ML16089A386

301 Section 6

ML16089A386
Person / Time
Site:	Surry
Issue date:	03/22/2016
From:	NRC/RGN-II
To:	Virginia Electric & Power Co (VEPCO)
References
Download: ML16089A386 (91)

Text

Surry 2014-301 Quadrant Power Tilt Calculation Page 1 of 9 U.S. Nuclear Regulatory Commission Surry Power Station SR14301 Administrative Job Performance Measure G2.1.7 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Perform a Quadrant Power Tilt Calculation.

K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Applicability Estimated Time Actual Time RO/SRO(D)/SRO(U) 15 Minutes Conditions Task is to be PERFORMED in the classroom.

Standards Correctly calculates Quadrant Power Tilt for given core conditions on the Calculation of Excore Quadrant Power Tilt Ratios, Attachment 6 of 0-AP-1.00, Rod Control Malfunction.

Initiating Cues A dropped rod has occurred on Unit 1.

A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00. Rod Control System Malfunction.

When you have determined the Quadrant Power Tilt, inform the examiner.

Terminating Cues Applicant has completed the QPTR Calculation.

Tools and Equipment Calculator NIS Setpoints and Power Range Currents Data Sheet Safety Considerations None

Surry 2014-301 Quadrant Power Tilt Calculation Page 2 of 9 Initial Conditions:

Unit 1 operating at 100% power.

o Control Rod D-10, Control Bank B, Group 1 dropped and is currently indicating 0 steps.

Initiating Cues Control Rod D-10, Control Bank B, has dropped on Unit 1.

A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00, Rod Control System Malfunction, Step 15.

The Shift Manager directs you to perform the Quadrant Power Tilt Calculation in accordance with Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios.

You are to perform these calculations to 4 significant digits.

You are provided a copy of the Power Range Currents from the NIS Data Book providing Normalized Values.

When you have determined the Quadrant Power Tilt, inform the examiner.

Notes Actual detector currents taken from the Power Range NIs:

N-41 Upper Detector Current 120.5 N-41 Lower Detector Current 124.2 N-42 Upper Detector Current 96.5 N-42 Lower Detector Current 94.23 N-43 Upper Detector Current 114.7 N-43 Lower Detector Current 115.5 N-44 Upper Detector Current 119.1 N-44 Lower Detector Current 121.8

Surry 2014-301 Quadrant Power Tilt Calculation Page 3 of 9 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

At the completion of the JPM all SRO Candidates will have a Follow-Up question.

START TIME: ____________

STEP 1:

Acknowledges NOTE prior to Step 1 of Att. 6.

Calculations for QPTR should be carried out to four places to the right of the decimal place to provide accuracy and consistency of results.

_______ SAT

_______ UNSAT STEP 2:

[Step 1, Att. 6]

a) Record Reactor Power, Date, and Time in appropriate blocks.

b) Initials Step 1.

STANDARD:

Records 100% for Reactor Power block, Current Date in Date block, Time in Time block.

EVALUATORS NOTE:

If Asked: Current Reactor Power is 100%.

If Asked: Use todays date.

If Asked: Use current time.

COMMENTS:

_______ SAT

_______ UNSAT STEP 3:

[Step 2, Att. 6]

a) Transcribes information from data sheets onto 0-AP-1.00, Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios, Step 2 Table.

STANDARD:

Places PR NI currents and Normalized Currents in appropriate location on Calculation of Excore Quadrant Power Tilt Ratios.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Quadrant Power Tilt Calculation Page 4 of 9 STEP 4:

[STEP 3, Att. 6]

a) Performs calculations to obtain normalized values for Upper Detectors.

STANDARD:

a) Divides Upper Detector current by Normalized currents for each detector.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT STEP 5:

[STEP 3, Att. 6]

a) Performs calculations to obtain Sum of normalized values for Upper Detectors.

STANDARD:

a) Adds Upper Detector Normalized currents for all Upper detectors EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.

COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

[STEP 3, Att. 6]

a) Performs calculations to obtain normalized values for Lower Detectors.

STANDARD:

a) Divides Lower Detector current by Normalized currents for each detector.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Quadrant Power Tilt Calculation Page 5 of 9 STEP 7:

[Step 3, Att. 6]

a) Performs calculations to obtain Sum of normalized values for Lower Detectors.

STANDARD:

a) Adds Lower Detector Normalized currents for all Lower Detectors.

b) Initials Step 3 of Attachment 6.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT STEP 8:

[Step 4, Att. 6]

a) Records the Number of Detectors in use.

b) Initials Step 4.

STANDARD:

a) Records the Number of Detectors in Step 4; b) Initials Step 4.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

If Asked: All 4 Detectors are used.

COMMENTS:

_______ SAT

_______ UNSAT STEP 9:

[Step 5, Att. 6]

a) Calculates the average upper and lower detector current values.

STANDARD:

a) Transcribes Upper and Lower detector Sum of Normalized Values from Step 3 of Attachment 6.

b) Divides each Sum by the number of Detectors in use.

c) Initials Step 5.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Quadrant Power Tilt Calculation Page 6 of 9 STEP 10: [Step 6, Att. 6]

a) From Step 3, Record the following values.

STANDARD:

a) Records the Maximum Normalized Upper Detector Current from Step 3 (N41 value of 1.0143.)

b) Records the Maximum Normalized Lower Detector Current From Step 3 (N41 value of 1.0393.)

c) Initials Step 6 of Attachment 6.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT STEP 11: [Step 7, Att. 6]

a) Calculates the maximum upper and lower Excore Quadrant Power Tilt Ratios.

STANDARD:

a) Divides Maximum Upper channel current by the Average Upper Detector currents to determine the Upper Excore Quadrant Power Tilt Ratio.

b) Divides Maximum Lower channel current by the Average Lower Detector current to determine the Lower Excore Quadrant Power Tilt Ratio.

c) Initials Step 7 of Attachment 6.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT STEP 12: [Step 8, Att. 6]

a) Calculates Tilt %.

STANDARD:

a) Calculates Tilt % for Upper channels.

b) Caculates % Tilt for Lower channels.

c) Initials Step 8 of Attachment 6.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Quadrant Power Tilt Calculation Page 7 of 9 STEP 13: Determines final Quadrant Power Tilt Value.

STANDARD:

a) Determines final Quadrant Power Tilt Value from above calculations to be 1.0898 or 8.98% Tilt based on the Lower Channels. (Range 8.6% - 9%; 8.6% based on rounding of NI current values; 9% based on rounding 8.98% to 9%)

b) Notifies Examiner, Task Complete.

EVALUATOR NOTES:

COMMENTS:

_______ SAT

_______ UNSAT STOP TIME:

EVALUATOR NOTE: Proceed to Follow-up question for SRO Candidates.

Surry 2014-301 Quadrant Power Tilt Calculation Page 8 of 9

Surry 2014-301 Quadrant Power Tilt Calculation Page 9 of 9

Surry 2014-301 Quadrant Power Tilt Calculation Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the classroom.

Perform a Quadrant Power Tilt calculation.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions:

Unit 1 operating at 100% power.

o Control Rod D-10, Control Bank B, Group 1 dropped and is currently indicating 0 steps.

Initiating Cues Control Rod D-10, Control Bank B, has dropped on Unit 1.

A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00, Rod Control System Malfunction, Step 15.

The Shift Manager directs you to perform a Quadrant Power Tilt Calculation in accordance with Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios.

You are provided a copy of the Power Range Currents from the NIS Data Book providing Normalized Values.

When you have determined the Quadrant Power Tilt, inform the examiner.

Actual detector currents taken from the Power Range NIs:

N-41 Upper Detector Current 120.5 N-41 Lower Detector Current 124.2 N-42 Upper Detector Current 96.5 N-42 Lower Detector Current 94.23 N-43 Upper Detector Current 114.7 N-43 Lower Detector Current 115.5 N-44 Upper Detector Current 119.1 N-44 Lower Detector Current 121.8

Surry 2014-301 Quadrant Power Tilt Calculation SRO ONLY ANSWER KEY NOT FOR TRAINEE QPTR FOLLOW-UP Question With the calculated Quadrant Power Tilt, what are the Tech Spec actions (if any)?

ANSWER: TS 3.12.B.6 requires:

3.12.B.6.a Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either hot channel factors shall be determined and power level adjusted to meet the requirement OR 3.12.B.6.b Power level to be reduced from Rated Power 2% for each percent of Quadrant Power Tilt. Therefore for a QPTR of 9% power must be reduced 18%. The high neutron flux trip setpoint shall also be reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Surry 2014-301 Quadrant Power Tilt Calculation SRO ONLY Candidate QPTR FOLLOW-UP Question With the calculated Quadrant Power Tilt, what are the Tech Spec actions (if any)?

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

Unit 1 operating at 100% power.

o Control Rod D-10, Control Bank B, Group 1 dropped and is currently indicating 0 steps.

Initiating Cues Control Rod D-10, Control Bank B, has dropped on Unit 1.

A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00, Rod Control System Malfunction, Step 15.

The Shift Manager directs you to perform a Quadrant Power Tilt Calculation in accordance with Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios.

You are provided a copy of the Power Range Currents from the NIS Data Book providing Normalized Values.

When you have determined the Quadrant Power Tilt, inform the examiner.

Actual detector currents taken from the Power Range NIs:

N-41 Upper Detector Current 120.5 N-41 Lower Detector Current 124.2 N-42 Upper Detector Current 96.5 N-42 Lower Detector Current 94.23 N-43 Upper Detector Current 114.7 N-43 Lower Detector Current 115.5 N-44 Upper Detector Current 119.1 N-44 Lower Detector Current 121.8

Surry Unit 1 NI Calibration Data Power Range Currents N41 N42 N43 N44 DELTA FLUX @

100%

I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps 0

118.8 119.5 118.5 119.3 119.1 119.5 119.1 119.5 DELTA FLUX @

120%

I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps 0

142.5 143.4 142.2 143.1 142.9 143.5 142.9 143.4 8

148.6 137.2 148.3 137.0 149.1 137.3 149.1 137.2

- 24 124.2 161.8 123.9 161.5 124.5 161.9 124.6 161.9 Data based on flux map number S1C26M15A Computer and Recorder Constants Recorder = K0411 = K0412 = K0413 = K0414 = 18.647 Performed / Verified By: __________/ __________ Date: _______

LaFrance Davis 7/21/14

Surry 2014-301 Auth Fuel Move U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure G2.1.40 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Authorize Fuel Movement K/A: G2.1.40 Knowledge of refueling administrative procedures (2.8/3.9)

Applicability Estimated Time Actual Time SRO(I)/SRO(U) 20 Minutes Conditions Task is to be PERFORMED in the simulator.

Standards Correctly identify all plant conditions that do not support fuel movement in accordance with 1-OSP-ZZ-004 attachment 8, given a specific set of plant conditions.

Terminating Cues 1-OSP-ZZ-004, attachment 8 assessment complete.

Procedures 1-OSP-ZZ-004, Unit 1 Safety Systems Status List For Cold Shutdown/Refueling Conditions, Revision 47.

Tools and Equipment Safety Considerations None None

Surry 2014-301 Auth Fuel Move Initiating Cues It is a Monday DAYSHIFT.

Unit One is in refueling shutdown with the head and upper internals removed. A request from the refueling supervisor has been made to authorize fuel movement (core offload) in accordance with 1-OSP-ZZ-004 attachment 8.

Current conditions are as follows (items not observable from the control room):

o Refueling containment integrity is set and verified by the shift manager.

o Cavity level is 26.5.

o RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

o The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

o Both station batteries are operable and split out.

o Both trains of SFP cooling are available with one in service.

o All make-up flowpaths to the SFP are available.

o 1-RM-Q7, CTMT PARTC ALERT/FAILURE and 1-RM-R7, 1-RM-RI-159 have just alarmed.

o A RHR pump in service to the A HX. B RHR pump and HX are tagged out for maintenance.

Headset communications between the MCR and the manipulator crane have been verified.

You are to authorize fuel movement after completing attachment 8, if conditions allow. If conditions do not allow, you are to list ALL issues present that must be resolved to allow fuel movement to commence.

Terminating Cues Applicant has completed the attachment and discussed results and problems with examiner.

Tools and Equipment 1-OSP-ZZ-004, Attachment 8 Technical Specifications Simulator Safety Considerations None Notes

Surry 2014-301 Auth Fuel Move PERFORMANCE CHECKLIST Simulator Set-up Recall a CSD IC (IC 274 Protected) or (IC35 25% Cold Cal) and ensure that RHR pump discharge and RCS temperatures are below 140 oF.

Align HHSI and fill pressurizer to 56.5% cold cal if necessary.

Fail Rad Monitor 1-RM-159 HI by inserting Malf RM0202 Fail NI-32 low NO0102-Severity -1 Tagout 1-RH-P-1B and place a red magnet above control switch.

Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

START TIME: _________________

Evaluators note-determination of items to be in non-compliance that actually are in compliance constitutes a critical step failure.

STEP 1:

Refueling Containment Integrity set.

Remarks:

IAW 1-OP-FH-001 STANDARD:

_____ Recalls (or refers to) turnover statement that refuel integrity is SET.

_____ Initials in D block for Refueling Containment Integrity set EVALUATOR NOTES:

If asked: The shift manager has verified that refueling integrity is set as directed by 1-OP-FH-001.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 2:

Radiation Monitors Operable:

Manipulator Crane 1 operable Containment Gaseous 1 operable Containment Particulate 0 operable SFP Bridge 1 operable Vent-Vent Gaseous 1 operable Vent-Vent Particulate 1 operable Remarks:

Alarms 1-RM-Q7, and 1-RM-R7 will both be lit.

STANDARD:

Examines each radiation monitor and verifies normal readings.

• CRITICAL TASK-TRAINEE DETERMINES RADIATION MONITOR 1-RM-RI-159 OPERABILITY PREVENTS FUEL MOVEMENT.

EVALUATOR NOTES:

If asked: Radiation monitors are as they appear.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 3:

Source Range Detectors (audible indication in CTMT must be verified operable) 2 operable Remarks: None STANDARD:

Observes normal indication on NI-31 Determines that NI-32 is reading erroneously.

• CRITICAL TASK-TRAINEE DETERMINES TWO SOURCE RANGE NIs ARE NOT OPERABLE.

EVALUATOR NOTES:

If directed: the operating team will implement 1-AP-4.00 (NI Malfunction).

If asked: there is NO audible count rate in containment.

Determination that audible count rate does not exist is not a critical step as the source range failure is the cause of the lack of audible count rate.

COMMENTS:

_______ SAT

_______ UNSAT STEP 4:

Cavity level > 23 feet.

Remarks:

OU-SU-201, should be maintained as high as possible. No fuel movement permitted if < 23 feet in Cavity STANDARD:

Recalls (or refers to) turnover statement that cavity level is 26.5.

Determines that adequate cavity level exists to support fuel movement.

EVALUATOR NOTES:

If asked: cavity level has been verified at 26.5.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 5:

RHR pump and Heat Exchanger:

Cavity Level > 23 feet 1 operable Cavity Level < 23 feet 2 operable STANDARD:

Recalls (or refers to) turnover statement that cavity level is 26.5.

Observes 1 RHR pump in operation and one tagged out.

Determines that with present cavity level and operable RHR pump, fuel movement can commence.

EVALUATOR NOTES:

If asked: cavity level has been verified at 26.5.

COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

Direct communication between the Control Room and Manipulator Crane Remarks: When changing core geometry STANDARD:

Recalls (or refers to) turnover statement that communications have been established.

Determines that communication capability allows for fuel movement.

EVALUATOR NOTES:

If asked: operator is in the MCR equipped with a headset in communication with the refueling team.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 7:

RCS Boron concentration-2350 PPM (Admin limit)

Remarks:

RCS must be sampled at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the head is unbolted (Not required if defueled and cavity is drained below flange level. (Ref 2.3.15)

STANDARD:

Recalls (or refers to) turnover statement that RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

Determines that current boron concentration allows for fuel movement.

EVALUATOR NOTES:

If asked: RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

COMMENTS:

_______ SAT

_______ UNSAT STEP 8:

RHR Temperature: 140 °F Remarks: None STANDARD:

Observes RHR pump discharge temperature and determines that current RCS temperature allows for fuel movement.

EVALUATOR NOTES:

If asked: All RCS loops are isolated and drained.

If asked: All CETCs have been disconnected.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 9:

Reactor shutdown greater than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Remarks: For movement of irradiated fuel STANDARD:

Recalls (or refers to) turnover statement that unit has been shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br />.

Determines that sufficient time from shutdown exists to allow fuel movement.

EVALUATOR NOTES:

If asked: The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 10:

Control Room and Relay Room Emergency Ventilation-2 Trains Remarks: None STANDARD:

Examines current configuration of MCR/ESGR ventilation and determines that all fans are available.

Determines that current MCR/ESGR Emergency Ventilation configuration allows for fuel movement by observing the configuration of 1-VS-F-41/42 and 2-VS-F-41/42.

EVALUATOR NOTES:

If asked: Conditions are as they appear.

COMMENTS:

_______ SAT

_______ UNSAT STEP 11:

Control Room Chillers-3 minimum Remarks: Operable IAW power supply requirements of TS 3.23 STANDARD:

Examines current configuration of MCR chillers and determines that all chillers are available.

Determines that current MCR Chiller configuration allows for fuel movement by observing the configuration of 1-VS-E-4A, B, C, D, E.

EVALUATOR NOTES:

If asked: Conditions are as they appear.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 12:

MCR/ESGR AHU-8 minimum Remarks: None STANDARD:

Examines current configuration of MCR/ESGR air handlers and determines that all Air Handling Units are operable.

Determines that current MCR/ESGR air handler configuration allows for fuel movement EVALUATOR NOTES:

If asked: Conditions are as they appear.

COMMENTS:

_______ SAT

_______ UNSAT STEP 13:

120 Volt Vital Buses-2 minimum Remarks: None STANDARD:

Observes that all vital busses are energized and NO UPS/Battery charger alarms are LIT.

Recalls (or refers to) turnover statement that all vital bus UPS are in a normal EVALUATOR NOTES:

If asked: All vital bus UPS are in a normal configuration.

If asked: Both station batteries are operable and split out.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 14:

SFP Cooling-1 train available Remarks: None STANDARD:

Observes that one spent fuel cooling pump is in service.

_____ Recalls (or refers to) turnover statement that both trains of SFP cooling are available with one in service.

EVALUATOR NOTES:

If asked: both trains of SFP cooling are available with one in service.

COMMENTS:

_______ SAT

_______ UNSAT STEP 16:

SFP makeup borated water source-1 source available Remarks: None STANDARD:

Recalls (or refers to) turnover statement that all make-up flowpaths to the SFP are available.

EVALUATOR NOTES:

If asked: All make-up flowpaths to the SFP are available.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 17:

Reports to Shift Manager that task is complete STANDARD:

Reports that fuel movement CANNOT commence until the following problems are resolved:

1-RM-RI-158 must be returned to operable status.

NI-32 must be returned to operable status EVALUATOR NOTES:

None COMMENTS:

_______ SAT

_______ UNSAT STOP TIME_______________________________________:

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Determine if current plant conditions support fuel movement..

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions:

Unit 1 is at Refueling Shutdown.

The containment refueling SRO has called the control room for permission to commence core offload.

Initiating Cues It is a Monday DAYSHIFT.

Unit One is in refueling shutdown with the head and upper internals removed. A request from the refueling supervisor has been made to authorize fuel movement (core offload) in accordance with 1-OSP-ZZ-004 attachment 8.

Current conditions are as follows (items not observable from the control room):

o Refueling containment integrity is set and verified by the shift manager.

o Cavity level is 26.5.

o RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

o The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

o Both station batteries are operable and split out.

o Both trains of SFP cooling are available with one in service.

o All make-up flowpaths to the SFP are available.

o 1-RM-Q7, CTMT PARTC ALERT/FAILURE and 1-RM-R7, 1-RM-RI-159 have just alarmed.

o A RHR pump in service to the A HX. B RHR pump and HX are tagged out for maintenance.

Headset communications between the MCR and the manipulator crane have been verified.

You are to authorize fuel movement after completing attachment 8, if conditions allow. If conditions do not allow, you are to list ALL issues present that must be resolved to allow fuel movement to commence.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

Unit 1 is at Refueling Shutdown.

The containment refueling SRO has called the control room for permission to commence core offload.

Initiating Cues It is a Monday DAYSHIFT.

Unit One is in refueling shutdown with the head and upper internals removed. A request from the refueling SRO has been made to authorize fuel movement (core offload) in accordance with 1-OSP-ZZ-004 attachment 8.

Current conditions are as follows (items not observable from the control room):

o Refueling containment integrity is set and verified by the shift manager.

o Cavity level is 26.5.

o RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

o The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

o Both station batteries are operable and split out.

o Both trains of SFP cooling are available with one in service.

o All make-up flowpaths to the SFP are available.

o 1-RM-Q7, CTMT PARTC ALERT/FAILURE and 1-RM-R7, 1-RM-RI-159 have just alarmed.

o A RHR pump in service to the A HX. B RHR pump and HX are tagged out for maintenance.

Headset communications between the MCR and the manipulator crane have been verified.

You are to authorize fuel movement after completing attachment 8, if conditions allow. If conditions do not allow, you are to list ALL issues present that must be resolved to allow fuel movement to commence.

Surry 2014-301 OPT Review Page 1 of 10 U.S. Nuclear Regulatory Commission Surry Power Station SR14301 Administrative Job Performance Measure G2.2.12 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Review 1-OPT-FW-006, Auxiliary Feedwater MOV Test.

K/A: G.2.2.12 - Knowledge of surveillance procedures. RO: 3.7/ SRO: 4.1 Applicability Estimated Time Actual Time RO/SRO(D)/SRO(U) 10 Minutes Conditions Task is to be PERFORMED in the CLASSROOM.

Standards Review 1-OPT-FW-006, Auxiliary Feedwater MOV Test.

Initiating Cues 1-OPT-FW-006 has been completed by the previous shift.

You are to review the completed OPT for accuracy and completeness.

Document any issues identified during review and operability requirements, if any, on the answer sheet provided.

When you have completed the review, inform your examiner.

Terminating Cues 1-OPT-FW-006 review complete.

Tools and Equipment Copy of 1-OPT-FW-006 Safety Considerations None

Surry 2014-301 OPT Review Page 2 of 14 Initial Conditions:

Unit 1 at 100% power.

Initiating Cues 1-OPT-FW-006 has been completed by the previous shift.

You are to review the completed OPT for accuracy and completeness.

Document any issues identified during review and operability requirements, if any, on the answer sheet provided.

When you have completed the review, inform your examiner.

Surry 2014-301 OPT Review Page 3 of 14 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

At the completion of the JPM all SRO Candidates will have a Follow-Up question.

START TIME: ____________

STEP 1:

Reviews Scheduled PT Cover Sheet.

STANDARD:

a) Reviews the following:

Reviews Schedule Date, Drop Dead Date, Actual Start Date & Time, and Actual Finish Date & time.

Determines that PT was performed on the Schedule Start Date.

Determines that PT was completed prior to the Drop Dead date.

Identifies check mark correct in Completed by DDD in Maximo, YES blank.

Identifies that Satisfactory blank is checked.

Identifies Departmental Signature on appropriate blank.

EVALUATOR NOTES:

If asked, it is desired to perform this Review now.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 4 of 14 STEP 2:

Reviews Initial Conditions and Precautions and Limitations.

STANDARD:

Identifies Initial Condition 3.1 initialed.

Identifies Precautions and limitations 4.1 through 4.5 initialed.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT STEP 3:

Reviews section 6.1, Work Preparation, of section 6.0, INSTRUCTIONS.

STANDARD:

Identifies correct use of N/A for Step 6.1.1.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT STEP 4:

Reviews section 6.2, Testing 1-FW-MOV-151E, SG A AFW Flow Isol.

STANDARD:

a) Step 6.2.1: Cycle 1-FW-MOV-151E and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.2.2: Return 1-FW-MOV-151E to position specified by Shift Supervision. Circle as left position.

Identifies Open circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.2.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 5 of 14 STEP 5:

Reviews section 6.3, Testing 1-FW-MOV-151F, SG A AFW Flow Isol.

STANDARD:

a) Step 6.3.1: Cycle 1-FW-MOV-151F and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.3.2: Return 1-FW-MOV-151F to position specified by Shift Supervision. Circle as left position.

• Identifies Neither Open or Closed circled.

• Identifies Return to position verification initial missing in verification blank.

c) Step 6.3.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES:

Acknowledge that return to position open/closed not circled, and verification initial missing.

Have the Candidate continue with the PT review.

COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

Reviews section 6.4, Testing 1-FW-MOV-151C, SG B AFW Flow Isol.

STANDARD:

a) Step 6.4.1: Cycle 1-FW-MOV-151C and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.4.2: Return 1-FW-MOV-151C to position specified by Shift Supervision. Circle as left position.

Identifies Open circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.4.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 6 of 14 STEP 7:

Reviews section 6.5, Testing 1-FW-MOV-151D, SG B AFW Flow Isol.

STANDARD:

a) Step 6.5.1: Cycle 1-FW-MOV-151D and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.5.2: Return 1-FW-MOV-151D to position specified by Shift Supervision. Circle as left position.

• Identifies Open Not circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.5.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. filled in appropriately.

• Identifies Cal Date Due Date: is blank.

EVALUATOR NOTES:

Acknowledge Open not circled, and Cal Date Due: is blank.

Have the Candidate continue the PT Review.

COMMENTS:

_______ SAT

_______ UNSAT STEP 8:

Reviews section 6.6, Testing 1-FW-MOV-151A, SG C AFW Flow Isol.

STANDARD:

a) Step 6.6.1: Cycle 1-FW-MOV-151A and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.6.2: Return 1-FW-MOV-151A to position specified by Shift Supervision. Circle as left position.

Identifies Open circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.6.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 7 of 14 STEP 9:

Reviews section 6.7, Testing 1-FW-MOV-151B, SG C AFW Flow Isol.

STANDARD:

a) Step 6.7.1: Cycle 1-FW-MOV-151B and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.7.2: Return 1-FW-MOV-151B to position specified by Shift Supervision. Circle as left position.

Identifies Open circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.7.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT STEP 10: reviews Section 7.0 Follow-On.

STANDARD:

Verifies Step 7.1.1 initialed.

Verifies Step 7.1.2 initialed.

Verifies Satisfactory checked.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 8 of 14 STEP 11:

Reviews Section 7.2 Follow-On Tasks.

STANDARD:

• Identifies inappropriate N/A of Step 7.2.3. (N/A should stop at Step 7.2.2), and Step 7.2.3 should be initialed.

EVALUATOR NOTES:

Acknowledge inappropriate N/A of Step 7.2.3.

Have the candidate continue review of the PT.

COMMENTS:

_______ SAT

_______ UNSAT STEP 12:

Reviews Section 7.3 Notification, Documentation, and Procedure Closeout.

STANDARD:

Identifies initial for Step 7.3.1.

Identifies Both Names listed in Table.

Identifies Signature and date at bottom of page.

EVALUATOR NOTES: NONE Candidate must identify 4/5 of the incorrect items (80%) to be satisfactory.

COMMENTS:

_______ SAT

_______ UNSAT STOP TIME: ________

Notes:

EVALUATOR NOTE: Proceed to Follow-up question for SRO Candidates.

Surry 2014-301 OPT Review Page 9 of 14 ANSWER KEY NOT FOR TRAINEE 1-OPT-FW-006 REVIEW

1.

Step 6.3.2 - Identifies Neither Open or Closed circled.

2.

Step 6.3.2 - Identifies Return to position verification initial missing in verification blank.

3.

Step 6.5.2 - Identifies Open not circled.

4.

Step 6.5.3 - Identifies Cal Date Due Date is blank.

5.

Step 7.2.3 - Identifies inappropriate N/A of Step 7.2.3 Candidate must identify 4/5 of the incorrect items (80%) to be satisfactory.

Surry 2014-301 OPT Review Page 10 of 14 EVALUATORS REFERENCE COPY Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the Classroom.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions:

Unit 1 at 100% power.

Initiating Cues 1-OPT-FW-006 has been completed by the previous shift.

You are to review the completed OPT for accuracy and completeness.

Document any issues identified during review and operability requirements, if any, on the answer sheet provided.

When you have completed the review, inform your examiner.

Surry 2014-301 OPT Review Page 11 of 14 SRO ONLY ANSWER KEY NOT FOR TRAINEE 1-OPT-FW-006 FOLLOW-UP Question 1-OPT-FW-006 has been completed and the following MOV had a Close stroke time outside the Acceptable range:

Stroke Time Reference Acceptable Range 1-FW-MOV-151C, SG B AFW ISOL 28.2 sec 20.0 sec 17.0 - 23.0 sec What actions are required by Technical Specifications?

ANSWER: TS 3.6.C.3 require two redundant flowpaths, including system piping, headers, valves, and control board indication required for operation.

TS 3.6.G.1 requires a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock to restore to OPERABLE status.

Surry 2014-301 OPT Review Page 12 of 14 SRO ONLY Candidate 1-OPT-FW-006 FOLLOW-UP Question 1-OPT-FW-006 has been completed and the following MOV had a Close stroke time outside the Acceptable range:

Stroke Time Reference Acceptable Range 1-FW-MOV-151C, SG B AFW ISOL 28.2 sec 20.0 sec 17.0 - 23.0 sec What actions are required by Technical Specifications?

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

Unit 1 at 100% power.

Initiating Cues 1-OPT-FW-006 has been completed by the previous shift.

You are to review the completed OPT for accuracy and completeness.

Document any issues identified during review and operability requirements, if any, on the answer sheet provided.

When you have completed the review, inform your examiner.

ANSWER SHEET 1-OPT-FW-006 REVIEW

Surry 2014-301 Emerg Exposure Auth.

1 of 5 U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure G2.3.4 (RO 3.2 / SRO 3.7)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Authorize Emergency Exposure in accordance with EPIP-4.04, Emergency Exposure Limits.

K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

Applicability Estimated Time Actual Time SRO(D)/SRO(U) 5 Minutes Conditions Task may be PERFORMED in the Classroom.

Unit has experienced a LBLOCA.

Standards Emergency Exposure Denied IAW EPIP-4.04.

Initiating Cues Nuclear Shift Manager Direction.

Terminating Cues EPIP-4.04, Emergency Exposure Limits, step 9.0 completed.

Procedures EPIP-1.01, Revision 56.

EPIP-1.03, Revision 22.

EPIP-4.04, Revision 9.

Tools and Equipment Safety Considerations None None

Surry 2014-301 Emerg Exposure Auth.

2 of 5 Initial Conditions You are the Station Emergency Manager.

Unit 1 experienced a LBLOCA today at 1330 hrs. An Alert was declared at 1340 based on EAL identifier FA1.1 due to loss of RCS barrier.

All notifications have been made.

The following unit conditions exist:

o RMT is currently in service.

o 1-SI-P-1A experienced excessive seal leakage and was spraying water on the motor. The pump has been secured.

o 1-SI-P-1B is in service at this time.

Maintenance has two mechanics standing by to repair the seal for 1-SI-P-1A. Both men are between the ages of 40-45.

The calculated estimated TEDE dose is 12 Rem per individual.

You are currently performing step 15 of EPIP-1.03.

The Radiological Assessment Director (RAD) has performed EPIP-4.04 through step 9 as required and is waiting on authorization from you for emergency exposure.

Initiating Cues Here is the completed, up through step 9, EPIP-4.04 from the RAD. I need you to approve or disapprove the emergency exposure for the two mechanics. When you finish the actions necessary to accomplish this, please inform me.

Notes Fill out copies of EPIP-1.01 through step 8, and EPIP-1.03 through step 15. FA1.1 is the EAL identifier.

Use todays date. Alert declared at 1340 due to a LBLOCA. Two-mechanics between the ages of 40-45 are prepared to repair a seal leak on 1-SI-P-1A and are waiting on approval from the SEM for emergency exposure.

The estimated dose to each individual is 12 Rem TEDE. Use the name of the SRO being evaluated in the SM name spots in EPIP-1.01 (step 3), EPIP-1.03 (step 1), and EPIP-4.04 (step 1).

Fill out EPIP 4.04 through step 9. Fill out two (2) Attachment 3 forms with name of individual and exposure. Both forms should be approved by the RAD with Final authorization by the Shift manager left blank.

Surry 2014-301 Emerg Exposure Auth.

3 of 5 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

Have copies of all procedures (EPIP-1.01, 1.03 and 4.04) available upon request.

Role play as Radiological Assessment Director.

START TIME: _________________

STEP 1:

AUTHORIZES EMERGENCY EXPOSURE:

STANDARD:

a) Reviews EPIP-4.04 and notes that the limit to save valuable equipment is 10 Rem TEDE.

b) Determines from initiating conditions and review of EPIP-4.04, ATTACHMENT 3 (12 REM) that both operators would exceed the maximum limit of Dose to protect equipment.

c)

• Does not authorize (DISAPPROVES) emergency exposure for the two mechanics.

EVALUATORS NOTE:

COMMENTS:

_______ SAT

_______ UNSAT STEP 2:

Report completion of Task.

COMMENTS:

JPM COMPLETE STOP TIME: ___________________________

Comments: __________________________________________________________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions You are the Station Emergency Manager.

Unit 1 experienced a LBLOCA today at 1330 hrs. An Alert was declared at 1340 based on EAL identifier FA1.1 due to loss of RCS barrier.

All notifications have been made.

The following unit conditions exist:

o RMT is currently in service.

o 1-SI-P-1A experienced excessive seal leakage and was spraying water on the motor. The pump has been secured.

o 1-SI-P-1B is in service at this time.

Maintenance has two mechanics standing by to repair the seal for 1-SI-P-1A. Both men are between the ages of 40-45.

The calculated estimated TEDE dose is 12 Rem per individual.

You are currently performing step 15 of EPIP-1.03.

The Radiological Assessment Director (RAD) has performed EPIP-4.04 through step 9 as required and is waiting on authorization from you for emergency exposure.

Initiating Cues Here is the completed, up through step 9, EPIP-4.04 from the RAD. I need you to approve or disapprove the emergency exposure for the two mechanics. When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions You are the Station Emergency Manager.

Unit 1 experienced a LBLOCA today at 1330 hrs. An Alert was declared at 1340 based on EAL identifier FA1.1 due to loss of RCS barrier.

All notifications have been made.

The following unit conditions exist:

o RMT is currently in service.

o 1-SI-P-1A experienced excessive seal leakage and was spraying water on the motor. The pump has been secured.

o 1-SI-P-1B is in service at this time.

Maintenance has two mechanics standing by to repair the seal for 1-SI-P-1A. Both men are between the ages of 40-45.

The calculated estimated TEDE dose is 12 Rem per individual.

You are currently performing step 15 of EPIP-1.03.

The Radiological Assessment Director (RAD) has performed EPIP-4.04 through step 9 as required and is waiting on authorization from you for emergency exposure.

Initiating Cues Here is the completed, up through step 9, EPIP-4.04 from the RAD. I need you to approve or disapprove the emergency exposure for the two mechanics. When you finish the actions necessary to accomplish this, please inform me.

Surry 2014-301 Calculate Rad Dose Page 1 of 9 U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure G2.3.4 (RO 3.2 / SRO 3.7)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Calculate Dose and Best Work Method K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.2/3.7)

Applicability Estimated Time Actual Time ALL 30 Minutes Conditions Task is to be PERFORMED in the classroom.

Standards Determines the maximum allowable time for opening 1-RH-MOV-1700 is 6 minutes.

Initial Conditions:

Unit 1 has experienced a small break LOCA with a safety injection.

The Operating Team is attempting to place the Residual Heat Removal System in service, but they are unable to open 1-RH-MOV-1700 from the Main Control Room.

You have been tasked with entering Containment and locally opening 1-RH-MOV-1700.

Your allowable dose limit for this job is 1800 mr.

General area radiation levels have been manually estimated based on installed radiation monitor readings.

Survey maps of the Unit 1 Containment are available, showing dose rates and one way travel time to reach the valve via the chosen route.

Health Physics personnel are currently unavailable to provide assistance for dose determination.

Surry 2014-301 Calculate Rad Dose Page 2 of 9 On the 36 elevation, travel time (one way) is all the way to 1-RH-MOV-1700. Calculate dose received on travel on the 36 based on pathway dose and not dose rate in loop room-time to walk across loop room floor to 1-RH-MOV-1700 is negligible.

Initiating Cues You have been directed to determine:

1. The maximum time you will have to open 1-RH-MOV-1700 without exceeding your allowable dose.

Terminating Cues Determines the maximum time for opening 1-RH-MOV-1700 without exceeding dose limits.

Tools and Equipment Calculator Survey Data VPAP-2101 Safety Considerations None Notes

Surry 2014-301 Calculate Rad Dose Page 3 of 9 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

Provide survey map to candidate.

START TIME:__________________

STEP 1:

Calculate path exposure to 1-RH-MOV-1700.

STANDARD:

___ 1.

(3 R/HR)(1000 MR/R)(1 HR/60 MIN)(1 MIN)(2 TRIPS) = 100 MR.

(Personnel Hatch to Stairway)

___ 2.

(3 R/HR)(1000 MR/R)(1 HR/60 MIN)(3 MIN)(2 TRIPS) = 300 MR.

(Stairway)

___ 3.

(12 R/HR)(1000 MR/R)(1 HR/60 MIN)(2 MIN)(2 TRIPS) = 800 MR.

(Stairway on -36 to valve)

___ 4.

(100 MR)+(300 MR)+(800MR) =

• 1200 MR.

EVALUATOR'S NOTES: Total exposure via this path: 1200 mr. (acceptable band - 1699-1701 mr). THIS IS A CRITICAL STEP COMMENTS:

_______ SAT

_______ UNSAT STEP 2:

Calculate remaining allowable exposure at valve.

STANDARD:

__ 1.

Allowable Dose to open the valve - (1800 MR) - (1200 MR) =

• 600 MR EVALUATOR'S NOTES:

Total allowable dose: 600 MR. THIS IS A CRITICAL STEP COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Calculate Rad Dose Page 4 of 9 STEP 3:

Determine the maximum allowable time the operator has to open 1-RH-MOV-1700.

STANDARD:

___ 1.

(600 MR)(HR/6R)(1R/1000 MR)(1 HR/60 MIN) =

• 6 MIN.

(Personnel Hatch to Stairway)

EVALUATOR'S NOTES: Determines maximum allowable time to operate the valve is 6 minutes. THIS IS A CRITICAL STEP COMMENTS:

_______ SAT

_______ UNSAT STOP TIME:

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the classroom.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions:

Unit 1 has experienced a small break LOCA with a safety injection.

The Operating Team is attempting to place the Residual Heat Removal System in service, but they are unable to open 1-RH-MOV-1700 from the Main Control Room.

You have been tasked with entering Containment and locally opening 1-RH-MOV-1700.

Your allowable dose limit for this job is 1800 mr.

General area radiation levels have been manually estimated based on installed radiation monitor readings.

Survey maps of the Unit 1 Containment are available, showing dose rates and one way travel time to reach the valve via the chosen route.

Health Physics personnel are currently unavailable to provide assistance for dose determination.

On the 36 elevation, travel time (one way) is all the way to 1-RH-MOV-1700. Calculate dose received on travel on the 36 based on pathway dose and not dose rate in loop room-time to walk across loop room floor to 1-RH-MOV-1700 is negligible.

Initiating Cues You have been directed to determine:

2. The maximum time you will have to open 1-RH-MOV-1700 without exceeding your allowable dose.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Task Task is to be performed in the classroom.

Initial Conditions:

Unit 1 has experienced a small break LOCA with a safety injection.

The Operating Team is attempting to place the Residual Heat Removal System in service, but they are unable to open 1-RH-MOV-1700 from the Main Control Room.

You have been tasked with entering Containment and locally opening 1-RH-MOV-1700.

Your allowable dose limit for this job is 1800 mr.

General area radiation levels have been manually estimated based on installed radiation monitor readings.

Survey maps of the Unit 1 Containment are available, showing dose rates and one way travel time to reach the valve via the chosen route.

Health Physics personnel are currently unavailable to provide assistance for dose determination.

On the 36 elevation, travel time (one way) is all the way to 1-RH-MOV-1700. Calculate dose received on travel on the 36 based on pathway dose and not dose rate in loop room-time to walk across loop room floor to 1-RH-MOV-1700 is negligible.

Initiating Cues You have been directed to determine:

1. The maximum time you will have to open 1-RH-MOV-1700 without exceeding your allowable dose.

Surry 2014-301 Obtain Data for EPIP-2.01 Page 1 of 9 U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure G 2.4.39 (RO 3.8 / SRO 3.7)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Obtain Required information in accordance with EPIP-2.01, Notification of State and Local Governments.

K/A: G2.4.39 - Knowledge of RO responsibilities in emergency plan implementation.

Applicability Estimated Time Actual Time RO/SRO 12 Minutes Conditions Task may be PERFORMED in classroom or Simulator.

A simulated GENERAL EMERGENCY is in progress.

Standards Determines Meteorological data in accordance with EPIP-2.01, Notification of State and Local Governments.

Initiating Cues Nuclear Shift Manager direction.

Terminating Cues EPIP-2.01 steps 16-21 complete.

Procedures EPIP-2.01, Revision 43 Tools and Equipment Safety Considerations None None

Surry 2014-301 Obtain Data for EPIP-2.01 Page 2 of 9 Initial Conditions You are an extra Reactor Operator assisting the shift.

A General Emergency was declared one-half hour ago due to a LBLOCA.

Initial Notifications to the State and Local governments were made on time.

Initial Notification to the NRC was also made on time.

PCS is inoperable.

The Corporate Emergency Response Center reports that their link to our MET tower is inoperable.

Initiating Cues I am the Nuclear Shift Manager and you are the RO / BOP. You are to acquire the following MET data in accordance with EPIP-2.01 and give that information to the State and Local Emergency Communicator.

1) Temperature

2) Average Wind Direction

3) Wind Speed

4) Stability class Notes

Surry 2014-301 Obtain Data for EPIP-2.01 Page 3 of 9 PERFORMANCE CHECKLIST Simulator Set-up Enter the following Meter Overrides for MET PANEL Recorder Name Variable Name Initial Value Final Value Recorder Reading Wind Dir Upper MET_WIND_DIR_UPR 0.6111111 0

0o Wind Dir Lower MET_WIND_DIR_LWR 0.6111111 0

0o Wind Speed Upper MET_WIND_SPD_UPR 0.23 0.5 50 mph Wind Speed Lower MET_WIND_SPD_LWR 0.23 0.2 20 mph Ambient Temp.

MET_TEMP 0.651852 0.763 90 oF Delta Temp MET_DELTAT 1.0 0.22

-1.1 Wind Dir Backup MET_WIND_DIR_BKP 0.611111 0.67 361.8 oF Wind Spd Backup MET_WIND_SPD_BKP 0.23 0.45 45 mph Sigma Theta MET_WIND-MET_SIGMA_THETA 0.28 0.4 20o When complete the Recorders should look as shown below.

Surry 2014-301 Obtain Data for EPIP-2.01 Page 4 of 9 Notes to the Evaluator.

Task critical elements are bolded and denoted by an asterisk (*).

START TIME: _________.

STEP 1:

Determines EPIP-2.01 steps 16 provides procedural guidance for obtaining MET data.

STANDARD:

a) Continuous Action Page directs RO to go to step 16.

EVALUATORS NOTE:

Candidate can also identify step 16 by review of procedure.

COMMENTS:

_______ SAT

_______ UNSAT STEP 2:

Notes: (Prior to Step 16)

Data may be obtained from MET panel charts, PCS, the computer modem or local data logger (Described in 0-AP-20.03, LOSS OF METEOROLOGICAL MONITORING INSTRUMENTATION).

Both the PCS EMCOMM feature and PCS Point Group #39, contains meteorological information averaged over the previous 15 minutes STANDARD:

a) Reads and acknowledges the Notes.

EVALUATORS NOTE:

If asked: PCS is inoperable, you are to use the MET Data Recorder.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 5 of 9 STEP 3:

Check ON-SITE METEOROLOGICAL INFORMATION - AVAILABLE. (Step 16)

STANDARD:

a) Determines that METEOROLOGICAL INFORMATION is available.

b) Initials Step 16.

EVALUATORS NOTE:

If asked: MET information is available on site.

COMMENTS:

_______ SAT

_______ UNSAT STEP 4:

Get current on-site meteorological information as requested. (Step 17)

STANDARD:

a) Candidate may obtain the information in any order.

b) Initials Step 17.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 6 of 9 STEP 5:

Get Temperature from Main Tower Temperature Indicator. (Step 18)

STANDARD:

a) Determines from MET Tower Primary Signal Recorder that Temperature is 90 oF.

b) Records Temperature 90.0 oF on data sheet.

c) Initials Step 18.

EVALUATORS NOTE:

Data sheet is provided to record indications, but candidate can write value on other paper.

COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

Notes: (Prior to Step 19)

Primary source of wind speed is the Main Tower Lower Level indicator.

Alternate sources are (1) Backup Tower, and (2) Main Tower Upper Level.

The Dose Assessment Team may direct the use of meteorological data from the Main Tower Upper Level, based on the nature of the release.

STANDARD:

a) Acknowledges Notes.

EVALUATORS NOTE:

If asked: The Dose Asessment Team has not made any requests.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 7 of 9 STEP 7:

GET WIND SPEED (Step 19)

STANDARD:

a) Determines from MET Tower Primary Signal Recorder that Wind Speed is 20mph.

b) Records Wind Speed 20.0 mph on data sheet.

c) Initials Step 19 EVALUATORS NOTE:

Note prior to Step 19 identifies the correct source for Wind Speed.

Data sheet is provided to record indications, but candidate can write value on other paper COMMENTS:

_______ SAT

_______ UNSAT STEP 7:

Notes: (Prior to Step 20)

An approximate average wind direction for the previous 15 minutes should be determined.

Primary source of wind direction is the Main Tower Lower Level indicator.

Alternate sources are (1) Backup Tower, and (2) Main Tower Upper Level.

STANDARD:

a) Candidate reads and acknowledges Notes.

EVALUATORS NOTE:

If asked: Time Compression: 15 minutes has been met.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 8 of 9 STEP 8:

GET AVERAGE WIND DIRECTION FROM PCS. (Step 20)

STANDARD:

a) Determines PCS is NOT Available.

b) Performs RNO gets Average Wind Direction from MET Recorder.

c) Records Wind Direction 0.0 reading on data sheet.

c) Initials step.

EVALUATORS NOTE:

Note prior to Step 20 identifies Primary source and Alternate source.

Data sheet is provided to record indications, but candidate can write value on other paper.

COMMENTS:

_______ SAT

_______ UNSAT STEP 9:

Notes: (Prior to Step 21)

Main Tower Delta T is the preferred source of stability class. Sigma Theta (Backup Tower) is the secondary source.

The value closer to G should be used if unable to distinguish Delta T or Sigma Theta value.

Numerical ranges presented below for Delta T and Sigma Theta are less than the range of the chart recorder and indicator in the Control Room. Indications are not expected to read outside the ranges found on these tables.

STANDARD:

a) Candidate reads and acknowledges Notes.

EVALUATORS NOTE:

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 9 of 9 STEP 10:

DETERMINE STABILITY CLASS. (Step 21)

STANDARD:

a) Candidate determines Stability class using Delta T. Delta T is -1.1 oF from MET Tower Primary Recorder.

b) Records Stability Class B on data sheet.

c) Initials Step.

EVALUATORS NOTE:

Note prior to step 21 identifies the correct column (Delta T) to use.

Data sheet is provided to record indications, but candidate can write value on other paper.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 10 of 9 STEP 11:

Provides MET data to Emergency Communicator.

Temperature 90.0 oF Wind Speed 20.0 mph Wind Direction 0.0 Stability Class B

STANDARD:

a)

• Provides MET Data as shown above. This is a critical step.

EVALUATORS NOTE:

Accept data as Emergency Communicator COMMENTS:

JPM COMPLETE

_______ SAT

_______ UNSAT STOP TIME: ___________________________

Comments: __________________________________________________________________________________

Surry 2014-301 Obtain Data for EPIP-2.01 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions You are an extra Reactor Operator assisting the shift.

A General Emergency was declared one-half hour ago due to a LBLOCA.

Initial Notifications to the State and Local governments were made on time.

Initial Notification to the NRC was also made on time.

PCS is inoperable.

The Corporate Emergency Response Center reports that their link to our MET tower is inoperable.

Initiating Cues I am the Nuclear Shift Manager and you are the RO / BOP. You are to acquire the following MET data in accordance with EPIP-2.01 and give that information to the State and Local Emergency Communicator.

1) Temperature

2) Average Wind Direction

3) Wind Speed

4) Stability class

Surry 2014-301 Obtain Data for EPIP-2.01 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions You are an extra Reactor Operator assisting the shift.

A General Emergency was declared one-half hour ago due to a LBLOCA.

Initial Notifications to the State and Local governments were made on time.

Initial Notification to the NRC was also made on time.

PCS is inoperable.

The Corporate Emergency Response Center reports that their link to our MET tower is inoperable.

Initiating Cues I am the Nuclear Shift Manager and you are the RO / BOP. You are to acquire the following MET data in accordance with EPIP-2.01 and give that information to the State and Local Emergency Communicator.

1) Temperature

2) Average Wind Direction

3) Wind Speed

4) Stability class Data Sheet Temperature Wind Speed Wind Direction Stability Class

Surry 2014-301 Determine Classification and PAR Page 1 of U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure 2.4.41(RO 2.9 / SRO 3.7)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title CLASSIFY AN EVENT AND DETERMINE THE REQUIRED PAR ACTIONS K/A: G2.4.41 - Knowledge of the emergency action level thresholds and classifications. (2.9/4.6)

Applicability Est Completion Time Actual Time SRO ONLY 20 Minutes (Portions **TC**)

Conditions Task is to be PERFORMED in the SIMULATOR or CLASSROOM.

A simulated GENERAL EMERGENCY is in progress.

Standards Evaluate a given set of plant conditions and determine that a General Emergency exists in accordance with EPIP-1.01 and the EAL table, and then determine that the appropriate PAR for that General Emergency is PAR B.

Initiating Cues Significant event notification.

EPIP-1.01, Emergency Manager Controlling Procedure.

Terminating Cues EPIP-1.06, Step 8 Completed.

Procedures EPIP-1.01, Emergency Manager Controlling Procedure, Revision 56.

EPIP-1.06, Protective Action Recommendations, Revision 10.

Tools and Equipment Safety Considerations None None

Surry 2014-301 Determine Classification and PAR Page 2 of MAKE SURE YOU PROVIDE THE CORRECT CUE SHEET (PAGE 1, LAST PAGE OF THIS JPM) FOR THE PORTION OF THE TASK TO BE PERFORMED!!!!

Initial Conditions You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The station has experienced a loss of offsite power due to grid collapse. The system operator reports 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for power restoration to Surrys switchyard.

Both units are currently at Hot Shutdown.

When attempting to load the AAC diesel on the 1J bus, the 1J bus faulted and electricians have determined that extensive damage has occurred to the buswork with repairs estimated to take 4 days.

1. 1 EDG tripped on overspeed during start-up. Mechanics reset the overspeed, and when started, the diesel experienced extremely high vibrations and casing penetration by a piston, and was subsequently tripped locally.

All radiation monitors indicate pre-event radiation levels.

Unit 1 team is currently performing the actions of ECA-0.0, Loss of All AC power.

Unit 2 team is completing the actions of ES-0.1, Reactor Trip Response.

Initiating Cues Here is a copy of EPIP 1.01, you are directed to classify this event in accordance with EPIP-1.01 and inform me of your classification as soon as it has been made.

This portion of the JPM is TIME CRITICAL.

Surry 2014-301 Determine Classification and PAR Page 1 of 18 Performance Checklist Notes to the Evaluator.

Task critical elements are denoted by an asterisk (*). If substeps of a critical element also have an asterisk (*),

then only those asterisked substeps are critical to performance of that task element.

Critical step sequencing requirements: 1 before 3.

START TIME: _________

Evaluators note-candidate may choose to make EAL classification straight from EAL tables and NOT implement steps of EPIP-1.01. Steps are given here as guidance.

Critical task time ends when classification determined regardless of determination method.

Caution and Note prior to step 1.

CAUTION: Declaration of the highest emergency class for which an Emergency Action Level is exceeded shall be made.

NOTE:

The PCS is potentially unreliable in the event of an earthquake. Therefore, PCS parameters should be evaluated for accuracy should an earthquake occur.

Standards (a)

Acknowledges CAUTION and NOTE Evaluators Note Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 2 of 18 EAL STEP 1:

EVALUATE EMERGENCY ACTION LEVELS:

a) Determine event category using the applicable Emergency Action Level Matrix:

Hot Conditions (RCS > 200 °F)

Cold Conditions (RCS 200 °F) b) Review EAL associated with event category c) Use Control Room monitors, PCS, and outside reports to get indications of emergency conditions listed in the EAL Matrix d) Verify EAL - CURRENTLY EXCEEDED e) Initiate a chronological log of events Standards (a)

Refers to the HOT chart (b)

Determines event category to be Loss of Power.

(c)

Refers to given conditions to determine EAL applicability (d)

DETERMINES EAL SG1.1 GENERAL EMERGENCY to be met.

(e)

Initiates (or verbalizes) a chronological log of events.

Evaluators Note: If candidate makes EAL determination at this step, record stop time.

Evaluator's Comments STOP TIME: ___________

TIME CRITIAL-15 minutes

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 3 of 18 EAL Step 2:

RECORD EAL IDENTIFIER, TIME EMERGENCY DECLARED AND SM/SEM NAME.

Standards (a)

Determines that event is a General Emergency based on EAL SG1.1 (Loss of all offsite and onsite power to Unit 1 Emergency Busses H and J-This is a critical step.

(b)

Classifies event as a GENERAL EMERGENCY-This is a critical step.

Evaluators Note: If candidate makes EAL determination at this step, record stop time.

Evaluator's Comments STOP TIME: ___________

TIME CRITIAL-15 minutes

_______ SAT

_______ UNSAT EAL Step 3:

ANNOUNCE THE FOLLOWING DECLARATIONS:

Station Emergency Manager position Emergency Classification EAL Time Declared Standards (a)

Makes announcement Evaluators Note If candidate makes incorrect classification end the JPM at this point.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 4 of 18 EVALUATOR:

Take EPIP-1.01 into your possession at this time.

HANDOUT PAGE 2 of OPERATOR INSTRUCTIONS AT THIS TIME.

Initial Conditions A simulated GENERAL EMERGENCY is in progress.

You are the Nuclear Shift Manager. A GENERAL EMERGENCY has been declared on SG1.1.

EPIP-1.05, Response to General Emergency, Step 3 has been completed.

The State and Local Communicator has determined wind direction to be (from) 180° and speed to be 17 mph.

There are no known impediments making evacuation dangerous.

A dose assessment has not been made.

All available radiation monitors indicate pre-event trends.

Initiating Cues Here's a copy of EPIP-1.06, Protective Action Recommendations. You are to complete EPIP-1.06, Protective Action Recommendations in its entirety.

When you finish the actions necessary to accomplish this, please inform me.

This portion of the JPM is TIME CRITICAL.

Notes to the Evaluator.

TIME CRITICAL REQUIREMENT:

This PAR must be identified and relayed to S&L communicators within 15 minutes.

START TIME:

PAR Step 1:

Procedure Step 1 INITIATE PROCEDURE.

Standards Fills in Name, Time and Date on Step 1.

Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 2:

Procedure Step 1 USE ATTACHMENT 1, PROTECTIVE ACTION RECOMMENDATION MATRIX, TO DETERMINE INITIAL PAR Standards (a)

Goes to Attachment 1.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 5 of 18 PAR Step 3:

- Flowchart block 1-Known impediments make evacuation dangerous.

Standards

- Determines there are no known impediments that make evacuation dangerous.

Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 4:

- Flowchart block 2-Radiological release in progress or has occurred related to the event. (YES or NO).

Standards

- Determines that no radiological release in progress.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 6 of 18 PAR Step 5:

- Flowchart-Evacuate 2 miles radius and 5 miles downwind.

Standards Determines that PAR B is required-This is a critical step.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 7 of 18 PAR Step 6 Evaluators note - Candidate will now return to step 3 of the procedure (attachment 1 items complete)

Notes prior to step 3-ATTACHMENT 2, AFFECTED SECTOR(S) MAP, is to be used for all PAR developments from this procedure. ATTACHMENT 2, AFFECTED SECOTR(S) MAP is not to be used for PARs developed IAW EPIP-4.07, PROTECTECTIVE MEASURES.

Standards

- Acknowledges notes CUES

- None Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 7 Procedure Step 3 IMPLEMENT ATTACHMENT 2, AFFECTED SECTOR(S) MAP:

a) Record time wind data acquired.

b) Record average wind direction from, in degrees and compass point.

c) Record average wind speed in mph.

d) Record affected sectors.

e) Mark affected sectors on map (use any writing implement available, e.g.,

pen, pencil, highlighter etc.)

f)

GO TO Step 6 Standards Completes attachment 2 as follows:

• At (now) wind direction from 180° (S), Wind Speed 17 mph, Sectors RAB.

- Using attachment 5 (as per the note), determines that affected sectors are R, A, B.

CUES

- If asked: Met data obtained at JPM start time.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 8 of 18 PAR Step 8 Procedure Step 6 COMPLETE ATTACHMENT 3, PROTECTIVE ACTION RECOMMENDATION FORM:

a) Protective Action Recommendation:

1) Mark appropriate PAR box(s)

2) Record Mile radius and Miles downwind

3) Record Downwind Sectors b) Remarks/Approval Information:

1) Record Remarks (optional)

2) Approve PAR (sign report)

3) Record date and time report approved Standards Completes item 1 of attachment 3 by marking EVACUATE 2 mile radius (360°) and 5 miles downwind in the following sectors R, A, B -

this is a critical step.

Completes item 2 by signing and entering the current time and date.

Evaluators Note None CUES If asked: None Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 9 of 18 PAR Step 9 Procedure Step 7 - HAVE EMERGENCY COMMUNICATORS NOTIFY OFF-SITE AUTHORITIES OF PAR:

Virginia Emergency Operations Center notified IAW:

EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS OR EPIP-4.07, PROTECTIVE MEASURES NRC notified IAW EPIP-2.02, NOTIFICATION OF NRC (notification made from Control Room or TSC, when activated)

NRC notified IAW EPIP-4.33, HEALTH PHYSICS NETWORK COMMUNICATIONS (notifications made from TSC or LEOF/CEOF only after NRC requests HPN be established)

Standards (a)

Directs State and Local EC to notify Virginia EOC - this is a critical step.

(b)

Directs NRC EC.

CUES Tell SRO: State and Local EC will transmit PAR to Virginia EOC.

Tell SRO: NRC EC will notify NRC of PAR.

If asked: HPN has not been requested yet.

Evaluator's Note This step must be complete within 15 minutes of start of task.

Record Time: ______

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 10 of 18 PAR Step 10 Procedure Step 8 -

CHECK IF CURRENT PROTECTIVE ACTION RECOMMENDATION - INITIAL PAR.

Standards Determines this is current PAR from CUES If Asked: This is the initial PAR.

Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 11 Procedure Step 9 -

HAVE RADIOLOGICAL ASSESSMENT DIRECTOR (RAD) IMPLEMENT EPIP-4.07, PROTECTIVE MEASURES [RADIOLOGICAL ASSESSMENT COORDINATOR (RAC) IF IN LEOF/CEOF]

Standards Tells Evaluator to Initiate EPIP-4.07.

CUES Tell SRO: EPIP-4.07 has been initiated.

Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 12 CAUTION prior to step 10 Previously issued Protective Action Recommendations should not be reduced until the threat is fully under control and after consulting with Commonwealth of Virginia emergency response organization Standards SRO Acknowledges the Caution.

CUES Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 13 NOTE prior to step 10

_______ SAT

Surry 2014-301 Determine Classification and PAR Page 11 of 18 A Shelter-in-Place recommendation may supersede a Radiological Evacuation recommendation based on known impediments.

Standards SRO Acknowledges the Note.

CUES Evaluator's Comments

_______ UNSAT PAR Step 14 Procedure Step 10 Standards (a)

Determines that no conditions at this time necessitate a change to the current PAR.

CUES If asked: HP does not recommend a radiological based PAR or implementation of Potassium Iodide strategies.

If asked: Met data remains as previously reported.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 12 of 18 PAR Step 15 Procedure Step 11 - CHECK EMERGENCY - TERMINATED Standards (a)

Asks Evaluator if Emergency is terminated.

(b)

Asks Evaluator if RAD/RAC recommends a PAR change.

(c)

Determines Procedure is completed until conditions change.

CUES If asked: Emergency classification is still in effect.

If asked: RAD/RAC does not recommend a PAR change at this time.

Evaluator's Comments STOP TIME:

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 13 of 18 KEY

Surry 2014-301 Determine Classification and PAR Page 14 of 18 Evaluator's Summary CLASSIFY AN EVENT AND DETERMINE THE REQUIRED PAR ACTIONS

Surry 2014-301 Determine Classification and PAR Page 15 of 18 PAGE 1 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The station has experienced a loss of offsite power due to grid collapse. The system operator reports 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for power restoration to Surrys switchyard.

Both units are currently at Hot Shutdown.

When attempting to load the AAC diesel on the 1J bus, the 1J bus faulted and electricians have determined that extensive damage has occurred to the buswork with repairs estimated to take 4 days.

1. 1 EDG tripped on overspeed during start-up. Mechanics reset the overspeed, and when started, the diesel experienced extremely high vibrations and casing penetration by a piston, and was subsequently tripped locally.

All radiation monitors indicate pre-event radiation levels.

Unit 1 team is currently performing the actions of ECA-0.0, Loss of All AC power.

Unit 2 team is completing the actions of ES-0.1, Reactor Trip Response.

Initiating Cues Here is a copy of EPIP 1.01, you are directed to classify this event in accordance with EPIP-1.01 and inform me of your classification as soon as it has been made.

This portion of the JPM is TIME CRITICAL.

Surry 2014-301 Determine Classification and PAR Page 16 of 18 PAGE 2 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions A simulated GENERAL EMERGENCY is in progress.

You are the Nuclear Shift Manager. A GENERAL EMERGENCY has been declared on SG1.1.

EPIP-1.05, Response to General Emergency, Step 3 has been completed.

The State and Local Communicator has determined wind direction to be (from) 180° and speed to be 17 mph.

There are no known impediments making evacuation dangerous.

A dose assessment has not been made.

All available radiation monitors indicate pre-event trends.

Initiating Cues Here's a copy of EPIP-1.06, Protective Action Recommendations. You are to complete EPIP-1.06, Protective Action Recommendations in its entirety.

When you finish the actions necessary to accomplish this, please inform me.

This portion of the JPM is TIME CRITICAL.

PAGE 2 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A simulated GENERAL EMERGENCY is in progress.

You are the Nuclear Shift Manager. A GENERAL EMERGENCY has been declared on SG1.1.

EPIP-1.05, Response to General Emergency, Step 3 has been completed.

The State and Local Communicator has determined wind direction to be (from) 180° and speed to be 17 mph.

There are no known impediments making evacuation dangerous.

A dose assessment has not been made.

All available radiation monitors indicate pre-event trends.

Initiating Cues Here's a copy of EPIP-1.06, Protective Action Recommendations. You are to complete EPIP-1.06, Protective Action Recommendations in its entirety.

When you finish the actions necessary to accomplish this, please inform me.

• This portion of the JPM is TIME CRITICAL.

PAGE 1 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The station has experienced a loss of offsite power due to grid collapse. The system operator reports 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for power restoration to Surrys switchyard.

Both units are currently at Hot Shutdown.

When attempting to load the AAC diesel on the 1J bus, the 1J bus faulted and electricians have determined that extensive damage has occurred to the buswork with repairs estimated to take 4 days.

1. 1 EDG tripped on overspeed during start-up. Mechanics reset the overspeed, and when started, the diesel experienced extremely high vibrations and casing penetration by a piston, and was subsequently tripped locally.

All radiation monitors indicate pre-event radiation levels.

Unit 1 team is currently performing the actions of ECA-0.0, Loss of All AC power.

Unit 2 team is completing the actions of ES-0.1, Reactor Trip Response.

Initiating Cues Here is a copy of EPIP 1.01, you are directed to classify this event in accordance with EPIP-1.01 and inform me of your classification as soon as it has been made.

This portion of the JPM is TIME CRITICAL

Surry 2014-301 Quadrant Power Tilt Calculation Page 1 of 9 U.S. Nuclear Regulatory Commission Surry Power Station SR14301 Administrative Job Performance Measure G2.1.7 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Perform a Quadrant Power Tilt Calculation.

K/A: G.2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Applicability Estimated Time Actual Time RO/SRO(D)/SRO(U) 15 Minutes Conditions Task is to be PERFORMED in the classroom.

Standards Correctly calculates Quadrant Power Tilt for given core conditions on the Calculation of Excore Quadrant Power Tilt Ratios, Attachment 6 of 0-AP-1.00, Rod Control Malfunction.

Initiating Cues A dropped rod has occurred on Unit 1.

A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00. Rod Control System Malfunction.

When you have determined the Quadrant Power Tilt, inform the examiner.

Terminating Cues Applicant has completed the QPTR Calculation.

Tools and Equipment Calculator NIS Setpoints and Power Range Currents Data Sheet Safety Considerations None

Surry 2014-301 Quadrant Power Tilt Calculation Page 2 of 9 Initial Conditions:

Unit 1 operating at 100% power.

o Control Rod D-10, Control Bank B, Group 1 dropped and is currently indicating 0 steps.

Initiating Cues Control Rod D-10, Control Bank B, has dropped on Unit 1.

A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00, Rod Control System Malfunction, Step 15.

The Shift Manager directs you to perform the Quadrant Power Tilt Calculation in accordance with Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios.

You are to perform these calculations to 4 significant digits.

You are provided a copy of the Power Range Currents from the NIS Data Book providing Normalized Values.

When you have determined the Quadrant Power Tilt, inform the examiner.

Notes Actual detector currents taken from the Power Range NIs:

N-41 Upper Detector Current 120.5 N-41 Lower Detector Current 124.2 N-42 Upper Detector Current 96.5 N-42 Lower Detector Current 94.23 N-43 Upper Detector Current 114.7 N-43 Lower Detector Current 115.5 N-44 Upper Detector Current 119.1 N-44 Lower Detector Current 121.8

Surry 2014-301 Quadrant Power Tilt Calculation Page 3 of 9 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

At the completion of the JPM all SRO Candidates will have a Follow-Up question.

START TIME: ____________

STEP 1:

Acknowledges NOTE prior to Step 1 of Att. 6.

Calculations for QPTR should be carried out to four places to the right of the decimal place to provide accuracy and consistency of results.

_______ SAT

_______ UNSAT STEP 2:

[Step 1, Att. 6]

a) Record Reactor Power, Date, and Time in appropriate blocks.

b) Initials Step 1.

STANDARD:

Records 100% for Reactor Power block, Current Date in Date block, Time in Time block.

EVALUATORS NOTE:

If Asked: Current Reactor Power is 100%.

If Asked: Use todays date.

If Asked: Use current time.

COMMENTS:

_______ SAT

_______ UNSAT STEP 3:

[Step 2, Att. 6]

a) Transcribes information from data sheets onto 0-AP-1.00, Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios, Step 2 Table.

STANDARD:

Places PR NI currents and Normalized Currents in appropriate location on Calculation of Excore Quadrant Power Tilt Ratios.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Quadrant Power Tilt Calculation Page 4 of 9 STEP 4:

[STEP 3, Att. 6]

a) Performs calculations to obtain normalized values for Upper Detectors.

STANDARD:

a) Divides Upper Detector current by Normalized currents for each detector.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT STEP 5:

[STEP 3, Att. 6]

a) Performs calculations to obtain Sum of normalized values for Upper Detectors.

STANDARD:

a) Adds Upper Detector Normalized currents for all Upper detectors EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.

COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

[STEP 3, Att. 6]

a) Performs calculations to obtain normalized values for Lower Detectors.

STANDARD:

a) Divides Lower Detector current by Normalized currents for each detector.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Quadrant Power Tilt Calculation Page 5 of 9 STEP 7:

[Step 3, Att. 6]

a) Performs calculations to obtain Sum of normalized values for Lower Detectors.

STANDARD:

a) Adds Lower Detector Normalized currents for all Lower Detectors.

b) Initials Step 3 of Attachment 6.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT STEP 8:

[Step 4, Att. 6]

a) Records the Number of Detectors in use.

b) Initials Step 4.

STANDARD:

a) Records the Number of Detectors in Step 4; b) Initials Step 4.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

If Asked: All 4 Detectors are used.

COMMENTS:

_______ SAT

_______ UNSAT STEP 9:

[Step 5, Att. 6]

a) Calculates the average upper and lower detector current values.

STANDARD:

a) Transcribes Upper and Lower detector Sum of Normalized Values from Step 3 of Attachment 6.

b) Divides each Sum by the number of Detectors in use.

c) Initials Step 5.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Quadrant Power Tilt Calculation Page 6 of 9 STEP 10: [Step 6, Att. 6]

a) From Step 3, Record the following values.

STANDARD:

a) Records the Maximum Normalized Upper Detector Current from Step 3 (N41 value of 1.0143.)

b) Records the Maximum Normalized Lower Detector Current From Step 3 (N41 value of 1.0393.)

c) Initials Step 6 of Attachment 6.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT STEP 11: [Step 7, Att. 6]

a) Calculates the maximum upper and lower Excore Quadrant Power Tilt Ratios.

STANDARD:

a) Divides Maximum Upper channel current by the Average Upper Detector currents to determine the Upper Excore Quadrant Power Tilt Ratio.

b) Divides Maximum Lower channel current by the Average Lower Detector current to determine the Lower Excore Quadrant Power Tilt Ratio.

c) Initials Step 7 of Attachment 6.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT STEP 12: [Step 8, Att. 6]

a) Calculates Tilt %.

STANDARD:

a) Calculates Tilt % for Upper channels.

b) Caculates % Tilt for Lower channels.

c) Initials Step 8 of Attachment 6.

EVALUATOR S NOTE:

(See attached Calculation of Excore Quadrant Power Tilt Ratios for calculations.)

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Quadrant Power Tilt Calculation Page 7 of 9 STEP 13: Determines final Quadrant Power Tilt Value.

STANDARD:

a) Determines final Quadrant Power Tilt Value from above calculations to be 1.0898 or 8.98% Tilt based on the Lower Channels. (Range 8.6% - 9%; 8.6% based on rounding of NI current values; 9% based on rounding 8.98% to 9%)

b) Notifies Examiner, Task Complete.

EVALUATOR NOTES:

COMMENTS:

_______ SAT

_______ UNSAT STOP TIME:

EVALUATOR NOTE: Proceed to Follow-up question for SRO Candidates.

Surry 2014-301 Quadrant Power Tilt Calculation Page 8 of 9

Surry 2014-301 Quadrant Power Tilt Calculation Page 9 of 9

Surry 2014-301 Quadrant Power Tilt Calculation Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the classroom.

Perform a Quadrant Power Tilt calculation.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions:

Unit 1 operating at 100% power.

o Control Rod D-10, Control Bank B, Group 1 dropped and is currently indicating 0 steps.

Initiating Cues Control Rod D-10, Control Bank B, has dropped on Unit 1.

A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00, Rod Control System Malfunction, Step 15.

The Shift Manager directs you to perform a Quadrant Power Tilt Calculation in accordance with Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios.

You are provided a copy of the Power Range Currents from the NIS Data Book providing Normalized Values.

When you have determined the Quadrant Power Tilt, inform the examiner.

Actual detector currents taken from the Power Range NIs:

N-41 Upper Detector Current 120.5 N-41 Lower Detector Current 124.2 N-42 Upper Detector Current 96.5 N-42 Lower Detector Current 94.23 N-43 Upper Detector Current 114.7 N-43 Lower Detector Current 115.5 N-44 Upper Detector Current 119.1 N-44 Lower Detector Current 121.8

Surry 2014-301 Quadrant Power Tilt Calculation SRO ONLY ANSWER KEY NOT FOR TRAINEE QPTR FOLLOW-UP Question With the calculated Quadrant Power Tilt, what are the Tech Spec actions (if any)?

ANSWER: TS 3.12.B.6 requires:

3.12.B.6.a Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either hot channel factors shall be determined and power level adjusted to meet the requirement OR 3.12.B.6.b Power level to be reduced from Rated Power 2% for each percent of Quadrant Power Tilt. Therefore for a QPTR of 9% power must be reduced 18%. The high neutron flux trip setpoint shall also be reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Surry 2014-301 Quadrant Power Tilt Calculation SRO ONLY Candidate QPTR FOLLOW-UP Question With the calculated Quadrant Power Tilt, what are the Tech Spec actions (if any)?

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

Unit 1 operating at 100% power.

o Control Rod D-10, Control Bank B, Group 1 dropped and is currently indicating 0 steps.

Initiating Cues Control Rod D-10, Control Bank B, has dropped on Unit 1.

A Quadrant Power Tilt Calculation needs to be performed as directed by 0-AP-1.00, Rod Control System Malfunction, Step 15.

The Shift Manager directs you to perform a Quadrant Power Tilt Calculation in accordance with Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios.

You are provided a copy of the Power Range Currents from the NIS Data Book providing Normalized Values.

When you have determined the Quadrant Power Tilt, inform the examiner.

Actual detector currents taken from the Power Range NIs:

N-41 Upper Detector Current 120.5 N-41 Lower Detector Current 124.2 N-42 Upper Detector Current 96.5 N-42 Lower Detector Current 94.23 N-43 Upper Detector Current 114.7 N-43 Lower Detector Current 115.5 N-44 Upper Detector Current 119.1 N-44 Lower Detector Current 121.8

Surry Unit 1 NI Calibration Data Power Range Currents N41 N42 N43 N44 DELTA FLUX @

100%

I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps 0

118.8 119.5 118.5 119.3 119.1 119.5 119.1 119.5 DELTA FLUX @

120%

I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps I (Top)

µamps I (Bottom)

µamps 0

142.5 143.4 142.2 143.1 142.9 143.5 142.9 143.4 8

148.6 137.2 148.3 137.0 149.1 137.3 149.1 137.2

- 24 124.2 161.8 123.9 161.5 124.5 161.9 124.6 161.9 Data based on flux map number S1C26M15A Computer and Recorder Constants Recorder = K0411 = K0412 = K0413 = K0414 = 18.647 Performed / Verified By: __________/ __________ Date: _______

LaFrance Davis 7/21/14

Surry 2014-301 Auth Fuel Move U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure G2.1.40 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Authorize Fuel Movement K/A: G2.1.40 Knowledge of refueling administrative procedures (2.8/3.9)

Applicability Estimated Time Actual Time SRO(I)/SRO(U) 20 Minutes Conditions Task is to be PERFORMED in the simulator.

Standards Correctly identify all plant conditions that do not support fuel movement in accordance with 1-OSP-ZZ-004 attachment 8, given a specific set of plant conditions.

Terminating Cues 1-OSP-ZZ-004, attachment 8 assessment complete.

Procedures 1-OSP-ZZ-004, Unit 1 Safety Systems Status List For Cold Shutdown/Refueling Conditions, Revision 47.

Tools and Equipment Safety Considerations None None

Surry 2014-301 Auth Fuel Move Initiating Cues It is a Monday DAYSHIFT.

Unit One is in refueling shutdown with the head and upper internals removed. A request from the refueling supervisor has been made to authorize fuel movement (core offload) in accordance with 1-OSP-ZZ-004 attachment 8.

Current conditions are as follows (items not observable from the control room):

o Refueling containment integrity is set and verified by the shift manager.

o Cavity level is 26.5.

o RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

o The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

o Both station batteries are operable and split out.

o Both trains of SFP cooling are available with one in service.

o All make-up flowpaths to the SFP are available.

o 1-RM-Q7, CTMT PARTC ALERT/FAILURE and 1-RM-R7, 1-RM-RI-159 have just alarmed.

o A RHR pump in service to the A HX. B RHR pump and HX are tagged out for maintenance.

Headset communications between the MCR and the manipulator crane have been verified.

You are to authorize fuel movement after completing attachment 8, if conditions allow. If conditions do not allow, you are to list ALL issues present that must be resolved to allow fuel movement to commence.

Terminating Cues Applicant has completed the attachment and discussed results and problems with examiner.

Tools and Equipment 1-OSP-ZZ-004, Attachment 8 Technical Specifications Simulator Safety Considerations None Notes

Surry 2014-301 Auth Fuel Move PERFORMANCE CHECKLIST Simulator Set-up Recall a CSD IC (IC 274 Protected) or (IC35 25% Cold Cal) and ensure that RHR pump discharge and RCS temperatures are below 140 oF.

Align HHSI and fill pressurizer to 56.5% cold cal if necessary.

Fail Rad Monitor 1-RM-159 HI by inserting Malf RM0202 Fail NI-32 low NO0102-Severity -1 Tagout 1-RH-P-1B and place a red magnet above control switch.

Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

START TIME: _________________

Evaluators note-determination of items to be in non-compliance that actually are in compliance constitutes a critical step failure.

STEP 1:

Refueling Containment Integrity set.

Remarks:

IAW 1-OP-FH-001 STANDARD:

_____ Recalls (or refers to) turnover statement that refuel integrity is SET.

_____ Initials in D block for Refueling Containment Integrity set EVALUATOR NOTES:

If asked: The shift manager has verified that refueling integrity is set as directed by 1-OP-FH-001.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 2:

Radiation Monitors Operable:

Manipulator Crane 1 operable Containment Gaseous 1 operable Containment Particulate 0 operable SFP Bridge 1 operable Vent-Vent Gaseous 1 operable Vent-Vent Particulate 1 operable Remarks:

Alarms 1-RM-Q7, and 1-RM-R7 will both be lit.

STANDARD:

Examines each radiation monitor and verifies normal readings.

• CRITICAL TASK-TRAINEE DETERMINES RADIATION MONITOR 1-RM-RI-159 OPERABILITY PREVENTS FUEL MOVEMENT.

EVALUATOR NOTES:

If asked: Radiation monitors are as they appear.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 3:

Source Range Detectors (audible indication in CTMT must be verified operable) 2 operable Remarks: None STANDARD:

Observes normal indication on NI-31 Determines that NI-32 is reading erroneously.

• CRITICAL TASK-TRAINEE DETERMINES TWO SOURCE RANGE NIs ARE NOT OPERABLE.

EVALUATOR NOTES:

If directed: the operating team will implement 1-AP-4.00 (NI Malfunction).

If asked: there is NO audible count rate in containment.

Determination that audible count rate does not exist is not a critical step as the source range failure is the cause of the lack of audible count rate.

COMMENTS:

_______ SAT

_______ UNSAT STEP 4:

Cavity level > 23 feet.

Remarks:

OU-SU-201, should be maintained as high as possible. No fuel movement permitted if < 23 feet in Cavity STANDARD:

Recalls (or refers to) turnover statement that cavity level is 26.5.

Determines that adequate cavity level exists to support fuel movement.

EVALUATOR NOTES:

If asked: cavity level has been verified at 26.5.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 5:

RHR pump and Heat Exchanger:

Cavity Level > 23 feet 1 operable Cavity Level < 23 feet 2 operable STANDARD:

Recalls (or refers to) turnover statement that cavity level is 26.5.

Observes 1 RHR pump in operation and one tagged out.

Determines that with present cavity level and operable RHR pump, fuel movement can commence.

EVALUATOR NOTES:

If asked: cavity level has been verified at 26.5.

COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

Direct communication between the Control Room and Manipulator Crane Remarks: When changing core geometry STANDARD:

Recalls (or refers to) turnover statement that communications have been established.

Determines that communication capability allows for fuel movement.

EVALUATOR NOTES:

If asked: operator is in the MCR equipped with a headset in communication with the refueling team.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 7:

RCS Boron concentration-2350 PPM (Admin limit)

Remarks:

RCS must be sampled at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the head is unbolted (Not required if defueled and cavity is drained below flange level. (Ref 2.3.15)

STANDARD:

Recalls (or refers to) turnover statement that RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

Determines that current boron concentration allows for fuel movement.

EVALUATOR NOTES:

If asked: RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

COMMENTS:

_______ SAT

_______ UNSAT STEP 8:

RHR Temperature: 140 °F Remarks: None STANDARD:

Observes RHR pump discharge temperature and determines that current RCS temperature allows for fuel movement.

EVALUATOR NOTES:

If asked: All RCS loops are isolated and drained.

If asked: All CETCs have been disconnected.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 9:

Reactor shutdown greater than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> Remarks: For movement of irradiated fuel STANDARD:

Recalls (or refers to) turnover statement that unit has been shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br />.

Determines that sufficient time from shutdown exists to allow fuel movement.

EVALUATOR NOTES:

If asked: The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 10:

Control Room and Relay Room Emergency Ventilation-2 Trains Remarks: None STANDARD:

Examines current configuration of MCR/ESGR ventilation and determines that all fans are available.

Determines that current MCR/ESGR Emergency Ventilation configuration allows for fuel movement by observing the configuration of 1-VS-F-41/42 and 2-VS-F-41/42.

EVALUATOR NOTES:

If asked: Conditions are as they appear.

COMMENTS:

_______ SAT

_______ UNSAT STEP 11:

Control Room Chillers-3 minimum Remarks: Operable IAW power supply requirements of TS 3.23 STANDARD:

Examines current configuration of MCR chillers and determines that all chillers are available.

Determines that current MCR Chiller configuration allows for fuel movement by observing the configuration of 1-VS-E-4A, B, C, D, E.

EVALUATOR NOTES:

If asked: Conditions are as they appear.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 12:

MCR/ESGR AHU-8 minimum Remarks: None STANDARD:

Examines current configuration of MCR/ESGR air handlers and determines that all Air Handling Units are operable.

Determines that current MCR/ESGR air handler configuration allows for fuel movement EVALUATOR NOTES:

If asked: Conditions are as they appear.

COMMENTS:

_______ SAT

_______ UNSAT STEP 13:

120 Volt Vital Buses-2 minimum Remarks: None STANDARD:

Observes that all vital busses are energized and NO UPS/Battery charger alarms are LIT.

Recalls (or refers to) turnover statement that all vital bus UPS are in a normal EVALUATOR NOTES:

If asked: All vital bus UPS are in a normal configuration.

If asked: Both station batteries are operable and split out.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 14:

SFP Cooling-1 train available Remarks: None STANDARD:

Observes that one spent fuel cooling pump is in service.

_____ Recalls (or refers to) turnover statement that both trains of SFP cooling are available with one in service.

EVALUATOR NOTES:

If asked: both trains of SFP cooling are available with one in service.

COMMENTS:

_______ SAT

_______ UNSAT STEP 16:

SFP makeup borated water source-1 source available Remarks: None STANDARD:

Recalls (or refers to) turnover statement that all make-up flowpaths to the SFP are available.

EVALUATOR NOTES:

If asked: All make-up flowpaths to the SFP are available.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Auth Fuel Move STEP 17:

Reports to Shift Manager that task is complete STANDARD:

Reports that fuel movement CANNOT commence until the following problems are resolved:

1-RM-RI-158 must be returned to operable status.

NI-32 must be returned to operable status EVALUATOR NOTES:

None COMMENTS:

_______ SAT

_______ UNSAT STOP TIME_______________________________________:

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Determine if current plant conditions support fuel movement..

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions:

Unit 1 is at Refueling Shutdown.

The containment refueling SRO has called the control room for permission to commence core offload.

Initiating Cues It is a Monday DAYSHIFT.

Unit One is in refueling shutdown with the head and upper internals removed. A request from the refueling supervisor has been made to authorize fuel movement (core offload) in accordance with 1-OSP-ZZ-004 attachment 8.

Current conditions are as follows (items not observable from the control room):

o Refueling containment integrity is set and verified by the shift manager.

o Cavity level is 26.5.

o RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

o The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

o Both station batteries are operable and split out.

o Both trains of SFP cooling are available with one in service.

o All make-up flowpaths to the SFP are available.

o 1-RM-Q7, CTMT PARTC ALERT/FAILURE and 1-RM-R7, 1-RM-RI-159 have just alarmed.

o A RHR pump in service to the A HX. B RHR pump and HX are tagged out for maintenance.

Headset communications between the MCR and the manipulator crane have been verified.

You are to authorize fuel movement after completing attachment 8, if conditions allow. If conditions do not allow, you are to list ALL issues present that must be resolved to allow fuel movement to commence.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

Unit 1 is at Refueling Shutdown.

The containment refueling SRO has called the control room for permission to commence core offload.

Initiating Cues It is a Monday DAYSHIFT.

Unit One is in refueling shutdown with the head and upper internals removed. A request from the refueling SRO has been made to authorize fuel movement (core offload) in accordance with 1-OSP-ZZ-004 attachment 8.

Current conditions are as follows (items not observable from the control room):

o Refueling containment integrity is set and verified by the shift manager.

o Cavity level is 26.5.

o RHR pump discharge and cavity boron is currently 2404 ppm (sampled 30 minutes ago).

o The reactor was shutdown 122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> ago.

o Both station batteries are operable and split out.

o Both trains of SFP cooling are available with one in service.

o All make-up flowpaths to the SFP are available.

o 1-RM-Q7, CTMT PARTC ALERT/FAILURE and 1-RM-R7, 1-RM-RI-159 have just alarmed.

o A RHR pump in service to the A HX. B RHR pump and HX are tagged out for maintenance.

Headset communications between the MCR and the manipulator crane have been verified.

You are to authorize fuel movement after completing attachment 8, if conditions allow. If conditions do not allow, you are to list ALL issues present that must be resolved to allow fuel movement to commence.

Surry 2014-301 OPT Review Page 1 of 10 U.S. Nuclear Regulatory Commission Surry Power Station SR14301 Administrative Job Performance Measure G2.2.12 Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Review 1-OPT-FW-006, Auxiliary Feedwater MOV Test.

K/A: G.2.2.12 - Knowledge of surveillance procedures. RO: 3.7/ SRO: 4.1 Applicability Estimated Time Actual Time RO/SRO(D)/SRO(U) 10 Minutes Conditions Task is to be PERFORMED in the CLASSROOM.

Standards Review 1-OPT-FW-006, Auxiliary Feedwater MOV Test.

Initiating Cues 1-OPT-FW-006 has been completed by the previous shift.

You are to review the completed OPT for accuracy and completeness.

Document any issues identified during review and operability requirements, if any, on the answer sheet provided.

When you have completed the review, inform your examiner.

Terminating Cues 1-OPT-FW-006 review complete.

Tools and Equipment Copy of 1-OPT-FW-006 Safety Considerations None

Surry 2014-301 OPT Review Page 2 of 14 Initial Conditions:

Unit 1 at 100% power.

Initiating Cues 1-OPT-FW-006 has been completed by the previous shift.

You are to review the completed OPT for accuracy and completeness.

Document any issues identified during review and operability requirements, if any, on the answer sheet provided.

When you have completed the review, inform your examiner.

Surry 2014-301 OPT Review Page 3 of 14 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

At the completion of the JPM all SRO Candidates will have a Follow-Up question.

START TIME: ____________

STEP 1:

Reviews Scheduled PT Cover Sheet.

STANDARD:

a) Reviews the following:

Reviews Schedule Date, Drop Dead Date, Actual Start Date & Time, and Actual Finish Date & time.

Determines that PT was performed on the Schedule Start Date.

Determines that PT was completed prior to the Drop Dead date.

Identifies check mark correct in Completed by DDD in Maximo, YES blank.

Identifies that Satisfactory blank is checked.

Identifies Departmental Signature on appropriate blank.

EVALUATOR NOTES:

If asked, it is desired to perform this Review now.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 4 of 14 STEP 2:

Reviews Initial Conditions and Precautions and Limitations.

STANDARD:

Identifies Initial Condition 3.1 initialed.

Identifies Precautions and limitations 4.1 through 4.5 initialed.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT STEP 3:

Reviews section 6.1, Work Preparation, of section 6.0, INSTRUCTIONS.

STANDARD:

Identifies correct use of N/A for Step 6.1.1.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT STEP 4:

Reviews section 6.2, Testing 1-FW-MOV-151E, SG A AFW Flow Isol.

STANDARD:

a) Step 6.2.1: Cycle 1-FW-MOV-151E and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.2.2: Return 1-FW-MOV-151E to position specified by Shift Supervision. Circle as left position.

Identifies Open circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.2.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 5 of 14 STEP 5:

Reviews section 6.3, Testing 1-FW-MOV-151F, SG A AFW Flow Isol.

STANDARD:

a) Step 6.3.1: Cycle 1-FW-MOV-151F and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.3.2: Return 1-FW-MOV-151F to position specified by Shift Supervision. Circle as left position.

• Identifies Neither Open or Closed circled.

• Identifies Return to position verification initial missing in verification blank.

c) Step 6.3.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES:

Acknowledge that return to position open/closed not circled, and verification initial missing.

Have the Candidate continue with the PT review.

COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

Reviews section 6.4, Testing 1-FW-MOV-151C, SG B AFW Flow Isol.

STANDARD:

a) Step 6.4.1: Cycle 1-FW-MOV-151C and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.4.2: Return 1-FW-MOV-151C to position specified by Shift Supervision. Circle as left position.

Identifies Open circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.4.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 6 of 14 STEP 7:

Reviews section 6.5, Testing 1-FW-MOV-151D, SG B AFW Flow Isol.

STANDARD:

a) Step 6.5.1: Cycle 1-FW-MOV-151D and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.5.2: Return 1-FW-MOV-151D to position specified by Shift Supervision. Circle as left position.

• Identifies Open Not circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.5.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. filled in appropriately.

• Identifies Cal Date Due Date: is blank.

EVALUATOR NOTES:

Acknowledge Open not circled, and Cal Date Due: is blank.

Have the Candidate continue the PT Review.

COMMENTS:

_______ SAT

_______ UNSAT STEP 8:

Reviews section 6.6, Testing 1-FW-MOV-151A, SG C AFW Flow Isol.

STANDARD:

a) Step 6.6.1: Cycle 1-FW-MOV-151A and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.6.2: Return 1-FW-MOV-151A to position specified by Shift Supervision. Circle as left position.

Identifies Open circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.6.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 7 of 14 STEP 9:

Reviews section 6.7, Testing 1-FW-MOV-151B, SG C AFW Flow Isol.

STANDARD:

a) Step 6.7.1: Cycle 1-FW-MOV-151B and verify full stroke. Record the time required to close and to open the MOV.

Identifies Close and Open times within the Acceptable Range.

b) Step 6.7.2: Return 1-FW-MOV-151B to position specified by Shift Supervision. Circle as left position.

Identifies Open circled.

Identifies Return to position correctly verified by initial in verification blank.

c) Step 6.7.3: record the stopwatch SQC No. and Cal Due Date.

Identifies SQC No. and Cal Due Date blanks filled out appropriately.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT STEP 10: reviews Section 7.0 Follow-On.

STANDARD:

Verifies Step 7.1.1 initialed.

Verifies Step 7.1.2 initialed.

Verifies Satisfactory checked.

EVALUATOR NOTES: NONE COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 OPT Review Page 8 of 14 STEP 11:

Reviews Section 7.2 Follow-On Tasks.

STANDARD:

• Identifies inappropriate N/A of Step 7.2.3. (N/A should stop at Step 7.2.2), and Step 7.2.3 should be initialed.

EVALUATOR NOTES:

Acknowledge inappropriate N/A of Step 7.2.3.

Have the candidate continue review of the PT.

COMMENTS:

_______ SAT

_______ UNSAT STEP 12:

Reviews Section 7.3 Notification, Documentation, and Procedure Closeout.

STANDARD:

Identifies initial for Step 7.3.1.

Identifies Both Names listed in Table.

Identifies Signature and date at bottom of page.

EVALUATOR NOTES: NONE Candidate must identify 4/5 of the incorrect items (80%) to be satisfactory.

COMMENTS:

_______ SAT

_______ UNSAT STOP TIME: ________

Notes:

EVALUATOR NOTE: Proceed to Follow-up question for SRO Candidates.

Surry 2014-301 OPT Review Page 9 of 14 ANSWER KEY NOT FOR TRAINEE 1-OPT-FW-006 REVIEW

1.

Step 6.3.2 - Identifies Neither Open or Closed circled.

2.

Step 6.3.2 - Identifies Return to position verification initial missing in verification blank.

3.

Step 6.5.2 - Identifies Open not circled.

4.

Step 6.5.3 - Identifies Cal Date Due Date is blank.

5.

Step 7.2.3 - Identifies inappropriate N/A of Step 7.2.3 Candidate must identify 4/5 of the incorrect items (80%) to be satisfactory.

Surry 2014-301 OPT Review Page 10 of 14 EVALUATORS REFERENCE COPY Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the Classroom.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions:

Unit 1 at 100% power.

Initiating Cues 1-OPT-FW-006 has been completed by the previous shift.

You are to review the completed OPT for accuracy and completeness.

Document any issues identified during review and operability requirements, if any, on the answer sheet provided.

When you have completed the review, inform your examiner.

Surry 2014-301 OPT Review Page 11 of 14 SRO ONLY ANSWER KEY NOT FOR TRAINEE 1-OPT-FW-006 FOLLOW-UP Question 1-OPT-FW-006 has been completed and the following MOV had a Close stroke time outside the Acceptable range:

Stroke Time Reference Acceptable Range 1-FW-MOV-151C, SG B AFW ISOL 28.2 sec 20.0 sec 17.0 - 23.0 sec What actions are required by Technical Specifications?

ANSWER: TS 3.6.C.3 require two redundant flowpaths, including system piping, headers, valves, and control board indication required for operation.

TS 3.6.G.1 requires a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock to restore to OPERABLE status.

Surry 2014-301 OPT Review Page 12 of 14 SRO ONLY Candidate 1-OPT-FW-006 FOLLOW-UP Question 1-OPT-FW-006 has been completed and the following MOV had a Close stroke time outside the Acceptable range:

Stroke Time Reference Acceptable Range 1-FW-MOV-151C, SG B AFW ISOL 28.2 sec 20.0 sec 17.0 - 23.0 sec What actions are required by Technical Specifications?

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions:

Unit 1 at 100% power.

Initiating Cues 1-OPT-FW-006 has been completed by the previous shift.

You are to review the completed OPT for accuracy and completeness.

Document any issues identified during review and operability requirements, if any, on the answer sheet provided.

When you have completed the review, inform your examiner.

ANSWER SHEET 1-OPT-FW-006 REVIEW

Surry 2014-301 Emerg Exposure Auth.

1 of 5 U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure G2.3.4 (RO 3.2 / SRO 3.7)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Authorize Emergency Exposure in accordance with EPIP-4.04, Emergency Exposure Limits.

K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

Applicability Estimated Time Actual Time SRO(D)/SRO(U) 5 Minutes Conditions Task may be PERFORMED in the Classroom.

Unit has experienced a LBLOCA.

Standards Emergency Exposure Denied IAW EPIP-4.04.

Initiating Cues Nuclear Shift Manager Direction.

Terminating Cues EPIP-4.04, Emergency Exposure Limits, step 9.0 completed.

Procedures EPIP-1.01, Revision 56.

EPIP-1.03, Revision 22.

EPIP-4.04, Revision 9.

Tools and Equipment Safety Considerations None None

Surry 2014-301 Emerg Exposure Auth.

2 of 5 Initial Conditions You are the Station Emergency Manager.

Unit 1 experienced a LBLOCA today at 1330 hrs. An Alert was declared at 1340 based on EAL identifier FA1.1 due to loss of RCS barrier.

All notifications have been made.

The following unit conditions exist:

o RMT is currently in service.

o 1-SI-P-1A experienced excessive seal leakage and was spraying water on the motor. The pump has been secured.

o 1-SI-P-1B is in service at this time.

Maintenance has two mechanics standing by to repair the seal for 1-SI-P-1A. Both men are between the ages of 40-45.

The calculated estimated TEDE dose is 12 Rem per individual.

You are currently performing step 15 of EPIP-1.03.

The Radiological Assessment Director (RAD) has performed EPIP-4.04 through step 9 as required and is waiting on authorization from you for emergency exposure.

Initiating Cues Here is the completed, up through step 9, EPIP-4.04 from the RAD. I need you to approve or disapprove the emergency exposure for the two mechanics. When you finish the actions necessary to accomplish this, please inform me.

Notes Fill out copies of EPIP-1.01 through step 8, and EPIP-1.03 through step 15. FA1.1 is the EAL identifier.

Use todays date. Alert declared at 1340 due to a LBLOCA. Two-mechanics between the ages of 40-45 are prepared to repair a seal leak on 1-SI-P-1A and are waiting on approval from the SEM for emergency exposure.

The estimated dose to each individual is 12 Rem TEDE. Use the name of the SRO being evaluated in the SM name spots in EPIP-1.01 (step 3), EPIP-1.03 (step 1), and EPIP-4.04 (step 1).

Fill out EPIP 4.04 through step 9. Fill out two (2) Attachment 3 forms with name of individual and exposure. Both forms should be approved by the RAD with Final authorization by the Shift manager left blank.

Surry 2014-301 Emerg Exposure Auth.

3 of 5 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

Have copies of all procedures (EPIP-1.01, 1.03 and 4.04) available upon request.

Role play as Radiological Assessment Director.

START TIME: _________________

STEP 1:

AUTHORIZES EMERGENCY EXPOSURE:

STANDARD:

a) Reviews EPIP-4.04 and notes that the limit to save valuable equipment is 10 Rem TEDE.

b) Determines from initiating conditions and review of EPIP-4.04, ATTACHMENT 3 (12 REM) that both operators would exceed the maximum limit of Dose to protect equipment.

c)

• Does not authorize (DISAPPROVES) emergency exposure for the two mechanics.

EVALUATORS NOTE:

COMMENTS:

_______ SAT

_______ UNSAT STEP 2:

Report completion of Task.

COMMENTS:

JPM COMPLETE STOP TIME: ___________________________

Comments: __________________________________________________________________________________

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the simulator.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions You are the Station Emergency Manager.

Unit 1 experienced a LBLOCA today at 1330 hrs. An Alert was declared at 1340 based on EAL identifier FA1.1 due to loss of RCS barrier.

All notifications have been made.

The following unit conditions exist:

o RMT is currently in service.

o 1-SI-P-1A experienced excessive seal leakage and was spraying water on the motor. The pump has been secured.

o 1-SI-P-1B is in service at this time.

Maintenance has two mechanics standing by to repair the seal for 1-SI-P-1A. Both men are between the ages of 40-45.

The calculated estimated TEDE dose is 12 Rem per individual.

You are currently performing step 15 of EPIP-1.03.

The Radiological Assessment Director (RAD) has performed EPIP-4.04 through step 9 as required and is waiting on authorization from you for emergency exposure.

Initiating Cues Here is the completed, up through step 9, EPIP-4.04 from the RAD. I need you to approve or disapprove the emergency exposure for the two mechanics. When you finish the actions necessary to accomplish this, please inform me.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions You are the Station Emergency Manager.

Unit 1 experienced a LBLOCA today at 1330 hrs. An Alert was declared at 1340 based on EAL identifier FA1.1 due to loss of RCS barrier.

All notifications have been made.

The following unit conditions exist:

o RMT is currently in service.

o 1-SI-P-1A experienced excessive seal leakage and was spraying water on the motor. The pump has been secured.

o 1-SI-P-1B is in service at this time.

Maintenance has two mechanics standing by to repair the seal for 1-SI-P-1A. Both men are between the ages of 40-45.

The calculated estimated TEDE dose is 12 Rem per individual.

You are currently performing step 15 of EPIP-1.03.

The Radiological Assessment Director (RAD) has performed EPIP-4.04 through step 9 as required and is waiting on authorization from you for emergency exposure.

Initiating Cues Here is the completed, up through step 9, EPIP-4.04 from the RAD. I need you to approve or disapprove the emergency exposure for the two mechanics. When you finish the actions necessary to accomplish this, please inform me.

Surry 2014-301 Calculate Rad Dose Page 1 of 9 U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure G2.3.4 (RO 3.2 / SRO 3.7)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Calculate Dose and Best Work Method K/A: G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.2/3.7)

Applicability Estimated Time Actual Time ALL 30 Minutes Conditions Task is to be PERFORMED in the classroom.

Standards Determines the maximum allowable time for opening 1-RH-MOV-1700 is 6 minutes.

Initial Conditions:

Unit 1 has experienced a small break LOCA with a safety injection.

The Operating Team is attempting to place the Residual Heat Removal System in service, but they are unable to open 1-RH-MOV-1700 from the Main Control Room.

You have been tasked with entering Containment and locally opening 1-RH-MOV-1700.

Your allowable dose limit for this job is 1800 mr.

General area radiation levels have been manually estimated based on installed radiation monitor readings.

Survey maps of the Unit 1 Containment are available, showing dose rates and one way travel time to reach the valve via the chosen route.

Health Physics personnel are currently unavailable to provide assistance for dose determination.

Surry 2014-301 Calculate Rad Dose Page 2 of 9 On the 36 elevation, travel time (one way) is all the way to 1-RH-MOV-1700. Calculate dose received on travel on the 36 based on pathway dose and not dose rate in loop room-time to walk across loop room floor to 1-RH-MOV-1700 is negligible.

Initiating Cues You have been directed to determine:

1. The maximum time you will have to open 1-RH-MOV-1700 without exceeding your allowable dose.

Terminating Cues Determines the maximum time for opening 1-RH-MOV-1700 without exceeding dose limits.

Tools and Equipment Calculator Survey Data VPAP-2101 Safety Considerations None Notes

Surry 2014-301 Calculate Rad Dose Page 3 of 9 PERFORMANCE CHECKLIST Notes to the Evaluator Task critical elements are bolded and denoted by an asterisk (*).

Provide survey map to candidate.

START TIME:__________________

STEP 1:

Calculate path exposure to 1-RH-MOV-1700.

STANDARD:

___ 1.

(3 R/HR)(1000 MR/R)(1 HR/60 MIN)(1 MIN)(2 TRIPS) = 100 MR.

(Personnel Hatch to Stairway)

___ 2.

(3 R/HR)(1000 MR/R)(1 HR/60 MIN)(3 MIN)(2 TRIPS) = 300 MR.

(Stairway)

___ 3.

(12 R/HR)(1000 MR/R)(1 HR/60 MIN)(2 MIN)(2 TRIPS) = 800 MR.

(Stairway on -36 to valve)

___ 4.

(100 MR)+(300 MR)+(800MR) =

• 1200 MR.

EVALUATOR'S NOTES: Total exposure via this path: 1200 mr. (acceptable band - 1699-1701 mr). THIS IS A CRITICAL STEP COMMENTS:

_______ SAT

_______ UNSAT STEP 2:

Calculate remaining allowable exposure at valve.

STANDARD:

__ 1.

Allowable Dose to open the valve - (1800 MR) - (1200 MR) =

• 600 MR EVALUATOR'S NOTES:

Total allowable dose: 600 MR. THIS IS A CRITICAL STEP COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Calculate Rad Dose Page 4 of 9 STEP 3:

Determine the maximum allowable time the operator has to open 1-RH-MOV-1700.

STANDARD:

___ 1.

(600 MR)(HR/6R)(1R/1000 MR)(1 HR/60 MIN) =

• 6 MIN.

(Personnel Hatch to Stairway)

EVALUATOR'S NOTES: Determines maximum allowable time to operate the valve is 6 minutes. THIS IS A CRITICAL STEP COMMENTS:

_______ SAT

_______ UNSAT STOP TIME:

Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Task Task is to be performed in the classroom.

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions:

Unit 1 has experienced a small break LOCA with a safety injection.

The Operating Team is attempting to place the Residual Heat Removal System in service, but they are unable to open 1-RH-MOV-1700 from the Main Control Room.

You have been tasked with entering Containment and locally opening 1-RH-MOV-1700.

Your allowable dose limit for this job is 1800 mr.

General area radiation levels have been manually estimated based on installed radiation monitor readings.

Survey maps of the Unit 1 Containment are available, showing dose rates and one way travel time to reach the valve via the chosen route.

Health Physics personnel are currently unavailable to provide assistance for dose determination.

On the 36 elevation, travel time (one way) is all the way to 1-RH-MOV-1700. Calculate dose received on travel on the 36 based on pathway dose and not dose rate in loop room-time to walk across loop room floor to 1-RH-MOV-1700 is negligible.

Initiating Cues You have been directed to determine:

2. The maximum time you will have to open 1-RH-MOV-1700 without exceeding your allowable dose.

Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Task Task is to be performed in the classroom.

Initial Conditions:

Unit 1 has experienced a small break LOCA with a safety injection.

The Operating Team is attempting to place the Residual Heat Removal System in service, but they are unable to open 1-RH-MOV-1700 from the Main Control Room.

You have been tasked with entering Containment and locally opening 1-RH-MOV-1700.

Your allowable dose limit for this job is 1800 mr.

General area radiation levels have been manually estimated based on installed radiation monitor readings.

Survey maps of the Unit 1 Containment are available, showing dose rates and one way travel time to reach the valve via the chosen route.

Health Physics personnel are currently unavailable to provide assistance for dose determination.

On the 36 elevation, travel time (one way) is all the way to 1-RH-MOV-1700. Calculate dose received on travel on the 36 based on pathway dose and not dose rate in loop room-time to walk across loop room floor to 1-RH-MOV-1700 is negligible.

Initiating Cues You have been directed to determine:

1. The maximum time you will have to open 1-RH-MOV-1700 without exceeding your allowable dose.

Surry 2014-301 Obtain Data for EPIP-2.01 Page 1 of 9 U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure G 2.4.39 (RO 3.8 / SRO 3.7)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title Obtain Required information in accordance with EPIP-2.01, Notification of State and Local Governments.

K/A: G2.4.39 - Knowledge of RO responsibilities in emergency plan implementation.

Applicability Estimated Time Actual Time RO/SRO 12 Minutes Conditions Task may be PERFORMED in classroom or Simulator.

A simulated GENERAL EMERGENCY is in progress.

Standards Determines Meteorological data in accordance with EPIP-2.01, Notification of State and Local Governments.

Initiating Cues Nuclear Shift Manager direction.

Terminating Cues EPIP-2.01 steps 16-21 complete.

Procedures EPIP-2.01, Revision 43 Tools and Equipment Safety Considerations None None

Surry 2014-301 Obtain Data for EPIP-2.01 Page 2 of 9 Initial Conditions You are an extra Reactor Operator assisting the shift.

A General Emergency was declared one-half hour ago due to a LBLOCA.

Initial Notifications to the State and Local governments were made on time.

Initial Notification to the NRC was also made on time.

PCS is inoperable.

The Corporate Emergency Response Center reports that their link to our MET tower is inoperable.

Initiating Cues I am the Nuclear Shift Manager and you are the RO / BOP. You are to acquire the following MET data in accordance with EPIP-2.01 and give that information to the State and Local Emergency Communicator.

1) Temperature

2) Average Wind Direction

3) Wind Speed

4) Stability class Notes

Surry 2014-301 Obtain Data for EPIP-2.01 Page 3 of 9 PERFORMANCE CHECKLIST Simulator Set-up Enter the following Meter Overrides for MET PANEL Recorder Name Variable Name Initial Value Final Value Recorder Reading Wind Dir Upper MET_WIND_DIR_UPR 0.6111111 0

0o Wind Dir Lower MET_WIND_DIR_LWR 0.6111111 0

0o Wind Speed Upper MET_WIND_SPD_UPR 0.23 0.5 50 mph Wind Speed Lower MET_WIND_SPD_LWR 0.23 0.2 20 mph Ambient Temp.

MET_TEMP 0.651852 0.763 90 oF Delta Temp MET_DELTAT 1.0 0.22

-1.1 Wind Dir Backup MET_WIND_DIR_BKP 0.611111 0.67 361.8 oF Wind Spd Backup MET_WIND_SPD_BKP 0.23 0.45 45 mph Sigma Theta MET_WIND-MET_SIGMA_THETA 0.28 0.4 20o When complete the Recorders should look as shown below.

Surry 2014-301 Obtain Data for EPIP-2.01 Page 4 of 9 Notes to the Evaluator.

Task critical elements are bolded and denoted by an asterisk (*).

START TIME: _________.

STEP 1:

Determines EPIP-2.01 steps 16 provides procedural guidance for obtaining MET data.

STANDARD:

a) Continuous Action Page directs RO to go to step 16.

EVALUATORS NOTE:

Candidate can also identify step 16 by review of procedure.

COMMENTS:

_______ SAT

_______ UNSAT STEP 2:

Notes: (Prior to Step 16)

Data may be obtained from MET panel charts, PCS, the computer modem or local data logger (Described in 0-AP-20.03, LOSS OF METEOROLOGICAL MONITORING INSTRUMENTATION).

Both the PCS EMCOMM feature and PCS Point Group #39, contains meteorological information averaged over the previous 15 minutes STANDARD:

a) Reads and acknowledges the Notes.

EVALUATORS NOTE:

If asked: PCS is inoperable, you are to use the MET Data Recorder.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 5 of 9 STEP 3:

Check ON-SITE METEOROLOGICAL INFORMATION - AVAILABLE. (Step 16)

STANDARD:

a) Determines that METEOROLOGICAL INFORMATION is available.

b) Initials Step 16.

EVALUATORS NOTE:

If asked: MET information is available on site.

COMMENTS:

_______ SAT

_______ UNSAT STEP 4:

Get current on-site meteorological information as requested. (Step 17)

STANDARD:

a) Candidate may obtain the information in any order.

b) Initials Step 17.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 6 of 9 STEP 5:

Get Temperature from Main Tower Temperature Indicator. (Step 18)

STANDARD:

a) Determines from MET Tower Primary Signal Recorder that Temperature is 90 oF.

b) Records Temperature 90.0 oF on data sheet.

c) Initials Step 18.

EVALUATORS NOTE:

Data sheet is provided to record indications, but candidate can write value on other paper.

COMMENTS:

_______ SAT

_______ UNSAT STEP 6:

Notes: (Prior to Step 19)

Primary source of wind speed is the Main Tower Lower Level indicator.

Alternate sources are (1) Backup Tower, and (2) Main Tower Upper Level.

The Dose Assessment Team may direct the use of meteorological data from the Main Tower Upper Level, based on the nature of the release.

STANDARD:

a) Acknowledges Notes.

EVALUATORS NOTE:

If asked: The Dose Asessment Team has not made any requests.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 7 of 9 STEP 7:

GET WIND SPEED (Step 19)

STANDARD:

a) Determines from MET Tower Primary Signal Recorder that Wind Speed is 20mph.

b) Records Wind Speed 20.0 mph on data sheet.

c) Initials Step 19 EVALUATORS NOTE:

Note prior to Step 19 identifies the correct source for Wind Speed.

Data sheet is provided to record indications, but candidate can write value on other paper COMMENTS:

_______ SAT

_______ UNSAT STEP 7:

Notes: (Prior to Step 20)

An approximate average wind direction for the previous 15 minutes should be determined.

Primary source of wind direction is the Main Tower Lower Level indicator.

Alternate sources are (1) Backup Tower, and (2) Main Tower Upper Level.

STANDARD:

a) Candidate reads and acknowledges Notes.

EVALUATORS NOTE:

If asked: Time Compression: 15 minutes has been met.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 8 of 9 STEP 8:

GET AVERAGE WIND DIRECTION FROM PCS. (Step 20)

STANDARD:

a) Determines PCS is NOT Available.

b) Performs RNO gets Average Wind Direction from MET Recorder.

c) Records Wind Direction 0.0 reading on data sheet.

c) Initials step.

EVALUATORS NOTE:

Note prior to Step 20 identifies Primary source and Alternate source.

Data sheet is provided to record indications, but candidate can write value on other paper.

COMMENTS:

_______ SAT

_______ UNSAT STEP 9:

Notes: (Prior to Step 21)

Main Tower Delta T is the preferred source of stability class. Sigma Theta (Backup Tower) is the secondary source.

The value closer to G should be used if unable to distinguish Delta T or Sigma Theta value.

Numerical ranges presented below for Delta T and Sigma Theta are less than the range of the chart recorder and indicator in the Control Room. Indications are not expected to read outside the ranges found on these tables.

STANDARD:

a) Candidate reads and acknowledges Notes.

EVALUATORS NOTE:

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 9 of 9 STEP 10:

DETERMINE STABILITY CLASS. (Step 21)

STANDARD:

a) Candidate determines Stability class using Delta T. Delta T is -1.1 oF from MET Tower Primary Recorder.

b) Records Stability Class B on data sheet.

c) Initials Step.

EVALUATORS NOTE:

Note prior to step 21 identifies the correct column (Delta T) to use.

Data sheet is provided to record indications, but candidate can write value on other paper.

COMMENTS:

_______ SAT

_______ UNSAT

Surry 2014-301 Obtain Data for EPIP-2.01 Page 10 of 9 STEP 11:

Provides MET data to Emergency Communicator.

Temperature 90.0 oF Wind Speed 20.0 mph Wind Direction 0.0 Stability Class B

STANDARD:

a)

• Provides MET Data as shown above. This is a critical step.

EVALUATORS NOTE:

Accept data as Emergency Communicator COMMENTS:

JPM COMPLETE

_______ SAT

_______ UNSAT STOP TIME: ___________________________

Comments: __________________________________________________________________________________

Surry 2014-301 Obtain Data for EPIP-2.01 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions You are an extra Reactor Operator assisting the shift.

A General Emergency was declared one-half hour ago due to a LBLOCA.

Initial Notifications to the State and Local governments were made on time.

Initial Notification to the NRC was also made on time.

PCS is inoperable.

The Corporate Emergency Response Center reports that their link to our MET tower is inoperable.

Initiating Cues I am the Nuclear Shift Manager and you are the RO / BOP. You are to acquire the following MET data in accordance with EPIP-2.01 and give that information to the State and Local Emergency Communicator.

1) Temperature

2) Average Wind Direction

3) Wind Speed

4) Stability class

Surry 2014-301 Obtain Data for EPIP-2.01 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions You are an extra Reactor Operator assisting the shift.

A General Emergency was declared one-half hour ago due to a LBLOCA.

Initial Notifications to the State and Local governments were made on time.

Initial Notification to the NRC was also made on time.

PCS is inoperable.

The Corporate Emergency Response Center reports that their link to our MET tower is inoperable.

Initiating Cues I am the Nuclear Shift Manager and you are the RO / BOP. You are to acquire the following MET data in accordance with EPIP-2.01 and give that information to the State and Local Emergency Communicator.

1) Temperature

2) Average Wind Direction

3) Wind Speed

4) Stability class Data Sheet Temperature Wind Speed Wind Direction Stability Class

Surry 2014-301 Determine Classification and PAR Page 1 of U.S. Nuclear Regulatory Commission Surry Power Station SR2014301 Administrative Job Performance Measure 2.4.41(RO 2.9 / SRO 3.7)

Applicant________________________________

Start Time___________________

Examiner_______________________________

Date ___________________________________

Stop Time___________________

Title CLASSIFY AN EVENT AND DETERMINE THE REQUIRED PAR ACTIONS K/A: G2.4.41 - Knowledge of the emergency action level thresholds and classifications. (2.9/4.6)

Applicability Est Completion Time Actual Time SRO ONLY 20 Minutes (Portions **TC**)

Conditions Task is to be PERFORMED in the SIMULATOR or CLASSROOM.

A simulated GENERAL EMERGENCY is in progress.

Standards Evaluate a given set of plant conditions and determine that a General Emergency exists in accordance with EPIP-1.01 and the EAL table, and then determine that the appropriate PAR for that General Emergency is PAR B.

Initiating Cues Significant event notification.

EPIP-1.01, Emergency Manager Controlling Procedure.

Terminating Cues EPIP-1.06, Step 8 Completed.

Procedures EPIP-1.01, Emergency Manager Controlling Procedure, Revision 56.

EPIP-1.06, Protective Action Recommendations, Revision 10.

Tools and Equipment Safety Considerations None None

Surry 2014-301 Determine Classification and PAR Page 2 of MAKE SURE YOU PROVIDE THE CORRECT CUE SHEET (PAGE 1, LAST PAGE OF THIS JPM) FOR THE PORTION OF THE TASK TO BE PERFORMED!!!!

Initial Conditions You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The station has experienced a loss of offsite power due to grid collapse. The system operator reports 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for power restoration to Surrys switchyard.

Both units are currently at Hot Shutdown.

When attempting to load the AAC diesel on the 1J bus, the 1J bus faulted and electricians have determined that extensive damage has occurred to the buswork with repairs estimated to take 4 days.

1. 1 EDG tripped on overspeed during start-up. Mechanics reset the overspeed, and when started, the diesel experienced extremely high vibrations and casing penetration by a piston, and was subsequently tripped locally.

All radiation monitors indicate pre-event radiation levels.

Unit 1 team is currently performing the actions of ECA-0.0, Loss of All AC power.

Unit 2 team is completing the actions of ES-0.1, Reactor Trip Response.

Initiating Cues Here is a copy of EPIP 1.01, you are directed to classify this event in accordance with EPIP-1.01 and inform me of your classification as soon as it has been made.

This portion of the JPM is TIME CRITICAL.

Surry 2014-301 Determine Classification and PAR Page 1 of 18 Performance Checklist Notes to the Evaluator.

Task critical elements are denoted by an asterisk (*). If substeps of a critical element also have an asterisk (*),

then only those asterisked substeps are critical to performance of that task element.

Critical step sequencing requirements: 1 before 3.

START TIME: _________

Evaluators note-candidate may choose to make EAL classification straight from EAL tables and NOT implement steps of EPIP-1.01. Steps are given here as guidance.

Critical task time ends when classification determined regardless of determination method.

Caution and Note prior to step 1.

CAUTION: Declaration of the highest emergency class for which an Emergency Action Level is exceeded shall be made.

NOTE:

The PCS is potentially unreliable in the event of an earthquake. Therefore, PCS parameters should be evaluated for accuracy should an earthquake occur.

Standards (a)

Acknowledges CAUTION and NOTE Evaluators Note Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 2 of 18 EAL STEP 1:

EVALUATE EMERGENCY ACTION LEVELS:

a) Determine event category using the applicable Emergency Action Level Matrix:

Hot Conditions (RCS > 200 °F)

Cold Conditions (RCS 200 °F) b) Review EAL associated with event category c) Use Control Room monitors, PCS, and outside reports to get indications of emergency conditions listed in the EAL Matrix d) Verify EAL - CURRENTLY EXCEEDED e) Initiate a chronological log of events Standards (a)

Refers to the HOT chart (b)

Determines event category to be Loss of Power.

(c)

Refers to given conditions to determine EAL applicability (d)

DETERMINES EAL SG1.1 GENERAL EMERGENCY to be met.

(e)

Initiates (or verbalizes) a chronological log of events.

Evaluators Note: If candidate makes EAL determination at this step, record stop time.

Evaluator's Comments STOP TIME: ___________

TIME CRITIAL-15 minutes

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 3 of 18 EAL Step 2:

RECORD EAL IDENTIFIER, TIME EMERGENCY DECLARED AND SM/SEM NAME.

Standards (a)

Determines that event is a General Emergency based on EAL SG1.1 (Loss of all offsite and onsite power to Unit 1 Emergency Busses H and J-This is a critical step.

(b)

Classifies event as a GENERAL EMERGENCY-This is a critical step.

Evaluators Note: If candidate makes EAL determination at this step, record stop time.

Evaluator's Comments STOP TIME: ___________

TIME CRITIAL-15 minutes

_______ SAT

_______ UNSAT EAL Step 3:

ANNOUNCE THE FOLLOWING DECLARATIONS:

Station Emergency Manager position Emergency Classification EAL Time Declared Standards (a)

Makes announcement Evaluators Note If candidate makes incorrect classification end the JPM at this point.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 4 of 18 EVALUATOR:

Take EPIP-1.01 into your possession at this time.

HANDOUT PAGE 2 of OPERATOR INSTRUCTIONS AT THIS TIME.

Initial Conditions A simulated GENERAL EMERGENCY is in progress.

You are the Nuclear Shift Manager. A GENERAL EMERGENCY has been declared on SG1.1.

EPIP-1.05, Response to General Emergency, Step 3 has been completed.

The State and Local Communicator has determined wind direction to be (from) 180° and speed to be 17 mph.

There are no known impediments making evacuation dangerous.

A dose assessment has not been made.

All available radiation monitors indicate pre-event trends.

Initiating Cues Here's a copy of EPIP-1.06, Protective Action Recommendations. You are to complete EPIP-1.06, Protective Action Recommendations in its entirety.

When you finish the actions necessary to accomplish this, please inform me.

This portion of the JPM is TIME CRITICAL.

Notes to the Evaluator.

TIME CRITICAL REQUIREMENT:

This PAR must be identified and relayed to S&L communicators within 15 minutes.

START TIME:

PAR Step 1:

Procedure Step 1 INITIATE PROCEDURE.

Standards Fills in Name, Time and Date on Step 1.

Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 2:

Procedure Step 1 USE ATTACHMENT 1, PROTECTIVE ACTION RECOMMENDATION MATRIX, TO DETERMINE INITIAL PAR Standards (a)

Goes to Attachment 1.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 5 of 18 PAR Step 3:

- Flowchart block 1-Known impediments make evacuation dangerous.

Standards

- Determines there are no known impediments that make evacuation dangerous.

Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 4:

- Flowchart block 2-Radiological release in progress or has occurred related to the event. (YES or NO).

Standards

- Determines that no radiological release in progress.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 6 of 18 PAR Step 5:

- Flowchart-Evacuate 2 miles radius and 5 miles downwind.

Standards Determines that PAR B is required-This is a critical step.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 7 of 18 PAR Step 6 Evaluators note - Candidate will now return to step 3 of the procedure (attachment 1 items complete)

Notes prior to step 3-ATTACHMENT 2, AFFECTED SECTOR(S) MAP, is to be used for all PAR developments from this procedure. ATTACHMENT 2, AFFECTED SECOTR(S) MAP is not to be used for PARs developed IAW EPIP-4.07, PROTECTECTIVE MEASURES.

Standards

- Acknowledges notes CUES

- None Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 7 Procedure Step 3 IMPLEMENT ATTACHMENT 2, AFFECTED SECTOR(S) MAP:

a) Record time wind data acquired.

b) Record average wind direction from, in degrees and compass point.

c) Record average wind speed in mph.

d) Record affected sectors.

e) Mark affected sectors on map (use any writing implement available, e.g.,

pen, pencil, highlighter etc.)

f)

GO TO Step 6 Standards Completes attachment 2 as follows:

• At (now) wind direction from 180° (S), Wind Speed 17 mph, Sectors RAB.

- Using attachment 5 (as per the note), determines that affected sectors are R, A, B.

CUES

- If asked: Met data obtained at JPM start time.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 8 of 18 PAR Step 8 Procedure Step 6 COMPLETE ATTACHMENT 3, PROTECTIVE ACTION RECOMMENDATION FORM:

a) Protective Action Recommendation:

1) Mark appropriate PAR box(s)

2) Record Mile radius and Miles downwind

3) Record Downwind Sectors b) Remarks/Approval Information:

1) Record Remarks (optional)

2) Approve PAR (sign report)

3) Record date and time report approved Standards Completes item 1 of attachment 3 by marking EVACUATE 2 mile radius (360°) and 5 miles downwind in the following sectors R, A, B -

this is a critical step.

Completes item 2 by signing and entering the current time and date.

Evaluators Note None CUES If asked: None Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 9 of 18 PAR Step 9 Procedure Step 7 - HAVE EMERGENCY COMMUNICATORS NOTIFY OFF-SITE AUTHORITIES OF PAR:

Virginia Emergency Operations Center notified IAW:

EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS OR EPIP-4.07, PROTECTIVE MEASURES NRC notified IAW EPIP-2.02, NOTIFICATION OF NRC (notification made from Control Room or TSC, when activated)

NRC notified IAW EPIP-4.33, HEALTH PHYSICS NETWORK COMMUNICATIONS (notifications made from TSC or LEOF/CEOF only after NRC requests HPN be established)

Standards (a)

Directs State and Local EC to notify Virginia EOC - this is a critical step.

(b)

Directs NRC EC.

CUES Tell SRO: State and Local EC will transmit PAR to Virginia EOC.

Tell SRO: NRC EC will notify NRC of PAR.

If asked: HPN has not been requested yet.

Evaluator's Note This step must be complete within 15 minutes of start of task.

Record Time: ______

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 10 of 18 PAR Step 10 Procedure Step 8 -

CHECK IF CURRENT PROTECTIVE ACTION RECOMMENDATION - INITIAL PAR.

Standards Determines this is current PAR from CUES If Asked: This is the initial PAR.

Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 11 Procedure Step 9 -

HAVE RADIOLOGICAL ASSESSMENT DIRECTOR (RAD) IMPLEMENT EPIP-4.07, PROTECTIVE MEASURES [RADIOLOGICAL ASSESSMENT COORDINATOR (RAC) IF IN LEOF/CEOF]

Standards Tells Evaluator to Initiate EPIP-4.07.

CUES Tell SRO: EPIP-4.07 has been initiated.

Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 12 CAUTION prior to step 10 Previously issued Protective Action Recommendations should not be reduced until the threat is fully under control and after consulting with Commonwealth of Virginia emergency response organization Standards SRO Acknowledges the Caution.

CUES Evaluator's Comments

_______ SAT

_______ UNSAT PAR Step 13 NOTE prior to step 10

_______ SAT

Surry 2014-301 Determine Classification and PAR Page 11 of 18 A Shelter-in-Place recommendation may supersede a Radiological Evacuation recommendation based on known impediments.

Standards SRO Acknowledges the Note.

CUES Evaluator's Comments

_______ UNSAT PAR Step 14 Procedure Step 10 Standards (a)

Determines that no conditions at this time necessitate a change to the current PAR.

CUES If asked: HP does not recommend a radiological based PAR or implementation of Potassium Iodide strategies.

If asked: Met data remains as previously reported.

Evaluator's Comments

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 12 of 18 PAR Step 15 Procedure Step 11 - CHECK EMERGENCY - TERMINATED Standards (a)

Asks Evaluator if Emergency is terminated.

(b)

Asks Evaluator if RAD/RAC recommends a PAR change.

(c)

Determines Procedure is completed until conditions change.

CUES If asked: Emergency classification is still in effect.

If asked: RAD/RAC does not recommend a PAR change at this time.

Evaluator's Comments STOP TIME:

_______ SAT

_______ UNSAT

Surry 2014-301 Determine Classification and PAR Page 13 of 18 KEY

Surry 2014-301 Determine Classification and PAR Page 14 of 18 Evaluator's Summary CLASSIFY AN EVENT AND DETERMINE THE REQUIRED PAR ACTIONS

Surry 2014-301 Determine Classification and PAR Page 15 of 18 PAGE 1 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Directions The evaluator will explain the initial conditions of the task to be performed and will provide the initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.

Initial Conditions You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The station has experienced a loss of offsite power due to grid collapse. The system operator reports 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for power restoration to Surrys switchyard.

Both units are currently at Hot Shutdown.

When attempting to load the AAC diesel on the 1J bus, the 1J bus faulted and electricians have determined that extensive damage has occurred to the buswork with repairs estimated to take 4 days.

1. 1 EDG tripped on overspeed during start-up. Mechanics reset the overspeed, and when started, the diesel experienced extremely high vibrations and casing penetration by a piston, and was subsequently tripped locally.

All radiation monitors indicate pre-event radiation levels.

Unit 1 team is currently performing the actions of ECA-0.0, Loss of All AC power.

Unit 2 team is completing the actions of ES-0.1, Reactor Trip Response.

Initiating Cues Here is a copy of EPIP 1.01, you are directed to classify this event in accordance with EPIP-1.01 and inform me of your classification as soon as it has been made.

This portion of the JPM is TIME CRITICAL.

Surry 2014-301 Determine Classification and PAR Page 16 of 18 PAGE 2 Operator Directions Handout (TO BE READ TO APPLICANT BY EXAMINER)

Initial Conditions A simulated GENERAL EMERGENCY is in progress.

You are the Nuclear Shift Manager. A GENERAL EMERGENCY has been declared on SG1.1.

EPIP-1.05, Response to General Emergency, Step 3 has been completed.

The State and Local Communicator has determined wind direction to be (from) 180° and speed to be 17 mph.

There are no known impediments making evacuation dangerous.

A dose assessment has not been made.

All available radiation monitors indicate pre-event trends.

Initiating Cues Here's a copy of EPIP-1.06, Protective Action Recommendations. You are to complete EPIP-1.06, Protective Action Recommendations in its entirety.

When you finish the actions necessary to accomplish this, please inform me.

This portion of the JPM is TIME CRITICAL.

PAGE 2 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions

• A simulated GENERAL EMERGENCY is in progress.

You are the Nuclear Shift Manager. A GENERAL EMERGENCY has been declared on SG1.1.

EPIP-1.05, Response to General Emergency, Step 3 has been completed.

The State and Local Communicator has determined wind direction to be (from) 180° and speed to be 17 mph.

There are no known impediments making evacuation dangerous.

A dose assessment has not been made.

All available radiation monitors indicate pre-event trends.

Initiating Cues Here's a copy of EPIP-1.06, Protective Action Recommendations. You are to complete EPIP-1.06, Protective Action Recommendations in its entirety.

When you finish the actions necessary to accomplish this, please inform me.

• This portion of the JPM is TIME CRITICAL.

PAGE 1 Operator Directions Handout (TO BE GIVEN TO APPLICANT)

Initial Conditions You are the Nuclear Shift Manager. An event is in progress with plant conditions as follows:

The station has experienced a loss of offsite power due to grid collapse. The system operator reports 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for power restoration to Surrys switchyard.

Both units are currently at Hot Shutdown.

When attempting to load the AAC diesel on the 1J bus, the 1J bus faulted and electricians have determined that extensive damage has occurred to the buswork with repairs estimated to take 4 days.

1. 1 EDG tripped on overspeed during start-up. Mechanics reset the overspeed, and when started, the diesel experienced extremely high vibrations and casing penetration by a piston, and was subsequently tripped locally.

All radiation monitors indicate pre-event radiation levels.

Unit 1 team is currently performing the actions of ECA-0.0, Loss of All AC power.

Unit 2 team is completing the actions of ES-0.1, Reactor Trip Response.

Initiating Cues Here is a copy of EPIP 1.01, you are directed to classify this event in accordance with EPIP-1.01 and inform me of your classification as soon as it has been made.

This portion of the JPM is TIME CRITICAL