Text

Initial Exam 2014-302 Final Administrative JPMs
	ML15013A271
Person / Time
Site:	Harris
Issue date:	01/13/2015
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
Shared Package
ML15013A407	List: IR 05000400/2014302; ML15013A231; ML15013A235; ML15013A238; ML15013A241; ML15013A245; ML15013A249; ML15013A251; ML15013A262; ML15013A267; ML15013A271; ML15013A275;
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Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 001004H101 Task

Title:

Perform A Manual Shutdown Margin JPM No.: 2014 NRC Exam Calculation Admin JPM RO A1-2 K/A

Reference:

G 2.1.25 RO 3.9 SRO 4.2 Alternate Path - NO Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss or perform, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The plant has been operating at 92% power for 2 weeks.

OST-1005, Control Rod and Rod Position Indicator Exercise Quarterly Interval Modes 1 - 3, was just performed.

Initial Conditions: One rod in Control Bank B was determined to be immovable/stuck.

Core burnup is 350 EFPD

RCS boron concentration is 600 ppm

POWERTRAX is NOT available The CRS has entered Tech Spec 3.1.1.1 and has directed you to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, Manual SDM Calculation (Modes 1 and 2) for current plant Initiating Cue: conditions.

NOTE: For this JPM notify evaluator when independent verification is required to be performed.

2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: OST-1036, Attachment 3, Manual SDM Calculation (Modes 1 and 2),

completed with SDM of 2872 + 100 pcm (tolerance based on total of curves used and their division readability)

Required Materials: Calculator, ruler General

References:

OST-1036, Shutdown Margin Calculation Modes 1-5 (Rev. 48)

Curve Book (Cycle 19)

Handouts: OST-1036, Shutdown Margin Calculation Modes 1-5 (Rev. 48), pg 19, 24 and 25 Time Critical Task: No Validation Time: 20 minutes Critical Step Justification Must determine correct rod insertion limit based on curve value. The Step 4 number of rod steps will be an input to the calculation.

Must determine correct power defect based on curve value. The power Step 7 defect will provide one of the inputs to the calculation.

Must determine the correct rod worth based on curve value. The rod Step 8 worth will provide one of the inputs to the calculation.

The total shutdown margin was the task that the CRS directed applicant Step 10 to perform.

2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Page 3 of 15 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

OST-1036 Performance Step: 1 OBTAIN PROCEDURE Standard: Reviews Procedure Evaluator Cue: Provide OST-1036 Section 7.3 and Attachment 3.

Comment:

NOTE: The curve numbers provided in this JPM are Evaluator Note: numbers from the 2014 NRC Exam Frozen Procedures Curve Book folder.

OST-1036 Section 7.3.1 Performance Step: 2 Enter the absolute value for each parameter on Attachment 3.

Standard: Reviews Attachment 3 and determines value for each parameter.

Comment:

OST-1036 Attachment 3 Step 1 Performance Step: 3 Enters Reactor Power Level Standard: Refers to given conditions and enters 92%

Comment:

- Denotes Critical Steps 2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Page 4 of 15 Form ES-C-1 PERFORMANCE INFORMATION OST-1036 Attachment 3 Step 2 Performance Step: 4 Determine Rod Insertion Limit for power level Standard: Refers to Curve F-19-1 and determines TS limit for RIL to be 170 steps (165 - 175 steps, tolerance based on curve division readability)

Comment:

OST-1036 Attachment 3 Step 3 Performance Step: 5 Enters core Burn Up Standard: Refers to given conditions and enters 350 EFPD Comment:

OST-1036 Attachment 3 Step 4 Performance Step: 6 Enters RCS Boron Concentration Standard: Refers to initial conditions and enters 600 ppm Comment:

ATT 3, STEP 5 NOT PERFORMED SINCE VALUE IS Evaluator Note:

INCLUDED AS PART OF ATTACHMENT.

- Denotes Critical Steps 2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Page 5 of 15 Form ES-C-1 PERFORMANCE INFORMATION OST-1036 Attachment 3 Step 6 Performance Step: 7 Determines Power Defect for current power level Standard: Refers to Curve C-19-3 and determines power defect to be 2520 + 50 pcm (tolerance based on curve division readability)

Comment:

OST-1036 Attachment 3 Step 7 Performance Step: 8 Determines Rod Worth for RIL position determined above Standard: Refers to Curve A-19-11 and determines rod worth to be 425 + 50 pcm (tolerance based on rod position tolerance from performance step 4 curve division readability)

Comment:

OST-1036 Attachment 3 Step 8 Performance Step: 9 Enters worth of any additional immovable or untrippable rods Standard: Refers to given conditions and enters 1294 pcm Comment:

- Denotes Critical Steps 2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Page 6 of 15 Form ES-C-1 PERFORMANCE INFORMATION OST-1036 Attachment 3 Step 9 Performance Step: 10 Determines Total Shutdown Margin Standard: Determines Total Shutdown Margin to be 2872 + 75 pcm (tolerance based on total of all curves used and their division readability)

Comment:

OST-1036 Section 7.3.2 Performance Step: 11 Perform the calculation listed on Attachment 3 Item 9 for the required SDM boron concentration for the projected conditions.

Standard: Refers to Attachment 3 Item 9 to document SDM Comment:

OST-1036 Section 7.3.3 Performance Step: 12 Perform an independent verification of Attachment 3..

Standard: Contacts evaluator to perform Independent Verification per initial conditions Comment:

When independent verification of OST-1036, Attachment 3, Evaluator Cue: Manual SDM Calculation is requested.

END OF JPM STOP TIME:

- Denotes Critical Steps 2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Page 7 of 15 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes Critical Steps 2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Page 8 of 15 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes Critical Steps 2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Page 9 of 15 Form ES-C-1 PERFORMANCE INFORMATION KEY

- Denotes Critical Steps 2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Page 10 of 15 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CALCULATION KEY (SHADED AREA BELOW INDICATES DATA ALREADY PROVIDED)

Manual SDM Calculation (Modes 1 and 2)

1. Reactor power level. 92 %

2. Rod insertion limit for the above power level 170 steps on bank D (165-175)

3. Burn up (POWERTRAX/MCR Status Board). 350 EFPD

4. Present RCS Boron Concentration 600 ppm NOTE: Use absolute values of numbers obtained from curves.

5. Total worth of all control and shutdown banks, minus the worth of the most reactive rod for Fuel Cycle 19.

7111 pcm (a)

6. Cycle 19 Power defect for the power level recorded in Step 1.

(Refer to Curves C-X-1 to C-X-3).

Curve used C-19-3 2520 + 50 pcm (b)

NOTE: HFP curves are used for power levels of 10% or greater.

7. Inserted control rod worth at the rod insertion limit recorded in Step 2.

(Refer to Curves A-X-6 to A-X-11)

Curve used A-19-11 425 + 50 pcm (c)

8. Worth of any additional immovable or untrippable rods (for each stuck rod, use the most reactive single rod worth (1294 pcm).

1294 pcm (d)

9. Determine the Total Shutdown Margin using the following formula:

Total SDM C B = 7111 - 2520 + 50 - 425 + 50 - 1294 (e) (a) (b) (c) (d) 2872 + 100 pcm (e)

- Denotes Critical Steps 2014 NRC Admin Exam RO A1-2 Rev. FINAL

Appendix C Page 11 of 15 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 NRC Exam Admin JPM RO A1-2 Perform A Manual Shutdown Margin Calculation OST-1036 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2014 NRC Admin Exam JPM RO A1-2 Rev. FINAL

Appendix C Form ES-C-1 JPM CUE SHEET Name:

Date:

The plant has been operating at 92% power for 2 weeks.

OST-1005, Control Rod and Rod Position Indicator Exercise Quarterly Interval Modes 1 - 3, was just performed.

Initial Conditions: One rod in Control Bank B was determined to be immovable/stuck.

Core burnup is 350 EFPD

RCS boron concentration is 600 ppm

POWERTRAX is NOT available The CRS has entered Tech Spec 3.1.1.1 and has directed you to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, Manual SDM Calculation (Modes 1 and 2) for current plant Initiating Cue: conditions.

NOTE: For this JPM notify evaluator when independent verification is required to be performed.

2014 NRC Admin Exam JPM RO A1-2 Rev. FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2014 NRC Admin Exam JPM RO A1-2 Rev. FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 119015H301 Task

Title:

Perform RCS Average Temperature JPM No.: 2014 NRC Exam Data Sheet and Determine Inverse Admin JPM RO SRO A1-1 Count Rate Ratio (1/M)

K/A

Reference:

004 A4.03 RO 2.7 SRO 3.2 Alternate Path - NO Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss or perform, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The unit is in Mode 2, with a plant startup in progress per GP-004, REACTOR STARTUP (MODE 3 TO MODE 2). The OATC has just Initial Conditions:

completed the 3rd doubling.

The CRS has assigned you to complete Attachment 2, Inverse Count Initiating Cue: Rate Ratio (1/M) and RCS Average Temperature Data Sheet and Attachment 3, 1/M Data Plot to predict when reactor will become critical.

2014 NRC Admin Exam RO SRO A1-1 Rev. FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Determines the predicted criticality will occur below the 500 pcm ECC rod height of 36 steps on CBD.

Required Materials: Calculator General

References:

GP-004, Rev 58 Handouts: JPM Cue Sheets Pages 8 and 9, GP-004 Attachment 3 pg 32 Time Critical Task: No Validation Time: 15 minutes Critical Step Justification Critical to correctly calculate inverse count ratio in order to predict the Step 3 estimated critical rod position following the doubling of source range counts Critical to correctly plot the inverse count ratio and controlling rod Step 4 position in order to predict the estimated critical rod position following the doubling of source range counts Critical to correctly calculate inverse count ratio in order to predict the Step 5 estimated critical rod position following the doubling of source range counts Critical to correctly plot the inverse count ratio and controlling rod Step 6 position in order to predict the estimated critical rod position following the doubling of source range counts Critical to correctly calculate inverse count ratio in order to predict the Step 7 estimated critical rod position following the doubling of source range counts Critical to correctly plot the inverse count ratio and controlling rod Step 8 position in order to predict the estimated critical rod position following the doubling of source range counts 2014 NRC Admin Exam RO SRO A1-1 Rev. FINAL

Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION Start Time: __________.

Performance Step: 1 OBTAIN PROCEDURE (GP-002 Attachment 2 and 3 will be provided to allow candidates to write on)

Standard: Obtains GP-004 and refers to Attachment 2 and 3.

Comment:

Performance Step: 2 Complete Attachment 3 Startup Information Standard: Transfers the following information from Attachment 2 to Attachment 3:

Date

Startup Number

Rod Insertion Limit

500 pcm below ECC

500 pcm above ECC

Control Operator The above information has been provided to the candidate as part of the JPM Cue sheet for Attachment 2.

Evaluator Note: The transfer of this information from Attachment 2 to Attachment 3 may be performed at any time before the completion of the JPM Comment:

Performance Step: 3 Calculation of 1/M data point at 0515 Standard: Divides initial source range count rate by source range count reading for 0515

150 cps / 305 cps = 0.49 Comment:

- Denotes a Critical Step 2014 NRC Admin Exam RO SRO A1-1 Rev. FINAL

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Plot 1/M data point to determine predicted Criticality position at 0515 Standard: Manually plots 1/M data point on Attachment 3 using data from Attachment 2 and interpolates data to determine predicted critical position is 216 steps on Control Bank D.

(208 - 224 steps, tolerance based on curve division readability)

Comment:

Performance Step: 5 Calculation of 1/M data point at 0530 Standard: Divides initial source range count rate by source range count reading for 0530

150 cps / 625 cps = 0.24 Comment:

Performance Step: 6 Plot 1/M data point to determine predicted Criticality position at 0530 Standard: Manually plots 1/M data point on Attachment 3 using data from Attachment 2 and interpolates data to determine predicted critical position is 96 steps on Control Bank D.

(88 - 104 steps, tolerance based on curve division readability)

Comment:

- Denotes a Critical Step 2014 NRC Admin Exam RO SRO A1-1 Rev. FINAL

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 7 Calculation of 1/M data point at 0545 Standard: Divides initial source range count rate by source range count reading for 0545

150 cps / 1275 cps = 0.12 Comment:

Performance Step: 8 Plot 1/M data point to determine predicted Criticality position at 0545 Standard: Manually plots 1/M data point on Attachment 3 using data from Attachment 2 and interpolates data to determine predicted critical position is 24 steps on Control Bank D.

(16 - 32 steps, tolerance based on curve division readability)

Determines the predicted criticality position is below the 500 pcm ECC value of 36 steps on Control Bank D Comment:

Performance Step: 9 Documents Attachment 3 results of predicted rod height for criticality Standard: Documents the predicted rod height is 24 steps on Control Bank D Comment:

Candidate determines the predicted rod height is below the Evaluator Note: 500 pcm ECC.

END OF JPM Comment:

Stop Time: _________

- Denotes a Critical Step 2014 NRC Admin Exam RO SRO A1-1 Rev. FINAL

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION KEY 2014 NRC Admin Exam RO SRO A1-1 Rev. FINAL

Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 NRC JPM Common RO SRO A1-1 Perform RCS Average Temperature Data Sheet and Determine Inverse Count Rate Ratio (1/M)

GP-004 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2014 NRC Admin Exam RO SRO A1-1 Rev. FINAL

Appendix C Form ES-C-1 JPM CUE SHEET Name:

Date:

The unit is in Mode 2, with a plant startup in progress per GP-004, REACTOR STARTUP (MODE 3 TO MODE 2). The OATC has just Initial Conditions:

completed the 3rd doubling.

The CRS has assigned you to complete Attachment 2, Inverse Count Initiating Cue: Rate Ratio (1/M) and RCS Average Temperature Data Sheet and Attachment 3, 1/M Data Plot to predict when reactor will become critical.

Predicted Rod Height for Reactor Criticality 2014 NRC Admin Exam RO SRO A1-1 Rev. FINAL

Appendix C Form ES-C-1 JPM CUE SHEET 2014 NRC Admin Exam RO SRO A1-1 Rev. FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Shearon Harris Task No.: 119013H304 Task

Title:

Determine Clearance Requirements JPM No.: 2014 NRC Exam for a CSIP Admin JPM RO SRO A2 K/A

Reference:

G 2.2.13 RO 4.1 SRO 4.3 Alternate Path - NO Examinee: ________________________ NRC Examiner:

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss, or perform and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The plant is defueled. CSIP 1A-SA is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are Initial Conditions:

NOT required to be placed under clearance. There is NO known isolation boundary leakage.

You have been directed to determine the clearance requirements for CSIP 1A-SA using the SFDs, and Plant Procedures, as necessary. The AOM-Shift has approved using single valve isolation.

NOTE: LISTING OF CITS IS NOT REQUIRED FOR THIS JPM.

Initiating Cue:

IT IS NOT INTENDED THAT YOU ACTUALLY GENERATE A CLEARANCE. ONLY PROVIDE THE EVALUATOR WITH A LISTING OF THE REQUIRED COMPONENTS, POSITIONS AND THE INSTALLATION SEQUENCE.

2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Provide complete electrical and mechanical isolation of CSIP 1A-SA Required Materials: OPS-NGGC-1301, Equipment Clearance, pgs. 38 and 41, Rev. 32 OP-107, Chemical and Volume Control System, Rev. 107 OP-107.03, Rev. 19 SFD 2165 S-1304 and S-1305 Additional copies of page 12 of this JPM available General

References:

OPS-NGGC-1301, Equipment Clearance, Rev. 32 OP-107, Chemical and Volume Control System, Rev. 107 OP-107.03, Rev. 19 SFD 2165 S-1304 and S-1305 Handouts: JPM Cue Sheets SFD 2165 S-1304 and S-1305 Time Critical Task: No Validation Time: 25 minutes 2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Critical Step Justification Step 2 Critical to remove power from the pump for personnel protection.

Step 3 Critical to isolate suction source to allow pump to be depressurized.

Step 4 Critical to isolate discharge path to allow pump to be depressurized.

Step 5 Critical to isolate miniflow path to allow pump to be depressurized.

Step 6 Critical to isolate miniflow path to allow pump to be depressurized.

Step 7 Critical to open vent path to allow pump to depressurize.

Step 8 Critical to open drain path to allow pump to depressurize.

NOTE: Provide applicants a copy of SFD 2165 S-1304 and 1305 Laptops are to be used for this JPM.

Prior to starting this JPM: Ensure each candidate is familiar with the contents of the frozen procedures and is able to access the files containing OP-107, Chemical and Volume Control System, OP-107.01, CVCS Boration, Dilution, and Chemistry Control, OP-107.02, CVCS Demineralizer Operations, and OP-107.03, CVCS Fill, Vent, Maintenance Activities and OPS-NGGC-1301, Equipment Clearance.

2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 4 of 14 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Performance Step: 1 Obtain a copy of the appropriate drawings and procedures (OPS-NGGC-1301, OP-107, SFD 2165 S-1304 and 1305)

Standard: Operator obtains a copy of OP-107 to determine electrical requirements. SFD 2165 S-1304 and S-1305 to determine mechanical requirements. OPS-NGGC-1301 to determine proper installation sequence for clearance.

Comment:

SEE JPM ATTACHMENT FOR A COMPLETE LISTING OF EACH COMPONENT AND REQUIRED POSITION. JPM Evaluator Note:

STEPS ARE NOT REQUIRED TO BE PERFORMED IN THE LISTED SEQUENCE.

Performance Step: 2 Determine the electrical supply breaker for CSIP 1B-SB Standard: Refers to OP-107 (or any other valid source) and determines the electrical supply breaker for CSIP 1A-SA to be 6.9 KV Emergency Bus 1A-SA, Cubicle 5 (BREAKER RACKED OUT)

Also determines pump has MCB and ACP switch and includes a CIT on CSIP A switch for each location Comment:

Evaluator Note: CRITICAL TO REMOVE POWER FROM PUMP.

- Denotes Critical Steps 2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 5 of 14 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 3 Determine the discharge isolation for CSIP 1A-SA Standard: Refers to S-1305 and determines the valve to isolate CSIP 1A-SA discharge is 1CS-183, A CSIP Discharge Isol Vlv (CLOSE)

Comment:

Performance Step: 4 Determine the suction valve for CSIP 1A-SA.

Standard: Refers to S-1305 and determines the suction valve for CSIP 1A-SA to be 1CS-173, A CSIP Suction Isol Vlv (CLOSE)

Comment:

Performance Step: 5 Determine the normal miniflow isolation for CSIP 1A-SA.

Standard: Refers to S-1305 and OP-107 and determines the valve to isolate normal miniflow path for CSIP 1A-SA is 1CS-182 SB, CHARGING/SI PUMP A-SA MINIFLOW ISOL, and power supply for valve is 1B35-SB (Breaker 7B)

(VALVE TO BE CLOSED WITH POWER REMOVED - LOCAL HANDWHEEL TO BE IN CLOSED)

Also determines valve has MCB switch and includes a CIT on 1CS-182 switch Comment:

CIT IS NOT REQUIRED TO BE INCLUDED FOR Evaluator Note:

SATISFACTORY COMPLETION OF THIS STEP.

- Denotes Critical Steps 2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 6 of 14 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Determine the alternate miniflow isolation for CSIP 1A-SA Standard: Refers to S-1304 and determines the valve to isolate alternate miniflow path for CSIP 1A-SA is 1CS-747, A CSIP Alt Mini Flow Man Isol (CLOSE)

Comment:

Performance Step: 7 Determine the vent path for CSIP 1A-SA Standard: Refers to S-1305 and determines the valve to vent CSIP 1A-SA is 1CS-174, A CSIP Suction Px Isol Vlv (OPEN WITH CAP REMOVED)

Comment:

EITHER STEP 7 OR STEP 8 IS CRITICAL. ONE OR THE OTHER MUST BE PERFORMED, BUT NOT BOTH.

Evaluator Note:

HOWEVER, IF BOTH ARE PERFORMED, THIS IS ALSO ACCEPTABLE.

- Denotes Critical Steps 2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 7 of 14 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 8 Determine the drain path for CSIP 1A-SA Standard: Refers to S-1305 and determines the valves to drain CSIP 1A-SA discharge piping to be 1CS-175, A CSIP Casing Leak Off Drain Vlv, and 1CS-176, A CSIP Casing Leak Off Drain Isol Vlv (BOTH OPEN)

Comment:

EITHER STEP 7 OR STEP 8 IS CRITICAL. ONE OR THE OTHER MUST BE PERFORMED, BUT NOT BOTH.

Evaluator Note:

HOWEVER, IF BOTH ARE PERFORMED, THIS IS ALSO ACCEPTABLE.

When applicant completes and returns clearance list.

Evaluator Cue:

END OF JPM Stop Time: _________

- Denotes Critical Steps 2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 8 of 14 Form ES-C-1 PERFORMANCE INFORMATION KEY JPM ATTACHMENT COMPONENT LISTING AND REQUIRED POSITIONS Critical sequences:

1) Remove power from the CSIP 1A-SA

2) Shut 1CS-183, A CSIP Discharge Isol Vlv.

2) Shut 1CS-182 SB, CHARGING/SI PUMP A-SA MINIFLOW ISOL

2) Remove power from 1CS-182 SB, CHARGING/SI PUMP A-SA MINIFLOW ISOL

3) Shut 1CS-173, A CSIP Suction Isol Vlv.

4) Open Vent and/or Drain to depressurize boundary 1CS-182 SB, CHARGING/SI PUMP A-SA MINIFLOW ISOL is on the discharge side of the CSIP and is normally shut from the MCB when the CIT is hung and then power is removed prior to shutting 1CS-183, Evaluator Note: A CSIP Discharge Isol Vlv. locally. It is acceptable for the candidate to identify power removed from 1CS-182 SB prior to tagging the either the Discharge or Miniflow valve shut locally provided the candidate assumed 1CS-182 SB is shut during the installation of the CIT.

1CS-182 and 1CS-747 have to be closed prior to opening vents and drains, otherwise there is no required sequence for branch paths.

COMPONENT POSITION

1) CSIP 1A-SA P.S. - 6.9 KV Emergency Bus 1A-SA, Cubicle 5. Racked Out

2) 1CS-182 SB, CHARGING/SI PUMP A-SA MINIFLOW ISOL Closed

3) 1CS-182 SB P.S. - 1B35-SB, Breaker 7B Off

4) 1CS-183, A CSIP Discharge Isol Vlv. Shut

5) 1CS-173, A CSIP Suction Isol Vlv. Shut

6) 1CS-747, A CSIP Alt Mini Flow Man Isol. Shut OR

1) CSIP 1A-SA P.S. - 6.9 KV Emergency Bus 1A-SA, Cubicle 5. Racked Out

2) 1CS-183, A CSIP Discharge Isol Vlv. Shut

3) 1CS-173, A CSIP Suction Isol Vlv. Shut

4) 1CS-182 SB, CHARGING/SI PUMP A-SA MINIFLOW ISOL Closed

5) 1CS-182 SB P.S. - 1B35-SB, Breaker 7B Off

6) 1CS-747, A CSIP Alt Mini Flow Man Isol. Shut OR

1) CSIP 1A-SA P.S. - 6.9 KV Emergency Bus 1A-AB, Cubicle 5. Racked Out

2) 1CS-183, A CSIP Discharge Isol Vlv. Shut

3) 1CS-173, A CSIP Suction Isol Vlv. Shut

4) 1CS-747, A CSIP Alt Mini Flow Man Isol. Shut

5) 1CS-182 SB, CHARGING/SI PUMP A-SA MINIFLOW ISOL Closed

6) 1CS-182 SB P.S. - 1B35-SB, Breaker 7B Off 2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 9 of 14 Form ES-C-1 PERFORMANCE INFORMATION

7) Accept - EITHER one vent path OR the drain path or BOTH a vent path and drain path.

NOTE: Any of the following vent valves will support a vent path for the pump. One or more of these vent paths are required to be identified VENT PATHS 1CS-174, A CSIP Suction Px Isol Vlv Uncapped/Open

- OR -

1CS-798, ECCS Outter Vent Vlv CSIP A Uncapped/Open Disch Upstream of 1CS-178

- AND -

1CS-797, ECCS Inner Vent Vlv CSIP A Disch Open Upstream of 1CS-178

- OR -

1CS-796, ECCS Outter Vent Vlv CSIP A Suct Uncapped/Open Downstream of 1CS-173

- AND -

1CS-795, ECCS Inner Vent Vlv CSIP A Suct Open Downstream of 1CS-173 DRAIN PATH 1CS-175, A CSIP Casing Leak Off Drain Vlv Open

- AND -

1CS-176, A CSIP Casing Leak Off Drain Isol Vlv Open NOTE - CITs are NOT required for satisfactory completion of JPM.

2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 10 of 14 Form ES-C-1 PERFORMANCE INFORMATION KEY 2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 11 of 14 Form ES-C-1 PERFORMANCE INFORMATION KEY 2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 12 of 14 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 NRC Exam Admin JPM RO SRO A2 Determine Clearance Requirements for a CSIP OPS-NGGC-1301 OP-107 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 13 of 14 Form ES-C-1 JPM CUE SHEET The plant is defueled. CSIP 1A-SA is required to be placed under a clearance for seal replacement. Cooling water and lube oil Initial Conditions:

systems are NOT required to be placed under clearance. There is NO known isolation boundary leakage.

You have been directed to determine the clearance requirements for CSIP 1A-SA using the SFDs, and Plant Procedures, as necessary. The AOM-Shift has approved using single valve isolation.

Initiating Cue: NOTE: LISTING OF CITS IS NOT REQUIRED FOR THIS JPM.

IT IS NOT INTENDED THAT YOU ACTUALLY GENERATE A CLEARANCE. ONLY PROVIDE THE EVALUATOR WITH A LISTING OF THE REQUIRED COMPONENTS, POSITIONS AND THE INSTALLATION SEQUENCE.

NOTE: Provide a list of components in the proper installation sequence to the examiner using the following page(s).

Additional pages are available upon request.

2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Page 14 of 14 Form ES-C-1 JPM CUE SHEET CSIP 1A-SA CLEARANCE COMPONENT LISTING AND REQUIRED POSITIONS SEQUENCE COMPONENT POSITION 2014 NRC Exam Admin JPM RO SRO A2 Rev FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 34502H601 Task

Title:

Determine TEDE While Working in a JPM No.: 2014 NRC Exam High Airborne Area Admin JPM RO SRO A3 K/A

Reference:

G2.3.4 RO 3.2 SRO 3.7 Alternate Path - NO Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss or perform, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The plant is shut down for refueling

The RAB AO is being directed to enter an area to inspect several malfunctioning valves.

While doing contract work the operator received a combined 1,325 mRem TEDE this calendar year.

In the same calendar year, the operator has received another 495 mRem TEDE at the Harris plant.

Initial Conditions:

The estimated dose rate in the work area is 465 mRem/hr.

An airborne contamination concern exists.

It is estimated that it will take 25 minutes to complete the inspection if the operator uses a respirator.

If the operator does NOT wear a respirator, the inspection will take 12 minutes, but Radiation Protection projects that the internal exposure will be 10 DAC-hrs.

1.a. Calculate the resultant total effective dose equivalent for with a respirator for this job and the accumulated dose for the year.

1.b. Calculate the resultant total effective dose equivalent for without a respirator for this job and the accumulated dose for the year.

Initiating Cue:

2. Using the lowest dose determined in number 1, determine if the individual can perform the task without exceeding Duke Energys Annual Administrative Dose Limit.

Show your calculations on the next page 2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Determination made that NOT wearing a respirator will result in a lower TEDE and that the individual can perform the task without exceeding Duke Energys Annual Administrative Dose Limit.

Required Materials: Laptop with General Reference PD-RP-ALL-0001, Radiation Worker Responsibilities, Rev 3 or hard copy General

References:

PD-RP-ALL-0001, Radiation Worker Responsibilities, Rev 3 Handouts: JPM Cue Sheet Pages 9 and 10 Time Critical Task: No Validation Time: 15 minutes Critical Step Justification Determining external exposure while wearing a respirator is required to Step 2 complete the calculations and answer.

Determining internal exposure while NOT wearing a respirator is Step 4 required to complete the calculations and answer.

Determining external exposure while NOT wearing a respirator is Step 5 required to complete the calculations and answer.

Determining individuals total exposure for the year if the work is allowed Step 8 without a respirator is required to complete the calculations and answer.

Determining individuals total exposure for the year if the work is allowed Step 9 with a respirator is required to complete the calculations and answer.

Determining if the individual can perform the work without exceeding Step 10 Duke Energys Annual Administrative Dose Limit of 2000 mRem is required to complete the calculations and answer.

2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Page 3 of 10 Form ES-C-1 PERFORMANCE INFORMATION Start Time: __________.

NOTE: Steps in this JPM may be performed in any order.

Performance Step: 1 Determines internal exposure while wearing a respirator Standard: Determines internal exposure to be ZERO while wearing a respirator Comment:

Performance Step: 2 Determines external exposure while wearing a respirator Standard: Determines external exposure to be 193.8 mRem TEDE while wearing a respirator (465 mRem / hr x 25 min = 193.8 mRem)

(NOTE: Could round to 194)

Comment:

Performance Step: 3 Determines TOTAL exposure while wearing a respirator Standard: Determines total exposure to be 193.8 mRem while wearing a respirator (0 mRem internal + 193.8 mRem external = 193.8 mRem total)

(NOTE: Could round to 194)

Comment:

- Denotes a Critical Step 2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Determines internal exposure while NOT wearing a respirator Standard: Determines internal exposure to be 25 mRem while not wearing a respirator (2.5 mRem / hr x 10 DAC-hr = 25 mRem)

(NO tolerance)

Comment:

Performance Step: 5 Determines external exposure while NOT wearing a respirator Standard: Determines external exposure to be 93.0 mRem TEDE while not wearing a respirator (465 mRem / hr x 12 min = 93 mRem)

(NO tolerance)

Comment:

Performance Step: 6 Determines TOTAL exposure while NOT wearing a respirator Standard: Determines total exposure to be 118 mRem while not wearing a respirator (25 mRem internal + 93 mRem external = 118 mRem total)

(NO tolerance)

Comment:

Performance Step: 7 Determines individuals total exposure for the year Standard: Determines individuals total exposure for the year to be 1820 mRem (1325 mRem + 495 mRem = 1820 mRem)

Comment:

- Denotes a Critical Step 2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 8 Determines individuals total exposure for the year if the work is allowed without a respirator Standard: Determines individuals total exposure for the year if the work is performed without a respirator to be 1938 mRem (1820 mRem + 118 mRem = 1938 mRem)

(NO tolerance)

Comment:

Performance Step: 9 Determines individuals total exposure for the year if the work is allowed with a respirator Standard: Determines individuals total exposure for the year if the work is performed with a respirator to be 2013.8 mRem (1820 mRem + 193.8 mRem = 2013.8 mRem)

Note: If calculated wearing a respirator the total exposure for the year will be 2013.8 mRem and work cannot be performed without an extension. The directions were to use the lowest dose and this represents UNSAT performance.

(NOTE: Could have rounded 193.8 to 194 and answer would be 2014 mRem)

Comment:

Performance Step: 10 Determines if the individual can perform the work without exceeding Duke Energys Annual Administrative Dose Limit of 2000 mRem without an administrative dose limit extension Standard: Determines the individual CAN perform the work without wearing a respirator will NOT exceed Duke Energys Annual Administrative Dose Limit of 2000 mRem (1820 mRem + 118mRem = 1938 mRem)

Comment:

When all calculations have been completed and the Evaluator Cue: determination that work can proceed, this JPM is complete.

Stop Time: _________

- Denotes a Critical Step 2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION KEY 1.a Calculation for resultant total effective dose equivalent with a respirator.

Determines internal exposure to be ZERO while wearing a respirator Determines external exposure to be 193.8 mRem TEDE while wearing a respirator (465 mRem / hr x 25 min = 193.8 mRem)

(NOTE: Could round to 194)

Determines TOTAL exposure while wearing a respirator (0 mRem internal + 193.8 mRem external = 193.8 mRem total)

(NOTE: Could round to 194)

Determines individuals total exposure for the year to be 1820 mRem (1325 mRem + 495 mRem = 1820 mRem)

Determines individuals total exposure for the year if the work is allowed to be 2013.8 mRem (1820 mRem + 193.8 = 2013.8 mRem)

(NOTE: Could round to 2014 mRem)

Note: If calculated wearing a respirator the total exposure for the year will be 2013.8 mRem and work CANNOT be performed without an extension. The directions were to use the lowest dose and this represents UNSAT performance.

1.b Calculation for resultant total effective dose equivalent without a respirator.

Determines internal exposure to be 25 mRem while not wearing a respirator (2.5 mRem / hr x 10 DAC-hr = 25 mRem)

(NO tolerance)

Determines external exposure to be 118 mRem TEDE while not wearing a respirator (495 mRem / hr x 12 min = 93 mRem)

Determines total exposure to be 118 mRem while not wearing a respirator (25 mRem internal + 93 mRem external = 118 mRem total)

Determines individuals total exposure for the year if the work is allowed to be 1938 mRem (1820 mRem + 118 = 1938 mRem)

The individual CAN perform the task without exceeding Duke Energys Annual Admin Dose Limit if the task is performed WITHOUT a respirator.

- Denotes a Critical Step 2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION KEY

2. Using the lowest dose determined from the above calculations (1a or 1b):

CAN the individual perform the task without exceeding Duke Energys Annual Administrative Dose Limit?

YES (without a respirator total dose would be 1,938 mRem which is < 2,000 mRem)

- Denotes a Critical Step 2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Page 8 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 NRC Exam JPM RO SRO A3 Determine TEDE While Working in a High Airborne Area PD-RP-ALL-0001 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Form ES-C-1 JPM CUE SHEET

The plant is shut down for refueling

The RAB AO is being directed to enter an area to inspect several malfunctioning valves.

While doing contract work the operator received a combined 1,325 mRem TEDE this calendar year.

In the same calendar year, the operator has received another 495 mRem TEDE at the Harris plant.

Initial Conditions:

The estimated dose rate in the work area is 465 mRem/hr.

An airborne contamination concern exists.

It is estimated that it will take 25 minutes to complete the inspection if the operator uses a respirator.

If the operator does NOT wear a respirator, the inspection will take 12 minutes, but Radiation Protection projects that the internal exposure will be 10 DAC-hrs.

1.a. Calculate the resultant total effective dose equivalent for with a respirator for this job and the accumulated dose for the year.

1.b. Calculate the resultant total effective dose equivalent for without a respirator for this job and the accumulated dose for the year.

Initiating Cue:

2. Using the lowest dose determined in number 1, determine if the individual can perform the task without exceeding Duke Energys Annual Administrative Dose Limit.

Show your calculations on the next page 2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Form ES-C-1 JPM CUE SHEET Name:

Date:

1.a Calculation for resultant total effective dose equivalent with a respirator.

1.b Calculation for resultant total effective dose equivalent without a respirator.

2. Using the lowest dose determined from the above calculations (1a or 1b):

CAN the individual perform the task without exceeding Duke Energys Annual Administrative Dose Limit?

2014 NRC Admin Exam RO SRO A3 Rev. FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Harris Nuclear Plant Task No.: 344047H402 Task

Title:

Complete GP-002, Attachment 5 - JPM No.:

2014 NRC Exam Minimum Equipment List (MEL) for Admin JPM SRO A1-2 Entry into Mode 4 K/A

Reference:

G2.1.43 4.1 / 4.3 Alternate Path: NO Examinee: ________________________ NRC Examiner: _________________

Facility Evaluator: ________________________ Date: ________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss or perform, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The unit is in Mode 5, making preparation to enter Mode 4 in accordance with GP-002, Normal Plant Heatup From Cold Solid To Hot Initial Conditions: Subcritical Mode 5 To Mode 3.

The current conditions for the plant are as listed on the data sheet.

The previous shift has completed a partial review of GP-002, Attachment 5 - MEL for Entry into Mode 4. The CRS has assigned you Initiating Cue: to review the remaining items to be completed on GP-002, Attachment 5 for any discrepancies AND identify any mode limiting items required by Technical Specifications.

2014 NRC Admin Exam SRO A1-2 Rev. FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: All conditions not meeting Mode 4 requirement identified.

Required Materials: Technical Specifications General

References:

GP-002, rev 61 Handouts: JPM Cue Sheets Pages 7, Plant Conditions sheet matching the JPM content.

Partially completed GP-002, Attachment 5 matching the Plant Conditions handout.

Time Critical Task: No Validation Time: 25 minutes Critical Step Justification Critical to comply with Technical Specification requirements to ensure Step 2 proper safety system alignment is configured as designed per the accident analysis.

Critical to comply with Technical Specification requirements to ensure Step 3 proper safety system alignment is configured as designed per the accident analysis.

Critical to comply with Technical Specification requirements to ensure Step 4 proper safety system alignment is configured as designed per the accident analysis.

2014 NRC Admin Exam SRO A1-2 Rev. FINAL

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION Start Time: __________.

Performance Step: 1 Obtain procedure and determine existing plant conditions.

Standard: Reviews Attachment 5 and Plant Conditions.

Provide handout (Plant Conditions Sheet and partially Evaluator Cue:

completed GP-002, Attachment 5).

All conditions except the following meet the MEL Evaluator Note:

requirements.

Comment:

Performance Step: 2 Compare Plant Conditions to Attachment 5 requirements.

Standard: Boric Acid Tank and Associated Temperatures:

Identify that Boric Acid Tank needs to be filled to 74%.

Comment:

Performance Step: 3 Compare Plant Conditions to Attachment 5 requirements.

Standard: Reactor Coolant Loops/RHR Loops:

Identify the need to either restore RHR Loop B or increase at least one S/G NR level to >30%.

Comment:

- Denotes a Critical Step 2014 NRC Admin Exam SRO A1-2 Rev. 4

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Compare Plant Conditions to Attachment 5 requirements.

Standard: Safety Related Electrical Buses:

Identify need to restore S1 Inverter and supply 1DP-1A-SI through the inverter, connected to DC Bus DP-1A-SA.

Comment:

Performance Step: 5 Provide Attachment 5 to the CRS.

Standard: Provides Attachment 5 to the CRS and may make a verbal report.

Evaluator Cue: Acknowledge any verbal communication.

Comment:

After Attachment 5 and/or the optional report has been Evaluator Cue:

provided to the CRS: Evaluation on this JPM is complete.

STOP TIME: __________

- Denotes a Critical Step 2014 NRC Admin Exam SRO A1-2 Rev. 4

Appendix C Page 5 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2014 NRC Exam Admin JPM SRO A1-2 Complete GP-002, Attachment 5 - Minimum Equipment List (MEL) for Entry into Mode 4 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature: Date:

2014 NRC Admin Exam SRO A1-2 Rev. FINAL

Appendix C Page 6 of 7 Form ES-C-1 JPM CUE SHEET The unit is in Mode 5, making preparation to enter Mode 4 in accordance with GP-002, Normal Plant Heatup From Cold Solid To Hot Initial Conditions: Subcritical Mode 5 To Mode 3.

The current conditions for the plant are as listed on the data sheet.

The previous shift has completed a partial review of GP-002, Attachment 5 - MEL for Entry into Mode 4. The CRS has assigned you Initiating Cue: to review the remaining items to be completed on GP-002, Attachment 5 for any discrepancies AND identify any mode limiting items required by Technical Specifications.

2014 NRC Admin Exam SRO A1-2 Rev. FINAL

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET 2014 NRC JPM SRO A1-2 PLANT CONDITIONS

The Reactor Trip Breakers are OPEN.

DRPI indicates all rods inserted.

All ventilation systems are in normal alignment with nothing tagged.

RCS Temperature is 195 F with a bubble in the PRZ.

LTOP is in service.

All PRZ Code Safety Valves are operable.

Chemistry has reported RCS Specific Activity, O, Cl, and Fl are within TS limits.

RHR Train A is providing cooling.

RHR Pump B is isolated and tagged due to mechanical seal leakage.

All RCPs are stopped.

CSIP B was stopped due to an oil leak 75 minutes ago and was declared inoperable, cleared and tagged 20 minutes later.

Operators removed the tags and started CSIP A 30 minutes ago.

Operable indicators indicate the following levels:

BAT - 20%

RWST - 93%

The BAT is at 93 F and 7450 ppm Boron.

Both BAT Pumps are operable.

The RWST is at 73 F and 2525 ppm.

Both Emergency Diesel Generators are operable.

Instrument Bus SI is powered from 1DP-S1, Alternate Supply from PP-1A211-SA, while a breaker is replaced in the inverter.

Two physically independent off-site power circuits are available.

All other AC buses are in normal alignment.

All DC buses are energized.

Operable indicators indicate SG NR Levels as:

SG A - 28%

SG B - 26%

SG C - 26%

SG WR Level indicators are inoperable.

All MSIVs and SG PORVs are closed.

CREVS and Train A and B are operable.

FHB Emergency Exhaust Train A and Train B are operable.

Engineering reported that all snubbers required for Mode 4 and 5 are operable.

2014 NRC Admin Exam SRO A1-2 Rev. FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet

`Facility: Harris Nuclear Plant Task No.: 345001H602 Task

Title:

Classify an EAL JPM No.: 2014 NRC Exam Admin JPM SRO A4 K/A

Reference:

G2.4.41 RO 2.9 SRO 4.6 Alternate Path - NO Examinee: _______________________ NRC Examiner: _________________

Facility Evaluator: _______________________ Date: _________________

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate, discuss or perform, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

This is a TIME CRITICAL JPM.

Given the following plant conditions:

The unit is operating at 100% power

The 'A' CNMT Spray Pump is under clearance

AOP-025, Loss of One Emergency AC Bus (6.9KV) Or One Emergency DC Bus (125V) is in progress:

Breaker 125 is tripped open

The 'B' EDG is failed to start The following occurs:

15 minutes ago, the crew entered AOP-016, Excessive Primary Initial Conditions: Plant Leakage and based on plant conditions, the Reactor was tripped and Safety Injection was actuated

The crew implemented EOP-E-0, Reactor Trip or Safety Injection

RCPs were secured based on RCP Trip foldout criteria

12 minutes ago the 'A' CSIP tripped on overcurrent

10 minutes ago the following conditions existed

CNMT Pressure was 12 psig

Core Exit TCs were 628°F

RCS Pressure was 1200 psig

RVLIS Full Range Level was 33%

Wind speed was 10 mph and wind direction was 185 degrees 2014 NRC Exam Admin JPM SRO A4 Rev. FINAL

Appendix C Job Performance Measure Form ES-C-1 Worksheet The time is now 0554 Evaluate the EAL Matrix and determine the highest classification Initiating Cue: required for these plant conditions. NOTE: Do not use SEC judgment.

NOTE: Write out EAL classification in blank provided then raise your hand and return your page to the Evaluator.

Task Standard: Classify the highest EAL as an Site Area Emergency FS1.1.

Required Materials: None General

References:

PEP-110 EAL Matrix PEP-110 EP-EAL (allowed reference)

Handouts:

Attached Initial Conditions

PEP-110

PEP-110 EAL Matrix

EP-EAL Time Critical Task: YES - 15 minutes for classification.

Validation Time: 15 minutes for classification CRITICAL STEP JUSTIFICATION Classification of the event is critical for determining State and County Step 2 notifications, public information notices, site information notices, and event reportability to the Nuclear Regulatory Commission.

2014 NRC Exam Admin JPM SRO A4 Rev. FINAL

Appendix C Page 3 of 13 Form ES-C-1 PERFORMANCE INFORMATION Start Time for this portion of JPM begins when the Evaluator Cue:

individual has been briefed.

START TIME:

Performance Step: 1 OBTAINS EP-EAL and EAL Matrix.

Standard : Obtains EP-EAL and EAL Matrix Comments:

Performance Step: 2 Identify EAL Classification for events in progress.

Standard : The correct EAL is: Site Area Emergency FS1.1 Loss or potential loss of any two barriers (Table F-1)):

Fuel barrier is determined to be a POTENTIAL LOSS based on CSFST Core Cooling ORANGE

RCS barrier is determined to be LOSS based on RCS leak rate > ECCS capability due to the loss of subcooling

CNMT barrier is determined to be POTENTIAL LOSS based CNMT Pressure > 10 psig with less than one full train of depressurization equipment. Neither CNMT Pump is available.

Comments:

Evaluator Cue: Event classification sheet provided to evaluator.

STOP TIME:

After the candidate returns this JPM classification record the Examiners Cue: stop time and then announce.

END of JPM.