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 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 Page 1 of 9

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

Surry 2014-301 Quadrant Power Tilt Calculation 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. _______ SAT Calculations for QPTR should be carried out to four places to the right of the _______ UNSAT decimal place to provide accuracy and consistency of results.

STEP 2: [Step 1, Att. 6] _______ SAT a) Record Reactor Power, Date, and Time in appropriate blocks.

b) Initials Step 1. _______ UNSAT 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:

STEP 3: [Step 2, Att. 6] _______ SAT a) Transcribes information from data sheets onto 0-AP-1.00, Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios, Step 2 Table. _______ UNSAT STANDARD:

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

COMMENTS:

Page 3 of 9

Surry 2014-301 Quadrant Power Tilt Calculation STEP 4: [STEP 3, Att. 6] _______ SAT a) Performs calculations to obtain normalized values for Upper Detectors.

_______ UNSAT 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:

STEP 5: [STEP 3, Att. 6] _______ SAT a) Performs calculations to obtain Sum of normalized values for Upper Detectors. _______ UNSAT 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:

STEP 6: [STEP 3, Att. 6] _______ SAT a) Performs calculations to obtain normalized values for Lower Detectors.

_______ UNSAT 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:

Page 4 of 9

Surry 2014-301 Quadrant Power Tilt Calculation STEP 7: [Step 3, Att. 6] _______ SAT a) Performs calculations to obtain Sum of normalized values for Lower Detectors. _______ UNSAT 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:

STEP 8: [Step 4, Att. 6] _______ SAT a) Records the Number of Detectors in use.

b) Initials Step 4. _______ UNSAT 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:

STEP 9: [Step 5, Att. 6] _______ SAT a) Calculates the average upper and lower detector current values.

_______ UNSAT 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:

Page 5 of 9

Surry 2014-301 Quadrant Power Tilt Calculation STEP 10: [Step 6, Att. 6] _______ SAT a) From Step 3, Record the following values.

_______ UNSAT 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:

STEP 11: [Step 7, Att. 6] _______ SAT a) Calculates the maximum upper and lower Excore Quadrant Power Tilt Ratios.

_______ UNSAT 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:

STEP 12: [Step 8, Att. 6] _______ SAT a) Calculates Tilt %.

_______ UNSAT 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:

Page 6 of 9

Surry 2014-301 Quadrant Power Tilt Calculation STEP 13: Determines final Quadrant Power Tilt Value. _______ SAT STANDARD: _______ UNSAT

• 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:

STOP TIME:

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

Page 7 of 9

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 I (Top) I (Bottom) I (Top) I (Bottom) I (Top) I (Bottom) I (Top) I (Bottom)

FLUX @ µamps µamps µamps µamps µamps µamps µamps µamps 100%

0 118.8 119.5 118.5 119.3 119.1 119.5 119.1 119.5 DELTA I (Top) I (Bottom) I (Top) I (Bottom) I (Top) I (Bottom) I (Top) I (Bottom)

FLUX @ µamps µamps µamps µamps µamps µamps µamps µamps 120%

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 LaFrance Davis 7/21/14 Performed / Verified By: __________/ __________ Date: _______

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 o

RCS temperatures are below 140 F.

• 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. _______ SAT

_______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 2: _______ SAT Radiation Monitors Operable: _______ UNSAT

• 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:

Surry 2014-301 Auth Fuel Move STEP 3: _______ SAT Source Range Detectors (audible indication in CTMT must be verified operable) _______ UNSAT

• 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:

STEP 4: _______ SAT Cavity level > 23 feet. _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 5: _______ SAT RHR pump and Heat Exchanger: _______ UNSAT 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:

STEP 6: _______ SAT Direct communication between the Control Room and Manipulator Crane _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 7: _______ SAT RCS Boron concentration- 2350 PPM (Admin limit) _______ UNSAT 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:

STEP 8: _______ SAT RHR Temperature: 140 °F _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 9: _______ SAT Reactor shutdown greater than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 10: _______ SAT Control Room and Relay Room Emergency Ventilation- 2 Trains _______ UNSAT 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:

STEP 11: _______ SAT Control Room Chillers- 3 minimum _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 12: _______ SAT MCR/ESGR AHU- 8 minimum _______ UNSAT 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:

STEP 13: _______ SAT 120 Volt Vital Buses- 2 minimum _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 14: _______ SAT SFP Cooling- 1 train available _______ UNSAT 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:

STEP 16: _______ SAT SFP makeup borated water source- 1 source available _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 17: _______ SAT Reports to Shift Manager that task is complete _______ UNSAT 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:

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 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 Page 1 of 10

Surry 2014-301 OPT Review 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.

Page 2 of 14

Surry 2014-301 OPT Review 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. _______ SAT

_______ UNSAT 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:

Page 3 of 14

Surry 2014-301 OPT Review STEP 2: Reviews Initial Conditions and Precautions and Limitations. _______ SAT STANDARD: _______ UNSAT

• Identifies Initial Condition 3.1 initialed.

• Identifies Precautions and limitations 4.1 through 4.5 initialed.

EVALUATOR NOTES: NONE COMMENTS:

STEP 3: Reviews section 6.1, Work Preparation, of section 6.0, INSTRUCTIONS. _______ SAT STANDARD: _______ UNSAT

• Identifies correct use of N/A for Step 6.1.1.

EVALUATOR NOTES: NONE COMMENTS:

STEP 4: Reviews section 6.2, Testing 1-FW-MOV-151E, SG A AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

Page 4 of 14

Surry 2014-301 OPT Review STEP 5: Reviews section 6.3, Testing 1-FW-MOV-151F, SG A AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

STEP 6: Reviews section 6.4, Testing 1-FW-MOV-151C, SG B AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

Page 5 of 14

Surry 2014-301 OPT Review STEP 7: Reviews section 6.5, Testing 1-FW-MOV-151D, SG B AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

STEP 8: Reviews section 6.6, Testing 1-FW-MOV-151A, SG C AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

Page 6 of 14

Surry 2014-301 OPT Review STEP 9: Reviews section 6.7, Testing 1-FW-MOV-151B, SG C AFW Flow Isol.

_______ SAT STANDARD:

_______ UNSAT 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:

STEP 10: reviews Section 7.0 Follow-On.

_______ SAT STANDARD: _______ UNSAT

• Verifies Step 7.1.1 initialed.

• Verifies Step 7.1.2 initialed.

• Verifies Satisfactory checked.

EVALUATOR NOTES: NONE COMMENTS:

Page 7 of 14

Surry 2014-301 OPT Review STEP 11: Reviews Section 7.2 Follow-On Tasks.

_______ SAT STANDARD:

_______ UNSAT

• 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:

STEP 12: Reviews Section 7.3 Notification, Documentation, and Procedure Closeout. _______ SAT STANDARD: _______ UNSAT

• 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:

STOP TIME: ________

Notes:

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

Page 8 of 14

Surry 2014-301 OPT Review 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.

Page 9 of 14

Surry 2014-301 OPT Review 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.

Page 10 of 14

Surry 2014-301 OPT Review 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.

Page 11 of 14

Surry 2014-301 OPT Review 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?

Page 12 of 14

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.

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 1 of 5

Surry 2014-301 Emerg Exposure Auth.

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.

2 of 5

Surry 2014-301 Emerg Exposure Auth.

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:

_______ SAT AUTHORIZES EMERGENCY EXPOSURE:

_______ UNSAT 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:

STEP 2:

Report completion of Task.

COMMENTS:

• • JPM COMPLETE **

STOP TIME: ___________________________

Comments: __________________________________________________________________________________

3 of 5

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 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.

Page 1 of 9

Surry 2014-301 Calculate Rad Dose

• 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 Page 2 of 9

Surry 2014-301 Calculate Rad Dose 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:

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

_______ UNSAT 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:

STEP 2:

_______ SAT Calculate remaining allowable exposure at valve.

_______ UNSAT 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:

Page 3 of 9

Surry 2014-301 Calculate Rad Dose STEP 3:

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

_______ UNSAT 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:

STOP TIME:

Page 4 of 9

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 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 Page 1 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 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 Page 2 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 PERFORMANCE CHECKLIST Simulator Set-up

• Enter the following Meter Overrides for MET PANEL Recorder Name Variable Name Initial Value Final Value Recorder Reading o

Wind Dir Upper MET_WIND_DIR_UPR 0.6111111 0 0 o

Wind Dir Lower MET_WIND_DIR_LWR 0.6111111 0 0 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 o

Ambient Temp. MET_TEMP 0.651852 0.763 90 F Delta Temp MET_DELTAT 1.0 0.22 -1.1 o

Wind Dir Backup MET_WIND_DIR_BKP 0.611111 0.67 361.8 F Wind Spd Backup MET_WIND_SPD_BKP 0.23 0.45 45 mph o

Sigma Theta MET_WIND- MET_SIGMA_THETA 0.28 0.4 20 When complete the Recorders should look as shown below.

Page 3 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 Notes to the Evaluator.

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

• START TIME: _________.

STEP 1:

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

_______ UNSAT 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:

STEP 2:

Notes: (Prior to Step 16) _______ SAT

• 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 _______ UNSAT 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:

Page 4 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 STEP 3:

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

_______ UNSAT STANDARD:

a) Determines that METEOROLOGICAL INFORMATION is available.

b) Initials Step 16.

EVALUATORS NOTE:

If asked: MET information is available on site.

COMMENTS:

STEP 4:

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

_______ UNSAT STANDARD:

a) Candidate may obtain the information in any order.

b) Initials Step 17.

COMMENTS:

Page 5 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 STEP 5:

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

_______ UNSAT STANDARD:

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

o b) Records Temperature 90.0 F 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:

STEP 6:

_______ SAT Notes: (Prior to Step 19)

_______ UNSAT

• 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:

Page 6 of 9

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

_______ SAT GET WIND SPEED (Step 19)

_______ UNSAT 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:

STEP 7:

_______ SAT Notes: (Prior to Step 20)

• An approximate average wind direction for the previous 15 minutes should be _______ UNSAT 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:

Page 7 of 9

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

_______ SAT GET AVERAGE WIND DIRECTION FROM PCS. (Step 20)

_______ UNSAT 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:

STEP 9:

_______ SAT Notes: (Prior to Step 21)

• Main Tower Delta T is the preferred source of stability class. Sigma Theta _______ UNSAT (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:

Page 8 of 9

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

_______ SAT DETERMINE STABILITY CLASS. (Step 21)

_______ UNSAT STANDARD:

o a) Candidate determines Stability class using Delta T. Delta T is -1.1 F 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:

Page 9 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 STEP 11:

_______ SAT Provides MET data to Emergency Communicator.

_______ UNSAT 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 **

STOP TIME: ___________________________

Comments: __________________________________________________________________________________

Page 10 of 9

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 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 Page 1 of

Surry 2014-301 Determine Classification and PAR 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 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.

Page 2 of

Surry 2014-301 Determine Classification and PAR 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 _______ SAT 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 _______ UNSAT 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 Page 1 of 18

Surry 2014-301 Determine Classification and PAR EAL STEP 1: _______ SAT EVALUATE EMERGENCY ACTION LEVELS: _______ UNSAT 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 Page 2 of 18

Surry 2014-301 Determine Classification and PAR EAL Step 2: _______ SAT RECORD EAL IDENTIFIER, TIME EMERGENCY DECLARED AND SM/SEM NAME. _______ UNSAT 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 EAL Step 3: _______ SAT ANNOUNCE THE FOLLOWING DECLARATIONS: _______ UNSAT

• 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 Page 3 of 18

Surry 2014-301 Determine Classification and PAR 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:

_______ SAT Procedure Step 1

_______ UNSAT INITIATE PROCEDURE.

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

Evaluator's Comments PAR Step 2:

_______ SAT Procedure Step 1

_______ UNSAT USE ATTACHMENT 1, PROTECTIVE ACTION RECOMMENDATION MATRIX, TO DETERMINE INITIAL PAR Standards (a) Goes to Attachment 1.

Evaluator's Comments Page 4 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 3: _______ SAT Attachment 1 - Flowchart block 1- _______ UNSAT Known impediments make evacuation dangerous.

Standards

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

Evaluator's Comments PAR Step 4: _______ SAT Attachment 1 - Flowchart block 2- _______ UNSAT 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 Page 5 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 5:

_______ SAT Attachment 1 - Flowchart-

_______ UNSAT Evacuate 2 miles radius and 5 miles downwind.

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

Evaluator's Comments Page 6 of 18

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

_______ UNSAT 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 PAR Step 7

_______ SAT Procedure Step 3

_______ UNSAT 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 Page 7 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 8

_______ SAT Procedure Step 6 COMPLETE ATTACHMENT 3, PROTECTIVE ACTION RECOMMENDATION FORM: _______ UNSAT 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 Page 8 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 9

_______ SAT Procedure Step 7 - HAVE EMERGENCY COMMUNICATORS NOTIFY OFF-SITE AUTHORITIES OF PAR: _______ UNSAT

- 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 Page 9 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 10

_______ SAT Procedure Step 8 -

_______ UNSAT 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 PAR Step 11

_______ SAT Procedure Step 9 -

_______ UNSAT 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 PAR Step 12

_______ SAT CAUTION prior to step 10

_______ UNSAT 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 PAR Step 13

_______ SAT NOTE prior to step 10 Page 10 of 18

Surry 2014-301 Determine Classification and PAR

_______ UNSAT A Shelter-in-Place recommendation may supersede a Radiological Evacuation recommendation based on known impediments.

Standards SRO Acknowledges the Note.

CUES Evaluator's Comments PAR Step 14

_______ SAT Procedure Step 10

_______ UNSAT 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 Page 11 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 15

_______ SAT Procedure Step 11 - CHECK EMERGENCY - TERMINATED

_______ UNSAT 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:

Page 12 of 18

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

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

Surry 2014-301 Determine Classification and PAR 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 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.

Page 15 of 18

Surry 2014-301 Determine Classification and PAR 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 16 of 18

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 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 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 Page 1 of 9

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

Surry 2014-301 Quadrant Power Tilt Calculation 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. _______ SAT Calculations for QPTR should be carried out to four places to the right of the _______ UNSAT decimal place to provide accuracy and consistency of results.

STEP 2: [Step 1, Att. 6] _______ SAT a) Record Reactor Power, Date, and Time in appropriate blocks.

b) Initials Step 1. _______ UNSAT 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:

STEP 3: [Step 2, Att. 6] _______ SAT a) Transcribes information from data sheets onto 0-AP-1.00, Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios, Step 2 Table. _______ UNSAT STANDARD:

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

COMMENTS:

Page 3 of 9

Surry 2014-301 Quadrant Power Tilt Calculation STEP 4: [STEP 3, Att. 6] _______ SAT a) Performs calculations to obtain normalized values for Upper Detectors.

_______ UNSAT 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:

STEP 5: [STEP 3, Att. 6] _______ SAT a) Performs calculations to obtain Sum of normalized values for Upper Detectors. _______ UNSAT 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:

STEP 6: [STEP 3, Att. 6] _______ SAT a) Performs calculations to obtain normalized values for Lower Detectors.

_______ UNSAT 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:

Page 4 of 9

Surry 2014-301 Quadrant Power Tilt Calculation STEP 7: [Step 3, Att. 6] _______ SAT a) Performs calculations to obtain Sum of normalized values for Lower Detectors. _______ UNSAT 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:

STEP 8: [Step 4, Att. 6] _______ SAT a) Records the Number of Detectors in use.

b) Initials Step 4. _______ UNSAT 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:

STEP 9: [Step 5, Att. 6] _______ SAT a) Calculates the average upper and lower detector current values.

_______ UNSAT 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:

Page 5 of 9

Surry 2014-301 Quadrant Power Tilt Calculation STEP 10: [Step 6, Att. 6] _______ SAT a) From Step 3, Record the following values.

_______ UNSAT 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:

STEP 11: [Step 7, Att. 6] _______ SAT a) Calculates the maximum upper and lower Excore Quadrant Power Tilt Ratios.

_______ UNSAT 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:

STEP 12: [Step 8, Att. 6] _______ SAT a) Calculates Tilt %.

_______ UNSAT 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:

Page 6 of 9

Surry 2014-301 Quadrant Power Tilt Calculation STEP 13: Determines final Quadrant Power Tilt Value. _______ SAT STANDARD: _______ UNSAT

• 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:

STOP TIME:

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

Page 7 of 9

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 I (Top) I (Bottom) I (Top) I (Bottom) I (Top) I (Bottom) I (Top) I (Bottom)

FLUX @ µamps µamps µamps µamps µamps µamps µamps µamps 100%

0 118.8 119.5 118.5 119.3 119.1 119.5 119.1 119.5 DELTA I (Top) I (Bottom) I (Top) I (Bottom) I (Top) I (Bottom) I (Top) I (Bottom)

FLUX @ µamps µamps µamps µamps µamps µamps µamps µamps 120%

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 LaFrance Davis 7/21/14 Performed / Verified By: __________/ __________ Date: _______

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 o

RCS temperatures are below 140 F.

• 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. _______ SAT

_______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 2: _______ SAT Radiation Monitors Operable: _______ UNSAT

• 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:

Surry 2014-301 Auth Fuel Move STEP 3: _______ SAT Source Range Detectors (audible indication in CTMT must be verified operable) _______ UNSAT

• 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:

STEP 4: _______ SAT Cavity level > 23 feet. _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 5: _______ SAT RHR pump and Heat Exchanger: _______ UNSAT 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:

STEP 6: _______ SAT Direct communication between the Control Room and Manipulator Crane _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 7: _______ SAT RCS Boron concentration- 2350 PPM (Admin limit) _______ UNSAT 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:

STEP 8: _______ SAT RHR Temperature: 140 °F _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 9: _______ SAT Reactor shutdown greater than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 10: _______ SAT Control Room and Relay Room Emergency Ventilation- 2 Trains _______ UNSAT 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:

STEP 11: _______ SAT Control Room Chillers- 3 minimum _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 12: _______ SAT MCR/ESGR AHU- 8 minimum _______ UNSAT 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:

STEP 13: _______ SAT 120 Volt Vital Buses- 2 minimum _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 14: _______ SAT SFP Cooling- 1 train available _______ UNSAT 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:

STEP 16: _______ SAT SFP makeup borated water source- 1 source available _______ UNSAT 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:

Surry 2014-301 Auth Fuel Move STEP 17: _______ SAT Reports to Shift Manager that task is complete _______ UNSAT 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:

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 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 Page 1 of 10

Surry 2014-301 OPT Review 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.

Page 2 of 14

Surry 2014-301 OPT Review 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. _______ SAT

_______ UNSAT 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:

Page 3 of 14

Surry 2014-301 OPT Review STEP 2: Reviews Initial Conditions and Precautions and Limitations. _______ SAT STANDARD: _______ UNSAT

• Identifies Initial Condition 3.1 initialed.

• Identifies Precautions and limitations 4.1 through 4.5 initialed.

EVALUATOR NOTES: NONE COMMENTS:

STEP 3: Reviews section 6.1, Work Preparation, of section 6.0, INSTRUCTIONS. _______ SAT STANDARD: _______ UNSAT

• Identifies correct use of N/A for Step 6.1.1.

EVALUATOR NOTES: NONE COMMENTS:

STEP 4: Reviews section 6.2, Testing 1-FW-MOV-151E, SG A AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

Page 4 of 14

Surry 2014-301 OPT Review STEP 5: Reviews section 6.3, Testing 1-FW-MOV-151F, SG A AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

STEP 6: Reviews section 6.4, Testing 1-FW-MOV-151C, SG B AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

Page 5 of 14

Surry 2014-301 OPT Review STEP 7: Reviews section 6.5, Testing 1-FW-MOV-151D, SG B AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

STEP 8: Reviews section 6.6, Testing 1-FW-MOV-151A, SG C AFW Flow Isol. _______ SAT STANDARD: _______ UNSAT 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:

Page 6 of 14

Surry 2014-301 OPT Review STEP 9: Reviews section 6.7, Testing 1-FW-MOV-151B, SG C AFW Flow Isol.

_______ SAT STANDARD:

_______ UNSAT 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:

STEP 10: reviews Section 7.0 Follow-On.

_______ SAT STANDARD: _______ UNSAT

• Verifies Step 7.1.1 initialed.

• Verifies Step 7.1.2 initialed.

• Verifies Satisfactory checked.

EVALUATOR NOTES: NONE COMMENTS:

Page 7 of 14

Surry 2014-301 OPT Review STEP 11: Reviews Section 7.2 Follow-On Tasks.

_______ SAT STANDARD:

_______ UNSAT

• 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:

STEP 12: Reviews Section 7.3 Notification, Documentation, and Procedure Closeout. _______ SAT STANDARD: _______ UNSAT

• 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:

STOP TIME: ________

Notes:

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

Page 8 of 14

Surry 2014-301 OPT Review 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.

Page 9 of 14

Surry 2014-301 OPT Review 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.

Page 10 of 14

Surry 2014-301 OPT Review 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.

Page 11 of 14

Surry 2014-301 OPT Review 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?

Page 12 of 14

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.

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 1 of 5

Surry 2014-301 Emerg Exposure Auth.

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.

2 of 5

Surry 2014-301 Emerg Exposure Auth.

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:

_______ SAT AUTHORIZES EMERGENCY EXPOSURE:

_______ UNSAT 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:

STEP 2:

Report completion of Task.

COMMENTS:

• • JPM COMPLETE **

STOP TIME: ___________________________

Comments: __________________________________________________________________________________

3 of 5

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 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.

Page 1 of 9

Surry 2014-301 Calculate Rad Dose

• 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 Page 2 of 9

Surry 2014-301 Calculate Rad Dose 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:

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

_______ UNSAT 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:

STEP 2:

_______ SAT Calculate remaining allowable exposure at valve.

_______ UNSAT 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:

Page 3 of 9

Surry 2014-301 Calculate Rad Dose STEP 3:

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

_______ UNSAT 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:

STOP TIME:

Page 4 of 9

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 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 Page 1 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 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 Page 2 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 PERFORMANCE CHECKLIST Simulator Set-up

• Enter the following Meter Overrides for MET PANEL Recorder Name Variable Name Initial Value Final Value Recorder Reading o

Wind Dir Upper MET_WIND_DIR_UPR 0.6111111 0 0 o

Wind Dir Lower MET_WIND_DIR_LWR 0.6111111 0 0 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 o

Ambient Temp. MET_TEMP 0.651852 0.763 90 F Delta Temp MET_DELTAT 1.0 0.22 -1.1 o

Wind Dir Backup MET_WIND_DIR_BKP 0.611111 0.67 361.8 F Wind Spd Backup MET_WIND_SPD_BKP 0.23 0.45 45 mph o

Sigma Theta MET_WIND- MET_SIGMA_THETA 0.28 0.4 20 When complete the Recorders should look as shown below.

Page 3 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 Notes to the Evaluator.

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

• START TIME: _________.

STEP 1:

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

_______ UNSAT 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:

STEP 2:

Notes: (Prior to Step 16) _______ SAT

• 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 _______ UNSAT 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:

Page 4 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 STEP 3:

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

_______ UNSAT STANDARD:

a) Determines that METEOROLOGICAL INFORMATION is available.

b) Initials Step 16.

EVALUATORS NOTE:

If asked: MET information is available on site.

COMMENTS:

STEP 4:

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

_______ UNSAT STANDARD:

a) Candidate may obtain the information in any order.

b) Initials Step 17.

COMMENTS:

Page 5 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 STEP 5:

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

_______ UNSAT STANDARD:

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

o b) Records Temperature 90.0 F 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:

STEP 6:

_______ SAT Notes: (Prior to Step 19)

_______ UNSAT

• 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:

Page 6 of 9

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

_______ SAT GET WIND SPEED (Step 19)

_______ UNSAT 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:

STEP 7:

_______ SAT Notes: (Prior to Step 20)

• An approximate average wind direction for the previous 15 minutes should be _______ UNSAT 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:

Page 7 of 9

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

_______ SAT GET AVERAGE WIND DIRECTION FROM PCS. (Step 20)

_______ UNSAT 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:

STEP 9:

_______ SAT Notes: (Prior to Step 21)

• Main Tower Delta T is the preferred source of stability class. Sigma Theta _______ UNSAT (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:

Page 8 of 9

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

_______ SAT DETERMINE STABILITY CLASS. (Step 21)

_______ UNSAT STANDARD:

o a) Candidate determines Stability class using Delta T. Delta T is -1.1 F 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:

Page 9 of 9

Surry 2014-301 Obtain Data for EPIP-2.01 STEP 11:

_______ SAT Provides MET data to Emergency Communicator.

_______ UNSAT 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 **

STOP TIME: ___________________________

Comments: __________________________________________________________________________________

Page 10 of 9

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 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 Page 1 of

Surry 2014-301 Determine Classification and PAR 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 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.

Page 2 of

Surry 2014-301 Determine Classification and PAR 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 _______ SAT 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 _______ UNSAT 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 Page 1 of 18

Surry 2014-301 Determine Classification and PAR EAL STEP 1: _______ SAT EVALUATE EMERGENCY ACTION LEVELS: _______ UNSAT 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 Page 2 of 18

Surry 2014-301 Determine Classification and PAR EAL Step 2: _______ SAT RECORD EAL IDENTIFIER, TIME EMERGENCY DECLARED AND SM/SEM NAME. _______ UNSAT 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 EAL Step 3: _______ SAT ANNOUNCE THE FOLLOWING DECLARATIONS: _______ UNSAT

• 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 Page 3 of 18

Surry 2014-301 Determine Classification and PAR 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:

_______ SAT Procedure Step 1

_______ UNSAT INITIATE PROCEDURE.

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

Evaluator's Comments PAR Step 2:

_______ SAT Procedure Step 1

_______ UNSAT USE ATTACHMENT 1, PROTECTIVE ACTION RECOMMENDATION MATRIX, TO DETERMINE INITIAL PAR Standards (a) Goes to Attachment 1.

Evaluator's Comments Page 4 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 3: _______ SAT Attachment 1 - Flowchart block 1- _______ UNSAT Known impediments make evacuation dangerous.

Standards

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

Evaluator's Comments PAR Step 4: _______ SAT Attachment 1 - Flowchart block 2- _______ UNSAT 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 Page 5 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 5:

_______ SAT Attachment 1 - Flowchart-

_______ UNSAT Evacuate 2 miles radius and 5 miles downwind.

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

Evaluator's Comments Page 6 of 18

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

_______ UNSAT 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 PAR Step 7

_______ SAT Procedure Step 3

_______ UNSAT 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 Page 7 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 8

_______ SAT Procedure Step 6 COMPLETE ATTACHMENT 3, PROTECTIVE ACTION RECOMMENDATION FORM: _______ UNSAT 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 Page 8 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 9

_______ SAT Procedure Step 7 - HAVE EMERGENCY COMMUNICATORS NOTIFY OFF-SITE AUTHORITIES OF PAR: _______ UNSAT

- 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 Page 9 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 10

_______ SAT Procedure Step 8 -

_______ UNSAT 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 PAR Step 11

_______ SAT Procedure Step 9 -

_______ UNSAT 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 PAR Step 12

_______ SAT CAUTION prior to step 10

_______ UNSAT 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 PAR Step 13

_______ SAT NOTE prior to step 10 Page 10 of 18

Surry 2014-301 Determine Classification and PAR

_______ UNSAT A Shelter-in-Place recommendation may supersede a Radiological Evacuation recommendation based on known impediments.

Standards SRO Acknowledges the Note.

CUES Evaluator's Comments PAR Step 14

_______ SAT Procedure Step 10

_______ UNSAT 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 Page 11 of 18

Surry 2014-301 Determine Classification and PAR PAR Step 15

_______ SAT Procedure Step 11 - CHECK EMERGENCY - TERMINATED

_______ UNSAT 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:

Page 12 of 18

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

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

Surry 2014-301 Determine Classification and PAR 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 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.

Page 15 of 18

Surry 2014-301 Determine Classification and PAR 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 16 of 18

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 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