Text

2015-10 Final Operating Test
	ML15293A564
Person / Time
Site:	South Texas
Issue date:	10/02/2015
From:	Vincent Gaddy; Operations Branch IV
To:	; South Texas
References
	Download: ML15293A564 (338)
	v • d • e

Rev. 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 09-28-2015 Examination Level: RO SRO Operating Test Number: LOT 20 NRC Exam Administrative Topic Type Describe activity to be performed (see Note) Code*

A1 Perform an RWST Blended Makeup Calculation Conduct of Operations N,R G2.1.25 Ability to interpret reference materials such as graphs, curves, tables, etc. (4.3/4.4)

A2 Verify an Excore QPTR Calculation Conduct of Operations D,P,R G2.1.20 Ability to interpret and execute procedural steps.

(4.6/4.6)

A3 Equipment Control Using Mechanical Drawings Determine the Isolation N,R Boundaries for a Leak on the RHR System G2.2.41 Ability to obtain and interpret station electrical NOTE: A3 and A7 are the and mechanical drawings. (3.5/3.9) same JPM.

A4 Calculate Stay Times based on Dose Rates M,R G2.3.4 Knowledge of radiation exposure limits under Radiation Control normal or emergency conditions. (3.2/3.7)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all five items).

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

Rev. 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 09-28-2015 Examination Level: RO SRO Operating Test Number: LOT 20 NRC Exam Administrative Topic Type Describe activity to be performed (see Note) Code*

A5 Calculate SDM with a Misaligned Control Rod and Conduct of Operations M,R Determine Applicable Technical Specifications.

G2.1.37 Knowledge of procedures, guidelines or limitations associated with Reactivity Management. (4.3/4.69)

A6 Perform a Calorimetric Heat Balance and Evaluate Technical Conduct of Operations N,R Specifications G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of operation. (4.3/4.4)

Equipment Control A7 Using Mechanical Drawings Determine the Isolation N,R Boundaries for a Leak on the RHR System NOTE: A3 and A7 are the G2.2.41 Ability to obtain and interpret station electrical and same JPM. mechanical drawings. (3.5/3.9)

A8 Approve completed Liquid Waste Release Permit. (alternate Radiation Control N,R path actual release did not match the approved release limits)

G2.3.6 Ability to approve release permits. (2.0/3.8)

A9 Determine EAL Emergency Procedures/Plan M,R G2.4.41 Knowledge of the emergency action level thresholds and classifications. (2.9/4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all five items).

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

Rev. 0 STP LOT-20 NRC Admin JPM Description RO (A1) Perform an RWST Blended Makeup Calculation Demonstrate the ability to set the boric acid flow integrator for a blended makeup to the RWST using 0POP02-CV-0001, Makeup to the Reactor Coolant System.

(A2) Verify an Excore QPTR Calculation Demonstrate the ability to perform and/or verify a QPTR. 0PSP10-NI-0002, Excore QPTR Determination.

(A3) Using Mechanical Drawings Determine the Isolation Boundaries for a Leak on the RHR System Demonstrate the ability to isolate portions of a system using a P&ID.

(A4) Calculate Stay Times based on Dose Rates Demonstrate the ability to determine stay times based on dose rates given in an RWP.

SRO (A5) Calculate SDM with a Misaligned Control Rod and Determine Applicable Technical Specifications Demonstrate the ability perform a SDM and apply appropriate TSs if required.

0PSP10-ZG-0005, Shutdown Margin Verification - Modes 1 and 2.

(A6) Perform a Calorimetric Heat Balance and Evaluate Technical Specifications Demonstrate the ability to perform a Calorimetric Verification and evaluate TSs.

0PEP02-CU-0001, Calorimetric Verification, and 0PSP03-NI-0001, Power Range NI Channel Calibration.

(A7) Using Mechanical Drawings Determine the Isolation Boundaries for a Leak on the RHR System Demonstrate the ability to isolate portions of a system using a P&ID.

(A8) Approve completed Liquid Waste Release Permit. (alternate path actual release did not match the approved release limits)

Demonstrate the ability to review a completed Liquid Waste Release Permit and determine if it was completed correctly. 0PSP07-WL-LDP1, Liquid Effluent Permit.

(A9) Determine Emergency Action Level Demonstrate the ability to correctly determine an Emergency Action Level for a given condition requiring entry into the STPNOC Emergency Action Plan.

NRC JPM NO: A1 Rev. 1 PAGE 1 OF 9 NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: PERFORM AN RWST BLENDED MAKEUP CALCULATION JPM NO.: A1 REVISION: 1

NRC JPM NO: A1 Rev.1 PAGE 2 OF 9 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

PERFORM AN RWST BLENDED MAKEUP CALCULATION JPM No.: A1 Rev. No: 1 STP Task: 70250, Operate the CVCS to Makeup to the RWST.

STP Objective: 70250, Operate the CVCS to Makeup to the RWST in accordance with 0POP02-CV-0001.

Related K/A

Reference:

2.1.25 [3.9/4.2] Ability to interpret reference materials, such as graphs, curves, tables, etc.

References:

0POP02-CV-0001, Makeup to the Reactor Coolant System Task Normally Completed By: RO Method of Testing: Actual performance Location of Testing: Classroom Time Critical Task: NO Alternate Path JPM: NO Validation Time: 10 minutes Required Materials (Tools/Equipment): Handout copy of 0POP02-CV-0001, Makeup to the Reactor Coolant System

NRC JPM NO: A1 Rev. 1 PAGE 3 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is in MODE 1 at 100% steady state conditions.

Refueling Water Storage Tank (RWST) level is 485,900 gallons.

RWST Boron Concentration is 2925 ppm.

Boric Acid Tank 1A Boron Concentration is 7325 ppm.

Boric Acid Tank 1B Boron Concentration is 7305 ppm.

You are the Unit 1 Extra Reactor Operator.

INITIATING CUE:

A scheduled activity will have the on-shift Crew raise RWST level to 510,000 gallons using the Reactor Makeup Water Storage Tank and Boric Acid Tank 1A.

The Unit Supervisor directs you to calculate the following per 0POP02-CV-0001, Makeup to the Reactor Coolant System, Section 15, Filling the RWST:

Calculate the BA Batch/Gallons

Calculate the Tot M/U Batch/Gallons

Calculate the BA Flow Control FK-0110 setpoint

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Correctly calculates the Boric Acid Batch/Gallons, Total M/U Batch/Gallons and BA Flow Control FK-0110 setpoint for the given conditions.

NRC JPM NO: A1 Rev. 1 PAGE 4 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Handout copy of 0POP02-CV-0001, Makeup to the Reactor Coolant System NOTES:

NRC JPM NO: A1 Rev. 1 PAGE 5 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

Critical steps are identified by (C).

Sequenced steps are identified by (S1, S2, . . .).

SAT/UNSAT Performance Step: 1 (C) Start time: __________

SET "BA BATCH/GALLONS FY-0110B" flow integrator for calculated gallons using the following formula: (Refer to Addendum 1, Setting Digital Reactor Makeup Flow Integrators)

BA batch/gallons = Tot M/U batch gallons x RWST Concentration BAT Concentration Standard:

____ Calculates the Tot M/U batch gallons for RWST: Desired level (510,000 gallons) minus the current level (485,900 gallons) equals 24,100 gallons.

____ Calculates the BA batch/gallons: Tot M/U batch gallons (24,100 gallons) times RWST Concentration (2925 ppm) divided by BAT 1A Concentration (7325 ppm)

____ ANSWER: BA batch/gallons equals 9624 gallons of Boric Acid.

Comment:

Cue:

Notes:

The actual BA batch/gallons calculates to 9623.549 gallons. If the student rounds the calculated value down to 9623 gallons the task will still be satisfied.

A calculated value of 9650 gallons would be incorrect as this would be the value if BAT 1B was used in the calculation.

NRC JPM NO: A1 Rev. 1 PAGE 6 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 (C)

SET "TOT M/U BATCH GALLONS FY-0111B" flow integrator for desired gallons.

Standard:

____ Calculates the Tot M/U batch gallons for RWST: Desired level (510,000 gallons) minus the current level (485,900 gallons) equals 24,100 gallons.

Comment:

This calculation for total M/U gallons is the same as in the previous step.

Cue:

Notes:

NRC JPM NO: A1 Rev. 1 PAGE 7 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 (C)

SET BA FLOW CONT FK-0110 setpoint, using the following formula:

Setpoint = {K} x Boron Concentration of RWST Boron Concentration of BAT Standard:

____ Calculates the BA FLOW CONT FK-0110 setpoint: {K} (20) (Modes 1, 2, 3, & 4 when CV-0198 is open) times Boron Concentration of RWST (2925 ppm) divided by Boron Concentration of BAT 1A (7325 ppm) equals 8.0 for the setpoint.

Comment:

Cue:

Notes:

The actual setpoint calculates to 7.9863 If the student rounds the calculated value down to 7.9 the task will still be satisfied.

If the student uses Boron Concentration for BAT 1B the setpoint calculation will not be significantly different however if the student uses 10 for {K} (Modes 4, 5, 6 and Core Off Loaded to SFP, when CV-0198 is throttled to < 110 gpm) then the calculated setpoint will be about 3.99 which would be incorrect.

- TERMINATE THE JPM - Stop time: _________

NRC JPM NO: A1 Rev. 1 PAGE 8 OF 9 VERIFICATION OF COMPLETION Job Performance Measure: A1, PERFORM AN RWST BLENDED MAKEUP CALCULATION Applicant's Name: _________________________

Date Performed: ___________________________

Time to Complete: _________________________

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

NRC JPM NO: A1 Rev. 1 PAGE 9 OF 9 JPM - HANDOUT READ TO PERFORMER:

When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is in MODE 1 at 100% steady state conditions.

Refueling Water Storage Tank (RWST) level is 485,900 gallons.

RWST Boron Concentration is 2925 ppm.

Boric Acid Tank 1A Boron Concentration is 7325 ppm.

Boric Acid Tank 1B Boron Concentration is 7305 ppm.

You are the Unit 1 Extra Reactor Operator.

INITIATING CUE:

A scheduled activity will have the on-shift Crew raise RWST level to 510,000 gallons using the Reactor Makeup Water Storage Tank and Boric Acid Tank 1A.

The Unit Supervisor directs you to calculate the following per 0POP02-CV-0001, Makeup to the Reactor Coolant System, Section 15, Filling the RWST:

Calculate the BA Batch/Gallons

Calculate the Tot M/U Batch/Gallons

Calculate the BA Flow Control FK-0110 setpoint WRITE ANSWER BELOW:

NRC JPM NO: A2 Rev. 1 PAGE 1 OF 8 NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: VERIFY AN EXCORE QPTR CALCULATION JPM NO.: A2 REVISION: 1

NRC JPM NO: A2 Rev. 1 PAGE 2 OF 8 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

VERIFY AN EXCORE QPTR CALCULATION JPM No.: A2 Rev. No.: 1 STP Task: 37750, Perform a Quadrant Power Tilt Ratio calculation STP Objective: 37750, Perform a Quadrant Power Tilt Ratio calculation in accordance with 0PSP10-NI-0002.

Related K/A

Reference:

2.1.20 [4.6] Ability to interpret and execute procedure steps.

References:

0PSP10-NI-0002, Excore QPTR Determination Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: Classroom Time Critical Task: NO Validation Time: 15 minutes Required Materials (Tools/Equipment): Calculator Student Handout 0PSP10-NI-0002 Student Handout Figure 5.1 of Plant Curve Book

NRC JPM NO: A2 Rev. 1 PAGE 3 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK INITIAL CONDITIONS:

Unit 2 has been at approximately 100% steady state power for several months. One (1) hour ago, Control Rod M12 (Control Bank D) dropped fully into the core. The crew has stabilized the plant and preparations are being made to lower Reactor power.

Control Room Annunciator 05M3 Window B-3, PR LOWER DET FLUX DEV HI/AUTO DEF, has alarmed. The Shift Manager has had a QPTR calculation done using the manual method (i.e.

without use of the Plant Computer or RO Calculator).

INITIATING CUE:

The Unit Supervisor instructs you to perform the Independent Verification of the QPTR calculation required by Step 5.2.9 of 0PSP10-NI-0002.

You are expected to correct any errors found, including subsequent entries/calculations, AND, once any corrections are made, determine if the Acceptance Criteria is/are met per step 5.3.

Additional information:

All Excore Nuclear Instrumentation Channels are operable.

The U2 Plant Curve Book Figure 5.1 is the latest approved version for purposes of this JPM AND there are no errors in the data of Figure 5.1.

Reactor Power is stable and meets the requirements of 0PSP10-NI-0002 Step 4.3.

Reactor Power is 99.7% by U1169, average NI power.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

The applicant must successfully discover an error on Form 3, accurately calculate the QPTR to at least 2 decimal places and determine Acceptance Criteria is NOT met.

NRC JPM NO: A2 Rev. 1 PAGE 4 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

0PSP10-NI-0002, Excore QPTR Determination

U2 Plant Curve Book Fig. 5.1 NOTES:

Examiner has a KEY of Form 3 of 0PSP10-NI-0002, Excore QPTR Determination. DO NOT give applicant copy of the page marked KEY.

Examiner has a STUDENT HANDOUT copy of Figure 5.1, Incore-Excore Cross-Calibration Constants. This is to be provided to the applicant at the start of the JPM. The data on this copy may be different from that contained in the current Plant Curve Book. The calculations performed in the KEY are based on the data from the STUDENT HANDOUT copy of Figure 5.1.

Actual numerical results will vary somewhat due to rounding and possibly using a most conservative approach. Because of this, there will be a range of numerical results, however the end result should be the same (i.e. numbers within the possible range should all indicate that Tech Spec QPTR Acceptance Criteria is NOT met).

NRC JPM NO: A2 Rev. 1 PAGE 5 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

Critical steps are identified by (C).

Sequenced steps are identified by (S1, S2, . . .).

SAT/UNSAT Performance Step: 1 Start time: _________

Obtain the procedure and Plant Curve Book Figure 5.1.

Standard:

_____ Applicant obtains handout copy of 0PSP10-NI-0002, Excore QPTR Determination, and the handout copy of U2 Figure 5.1.

Comment:

The Student Handout Copy of 0PSP10-NI-0002, Excore QPTR Determination includes completed procedure steps and applicable forms.

The Student Copy of U2 Figure 5.1, Incore-Excore Cross-Calibration Constants, may not be the current data in the Unit 2 Plant Curve Book, but contains the data applicable to this JPM. The data on this copy of Figure 5.1 should be used in the QPTR calculation.

Cue:

Provide the following to the applicant:

Student Handout Copy of 0PSP10-NI-0002, Excore QPTR Determination.

Student Handout Copy of Figure 5.1.

Notes:

NRC JPM NO: A2 Rev. 1 PAGE 6 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 (C)

Standard:

_____ Applicant determines there is an error on the calculation of NI 43 data and recalculates the result.

Comment:

For N44L, the 100% Power Detector Current should be 396.5 from Figure 5.1. The value used (418.1) by the performer is for NI 44 Upper Detector. After performing the division correctly, the result should be an LTR of 1.038.

Refer to KEY to see details of error.

Cue:

Notes:

SAT/UNSAT Performance Step: 3 (C)

Standard:

_____ Based on the error found for NI 44 data, the applicant corrects subsequent error carried forward results, and determines the Acceptance Criteria is NOT met.

Comment:

Refer to the KEY to see details of the error carried forward data and the final result that is NOT within the Acceptance Criteria of procedure section 6.1.

Cue:

Notes:

- TERMINATE THE JPM - Stop time: __________

NRC JPM NO: A2 Rev. 1 PAGE 7 OF 8 VERIFICATION OF COMPLETION Job Performance Measure: VERIFY AN EXCORE QPTR CALCULATION Applicant's Name: _________________________

Date Performed: ___________________________

Time to Complete: _________________________

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

NRC JPM NO: A2 Rev. 1 PAGE 8 OF 8 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOUVE COMPLETED THE TASK INITIAL CONDITIONS:

Unit 2 has been at approximately 100% steady state power for several months. One (1) hour ago, Control Rod M12 (Control Bank D) dropped fully into the core. The crew has stabilized the plant and preparations are being made to lower Reactor power.

Control Room Annunciator 05M3 Window B-3, PR LOWER DET FLUX DEV HI/AUTO DEF, has alarmed. The Shift Manager has had a QPTR calculation done using the manual method (i.e.

without use of the Plant Computer or RO Calculator).

INITIATING CUE:

The Unit Supervisor instructs you to perform the Independent Verification of the QPTR calculation required by Step 5.2.9 of 0PSP10-NI-0002.

You are expected to correct any errors found, including subsequent entries/calculations, AND, once any corrections are made, determine if the Acceptance Criteria is/are met per step 5.3.

Additional information:

All Excore Nuclear Instrumentation Channels are operable.

The U2 Plant Curve Book Figure 5.1 is the latest approved version for purposes of this JPM AND there are no errors in the data of Figure 5.1.

Reactor Power is stable and meets the requirements of 0PSP10-NI-0002 Step 4.3.

Reactor Power is 99.7% by U1169, average NI power.

0PSP10-NI-0002 Rev. 16 Page 15 of 15 Excore QPTR Determination Form 3 Excore QPTR Manually Calculated Data Sheet Page 1 of 1 5.2.2.1 Unit 2 Cycle 18 Date Today Time Now 5.2.2.2 Reactor Power 99.7% Indicator U1169 UPPER DETECTORS N41U N42U N43U N44U Current Meter Range 5.2.3 Switch Scale 1 1 1 1 (0.1, 0.5, 1 or 5)

Indicated Detector 419 5.2.4 Current (A) 415 399 411 KEY 100% Power Detector 5.2.5.2 5.2.5.3 5.2.2.3 Current (A) 416.5 412.9 394.3 418.1 Sum IU Average IU Normalized (IU) 5.2.5.1 1.006 1.005 1.012 0.983 4.006 1.0015 Currents 1

Maximum IU 100% 1.010 5.2.5.4 UPPER TILT RATIO (UTR) = = __________________

Power Average IU Detector Current for N44L should be LOWER DETECTORS 396.5 which makes N41L N42L N43L N44L Normalized Current Meter Range Current 1.060 5.2.3 Switch Scale 1 1 1 1 2 (0.1, 0.5, 1 or 5)

Sum IL should be 4.083 Indicated Detector Average IL should be 1.021 5.2.4 Current (A) 459 431 401 420 100% Power Detector 5.2.6.2 5.2.6.3 5.2.2.3 Current (A) 457.3 428.4 395.9 418.1 Sum IL Average IL Normalized (IL) 1.004 1.013 4.028 5.2.6.1 Currents 1.006 1.005 1.007 5.2.6.4 LOWER TILT RATIO (LTR) Maximum IL 1.006

= __________________

= Average IL 3

5.2.7 QPTR = Larger numerical value of the UTR or LTR = 1.010 LTR should be 1.038 and should 5.2.8 Performed by: Randy White Date: Today be the larger 5.2.9 Verified (IV) by: Date: numerical value.

If the Student calculates LTR to 2 decimal The QPTR does not meet the Acceptance Criteria of Step 6.1 places then the only correct answer is 1.04.

The QPTR SHALL NOT exceed 1.02. If the Student calculates LTR to 3 decimal places then 1.037 to 1.040 is acceptable.

This form, when completed, SHALL be retained for the life of the plant.

NRC JPM NO: A3 Rev. 2 PAGE 1 OF 8 NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR JPM NO.: A3 REVISION: 2

NRC JPM NO: A3 Rev. 2 PAGE 2 OF 8 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR JPM No.: A3 Rev. No: 2 STP Task: N/A N0025 - INTERPRET and use the symbols and acronyms used in One-STP Objective:

Line Diagrams.

Related K/A

Reference:

2.2.41 [3.5/3.9] Ability to obtain and interpret station electrical and mechanical drawings.

References:

5R169F20000 - P&ID for RHR System Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: N/A Time Critical Task: NO Alternate Path JPM: NO Validation Time: 10 minutes Required Materials (Tools/Equipment): None

NRC JPM NO: A3 Rev. 2 PAGE 3 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is in Mode 6 with the following conditions:

Core reload is in progress.

RHR Pump 1B is in service.

RHR Pump 1A is Operable but secured.

RHR Pump 1C is OOS for Maintenance.

Subsequently Control Room personnel notice that Reactor Cavity level is slowly lowering. A Plant Operator sent to investigate reports back that Flow Element FE-0852 for RHR Train 1B is leaking. The Unit Supervisor directs the Primary RO to start RHR Pump 1A and secure RHR Pump 1B.

INITIATING CUE:

You are the Extra Reactor Operator.

The Unit Supervisor directs you to determine the necessary valves that need to be ensured closed to isolate the RHR leak.

NOTE: The Unit Supervisor specifies that Check Valves and Air Operated Valves are NOT to be used to isolate the leak.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Determines that the following valves will need to be ensured closed:

RH-MOV-0019B, LOOP Th INJ

RH-MOV-0031B, LOOP Tc INJ

RH-MOV-0066B, RHR CVCS ISOL

RH-MOV-0067B, MINI FLOW ISOL

SI-0207B, LHSI PUMP 1B DISCHARGE ISOLATION

RH-0062B, B PUMP DISCH IF RH-MOV-0067B or RH-0062B are NOT used then the following must be used

RH-MOV-0061B or RH-MOV-0060B, B PUMP SUCT ISOL

RH-0063B or RH-0064B, RWST RTN ISOL

NRC JPM NO: A3 Rev. 2 PAGE 4 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

5R169F20000 - P&ID for RHR System NOTES:

NRC JPM NO: A3 Rev. 2 PAGE 5 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

Critical steps are identified by (C).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain 5R169F20000 - P&ID for RHR System.

Standard:

_____ Obtains 5R169F20000 - P&ID for RHR System.

Comment:

Cue:

Notes:

NRC JPM NO: A3 Rev. 2 PAGE 6 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET SAT/UNSAT Performance Step: 2 (C)

Determines valves needed to isolate the Train B RHR leak from Flow Element FE-0852 and does NOT consider Check Valves or Air Operated Valves.

Standard:

Determines valves needed to isolate the Train B RHR leak from Flow Element FE-0852:

RH-MOV-0019B, LOOP Th INJ

RH-MOV-0031B, LOOP Tc INJ

RH-MOV-0066B, RHR CVCS ISOL

RH-MOV-0067B, MINI FLOW ISOL

SI-0207B, LHSI PUMP 1B DISCHARGE ISOLATION

RH-0062B, B PUMP DISCH IF RH-MOV-0067B or RH-0062B are NOT used then the following must be used

RH-MOV-0061B or RH-MOV-0060B, B PUMP SUCT ISOL

RH-0063B or RH-0064B, RWST RTN ISOL Comment:

The student may identify that RH-0172, RCP Seal Standpipe Fill, needs to be closed, however, with the given conditions (Mode 5 and Mode 6) this valve would already be closed and locked.

The student may identify that RH-0086B, Primary Sampling Isol, needs to be closed, however, this valve would not have any back pressure from the primary sampling system and would not be required to be closed to isolate the leak.

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

NRC JPM NO: A3 Rev. 2 PAGE 7 OF 8 VERIFICATION OF COMPLETION Job Performance Measure: A4, DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR Applicant's Name:

Date Performed:

Time to Complete:

JPM Results:

Sat / Unsat Evaluator: Signature __________________________

Date ____________________

NRC JPM NO: A3 Rev. 2 PAGE 8 OF 8 JPM - STUDENT HANDOUT READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is in Mode 6 with the following conditions:

Core reload is in progress.

RHR Pump 1B is in service.

RHR Pump 1A is Operable but secured.

RHR Pump 1C is OOS for Maintenance.

Subsequently Control Room personnel notice that Reactor Cavity level is slowly lowering. A Plant Operator sent to investigate reports back that Flow Element FE-0852 for RHR Train 1B is leaking. The Unit Supervisor directs the Primary RO to start RHR Pump 1A and secure RHR Pump 1B.

INITIATING CUE:

You are the Extra Reactor Operator.

The Unit Supervisor directs you to determine the necessary valves that need to be ensured closed to isolate the RHR leak.

NOTE: The Unit Supervisor specifies that Check Valves and Air Operated Valves are NOT to be used to isolate the leak.

WRITE ANSWER BELOW:

NRC JPM NO: A4 Rev. 1 PAGE 1 OF 8 NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: CALCULATE MAXIMUM STAY TIME JPM NO.: A4 REVISION: 1

NRC JPM NO: A4 Rev. 1 PAGE 2 OF 8 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

CALCULATE MAXIMUM STAY TIME JPM No.: A4 Rev. No: 1 STP Task: N/A STP Objective: 92186 - Given the title of an administrative procedure, DISCUSS the requirements associated with the referenced procedure.

Related K/A

Reference:

2.3.4 [3.2/3.7] Knowledge of radiation exposure limits under normal or emergency conditions.

References:

0PGP03-ZR-0050, Radiation Protection Program Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: N/A Time Critical Task: NO Alternate Path JPM: NO Validation Time: 5 minutes Required Materials (Tools/Equipment): Calculator

NRC JPM NO: A4 Rev. 1 PAGE 3 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is shutdown for maintenance. An individual has been assigned to work on ED-FV-7800 that is located in a room 108C in the Unit 1 MAB. The worker has the following radiation history:

40 year old radiation worker.

NRC Form 4 on file

Lifetime exposure 5.75 Rem TEDE.

Annual exposure 1.2 Rem TEDE.

INITIATING CUE:

You are to determine the maximum length of time the worker may spend in the area of the valve without exceeding the STPNOC Administrative Action Level (AAL) for Annual TEDE.

Use the Survey Map given for room 108C.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Calculates the maximum time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months that the worker may spend in the radiation area without exceeding the Administrative Action Level (AAL) for Annual TEDE.

NRC JPM NO: A4 Rev. 1 PAGE 4 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

0PGP03-ZR-0050, Radiation Protection Program Survey Map NOTES:

NRC JPM NO: A4 Rev. 1 PAGE 5 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

Critical steps are identified by (C).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain value for AAL on Annual TEDE from plant procedure.

Standard:

Obtains the AAL on Annual TEDE of 1.5 Rem from 0PGP03-ZR-0050, Radiation Protection Program procedure.

Comment:

Candidate may or may not reference plant procedures to determine the Annual TEDE AAL.

Reference:

0PGP03-ZR-0050, Radiation Protection Program, Step 5.5.2.

Cue:

Notes:

NRC JPM NO: A4 Rev. 1 PAGE 6 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 (C)

Calculate the maximum stay time without exceeding the Annual TEDE AAL.

Standard:

Determines that 1-ED-FV-7800 is in a 50 mrem/hr radiation field as per the Survey Map and calculates the maximum stay time to be 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Comment:

AAL for Annual TEDE 1500 mrem Annual exposure TEDE - 1200 mrem Available Margin 300 mrem Available Margin / Dose Rate = Max. Stay Time 300 mrem / 50 mrem/hour = 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

NRC JPM NO: A4 Rev. 1 PAGE 7 OF 8 VERIFICATION OF COMPLETION Job Performance Measure: A4, CALCULATE MAXIMUM STAY TIME Applicant's Name:

Date Performed:

Time to Complete:

JPM Results:

Sat / Unsat Evaluator: Signature __________________________

Date ____________________

NRC JPM NO: A4 Rev. 1 PAGE 8 OF 8 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU=VE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is shutdown for maintenance. An individual has been assigned to work on 1-ED-FV-7800 that is located in a room 108C in the Unit 1 MAB. The worker has the following radiation history:

40 year old radiation worker.

NRC Form 4 on file

Lifetime exposure 5.75 Rem TEDE.

Annual exposure 1.2 Rem TEDE.

INITIATING CUE:

You are to determine the maximum length of time the worker may spend in the area of the valve without exceeding the STPNOC Administrative Action Level (AAL) for Annual TEDE.

Use the Survey Map given for room 108C.

WRITE ANSWER BELOW:

NRC JPM NO: A5 Rev. 1 PAGE 1 OF 9 NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: REVIEW SDM CALCULATION JPM NO.: A5 REVISION: 1 THIS JPM REQUIRES THAT A UNIT 1, CYCLE 19 NDR BE AVAILABLE FOR EACH SRO APPLICANT TAKING THIS TEST AT THE SAME TIME.

NRC JPM NO: A5 Rev. 1 PAGE 2 OF 9 JPM

Title:

REVIEW A SDM CALCULATION JPM No.: A5 Rev. No: 1 STP Task: 76950 Perform a Shutdown Margin Verification STP Objective: 76950 Perform a Shutdown Margin Verification in accordance with 0PSP10-ZG-0003 Related K/A

Reference:

G2.1.37 [4.3/4.6] Knowledge of procedures, guidelines, or limitations associated with reactivity management.

References:

Unit 1 Plant Curve Book Figure 5.4.

Nuclear Design Report, Unit 1, Cycle 19.

0PSP10-ZG-0005, Shutdown Margin Verification Modes 1 & 2 Task Normally Completed By: SRO Method of Testing: Actual Performance Location of Testing: Classroom Time Critical Task: NO Alternate Path JPM: NO Validation Time: 30 minutes Required Materials (Tools/Equipment): Calculator, Student Handout 0PSP05-ZG-0005, Unit 1 Cycle 19 NDR, PCB Figure 5.4

NRC JPM NO: A5 Rev. 1 PAGE 3 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power during Cycle 19. During performance of 0PSP03-RS-0001, Monthly Control Rod Operability, all three (3) Control Rods in Control Bank D, Group 2, failed to move outward after being inserted. I&C has determined that all three (3) Control Rods are being affected by Rod Control logic problems. Further testing has determined that Control Rods H-8 and M-4 are known to be untrippable (mechanically stuck). Control Rod D-12 slipped to a lower position and has been determined to be trippable.

NOTE the following:

Reactor power is stable at 100% by U1169.

Core Burnup is at End-of Life (EOL) - 15,500 MWD/MTU.

Full Out Position (FOP) And Bank Overlap (BOL) are set as follows:

FOP = 254

BOL = 117

RCS Boron is 380 ppm.

Rod H-8 is at 240 steps.

Rod M-4 is at 240 steps.

Rod D-12 is at 222 steps.

All other Rods are at 254 steps.

A Shutdown Margin Calculation was performed in accordance with 0PSP10-ZG-0005, Shutdown Margin Verification - Modes 1 and 2, using the MANUAL method, to verify compliance with Technical Specifications.

INITIATING CUE:

You are the Shift Manager and you are to perform a second review of the test data per step 5.17 of 0PSP10-ZG-0005, Shutdown Margin Verification - Modes 1 and 2, to determine if the Test Results are ACCEPTABLE or UNACCEPTABLE.

For the purposes of this JPM abide by the following:

DO NOT use Conservative Values. Use data directly derived from charts or tables.

Data derived from FIG 5.4 is verified correct and does NOT require re-interpolation.

WHEN YOUVE COMPLETED YOUR REVIEW, PRESENT YOUR RESULTS TO THE EXAMINER.

NRC JPM NO: A5 Rev. 1 PAGE 4 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Determines the SDM calculation is in error, calculates the correct SDM, SDM requirements are NOT met and a TS entry is required.

HANDOUTS:

Provide the following to the applicant at the start of the JPM:

Student Handout copy of 0PSP10-ZG-0005, Shutdown Margin Verification - Modes 1 and 2.

This handout copy has information filled in to match conditions given in the Initial Conditions.

Student Handout copy of Unit 1 Plant Curve Book for Cycle 19, Figure 5.4.

Unit 1 Cycle 19 NDR NOTES:

The procedure used to perform the Shutdown Margin calculation allows interpretation of data as well as a most-conservative approach. The instructions provided to the applicant specify he/she is to NOT use most-conservative data in order to get the best result based on plant conditions.

NRC JPM NO: A5 Rev. 1 PAGE 5 OF 9 VERIFICATION OF COMPLETION NOTE:

Critical steps are identified by (C).

Sequenced steps are identified by (S1, S2, . . .).

SAT/UNSAT Performance Step: 1 (C) Start time: _________

Procedure Step 5.5.6: Number of Inoperable RCCA (immovable as a result of excessive friction or mechanical interference, or known to be untrippable).

Standard:

_____ Determines that 2 control rods should have been marked as INOPERABLE due to excessive friction or mechanical interference or known to be untrippable.

Comment:

One control rod is in an ABNORMAL RCCA configuration but it is not the one that is untrippable.

Notes:

SAT/UNSAT Performance Step: 2 (C)

Procedure Step 5.8.7: Inoperable RCCA Worth (INOP RW) = (AMRSR) x (Number of Inoperable RCCA) = 5.8.4 x 5.5.6 Standard:

_____ Determines that calculated value should be 2380 pcm instead of 1190 pcm because 2 control rods are untrippable.

Comment:

Notes:

NRC JPM NO: A5 Rev. 1 PAGE 6 OF 9 VERIFICATION OF COMPLETION SAT/UNSAT Performance Step: 3 (C)

Procedure Step 5.8.8: Available RCCA Worth = (ARI LMRSR) - (IRW) - (ARCW) - (INOP RW) = 5.8.3 - 5.8.5 - 5.8.6.2.c - 5.8.7 Standard:

_____ Determines that the calculated value should be 3119 pcm instead of 4309 pcm. Mistake carried forward from Performance Step 2.

Comment:

Notes:

SAT/UNSAT Performance Step: 4 (C)

Procedure Step 5.8.10: Actual Shutdown Margin = (Available RCCA Worth) + (Total Power Defect) = 5.8.8 + 5.8.9 Standard:

_____ Determines that calculated value should be 452 pcm instead of 1642 pcm. Mistake carried forward from Performance Step 2.

Comment:

Notes:

NRC JPM NO: A5 Rev. 1 PAGE 7 OF 9 VERIFICATION OF COMPLETION SAT/UNSAT Performance Step: 5 (C)

Procedure Step 5.7.3: Obtain the Inserted RCCA Bank Worth at the RCCA positions recorded in Step 5.3.3 from the NDR. Enter as a positive value on Form 3.

Standard:

_____ Determines that Actual SDM is NOT greater than Required SDM. Acceptance Criteria is NOT satisfied and TS 3.1.1.1 for Shutdown Margin Modes 1 and 2 applies.

Comment:

Notes:

- TERMINATE THE JPM - Stop time: _________

NRC JPM NO: A5 Rev. 1 PAGE 8 OF 9 VERIFICATION OF COMPLETION Job Performance Measure: A5, REVIEW A SDM CALCULATION Applicant's Name: _________________________

Date Performed: ___________________________

Time to Complete: _________________________

JPM Results: Sat / Unsat Evaluator: _________________________ Signature: __________________________

Date: ____________________

NRC JPM NO: A5 Rev. 1 PAGE 9 OF 9 JPM - STUDENT HANDOUT READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power during Cycle 19. During performance of 0PSP03-RS-0001, Monthly Control Rod Operability, all three (3) Control Rods in Control Bank D, Group 2, failed to move outward after being inserted. I&C has determined that all three (3) Control Rods are being affected by Rod Control logic problems. Further testing has determined that Control Rods H-8 and M-4 are known to be untrippable (mechanically stuck). Control Rod D-12 slipped to a lower position and has been determined to be trippable.

NOTE the following:

Reactor power is stable at 100% by U1169.

Core Burnup is at End-of Life (EOL) - 15,500 MWD/MTU.

Full Out Position (FOP) And Bank Overlap (BOL) are set as follows:

FOP = 254

BOL = 117

RCS Boron is 380 ppm.

Rod H-8 is at 240 steps.

Rod M-4 is at 240 steps.

Rod D-12 is at 222 steps.

All other Rods are at 254 steps.

A Shutdown Margin Calculation was performed in accordance with 0PSP10-ZG-0005, Shutdown Margin Verification - Modes 1 and 2, using the MANUAL method, to verify compliance with Technical Specifications.

INITIATING CUE:

You are the Shift Manager and you are to perform a second review of the test data per step 5.17 of 0PSP10-ZG-0005, Shutdown Margin Verification - Modes 1 and 2, to determine if the Test Results are ACCEPTABLE or UNACCEPTABLE.

For the purposes of this JPM abide by the following:

DO NOT use Conservative Values. Use data directly derived from charts or tables.

Data derived from FIG 5.4 is verified correct and does NOT require re-interpolation.

WHEN YOUVE COMPLETED YOUR REVIEW, PRESENT YOUR RESULTS TO THE EXAMINER.

NRC JPM NO: A6 Rev. 1 PAGE 1 OF 7 NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: REVIEW A CALORIMETRIC HEAT BALANCE & EVALUATE TSs JPM NO.: A6 REVISION: 1

NRC JPM NO: A6 Rev. 1 PAGE 2 OF 7 JPM

Title:

REVIEW A CALORIMETRIC HEAT BALANCE & EVALUATE TSs JPM No.: A6 Rev. No: 1 STP Task: SRO-12000 Authorize the start of and review surveillance tests.

STP Objective: SRO-12000 AUTHORIZE the start of Operations surveillance tests, and review completion in accordance with PGP03-ZE-0004 Related K/A

Reference:

G2.1.23 [4.3/4.4] Ability to perform specific system and integrated plant procedures during all modes of plant operation.

References:

0PSP03-NI-0001, Power Range NI Channel Calibration Task Normally Completed By: SRO Method of Testing: Actual Performance Location of Testing: Classroom Time Critical Task: NO Alternate Path JPM: NO Validation Time: 25 minutes Required Materials (Tools/Equipment): None

NRC JPM NO: A6 Rev. 1 PAGE 3 OF 7 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is being brought back to 100% power after a 7 day forced outage. Currently power is at 98%. A Reactor Operator has performed a calorimetric per step 7.58.4 of 0POP03-ZG-0005, Plant Startup to 100%.

INITIATING CUE:

You are the Shift Manager and you have been given the calorimetric, 0PSP03-NI-0001, Power Range NI Channel Calibration, for review per step 6.11.12.

Determine if the surveillance is ACCEPTABLE or UNACCEPTABLE WHEN YOUVE COMPLETED YOUR REVIEW, PRESENT YOUR RESULTS TO THE EXAMINER.

NRC JPM NO: A6 Rev. 1 PAGE 4 OF 7 JOB PERFORMANCE MEASURE INFORMATION SHEET

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

The Shift Manager determines that the Qsec %power from Data Sheet 3 was transcribed incorrectly over to Data Sheet 2 and calculates the correct As Left Difference. This miscalculation caused the As Left Difference between Qsec %power and %RTP on all 4 Power Range NI Channels to be in error.

The Shift Manager determines from the miscalculation that all 4 Power Range NI Channels must be adjusted and that Power Range Channel NI-0041 is INOPERABLE until the channel is adjusted. Refer to TS 3.3.1, Instrumentation, for Power Range Neutron Flux.

HANDOUTS:

A marked up copy of 0PSP03-NI-0001, Power Range NI Channel Calibration, for the Student.

A KEY for the Examiner.

NOTES:

None

NRC JPM NO: A6 Rev. 1 PAGE 5 OF 7 VERIFICATION OF COMPLETION NOTE:

Critical steps are identified by (C).

Sequenced steps are identified by (S1, S2, . . .).

SAT/UNSAT Performance Step: 1 (C) Start time: _________

The Shift Manager/Unit Supervisor SHALL:

PERFORM a second review of the test data.

SIGN and RECORD the date and time on Data Sheet 1.

TRANSFER the Data Package in accordance with 0PGP03-ZA-0055, Plant Surveillance Scheduling.

(step 6.11.12)

Standard:

_____ The Shift Manager determines that the Qsec %power from Data Sheet 3 was transcribed incorrectly over to Data Sheet 2 and calculates the correct As Left Difference. This miscalculation caused the As Left Difference between Qsec %power and %RTP on all 4 Power Range NI Channels to be in error.

_____ The Shift Manager determines from the miscalculation that all 4 Power Range NI Channels must be adjusted and that Power Range Channel NI-0041 is INOPERABLE until the channel is adjusted. Refer to TS 3.3.1, Instrumentation, for Power Range Neutron Flux.

Comment:

A KEY is provided with this JPM.

Notes:

- TERMINATE THE JPM - Stop time: _________

NRC JPM NO: A6 Rev. 1 PAGE 6 OF 7 VERIFICATION OF COMPLETION Job Performance Measure: A6, REVIEW A CALORIMETRIC HEAT BALANCE &

EVALUATE TSs Applicant's Name: _________________________

Date Performed: ___________________________

Time to Complete: _________________________

JPM Results: Sat / Unsat Evaluator: _________________________ Signature: __________________________

Date: ____________________

NRC JPM NO: A6 Rev. 1 PAGE 7 OF 7 JPM - STUDENT HANDOUT READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is being brought back to 100% power after a 7 day forced outage. Currently power is at 98%. A Reactor Operator has performed a calorimetric per step 7.58.4 of 0POP03-ZG-0005, Plant Startup to 100%.

INITIATING CUE:

You are the Shift Manager and you have been given the calorimetric, 0PSP03-NI-0001, Power Range NI Channel Calibration, for review per step 6.11.12.

Determine if the surveillance is ACCEPTABLE or UNACCEPTABLE WHEN YOUVE COMPLETED YOUR REVIEW, PRESENT YOUR RESULTS TO THE EXAMINER.

WRITE RESULTS BELOW:

RMS File Z-16 0PSP03-NI-0001 Rev. 29 Page 41 of 59 Power Range NI Channel Calibration Data Sheet 2 Calibration Data Page 1 of 1 Unit Cycle Date 7RGD\

6.2.2 Data Collection Started: Date 7RGD\ Time 0LQ$JR New Calculations 6.10 Data Collection Stopped: Date 7RGD\ Time 0LQ$JR Transcribed Incorrectly. See As Found As Left Data Sheet 3,As 6.0 Guidelines (%RTP)

Found Difference As Left Difference Channel Indication Qsec (%) (%RTP) Indication (%RTP) Qsec t 90% Q < 90%

sec

[1] (%RTP) (%RTP) [2], [3] (%RTP) [4]

N-41 2 +2.03 r0.5 +2, -0.5 N-42 97.77 2 +1.98 r0.5 +2, -0.5

KEY

r0.5 N-43 2 +1.97 +2, -0.5 N-44 2 +1.95 r0.5 +2, -0.5 Average As Found Average As As Left As Found As Found Difference As Left Left NI Difference U1169 NI Power (U1169 - Avg NI) U1169 Power (U1169 - Avg NI)

[1] Refer to Precautions Step 4.8 for Channels Out of Service.

[2] As Found Difference = As Found Indication - Qsec. Therefore, the sign of the As Found Difference will be negative (-) when the NI is lower than Qsec and positive (+) when the NI is higher than Qsec.

[3] IF adjustment downward greater than 2% is required, THEN verify Qsec per Addendum 3, Step 1.0.

1$

Addendum 3, Step 1.0: Verification Performed By:

[4] As Left Difference = As Left Indication - Qsec ACCEPTANCE CRITERION: The absolute value of each OPERABLE NI "As Left Difference" SHALL BE less than or equal to 2% (that is, greater than or equal to -2% AND less than or equal to +2%).

NI-41 As Left Difference is more than All other NI Channels As Left 2%. It is Inoperable until adjusted. Difference is more than +0.5% and Refer to TS 3.3.1, Instrumentation, for must be adjusted at this power level.

Power Range Neutron Flux.

Completed by: %DEH5XWK Date: 7RGD\

Verified by: :LOOLH0D\V Date: 7RGD\

This package, when completed, SHALL BE retained for a minimum of five (5) years.

RMS File Z-16 0PSP03-NI-0001 Rev. 29 Page 42 of 59 Power Range NI Channel Calibration Data Sheet 3 Computer Point Data Page 1 of 1 Unit Cycle Date 7RGD\

COMPUTER-BASED Method data (Addendum 1): Initials 1.0 U1118 Verified Reliable per 0PEP02-CU-0001 within the last 8 days. %5 2.0 0PEP02-CU-0001 performed since power changed regions (if applicable). %5 3.0 Plant Computer point ICQUG1118O has GOOD quality. %5 4.0 Delta-T Power from operable Delta-T's t 30%. %5 6.0 ICQUG1118O = Qsec(%) %

KEY 7.0 C Clarifier present for ICQUG1118O Yes No N/A IF Plant Computer point ICQUG1118O has a C clarifier, THEN verify all the UTF correction factors are equal to 1.00.

ICCUR0411 = 1.00 Yes No N/A ICCUR0431 = 1.00 Yes No N/A ICCUR0451 = 1.00 Yes No N/A ICCUR0471 = 1.00 Yes No N/A Completed by: %DEH5XWK Date: 7RGD\

This package, when completed, SHALL BE retained for a minimum of five (5) years.

NRC JPM NO: A7 Rev. 2 PAGE 1 OF 8 NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR JPM NO.: A7 REVISION: 2

NRC JPM NO: A7 Rev. 2 PAGE 2 OF 8 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR JPM No.: A7 Rev. No: 2 STP Task: N/A N0025 - INTERPRET and use the symbols and acronyms used in One-STP Objective:

Line Diagrams.

Related K/A

Reference:

2.2.41 [3.5/3.9] Ability to obtain and interpret station electrical and mechanical drawings.

References:

5R169F20000 - P&ID for RHR System Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: N/A Time Critical Task: NO Alternate Path JPM: NO Validation Time: 10 minutes Required Materials (Tools/Equipment): None

NRC JPM NO: A7 Rev. 2 PAGE 3 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is in Mode 6 with the following conditions:

Core reload is in progress.

RHR Pump 1B is in service.

RHR Pump 1A is Operable but secured.

RHR Pump 1C is OOS for Maintenance.

Subsequently Control Room personnel notice that Reactor Cavity level is slowly lowering. A Plant Operator sent to investigate reports back that Flow Element FE-0852 for RHR Train 1B is leaking. The Unit Supervisor directs the Primary RO to start RHR Pump 1A and secure RHR Pump 1B.

INITIATING CUE:

You are the Extra Reactor Operator.

The Unit Supervisor directs you to determine the necessary valves that need to be ensured closed to isolate the RHR leak.

NOTE: The Unit Supervisor specifies that Check Valves and Air Operated Valves are NOT to be used to isolate the leak.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Determines that the following valves will need to be ensured closed:

RH-MOV-0019B, LOOP Th INJ

RH-MOV-0031B, LOOP Tc INJ

RH-MOV-0066B, RHR CVCS ISOL

RH-MOV-0067B, MINI FLOW ISOL

SI-0207B, LHSI PUMP 1B DISCHARGE ISOLATION

RH-0062B, B PUMP DISCH IF RH-MOV-0067B or RH-0062B are NOT used then the following must be used

RH-MOV-0061B or RH-MOV-0060B, B PUMP SUCT ISOL

RH-0063B or RH-0064B, RWST RTN ISOL

NRC JPM NO: A7 Rev. 2 PAGE 4 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

5R169F20000 - P&ID for RHR System NOTES:

NRC JPM NO: A7 Rev. 2 PAGE 5 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

Critical steps are identified by (C).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain 5R169F20000 - P&ID for RHR System.

Standard:

_____ Obtains 5R169F20000 - P&ID for RHR System.

Comment:

Cue:

Notes:

NRC JPM NO: A7 Rev. 2 PAGE 6 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET SAT/UNSAT Performance Step: 2 (C)

Determines valves needed to isolate the Train B RHR leak from Flow Element FE-0852 and does NOT consider Check Valves or Air Operated Valves.

Standard:

Determines valves needed to isolate the Train B RHR leak from Flow Element FE-0852:

RH-MOV-0019B, LOOP Th INJ

RH-MOV-0031B, LOOP Tc INJ

RH-MOV-0066B, RHR CVCS ISOL

RH-MOV-0067B, MINI FLOW ISOL

SI-0207B, LHSI PUMP 1B DISCHARGE ISOLATION

RH-0062B, B PUMP DISCH IF RH-MOV-0067B or RH-0062B are NOT used then the following must be used

RH-MOV-0061B or RH-MOV-0060B, B PUMP SUCT ISOL

RH-0063B or RH-0064B, RWST RTN ISOL Comment:

The student may identify that RH-0172, RCP Seal Standpipe Fill, needs to be closed, however, with the given conditions (Mode 5 and Mode 6) this valve would already be closed and locked.

The student may identify that RH-0086B, Primary Sampling Isol, needs to be closed, however, this valve would not have any back pressure from the primary sampling system and would not be required to be closed to isolate the leak.

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

NRC JPM NO: A7 Rev. 2 PAGE 7 OF 8 VERIFICATION OF COMPLETION Job Performance Measure: A7, DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR Applicant's Name:

Date Performed:

Time to Complete:

JPM Results:

Sat / Unsat Evaluator: Signature __________________________

Date ____________________

NRC JPM NO: A7 Rev. 2 PAGE 8 OF 8 JPM - STUDENT HANDOUT READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is in Mode 6 with the following conditions:

Core reload is in progress.

RHR Pump 1B is in service.

RHR Pump 1A is Operable but secured.

RHR Pump 1C is OOS for Maintenance.

Subsequently Control Room personnel notice that Reactor Cavity level is slowly lowering. A Plant Operator sent to investigate reports back that Flow Element FE-0852 for RHR Train 1B is leaking. The Unit Supervisor directs the Primary RO to start RHR Pump 1A and secure RHR Pump 1B.

INITIATING CUE:

You are the Extra Reactor Operator.

The Unit Supervisor directs you to determine the necessary valves that need to be ensured closed to isolate the RHR leak.

NOTE: The Unit Supervisor specifies that Check Valves and Air Operated Valves are NOT to be used to isolate the leak.

WRITE ANSWER BELOW:

@RF SEE PSY NOTE ""-~' ZLP 3944 t FY 3859 c-HK FT IPc,:cf- ;2~

2 A 853 1 f - [ ) 9F05004<'~ c-s> ~

~

SI 929 u RCP SEAL STANDPIPE 1C SI

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ISSUE ISSUE DATE REVISION ORIG CKR RE DV SE NO_ DATE REVISION OR!G CKR RE DV SE 1 5R169F20000#1.DGN 0070928 NONE 5 R16 9 F 2 0 0 0 0 #1 27 I 8 7 6 5 4 3 2 1 2114/2013 4:44:32 PM JGL _j

NRC JPM NO: A8 Rev. 1 PAGE 1 OF 7 NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: APPROVE A LIQUID WASTE RELEASE PERMIT JPM NO.: A8 REVISION: 1

NRC JPM NO: A8 Rev. 1 PAGE 2 OF 7 JPM

Title:

APPROVE A LIQUID WASTE RELEASE PERMIT JPM No.: A8 Rev. No: 1 STP Task: 13400 Authorize a release of liquid waste.

STP Objective: SRO 13400 AUTHORIZE a release of liquid waste in accordance with 0PSP07-WL-LDP1.

Related K/A

Reference:

G2.3.6 [2.0/3.8] Ability to approve release permits.

References:

0PSP07-WL-LDP1, Liquid Effluent Permit Task Normally Completed By: SRO Method of Testing: Actual Performance Location of Testing: Classroom Time Critical Task: NO Alternate Path JPM: NO Validation Time: 10 minutes Required Materials (Tools/Equipment): Student Handout 0PSP07-WL-LDP1, Liquid Effluent Permit, with Liquid Effluent Permit - OPEN attached.

NRC JPM NO: A8 Rev. 1 PAGE 3 OF 7 VERIFICATION OF COMPLETION READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is preparing to release Waste Monitor Tank (WMT) 1E. RT-8038 is Operable. Per step 5.38.4 of 0POP02-WL-0100, Liquid Waste Release, a Plant Operator has just contacted the control room to ensure that the Shift Manager has signed 0PSP07-WL-LDP1, Liquid Effluent Permit, which will authorize the release.

INITIATING CUE:

You are the Shift Manager. You are to perform step 5.1.28 of 0PSP07-WL-LDP1, Liquid Effluent Permit, to authorize the release of WMT 1E.

Review the Liquid Effluent Permit in its entirety.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Determines BOTH of the two following errors and that WMT 1E is NOT to be released at this time. (i.e. Does NOT sign Permit)

Total sample activity is greater than the total activity guidelines. (Step 5.1.11)

Projected Total Body Dose (31 Day) does NOT meet the Acceptance Criteria. (Step 5.1.14)

NRC JPM NO: A8 Rev. 1 PAGE 4 OF 7 VERIFICATION OF COMPLETION HANDOUTS:

Provide the following to the applicant at the start of the JPM:

Student Handout copy of 0PSP07-WL-LDP1, Liquid Effluent Permit, with Liquid Effluent Permit - OPEN attached.

NOTES:

A KEY has been prepared for this JPM to aid in determining satisfactory performance.

NRC JPM NO: A8 Rev. 1 PAGE 5 OF 7 VERIFICATION OF COMPLETION NOTE:

Critical steps are identified by (C).

Sequenced steps are identified by (S1, S2, . . .).

SAT/UNSAT Performance Step: 1 (C) Start time: _________

Procedure Step 5.1.11: COMPARE the sample results of the WMT to be released to the activity guidelines listed below: (Ref. 0PCP01-ZA-0021)

Cs-137 1E-06 µCi/mL Total Activity (excluding Tritium and Noble Gases) 5E-06 µCi/mL Procedure Step 5.1.14: Verify the 31 Day Dose Projection does not exceed the limits of ODCM Part A, Control 3.11.1.3:

Projected Total Body Dose (31 Day) and the Projected Max Organ Dose (31 Day) both indicate PASS in the Verifications Section of the Liquid Effluent Permit.

Standard:

_____ Determines that total activity is greater than 5E-06 µCi/mL.

AND

_____ Determines that Acceptance Criteria for Projected Total Body Dose (31 Day) is NOT satisfied.

AND

_____ Determines that the Effluent Release Permit authorizing the release of WMT 1E should not be signed at this time.

Comment:

See KEY.

Notes:

- TERMINATE THE JPM - Stop time: _________

NRC JPM NO: A8 Rev. 1 PAGE 6 OF 7 VERIFICATION OF COMPLETION Job Performance Measure: A8, APPROVE A LIQUID WASTE RELEASE PERMIT Applicant's Name: _________________________

Date Performed: ___________________________

Time to Complete: _________________________

JPM Results: Sat / Unsat Evaluator: _________________________ Signature: __________________________

Date: ____________________

NRC JPM NO: A8 Rev. 1 PAGE 7 OF 7 JPM - STUDENT HANDOUT READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

INITIAL CONDITIONS:

Unit 1 is preparing to release Waste Monitor Tank (WMT) 1E. RT-8038 is Operable. Per step 5.38.4 of 0POP02-WL-0100, Liquid Waste Release, a Plant Operator has just contacted the control room to ensure that the Shift Manager has signed 0PSP07-WL-LDP1, Liquid Effluent Permit, which will authorize the release.

INITIATING CUE:

You are the Shift Manager. You are to perform step 5.1.28 of 0PSP07-WL-LDP1, Liquid Effluent Permit, to authorize the release of WMT 1E.

Review the Liquid Effluent Permit in its entirety.

0PSP07-WL-LDP1 Rev. 17 Page 8 of 20 Liquid Effluent Permit Initials 5.1.10 IF the sample volume is 1 liter OR the sample is counted for 2500 seconds, THEN VERIFY the analysis results meet the following required LLD values: N/A Principle Principle Gamma A Priori Gamma A Priori Emitters LLD Ci/mL Emitters LLD Ci/mL Mn-54 5E-7 Mo-99 5E-7 Fe-59 5E-7 Cs-134 5E-7 Co-58 5E-7 Cs-137 5E-7 Co-60 5E-7 Ce-141 5E-7 Zn-65 5E-7 Ce-144 5E-6 I-131 1E-6 Kr-87 1E-5 Kr-88 1E-5 Xe-133 1E-5 Xe-133m 1E-5 Xe-135 1E-5 KEY Xe-138 1E-5 5.1.11 COMPARE the sample results of the WMT to be released to the activity guidelines listed below: (Ref. 0PCP01-ZA-0021)

Cs-137 1E-06 Ci/mL reading was 5.926E-6 Total Activity (excluding Tritium and Noble Gases) 5E-06 Ci/mL 5.1.11.1 IF sample activity is less than or equal to the activity Total Activity is greater guidelines, THEN GO TO Step 5.1.12. JB than activity guidelines.

See Page 9 of 9 of the 5.1.11.2 IF sample activity is greater than the activity guidelines, Unit 1 Tech Services THEN recommend that the tank be reprocessed to meet Count Room Pages of the the activity guidelines, OTHERWISE ENSURE a Release Package. Deviation Report is completed per 0PCP01-ZA-0021, Radioactive Waste Processing Guidelines, prior to proceeding to Step 5.1.12. N/A 5.1.12 IF the WMT to be released is in Short Path Recirculation, THEN notify Operations to place the WMT in Long Path Recirculation. JB 5.1.13 Generate and print a Liquid Effluent Permit per 0PCP09-ZR-0017, Liquid Permit Generation, and include it in the release package. JB This procedure, when completed, shall be retained.

0PSP07-WL-LDP1 Rev. 17 Page 9 of 20 Liquid Effluent Permit Initials AC 5.1.14 Verify the 31 Day Dose Projection does not exceed the limits of ODCM Part A, Control 3.11.1.3:

Projected Total Body Dose (31 Day) and the Projected Max Organ Dose (31 Day) both indicate PASS in the Verifications Section of Projected Total Body the Liquid Effluent Permit. limit is <0.06 and reading was 6.5E-2 Dose Does NOT meet Acceptance Criteria. Acceptance See page in Permit JB Criteria Met Initials: _________ Date: ________ 30 Min Ago Today Time: ________

Package titled Liquid Effluent Permit - OPEN 5.1.14.1 IF the 31 Day Dose Projection exceeds the limits of ODCM Part A, Control 3.11.1.3, THEN complete Data Sheet 1 AND leave a copy with the Shift Manager. _N/A_

AC 5.1.15 Verify the Quarterly and Annual Dose projections do not exceed the limits of ODCM Part A, Control 3.11.1.1 and 3.11.1.2:

KEY Total ECL Fraction, Post Dilution Noble Gas Conc, Cum. Total Body Dose (Qtrly and Annual), Cum. Max Organ Dose (Qtrly and Annual) all indicate PASS in the Verifications Section of the Liquid Effluent Permit.

Acceptance JB Criteria Met Initials: _________ 30 Min Ago Today Time: ________

Date: ________

NOTE 0POP02-WL-0100, Liquid Waste Release, requires that recirculation of all other WMTs be secured while the WMT to be released is in Long Path Recirculation.

5.1.16 Verify with Operations that the WMT to be released is in Long Path Recirculation. JB 5.1.17 Verify that ONLY the WMT to be released is in recirculation by checking the correct WMT pump in operation in Radwaste Control Room: JB 1E WMT in recirculation: ________________

5.1.18 WHEN the RT-8038 10 minute trend has updated at least twice, THEN select a representative 10 minute trend reading from RM-11 Channel 1(2)138 and record reading as the Actual Monitor Reading: JB 7.10 E-8 Actual Monitor Reading (AMR): _________________Ci/mL This procedure, when completed, shall be retained.

0PSP07-WL-LDP1 Rev. 17 Page 11 of 20 Liquid Effluent Permit Initials 5.1.26 IF any alarm setpoints or channel items were changed, THEN independently verify each changed setpoint is correct.

(Enter NA for setpoints that were NOT changed) (SPR 92-0191 and SPR 92-0310)

Alert and High Setpoints are correct. N/A Ind. Verif Conversion Factor is correct. PR Ind. Verif 5.1.27 Have the Chemical Technician Supervisor or designee independently review the Liquid Effluent Permit. PR Ind. Verif 5.1.28 Forward package to Shift Manager for signature for the following: JB KEY Review of the Liquid Effluent Permit Approval for the discharge RT-8038 status verified operable.

Shift Manager Date: Time:

Shift Manager Should NOT sign for the release.

This procedure, when completed, shall be retained.

0PSP07-WL-LDP1 LIQUID EFFLUENT PERMIT - OPEN Permit No 1378 Release Type Batch Unit 1 Source WMT 1E Sample No WL 1522 2015 Permit Details Start Date Time Today/3 Hours Ago End Date Time Today/2 Hours Ago Recirc Start Date Time Minimum Circ Time Sample After Date Time Today/15 Hours Ago 30 Minutes Today/14 Hours 30 Min Ago Effluent Volume (GAL) 20000.00 Dilution Volume (GAL) 32092000.00 Effluent Rel Rate (GPM) 280.00 Dilution Flow Rate (GPM) 452000.00 Pre Dilution ECL Frac 1.59E+02 Post Dilution ECL Frac 9.89E-02 Setpoint Calculations Conversion Factor (uCi/ml/cpm) 5.41 E-09 Expected Monitor Response (uCi/ml) 2.66E-07 KEY Alarm Channel 1 (uCi/ml) 5.00E-03 Alarm Channel 2 (uCi/sec) 8.83E+01 Dose Calculations Total Body Dose Max Organ Dose Projected Doses (mRem) 3.84E-03 1.08E-02 Quarterly Doses (mRem) 1.35E-03 1.36E-03 Annual Doses (mRem) 5.01E-03 5.04E-03 Verifications FAIL - Projected Total Body Dose (31 Days) < 0.06 (6.5E-02)

PASS - Projected Max Organ Dose (31 Days) < 0.2 (1.75E-01) Projected Total Body Dose is PASS - Total ECL Fraction < 10 (1.1E-01) above the limit and PASS - Post Dilution Noble Gas Conc < 2.0E-04 ( )

has FAILED.

PASS - Cum. Total Body Dose (QTRLY) < 1.5 (2.75E-03)

PASS - Cum. Total Body Dose (ANNUAL) < 3.0 (6.0E-03)

PASS - Cum. Max Organ Dose (QTRLY) < 5.0 (2.9E-03)

PASS - Cum. Max Organ Dose (ANNUAL) < 10.0 (6.0E-03)

Remarks RDRLQPO This report is SQA level 2 per 0PGP07-ZA-0014

1 1

U1 1E U1 1E Today/90 Min Ago 9.570 E-07 1.985 E-06 9.905 E-07 1.993 E-06 5.926 E-06 Total activity should be less than 5.0 E-6.

KEY See Procedure step 5.1.11

NRC JPM NO: A9 Rev. 1 PAGE 1 OF 9 NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: DECLARE EMERGENCY ACTION LEVEL JPM NO.: A9 REVISION: 1

NRC JPM NO: A9 Rev. 1 PAGE 2 OF 9 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

DECLARE EMERGENCY ACTION LEVEL JPM No.: A9 Rev. No.: 1 Task No.: 74026 (SRO), Classify emergency conditions.

STP Objective: Given an emergency condition and a copy of the emergency classification tables from 0ERP01-ZV-IN01, Emergency Classification, classify the emergency condition.

Related K/A

Reference:

2.4.41 [2.9/4.6], Knowledge of the emergency action level thresholds and classifications.

References:

0ERP01-ZV-IN01, Rev. 9, Emergency Classification Task Normally Completed By: SRO Method of Testing: Actual Performance Location of Testing: Classroom Time Critical Task: YES (15 minutes based on E-Plan Evaluation criteria)

Alternate Path JPM: NO Validation Time: 5 minutes Required Materials (Tools/Equipment): None

NRC JPM NO: A9 Rev. 1 PAGE 3 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK INITIAL CONDITIONS:

Both Units are at 100% power, steady-state.

While a strong cold front was moving through the plant a tornado was sighted moving across the Main Reservoir from the Southeast. The tornado touched down just west of the CWIS but dissipated as it moved into the Protected Area.

As the winds from the tornado died down, the Unit 1 Yard was instructed to assess any damage.

The Unit 1 Yard watch reported the following:

The building around the Lighting Diesel Generator was heavily damaged.

Parts of the Auxiliary Boiler are damaged.

A section of the Main Reservoir west of the CWIS is damaged and water is flowing out of the Main Reservoir into the Protected Area.

INITIATING CUE:

This JPM is time-critical. The time limit starts when you (the applicant) understand the Initial Conditions and Initiating Cue.

You are the Unit 1 Shift Manager. Based on the CURRENT Plant conditions as described above:

1. Classify the event at its MINIMUM Emergency Classification (i.e. over-classification will be incorrect).

2. Indicate on the Student copy of the initiating cue sheet the underlying plant condition/s or criteria you used to make your determination of the classification. (i.e. if points were used in determination of classification then explain why the point was used)

Notify your Evaluator when you have completed the JPM.

NRC JPM NO: A9 Rev. 1 PAGE 4 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

An ALERT is declared under INITIATING CONDITION HA1, Natural or Destructive Phenomena Potentially Affecting Safe Operation, EMERGENCY ACTION LEVEL EAL-4, Predicted or actual breach of Main Cooling Reservoir retaining dike along the North Wall.

HANDOUTS:

Copy of 0ERP01-ZV-IN01, Emergency Classification NOTES:

Copies of E-Plan procedures are to be provided in the Exam.

NRC JPM NO: A9 Rev. 1 PAGE 5 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

Critical steps are identified by (C).

Sequenced steps are identified by (S1, S2, . . .).

SAT/UNSAT Performance Step: 1 Start time: __________

Obtain a copy of 0ERP01-ZV-IN01, Emergency Classification.

Standard:

_____ Student obtains a copy of 0ERP01-ZV-IN01, Emergency Classification.

Comment:

Copies of E-Plan Procedures will be provided in the Exam Room.

Cue:

Notes:

NRC JPM NO: A9 Rev. 1 PAGE 6 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 (C)

Classifies the event in accordance with 0ERP01-ZV-IN01, Emergency Classification, AND indicates the underlying plant conditions/criteria the classification is based on by annotating them in the student handout.

Standard:

_____ Classifies the event as an ALERT (HA1)

AND

_____ On the Student copy of the Initiating Cue sheet, annotates in some way the underlying plant conditions or criteria the classification is based on in the student handout. (EAL-4)

EXAMPLE INITIATING CONDITION HA1, Natural or Destructive Phenomena Potentially Affecting Safe Operation.

EMERGENCY ACTION LEVEL EAL-4, Predicted or actual breach of Main Cooling Reservoir retaining dike along the North Wall.

Comment:

The tornado by itself would be classified as an UNUSUAL EVENT but this would not cover the potential effects of a breach of the Main Reservoir.

Cue:

When the student completes the JPM and turns in his/her results, BEFORE ALLOWING THE STUDENT TO LEAVE, ensure the student has annotated in some way on their student handout, what the underlying plant conditions/criteria are for the declaration made.

Notes:

This declaration must be completed within 15 minutes of the time when the applicant understands the initial conditions and initiating cue.

- TERMINATE THE JPM - Stop time: _________

NRC JPM NO: A9 Rev. 1 PAGE 7 OF 9 VERIFICATION OF COMPLETION Job Performance Measure: A9, DECLARE EMERGENCY ACTION LEVEL Applicant's Name: _________________________

Date Performed: ___________________________

Time to Complete: _________________________

JPM Results: Sat / Unsat Evaluator: _________________________ Signature: _________________________

Date: ____________________

NRC JPM NO: A9 Rev. 1 PAGE 8 OF 9 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK INITIAL CONDITIONS:

Both Units are at 100% power, steady-state.

While a strong cold front was moving through the plant a tornado was sighted moving across the Main Reservoir from the Southeast. The tornado touched down just west of the CWIS but dissipated as it moved into the Protected Area.

As the winds from the tornado died down, the Unit 1 Yard was instructed to assess any damage.

The Unit 1 Yard watch reported the following:

The building around the Lighting Diesel Generator was heavily damaged.

Parts of the Auxiliary Boiler are damaged.

A section of the Main Reservoir west of the CWIS is damaged and water is flowing out of the Main Reservoir into the Protected Area.

Initiating Cue Continued on next page.

NRC JPM NO: A9 Rev. 1 PAGE 9 OF 9 JPM - HANDOUT Continuation of Initiating Cue from previous page.

INITIATING CUE:

This JPM is time-critical. The time limit starts when you (the applicant) understand the Initial Conditions and Initiating Cue.

You are the Unit 1 Shift Manager. Based on the CURRENT Plant conditions as described above:

1. Classify the event at its MINIMUM Emergency Classification (i.e. over-classification will be incorrect).

2. Indicate on the Student copy of the initiating cue sheet the underlying plant condition/s or criteria you used to make your determination of the classification. (i.e. if points were used in determination of classification then explain why the point was used)

Notify your Evaluator when you have completed the JPM.

WRITE ANSWER BELOW:

Rev 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-28-2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 20 NRC Exam Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System/JPM Title Type Safety Code* Function

a. (S1) Manually Load an ESF Bus KA: 062 A4.01 (3.3/3.1) A,D,E,EN,S 6

b. (S2) Cross Connect AFW & Feed 2 SGs from the same AFW Pump E,L,N,S 4S KA: 061 A1.05 (3.6/3.7)

c. (S3) Commence Emergency Boration KA: 004 A4.18 (4.3/4.1) E,N,S 2

d. (S4) Re-Establish Letdown KA: 004 A4.06 (3.6/3.1) A,D,E,S 1

e. (S5) Perform a CCW Valve Operability Test KA: 008 A4.01 (3.3/3.1) N,S 8

f. (S6) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8) D,E,L,P,S 3

g. (S7) Manual Containment Isolation Phase A KA: 103 A3.01 (3.9/4.2) A,E,EN,L,N,S 5

h. (S8) Respond to Radiation Monitor Alarm KA: 073 A4.02 (3.7/3.7) A,D,E,S 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Locally Operate a SG PORV KA: 035 A1.02 (3.5/3.8) D,E,L 4S

j. (P2) Commence a Liquid Waste Release; then a CW Pump trips requiring A,N,R 9 the release to be secured. KA: 068 A4.02 (3.2/3.1)

k. (P3) Place RWST on Recirculation KA: 006 A4.02 (4.0/3.8) D,E,EN 2 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Code Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered Safety Features 1 / 1 / 1 (control room system)

(L)ow-Power/Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator