendix Job Performance Measure Form ES-C-I Worksheet APPLICANT'S CUE SHEET Initial Conditions: Unit 1 was in Mode 1 at 100% power. The overhead annunciator alarm E55 "lIB RCP SEAL TEMP HIIPRESS" has come in You are performing the duties ofthe Unit 1 RO. Initiating Initiating Cue: The CRS directs you to respond to alarm window I APPLICANT:

__CAL VER l' NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

Appendix C Job Performance Measure Form ES-C-l Worksheet Facility:

Calvert Cliffs 1 & 2 Job Performance Measure No.: Task Title: Respond to the loss of a 120 volt vital AC Task Number: KIA

Reference:

006 A2.01 (3.4, Method of 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 The CRS directs you to Perform block step IV.A of Task Standard:

The candidate will use AOP-7J to diagnose llioss of 1 YO 1. The candidate restore pressurizer pressure and level instrUlments affected by the bus loss. candidate will protect the pressurizer by securing charging pumps exceeding 225 inches. The cllndidate will protect RCPs by placing 12 CC HX

Appendix Job Performance Measure Form ES-C-l Worksheet Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. 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-7J, Loss of 120 Volt Vital AC or 125 Volt Vital DC Power Time Critical Task: No Validation Time: 20 minutes Simulator Setup: __ 1. Reset to IC-24 (both units at 100%) 2. Enter malfunctions:
a. Loss of 1 YOI on Fl 3. Place simulator in run 4. Secure 12 CC HX per 01-16 5. Initiate the loss of 1 YOI __6. Freeze simulator when level or pressure alarm annunciates

---i Job Perfonnance 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 Same as element. CUE: The CRS will perform step 1 Perform the following immediate actions: a. Confirm with the Fuel Handling that any fuel assembly being handled been placed in a safe

b. Suspend movement of irradiated fuel. N/A Suspend movement of heavy loads irradiated d. IF in Modes 5 or 6, THEN suspend involving positive reactivity additions could result in loss of required SDM or
12. GO TO 1Same 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 1 YO 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 I YOI has occurred and proceeds to section V on page 9.(1Y01). Cue: Acknowledge recommendation, continue with the procedure I 1. Verify that the PRZR PRESS CH SEL Switch is in The candidate places the Y position.

PRESS CH SEL Switch in The candidate places RRS CH 2. Verify that the RRS CH SEL Switch is in SEL Switch in RRS-Y position.

3. Verify that the PRZR LVL CH SEL Switch is in the Same as element. 11 OY
4. Verify that the PZR HTR LO LVL CUT-OFF The candidate places PZR HTR Switch is in the Y position.

LO LVL CUT-OFF SEL Switch in Y.

Appendix Job Performance Measure ELEMENT STANDARD (SHADED = CRITICAL STEP) CUE: Another operator will place switch 81 in OFF, continue 5. Isolate the RCS Loop 11 instruments to RRS NIA Channel Y by placing switch S1 to OFF. 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 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 VL Vs 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. 9. Restore 11 Saltwater header: The candidate will place 12 CC HX in service by a. Verify 12 CC HX is in service.

  • opening l-CC-3826-CV throttle open 12 CC HX SW FLOW CONTR, 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 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 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 The CRS directs you to Perform block step IV.A of AOP-7 I APPLICANT:

___CALVERT CLIFFS POWER 2011 INITIAL OPERATOR JPM #:

Appendix C Job Performance Measure Form ES-C-l Worksheet Facility:

Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-7 (Alt Task Title: Override shut a Task Number: KIA

Reference:

007.A2.01 Method of Simulated Performance:

D Actual Performance: 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 Job PerformanCE!

Measure Form ES-C-l Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. 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: Resetto IC-1 Enter malfunctions: Override 1-PI-103-1 to 1533# Place simulator in run Override PORV 402 to "manopen" Freeze the simulator when pressurizer pressure lowers to 225 psia.

Appendix C Job 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 1 C06 alarm manual and refers to E-21 Same as element. The candidate determines the step 1. The PORVs are energized.

is applicable since PORV 402 is open 1. PERFORM the following:

The candidate determines the a. IF reactor trip occurs, THEN IMPLEMENT reactor is shut down and step is NOT applicable.

EOP-O, Post-Trip Immediate Actions. CUE: The shift manager will contact the electric shop b. NOTIFY the electric shop to verify the status of the PORV thermal overloads ensure PORV operability. 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 current lineup and determines OPERATING AREA of the RCP curve RCP are in the non-operating area of the curve. Candidate secures 11 A and 12B RCPs Appendix Job Performance Measure Form ES-C-l ELEMENT (SHADED = CRITICAL STEP) (2) WHEN the cause of the high pressure condition has been corrected, THEN: [B0064] (3) IF a PORV fails to shut or is open due to a failed transmitter, THEN SHUT the applicable PORV Block, 1-RC-403-MOV or 1-RC-405-MOV.

CUE: The CRO will perform step l.d.(4) (4) DRAIN the PORV discharge piping to the Quench Tank as follows: MONITOR computer points T106, T107, and T1 08 for leak-off temperatures.

STANDARD Candidate determines the PORV is open due to equipment malfunction and not high RCS pressure.

Determines step is NI A The candidate determines PORV 402 is open due to a failed transmitter and closes the PORV 402 block valve l-RC-403-MOV N/A Candidate uses plant computer to 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 Measure Form ES-C-l Verification of CI)mpletion Job Performance Measure Number: SIM-7 Applicant:

NRC Examiner:

Date Performed:

Facility Number of Time to 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:

__CAL VERNUCLEAR POW 2011 INITIAL OPERATOR JPM #:

PertorJmaJl1ce 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 KJ A

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: A severe fire has resulted in Control Room evacuation.

AOP-9A has been implemented. 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 Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made. Required Materials: Procedures and manuals normally available in the plant General

References:

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 i Appendix 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 Same as element. Candidate proceeds to the Unit-2 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 Condensate Supply, 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 indication for the Component Cooling Service Water Head Same as element a. Component Cooling Head Tank: (1) Open Component Cooling Head Makeup Bypass, (2) Shut 2-CC-3820-CV Inlet Isol, 2-CC-107 Same as element 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 Same as element Makeup Bypass, 2-SRW-114 (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 Same as element Service Water Head Tanks levels and fill as 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 Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE Initial Conditions: A severe fire has resulted in Control Room evacuation.

AOP-9A has been implemented. You are performing the duties of the U nit-2 ABO. Initiating Cue: You have just completed Step CG, ESTABLISH SAL TW ATER FLOW THROUGH THE COMPONENT COOLING HEAT EXCHANGERS which directs you to "Go to the 69' Aux Building to perform Step CH".

  • , CALVER1' NUCLEAR PO'WER 2011 INITIAL OPERATOR JPM #:

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:

1. Maintenance is scheduled to be performed on AF AS channel ZE 2. Shift Manager approval has been
3. You are performing the duties of the Unilt-2 CRO. Initiating The CRS directs you to shutdown AF AS Sensor Cabinet Task This JPM is complete when AF AS ZE sensor cabinet is Form ES-C-l Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made. Required Materials: Procedures and manuals normally available in the plant General

References:

01-32B, AF AS SYSTEM OPERATION Time Critical Task: No Validation Time: 20 minutes Simulator Setup: 1. None

Appendix Job Performanc1e Measure Form ES-C-l Worksheet ELEMENT STANDARD (SHADED = CRITICAL STEP) Time CUE: The CRS directs you to shutdown AFAS Sensor Cabinet Locate OI-32B Section 6.3. Same as 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 CHECK that NO trips are present on any other Same as element Sensor Cabinets for SG Low Level or for Differential

3. CHECK that NO trips are present on either of the Same as element Logic Cabinets.

[B0068] PLACE the circuit breaker on the Sensor Cabinet Same as element to be shutdown to the OFF position. (FIGURE 1) 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 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 Initial Conditions:

1. Maintenance is scheduled to be performed on AF AS channel ZE 2. Shift Manager approval has been obtained.
3. You are performing the duties of the Unit-2 CRO. Initiating The CRS directs you to shutdown AF AS Sensor Cabinet APPLICANT:

__CALVERT NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

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: A severe fire has resulted in Control Room evacuation.

has been implemented. 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: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made. Required Materials: Procedures and manuals nonnally available in the plant General

References:

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 Form ES-C-I ELEMENT STANDARD (SHADED = CRITICAL STEP) Time CUE: The CRS directs you to perform step AP, Override Saltwater to the 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
  • Overboard, 1-CV-5149, to OVERRIDE 2. Place the following Handvalves to OVERRIDE {from left to right}:
j. 11A & 11B SRW HXs SW INLET, 5150 Same as element Same as element Same as element Same as element Same as element Same as element Same as element Same as element Same as element Same as element Same as element Job Performance Form ES-C-l West HV transfer stanchion 12A SRW HX SW STNR DIVERTER, 1-HV-Same as 12A SRW HX SW STNR FLUSH, 1-HV-Same as element 5158A 12B SRW HX SW STNR DIVERTER, Same as element HV-5159 d. 12B SRW HX SW STNR FLUSH, 1-HV-Same as element 5159A 12A &12B SRW HXs SW INLET, 1-HV-Same as element 5152 12A &12B SRW HXs SW BtU OUT, Same as element HV-5153 12A & 12B SRW HXs SW BYPASS, Same as element HV-5157 12A SRW HX SW OUTLET, 1-HV-5211 Same as element i. 12B SRW HX SW OUTLET, 1-HV-5212 Same as element Perform the next TBO assigned step. Terminating Cue: This JPM is complete when Saltwater to the Service Water Heat Exchan g ers is overridden.

No further actions are re q uired. The evaluator is ex p 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 Form ES-C-I APPLICANT'S CUE Initial Conditions: 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 NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

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 Plant: D Simulator:

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 Job Performance Measure Form ES-C-l Worksheet Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. 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:

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 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 developed head is less than the Steps 6.1.31.15 Did 11 AFW Pump develop a TDH required in step 6.1.31.15.

greater than or equal to 2800 feet in 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 Determines 11 AFW pump testing is UNSAT in step 6.1.31.16 if YES or NI A was answered in all steps 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 Verification of Completion Job Performance Measure Number:

NRC Date Facility Number of Attempts:

________________Time to Follow up Question:

________________________Applicant Response:

________________________Result: SAT 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 FEEDW ATER 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 NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

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

1) Unit-l and Unit-2 were at 100% reactor 2) A loss of offsite power occurred at 0800. SME:CO is
3) The OC DG is unavailable, the lA DG failed to start, 14 4kv bus is deenergized due to 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 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 Form ES-C-l Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. 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:

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. 1. WHEN the RCS parameters have been stabilized, THEN evaluate the need for a plant cooldown based on: Plant Status Auxiliary systems availability Condensate inventory PERATIACHMENT (9), MAKEUP WATER REQUIRED FOR RCS COOLDOWN Locate EOP Attachment (9) 1. Determine the amount of makeup water required to perform an ADV cooldown and a TBV cooldown, based on the time after shutdown:

a. ADV cooldown and time after shutdown b. TBV cooldown and time after shutdown 2. Determine the amount of makeup water available in the CSTs: a. Record the level in 11 CST. b. Record the level in 12 CST. c. Record the level in 21 CST. d. Determine the status of Unit 2 (check ()ne): (1) Mode 1, 2 or 3 and does NOT require AFWoperation.

(2) _ Mode 1, 2 or 3 and does require AFW operation. Mode 4, 5, 6 or defueled.

Same as element. Candidate will determine Attachment (9) completion is required Same as element. Candidate enters uses table 'INVENTORY REQUIRED TO COOL DOWN TO 300F' and determines 625067 gallons are required.

Candidate enters uses table 'INVENTORY REQUIRED TO COOL DOWN TO 300F' and determines 94828 gallons are required.

The candidate determines the tank levels from the initiating cue Candidate checks d.2. The loss of offsite power has caused a dual unit trip. Main feed water is NOT available to either unit on a loss of offsite power.

Job Performance Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP) NOTE: Calculated negative values should be entered as zero. e. Determine the amount of makeup available to Unit 1 using one of the formulas, based on the status checked in step (1) IF step d.(1) is checked, THEN correct 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 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 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 The nominal capacity of a Well Water pump is 300 The nominal capacity of a Demineralized Water Transfer pump is 300 The Fire System can fill the CST via fire hoses at greater than 500 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 adequate inventory to perform cooldown, THEN determine if an adequate makeup source exists to maintain hot statndby.

Water required is 625067, inventory

! available is 327650 Job Performance 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 Worksheet Form ES-C-l ELEMENT (SHADED = CRIT STEP)ICAL STANDARD 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 Job Performance Measure Form ES-C-l APPLICANT'S CUE SHEET Initial

1) Unit-l and Unit-2 were at 100% reactor 2) A loss of offsite power occurred at 0800. SMECO is
3) The OC DG is unavailable, the lA DG failed to start, 14 4kv bus is deenergized due to ground fault. 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:

__CAL VER l' NUCLEAR 2011 INITIAL OPERATOR JPM #:

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 Plant: 0 Simulator:

0 READ TO THE APPLICANT:

I will explain the initial conditions, which steps to simulate or discuss, and initiating cues. When you complete the task successfully, the objective for this performance measure will be Initial

1) Unit-l is at 100% reactor 2) STP O-SA-1 is scheduled 3) No maintenance was performed on the lA 4) You are performing the duties of the Initiating The Shift Manager directs you to prepare STP O-SA-l for performance completing SRO portions of step Task The candidate correctly completes the SRO portion of the STP preliminary using the plan of the day and Technical The evaluator is expected to end the Appendix Job Measure Form ES-C-1 Worksheet Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. 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:

STP 0-8A-I, TEST OF lA DG AND 11 4KV BUS LOCI SEQUENCER

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 SIAS/UV OR LOCI SEQ test required: (check based on the preceding note required tests) Candidate checks this checkbox PERFORM Section 6.5, MONTHLY 11 based on the preceding note 4KV BUS LOCI SEQUENCER TEST PERFORM Section 6.4, QUARTERL Y 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 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 equipment availability AND INDICATE 1A 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 Job Performance Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP) Candidate DOES NOT check this checkbox based on the preceding 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: Slow start of 1A DG: Emergency start of 1 A DG: Start of 1A DG NOT required 5. REVIEW the Surveillance Schedule OR PMT to '.."ine YES -Performance of Sect. 6.1 is required Monthly FO TRANSFER PP Automatic Start test reQuired.

Quarterly 1ST FO TRANSFER PP Performance Capacity test required.

NO -Performance is NOT required; LEAVE Sect. 6.1 blank DYES -Performance of Sect. 6.9 is required NO -Performance is NOT required; LEAVE Sect. 6.9 blank based on the surveillance requirements (Non-fast speed start) Candidate does not check this checkbox based on the surveillance requirements.

Candidate does not check this checkbox based on the surveillance requirements.

Candidate checks these checkboxes

  • based on the surveillance requirements.

Candidate checks this based on the , Candidate does not check this checkbox based on the surveillance reqUlrements.

Candidate checks this based on the Candidate does not check this checkbox based on the surveillance requirements.

I 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 NOT Applicable minimum 1A DG loaded run time for Sect. 6.8: (N/A if NOT first test after EDG-13) [80273] 7. REVIEW the Surveillance Schedule OR PMT determine if Quarterly air receiver check valve testing Candidate checks yes based on YES -Quarterly air receiver check valve surveillance requirements.

testing is required.

NO Quarterly air receiver check valve is NOT Terminating Cue: This JPM is complete when all SRO steps are complete in section 4.0. The evaluator is expected to end the JPM.

Job 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: CAL VER l' NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

Appendix Job Performance Measure Form ES-C-l Worksheet Facility:

Calvert Cliffs 1&2 Job Performance Measure Task Title: Determine radiological conditions for personnel Task Number: No equivalent task at KIA

Reference:

2.3.7 (3.5, Method Simulated Performance:

Actual Performance: Classroom: Simulator: 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: Unit 2 is at 100% power. 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. 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 What is the definition of a Locked High Radiation Task Standard:

Determine radiological conditions for p,ersonnel exposure Page 2 of6 NUREG-1 021, Revision 9 Appendix Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria: All critical steps completed. All sequential steps completed in order. All time-critical steps completed within allotted time. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made. Required Materials: Spent Fuel Cooling Room Survey Map RWP 106 task 2, "Operations Activities in High Radiation Areas (HRAs)" 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 Page 3 of6 NUREG-1 021, Revision 9 ELEMENT (* = CRITICAL STEP) TIME START Review survey map and R WP. 1. State protective clothing requirements. 2. Identify highest radiation level in the area. 3. Calculate expected dose for this assignment.

  • Identifies dose rate alarm setpoint.
  • Locates low dose waiting area. 6. Explains the radiation classification of a Locked High Radiation Area. TIME STOP STANDARD Same as element. Determines that R WP specifies Anti-Cs and conferring with RST (Radiation Safety Technician).

Determines that highest radiation level in the area is 350 mRlhr SFP-196. Determines that expected dose in 10 minutes is 1/6

  • 350mRlhr = 58.3 mR Determines from R WP that dose rate alarm will be set at 950 mRlhr. 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. States that Locked HRA is an area where dose could exceed 1 RIhr at 30cm. Examiner Note: The task is complete when the applicant has provided requested radiological informatilon. Page 4 of6 NUREG-l 021, Revision 9

Appendix C Job Performance Measure Form ES-C-l Verification of Completion ADMIN-4 Job Performance Measure Number: Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts:

_______________

_ Time to Complete:

Follow up Question:

_______________________

_ Applicant Response:

________________________

_ Result: SAT Examiner's Signature and Date: ___________________NRC-17 Page 50f6 NUREG-l 021, Revision 9 Appendix Job Performance Measure Form ES-C-l Worksheet APPLICANT'S CUE SHEET Initial Conditions: Unit 2 is at 1000/0 power. 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. 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 What is the definition of a Locked High Radiation Page 6 of6 NUREG-l 021, Revision 9 I APPLICANT:

__NUCLEAR POWER 2011 INITIAL OPERATOR JPM #:

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 KJ A

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 initiating cues. When you complete the task successfully, the objective for this performance measure will be Initial

1) Unit-l is at 100% reactor 2) An unisolable RCS leak has
3) 13 Charging pump is tagged out for
4) Chemistry reports no activity in Steam
5) You are performing the duties of the Initiating The Shift Manager directs you to determine the RCS leak Rate per Task 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 Form ES-C-l Evaluation Criteria: All critical steps completed (denoted by shading). All sequential steps completed in order. All time-critical steps (denoted by an asterisk) completed within allotted time. JPM completed within validated 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:

AOP-2A, Excessive RCS Leakage 2. ERPIP, Emergency Response Plan Implementation Procedure Time Critical Task: No Validation Time: 30 minutes Simulator Setup: a. None

Job Form ES-C-l STANDARD

  • Time Start: CUE: The Shift Manager directs you to determine the RCS leak Rate per The candidate locates AOP-2A Same as CUE: The STA has collected plant information on attachment 1 of Determine Factors: The candidate determines 18.9 Estimate PZR volume factor based on Pressure Step I. Estimate ReS expansion factor based on ReS The candidate determines 86.2 Temp., TAVEStep e. i Calculate Leak Rate: The candidate calculates approximately 264 m.PZR Level The candidate calculates ReS Temperature approximately 86 I The candidate calculates 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 The candidate locates ERPIP 3.0, 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 Form ES-C-l ELEMENT STANDARD (SHADED = CRITICAL STEP) AfTACHMENT 2, EMERGENCY CLASSIFICATION A. CLASSIFY the Event 1. WHEN an event is in progress requiring emergency response, CONDUCT the following actions in CUE: The Unit 2 CRS will perform step A.1.a .........

a. DETERMINE if existing conditions implementation of one of emergency 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 S/G Level Monitoring During Damage Mitigation, Att Determines an ALERT classification is warranted under FISSION PRODUCT BARRIER *b. EVALUATE the existing conditions against DEGRADATION, based on a Attachment I, Emergency potential loss of RCS barrier. (EAL) Criteria, to determine if an EAL RCS Barrier-Unisolable ReS threshold has been met. 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

2. IF an EAL condition is met, THEN OBTAIN an Attachment 3, Initial Notification Form, AND GO TO Determines from previous evaluation the appropriate EAL Declaration attachment:

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, Form. Notification 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 Checks "is" a drill CI Complete Item

  • Checks "Unit 1" CJ Complete Item Checks "ALERT" CJ Complete Item Enters "H.A.5 .1. 2" CI Complete Item Checks "Yes" Appendix C Job Performance Measure Worksheet Form ES-C-l ELEMENT (SHADED = CRITICAL STEP) STANDARD 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 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:

NRC Date Facility Number of Attempts:

_______________Time to 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 2) An unisolable RCS leak has
3) 13 Charging pump is tagged out for
4) Chemistry reports no activity in Steam
5) You are performiug the duties of the Initiating Cue: The Shift Manager directs you to determine the RCS leak Rate per AOP-2A
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