Examination Level: RO SRO · 0POP02-CV-0001. Related K/A Reference: 2.1.25 [3.9/4.2] Ability to...

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 (see Note)

Type Code*

Describe activity to be performed

Conduct of Operations N,R

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

Conduct of Operations D,P,R

A2 Verify an Excore QPTR Calculation G2.1.20 Ability to interpret and execute procedural steps. (4.6/4.6)

Equipment Control

NOTE: A3 and A7 are the same JPM.

N,R

A3 Using Mechanical Drawings Determine the Isolation Boundaries for a Leak on the RHR System G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (3.5/3.9)

Radiation Control

M,R

A4 Calculate Stay Times based on Dose Rates G2.3.4 Knowledge of radiation exposure limits under 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


Examination Level: RO □ SRO ■ Operating Test Number: LOT 20 NRC Exam

Administrative Topic (see Note)

Type Code*

Describe activity to be performed

Conduct of Operations M,R

A5 Calculate SDM with a Misaligned Control Rod and Determine Applicable Technical Specifications. G2.1.37 Knowledge of procedures, guidelines or limitations associated with Reactivity Management. (4.3/4.69)

Conduct of Operations N,R

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

Equipment Control

NOTE: A3 and A7 are the same JPM.

N,R

A7 Using Mechanical Drawings Determine the Isolation Boundaries for a Leak on the RHR System G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings. (3.5/3.9)

Radiation Control N,R

A8 Approve completed Liquid Waste Release Permit. (alternate path actual release did not match the approved release limits) G2.3.6 Ability to approve release permits. (2.0/3.8)

Emergency Procedures/Plan M,R

A9 Determine EAL 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


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

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.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -


JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS: Handout copy of 0POP02-CV-0001, Makeup to the Reactor Coolant System NOTES:


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.


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:


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: _________


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 ____________________


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 YOU’VE 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:


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


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


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’VE 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.

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.



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).



NOTE:


• 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:


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: __________


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 ____________________


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’VE 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.

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

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 Cycle Date Time

5.2.2.2 Reactor Power Indicator

UPPER DETECTORS

N41U N42U N43U N44U

5.2.3 Current Meter Range Switch Scale (0.1, 0.5, 1 or 5)

5.2.4 Indicated Detector Current (μA)

5.2.2.3 100% Power Detector Current (μA)

5.2.5.2 Sum IU

5.2.5.3 Average IU

5.2.5.1 Normalized (IU) Currents

5.2.5.4 UPPER TILT RATIO (UTR) = Maximum IU = __________________Average IU

LOWER DETECTORS

N41L N42L N43L N44L

5.2.3 Current Meter Range Switch Scale (0.1, 0.5, 1 or 5)

5.2.4 Indicated Detector Current (μA)

5.2.2.3 100% Power Detector Current (μA)

5.2.6.2 Sum IL

5.2.6.3 Average IL

5.2.6.1 Normalized (IL) Currents

5.2.6.4 LOWER TILT RATIO (LTR) =

Maximum IL = __________________Average IL

5.2.7 QPTR = Larger numerical value of the UTR or LTR =

5.2.8 Performed by: Date:

5.2.9 Verified (IV) by: Date:

2 18 Today Now

99.7% U1169

1 1 1 1

1 1 1 1

419 415 399 411

416.5 412.9 394.3 418.1

1.006 1.005 1.012 0.983 4.006 1.0015

1.010

459 431 401 420

457.3 428.4 395.9 418.1

1.004 1.006 1.013 1.005 4.028 1.007

1.006

1.010

Randy White Today

KEY

If the Student calculates LTR to 2 decimal places then the only correct answer is 1.04. If the Student calculates LTR to 3 decimal places then 1.037 to 1.040 is acceptable.

Stpuser

Oval

Stpuser

Oval

Stpuser

Text Box

100% Power Detector Current for N44L should be 396.5 which makes Normalized Current 1.060

Stpuser

Oval

Stpuser

Line

Stpuser

Line

Stpuser

Text Box

Sum IL should be 4.083 Average IL should be 1.021

Stpuser

Oval

Stpuser

Oval

Stpuser

Line

Stpuser

Line

Stpuser

Oval

Stpuser

Oval

Stpuser

Text Box

LTR should be 1.038 and should be the larger numerical value.

Stpuser

Line

Stpuser

Line

Stpuser

Line

Stpuser

Text Box

1

Stpuser

Text Box

2

Stpuser

Text Box

3

Stpuser

Text Box

The QPTR does not meet the Acceptance Criteria of Step 6.1 The QPTR SHALL NOT exceed 1.02.


NUCLEAR TRAINING DEPARTMENT

ADMINISTRATIVE JOB PERFORMANCE MEASURE

TITLE: DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR

JPM NO.: A3

REVISION: 2


JOB PERFORMANCE MEASURE WORKSHEET

JPM Title: DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR

JPM No.: A3

Rev. No:

STP Task:

STP Objective:

2

N/A

N0025 – INTERPRET and use the symbols and acronyms used in One-

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


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.

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




HANDOUTS:

5R169F20000 – P&ID for RHR System

NOTES:



NOTE:


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:



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



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.

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

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.


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 ____________________


JPM - STUDENT HANDOUT




WRITE ANSWER BELOW:


NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: CALCULATE MAXIMUM STAY TIME JPM NO.: A4 REVISION: 1


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


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.

COMPLETION CRITERIA: Calculates the maximum time of 6 hours that the worker may spend in the radiation area without exceeding the Administrative Action Level (AAL) for Annual TEDE.



JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS: 0PGP03-ZR-0050, Radiation Protection Program Survey Map NOTES:



NOTE:


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:


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 hours. 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 hours Cue: Notes: - TERMINATE THE JPM - JPM STOP TIME


VERIFICATION OF COMPLETION Job Performance Measure: A4, CALCULATE MAXIMUM STAY TIME Applicant's Name: Date Performed: Time to Complete:



Date ____________________


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:


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.


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


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 YOU’VE COMPLETED YOUR REVIEW, PRESENT YOUR RESULTS TO THE EXAMINER.



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.




NOTE:


• 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:


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:


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: _________


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: ____________________


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 YOU’VE COMPLETED YOUR REVIEW, PRESENT YOUR RESULTS TO THE EXAMINER.


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


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


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 YOU’VE COMPLETED YOUR REVIEW, PRESENT YOUR RESULTS TO THE EXAMINER.



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




NOTE:


• 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: _________


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: ____________________


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 YOU’VE COMPLETED YOUR REVIEW, PRESENT YOUR RESULTS TO THE EXAMINER. WRITE RESULTS BELOW:

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

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

6.2.2 Data Collection Started: Date Time

6.10 Data Collection Stopped: Date Time

Channel [1]

As Found Indication (%RTP)

Qsec (%) (%RTP)

As Found Difference (%RTP) [2], [3]

As Left Indication (%RTP)

As Left Difference (%RTP)

[4]

Guidelines (%RTP)

Qsec 90% Qsec< 90%

N-41 0.5 +2, -0.5 N-42 0.5 +2, -0.5 N-43 0.5 +2, -0.5 N-44 0.5 +2, -0.5

As Found U1169

Average As Found NI Power

As FoundDifference

(U1169 - Avg NI)As Left U1169

Average As Left NI Power

As LeftDifference

(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. 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%).

Completed by: Date:

Verified by: Date:

22

22

+1.98+1.97+1.95

97.77+2.03

KEY

Stpuser

Oval

Stpuser

Line

Stpuser

Oval

Stpuser

Oval

Stpuser

Line

Stpuser

Line

Stpuser

Text Box

New Calculations

Stpuser

Text Box

Transcribed Incorrectly. See Data Sheet 3, 6.0

Stpuser

Text Box

NI-41 As Left Difference is more than 2%. It is Inoperable until adjusted. Refer to TS 3.3.1, Instrumentation, for Power Range Neutron Flux.

Stpuser

Oval

Stpuser

Line

Stpuser

Oval

Stpuser

Text Box

All other NI Channels As Left Difference is more than +0.5% and must be adjusted at this power level.

Stpuser

Line

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

COMPUTER-BASED Method data (Addendum 1): Initials

1.0 U1118 Verified Reliable per 0PEP02-CU-0001 within the last 8 days.

2.0 0PEP02-CU-0001 performed since power changed regions (if applicable).

3.0 Plant Computer point ICQUG1118O has GOOD quality.

4.0 Delta-T Power from operable Delta-T's 30%.

6.0 ICQUG1118O = Qsec(%) %

7.0 “C” Clarifier present for ICQUG1118O Yes No N/AIF 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/AICCUR0431 = 1.00 Yes No N/AICCUR0451 = 1.00 Yes No N/AICCUR0471 = 1.00 Yes No N/A

Completed by: Date:

KEY

Stpuser

Oval



ADMINISTRATIVE JOB PERFORMANCE MEASURE

TITLE: DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR

JPM NO.: A7

REVISION: 2



JPM Title: DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR

JPM No.: A7

Rev. No:

STP Task:

STP Objective:

2

N/A

N0025 – INTERPRET and use the symbols and acronyms used in One-

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



Location of Testing: N/A










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






HANDOUTS:

5R169F20000 – P&ID for RHR System

NOTES:



NOTE:


JPM START TIME


Obtain 5R169F20000 – P&ID for RHR System.

Standard:

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

Comment:

Cue:

Notes:




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



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.

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

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.



Job Performance Measure: A7, DETERMINE ISOLATION BOUNDARIES FOR LEAK ON RHR

Applicant's Name:

Date Performed:

Time to Complete:



Date ____________________






WRITE ANSWER BELOW:

I

RCP SEAL STANDPIPE 1C

2

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ARH0019C I 8"RH1314882

RCB GRAVITY DRAINS

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NOTE 12 "RH1301881 1

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RESIDUAL HEAT REMOVAL HEAT EXCHANGER 1C 2R161NHX101C

PRIMARY CRHAHRSJ 1

SAMPLE PANEL 12"RH1303K82

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N

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FT Fl HS 852 852 ®

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8"RH1207882 ~ i---------------=~~~~~~~Z8 SIS ACC 8 DISCH

1 NOTE 11

IMB+OMB

TC/D

RCB GRAVITY DRAIN :

( 9F90010<4 D-3(- ] '

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PO

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XRH00688

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RCS PRT 4"RC1021UD7 I 3851 %"CV1269UD7 NOTE 12 & 15

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8 l I

NOTE 13 A NOTE 13 A I ESF- A 1- -yr;l ESF- B 1- -v- j PCC I

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ISSUE DATE

XRH0060A 112"RH1101BB1 ' NOTE 11

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N1RC06 N1RH01

v

REVISION

PI 871

~'I 'I

--------------------,

RCB GRAVITY DRAIN :

< 9F90010<4 D-3( -J" %"ED1251TC7

POI

871

SEC FE 867

ORIG CKR RE DV SE NO_

RH0094A

ISSUE DATE

11" I I

' RH0157 '

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I

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12"X8" RESIDUAL HEAT REMOVAL HEAT EXCHANGER 1A

~~ 2R161NHX101A "'I (RHAHRSJ ~~ 1 PRIMAAY SAMPLE PANEL

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REVISION

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J

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B N1RH01 N1RH02

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4"RH1213KB2

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REFERENCES: t FOR PIPING & INSTRUMENT SYMBOLS

9A310F00001 & 9A310F00002-2. WESTINGHOUSE DRAWING NO_ 1207E17

SHEETS 1,2, & 3. SEC NO. 14926--0284--0100001WN BEC NO. 14926--0284--0100002WN BEC NO. 14926--0284--0100003WN

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SEE DRAWINGS

STP

SOUTH TEXAS PROJECT NUCLEAR OPERATING COMPANY

PRIORITY CAOD FILE NO_ NO. L NO. SCALE

OR!G CKR RE DV SE 1 5R169F20000#1.DGN 0070928 NONE

NOTES:

1. SEE@ NSSS SYS. STANDAAD DESIGN CRITERIA t12, LAYOUT GUIDELINES.

2_ LOCATE TEST CONNECTION AS CLOSE AS POSSIBLE TO ISOLATION VALVE. TEST CONNECTIONS ATTACHED TO BOTTOM OF PIPING TO FACILITATE DRAINING OF LINES.

3. MATING FLANGE FOR VALVE MUST BE 300*, GRADE F316 TO MEET @ PIPE SPEC. G-£78854, REV.2 REQUIREMENTS.

4. LOCATE RH0159 AS CLOSE AS POSSIBLE TO THE RH0148 TEST CONNECT I DN.

5_ ALL INSTRUMENTS ON THIS P & ID HAVE SYSTEM DESIGNATOR RH UNLESS OTHERWISE NOTED.

6- ALL INSTRUMENTS ON THIS P&ID HAVE SEPARATION GROUP DESIGNATOR N UNLESS OTHERWISE NOTED.

7_ DELETED.

8- PROVIDE %" IO FLOW RESTRJCTOR FOR TRANSITION FROM SAFETY CLASS 1TO SAFETY CLASS

9. DELETED-

10. BREAKOUT FLANGES ARE REQUIRED FOR PUMP REMOVAL FOR MAINTENANCE.

11. THIS VALVE IS POWER LOCKED OUT AT THE MCC.

12-STANDPIPE VALVE IS TO BE LOCKED CLOSED IN MODES 5 AND 6,AND IN MODE 4 WHEN THE RCS PRESSURE IS LESS THAN THE STATIC HEAD OF THE WATER COLUMN IN THE STANDPIPE.

13_ THE AUTO CLOSURE FEATURE FOR MOV'S 0060A, 8, C & 0061A, 8, C HAS BEEN DELETED_

14.SOLENOID IS DE-ENERGIZED IN MODES 1,2 AND 3 TO SUPPORT EMERGENCY CORE COOL! NG. ;-o.,-..,-..,-..,-..,-.'-

15_ THESE VALVES MAY NEED TO BE LOCKED CLOSED IN MODE 58 AND MODE 6 TO PREVENT UNBORATED WATER FROM REACHING THE RCS.REF-CALC NC07090.

PIPING AND INSTRUMENTATION DIAGRAM RESIDUAl HEAT REMOVAL SYSTEM

DWG. NO_

5 R 16 9 F 2 0 0 0 0 #1 27 2114/2013 4:44:32 PM JGL

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RH-MOV-0019B

RH-MOV-0031B

RH-MOV-0066B

RH-MOV-0067B

RH-0086B NOT Required

SI-0207B

RH-0062B

RH-MOVs-0060 & 61B

RH-0063 & 64B

RH-0172Locked Closed in Mode 5 & 6

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


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.


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.

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)



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.



NOTE:


• 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: _________


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: ____________________


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

This procedure, when completed, shall be retained.

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 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

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 guidelines, THEN GO TO Step 5.1.12. _____

5.1.11.2 IF sample activity is greater than the activity guidelines, THEN recommend that the tank be reprocessed to meet the activity guidelines, OTHERWISE ENSURE a Deviation Report is completed per 0PCP01-ZA-0021, Radioactive Waste Processing Guidelines, prior to proceeding to Step 5.1.12. _____

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. _____

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

N/A

JB

JB

KEYreading was 5.926E-6

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Total Activity is greater than activity guidelines. See Page 9 of 9 of the Unit 1 Tech Services Count Room Pages of the Release Package.




Initials

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.

Acceptance Criteria Met Initials: _________ Date: ________ Time: ________

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_

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:

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 Criteria Met Initials: _________ Date: ________ Time: ________

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. _____

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: _____

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: _____

Actual Monitor Reading (AMR): _________________Ci/mL

AC

AC

JB Today 30 Min Ago

JB Today 30 Min Ago

JB

JB

JB

1E

7.10 E-8

KEY

limit is <0.06 and reading was 6.5E-2

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Projected Total Body Dose Does NOT meet Acceptance Criteria. See page in Permit Package titled Liquid Effluent Permit - OPEN

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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. _____ Ind. Verif

Conversion Factor is correct. _____ Ind. Verif

5.1.27 Have the Chemical Technician Supervisor or designee independently review the Liquid Effluent Permit. _____

Ind. Verif

5.1.28 Forward package to Shift Manager for signature for the following: _____

Review of the Liquid Effluent Permit

Approval for the discharge

RT-8038 status verified operable.

Shift Manager

Date: Time:

N/A

JB

PR

PR

KEY

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Shift Manager Should NOT sign for the release.

0PSP07-WL-LDP1

LIQUID EFFLUENT PERMIT – OPEN

Permit No 1378 Release Type Batch Unit 1Source 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

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)

PASS – Total ECL Fraction < 10 (1.1E-01)

PASS – Post Dilution Noble Gas Conc < 2.0E-04 ( )

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

KEY

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Projected Total Body Dose is above the limit and has FAILED.

1

U1U1

1E1E

Today/90 Min Ago

9.570 E-071.985 E-06

1.993 E-069.905 E-07

5.926 E-06

1

KEY

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Total activity should be less than 5.0 E-6. See Procedure step 5.1.11


NUCLEAR TRAINING DEPARTMENT ADMINISTRATIVE JOB PERFORMANCE MEASURE TITLE: DECLARE EMERGENCY ACTION LEVEL JPM NO.: A9 REVISION: 1


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


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.



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.




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:


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: _________


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: ____________________


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.


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


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 Code*

Safety 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 KA: 061 A1.05 (3.6/3.7)

E,L,N,S 4S

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 the release to be secured. KA: 068 A4.02 (3.2/3.1)

A,N,R 9

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 (C)ontrol Room (D)irect from Bank (E)mergency or abnormal in-plant (EN)gineered Safety Features (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 Exams (R)CA (S)imulator

4-6 / 4-6 / 2-3 ≤ 9 / ≤ 8 / ≤ 4 ≥ 1 / ≥ 1 / ≥ 1 ≥ 1 / ≥ 1 / ≥ 1 (control room system) ≥ 1 / ≥ 1 / ≥ 1 ≥ 2 / ≥ 2 / ≥ 1 ≤ 3 / ≤ 3 / ≤ 2 (randomly selected) ≥ 1 / ≥ 1 / ≥ 1

Rev 0



Exam Level: RO □ SRO-I ■ SRO-U □ Operating Test No.: LOT 20 NRC Exam



Safety Function


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

E,L,N,S 4S

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



h. (S8) Respond to Radiation Monitor Alarm KA: 073 A4.02 (3.7/3.7) A,D,E,S 7


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


A,N,R 9






Rev 0



Exam Level: RO □ SRO-I □ SRO-U ■ Operating Test No.: LOT 20 NRC Exam



Safety Function






A,N,R 9






Rev 0

STP LOT-20 NRC Systems JPM Description

Control Room Systems JPMs (S1) Manually Load an ESF Bus – Alternate Path

Demonstrate the ability to ensure equipment has properly loaded on to an ESF 4.16KV Bus in accordance with 0POP04-AE-0001, First Response To Loss Of Any Or All 13.8 KV Or 4.16 KV Bus.

(S2) Cross Connect AFW & Feed 2 SGs from the same AFW Pump Demonstrate the ability to control AFW flow to multiple SGS from one AFW Pump in accordance with 0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance.

(S3) Commence Emergency Boration Demonstrate the ability to align boration flow through the alternate boration isolation valve in accordance with 0POP04-CV-0003, Emergency Boration.

(S4) Re-Establish Letdown – Alternate Path Demonstrate the ability to establish normal letdown flow after an SI in accordance with 0POP05-EO-ES11, SI Termination.

(S5) Perform a CCW Valve Operability Test Demonstrate the ability to perform a CCW System Valve Operability Surveillance in accordance with 0PSP03-CC-0008, Component Cooling Water System Train 1B(2B) Valve Operability Test.

(S6) Transfer to Hot Leg Recirculation Demonstrate the ability to align ECCS Hot Leg Recirculation in accordance with 0POP05-EO-ES14, Transfer to Hot Leg Recirculation.

(S7) Manual Containment Isolation Phase A – Alternate Path Demonstrate the ability to manually isolate containment penetrations that were not isolated properly following an SI in accordance with 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 1 and 5.

(S8) Respond to Radiation Monitor Alarm – Alternate Path Demonstrate the ability to respond to Radiation Transmitter alarms on the RM-11 Radiation Monitor Panel in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response.

NOTE: The following JPMs will be performed in pairs; S2 & S7 together, S3 & S5 together and S6 & S8 together. JPMs S1 and S4 will be performed by themselves.

Rev 0

STP LOT-20 NRC Systems JPM Description

In Plant Systems JPMs (P1) Locally Operate a SG PORV

Demonstrate the ability to locally operate a SG PORV in accordance with 0POP05-EO-EC00, Loss of All AC Power, Addendum 6.

(P2) Commence a Liquid Waste Release; then a CW Pump trips requiring the release to be secured. – Alternate Path Demonstrate the ability to perform a rad waste release and terminate the release when needed in accordance with 0POP02-WL-0100, Liquid Waste Release.

(P3) Place RWST on Recirculation Demonstrate the ability to place the Refueling Water Storage Tank on purification recirculation in accordance with 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System.

NRC JPM NO: S1 Rev.2 PAGE 1 OF 12


OPERATING JOB PERFORMANCE MEASURE

TITLE: MANUALLY LOAD AN ESF BUS

JPM NO.: S1

REVISION: 2

LOCATION: SIMULATOR



JPM Title: MANUALLY LOAD AN ESF BUS

JPM No.: S1

Rev. No:

STP Task:

2

T75050, Respond to ESF DG Alarms

STP Objective: CRO 45200, Respond to a DG Trouble Alarm

Related K/A Reference: 062 A4.01 [3.3/3.1] Ability to manually operate and/or monitor in the

control room: All breakers (including available switchyard).

and/or 064 A1.01 [3.0/3.1] Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: ED/G lube oil temperature and pressure.

References: 0POP04-AE-0001, First Response to Loss of Any or All 13.8 kV or 4.16 kV Bus

0POP09-AN-03M3-A-4, Annunciator Lampbox 3M3 Response Instructions



Location of Testing: Simulator

Time Critical Task: No

Alternate Path JPM: Yes

Validation Time: 15 min.




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’VE COMPLETED THE TASK.

INITIAL CONDITIONS:

The plant is in Mode 1 operating at 100% power. The feeder breaker from 13.8 kV Standby Bus 1G has tripped open causing a loss of normal power to 4160v ESF Bus E1B. The control switch for this breaker on CP-010 has been placed in PTL.

#12 ESF DG has JUST started. A Plant Operator (Yard Watch) has been dispatched to # 12 ESF DG, but has not yet arrived.

INITIATING CUE:

The Unit Supervisor has directed you to ensure 4160v ESF Bus 1B is energized AND loaded by performing 0POP04-AE-0001, Steps 3, 4 and 5.

COMPLETION CRITERIA:

Manually loads B Train Equipment on 4.16KV Bus Train B and immediately stops ESF DG # 12 when low lube oil pressure is noted.




HANDOUTS:

Use Simulator Procedures for:

0POP04-AE-0001, First Response to Loss of Any or All 13.8 kV or 4.16 kV Bus

0POP09-AN-03M3-A-4, Annunciator Lampbox 3M3 Response InstructionsNOTES: 1. This JPM is formatted for dynamic simulator performance only. The cues provided are

related to communications and other general information needed for dynamic performance.NO indication type cues are provided.

2. This JPM is an Alternate path JPM. Basically, the student will load the 4160v ESF Bus fromit’s respective DG. The Train B RCFCs and CCW Pump will have to be manually started.Once this is done a low lube oil condition will develop on the DG causing a DG Troublealarm. The student should refer to the annunciator response, determine the DG must betripped and carry out this action. This is the termination point of the JPM.

3. It is important that the examiner brief the student that alarms that come in are theresponsibility of the student unless specifically told otherwise by the examiner.

IC SET UP: 1. Pick a 100% IC. Go to RUN on the simulator and insert the following malfunctions:

Inhibit auto start of CCW Pump 1B (50-KA-05).

Set Time Delay for RCFC 11B and 12B Mode 2 start (RDPUTIMERU76358DELAY) to80,000 (seconds).

Set 03M3 A6, DG 12 TRBL, (LA03M3-A-6) to annunciate 10 seconds after CCW Pump1B is started.

Set DG 12 Lube Oil Pressure Meter (H_A1_A1_M72_1) to 5.0 10 seconds after CCWPump 1B is started.

2. Open the supply breaker from 13.8KV STBY Bus 1G to 4.16KV ESF Bus E1B.3. After the sequencer has timed out, about 5 minutes, go to FREEZE on the simulator.4. Store the IC to an empty store point.



SIMULATOR SETUP: 1) This JPM is scheduled to be performed by itself.

2) Ensure Radio volume for both stations are set to a reasonable level.

3) Ensure the PA buttons on the communications consoles are taped to help eliminate usage.

4) Reset to IC #223 and verify: Step counter position annunciator light is out on CP-005 Red light at the end of CP-010 is out

5) Check and clean the following procedures (JPM specific):

0POP04-AE-0001, First Response to Loss of Any or All 13.8 kV or 4.16 kV Bus 0POP09-AN-03M3-A-4, Annunciator Lampbox 3M3 Response Instructions

6) FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarmsthen place the simulator in Freeze again.

Do not go to Run for JPM performance until the student performing this JPM has read theintial conditions, task statement, etc. and is ready to proceed in order to limit the heatup ofDG lube oil and jacket cooling water.

7) When the student and the examiners are ready to proceed, place the simulator in RUN.No further action will be needed as the malfunction is on a conditional trigger. An ESF DGTrouble alarm and loss of lube oil pressure will occur 10 seconds after starting CCW Pump1B.

INSTRUCTOR ACTIONS: As Yard Operator, if contacted by the Control Room AFTER THE DG TROUBLE ALARM COMES IN, inform them you just entered the DG Room, the Diesel is running and there is a large puddle of oil on the floor.



NOTE:

Critical steps are identified by (C).

JPM START TIME _____


CHECK 4.16 KV ESF Bus Status: (step 3.0)

ANY 4.16 KV ESF Bus NOT energized from offsite power (VERIFY the voltage on allthree phases of each ESF Bus).

VERIFY Applicable STBY DG(s) running. VERIFY Applicable STBY DG(s) output breaker(s) closed to the associated 4.16 KV

ESF bus.Standard:

_____ Determines 4.16 KV ESF Bus Train B is not energized from offsite power.

_____ Determines ESF DG #12 is running.

_____ Determines ESF DG #12 output breaker is closed.

Comment:

This is the procedure entry point for the specified task.

Cue:

Notes:




Check ECW Status: (step 4.0)

ECW Pump – RUNNING ECW Pump Discharge Isolation Valves - OPEN ECW Blowdown Isolation Valves - CLOSED

Standard:

_____ Checks ECW Pump 1B running.

_____ Checks ECW Pump 1B Discharge Valve, EW-MOV-0137, open.

_____ Checks ECW Pump 1B Blowdown Isolation Valve, EW-FV-6936, closed.

Comment:

Cue:

Notes:




Check Sequencer Loading for any running STBY DG per Addendum 1. (step 5)

Standard:

_____ Refers to Addendum 1 and begins checking ‘B’ Train equipment status.

480V Load Centers ECW Pump• RCFCs (11B & 12B)• *CCW Pump* AFW Pump Essential Chilled Water Pumps EAB HVAC Supply Fans EAB HVAC Return Fans Control Room Supply, Return and Cleanup HVAC Fans FHB Main Exhaust HVAC Fans Essential Chillers

Comment:

1. Train B RCFCs 11B & 12B and CCW Pump 1B failed to auto start and must be started manually.

2. 10 seconds after CCW Pump 1B is started, the DG TRBL alarm will come in with a loss of lube oil pressure. Starting CCW Pump 1B is the critical portion of this step.

Cue:

Notes:

* Denotes critical portion of this JPM step.* Steps are bulleted and can be performed in any order.




DG 12 TRBL annunciator alarm

Standard:

_____ Acknowledges DG #12 Trouble alarm and refers to Annunciator Response Instructions

Comment:

The DG Trouble alarm is the initiating event for the alternate path. This will occur 10 seconds after the student starts CCW Pump 1B.

This alarm will have already come in due to other conditions, but will re-flash and annunciate when lube oil pressure is lost. The re-flash may be ‘masked’ by other alarms clearing and/or flashing.

Cue:

Notes:




If lube oil pressure is less than 30 psig then ensure the DG is tripped.

Standard:

_____ Determines lube oil pressure is less than 30 psig and trips the ESF DG #12.

Comment:

This is an immediate action step of the Annunciator Response Instructions

Cue:

If the student seeks Unit Supervisor concurrence to perform actions, inform him/her to carry out the prescribed actions in the procedure.

Notes:

-TERMINATE THE JPM- Stop Time: ______



Job Performance Measure: MANUALLY LOAD AN ESF BUS

Applicant's Name: _____________________________________

Date Performed: _______________________________________

Time to Complete: _____________________________________


Evaluator: Signature

Date





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

INITIAL CONDITIONS:

The plant is in Mode 1 operating at 100% power. The feeder breaker from 13.8 kV Standby Bus 1G has tripped open causing a loss of normal power to 4160v ESF Bus E1B. The control switch for this breaker on CP-010 has been placed in PTL.

#12 ESF DG has JUST started. A Plant Operator (Yard Watch) has been dispatched to # 12 ESF DG, but has not yet arrived.

INITIATING CUE:

The Unit Supervisor has directed you to ensure 4160v ESF Bus 1B is energized AND loaded by performing 0POP04-AE-0001, Steps 3, 4 and 5.


NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: CROSS CONNECT AFW & FEED 2 SGs FROM THE SAME AFW PUMP JPM NO.: S2 REVISION: 1 LOCATION: SIMULATOR


JOB PERFORMANCE MEASURE WORKSHEET JPM Title: CROSS CONNECT AFW & FEED 2 SGs FROM THE SAME AFW

PUMP

JPM No.: S2

Rev. No: 1

STP Task: T43750, Monitor the AFW System

STP Objective: CRO 061, During all modes of plant operating conditions, operate the

Auxiliary Feedwater System in accordance with the plant operating procedures and technical specifications.

Related K/A Reference: 061 A1.05 [3.6/3.7] Ability to predict and/or monitor changes in

parameters (to prevent exceeding design limits) associated with operating the AFW controls including:

AFW flow/motor amps.

References: 0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance





Alternate Path JPM: No




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’VE COMPLETED THE TASK. INITIAL CONDITIONS: A SBLOCA has occurred in Unit 1. There was a fault with Actuation Train B and AFW Pump #12 failed to manually start. AFW Pump #12 has been placed in PTL. INITIATING CUE: The Unit Supervisor has directed you to cross connect and feed SGs 1A and 1B with AFW Pump 11 until SGs 1A and 1B Narrow Range Levels are between 22% and 50% using 0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance.

COMPLETION CRITERIA: Manually feeds SGs 1A and 1B from AFW Pump #11 without exceeding 675 gpm total flow to both SGs.



JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Use Simulator Procedures for:

0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance. NOTES: 1. JPMs S2 and S7 are ruin together. 2. Both JPMs are formatted for dynamic simulator performance only. The cues provided are

related to communications and other general information needed for dynamic performance. NO indication type cues are provided.

3. In the IC for this JPM, S2, open breaker 6 from DP-1203 (schematic ee_dp1203) (ee_dp1203tc89_6). Insert 08-03-02, Loss of AFW Pump #12. Insert a SBLOCA of about 250 gpm. Actuate SI. Place AFW Pump #11 in PTL temporarily so that levels in SGs 1A and 1B stay below 14% while SGs 1C and 1D trend above 22%. Place AFW Pump #11 back in Auto and manually control 1A, 1C and 1D AFW flow to 50 to 100gpm. Place simulator in FREEZE and store IC.

4. JPM S7 is an Alternate path JPM. Basically, the student will verify containment isolation Phase A using 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation, and 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 1, Phase A Isolation Verification.



SIMULATOR SETUP: 1) JPMs S2 and S7 are to run together. The following steps will set up the simulator for BOTH

JPMs.





0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance.

6) FROM THE BOOTH:

Place simulator in RUN

Quickly silence/acknowledge/reset alarms

Place one FHB exhaust damper in manual and closed

Place simulator in FREEZE

NOTE: Do not go to Run for JPM performance until the student performing this JPM has read the initial conditions, task statement, etc. and is ready to proceed.

7) When the student and the examiners are ready to proceed, place the simulator in RUN No further action will be needed.

INSTRUCTOR ACTIONS: None.



NOTE:


SAT/UNSAT Performance Step: 1 Start Time: _____ Obtain a copy of 0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance.

Standard: _____ The operator obtains a copy of 0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance.

Comment:

Cue: Hand out the copy of 0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance, Addendum 5, Cross Connecting AFW.

Notes:

SAT/UNSAT Performance Step: 2 ENSURE SI is reset. (add 5 step 1) Standard: _____ Ensures SI is reset on at least A and C Train. Comment: Cue: Notes: SI will have already been reset.


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 ENSURE SG LO-LO level AFW actuations are reset. (add 5 step 2) Standard: _____ Ensures SG LO-LO level AFW actuations are reset on at least A and C Train. Comment: Cue: Notes:

SG LO-LO level AFW actuation will have already been reset. SAT/UNSAT Performance Step: 4 VERIFY 5M24 D-4, “C20 AMSAC BLOCKED” illuminated. (add 5 step 3) Standard: _____ Verifies that AMSAC BLOCKED annunciator is illuminated. Comment: AMSAC will have timed out and be blocked.

Cue:

Notes: 5M24 D-4, “C20 AMSAC BLOCKED” illuminates when the 360 second time delay for the AMSAC disarming relay times out. Computer point AMJR0511A would indicate “BLKD”


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5 (C) CLOSE AFW REG valve for the SG(s) that will be fed via the cross-connect(s). (add 5 step 4) Standard: _____ Closes SG 1A AF-FV-7525 and SG 1B AF-FV-7524. Comment:

Cue:

Notes: Only SG 1B AFW REG valve has to be closed per the procedure step. SAT/UNSAT Performance Step: 6 (C) ENSURE AFW OCIV OPEN for required SG(s). (add 5 step 5) Standard: _____ Ensures SG 1A AFW OCIV AF-MOV-0048 is open and opens SG 1B AFW OCIV AF-MOV-0065. Comment: SG 1A AFW OCIV AF-MOV-0048 will already be open.

Cue:

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 7 (C)

ESTABLISH AFW flowpath to the required SG(s):

OPEN “X CONN” on the SG with the running AFW pump.

OPEN “X CONN” to the SG(s) to be supplied. (add 5 step 6)

Standard: _____ Opens SG 1A AFW Cross Connect AF-FV-7517 and SG 1B AFW Cross Connect AF-FV-

7516. Comment:

Cue:

Notes: SAT/UNSAT Performance Step: 8 (C)

THROTTLE OPEN AFW REG valve(s) while maintaining total AFW flow from the feeding AFW pump to LESS THAN 675 gpm. (add 5 step 7)

Standard: _____ Throttles open SG 1A AF-FV-7525 and SG 1B AF-FV-7524 to feed SGs 1A and 1B.

Maintains total AFW Flow from AFW Pump #11 at less than 675 gpm. Comment: It is not necessary to wait until SG levels in 1A and 1B get to within 22% and 50% as long as the student demonstrates that total AFW flow from AFW Pump #11 can be maintained less than 675 gpm.

Cue:

Notes: -TERMINATE THE JPM- Stop Time: ______


VERIFICATION OF COMPLETION Job Performance Measure: CROSS CONNECT AFW & FEED 2 SGs FROM THE SAME

AFW PUMP Applicant's Name: _____________________________________ Date Performed: _______________________________________ Time to Complete: _____________________________________ JPM Results: Sat / Unsat Evaluator: Signature

Date


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’VE COMPLETED THE TASK. INITIAL CONDITIONS: A SBLOCA has occurred in Unit 1. There was a fault with Actuation Train B and AFW Pump #12 failed to manually start. AFW Pump #12 has been placed in PTL. INITIATING CUE: The Unit Supervisor has directed you to cross connect and feed SGs 1A and 1B with AFW Pump 11 until SGs 1A and 1B Narrow Range Levels are between 22% and 50% using 0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance.


NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: COMMENCE EMERGENCY BORATION JPM NO.: S3 REVISION: 1 LOCATION: SIMULATOR


JOB PERFORMANCE MEASURE WORKSHEET JPM Title: Commence Emergency Boration

JPM No.: S3

Rev. No: 1

STP Task: 85450, Perform an Emergency Boration

STP Objective: CRO 85450, Perform an Emergency Boration per POP04-CV-0003

Related K/A Reference: 004 A4.18 [4.3/4.1] Ability to manually operate and/or monitor in the

Control Room: Emergency borate valve

References: 0POP09-AN-05M3, ANNUNCIATOR LAMPBOX 05M3 RESPONSE INSTRUCTIONS, E4, BANK INSERT LO-LO

0POP04-CV-0003, EMERGENCY BORATION

Core Operating Limits Report Figure 5, Control Rod Insertion Limits versus Power Level





Alternate Path JPM: No




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’VE COMPLETED THE TASK. INITIAL CONDITIONS: A rapid load reduction has just been completed. Annunciator lampbox 5M03-E4 BANK INSRT LO- LO just came in. INITIATING CUE: The Unit Supervisor directs you to respond to annunciator lampbox 05M03-E4, BANK INSRT LO-LO.

COMPLETION CRITERIA: Initiates Emergency Boration flow to the Reactor Coolant System.



JOB PERFORMANCE MEASURE CHECK SHEET HANDOUTS:

• 0POP09-AN-05M3, ANNUNCIATOR LAMPBOX 05M3 RESPONSE INSTRUCTIONS, E4, BANK INSERT LO-LO

• Core Operating Limits Report Figure 5, Control Rod Insertion Limits versus Power Level

• 0POP04-CV-0003, EMERGENCY BORATION (NOTE: Use procedure in simulator)

Notes: This JPM is formatted for dynamic simulator performance only. The cues provided are related to communications and other general information needed for dynamic performance. NO indication type cues are provided. SIMULATOR SETUP: 1. JPMs S3 and S5 are to be run together. The following steps will set up the simulator for

BOTH JPMs.

2. Ensure Radio volume for both stations are set to a reasonable level.

3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.

4. Reset to IC #221 and verify:

• Red light at the end of CP-010 is out. • ICS Annunciators have stopped counting up.

5. Check and clean the following procedures: • 0POP04-CV-0003, Emergency Boration

6. Place simulator in run. Silence/acknowledge/reset alarms as appropriate.

7. Place the simulator in ‘FREEZE’ until the examiners are ready to proceed.

8. There is no simulator lesson for either of these JPMs. INSTRUCTOR ACTIONS:

None.



NOTE:


SAT/UNSAT Performance Step: 1 Start Time: _____ Obtain a copy of 0POP09-AN-05M3, Annunciator Lampbox Response Instructions.

Standard: _____ The operator obtains a copy of 0POP09-AN-05M3, Annunciator Lampbox Response

Instructions.

Comment:

Cue:

There are two procedure handouts with this JPM.

ONLY 0POP09-AN-05M3, Annunciator Lampbox Response Instructions to be handed out at this time.

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 COMPARE rod bank positions on DRPI with Rod Insertion Limits. (Annunciator Response Step 1) Standard: _____ Compares Control Rod Bank positions shown on DRPI display to Reactor Thermal Power

Level and determine the Control Rod Insertion Limits in Core Operating Limits Figure 5 have been exceeded.

Comment: Core Delta T Power should be used to determine current Reactor Power level since the transient may affect the accuracy of Power Range NI detectors. Cue: Once the examinee has located Figure 5 in the Core Operating Limits Report hand out a copy of Figure 5. Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 IF any RCCA bank is positioned below the Rod Insertion Limits for the current reactor power, THEN GO TO 0POP04-CV-0003, Emergency Boration.

Standard: _____ Transitions to POP04-CV-0003, Emergency Boration. Comment:

Cue:

Notes:

Use the procedure in the Simulator for completing JPM. SAT/UNSAT Performance Step: 4 CHECK Boric Acid Storage Tank – OPERABLE OR AVAILABLE (Step 1.0) Standard: _____ VERIFY Boric Acid Tanks are available Comment:

Cue:

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5 ENSURE CVCS Charging Line “OCIV MOV-0025” - OPEN (Step 2.0) Standard: _____ VERIFY Charging OCIV CV-MOV-0025 is OPEN. Comment:

Cue:

Notes: SAT/UNSAT Performance Step: 6 ENSURE One Of The Following Valves Are Open:

• Normal Charging “LOOP A ISOL MOV-0003.”

OR

• Alternate Charging “LOOP C ISOL MOV-0006.” (Step 3.0) Standard: _____ VERIFY Normal Charging Loop A Isolation Valve CV-MOV-0003 is OPEN. Comment:

Cue:

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 7 CHECK Charging Pump - RUNNING (Step 4.0) Standard: _____ VERIFY a Charging Pump running. Comment:

Cue:


START a BA Transfer Pump (Step 5.1) Standard: _____ START a Boric Acid Transfer Pump. Comment:

Cue:

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 9 (C) OPEN "ALT BORATION ISOL MOV-0218" (Step 5.2) Standard: _____ OPEN Alternate Boration Isolation Valve CV-MOV-0218. Comment:

Cue:

Notes: SAT/UNSAT Performance Step: 10 MAINTAIN Greater Than 50 gpm On FI-0205A Using "CHG FLOW CONT FK-0205" (Step 6.0) Standard: _____ MAINTAIN greater than 50 gpm on FI-0205. Comment: Charging Flow Control Valve CV-FV-0205 will maintain a minimum of 50 gpm in automatic. Emergency Boration flow will continue until the “BANK INSRT LO-LO” alarm clears. The JPM terminates once flow is commenced due to the time it would take to clear the alarm.

Cue:

Notes: -TERMINATE THE JPM- Stop Time: ______


VERIFICATION OF COMPLETION Job Performance Measure: Commence Emergency Boration Applicant's Name: _____________________________________ Date Performed: _______________________________________ Time to Complete: _____________________________________ JPM Results: Sat / Unsat Evaluator: Signature

Date


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’VE COMPLETED THE TASK. INITIAL CONDITIONS: A rapid load reduction has just been completed. Annunciator lampbox 5M03-E4 BANK INSRT LO- LO just came in. INITIATING CUE: The Unit Supervisor directs you to respond to annunciator lampbox 05M03-E4, BANK INSRT LO-LO. .



JOB PERFORMANCE MEASURE

TITLE: RE-ESTABLISH LETDOWN (ES-11)

JPM NO.: S4

REVISION: 1 LOCATION: SIMULATOR



JPM Title: RE-ESTABLISH LETDOWN (ES-11)

JPM No.: S4

Rev. No.: 1

STP Task: T48700 - Place the CVCS in service.

STP Objective: CRO 004 - During all modes of plant operating conditions, operate the CVCS in accordance with plant operating procedures and technical specifications.

Related K/A Reference: 004 A4.06 [3.6/3.1] Ability to manually operate and/or monitor in the control

room: Letdown isolation and flow control valves.

References: 0POP05-ES-ES11, SI Termination

0PO04-RP-0002, Loss of Automatic Pressurizer Level Control











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’VE COMPLETED THE TASK.

INITIAL CONDITIONS:

An inadvertent Reactor Trip and Safety Injection occurred. The Crew has transitioned from 0POP05-EO-EO00, Reactor Trip or Safety Injection, to 0POP05-EO-ES11, SI Termination, and are currently at step 12. The crew restored charging flow for inventory control and Pressurizer Level is slowly rising. INITIATING CUE:

The Unit Supervisor directs you to continue with 0POP05-EO-ES11, SI Termination, at Step 12, Check if letdown can be established.



Normal Letdown Flow is restored with manual control of CV-PCV-0135, Letdown Pressure Control Valve.



HANDOUTS: Use Simulator Procedures for:

• 0POP05-EO-ES11, SI Termination

NOTES: 1. This JPM is formatted for dynamic simulator performance only. The cues provided are related to

communications and other general information needed for dynamic performance. NO indication type cues are provided.

2. This JPM is an Alternate path JPM. Basically, the student will perform Addendum 2 of 0POP05-EO-ES11, SI Termination, including RNO Steps, to place normal letdown in service.

SIMULATOR SETUP: 1. This JPM is scheduled to be performed by itself.




• Step counter position annunciator light is out on CP-005 • Red light at the end of CP-010 is out

5. Check and clean the following procedures (JPM specific):

• 0POP05-EO-ES11, SI Termination. Once the procedure is clean place check marks up to step 11. Place procedure on the US console.

6. FROM THE BOOTH, place simulator in run and quickly silence/acknowledge/reset alarms then place the simulator in Freeze again.

7. From the Orchid Instructor Station, in INSTRUCTOR MODE, go to Panel 4 and enter 0.0 for the Set Point on CV-PCV-0135. This has to be done for each time JPM is run.

8. Do not go to Run for JPM performance until the student performing this JPM has read the initial conditions, task statement, etc. and is ready to proceed.

9. When the student and the examiners are ready to proceed, place the simulator in RUN. INSTRUCTOR ACTIONS: None.



NOTE:


SAT/UNSAT Performance Step: 1 Start Time: _______

Obtain a copy of 0POP05-EO-ES11, SI Termination.

Standard: _____ The operator obtains a copy of 0POP05-EO-ES11, SI TERMINATION.

Comment:

The operator will use the simulator copy of 0POP05-EO-ES11, SI Termination. The copy is on the US console and is marked off up to step 11. Per the initiating cue the student should start at step 12.

Cue:

Notes:


CHECK if letdown can be established: (step 12)

• Pressurizer level – GREATER THAN 22% [50%]

• ESTABLISH normal letdown per ADDENDUM 2, ESTABLISH NORMAL LETDOWN

Standard: _____ The operator determines that Pressurizer level is greater than 22% [No Adverse Containment] and

determines normal letdown can be placed in service by proceeding to Addendum 2.

Comment: The operator will determine normal letdown can be placed in service by checking charging available (charging is in service per the initiating cue) and CCW available for the letdown heat exchanger.

Cue:

Notes:


JOB PERFORMANCE MEASURE SAT/UNSAT Performance Step: 3 VERIFY charging - IN SERVICE (add. 2 step 1)

Standard:

_____ The operator verifies charging is in service.

Comment:

Cue:

Notes: Charging will be in service with about 50 gpm flow per the initiating cue.


VERIFY at least one train of CCW – ALIGNED TO THE LETDOWN HEAT EXCHANGER (add. 2 step 2)

Standard:

_____ The operator verifies CCW Pumps running and then opens CC-MOV-0235 and CC- MOV-0236 to align CCW to the letdown heat exchanger per the RNO step.

Comment:

Cue:

Notes:

All CCW Pumps will be running.

CC-MOVs-0235 & 0236 are non-essential CCW Header isolation valves that are normally open but are closed on a Safety Injection.


JOB PERFORMANCE MEASURE SAT/UNSAT Performance Step: 5 CLOSE RCS letdown orifice isolation valves. (add. 2 step 3)

Standard: _____ The operator closes valves: FV-0012, FV-0013 and MOV-0014 on CP-004.

Comment:

Cue:

Notes: FV-0012 is the only valve that is actually open prior to this step. SAT/UNSAT Performance Step: 6 VERIFY letdown pressure - WITHIN 100 psi OF RCS PRESSURE.

• (35 ft EAB Relay Room North Wall, Panel ZLC505)

• "1(2)-CV-PI-0469" "EXCESS/NORMAL LETDN PRESSURE" (add. 2 step 4)

Standard: _____ The operator verifies the pressure on "1(2)CV-PI-0469 EXCESS/NORMAL LETDN PRESSURE" is

within 100 PSI of RCS pressure.

Comment:

1(2)CV-PI-0469 is in the EAB 35 ft Relay Room North Wall, Panel ZLC505. A Plant Operator is normally dispatched to read the pressure on PI-0469

Cue:

As a plant operator report that CV-PI-0469 reads 2200 psig. (Or give a value that would be within 100psi of RCS pressure.)

Notes: RCS pressure should be about 2235 psig by this time.


JOB PERFORMANCE MEASURE SAT/UNSAT Performance Step: 7 (C) PLACE the letdown pressure controller in MANUAL, and THROTTLE letdown pressure control valve 1(2)-PCV-0135 to 50%. (add. 2 step 5 & 6)

Standard: _____ The operator pushes the "MAN" button on Letdown Pressure Controller PCV-0135 and adjusts the

demand to 50%.

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 8 (C) OPEN letdown line containment isolation valves.

• OCIV MOV-0024

• ICIV MOV-0023 (add. 2 step 7)

Standard: _____ The operator opens ICIV MOV-0023 and OCIV MOV-0024.

Comment:

Cue:

Notes: OCIV MOV-0024 and ICIV MOV-0023 are normally open but will be closed due to the Safety Injection.

SAT/UNSAT Performance Step: 9 OPEN letdown line loop isolation valves.

• LETDN ISOL LCV-0465

• LETDN ISOL LCV-0468 (add. 2 step 8)

Standard: _____ The operator opens LETDN ISOL LCV-0465and LCV-0468.

Comment:

Cue:

Notes:

These valves will already be open.


JOB PERFORMANCE MEASURE SAT/UNSAT Performance Step: 10 (C) OPEN letdown orifice header isolation valve.

• LTDN ORIF HDR ISOL FV-0011 (add. 2 step 9)

Standard: _____ The operator opens LTDN ORIF HDR ISOL FV-0011.

Comment:

Cue:

Notes: LTDN ORIF HDR ISOL FV-0011 will be closed due the inadvertent SI signal.


OPEN desired letdown line orifice isolation valve: • FV-0012 • FV-0013 • MOV-0014 (add. 2 step 10)

Standard: _____ The operator opens FV-0012 on CP-004.

Comment: This step must be performed in rapid sequence with the next step to prevent letdown flashing or lifting of the letdown relief valve to PRT.

Cue:

If the student elects to open FV-0013 or MOV-0014, as the US, direct the 120-150 gpm letdown orifice be placed in service, FV-0012.

Notes:




THROTTLE letdown pressure controller to maintain 375 to 385 psig. (add. 2 step 11)

Standard: _____ The operator adjusts pressure controller PCV-0135 to establish a letdown pressure of 375 to 385

psig.

Comment: This step must be performed in rapid sequence with the previous step to prevent letdown flashing or lifting of the letdown relief valve to PRT.

If there is letdown flashing from low pressure or the letdown relief valve lifts it would not be a failure of this critical step as long as letdown pressure is controlled between 375 to 385 psig prior to going to the next step.

Cue:

Notes: Operator should reduce controller output (throttle PCV-135 in the closed direction) if Letdown Pressure is below 375 psig.

Operator should raise controller output (throttle PCV-135 in the open direction) if Letdown Pressure is above 385 psig.




OPEN additional letdown orifice isolation valves as desired. (add. 2 step 12)

Standard: _____ The operator will open additional orifice isolation valves if desired.

Comment:

Cue: If the student starts to open additional letdown orifice isolation valves, then as the US, tell the student that opening additional letdown orifice isolation valves is not desired at this time.

Notes:

SAT/UNSAT Performance Step: 14 PLACE letdown pressure controller in AUTO. (add. 2 step 13)

Standard: _____ The operator places the letdown pressure controller in AUTO but then realizes that auto control is

not working.

Comment:

Cue:

Notes: A malfunction has been inserted that affects the letdown pressure control valve when placed in auto.



SAT/UNSAT Performance Step: 15 (C) CONTROL letdown pressure controller in MANUAL. (add. 2 step 13 RNO)

Standard: _____ The operator places the letdown pressure controller in MANUAL and restores letdown pressure to

between 375 and 385 psig.

Comment: The letdown pressure controller is very sensitive when in MANUAL control.

Cue:

Notes:

- TERMINATE THE JPM - Stop time: ________


JOB PERFORMANCE MEASURE Job Performance Measure: RE-ESTABLISH LETDOWN (ES-11) Applicant's Name: _____________________________________ Date Performed: _______________________________________ Time to Complete: _____________________________________ JPM Results: Sat / Unsat Evaluator: Signature

Date



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’VE COMPLETED THE TASK. INITIAL CONDITIONS:

An inadvertent Reactor Trip and Safety Injection occurred. The Crew has transitioned from 0POP05-EO-EO00, Reactor Trip or Safety Injection, to 0POP05-EO-ES11, SI Termination, and are currently at step 12. The crew restored charging flow for inventory control and Pressurizer Level is slowly rising. INITIATING CUE:

The Unit Supervisor directs you to continue with 0POP05-EO-ES11, SI Termination, at Step 12, Check if letdown can be established.


NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: PERFORM CCW VALVE OPERABILITY SURVEILLANCE JPM NO.: S5 REVISION: 1 LOCATION: SIMULATOR



JPM Title: PERFORM CCW VALVE OPERABILITY SURVEILLANCE JPM No.: S5 Rev. No: 1 STP Task: CR 00101 – Valve Operability Surveillances. (Program Hierarchy) STP Objective: NOTE: There is not a direct Task or Objective from VISION that ties to

the CCW Valve Operability Surveillance. Related K/A Reference: 008 A4.01 [3.3/3.1] Ability to manually operate and/or monitor in the

control room: CCW Indications and Controls. References: 0PSP03-CC-0008, Component Cooling Water System Train 1B(2B) Valve

Operability Test







Required Materials (Tools/Equipment): Stop Watch for timing valve strokes.



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’VE COMPLETED THE TASK. INITIAL CONDITIONS: Unit 1 is at 80% Power with all systems in a normal lineup. Maintenance has just been completed on CC-MOV-0136, CCW SPLY OCIV, and CC-MOV-0148, CCW RET OCIV. It has been determined that the valves need to be time stroke tested prior to declaring Operable. INITIATING CUE: The Unit Supervisor directs you to perform 0PSP03-CC-0008, Component Cooling Water System Train 1B(2B) Valve Operability Test, Section 5.8. Section 4.0, Prerequisites is complete and the Shift Manager has given permission to start the test.

COMPLETION CRITERIA: The Reactor Operator completes Section 5.8 of 0PSP03-CC-0008, Component Cooling Water System Train 1B(2B) Valve Operability Test, and gives the Surveillance to the Unit Supervisor/Shift Manager for review.




HANDOUTS:

• 0PSP03-CC-0008, Component Cooling Water System Train 1B(2B) Valve Operability Test, filled out up to Section 5.1.

• Stop Watch for timing valve strokes. NOTES: 1. This JPM is formatted for dynamic simulator performance only. The cues provided are


2. This JPM can be run at any power level or at shutdown if an SI as not been actuated. The JPM can be performed on other Trains and it is best if the RCFCs are already secured on the Train being tested.

SIMULATOR SETUP: 1. JPMs S3 and S5 are to be run together. The following steps will set up the simulator for

BOTH JPMs.




• Red light at the end of CP-010 is out. • ICS Annunciators have stopped counting up.

5. Check and clean the following procedures: • 0POP04-CV-0003, Emergency Boration

6. Place simulator in run. Silence/acknowledge/reset alarms as appropriate.

7. Place the simulator in ‘FREEZE’ until the examiners are ready to proceed.

8. There is no simulator lesson for either of these JPMs.

INSTRUCTOR ACTIONS None



NOTE:

Critical steps are identified by (C). SAT/UNSAT Performance Step: 1 Start time: _______ ENSURE the Prerequisites Section has been completed and Precautions and Notes Section has been read. (Step 5.1.1) Standard: _____ Ensures prerequisite section has been completed. Comment: As per the Initiating Cue, Section 4 Prerequisites have been completed. Cue: Notes: SAT/UNSAT Performance Step: 2 CONDUCT a prejob briefing, including any changes in Work Activity Risk Assessment as noted in the Remarks Section of the PPDS. (step 5.1.2) Standard: _____ Conducts a prejob brief. Comment:

A prejob brief does not work with a JPM, however, the student may look at the Notes and Precautions Section as a review.

Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 ENSURE a Control Room Logbook entry is made to document commencement of this surveillance test. (step 5.1.3) Standard: _____ Ensures a logbook entry has been documented. Comment: Cue: Another Reactor Operator will make the logbook entry. Notes: SAT/UNSAT Performance Step: 4 RECORD the AS FOUND position for RCFC 11B(21B) and 12B(22B) CCW Supply Isolation Valve “CCW SPLY OCIV MOV-0136” in Step 5.8.11. (Step 5.8.1) Standard: _____ Records CLOSED for the as found position of CC-MOV-0136 on step 5.8.11. Comment: Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5 RECORD the AS FOUND position for RCFC 11B(21B) and 12B(22B) CCW Return Isolation Valve “CCW RET OCIV MOV-0148” in Step 5.8.12. (step 5.8.2) Standard: _____ Records CLOSED for the as found position of CC-MOV-0148 on step 5.8.12.

Comment: Cue: Notes: SAT/UNSAT Performance Step: 6 RECORD the AS FOUND position for RCFC 11B(21B) and 12B(22B) Chilled Water Supply Isolation Valve “CHWS SPLY OCIV MOV-0137” in Step 5.8.13. (step 5.8.3) Standard: ______ Records OPEN for the as found position of CC-MOV-0137 on step 5.8.13. Comment: Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 7 RECORD the AS FOUND position for RCFC 11B(21B) and 12B(22B) Chilled Water Return Isolation Valve “CHWS RET OCIV MOV-0149” in Step 5.8.14. (step 5.8.4) Standard: ______ Records OPEN for the as found position of CC-MOV-0149 on step 5.8.14. Comment: Cue: Notes: SAT/UNSAT Performance Step: 8 (C) ENSURE RCFC 11B(21B) and 12B(22B) Chilled Water Return Isolation Valve “CHWS RET OCIV MOV-0149” closed. (step 5.8.5) Standard: _____ ENSURES CC-MOV-0149 is CLOSED. Comment: Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 9 (C) ENSURE RCFC 11B(21B) and 12B(22B) Chilled Water Supply Valve “CHWS SPLY OCIV MOV-0137” closed. (step 5.8.6) Standard: _____ ENSURES CC-MOV-0137 is CLOSED. Comment: Cue: Notes: SAT/UNSAT Performance Step: 10 (C) Simultaneously START the stopwatch AND OPEN “CCW SPLY OCIV MOV-0136” by momentarily placing the handswitch located on CP002 to OPEN. (step 5.8.7.1) Standard: ______ Simultaneously starts the stop watch and opens CC-MOV-0136. Comment: Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 11 (C) WHEN “CCW SPLY OCIV MOV-0136” is full open (red lamp illuminated and green lamp off), THEN STOP the stopwatch AND RECORD the valve stroke time. (step 5.8.7.2) Standard: _____ Stops the stop watch when CC-MOV-0136 is full open. Records stroke time. Comment: Stroke time should be ≤ 17 seconds.

Cue: Notes: SAT/UNSAT Performance Step: 12 VERIFY the time recorded in Step 5.8.7.2 satisfies the Acceptance Criteria. (step 5.8.7.3) Standard: _____ Verifies open stroke time for CC-MOV-0136 meets acceptance criteria. Comment: Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 13 (C) CLOSE “CCW SPLY OCIV MOV-0136” by momentarily placing the handswitch located on CP002 to CLOSE. (step 5.8.8.1) Standard: _____ Closes CC-MOV-0136. Comment:

Cue: Notes: SAT/UNSAT Performance Step: 14 VERIFY “CCW SPLY OCIV MOV-0136” is full closed (green lamp illuminated and red lamp off). (steps 5.8.8.2) Standard: _____ Verifies CC-MOV-0136 fully closed. Comment: Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 15 (C) Simultaneously START the stopwatch AND OPEN “CCW RET OCIV MOV-0148” by momentarily placing the handswitch located on CP002 to OPEN. (step 5.8.9.1) Standard: _____ Simultaneously starts the stop watch and opens CC-MOV-0148. Comment: Cue: Notes: SAT/UNSAT Performance Step: 16 (C) WHEN “CCW RET OCIV MOV-0148” is full open (red lamp illuminated and green lamp off), THEN STOP the stopwatch AND RECORD the valve stroke time. (step 5.8.9.2) Standard: _____ Stops the stop watch when CC-MOV-0148 is full open. Records stroke time. Comment: Stroke time should be ≤ 17 seconds.

Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 17 VERIFY the time recorded in Step 5.8.9.2 satisfies the Acceptance Criteria. (step 5.8.9.3)

Standard: _____ Verifies open stroke time for CC-MOV-0148 meets acceptance criteria. Comment: Cue: Notes: SAT/UNSAT Performance Step: 18 (C) CLOSE “CCW RET OCIV MOV-0148” by momentarily placing the handswitch located on CP002 to CLOSE. (step 5.8.10.1) Standard: _____ Closes CC-MOV-0148. Comment:

Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 19 VERIFY “CCW RET OCIV MOV-0148” is full closed (green lamp illuminated and red lamp off). (steps 5.8.10.2) Standard: _____ Verifies CC-MOV-0148 fully closed. Comment: Cue: Notes: SAT/UNSAT Performance Step: 20 PLACE “CCW SPLY OCIV MOV-0136” in the as found position or a position as specified by the Shift Manager/Unit Supervisor. RECORD the AS LEFT position:

• AS FOUND Position ________

• AS LEFT Positon ________ (step 5.8.11) Standard: _____ Records the AS LEFT position for CC-MOV-0136. Comment: AS LEFT position will be CLOSED.

Cue: Independent Verification is required for this step. As the Unit Supervisor inform the student to continue with the surveillance. Another RO will provide Independent Verification shortly.

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 21 PLACE “CCW RET OCIV MOV-0148” in the as found position or a position as specified by the Shift Manager/Unit Supervisor. RECORD the AS LEFT position:


• AS LEFT Positon ________ (step 5.8.12) Standard: _____ Records the AS LEFT position for CC-MOV-0148. Comment:

AS LEFT position will be CLOSED.

Cue:

Independent Verification is required for this step. As the Unit Supervisor inform the student to continue with the surveillance. Another RO will provide Independent Verification shortly.

Notes: SAT/UNSAT Performance Step: 22 (C) PLACE “CHWS SPLY OCIV MOV-0137” in the AS FOUND position or a position as specified by the Shift Manager/Unit Supervisor. RECORD the AS LEFT position:


• AS LEFT Positon ________ (step 5.8.13) Standard: _____ OPENS and records the AS LEFT position for CC-MOV-0137. Comment: AS LEFT position will be OPEN.

Cue: Independent Verification is required for this step. As the Unit Supervisor inform the student to continue with the surveillance. Another RO will provide Independent Verification shortly.

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 23 (C) PLACE “CHWS RET OCIV MOV-0149” in the AS FOUND position or a position as specified by the Shift Manager/Unit Supervisor. RECORD the AS LEFT position:


• AS LEFT Positon ________ (step 5.8.14) Standard: _____ OPENS and records the AS LEFT position for CC-MOV-0149. Comment:

AS LEFT position will be OPEN.

Cue:

Independent Verification is required for this step. As the Unit Supervisor inform the student to continue with the surveillance. Another RO will provide Independent Verification shortly.

Notes: SAT/UNSAT Performance Step: 24

NOTIFY the Shift Manager that testing is complete. (step 5.14.1) Standard: _____ Notifies the Shift Manager/Unit Supervisor that testing is complete. Comment:

Cue:

Notes: - TERMINATE THE JPM - Stop Time: _____


VERIFICATION OF COMPLETION Job Performance Measure: PERFORM CCW VALVE OPERABILITY SURVEILLANCE Applicant's Name: _________________________ Date Performed: ___________________________ Time to Complete: _________________________

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________


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 at 80% Power with all systems in a normal lineup. Maintenance has just been completed on CC-MOV-0136, CCW SPLY OCIV, and CC-MOV-0148, CCW RET OCIV. It has been determined that the valves need to be time stroke tested prior to declaring Operable. INITIATING CUE: The Unit Supervisor directs you to perform 0PSP03-CC-0008, Component Cooling Water System Train 1B(2B) Valve Operability Test, Section 5.8. Section 4.0, Prerequisites is complete and the Shift Manager has given permission to start the test.

NRC JPM NO: S6 Rev. 1 PAGE 1 OF 10


OPERATING JOB PERFORMANCE MEASURE TITLE: TRANSFER TO HOT LEG RECIRCULATION JPM NO.: S6 REVISION: 1 LOCATION: SIMULATOR


JOB PERFORMANCE MEASURE WORKSHEET JPM Title: TRANSFER TO HOT LEG RECIRCULATION JPM No.: S6 Rev. No.: 1 STP Task: 81637 - Transfer to Hot Leg Recirculation STP Objective: 81637 - Transfer to Hot Leg Recirculation IAW 0POP05-E0-ES14 Related K/A Reference: 006 A4.05 [3.9/3.8] Ability to manually operate and/or monitor in the

control room: Transfer of ECCS flowpaths prior to recirculation. References: 0POP05-E0-ES14, Transfer to Hot Leg Recirculation Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: Simulator Time Critical Task: NO Alternate Path JPM: NO Validation Time: 10 minutes Required Materials (Tools/Equipment): None


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’VE COMPLETED THE TASK. CAUTION: Do not operate or alter equipment configuration in the plant without proper

authorization. INITIAL CONDITIONS: A large break LOCA occurred 5.5 hours ago. The control room operators have completed 0POP05-EO-EO10 and are evaluating long term plant status.

INITIATING CUE: The Unit Supervisor directs you to transfer SI Trains to Hot Leg recirculation in accordance with 0POP05-EO-ES14, Transfer to Hot Leg Recirculation, starting with Train A.

COMPLETION CRITERIA: The Performer transfers SI Recirculation Flow from Cold Leg to Hot Leg for SI Train ‘A’ per 0POP05-EO-ES14.



JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS: None, the applicant is expected to use the simulator copy of the procedure. NOTES: 1. This JPM is formatted for dynamic simulator performance only. The cues provided are


SIMULATOR SETUP

1. JPMs S6 and S8 are to run together. The following steps will set up the simulator for BOTH JPMs.

2. Ensure Radio volume for both stations are set to a reasonable level. 3. Ensure the simulator PA buttons on the communications consoles are taped to help eliminate

usage. 4. Reset to IC #222 and verify:

• Red light at the end of CP-010 is out. • ICS annunciators have stopped counting up • MOV-0031A, B and C are energized.

5. Check and Clean the following procedures in the simulator (JPM specific)

• 0POP04-RA-0001, Radiation Monitoring System Alarm Response • 0POP05-EO-ES14, Transfer to Hot Leg Recirculation

6. Place simulator in run. Silence/acknowledge /reset alarms as appropriate

7. ENSURE one Train of FHB Exhaust Fans and Booster Fans in PTL.

8. ENSURE one FHB HVAC Exhaust Filter Damper in Manual and Closed.

9. Place the simulator in “FREEZE” until the examiners are ready to proceed.

10. Ensure a calculator is available at CP-002.

11. There is no simulator lesson plan for S6 or S8. INSTRUCTOR ACTIONS None



NOTE:


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

SAT/UNSAT Performance Step: 1 Start time: ________ Obtain a copy of 0POP05-EO-ES14, Transfer to Hot Leg Recirculation Standard: _____ Obtains a copy of 0POP05-EO-ES14, Transfer to Hot Leg Recirculation. Comment: The applicant should use the simulator copy of the procedure. Cue: Notes: SAT/UNSAT Performance Step: 2 CHECK Three SI Trains – OPERABLE (Step 1) Standard: ____ Determines that all three Trains of SI are OPERABLE. Comment: All three SI trains are Operable. Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3

SELECT First SI Train for HOT Leg Recirculation. (Step 2)

Standard: _____ Selects Train A as the first SI Train to be aligned for Hot Leg Recirculation.

Comment:

Selecting Train A is in the Initiating Cue.

Cue:

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3(C) ALIGN selected HHSI for hot leg recirculation. (Train A) (Step 2a) Standard: _____ ENERGIZE selected SI train HHSI hot leg injection valve. (Train A, MOV-0008A) _____ OPEN HHSI hot leg injection valve. (Train A, MOV-0008) _____ CLOSE HHSI cold leg injection valve. (Train A, MOV-0006A) _____ VERIFY Hot Leg Injection flow. (Train A, FI-0917) _____ DEENERGIZE selected SI train HHSI hot leg injection valve. (Train A, MOV-0008A)

Comment:

Cue:

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4(C) ALIGN selected LHSI for hot leg recirculation. (Train A) (Step 2b) Standard: _____ DISPATCH Operator to UNLOCK and CLOSE the selected LHSI Cold Leg Injection Valve

Breakers. (Train A, MOV-0031A) _____ ENERGIZE selected SI train LHSI hot leg injection valve. (Train A, MOV-0019A) _____ OPEN LHSI hot leg injection valve. (Train A, MOV-0019A) _____ CLOSE LHSI cold leg injection valve. (Train A, MOV-0031A) _____ VERIFY Hot Leg Injection flow. (Train A, FI-0927) _____ DEENERGIZE selected SI train LHSI hot leg injection valve. (Train A, MOV-0019A)

Comment: LHSI Cold Leg Injection Valves, SI-MOV-0031A,B,C are already energized.

Cue:

Notes: Once the student has verified hot leg injection flow on Train A the JPM can be terminated. - TERMINATE THE JPM - Stop time _________



Job Performance Measure: S6, TRANSFER TO HOT LEG RECIRCULATION Applicant's Name: _________________________ Date Performed: ___________________________ Time to Complete: _________________________ JPM Results: Sat / Unsat Evaluator: Signature: ________________________

Date: _______________


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. CAUTION: Do not operate or alter equipment configuration in the plant without

proper authorization. INITIAL CONDITIONS: A large break LOCA occurred 5.5 hours ago. The control room operators have completed 0POP05-EO-EO10 and are evaluating long term plant status.

INITIATING CUE: The Unit Supervisor directs you to transfer SI Trains to Hot Leg recirculation in accordance with 0POP05-EO-ES14, Transfer to Hot Leg Recirculation, starting with Train A.


NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: MANUAL CONTAINMENT ISOLATION PHASE A ACTUATION JPM NO.: S7 REVISION: 1 LOCATION: SIMULATOR


JOB PERFORMANCE MEASURE WORKSHEET JPM Title: MANUAL CONTAINMENT ISOLATION PHASE A ACTUATION

JPM No.: S7

Rev. No: 1

STP Task: T80000, Respond to a Reactor Trip or Safety Injection

STP Objective: CRO 80000, Respond to a Reactor Trip or Safety Injection in accordance

with 0POP05-EO-EO00, Reactor Trip or SI.

Related K/A Reference: 103 A3.01 [3.9/4.2] Ability to monitor automatic operation of the

containment system including: Containment Isolation.

References: 0POP05-EO-EO00, Reactor Trip or Safety Injection









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’VE COMPLETED THE TASK. INITIAL CONDITIONS: A SBLOCA has occurred in Unit 1. There was a fault with Actuation Train B that prevent Train B equipment from actuating on the Safety Injection. INITIATING CUE: Another RO has performed the first 5 steps of 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of SI Equipment Operation. The Unit Supervisor has directed you to continue with Addendum 5 at step 6.

COMPLETION CRITERIA: Manually actuates Phase A and performs 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 1, Phase A Isolation Verification, for the Train B valves.



JOB PERFORMANCE MEASURE CHECK SHEET HANDOUTS:

0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation.

0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 1, Phase A Isolation Verification.

NOTES: 1. JPMs S2 and S7 are ruin together. 2. Both JPMs are formatted for dynamic simulator performance only. The cues provided are


3. In the IC for this JPM, S7, open breaker 6 from DP-1203 (schematic ee_dp1203) (ee_dp1203tc89_6). Override the valve position to open for GWPS ICIV FV-4920 and Seal Return ICIV CV-MOV-0077. Insert a SBLOCA of about 250 gpm. Actuate SI and allow the plant to stabilize for a couple of minutes. Place simulator in FREEZE and store IC.

4. This JPM, S7, is an Alternate path JPM. Basically, the student will verify containment isolation Phase A using 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation, and 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 1, Phase A Isolation Verification.



SIMULATOR SETUP: 1) JPMs S2 and S7 are to run together. The following steps will set up the simulator for BOTH

JPMs.





0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance.

6) FROM THE BOOTH:

Place simulator in RUN

Quickly silence/acknowledge/reset alarms

Place one FHB exhaust damper in manual and closed

Place simulator in FREEZE

NOTE: Do not go to Run for JPM performance until the student performing this JPM has read the initial conditions, task statement, etc. and is ready to proceed.

7) When the student and the examiners are ready to proceed, place the simulator in RUN No further action will be needed.

INSTRUCTOR ACTIONS: None.



NOTE:


SAT/UNSAT Performance Step: 1 Start Time: _____ Obtain a copy of 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation.

Standard: _____ The operator obtains a copy of 0POP05-EO-EO00, Reactor Trip or Safety Injection,

Addendum 5, Verification of Equipment Operation.

Comment:


ONLY 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation, Pages 1 – 8 are to be handed out at this time.

Cue:

Notes:

SAT/UNSAT Performance Step: 2 VERIFY containment isolation phase A:

Phase A ACTUATED. (add 5 step 6a) Standard: _____ Determines Containment Isolation Phase A has actuated but not on Train B and

MANUALLY ACTUATES Phase A using the red handswitch per the RNO step. Comment: Cue: Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 VERIFY containment isolation phase A:

Phase A valves - CLOSED. (add 5 step 6b) Standard: _____ Determines that Phase A still did not work for valves on Train B and that Train B valves

will have to be manually closed per the RNO step using Addendum 1, Phase A Isolation Verification, as reference.

Comment:


When the student asks for or starts to get Addendum 1, Phase A Isolation Verification, then hand out the copy provided.

Cue:

Notes:

The next steps follow the order of Addendum 1, however, the valves can be verified in any order. Only the Train B valves are listed since only Train B Phase A failed to actuate. The exception to this is noted on JPM step 16 which is a Train A valve that failed to close and JPM step 20 which is a Train C valve that failed to close. SAT/UNSAT Performance Step: 4 (C) VERIFY “IA-OCIV FV-8565” CLOSED. (add 1, 1st B Train Valve) Standard: _____ Determines that “IA-OCIV FV-8565” is OPEN and closes “IA-OCIV FV-8565”. Comment:

Cue:

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5 VERIFY “RHR SAMPLE ICIV FV-4823” CLOSED. (add 1, 2nd B Train Valve) Standard: _____ Determines that “RHR SAMPLE ICIV FV-4823” is CLOSED. Comment:

Cue:

Notes: SAT/UNSAT Performance Step: 6 VERIFY “SI ACC SAMPLE OCIV FV-4466” CLOSED. (add 1, 3rd B Train Valve) Standard: _____ Determines that “SI ACC SAMPLE OCIV FV-4466” is CLOSED. Comment:

Cue:

Notes:



VERIFY “RCS SAMPLE OCIV FV-4456” CLOSED. (add 1, 4th B Train Valve) Standard: _____ Determines that “RCS SAMPLE OCIV FV-4456” is CLOSED. Comment:

Cue:


VERIFY “PZRR LIQUID SAMPLE ICIV FV-4451” CLOSED. (add 1, 5th B Train Valve) Standard: _____ Determines that “PZRR LIQUID SAMPLE ICIV FV-4451” is CLOSED. Comment:

Cue:

Notes:



VERIFY “PZRR VAPOR SAMPLE ICIV FV-4450” CLOSED. (add 1, 6th B Train Valve) Standard: _____ Determines that “PZRR VAPOR SAMPLE ICIV FV-4450” is CLOSED. Comment:

Cue:


VERIFY “RCS SAMPLE OCIV FV-2455/2455A” CLOSED. (add 1, 7th B Train Valve) Standard: _____ Determines that “RCS SAMPLE OCIV FV-2455/2455A” is CLOSED. Comment:

Cue:

Notes:



VERIFY “TEST LN ICIV FV-3970” CLOSED. (add 1, 8th B Train Valve) Standard: _____ Determines that “TEST LN ICIV FV-3970” is CLOSED. Comment:

Cue:


VERIFY “OCIV FV-3652” CLOSED. (add 1, 9th B Train Valve) Standard: _____ Determines that “OCIV FV-3652” is CLOSED. Comment:

Cue:

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 13 (C) VERIFY “OCIV FV-3651” CLOSED. (add 1, 10th B Train Valve) Standard: _____ Determines that “OCIV FV-3651” is OPEN and closes “OCIV FV-3651”. Comment:

Cue:


VERIFY “OCIV FV-4913” CLOSED. (add 1, 11th B Train Valve) Standard: _____ Determines that “OCIV FV-4913” is OPEN and closes “OCIV FV-4913”. Comment:

Cue:

Notes:



VERIFY “OCIV FV-4919” CLOSED. (add 1, 12th B Train Valve) Standard: _____ Determines that “OCIV FV-4919” is OPEN and closes OCIV FV-4919. Comment: A failure was put in for the other valve in this penetration, ICIV FV-4920. OCIV FV-4919 must be closed to isolate the penetration.

Cue:


VERIFY “ICIV FV-4920” CLOSED. (add 1, A Train Valve that independently failed to close) Standard: _____ Determines that “ICIV FV-4920” is OPEN and has failed to close. Comment:

As long as OCIV FV-4919 gets closed the penetration will be isolated.

Cue:

Notes:



VERIFY “DISCH ICIV MOV-0064” CLOSED. (add 1, 13th B Train Valve) Standard: _____ Determines that “DISCH ICIV MOV-0064” is OPEN and closes MOV-0064. Comment:

Cue:


VERIFY “OCIV MOV-0024” CLOSED. (add 1, 14th B Train Valve) Standard: _____ Determines that “OCIV MOV-0024” is OPEN and CLOSES MOV-0024. Comment:

Cue:

Notes:


JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 19 (C) VERIFY “SEAL RTN OCIV MOV-0079” CLOSED. (add 1, 15th B Train Valve) Standard: _____ Determines that “SEAL RTN OCIV MOV-0079” is OPEN and CLOSES MOV-0079. Comment: A failure was put in for the other valve in this penetration, SEAL RTN ICIV MOV-0077. SEAL RTN OCIV MOV-0079 must be closed to isolate the penetration.

Cue:


VERIFY “SEAL RTN OCIV MOV-0077” CLOSED. (add 1, C Train Valve that independently failed to close) Standard: _____ Determines that “SEAL RTN OCIV MOV-0077” is OPEN and will not close due to a

malfunction that also caused a loss of valve position indication. Comment:

As long as SEAL RTN OCIV MOV-0079 gets closed the penetration will be isolated.

Cue:

Notes: When MOV-0077 is taken to CLOSE, the breaker trips and valve position indication is lost. A BYPASS/INOP indication will also come in on CP-002. -TERMINATE THE JPM- Stop Time: ______


VERIFICATION OF COMPLETION Job Performance Measure: MANUAL CONTAINMENT ISOLATION PHASE A

ACTUATION Applicant's Name: _____________________________________ Date Performed: _______________________________________ Time to Complete: _____________________________________ JPM Results: Sat / Unsat Evaluator: Signature

Date


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’VE COMPLETED THE TASK. INITIAL CONDITIONS: A SBLOCA has occurred in Unit 1. There was a fault with Actuation Train B that prevent Train B equipment from actuating on the Safety Injection. INITIATING CUE: Another RO has performed the first 5 steps of 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of SI Equipment Operation. The Unit Supervisor has directed you to continue with Addendum 5 at step 6.

DEVICE ACTUATION POSITION CHECK

TRAINS

Fire Water to Containment

"FIRE WTR OCIV MOV-0756" C CLOSED

Instrument Air to Containment

"IA OCIV FV-8565" B CLOSED

Containment H2 Monitoring

"VPI FV-4101" A CLOSED

"VPI FV-4127" A CLOSED

"VPI FV-4104" C CLOSED

"VPI FV-4133" C CLOSED

"H2 SAMPLE INL ICIV FV-4135" A CLOSED

"H2 SAMPLE DISCH ICIV FV-4128" A CLOSED

"H2 SAMPLE INL ICIV FV-4136" C CLOSED

"H2 SAMPLE DISCH ICIV FV-4134" C CLOSED

Primary Sampling System

"RHR SAMPLE ICIV FV-4823" B CLOSED

"RHR SAMPLE OCIV FV-4461" C CLOSED

"SI ACC SAMPLE ICIV FV-4824" C CLOSED

"SI ACC SAMPLE OCIV FV-4466" B CLOSED

"RCS LOOP 1A(2A) Th SAMPLE ICIV" C

"FV-4454" CLOSED


TRAINS

Primary Sampling System (con't)

"RCS LOOP 1C(2C) Th SAMPLE ICIV" C

"FV-4455" CLOSED

"RCS SAMPLE OCIV FV-4456" B CLOSED

"PRZR LIQ SAMPLE OCIV FV-4451B" C CLOSED

"PRZR LIQ SAMPLE ICIV FV-4451" B CLOSED

"PRZR VAPOR SAMPLE OCIV FV-4452" C CLOSED

"PRZR VAPOR SAMPLE ICIV FV-4450" B CLOSED

Post Accident Sample System

"CNTMT SUMP SAMPLE OCIV FV-2453" A CLOSED

"RHR SAMPLE OCIV FV-2454" A CLOSED

"RCS SAMPLE OCIV FV-2455/2455A" B CLOSED

"CNTMT AIR SAMPLE OCIV FV-2456" C CLOSED

"RETURN TO PRT OCIV FV-2458" C CLOSED

"CNTMT AIR RETURN OCIV FV-2457" C CLOSED

SI Accumulators

"TEST LN ICIV FV-3970" B CLOSED

"TEST LN OCIV FV-3971" A CLOSED

"N2 SPLY OCIV FV-3983" A CLOSED


TRAINS

Pressurizer Relief Tank

"OCIV FV-3652" B CLOSED

"ICIV FV-3653" A CLOSED


Reactor Coolant Drain Tank


"ICIV MOV-0312" A CLOSED


"ICIV FV-4920" A CLOSED

Containment Normal Sump

"DISCH ICIV MOV-0064" B CLOSED

"DISCH OCIV FV-7800" A CLOSED

CVCS Letdown

"OCIV MOV-0024" B CLOSED

"ICIV MOV-0023" C CLOSED

"LTDN ORIF HDR ISOL FV-0011" C CLOSED

CVCS Seal Return

"SEAL RTN ICIV MOV-0077" C CLOSED

"SEAL RTN OCIV MOV-0079" B CLOSED


TRAINS

CVCS Charging

"OCIV MOV-0025" A CLOSED

Personnel Airlock Seal OCIVs

"INNER SEAL FV-1025" A CLOSED

"INNER SEAL FV-1028" A CLOSED

"OUTER SEAL FV-1026" A CLOSED

"OUTER SEAL FV-1027" A CLOSED




TITLE: RESPOND TO A RADIATION MONITOR ALARM JPM NO.: S8 REVISION: 1 LOCATION: SIMULATOR



JPM Title: RESPOND TO A RADIATION MONITOR ALARM

JPM No.: S8 Rev. No.: 1 STP Task: 11700 – Respond to Radiation Monitoring System Alarm STP Objective: 11700 – Respond to Radiation Monitoring System Alarm Related K/A Reference: 073 A4.02 Process Radiation Monitoring (PRM) System: Ability to

manually operate and/or monitor in the control room; Radiation monitoring system control panel. [3.7/3.7]

References: 0POP04-RA-0001, Radiation Monitoring System Alarm Response Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: Simulator Time Critical Task: NO Alternate Path JPM: YES Validation Time: 10 minutes Required Materials (Tools/Equipment): None



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’VE COMPLETED THE TASK. CAUTION: Do not operate or alter equipment configuration in the plant without proper

authorization.

INITIAL CONDITIONS:

A large break LOCA occurred. The control room operators have completed 0POP05-EO-EO10 and are evaluating long term plant status.

INITIATING CUE:

The Control Room has recently received radiation monitor alarms on the RM-11. The Unit Supervisor directs you to investigate the cause of the alarms and take any action necessary IAW 0POP04-RA-0001, Radiation Monitoring System Alarm Response.



The Operator determines that RT-8012 indicates above the high alarm setpoint and isolates the Containment Ventilation system.



HANDOUTS:

None, the applicant is expected to use the simulator copy of the procedure.

NOTES: 1. This JPM is formatted for dynamic simulator performance only. The cues provided are


SIMULATOR SETUP

1. JPMs S6 and S8 are to run together. The following steps will set up the simulator for BOTH JPMs.

2. Ensure Radio volume for both stations are set to a reasonable level. 3. Ensure the simulator PA buttons on the communications consoles are taped to help eliminate

usage. 4. Reset to IC #222 and verify:

• Red light at the end of CP-010 is out. • ICS annunciators have stopped counting up • MOV-0031A, B and C are energized.

5. Check and Clean the following procedures in the simulator (JPM specific)

• 0POP04-RA-0001, Radiation Monitoring System Alarm Response • 0POP05-EO-ES14, Transfer to Hot Leg Recirculation

6. Place simulator in run. Silence/acknowledge /reset alarms as appropriate

7. ENSURE one Train of FHB Exhaust Fans and Booster Fans in PTL.

8. ENSURE one FHB HVAC Exhaust Filter Damper in Manual and Closed.

9. Place the simulator in “FREEZE” until the examiners are ready to proceed.

10. Ensure a calculator is available at CP-002.

11. There is no simulator lesson plan for S6 or S8

INSTRUCTOR ACTIONS None



NOTE:


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

SAT/UNSAT Performance Step: 1 Start time: _______

CHECK RM-11 Available (Step 1.0)

Standard:

_____ Obtains a copy of 0POP04-RA-0001, Radiation Monitoring System Alarm Response, and checks RM-11 available per the first step.

Comment:

Cue:

Notes:

The student may also check CP-023. RT-8012 and RT-8013 can be monitored from this panel as well.



SAT/UNSAT Performance Step: 2 PERFORM The Following From RM-11 Panel To DETERMINE The Type Of Alarm:

DEPRESS <SYSTEM ACK> button or any grid button to silence the audible alarm. DEPRESS the grid display button (1-6) that corresponds with the flashing indicator on the

bottom right hand side of the screen DEPRESS the <SEL> key DEPRESS the <STATUS> key (Step 2.0)

Standard:

_____ Obtains information from the RM-11 Computer to determine the reason for the alarm.

Comment:

Cue:

Notes:


CHECK The Individual Monitor In Alarm – ALERT OR HIGH (yellow or red) (Step 3.0)

Standard: _____ Determines from RM-011 that RT-8012 is in Alarm (Red) and RT-8013 is in Alert

(Yellow).

Comment:

Cue:

Notes:

RT-8010A and 8010B (MAB Exhaust Rad Monitors) will also be in alarm but under the given conditions this would be expected. The priority will be RT-8012 & 8013 (Containment Purge Rad Monitors) and getting the Containment Purge secured.




PERFORM The Following: • DEPRESS the <TREND 10 MIN> key • EVALUATE activity readings for a reasonable indication of increased radioactivity • GO TO the correct Addendum listed below for the monitor in alarm (Step 4.0)

Standard: _____ Determines that 0POP04-RA-0001, Addendum 3, needs to be performed.

Comment:

Cue:

Notes: JPM Steps 1-4 reference procedure steps from 0POP04-RA-0001, Radiation Monitoring system Alarm Response that instruct the student on how to read data on the RM-11. They can be performed without the procedure, however, the student must still be able to determine that 0POP04-RA-0001, Radiation Monitoring System Alarm Response, Addendum 3, is required to be performed because of the high alarm on RT-8012.


CHECK HIGH Alarm Exists On Radiation Monitor RT-8012 or RT-8013 (Add 3 Step 1.0)

Standard: _____ Determines that RT-8012 is in High Alarm.

Comment:

Cue:

Notes:



SAT/UNSAT Performance Step: 6 (C) CHECK The Following Automatic Actions Have Occurred:

Normal Containment Purge Fans stopped Supplementary Containment Purge Fans stopped Normal Containment Purge valves closed Supplementary Containment Purge valves closed (Add 3 Step 2.0)

Standard: _____ Determines that Supplementary Containment Purge Supply and Exhaust Fans 11A are

running and manually secures the fans.

_____ Determines that all 4 Supplementary Containment Purge valves are open and manually closes the valves.

FV-9776

MOV-0003

MOV-0005

FV-9777

Comment:

Cue:

Notes:

- TERMINATE THE JPM - Stop time: ________



Job Performance Measure: S8, RESPOND TO A RADIATION MONITOR ALARM Applicant's Name: _________________________ Date Performed: ___________________________ Time to Complete: _________________________ JPM Results: Sat / Unsat Evaluator: Signature: ________________________

Date: _______________


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 EVALUATOR WHEN YOU’VE COMPLETED THE TASK. CAUTION: Do not operate or alter equipment configuration in the plant without

proper authorization.

INITIAL CONDITIONS:

A large break LOCA occurred. The control room operators have completed 0POP05-EO-EO10 and are evaluating long term plant status.

INITIATING CUE:

The Control Room has recently received radiation monitor alarms on the RM-11. The Unit Supervisor directs you to investigate the cause of the alarms and take any action necessary IAW 0POP04-RA-0001, Radiation Monitoring System Alarm Response.

NRC JPM NO: P1 Rev. 2 PAGE 1 OF 10



TITLE: LOCALLY OPERATE ‘C’ SG PORV

JPM NO.: P1

REVISION: 2

LOCATION: UNIT 1 or 2


JOB PERFORMANCE MEASURE WORKSHEET SOUTH TEXAS PROJECT

JPM Title: LOCALLY OPERATE ‘C’ SG PORV

JPM No.: P1

Rev. No:

STP Task:

STP Objective:

2

CRO82044, Respond to a Loss of All AC Power Condition

CRO82044, Respond to a Loss of All AC Power Condition in accordance

with 0POP05-EO-EC00

Related K/A Reference: 035 A1.02 [3.5, 3.8] Ability to predict and/or monitor changes in

parameters (to prevent exceeding design limits) associated with operating the S/GS controls including: S/G pressure.

References: 0POP05-EO-EC00, LOSS OF ALL AC POWER, Addendum 6

Task Normally Completed By: PO

Method of Testing: Simulated

Location of Testing: Plant




Required Materials Working copy 0POP05-EO-EC00, Loss of All AC Power, Addendum 6. (Tools/Equipment):





CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A Loss of All AC Power has occurred. The SG PORVs must be locally controlled to establish and maintain a cooldown. The EAB Plant Operator has performed Step 1 of 0POP05-EO-EC00, LOSS OF ALL AC POWER, Addendum 6, SG PORV Local Operation, which de-energizes power to the SG PORVs.

INITIATING CUE:

The Unit Supervisor directs you to locally operate 1C(2C) SG PORV in accordance with 0POP05-EO-EC00, LOSS OF ALL AC POWER, Addendum 6, SG PORV Local Operation, starting at step 2.


The operator demonstrates how to locally operate 1C(2C) SG PORV.

HANDOUTS:

Working copy of 0POP05-EO-EC00, Loss of All AC Power, Addendum 6.

NOTES:




NOTE: $ Critical steps are identified by (C).

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

SAT/UNSAT Performance Step: 1 Start time:________

Obtain the procedure.

Standard:

_____ The operator obtains a copy of Addendum 6 of 0POP05-EO-EC00.

Comment:

Provide the operator with a copy of Addendum 6 of 0POP05-EO-EC00.

Cue:

If asked, state that radiation levels are normal.

Notes:




ESTABLISH Communication with the Control Room. (Addendum Step 2)

Standard:

_____ The operator establishes continuous communication with the Control Room by use of a radio or sound powered head phones.

Comment:

Radio use is NOT normally allowed on this level of the IVC. However, with the conditons given, the Unit Supervisor and/or Shift Manager would give permission.Cue:

2) Communications are established.

3) The Unit Supervisor directs you to open the PORV to 40%.

Notes:

1) The Unit Supervisor had given permission to uae a hand held radio for communication.




Open the PORV to the desired initial opening. (Addendum Step 4)

Standard:

The operator opens the PORV to between about 40% but less than 50% by:

Turning PV 7431 manual override knobs on solenoid "A" and "B" simultaneously in the CLOSE direction (clockwise).

WHEN the desired PORV position is reached, THEN TURN knob of "A" solenoid to the full OPEN position (counterclockwise).

Comment:

1) PV-7431 is located in RM 501 of 58 ft IVC:

2) As you approach the valve, Solenoid ‘A’ is the closest of the two. There are name plateslocated near the solenoid override knobs to identify the specific solenoids.

3) When opening the valve, if the override knobs are not operated at the same time, thevalve will not begin to move until the second override knob is operated.

4) There is a picture of SG 2C PORV Solenoid Valves on the next page.

Cue:

1) PORV is closed initially; Give increasing PORV position when override knobs areoperated (see comment 3 above).

(To be given after the PORV is opened to desired opening)

2) The control room orders the PORV to be closed to 20%.

Notes:

There is a caution at the beginning of this addendum to NOT open the SG PORV more than 50%.




Close the PORV to 20%. (Addendum Step 5)

Standard:

The operator closes the PORV to 20% by:

Turning the manual override knob for solenoid "B" in the OPEN direction (counterclockwise).

WHEN desired position of PORV is reached THEN TURN knob of "B" solenoid to the full CLOSE position (clockwise).

Comment:

Cue:

Give decreasing SG PORV position as the SG PORV is closed to 20%.

Notes:

- TERMINATE THE JPM - Stop time:________



Job Performance Measure: LOCALLY OPERATE ‘C’ SG PORV

Performers Name:

Date Performed:

Time to Complete:



Date ____________________



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.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A Loss of All AC Power has occurred. The SG PORVs must be locally controlled to establish and maintain a cooldown. The EAB Plant Operator has performed Step 1 of 0POP05-EO-EC00, LOSS OF ALL AC POWER, Addendum 6, SG PORV Local Operation, which de-energizes power to the SG PORVs.

INITIATING CUE:

The Unit Supervisor directs you to locally operate 1C(2C) SG PORV in accordance with 0POP05-EO-EC00, LOSS OF ALL AC POWER, Addendum 6, SG PORV Local Operation, starting at step 2.




TITLE: LIQUID WASTE RELEASE WITH CW PUMP TRIP JPM NO: P2 REVISION: 1 LOCATION: UNIT 1 or 2



JPM Title: LIQUID WASTE RELEASE WITH CW PUMP TRIP JPM No.: P2 Rev. No.: 1 STP Task: T030301, Determine appropriate processing flow path using

processing guidelines. STP Objective: NLO 030100, Given the specified procedure(s), logs/forms, tools

and equipment, operate the Liquid Waste Processing Subsystem (LWPS) IAW the specified procedure(s), with no assistance allowed in operating the system.

Related K/A Reference: 068 A4.02 [3.2/3.1] Liquid Radwaste System (LRS): Ability to

manually operate and/or monitor in the control room; Remote radwaste release.

References: 0POP02-WL-0100, Liquid Waste Release 0PSP07-WL-LDP2, Liquid Effluent Permit With RT-8038

Inoperable P&ID, LWPS 7R309F90021#2

Task Normally Completed By: PO Method of Testing: Simulated Location of Testing: Plant Time Critical Task: NO Alternate Path JPM: YES Validation Time: 20 Minutes Required Materials (Tools/Equipment): None


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 applicant): 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’VE COMPLETED THE TASK. CAUTION: Do not operate or alter equipment configuration in the plant without

proper authorization. INITIAL CONDITIONS: The Unit is at 100% Power. The following conditions have been established for the release of Waste Monitor Tank (WMT) 1(2)D:

• WMT 1(2)D is on Long Path Recirculation. • RT-8038, Liquid Waste Monitor, is INOPERABLE • All four (4) Circulating Water (CW) Pumps are running. • MAB Chillers 11C(21C) and 11D(21D) are in service. • Open Loop ACW is isolated to MAB Chiller 11A(21A). • RCB Chillers 11A(21A) and 11B(21B) are in service. • Open Loop Valve 1(2)-OC-0292 is OPEN. • The Shift Manager has 0PSP07-WL-LDP2, Liquid Effluent Permit With RT-8038

Inoperable, and is ready to authorize the release of WMT 1(2)D. • Chemistry has just called and is ready for the release of WMT 1(2)D.

INITIATING CUE: The Unit Supervisor directs you to continue with 0POP02-WL-0100, Liquid Waste Release, at Step 5.38 for the release of WMT 1(2)D.

-DO NOT DISCLOSE INFORMATION BELOW THIS LINE- COMPLETION CRITERIA: Initiates release of WMT 1(2)D and then secures the release after Circulating Water Pump #14(24) trips.


JOB PERFORMANCE MEASURE INFORMATION SHEET (cont’d)

HANDOUTS:

• Working copy of 0POP02-WL-0100, Liquid Waste Release.

NOTE: The following P&ID is to ONLY be handout if the student produces a working copy. (Example would be from Computers in the Rad Waste Control Room using FILENET or ORACLE applications. There may also be a working copy in the desk drawer in the Rad Waste Control Room.)

• Working copy of P&ID, LWPS 7R309F90021#2 NOTES: A Liquid Waste Release Permit will not be available for this JPM. The JPM has all the cues needed for Liquid Waste Release Permit information. Candidate may make reference for the need to use gloves while manipulating valves and equipment in the field. If the candidate indicates that he/she will have to get a pair of gloves, acknowledge it and tell them because we will be simulating operations and that gloves will not be required.

This JPM can be performed in either Unit.



NOTE:


SAT / UNSAT Performance Step: 1 JPM START TIME_______________ Obtain a copy of the procedure. Standard: _____ Obtains a working copy of 0POP02-WL-0100, Liquid Waste Release. Comment: Cue: Provide the Handout copy of 0POP02-WL-0100, Liquid Waste Release. Notes: This JPM can be performed in either Unit. The student should circle the Unit as applicable on the Procedure Performance Data Sheet.

A Liquid Waste Release Permit will not be available for this JPM. The JPM has all the cues needed for Liquid Waste Release Permit information.



SAT / UNSAT Performance Step: 2 WHEN Chemistry indicates that the WMT is ready for release, THEN PERFORM the following: (Step 5.38) Standard: _____ RECORD the Pre-Release Permit Number on the Procedure Performance Data

Sheet. _____ ENSURE the corresponding flow from the running number of CW pumps is greater

than or equal to the flow recorded on the permit. _____ ENSURE Section 5.1, Prerelease Instructions, of the applicable procedure below is

completed: • With RT-8038 inoperable, Section 5.1 of 0PSP07-WL-LDP2, Liquid Effluent

Permit With RT-8038 Inoperable completed. _____ ENSURE the Shift Manager has signed 0PSP07-WL-LDP2 authorizing the release. Comment: The Pre-Release Permit number is already on the Procedure Performance Data Sheet. (#1378)

Cue: If asked about CW flow from the Liquid Effluent Permit respond as the Shift Manager that CW flow on the permit is 4 CW Pumps and 452,000 gpm.

If asked report as the Shift Manager that Section 5.1 of 0PSP07-WL-LDP2, Liquid Effluent Permit, is complete.

Report as the Shift Manager that authorization for the release has been approved and 0PSP07-WL-LDP2 has been signed.

If asked, report as the Shift Manager that RT-8038 is INOPERABLE. (Step 5.39)

Notes:



SAT / UNSAT Performance Step: 3 (C)

ENSURE the following valves CLOSED to verify WMT 1D(2D) discharge line valving with RT-8038 inoperable: (Step 5.39.7)

Standard: _____ “WL-1235 WMT SUMP EMPTYING PUMP DISCHARGE VALVE”. (On WMT

1D(2D), 1E(2E) and 1F(2F) Skid above Sump Emptying Pump) _____ “1(2)-WL-0279 WASTE MONITOR TANK PUMPS 1A,B&C(2A, B&C) DISCHARGE

HEADER ISOLATION VALVE”. (MAB 10’ Room 061 NE of WMT 1C(2C)) Indication on ZLP-189

_____ “1(2)-WL-FV-5064A WASTE MONITOR TANK PUMP 1E(2E) DISCHARGE/RECIRC FLOW CONTROL VALVE” (ZLP-722)

_____ “1(2)-WL-FV-5070A WASTE MONITOR TANK PUMP 1F(2F) DISCHARGE FLOW CONTROL VALVE” (ZLP-722)

_____ “1(2)-WL-FV-5066 WASTE MONITOR TANK PUMPS 1D&E(2D&E) DISCHARGE CROSS-TIE FLOW CONTROL VALVE” (ZLP-722)

_____ “1(2)-WL-FV-5063 WASTE MONITOR TANK PUMPS 1D&E(2D&E) SUCTION CROSS-TIE FLOW CONTROL VALVE” (ZLP-722)

_____ GO TO Step 5.40 Comment: WL-1235 will be the only valve open. The student will have to locate this manual valve and simulate closing it. WL-1235 is located outside of the south end of the Mechanical Auxiliary Building but still in the RRA. The description of the valve gives the location as ‘On WMT 1D(2D), 1E(2E) and 1F(2F) Skid above Sump Emptying Pump’ but does not give the location of the sump. The location is listed this way in other procedures and it assumes an operator knows the location of WMTs D, E & F. The working procedure references P&ID, LWPS 7R309F90021. In the RWCR, using Computer ORACLE or FILENET applications or looking through the RWCR desk drawer, if the student can pull up the referenced P&ID, then hand out the P&ID with this JPM. Cue: WL-1235 Initial position is OPEN.

After the student simulates closing the valve then WL-1235 final position is CLOSED.

Notes: WL-1235 out of position would constitute a Configuration Management issue. If the student wants to stop at this point then as the Shift Manager instruct the student to reposition WL-1235 to the closed positon and continue with the liquid waste release. The Control Room Staff will generate the CR to address WL-1235 being out of position.

Step 5.40 will be NA.



SAT / UNSAT Performance Step: 4 ENSURE Open Loop Auxiliary Cooling Water running through MAB Chiller 11A(21A) was not used to satisfy Prerequisite Step 3.8 prior to performing Step 5.42. (Step 5.41) Standard: _____ Determines that current OL-ACW alignment associated with MAB Chiller

11A(21A) was NOT used to satisfy Prerequisite Step 3.8. Comment: Prerequisite Step 3.8 reads as follows:

The Open Loop Auxiliary Cooling Water System SHALL be running when the discharge is started with Open Loop Auxiliary Cooling Water flow through at least one RCB or MAB Chiller and “1(2)-OC-0292 CHILLER UNITS RETURN HEADER ISOL” OPEN.

Cue: If asked, report as the TGB Watch that 1(2)-OC-0292, “CHILLER UNITS RETURN HEADER ISOL” is OPEN.

Notes: MAB Chiller 11A(21A) is secured per the Initiating Cue

This step may be a little confusing but it should be initialed and NOT NA.



SAT / UNSAT Performance Step: 5 REQUEST The Turbine Generator Building watch perform one of the following: (Step 5.42) Standard: _____ PLACE OC to MAB Chiller 11A(21A) in service OR _____ CLOSE the following valves during the release:

• 1(2)-OC-0058, MAB CHILLER 11A(21A) OPEN LOOP ACW RETURN FV-9316 INLET ISOLATION VALVE

• 1(2)-OC-0059, MAB CHILLER 11A(21A) OPEN LOOP ACWRETURN FV-9316 OUTLET ISOLATION VALVE

Comment: MAB Chiller 11A(21A) is secured per the Initiating Cue

OC-0058 and OC-0059 are already closed per the Initiating Cue which satisfies this step.

Cue: If asked report as the TGB watch that Open Loop flow to MAB Chiller 11A(21A) is isolated and OC-0058 and OC-0059 are closed.

Notes:



SAT / UNSAT Performance Step: 6 IF 1(2)WL-FQI-4078 LWPS Discharge Header Flow Totalizer Indicator is operable, THEN RECORD the beginning totalizer reading: (Step 5.43) Standard: _____ RECORDS beginning Totalizer Reading. Comment: The student should be able to record the Totalizer reading as read from the indicator.

Cue: If asked report from the control room that there are no OAS entries for WL-FQI-4078 and that the Flow Totalizer is Operable.

Notes: SAT / UNSAT Performance Step: 7 NOTIFY Control Room personnel the release is to commence. (Step 5.44) Standard: _____ NOTIFIES Control Room personnel that release of WMT 1(2)D is to commence.

Comment: Cue: Notes:



SAT / UNSAT Performance Step: 8 REQUEST Control Room to immediately notify Radwaste Control Room Operator if the number of running CW pumps is decreased during the release. (Step 5.45) Standard: _____ REQUESTS Control Room assistance in monitoring CW Pump flow. Comment: Cue: Acknowledge that Control Room personnel will inform student of any changes to CW Pump flow.

Notes: SAT / UNSAT Performance Step: 9 REQUEST Control Room personnel to log time/date, release number and tank being released. (Step 5.46) Standard: _____ REQUESTS Control Room to log WMT 1(2)D release time, release number and tank

being released.. Comment: Cue: Acknowledge that Control Room personnel will make log book entry.

Notes:



SAT / UNSAT Performance Step: 10 (C) PLACE “1(2)WL-FV-4077 WASTE MONITOR TANK PUMPS 1A, B & C(2A, B & C) DISCHARGE DIVERT VALVE” handswitch in DISCHARGE. (Step 5.47)

Standard: _____ PLACES “1(2)WL-FV-4077 WASTE MONITOR TANK PUMPS 1A, B & C(2A, B &

C) DISCHARGE DIVERT VALVE” handswitch in DISCHARGE. Comment: Cue: Shortly after student has simulated placing “1(2)WL-FV-4077 WASTE MONITOR TANK PUMPS 1A, B & C(2A, B & C) DISCHARGE DIVERT VALVE” handswitch in DISCHARGE, then make a simulated PA announcement that CW Pump #14 has tripped. Notes: Steps 5.48, 5.49, 5.50, 5.51 & 5.52 may or may not be performed depending on when the examiner makes the CW Pump #14 trip announcement. SAT / UNSAT Performance Step: 11 (C) IF the running number of CW pumps becomes less than that assumed on the Effluent Release Permit, OR Radiation Monitor RT-8038 trips for any reason, THEN immediately PERFORM the following: (Step 5.53)

Standard: _____ PLACE “1(2)WL-FV-4077 WASTE MONITOR TANK PUMPS 1A, B & C(2A, B & C)

DISCHARGE DIVERT VALVE” in RECIRC position. _____ NOTIFY the Unit Supervisor/Shift Manager the release is secured. _____ NOTIFY Chemistry the release is secured. _____ GO TO Step 5.55. Comment: Based on the Caution prior to step 5.47 the student may secure the release as soon as the announcement of CW Pump #14 trip is made. The Critical Task is satisfied as long the student secures the release. Cue: Notes: -TERMINATE THE JPM STOP TIME_______________



Job Performance Measure: LIQUID WASTE RELEASE WITH CW PUMP TRIP Performer’s Name: _____________________________________________ Date Performed: ____________________ Time to Complete: ____________________ JPM Results: Sat / Unsat Evaluator:_________________________ Signature:_________________________ Date: _________________________




proper authorization. The Unit is at 100% Power. The following conditions have been established for the release of Waste Monitor Tank (WMT) 1(2)D:

• WMT 1(2)D is on Long Path Recirculation. • RT-8038, Liquid Waste Monitor, is INOPERABLE • All four (4) Circulating Water (CW) Pumps are running. • MAB Chillers 11C(21C) and 11D(21D) are in service. • Open Loop ACW is isolated to MAB Chiller 11A(21A). • RCB Chillers 11A(21A) and 11B(21B) are in service. • Open Loop Valve 1(2)-OC-0292 is OPEN. • The Shift Manager has 0PSP07-WL-LDP2, Liquid Effluent Permit With RT-8038

Inoperable, and is ready to authorize the release of WMT 1(2)D. • Chemistry has just called and is ready for the release of WMT 1(2)D.

INITIATING CUE: The Unit Supervisor directs you to continue with 0POP02-WL-0100, Liquid Waste Release, at Step 5.38 for the release of WMT 1(2)D.




TITLE: PLACE RWST ON RECIRCULATION JPM NO: P3 REVISION: 1 LOCATION: UNIT 1 or 2



JPM Title: PLACE RWST ON RECIRCULATION JPM No.: P3 Rev. No.: 1 STP Task: T18450, Lineup to recirculate and / or purify the refueling /

borated water storage tank. STP Objective: CRO92051, GIVEN a plant or system condition, PREDICT the

operation of the Spent Fuel Pool Cooling and Cleanup System. Related K/A Reference: 006 A4.02 [4.0/3.8] Emergency Core Cooling System: Ability to

manually operate and/or monitor in the control room; Valves. References: 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System Task Normally Completed By: PO Method of Testing: Simulated Location of Testing: Plant Time Critical Task: NO Alternate Path JPM: NO Validation Time: 30 Minutes Required Materials (Tools/Equipment): Student Handout copy of 0POP02-FC-0001, Spent Fuel Pool

Cooling and Cleanup System, Section 7.4



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 applicant): 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’VE COMPLETED THE TASK. CAUTION: Do not operate or alter equipment configuration in the plant without

proper authorization. INITIAL CONDITIONS: Unit 1 is at 100% power, steady state conditions. Maintenance has been recently completed on the Refueling Water Purification Pump (RWPP) and it is time to return it to service. INITIATING CUE: The Unit Supervisor directs you to place the RWST on purification recirculation using the RWPP through SFP demineralizer 1A(2A) in accordance with 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System. Prerequisites of this procedure have been verified. SFP Purification is aligned through SFP Demin 1B(2B). Another Plant Operator is available in the FHB to start the RWWPP when ready.

-DO NOT DISCLOSE INFORMATION BELOW THIS LINE- COMPLETION CRITERIA: Places RWST on Purification recirc IAW section 7.4 of POP02-FC-0001.


JOB PERFORMANCE MEASURE INFORMATION SHEET (cont’d)

HANDOUTS: Student HO of working copy of 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System. NOTES:

1) The Handout copy of the procedure has only the front section for Prerequisites and Notes/Precautions and the applicable sections for performance of the task.

2) The area around the Refueling Water Purification Pump (RWPP) may be posted as a Radiation Area in both units. In addition the area around the RWPP in Unit 2 may be posted as a Contaminated Area. This contaminated area is limited to the area immediately around the pump base and the area immediately forward of the pump, centered around a floor drain immediately forward of the pump. The valves and indications that will need to be accessed for this JPM are not in the contaminated area.

3) Candidate may make reference for the need to use gloves while manipulating valves and equipment in the field. If the candidate indicates that he/she will have to get a pair of gloves, acknowledge it and tell them because we will be simulating operations and that gloves will not be required.



NOTE:


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

SAT / UNSAT Performance Step: 1 JPM START TIME_______________ Obtain a current copy of 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System. Standard: _____ Obtains a copy of 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup

System. Comment: When the operator demonstrates he/she can locate a controlled copy of the correct procedure, provide him/her the JPM copy. The operator should review notes and precautions. Cue: Notes:



SAT / UNSAT Performance Step: 2 Review the Prerequisites, Notes, and Precautions Standard: _____ Reviews the procedure Notes and Precautions Comment:

1) It is not necessary for performer to read aloud.

2) The performer should transition to section 7.4, Purification of RWST

Cue: (If Asked) The 1A (2A) SFP Demineralizer Boron concentrations are equalized. (If Asked) No Emergency Diesel Generator (ESF Diesel) is operating or is scheduled to be run. Notes:



SAT / UNSAT Performance Step: 3 IF simultaneous purification of the SFPCCS AND RWST is desired, THEN ENSURE the Spent Fuel Pool Purification System is aligned to Demineralizer 1B(2B). (Step 7.4.1) Standard: _____ Verifies SFP purification is in service and aligned through SFP demin 1B (2B). Comment: As per the Initiating Cue, SFP Purification is aligned through SFP Demin 1B(2B). Cue: The Unit Supervisor reports that SFP purification is in service and aligned through SFP demin 1B. Notes:



SAT / UNSAT Performance Step: 4 OPEN "RWST TO SFP CLEANUP SYS FV-3936" valve. (Step 7.4.2) OPEN "RWST TO SFP CLEANUP SYS FV-3937" valve. (Step 7.4.4) Standard: _____ Contacts the Control Room to open the RWST TO SFP CLEANUP SYS valves FV-

3936 and FV-3937. Comment: Cue: (After a few seconds) – The Control Room reports valves SI-FV-3936 and SI-FV-3937 are open.

If performing in Unit 2 the student should ask about TMOD T2-14-13955-103. State that this TMOD is NOT installed. Notes: The student will NA procedure step 7.4.3.



SAT / UNSAT Performance Step: 5 (C) OPEN 1(2)-FC-0046B "SFP PURIFICATION LOOP 1A(2A) RETURN TO RWST ISOLATION VALVE". (Step 7.4.5) Standard: _____ Opens 1(2)-FC-0046B “SFP PURIFICATION LOOP 1A(2A) RETURN TO RWST

ISOLATION VALVE. Comment: 1) This valve is located in the MAB 41’ elevation, filter row Room 237. It is a wall

mounted reach rod 90° turn valve requiring a wrench for operation. When facing the south wall, it is about 1/3 of the way down the hall, on the right side, approximately 1’ above the ground.

2) A ratchet wrench is needed to operate the valve and is available in the Radwaste Control Room.

Cue: 1(2)-FC-0046B: Initially - CLOSED Finally - OPEN Notes:



SAT / UNSAT Performance Step: 6 START " N1(2)FCHS1419 RWPP 1A(2A)". (Step 7.4.6) Standard: _____ Calls the available Plant Operator in the FHB on the radio to start the 1A(2A)

RWPP. Comment: The Pump Control Handswitch is located in the FHB and the pump itself is located in the MAB. Cue: 1) If asked, pump supply breaker is closed. 2) If the candidate calls the available Plant Operator:

a) The Operator reports that he has taken the pump start switch to “START” and has a RED indicating light illuminated on ZLP-749.

b) The RW Purification Flow Low Alarm on ZLP-749 has cleared. c) The available Plant Operator is leaving the area to continue rounds.

Notes:



SAT / UNSAT Performance Step: 7 (C) THROTTLE 1(2)-FC-0042 "REFUELING WATER PURIF PUMP DISCHARGE THROTTLE VALVE", as necessary to obtain between 190 AND 200 gpm as indicated by "1(2)-FC-FIS-1417". (Step 7.4.7) Standard: _____ Throttles 1(2)-FC-0042, REFUELING WATER PURIF PUMP DISCHARGE

THROTTLE VALVE, as necessary to obtain between 190 and 200 gpm on 1(2)-FC-FIS-1417.

Comment: All of the components are located in the RCB/MAB Chilled Water Pump Room – MAB 10’ elevation Room 64 (Penetration Space). 1(2)-FC-FIS-1417 is on the south wall, forward of the RWPP.

The area around the Refueling Water Purification Pump (RWPP) may be posted as a Radiation Area in both units. In addition the area may be posted as a Contaminated Area. If contaminated, the area is normally limited to the area immediately around the pump base, the area immediately forward of the pump and centered around a floor drain immediately forward of the pump. The valves and indications that will need to be accessed for this JPM can be pointed to and a description given of how the valve would be operated.

If needed the next page has a picture of 1(2)-FC-FIS-1417. Cue: If asked:

1) RWPP is running smoothly, initial discharge pressure is 130 psig.

2) Discharge flow on 1(2)-FC-FIS-1417 is initially indicating 225 gpm.

3) As the candidate simulates throttling down on 1(2)-FC-0042, give flow decrements of 10 gpm down to 195 gpm. Final pump discharge pressure is 140 psig.

Notes:



SAT / UNSAT Performance Step: 8 VERIFY SFP Demineralizer ∆P less than 20 psid. Demin 1A(2A) "1(2)-FC-PDI-4405" (Step 7.4.8)

VERIFY SFP demineralizer outlet filter ∆P less than 35 psid. Demin 1A(2A) "1(2)-FC-PI-1412" - "1(2)-FC-PI-1413" (Step 7.4.9)

VERIFY SFP demineralizer flow less than 250 gpm. Demin 1A(2A) "1(2)-FC-FI-1414" (Step 7.4.10) Standard: _____ Verifies the following SFP demineralizer parameters:

1) SFP demineralizer ΔP < 20 psid. 2) SFP demineralizer outlet filter ΔP is < 35 psid. 3) SFP demineralizer flow < 250 gpm.

Comment: 1) 1(2)-FC-PDI-4405, Demin 1A(2A) ΔP Indicator is located on the 41’ MAB Rm 238

Demin Row.

2) 1(2)-FC-PI-1412 & 13, SFP Demin Filter 1A(2A) Inlet & Outlet Pressure Indicator is located on the 41’ MAB Rm 237 Filter Row.

3) 1(2)-FC-PI-1414, SFP Demin Flow is located on the 41’ MAB Rm 237 Filter Row.

Cue:

1) Demineralizer ΔP on 1(2)-FC-PDI-4405 → 7 psid

2) Outlet Filter ΔP is reading 1(2)-FC-PI-1412 13 psig and 1(2)-FC-PI-1413 9 psig

3) Demineralizer flow on 1(2)- FC-FI-1414, → 195 gpm

Notes: -TERMINATE THE JPM STOP TIME_______________


VERIFICATION OF COMPLETION Job Performance Measure: PLACE RWST ON RECIRCULATION Performer’s Name: _____________________________________________ Date Performed: ____________________ Time to Complete: ____________________ JPM Results: Sat / Unsat Evaluator:_________________________ Signature:_________________________ Date: _________________________




proper authorization. INITIAL CONDITIONS: Unit 1 is at 100% power, steady state conditions. Maintenance has been recently completed on the Refueling Water Purification Pump (RWPP) and it is time to return it to service. INITIATING CUE: The Unit Supervisor directs you to place the RWST on purification recirculation using the RWPP through SFP demineralizer 1A(2A) in accordance with 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System. Prerequisites of this procedure have been verified. SFP Purification is aligned through SFP Demin 1B(2B). Another Plant Operator is available in the FHB to start the RWPP when ready.

LOT 20 NRC OP-TEST SCENARIO #3 Rev #1 Page 1 of 26

LOT 20 NRC EXAM

SIMULATOR OPERATING TEST SCENARIO #3 Revision #1 Week of 09/28/2015


SCENARIO OUTLINE

Facility: South Texas Project Scenario No.: 3 Op-Test No.: LOT 20 NRC Examiners: Operators:

Initial Conditions: • Reactor Power is in Mode 2 at 10-8 AMPs and Stable. BOL (IC #217) Turnover: • Unit 1 is returning to service after a forced 7 day outage. • After the Reactor was taken critical, HHSI & LHSI Pumps 1B and ECW Pump 1B were taken

out of service to repair an issue with the breakers. Expected return to service is 2 hours. The crew is to continue raising power per 0POP03-ZG-0004, Reactor Startup, Step 6.32 and be prepared to enter Mode 1 as soon as the breakers are returned to service.

• Circulating Water Pump #14 is removed from service for maintenance. • SU SGFP #14 is in service. Lineups are being performed on SGFPT #11 so that warmup of

the pump can begin. Lineups have not been started yet for SGFPTs #12 and #13.

Event No. Malf. No. Event Type* Event Description

1 (0 min)

NA RO (R) SRO (R) Withdraw control rods to raise reactor power to 1% - 3%

2 (20 min)

05-12-04 1

BOP (I) SRO (I, TS) SG 1D Controlling NR level channel fails low. LT-0549

3 (30 min)

04-09-03 1

RO (C) SRO (C, TS) Over current trip on ECW Pump 1C

4 (40 min)

08-12-04 1

BOP (C) SRO (C) Over current trip on SU SGFP #14.

5 (50 min)

50-HV-01 1 ALL (M) PZR PORV RC-PSV-655A fails open. Manual closure attempt is

unsuccessful. Manual block valve will not close. (Requires a Rx trip if not already)

SBLOCA due to PORV (Critical Task) 6

(60 min) 01-12-04B

1 BOP (C) Train B of Phase A fails to auto actuate with CV-MOV-0023 failed open

7 (N/A)

10-09-01 1 RO (C)

SRO (C)

During SBLOCA, a lockout on 13.8KV STBY Bus 1F causes Sequencer Mode 3 on Train A. ECW Pump 1A fails to auto start. (Critical Task)

* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.


SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES: Refer to the Instructor Guide for directions on Simulator Setup, Expected Booth Communications and Expected Booth Actions.

CRITICAL PARAMETERS: The following parameters may be of value in evaluating crew performance and should be automatically recorded during the scenario. Once the scenario is complete for each crew, printout the Critical Parameters and label the printout with date, time, Crew # and scenario #. • ESF DG #11 Speed • HHSI Pump 1A Running Indication • RCS Wide Range Pressure • ECW Pump 1A Running Indication OPERATOR ACTIONS TABLE NOTES: 1. Critical Tasks are indicated by "C" in the position column and indicated in bold type. 2. Actions required throughout the event are indicated as "(continuous)" in the position

column. 3. Shaded cells indicate procedural entry points.


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event Description: Withdraw control rods to raise reactor power to 1% - 3%

Time

Position

Required Operator Actions

Notes RO NOTIFY Chemistry to secure RCS boron

sampling. 0POP03-ZG-0004, Reactor Startup, Step 6.31.

RO WHEN RCS average temperature is greater than or equal to 571ºF OR Tave/Tref deviation alarm is clear, THEN SECURE taking data on Form 1.

Step 6.32 0POP03-ZG-0004, Reactor Startup, Form 1 will be partially filled out and given with the turnover sheet.

RO RAISE Reactor Power to approximately 1 to 3%.

Step 6.33 Will use control rods.

SRO ATTACH all ECPs to this completed procedure.

Step 6.34 If asked, then let the US know that the Shift Manager has the ECPs and will attach them to the completed procedure.

SRO CONTINUE plant startup per 0POP03-ZG-0005, Plant Startup to 100%.

Step 6.35

SRO FORWARD a copy of the completed Reactor Startup package to Reactor Engineering. This information will be used to evaluate estimated versus actual critical conditions.

Step 6.36 If asked, then inform US that the Shift Manager will perform this step. Event 2 can be triggered on signal from NRC Examiner.


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event Description: SG 1D Controlling NR level channel fails low. LT-0549

Time

Position


Notes

BOP Acknowledges and announces the following annunciators on 06M4: SG 1D LEVEL LO-LO ALERT (D-6)

Operator will respond using the Annunciator Response Procedure but should also recognize the need to perform immediate actions.

SRO/BOP

Determines SG 1D Controlling Narrow Range Channel LT-0549 is failed low. Performs immediate actions of 0POP04-FW-0001: • PLACE any SG Feedwater

Regulating Valve(s) not properly responding in MANUAL AND ADJUST as necessary to restore affected SG NR level(s) to between 68% and 74%.

Failed Channel is FW-LT-0549. This is an Immediate Action – BOP takes Manual control of SG 1D LPFRV.

SRO

(continuous)

Directs actions of 0POP04-FW-0001, Loss of Steam Generator Level Control.

BOP CHECK SG Feedwater Regulating Valve(s) - RESPONDING IN AUTOMATIC (See previous immediate action step)

0POP04-FW-0001, Loss of Steam Generator Level Control, Step 1.0

BOP CHECK SGFP Speed Controllers - RESPONDING IN AUTOMATIC

Step 2.0 NA Speed Controllers OOS

BOP CHECK Main Feedwater Regulating Valves:

Step 3.0 MFRVs are not in service.

BOP CHECK Low Power Feedwater Regulating Valves: • CHECK Low Power Feedwater

Regulating Valve(s) - IN SERVICE • CHECK Low Power Feedwater

Regulating Valve(s) - ANY IN MANUAL

• CHECK Affected Low Power Feedwater Regulating Valve(s) - RESPONDING IN MANUAL

Step 4.0

BOP CHECK SGFP Master Speed Controller - IN MANUAL


BOP CHECK Individual SGFP Speed Controllers - ANY IN MANUAL



OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event Description: SG 1D Controlling NR level channel fails low. LT-0549 Time

Position

Applicant’s Actions or Behavior

Notes

BOP MONITOR Feedwater/Steam Header DP Step 9.0 NA SGFPT’s are NOT running.

BOP RESTORE Affected SG NR Level(s) To Between 68% And 74%

Step 10.0

BOP

MONITOR SG NR Levels - GREATER THAN 20%

Step 11.0

BOP

MONITOR SG NR Levels - LESS THAN 87.5%

Step 12.0

BOP CHECK SG NR Level Indicators - ALL OPERABLE (RNO) PERFORM the following: • SELECT the operable SG level channel

for affected SG(s) level control. • CHECK status of “QDPS ALARM

SGWLCS” Annunciator Lampbox 06M3-A8

• IF Annunciator Lampbox 06M3-A8 is illuminated, THEN DETERMINE the alarming channel(s) using the QDPS DETAIL DATA Menu, Page 5 display.

Step 13.0 SG 1D NR LT-0549 is failed low. Will select LT-574 for control. Annunciator Lampbox 06M3-A8 will NOT be illuminated.

BOP CHECK Feedwater Flow Transmitters - ALL OPERABLE

Step 14.0

BOP CHECK Steam Flow Transmitters - ALL OPERABLE

Step 15.0

BOP CHECK Steam Pressure Transmitters - ALL OPERABLE

Step 16.0

BOP CHECK SG NR Levels - BETWEEN 68% And 74%

Step 17.0

BOP CHECK Main Feedwater Regulating And Low Power Feedwater Regulating Valves Automatic Control - OPERABLE

Step 18.0 MFRVs are NOT in service.


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event Description: SG 1D Controlling NR level channel fails low. LT-0549 Time

Position

Applicant’s Actions or Behavior

Notes

BOP CHECK Main Feedwater Regulating OR Low Power Feedwater Regulating Valve(s) - IN AUTO (RNO) WHEN SG levels return to between 68% and 74%, THEN PERFORM the following: • PLACE in-service Feedwater

Regulating Valve(s) with operable Automatic Control in Auto.

• MONITOR proper operation of Feedwater Regulating Valve(s) in Auto.

Step 19.0

BOP CHECK SGFP Master Speed Controller - IN AUTO


SRO TAKE Appropriate Actions Per Technical Specifications 3.3.1, 3.3.2, 3.3.3.6 and TRM 3.7.1.7

Step 21.0 See TS Actions below.

TS 3.3.3.6 and TRM 3.7.1.7 do NOT apply.

SRO NOTIFY I&C To Place The Affected Channel In Trip Or Bypass. REFER TO Addendum 2, Procedure List For The Appropriate Procedure.

Step 22.0 Event 3 can be triggered after SRO has checked TS.

SRO INITIATE Corrective Actions For Failed

Component Step 23.0

Most Limiting TS:

3.3.1.14 Action 6 and 3.3.2.5.b & 3.3.2.6.d Action 20

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: a. For Functional Units with installed bypass test capability, the inoperable channel may be placed in bypass, and must be placed in the tripped condition within 72 hours. Note: A channel may be bypassed for up to 12 hours for surveillance testing per Specification 4.3.1.1, provided no more than one channel is in bypass at any time. b. For Functional Units with no installed bypass test capability, 1. The inoperable channel is placed in the tripped condition within 72 hours, and 2. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 12 hours for surveillance testing of other channels per Specification 4.3.1.1. (4.3.2.1)


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event Description: Over current trip on ECW Pump 1C.

Time

Position


Notes RO Acknowledges and announces the

following annunciators from 02M4: ECW PMP 1C TRIP (C-7)

There are other alarms that will annunciate due to the trip of ECW Pump 1C.

RO Determines ECW Pump ‘C’ has tripped. SRO

(continuous) Directs actions of 0POP09-AN-02M4, Window C-7, ECW PMP 1C TRIP.

RO ENSURE standby ECW and CCW train started.

0POP09-AN-02M4, Window C-7, Step 1 & 2

RO PLACE Standby DG 13(23) "EMER STOP" plunger in the PULL TO STOP position to prevent diesel operation without cooling water.

Step 3

RO PLACE the following handswitches in PULL TO LOCK: • ECW Pump ‘1C’ • ECW Screenwash Booster Pump ‘1C’ • ECW Traveling Screen ‘1C’

Step 4

RO IF ECW Train 1C(2C) is being used for ECP Blowdown, THEN ENSURE "ECW TRAIN C BLWDN ISOL FV-6937" closed. { CP002}

Step 5

The Blowdown Valve should have automatically closed with the ECW Pump tripped.

RO SECURE the affected CCW train (IF running) per 0POP02-CC-0001, Component Cooling Water.

Step 6 NA CCW Pump 1A was running.

RO SECURE the affected ECW train (IF running) per 0POP02-EW-0001, Essential Cooling Water Operations.

Step 7

RO IF adequate CCW pumps are NOT available to provide flow for current plant conditions, THEN adjust loads as needed per 0POP02-CC-0001, Component Cooling Water.

Step 8


OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 3

Event Description: Over current trip on ECW Pump 1C.

Time

Position


Notes RO PERFORM the following:

• ENSURE Essential Chiller 12C(22C) secured per 0POP02-CH- 0005, Essential Chiller Operation.

• PLACE Essential Chiller 12C(22C) handswitch in PTL.

• START essential chiller(s) as needed per 0POP02-CH-0005, Essential Chiller Operation.

Step 9

RO PLACE Essential Chilled Water Train C Pump 11C(21C) to PTL.

Step 10

RO START additional trains of CRE and EAB HVAC, as necessary, per 0POP02-HE-0001, Electrical Auxiliary Building HVAC System.

Step 11

RO IF RHR Train C was in service, THEN PERFORM the following: • PLACE an alternate RHR train in

service per 0POP02-RH-0001, Residual Heat Removal System Operation.

• SECURE RHR Train C per 0POP02-RH-0001, Residual Heat Removal System Operation.

• PLACE the pump handswitch in PTL.

Step 12 NA RHR is not in service.

RO PERFORM the following: • ENSURE CCW Train C secured per

0POP02-CC-0001, Component Cooling Water

• PLACE “COMP CLG WTR PUMP 1C(2C)” handswitch in PTL

Step 13

SRO ENSURE ECW Train C secured per 0POP02-EW-0001, Essential Cooling Water Operations

Step 14

RO TAKE appropriate action per Technical Specifications 3.5.2, 3.6.2.1, 3.6.2.3, 3.7.3, 3.7.4, 3.7.7, 3.7.14, 3.8.1.1, 3.8.1.2 and 3.8.1.3

Step 15 See next page for TSs.

RO INVESTIGATE cause of ECW Pump 1C(2C) trip.

Step 16 Event 4 can be triggered on a signal from the NRC Examiner.


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event Description: Over current trip on ECW Pump 1C.

Time

Position


Notes Tech Specs Information: • TS 3.5.2 Action b. With less than 2 of the required subsystems OPERABLE, within 1 hour restore

at least two subsystems to OPERABLE status or apply the requirements of the CRMP, or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.

• TS 3.7.4 Action b. With two or more essential cooling water loops inoperable, within 1 hour restore at least two loops to OPERABLE status or apply the requirements of the CRMP, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Similar action for other Train B components affected by ECW.

• TS 3.8.1.1, Action f. With two or three of the above required standby diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing the requirements of Specification 4.8.1.1.1.a within 1 hour and at least 8 hours thereafter. With two of the above required standby diesel generators inoperable, within 24 hours restore at least two standby diesel generators to OPERABLE status or apply the CRMP, or be in at least HOT STANBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

• TS 3.8.1.1, Action d applies. • Action ‘d’ requires within 24 hours make the remaining ESF DG’s operable (including

support systems) and the Turbine Driven AFW Pump operable, otherwise apply the CRMP or be in at least Hot Standby within the next 6 hours and in Cold Shutdown within the following 30 hours.

• TS 3.6.2.1 CS, 3.6.2.3 RCFCs, 3.7.3, CCW, 3.7.14 Ess Chill Water cascade in Inoperability due to this event. All have an Action b that is similar to Action b in TS 3.5.2 and TS 3.7.4.

• TS 3.7.7 CRE HVAC Action c. With two Control Room Makeup and Cleanup Filtration Systems inoperable for reasons other than condition e, within 72 hours restore at least two systems to OPERABLE status, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

SUMMARY: The most time-limiting TS 3.5.2 & TS is 3.7.4 Action b (and cascading systems a Action b) 1 HOUR and TS 3.8.1.1 Action f 1 HOUR (Power Availability Surveillance) NOTE: TS 3.8.1.2 and 3.8.1.3 Do NOT Apply.


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event Description: Over current trip on SU SGFP #14.

Time

Position


Notes

BOP Acknowledges and announces the following annunciator on 07M3: S/U SGFP L.O> SYS TRBL (F-6)

This alarm will clear shortly after the SU SGFP #14 trips and the Crew may not respond to this alarm.

SRO/BOP Determines that SU SGFP #14 has tripped. SRO

(continuous) Directs actions of 0POP04-FW-0002, SGFPT Trip.

After immediate action is completed Crew will go directly to Step 5 of 0POP04-FW-0002, SGFPT Trip, if they recognize the CIP action for being less than 15% power.

BOP CHECK SGFPTs - REQUIRED NUMBER RUNNING (RNO) PERFORM the following: • ENSURE SU SGFP is running. • START a Standby FW Booster Pump. • IF a SGFPT trips with the SU SGFP

already in service OR NOT available, THEN PERFORM the following: • IF an idle (3300 RPM) SGFPT is

available, THEN raise its speed using its individual speed controller to provide adequate Feedwater flow.

• IF feedwater flow is still LESS THAN required to recover SG Level, THEN GO TO Addendum 1, Turbine Load Reduction, to reduce Turbine load to match steam flow with feedwater flow.

0POP04-FW-0002, SGFPT Trip, Step 1.0 The Crew will start a standby FWBP. SGFPTs will not be available to be placed in service yet and the Main Turbine is not online so the Crew will have to continue with the procedure.


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event Description: Over current trip on SU SGFP #14.

Time

Position


Notes BOP CHECK SGFP Master Speed Controller –

• Controller – OPERABLE In Automatic • Steam Header Pressure PT-557 status -

OPERABLE • Feedwater Pump Discharge Pressure

PT-558 status - OPERABLE • Controlling Steam Flow Channels -

OPERABLE

Step 2.0 Immediate Action but NA because NOT in service.

BOP CHECK Feedwater Flow – ADEQUATE FOR CURRENT STEAM DEMAND (RNO) IF Reactor Power - LESS THAN OR EQUAL to 15%, THEN GO TO Step 5.0.

Step 3.0 Crew will go to step 5.0

BOP MONITOR Reactor Power – GREATER THAN 15% (RNO) IF feedwater flow is still inadequate, THEN PERFORM the following: • TRIP the Turbine. • REDUCE Reactor Power to between 1%

and 3%. • ENSURE Steam Dump Mode Selector

Switch in STEAM PRESSURE mode. • USE AFW to control SG levels as

directed by Unit Supervisor/Shift Manager.

Step 5.0 Steam Dumps are already in the Steam Pressure Mode. The Crew will have to start AFW. Event 5 can be triggered on a signal from the NRC Examiner.


OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 5, 6 & 7

Event 5 Description: PZR PORV RC-PSV-655A fails open. Manual closure attempt is unsuccessful. Manual block valve will not close. (Requires a Rx trip if not already) SBLOCA due to PORV (Critical Task) Event 6 Description: Train B of Phase A fails to auto actuate with CV-MOV-0023 failed open Event 7 Description: During SBLOCA, a lockout on 13.8KV STBY Bus 1F causes Sequencer Mode 3 on Train A. ECW Pump 1A fails to auto start. (Critical Task)

Time

Position


Notes

RO Acknowledges and announces alarms associated with PZR PORV RC-PSV-0655A failing open.

This event will cause PZR pressure and level to lower quickly. The Crew may not have time to respond with annunciator response procedures.

SRO/RO Determines PZR PORV RC-PSV-0655A has failed open.

SRO (continuous)

Directs a Reactor Trip and Safety Injection. Enters 0POP05-EO-EO00, Reactor Trip or Safety Injection.

RO/BOP Completes immediate actions of EO00. Reactor Trip/SI: • Reactor Tripped. • Turbine Tripped. • AC ESF Busses energized. • SI is actuated or will perform a manual

SI due to degrading conditions.

0POP05-EO-EO00, Reactor Trip or Safety Injection Steps 1-4. RO will announce status of immediate action steps as he/she performs them.

BOP Operator will monitor the plant and make an announcement of the Reactor trip.

SRO Directs/ensures the immediate actions of 0POP05-EO-EO00, Reactor Trip or Safety Injection have been completed by performing a procedure read through of them.

Before beginning the verification of immediate actions, the US may direct the BOP operator to throttle AFW flow to limit RCS cooldown.

BOP VERIFY Proper SI Equipment Operation Per ADDENDUM 5, VERIFICATION OF SI EQUIPMENT OPERATION

(Step 5) See Actions on Page 17 - 21


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 3 Event No.: 5, 6 & 7

Event 5 Description: PZR PORV RC-PSV-655A fails open. Manual closure attempt is unsuccessful. Manual block valve will not close. (Requires a Rx trip if not already) SBLOCA due to PORV (Critical Task) Event 6 Description: Train B of Phase A fails to auto actuate with CV-MOV-0023 failed open Event 7 Description: During SBLOCA, a lockout on 13.8KV STBY Bus 1F causes Sequencer Mode 3 on Train A. ECW Pump 1A fails to auto start. (Critical Task) Time

Position


Notes

RO MONITOR If Containment Spray Is Required: • Containment pressure ‑ GREATER

THAN 9.5 PSIG (QDPS) (RNO) • PERFORM the following:

• CHECK Containment pressure - HAS EXCEEDED 9.5 PSIG (CP - 18) • "PRESS PR‑ 0934"

OR • "EXTD RNG PRESS

PR‑ 9759" • IF containment pressure HAS

EXCEEDED 9.5 PSIG, THEN GO TO Step 6.b.

• IF containment pressure HAS REMAINED LESS THAN 9.5 PSIG, THEN GO TO Step 7.

(Step 6) Containment pressure will be less than 9.5 psig.




Position


Notes

RO CHECK RCP Seal Cooling: • ENSURE seal injection flow between

6 and 13 gpm

(Step 7) RO may have to adjust seal injection.

RO MONITOR RCS Temperatures ‑ • WITH ANY RCP RUNNING, RCS

TAVG STABLE AT OR TRENDING TO 567°F

OR • WITHOUT ANY RCP RUNNING,

RCS TCOLD STABLE AT OR TRENDING TO 567°F

(Step 8) If AFW has been properly throttled from the original Reactor Trip then RCS temperature should be trending to 567°F.

RO CHECK Pressurizer Status: • PORVs ‑ CLOSED • Normal pressurizer spray valves -

CLOSED • Auxiliary spray valve - CLOSED • Excess letdown isolation valves -

CLOSED

(Step 9)

SRO/RO (C)

MONITOR If RCPs Should Be Stopped: • HHSI pump - AT LEAST ONE

RUNNING • RCS pressure - LESS THAN 1430

PSIG • STOP all RCPs OR (RNO) • GO TO Step 11

(Step 10) Trip all RCPs when the RCP Trip Criteria is met from the EOPs. May occur before or after this step because the criteria is listed on the CIP. NOTE: When these conditions are met the crew has 5 minutes to trip the RCPs.

RO VERIFY The Following Containment Isolation Valves – CLOSED • Seal return isolation valves • Containment atmosphere radiation

monitor isolation valves

(Step 11)




Position


Notes

RO CHECK If SG Secondary Pressure Boundary Intact: • CHECK pressures in all SGs –

• CONTROLLED OR RISING • GREATER THAN

CONTAINMENT PRESSURE

(Step 12)

RO CHECK If SG Tubes Are Intact: • Main steamline radiation ‑

NORMAL • IF SG blowdown in service, THEN

SG blowdown radiation ‑ NORMAL • CARS pump radiation ‑ NORMAL • NO SG level rising in an uncontrolled

manner

(Step 13)

RO CHECK If RCS Is Intact: • Containment radiation ‑ NORMAL • Containment pressure ‑ NORMAL • Containment wide range water level

‑ NORMAL (RNO) GO TO 0POP05-EO-EO10, LOSS OF REACTOR OR SECONDARY COOLANT, Step1. • MONITOR Critical Safety Functions. • WHEN Addendum 5 of this procedure

is complete, THEN Functional Restoration Procedures may be IMPLEMENTED.

(Step 14)

BOP Completes 0POP05-EO-EO00, Addendum 5.

Will not transition to a Functional Recovery Procedure until Addendum 5 is complete.




Position


Notes

BOP VERIFY FW isolation: • SGFPTs – TRIPPED • SU SGFP – TRIPPED • VERIFY the following valves –

CLOSED • FWIVs • FWIBs • FW preheater bypass valves • FW regulating valves • Low power FW regulating valves • SG blowdown isolation valves • SG sample isolation valves

0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation. (Step 1) This addendum is performed in parallel with Steps 5 to 14 of 0POP05-EO-EO00, Reactor Trip or Safety Injection.

BOP CHECK if main steamline should be isolated: • CHECK for any of the following

conditions: • Containment pressure – GREATER

THAN OR EQUAL TO 3 PSIG OR

• SG pressure (without low steamline pressure SI blocked) - LESS THAN OR EQUAL TO 735 PSIG

OR • SG pressure (with low steamline

pressure SI blocked) - LOWERING AT A RATE GREATER THAN OR EQUAL TO 100 PSI/SEC,BY OBSERVANCE OF THE STEAMLINE PRESSURE RATE BISTABLES

(Step 2)

BOP VERIFY AFW system status: • Motor-driven pump – RUNNING • Turbine-driven pump - RUNNING

(Step 3)




Position


Notes

BOP VERIFY AFW valve alignment - PROPER EMERGENCY ALIGNMENT

(Step 4)

BOP VERIFY total AFW Flow - GREATER THAN 576 GPM

(Step 5)

BOP VERIFY containment isolation phase A: • Phase A – ACTUATED (RNO) • Manually ACTUATE phase A. (Back to A/ER) • Phase A valves - CLOSED, REFER

TO ADDENDUM 1, PHASE A ISOLATION VERIFICATION

(RNO) • Manually CLOSE valves.

(Step 6) Event 6 Phase A, Train B, fails to actuate. Manually Actuate Phase A OR manually close CV-MOV-0024 to isolate normal letdown penetration.

BOP VERIFY ECW status: • ECW pumps – RUNNING • ECW pump discharge isolation valves

- OPEN

(Step 7)

BOP VERIFY CCW pumps - RUNNING (Step 8) BOP VERIFY RCFC status:

• RCFCs – RUNNING • Cooling water - TRANSFERRED TO

CCW

(Step 9)

BOP VERIFY SI pump status: • HHSI pumps – RUNNING • LHSI pumps – RUNNING

(Step 10)




Position


Notes

BOP VERIFY SI valve alignment – PROPER EMERGENCY ALIGNMENT

(Step 11)

BOP VERIFY SI flow: • RCS pressure - LESS THAN 1745

PSIG • HHSI pump flow – INDICATED • RCS pressure - LESS THAN 415

PSIG (RNO) • GO TO Step 13 of this Addendum.

(Step 12) RCS pressure may or may not be less than 1745 psig but will be greater than 415 psig so BOP will continue to step 13.

BOP VERIFY containment ventilation isolation: • Containment atmosphere radiation

monitor isolation valves – CLOSED • Normal purge supply and exhaust fans

– STOPPED • Supplemental purge supply and

exhaust fans – STOPPED • Purge Dampers - CLOSED

(Step 13)




Position


Notes

BOP VERIFY ventilation actuation: • Control room HVAC – OPERATING

IN EMERGENCY RECIRC • EAB HVAC - OPERATING IN

EMERGENCY RECIRC • FHB HVAC - OPERATING IN

EMERGENCY MODE • FHB Exhaust Fans - ONLY TWO

TRAINS OPERATING • Exhaust booster fans • Main exhaust fans

(RNO) • PERFORM the following:

• IF three trains FHB exhaust fans running, THEN PLACE one train FHB exhaust fans in PULL TO LOCK.

(Back to A/ER) • SECURE one FHB filter train by

PERFORMING the following: • PLACE the outlet damper

Controller in manual • Manually close the outlet damper • VERIFY proper operation of filter

train in service • Essential chilled water pumps –

RUNNING • Essential chillers – RUNNING • ECCS pump room fan coolers –

RUNNING • AFW pump cubicle fans – RUNNING • FHB truck bay doors - CLOSED

(Step 14)




Position


Notes

BOP NOTIFY Unit Supervisor that Addendum 5 is COMPLETE

(Step 15)

SRO IMPLEMENT Functional Restoration Procedures as required

(Step 16)

SRO RETURN TO procedure step in effect. (Step 17)


OPERATOR ACTIONS



Time

Position


Notes SRO

(continuous) Informs crew of transition to 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, and to monitor Critical Safety Functions

SRO/RO

(C)

MONITOR If RCPs Should Be Stopped: • HHSI pumps - AT LEAST ONE

RUNNING • RCS pressure - LESS THAN 1430

PSIG • STOP all RCPs

0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, Step 1.0 Trip all RCPs when the RCP Trip Criteria is met from the EOPs. Task will probably have already been completed by this time. NOTE: When these conditions are met the crew has 5 minutes to trip the RCPs.




Time

Position


Notes BOP

DEPRESSURIZE Intact SGs To 1000 PSIG • CHECK RCS pressure - GREATER

THAN 415 PSIG • CHECK pressurizer pressure LESS

THAN 1985 PSIG • BLOCK Low Steamline Pressure SI • CHECK condenser – AVAILABLE • CHECK steam dump in steam pressure

mode • PLACE steam dump controller in

MANUAL with zero demand. • ADJUST "HDR PRESS CONT PK-

0557" setpoint to BETWEEN 7.0 (980 PSIG) and 7.1 (994 PSIG).

• PLACE steam dump "MODE SEL" switch in the STEAM PRESS position.

• DEPRESSURIZE intact SGs to BETWEEN 980 PSIG and 994 PSIG using steam dumps in MANUAL.

• GO TO Step i. • CHECK RCS TAVG - LESS THAN

563ºFCHECK RCS TAVG - LESS THAN 563ºF

• PLACE steam dump "INTLK SEL" switches to BYPASS INTERLCK.

• ENSURE "HDR PRESS CONT PK-0557" in AUTO

• VERIFY steam dumps controlling SG pressures LESS THAN OR EQUAL TO 994 PSIG

• ADJUST intact SG PORV controller setpoints to BETWEEN 995 PSIG and 1000 PSIG (QDPS PRI/SEC).

• ENSURE SG PORV controllers in AUTO.

Step 2.0 With size of a SBLOCA the SG Pressures may already be below 1000 psig. If the condenser is NOT available (which is possible) This step will have the crew use the SG PORVs to depress the intact SGs to between 990 and 1000 psig. Event 7 will come in 10 minutes after the initiation of the Safety Injection. During SBLOCA, a lockout on 13.8KV STBY Bus 1F causes Sequencer Mode 3 on Train A. ECW Pump 1A fails to auto start. Critical Task Manually start ECW Pump 1A when it is determined that the pump did not auto re-start. Can Terminate Scenario when Depressurization of SGs begins if CT for ECW Pump has been accomplished.


OPERATOR ACTIONS



Time

Position


Notes RO/BOP MONITOR If SG Secondary Pressure

Boundary Intact: • CHECK pressures in all SGs ‑

• CONTROLLED OR RISING • GREATER THAN

CONTAINMENT PRESSURE

Step 3.0

RO RESET SI

Step 4.0

RO RESET ESF Load Sequencers

Step 5.0

RO RESET Containment Isolation Phase A

Step 6.0

RO RESET Containment Isolation Phase B

Step 7.0

SRO MONITOR INTACT SG Levels:

• NR levels ‑ GREATER THAN 14% [34%]

• CONTROL AFW flow to maintain NR levels BETWEEN 22% [34%] and 50%

Step 8.0 Terminate Scenario


CRITICAL TASK SUMMARY

POSITION

EXPECTED RESPONSE

ACCEPTANCE CRITERIA

SAT/

UNSAT SRO/RO TRIP ALL RCPs WHEN THE

RCP TRIP CRITERIA FROM THE EOPs IS MET.

Trip all RCPs so that CET temperatures do not become superheated when forced circulation in the RCS stops. NOTE: Within 5 minutes of reaching the RCP trip criteria.

SRO/RO MANUALLY STARTS ECW PUMP 1A WHEN IT IS DETERMINED THAT THE PUMP DID NOT AUTO START.

Manually start at least one ECW Pump (ECW Pump 1A) prior to the associated EDG tripping.


TURNOVER INFORMATION

• Reactor Power is in Mode 2 at 10-8 AMPs and Stable. BOL

• Unit 1 is returning to service following a forced 7 day outage.

• After the Reactor was taken critical, HHSI & LHSI Pumps 1B and ECW Pump 1B were taken out of service to repair an issue with the breakers. Expected return to service is 2 hours.

• The crew is to continue raising power per 0POP03-ZG-0004, Reactor Startup, Step 6.31. Critical Data has been recorded. A set of readings from 0POP03-ZG-0004, Form 1, will be due when you take the watch.

• After completing 0POP03-ZG-0004, Reactor Startup, then transition to 0POP03-ZG-0005, Plant Startup to 100%, and be prepared to enter Mode 1 as soon as the breakers for HHSI & LHSI Pumps 1B and ECW Pump 1B are returned to service.

• Circulating Water Pump #14 is OOS for maintenance. Expected return to service is 12 hours.

• SU SGFP #14 is in service. Lineups are being performed on SGFPT #11 so that warmup of the pump can begin. Lineups have not been started yet for SGFPTs #12 and #13.

• Cycle Burnup is 150 MWD/MTU. (BOL)

• RCS Boron Concentration is 2064 ppm.

• Boric Acid Tank ‘A’ is at 7315 ppm and ‘B’ is at 7309 ppm.

• No liquid waste discharges are in progress or planned.

• No personnel are in containment.

• FHB Truck Bay doors are closed.

• No ESF DG FOST’s are on recirc.

LCO Actions:

ESF DG 12 – TS 3.8.1.1 Action b and d. 0PSP03-EA-0002, ESF Power Availability, was completed 15 minutes ago. Action d was entered in the log 30 minutes ago as SAT.

ECW 1B - TS 3.7.4 ECW, 3.7.3 CCW, 3.6.2.1 CS, 3.6.2.3 RCFCs, 3.5.2 SI, 3.7.7 CRE HVAC, 3.7.14 Essential Cooling Water

HHSI & LHSI – TS 3.5.2 SI (Included with ECW)


LOT 20 NRC EXAM

SIMULATOR OPERATING TEST

SCENARIO #4

Revision #2

Week of 09/28/2015


SCENARIO OUTLINE

Facility: South Texas Project Scenario No.: 4 Op-Test No.: LOT 20 NRC

Examiners: Operators:

Initial Conditions: • Unit 1 is at 67% power. BOL (IC #218)Turnover: • Unit 1 is reducing power to 60% due to an offsite electrical grid disturbance.• The Unit is at step 5.15 of 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby.• The Crew is to continue the power reduction at 40%/hour.• At 65% power the crew will remove SGFPT #13 from service and idle the pump at 3300

rpm.• CW Pump #13 is removed from service for maintenance.


1 (0 min) N/A RO (R)

SRO (R) Continue to lower reactor power to 60%

2 (10 min) N/A BOP (N) Remove SGFPT #13 form service and idle at 3300 rpm

3 (20 min)

06-16-02 0

BOP (I) SRO (I, TS) Turbine Impulse Pressure, PT-0505, fails low

4 (25 min)

02-26-02 1

RO (I) SRO (I, TS) Loop 1B Cold Leg RTD T-0420B fails high

5 (35 min)

05-09-01 1.0

BOP (C) SRO (C) Gland Steam Pressure Regulator fails open

6 (40 min)

50-SA-11 0.5 ALL (M) SG 1B Steamline Break upstream of the MSIV

7 (N/A)

05-07-02 1 BOP (C) SG 1A & 1B MSIV fails to auto close (Critical Task)

8 (N/A)

A6_A1_S77_41

BOP (C) AFW Pump #12 will not stop from the control room switch (Critical Task)



SCENARIO MISCELLANEOUS INFORMATION

INSTRUCTOR NOTES:

Refer to the Instructor Guide for directions on Simulator Setup, Expected Booth Communications and Expected Booth Actions.

CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance and should be automatically recorded during the scenario. Once the scenario is complete for each crew, printout the Critical Parameters and label the printout with date, time, Crew # and scenario #.

• AFW Flow on AFW Pump #12• Extended Range NI• Wide Range Cold Leg Temperature

OPERATOR ACTIONS TABLE NOTES:

1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.

2. Actions required throughout the event are indicated as "(continuous)" in the positioncolumn.

3. Shaded cells indicate procedural entry points.


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 4 Event No.: 1 and 2

Event 1 Description: Continue to lower reactor power to 60%. Event 2 Description: Remove SGFPT #13 form service and idle at 3300 rpm.

Time Position Required Operator Actions Notes ALL COMMENCE a Reactor Power reduction

to less than ≈ 65% Rx Pwr. 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby, Step 5.15

See Page 5 and 6 for Boration and Turbine Load changes.

SRO/BOP IF Reactor Power is to remain below ≈ 65% for an extended period, THEN one SGFP may be secured as follows: • IF S/U SGFP 14(24) is NOT

operating, THEN PLACE "S/U SGFP 14(24)" handswitch in the PULL TO LOCK position.

• SECURE one SGFP per 0POP02-FW-0002, S.G.F.P. Turbine.

• WHEN SGFP testing is complete,THEN ENSURE “S/U SGFP 14”handswitch is in the AUTO position.

Step 5.16

The operator will place SU SGFP #14 handswitch in the PTL position.

The BOP will perform the applicable steps of 0POP02-FW-0002, SGFP Turbine. See Page 7.

The crew will return to this step after Shutting down SGFPT #13 to an idling condition.

Event 3 can be triggered on a signal from the NRC Examiner.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes RO RO will perform borations for the down

power per 0POP02-CV-0001, Makeup to the Reactor Coolant System

0POP02-CV-0001, Makeup to the Reactor Coolant System, Section 9.0

RO DETERMINE amount of boric acid to be added

Step 9.1

RO TURN "RC M/U CONT SYS ON" switch to "STOP".

Step 9.2

RO PLACE "RC M/U CONT" switch in "BORATE"

Step 9.3

RO ENSURE "BA BATCH/GALLONS FY-0110B" flow integrator is set for required number of gallons.

Step 9.4

RO ENSURE “BA FLOW CONT FK-0110” is set for the desired flowrate

Step 9.5

RO TURN "RC M/U CONT SYS ON" switch to "START"

Step 9.6 This starts the boration sequence.

RO VERIFY "BA XFER PUMP 1A(2A)" OR "BA XFER PUMP 1B(2B)" starts

Step 9.7

RO WHEN the required gallons of boric acid are added, THEN ENSURE makeup is stopped

Step 9.8 Boration will auto stop after set amount of boration. The RO may request to leave Reactor Makeup line up as is and just return to step 9.6 for additional borations.

RO FLUSH Makeup line with 15 to 20 gallons of RMW as follows

Step 9.9

RO IF in Mode 1, 2, 3 and 4*, THEN RETURN Makeup System to Automatic Operation per Section 8.0

Step 9.10


OPERATOR ACTIONS



Time Position Required Operator Actions Notes RO RO will make Turbine Load Changes

using Form 1 of 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby.

NOTE: There are other Plant Operating Procedures that have these same steps that the Operator can use.

0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby, Form 1

Under most circumstances the BOP would perform these steps but it is likely the BOP will be performing the steps for idling SGFPT #13.

RO ENSURE the LOAD RATE - PRCT MW/MIN” Thumbwheel is set as authorized by the Shift Manager/Unit Supervisor

Step 1.0

RO RAISE/LOWER (ADJUST) “SETPOINT” to the desired value

Step 2.0

RO DEPRESS the SETPOINT CONTROL “GO” pushbutton and MONITOR for the proper load changes

Step 3.0


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP BOP will perform the applicable steps of

0POP02-FW-0002, SGFP Turbine. 0POP02-FW-0002, SGFP Turbine, Section 17, Shutdown of a SGFP.

BOP CHECK the “STM LN DRAIN” switch in “AUTO”: • SGFP 13(23) “LV-7950/ 7951/ 7975”

Step 17.1.1

BOP ENSURE the “SPEED” controller in the “MAN” position.

Step 17.1.2

BOP IF the S/U SGFP 14(24) is NOT running, THEN ENSURE the S/U SGFP 14(24) is in “PULL TO LOCK”.

Step 17.1.3 The operator will place SU SGFP #14 handswitch in the PTL position.

BOP IF SGFP Turbine is being shutdown for maintenance outage, THEN PERFORM Mechanical Overspeed Test per Section 12.0 at the discretion of the Shift Manager.

Step 17.1.4 This step will be N/Ad.

BOP Slowly REDUCE Turbine speed to 3300 rpm by repeatedly depressing the SPEED controller "LOWER" Pushbutton.

Step 17.1.5

BOP CLOSE the “FW DISCH” Valve: • SGFP 13(23) “MOV-0061”

Step 17.1.6 Per the turnover the operator will stop here and leave SGFPT #13 idling at 3300 rpm. The US may or may not have the BOP perform this step when leaving SGFPT #13 idling.

BOP WHEN SGFP testing is complete THEN ENSURE "S/U SGFP 14(24)" handswitch is in the AUTO position.

Back to 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby. The operator will place SU SGFP #14 back in auto. See Page 4.


OPERATOR ACTIONS

Op-Test No.: 1 Scenario No.: 4 Event No.: 3

Event Description: Turbine Impulse Pressure, PT-0505, fails low

Time Position Required Operator Actions Notes RO/BOP Recognize and respond to the following

alarms at CP-005 and indication at CP-006: • TREF/AUCT TAVG DEV• TURB IMP PRESS ROD

WTHDRWL BLKD• PI-505 indicating off scale LOW

Listing of symptoms is not inclusive. If the crew placed control rods in auto prior to this malfunction being entered then the control rods will be stepping in and will need to be placed in manual.

SRO/BOP Determines Impulse Pressure channel PT-0505 as failed low.

SRO (continuous)

Implements 0POP04-TM-0004, Failure of Turbine Impulse Pressure Transmitter (PT-505/506).

BOP VERIFY Rod Control - IN MANUAL. 0POP04-TM-0004, Failure of Turbine Impulse Pressure Transmitter (PT-505/506) Step 1.0 Control Rods may already be in manual.

BOP VERIFY RCS Tavg – WITHIN 1.5ºF OF PROGRAM RCS TAVG PER Addendum 1, Percent Power vs Program Tavg

Step 2.0 Unless Control Rods were in auto Tavg will be within 1.5ºF of Tref.


OPERATOR ACTIONS



Time Position Applicant’s Actions or Behavior Notes BOP CHECK Steam Dump Control -

PRESSURE CONTROL MODE (RNO) • TRANSFER steam dump control to

pressure control mode as follows:• ADJUST Steam Dump “HDR PRESS

CONT” PK-0557 setpoint for no loadsteam pressure of 1185 psig(approximately 8.46 controller setpoint)

• PLACE “INTLK SEL” Switch toOFF/RESET for the following:• Train “A” OR Train “B”

• PLACE Steam Dump “MODE SEL”switch in STEAM PRESS position.

• ENSURE steam dump “DEMAND” UI-0555 is 0% using Steam Dump “HDRPRESS CONT” PK-0557.

• ENSURE "INTLK SEL" Switch to ONfor both the following:• Train “A” and Train “B”

• ENSURE Steam Dump “HDR PRESSCONT” PK-0557 in AUTO.

• ENSURE all steam dump valves closed.

Step 3.0

BOP SELECT The Failed Channel To “DEFEAT” On The “IMP SEL” Switch

Step 4.0

BOP CHECK “TURB IMP PRESS WTHDRWL BLKD” Annunciator - EXTINGUISHED (Lampbox 5M02, Window E-5)

Step 5.0

BOP VERIFY Permissive P-13 Annunciator Window Is In The Correct State For Current Plant Conditions Within One Hour Per Technical Specifications 3.3.1. • Turbine Load GREATER THAN

10% Permissive lampbox for P-13should be dark (not illuminated).

• Turbine Load LESS THAN 10%Permissive lampbox for P-13 should beilluminated.

Step 6.0 TS 3.3.1.19.f – Action 8 This procedure step will satisfy the TS requirements.

See next page for full TS Action.


OPERATOR ACTIONS



Time Position Applicant’s Actions or Behavior Notes BOP CHECK Reactor Power – LESS THAN

10% Step 7.0

BOP CHECK PT-505, Turbine First Stage Pressure (Impulse Pressure) - FAILED

Step 8.0

BOP INITIATE A Condition Report To Repair The Inoperable Channel

Step 9.0

SRO GO TO The Appropriate Plant Procedure As Determined By The Shift Manager/Unit Supervisor

Step 10.0

Event 4 can be triggered after SRO has checked TS.

TS 3.3.1.19.f Action 8

With less than the Minimum Number of Channels OPERABLE, within 1 hour determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.


OPERATOR ACTIONS


Event Description: Loop 1B Cold Leg RTD T-0420B fails high

Time Position Required Operator Actions Notes

RO Acknowledges and announces the following annunciators from 05M2: OPDT RX PRETRIP (A-6) T AVG/AUCT T AVG DEV (C-6) DT/AUCT DT DEV (D-6)

RO uses annunciator response procedures.

SRO/RO Determines LOOP B Cold Leg RTD T-420B failed high.

SRO (continuous)

Directs actions of 0POP04-RP-0004, Failure of RCS Loop RTD Protection Channel.

RO ENSURE "ROD BANK SEL" Switch In MANUAL

0POP04-RP-0004, Failure of RCS Loop RTD Protection Channel, Step 1.0

SRO/RO CHECK The Following Indications - NORMAL • RCS loop temperature indicators (Tavg,

Th, Tc, and ΔT) {CP005}• QDPS DETAIL DATA Page 2 for RCS

Loop Th• Plant Computer(RNO) IF any RCS loop RTD channel is NOT operable, THEN PERFORM the following: {CP005} • SELECT The Failed Loop On "BYP

SEL ∆T" Switch.• SELECT The Failed Loop On "BYP

SEL T AVG" Switch.

Step 2.0

RO CHECK Tavg - WITHIN 1.5°F OF Tref (REFER TO Addendum 1)

Step 3.0 Tavg will probably be within 1.5°F of Tref.

RO CHECK Pressurizer Level - • AT PRESSURIZER PROGRAM

LEVELOR

• TRENDING TO PRESSURIZERPROGRAM LEVEL

Step 4.0


OPERATOR ACTIONS


Event Description: Loop 1B Cold Leg RTD T-0420B fails high

Time Position Required Operator Actions Notes SRO/RO Establish Automatic Rod Control:

• DETERMINE if it is desired to placeRod Control System in Automatic

• CHECK Tavg - WITHIN 0.5°F OFTREF

• PLACE "ROD BANK SEL" Switch InAUTO {CP005}

• VERIFY Rod Control System -PROPER RESPONSE IN AUTOMATIC

Step 5.0 The Unit Supervisor will NOT place Control Rods in Auto at this time due to PT-0505 failure.

RO CHECK "ΔT AND ΔT SETPTS TR-0412" Recorder - SELECTED TO OPERABLE CHANNEL (CP-018) • SELECT an operable channel on "ΔT

AND ΔT SETPTS TR-0412" Recorder.

Step 6.0 Will have to select an operable channel for the recorder.

SRO TAKE Appropriate Actions Per Technical Specifications. TS 3.3.1.8 & 9 OT & OPDT Action 6 TS 3.3.2.5.f LOW Tavg P4 Action 20 Most Limiting Condition: Place the failed channel in the tripped condition within 72 hours.

Step 7.0 SRO will check TS.

Event 6 can be triggered after the SRO has checked TS.

SRO NOTIFY I&C To Place The Affected Channel In Trip Or Bypass. REFER TO Addendum 2, Procedure List For The Appropriate Procedure

Step 8.0

SRO INITIATE A Condition Report To Repair Failed Component

Step 9.0

TS 3.3.1.8 & 9 Action 6 and TS 3.3.2.5.f Action 20 NOTE: Action 6 and Action 20 are the same.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: a. For Functional Units with installed bypass test capability, the inoperable channel may be placed inbypass, and must be placed in the tripped condition within 72 hours.

Note: A channel may be bypassed for up to 12 hours for surveillance testing per Specification 4.3.1.1, provided no more than one channel is in bypass at any time.


OPERATOR ACTIONS


Event Description: Gland Steam Pressure Regulator fails open.

Time Position Required Operator Actions Notes RO/BOP BOP - Acknowledges Plant Computer

Annunciator on 8M03 – A8. Computer point P6100, Gland Steam Header Pressure. RO – Reports a slowly lowering Tavg and a slow rise in Reactor Power.

There are no other annunciators associated with this malfunction. Control Board Indicator for GS pressure, PI-6151, will be indicating high.

RO/BOP Determines Gland Steam Header Pressure Control Valve, GS-PV-6150, has failed open.

SRO (continuous)

Directs actions of 0POP04-MS-0001, Excessive Steam Demand.

This is a large enough steam leak through the safety lifting on the GS header to warrant entry into the procedure.

RO CHECK Reactor Power – LESS THAN OR EQUAL TO 100%

0POP04-MS-0001, Excessive Steam Demand, Step 1.0

BOP IDENTIFY And ISOLATE Steam Leak: DISPATCH Operator(s) To PERFORM The Following: • Walk Down the Main Steam System

In IVC And TGB as directed by ShiftManager/Unit Supervisor – NOLEAKAGE

(RNO) • IF steam leakage can be isolated in

current plant configuration, THENISOLATE components that will stopthe abnormal steam leakage.

Per the CIP: IF the location of the steam leakage is identified, THEN Step 2.0 Substeps may be performed out of order to isolate the leakage provided that the remainder of the Substeps are completed to identify any additional leakage that may exist.

SRO (continuous)

Directs actions of 0POP02-GS-0001, Turbine Gland Seal Steam System, Section 14, Bypassing Gland Seal Steam Regulator Valve, PV-6150.

The Crew may not use the POP02 Procedure to bypass the failed regulator because 0POP04-MS-0001 simply states isolate the steam leak if possible.

BOP Slowly CLOSE “1(2)-GS-MOV-0014, MAIN STEAM TO GLAND STEAM SUPPLY PV-6150 INLET MOV OPERATOR” using the LOCAL HANDWHEEL until Gland Steam Header Pressure lowers slightly.

0POP02-GS-0001, Turbine Gland Seal Steam System, Step 14.1.1 Crew coordinates with the Plant Operator.


OPERATOR ACTIONS


Event Description: Gland Steam Pressure Regulator fails open.

Time Position Required Operator Actions Notes BOP Slowly JOG OPEN Main Steam To

Gland Steam Supply PV-6150 Bypass MOV-0016 until Gland Steam Header Pressure rises slightly using one of the following methods: • “STM SEAL BYPASS”• “1(2)-GS-MOV-0016 MAIN STEAM

GLAND STEAM SUPPLY BYPASS LOCAL HAND SWITCH”

Step 14.1.2

BOP CONTINUE throttling “1(2)-GS-MOV-0014, MAIN STEAM TO GLAND STEAM SUPPLY PV-6150 INLET MOV OPERATOR” closed while throttling 1(2)-GS-MOV-0016 to maintain 120 to 140 psig until “1(2)-GS-MOV-0014” is closed.

Step 14.1.3

BOP CLOSE “1(2)-GS-0015 MAIN STEAM TO GLAND STEAM SUPPLY PV-6150 OUTLET ISOLATION VALVE”.

Step 14.1.4

BOP MAINTAIN between 120 and 140 psig as indicated on “PI-6151 STM HDR PRESS” by throttling “1(2)-GS-MOV-0016 STM SEAL BYPASS” valve.

Step 14.1.5



OPERATOR ACTIONS


Event 6 Description: SG 1B Steamline Break upstream of the MSIV. Event 7 Description: SG 1A & 1B MSIV fails to auto close. (Critical Task) Event 8 Description: AFW Pump #12 will not stop from the control room switch. (Critical Task)

Time Position Required Operator Actions Notes ALL A large steam line break in containment

will cause a Safety Injection and Main Steam Line Isolation except the Main Steam Lines will fail to Auto Actuate causing the crew to have to Manually initiate the actuation.

Event 7 & 8 are integral to the event.

SRO (continuous)

Enters 0POP05-EO-EO00, Reactor Trip or Safety Injection.

BOP/RO Completes immediate actions of EO00. Reactor Trip/SI: • Reactor Tripped.• Turbine Tripped.• AC ESF Busses energized.• SI is actuated.

0POP05-EO-EO00, Reactor Trip or Safety Injection Steps 1-4. RO will announce status of immediate action steps as he/she performs them. BOP Operator will monitor the plant and make an announcement of the Reactor trip.

SRO Directs/ensures the immediate actions of 0POP05-EO-EO00, Reactor Trip or Safety Injection have been completed by performing a procedure read through of them.

Before beginning the verification of immediate actions, the US may direct the BOP operator to throttle AFW flow to limit RCS cooldown.


(Step 5) See Actions on Page 19 - 24


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP (C)

Per the CIP of 0POP05-EO-EO00, Reactor Trip or Safety Injection:

IF a faulted SG(s) is NOT required to maintain at least two SGs available for RCS cooldown, THEN the US or SM may direct actions be taken to isolate the faulted SG(s).

Also see Page 26

Event 8

Early isolation of a Faulted SG includes placing the associated AFW Pump handswitch in PTL. However, AFW Pump #12 will not stop.

The crew will have to reset SI & LO-LO SG AFW Actuation and then close SG 1B AFW OCIV or reset SG 1B Reg Valve and then close the Reg Valve to satisfy the critical task.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes RO MONITOR If Containment Spray Is

Required: • Containment pressure ‑ GREATER

THAN 9.5 PSIG (QDPS)(RNO) • PERFORM the following:

• CHECK Containment pressure -HAS EXCEEDED 9.5 PSIG (CP - 18) • "PRESS PR‑ 0934"

OR • "EXTD RNG PRESS PR‑ 9759"

• IF containment pressure HASEXCEEDED 9.5 PSIG, THEN GOTO Step 6.b.

• IF containment pressure HASREMAINED LESS THAN 9.5PSIG, THEN GO TO Step 7.



6 and 13 gpm


RO MONITOR RCS Temperatures ‑• WITH ANY RCP RUNNING, RCS

TAVG STABLE AT OR TRENDINGTO 567°F


RCS TCOLD STABLE AT ORTRENDING TO 567°F

(Step 8) If AFW has been properly throttled from the original Reactor Trip then RCS temperature should be trending to 567°F.

RO CHECK Pressurizer Status: • PORVs ‑ CLOSED• Normal pressurizer spray valves -

CLOSED• Auxiliary spray valve - CLOSED• Excess letdown isolation valves -

CLOSED

(Step 9)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes RO MONITOR If RCPs Should Be Stopped:

• HHSI pump - AT LEAST ONERUNNING

• RCS pressure - LESS THAN 1430PSIG

(RNO) • GO TO Step 11

(Step 10) Reactor Coolant Pump Trip Criteria will probably NOT be met if AFW has been properly throttled.

RO VERIFY The Following Containment Isolation Valves – CLOSED • Seal return isolation valves• Containment atmosphere radiation


(Step 11)

RO CHECK If SG Secondary Pressure Boundary Intact: • CHECK pressures in all SGs –

• CONTROLLED OR RISING• GREATER THAN

CONTAINMENT PRESSURE(RNO) • IF any faulted SG is NOT isolated,

AND is NOT needed for RCScooldown, THEN PERFORM thefollowing:• GO TO 0POP05‑ EO‑ EO20,

FAULTED STEAMGENERATOR ISOLATION, Step1

• MONITOR Critical SafetyFunctions

• WHEN Addendum 5 of thisprocedure is complete, THENFunctional Restoration Proceduresmay be IMPLEMENTED

(Step 12)

SG 1B is faulted

See Page 25


Will not transition to a Functional Recovery Procedure until Addendum 5 is complete.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP VERIFY FW isolation:

• SGFPTs – TRIPPED• SU SGFP – TRIPPED• VERIFY the following valves –

CLOSED • FWIVs• FWIBs• FW preheater bypass valves• FW regulating valves• Low power FW regulating valves• SG blowdown isolation valves• SG sample isolation valves

0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation. (Step 1) This addendum is performed in parallel with Steps 5 to 14 of 0POP05-EO-EO00, Reactor Trip or Safety Injection.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes SRO/BOP

(C) CHECK if main steamline should be isolated: • CHECK for any of the following

conditions:• Containment pressure – GREATER

THAN OR EQUAL TO 3 PSIGOR

• SG pressure (without low steamlinepressure SI blocked) - LESS THANOR EQUAL TO 735 PSIG


pressure SI blocked) - LOWERINGAT A RATE GREATER THANOR EQUAL TO 100 PSI/SEC,BYOBSERVANCE OF THESTEAMLINE PRESSURE RATEBISTABLES

• VERIFY main steamline isolation• MSIVs – CLOSED• MSIBs – CLOSED(RNO) • Manually CLOSE valves• IF any MSIV and MSIB can NOT

be closed, THEN DISPATCHoperator to close MSIV and MSIBper Addendum 6, FAILING AIRTO MSIVs AND MSIBs

(Step 2)

Event 7

Crew has to manually initiate Main Steam Line Isolation and upon doing so SG 1A & 1B MSIV fail to auto close.

Operator calls Plant Operator to isolate air to SG 1A MSIV.

Operator uses either the Class Solenoid Handswitches or the Normal Handswitch for SG 1B MSIV.

BOP VERIFY AFW system status: • Motor-driven pump – RUNNING• Turbine-driven pump - RUNNING

(Step 3)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP VERIFY AFW valve alignment -

PROPER EMERGENCY ALIGNMENT (Step 4)


(Step 5)

BOP VERIFY containment isolation phase A: • Phase A – ACTUATED• Phase A valves - CLOSED, REFER

TO ADDENDUM 1, PHASE AISOLATION VERIFICATION

(Step 6)

BOP VERIFY ECW status: • ECW pumps – RUNNING• ECW pump discharge isolation valves

- OPEN

(Step 7)


• RCFCs – RUNNING• Cooling water - TRANSFERRED TO

CCW

(Step 9)

BOP VERIFY SI pump status: • HHSI pumps – RUNNING• LHSI pumps – RUNNING

(Step 10)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP VERIFY SI valve alignment – PROPER

EMERGENCY ALIGNMENT (Step 11)


PSIG • HHSI pump flow – INDICATED• RCS pressure - LESS THAN 415

PSIG(RNO) • GO TO Step 13 of this Addendum.




– STOPPED• Supplemental purge supply and

exhaust fans – STOPPED• Purge Dampers - CLOSED

(Step 13)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP VERIFY ventilation actuation:

• Control room HVAC – OPERATINGIN EMERGENCY RECIRC

• EAB HVAC - OPERATING INEMERGENCY RECIRC

• FHB HVAC - OPERATING INEMERGENCY MODE

• FHB Exhaust Fans - ONLY TWOTRAINS OPERATING• Exhaust booster fans• Main exhaust fans


• IF three trains FHB exhaust fansrunning, THEN PLACE one trainFHB exhaust fans in PULL TOLOCK.


PERFORMING the following:• PLACE the outlet damper

Controller in manual• Manually close the outlet damper• VERIFY proper operation of filter

train in service• Essential chilled water pumps –

RUNNING• Essential chillers – RUNNING• ECCS pump room fan coolers –

RUNNING• AFW pump cubicle fans – RUNNING• FHB truck bay doors - CLOSED

(Step 14)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP NOTIFY Unit Supervisor that Addendum

5 is COMPLETE (Step 15)


(Step 16)



OPERATOR ACTIONS



Time Position Required Operator Actions Notes SRO

(continuous) Informs crew of transition to 0POP05-EO-EO20, Faulted SG Isolation, and to monitor Critical Safety Functions

BOP (C)

Checks MSIV’s and MSIB’s closed. (RNO) PERFORM the following: • Manually CLOSE MSIV(s) and

MSIB(s) • IF MSIV(s) and MSIB(s) can NOT

be closed, THEN DISPATCH operator to close MSIV(s) and MSIB(s) per Addendum 1

• IF MSIV(s) OR MSIB(s) still remainsopen, THEN ISOLATE the main steam header per ADDENDUM 3, MAIN STEAM HEADER ISOLATION

0POP05-EO-EO20, Faulted SG Isolation, Step 1

This step will probably already be performed. See Page 20

BOP CHECK If Any SG Secondary Pressure Boundary Intact: • CHECK pressures in all SGs – ANY

SG PRESSURE CONTROLLED OR RISING

Step 2 SG’s ‘A’, ‘C’ and ‘D’ pressures are ‘controlled’. SG ‘B’ pressure is NOT controlled.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes SRO/BOP IDENTIFY Faulted SG(s):

• CHECK pressure in all SGs –• ANY SG PRESSURLOWERING

IN AN UNCONTROLLEDMANNER

OR • ANY SG COMPLETELY

DEPRESSURIZED

Step 3

SG 1B is Faulted

SRO/BOP (C)*

* denotescritical items

Isolates the faulted SG (1B) • Verifies all FWIV’s closed.*• Verifies all FWIB’s closed.*• Verifies all FW Preheater bypass

valves closed. *• Verifies all FW Regulating and Low

Power FW Regulating Valvesclosed.*

• Isolates AFW flow to ‘B’ SG *• Resets SI• Resets ESF load sequencers• Resets SG LO-LO level AFW

actuations• Checks SG 1D intact• Closes ‘B’ SG AFW OCIV*

• Verifies SG 'B' PORV closed *• Verifies SG ‘B’ Blowdown and

sample isolation valves closed *

Step 4

CT-Verifies the faulted S/G is isolated, the crew will have to reset SI, load sequencers, SG LO-LO actuation in order to be able to close the AFW OCIV May have already been completed. See page 12 of 18.

SG 1D is intact.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP/SRO Check Secondary Radiation:

• Resets SI• Resets SG LO-LO level AFW

actuations• Resets SG Blowdown and Sampling

Isolations• Notifies Chemistry to sample all SG’s

hourly for activity.• Checks the following Rad Monitors:

• Main Steamline• SG Blowdown• CARS Pump

• WHEN SG sample results arereceived, THEN VERIFY SG sampleactivity - NORMAL

Step 5

The first 3 resets have already been done so the operator will just check that they are still reset.

CARS = Condenser Air Removal System.

ALL Check if SI flow should be terminated • RCS subcooling - >35°F [45°F]• Secondary heat sink – NR level in one

SG > 14%[34%] OR total AFW Flow> 576 gpm.

• RCS pressure > 1745 psig and stableor rising

• Pressurizer level > 8%

Step 6

If conditions are met, a transition to 0POP05-EO-ES11, SI Termination, will be made. Conditions will likely NOT be met for transition at this time. If not met (expected), the crew will transition to 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.

SRO Announces transition from 0POP05-EO-EO20 (to ES11 or E010, as appropriate).

Terminate the scenario.



POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/ UNSAT

SRO/BOP MANUALLY CLOSE THE MSIV FOR SG 1A & 1B DUE TO FAILING TO AUTO CLOSE.

Manually actuate main steamline isolation or close MSIVs before a severe (orange-path) challenge develops to either the subcriticality or the integrity CSF or before transition to EC21, whichever happens first.

SRO/BOP MANUALLY CLOSE THE AFW REG VALVE AND/OR THE AFW OCIV FOR SG 1B DUE TO AFW PUMP #12 FAILING TO STOP FROM THE CONTROL ROOM.

Isolate a Steam Generator before transitioning out of 0POP05-EO-EO20, Faulted Steam Generator Isolation.



• Reactor Power is currently at 67%. BOL

• The previous crew was reducing power to 60% due to an offsite electrical grid disturbance. Theoncoming Crew is to continue the down power at step 5.15 of 0POP03-ZG-0006, PlantShutdown from 100% to Hot Standby, using a ramp rate of 40%/hour.

• At 65% power the crew will remove SGFPT #13 from service and idle the pump at 3300 rpm.Testing of the Pump will NOT be performed.

• Circulating Water Pump #13 is OOS for maintenance. Expected return to service is 12 hours.








LCO Actions:

NONE


LOT 20 NRC EXAM

SIMULATOR OPERATING TEST

SCENARIO #5

Revision #2 Week

of 09/28/2015


SCENARIO OUTLINE

Facility: South Texas Project Scenario No.: 5 Op-Test No.: LOT 20 NRC

Examiners: _____________________ Operators: _____________________ _____________________ _____________________ _____________________ _____________________

Initial Conditions: • Unit 1 is at 78% power. BOL (IC #219)Turnover: • The crew will continue to raise power to 100%• CD Pump #13 and SUSGFP #14 are removed from service for maintenance.• A line of thunderstorms just passed through Markham and are tracking south towards the

STP site.


1 (0 min) N/A ALL (R) Power increase.

2 (10 min) Multiple BOP (C)

SRO (C) CW Pump #14 Traveling Screen high differential level.

3 (25 min)

02-20-01 0

RO (I) SRO (I, TS)

PZR level channel LT-0465 fails low

4 (35 min)

05-11-02 0

BOP (I) SRO (I)

SG 1B controlling steam flow channel FT-0522 fails low

5 (45 min)

EE_E1B1TF Fault

1

ALL (C)

SRO (TS) Loss of 480 V LC E1B1

6 (60 min)

10-06-01 1 ALL (M) Main Generator Output Breaker trips open and inadvertent FWI.

7 (NA)

06-02-01 1 BOP (C) Main Turbine fails to auto trip on reactor trip. (Critical Task)

8 (NA) Multiple ALL (C) Loss of Heat Sink and entry into FRH1 (Critical Task)



SCENARIO MISCELLANEOUS INFORMATION

INSTRUCTOR NOTES:

Refer to the Instructor Guide for directions on Simulator Setup, Expected Booth Communications and Expected Booth Actions.

CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance and should be automatically recorded during the scenario. Once the scenario is complete for each crew, printout the Critical Parameters and label the printout with date, time, Crew # and scenario #.

• Main Turbine Throttle Valve Position• RCS Wide Range Cold Leg Temperature• Extended Range NI• CET MAX QUAD T/C AVG

OPERATOR ACTIONS TABLE NOTES:

1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.

2. Actions required throughout the event are indicated as "(continuous)" in the positioncolumn.

3. Shaded cells indicate procedural entry points.


OPERATOR ACTIONS


Event Description: Raise Reactor Power.

Time Position Required Operator Actions Notes ALL COMMENCE raising Reactor Power and

Main Turbine to between 88% to 90% Rx Pwr.

0POP03-ZG-0005, Plant Startup to 100%, Step 7.51

SRO Provide oversight of reactivity additions. RO Start a dilution per 0POP02-CV-0001,

Makeup to the Reactor Coolant System. NOTE: Operator can perform a Normal Dilution, Section 10, or an Alternate Dilution, Section 11. The steps between the two are similar. Section 10 is given.

RO DETERMINE amount of dilution water to be added.

0POP02-CV-0001, Makeup to the Reactor Coolant System, Step 10.1

RO TURN "RC M/U CONT SYS ON" switch to "STOP"

Step 10.2

RO TURN "RC M/U CONT" to "DILUTE" Step 10.3 RO ENSURE "TOT M/U BATCH

GALLONS FY-0111B" flow integrator is set for required gallons of dilution water.

Step 10.4

RO ENSURE “RMW FLOW CONT FK-0111” is set for desired flowrate.

Step 10.5 Normal dilution flow rate is set for 100 gpm (3.3 pot setting)

RO TURN "RC M/U CONT SYS ON" switch to "START".

Step 10.6 This starts the dilution sequence.

RO VERIFY "RMW PUMP 1A(2A)" OR "RMW PUMP 1B(2B)" starts.

Step 10.7

RO WHEN the required gallons of dilution water are added, THEN ENSURE makeup is stopped.

Step 10.8 Dilution will auto stop after set amount of water added. The RO may request to leave Reactor Makeup line up as is and just return to step 10.6 for additional dilutions.

RO IF in Mode 1, 2, 3 and 4*, THEN RETURN Makeup System to Automatic Operation per Section 8.0

Step 10.9


OPERATOR ACTIONS


Event Description: Raise Reactor Power.

Time Position Required Operator Actions Notes BOP RO will make Turbine Load Changes

using Form 1 of 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby.

NOTE: There are other Plant Operating Procedures that have these same steps that the Operator can use.

0POP03-ZG-0005, Plant Startup to 100%, Form 1

BOP ENSURE the LOAD RATE - PRCT MW/MIN” Thumbwheel is set as authorized by the Shift Manager/Unit Supervisor

Step 1.0

BOP RAISE/LOWER (ADJUST) “SETPOINT” to the desired value

Step 2.0

BOP DEPRESS the SETPOINT CONTROL “GO” pushbutton and MONITOR for the proper load changes

Step 3.0



OPERATOR ACTIONS


Event Description: CW Pump #14 Traveling Screen high differential level.

Time Position Required Operator Actions Notes RO/BOP BOP - Acknowledges Plant Computer

Annunciator on 8M03 – A8. Computer point P6100, Circ Water Screen Wash Pump RUN.

Will dispatch a Plant Operator to investigate.

SRO/BOP Determines that CW Pump #14 Traveling Screens did not start in response to a high differential level across the screens.

Determination of traveling screen issue may not be made until after Plant Operator report of CW status.

SRO (continuous)

Implements 0POP04-CW-0001, Loss of Circulating Water Flow.

SRO CHECK This Procedure Has Been Entered Due To Circulating Water Traveling Screen High Differential Level

0POP04-CW-0001, Loss of Circulating Water Flow, Step 1.0

SRO GO TO Addendum 5, Circulating Water Traveling Screen High Differential Level Response.

Step 2.0

BOP CHECK Circulating Water Traveling Screen Differential Level Rising.

ADD. 5 Step 1.0 Report from Plant Operator will be that CW Pump #14 Traveling Screen Differential Level is rising and the screens are not rotating.

BOP ENSURE Operator Is At CWIS With Direct Communication With The Control Room.

ADD. 5 Step 2.0

BOP CHECK Affected Traveling Screen And Screen Wash In Service. (RNO) IF affected Traveling Screen and Screen Wash is NOT in service, THEN PERFORM steps to restore affected Traveling Screen and Screen Wash.

ADD. 5 Step 3.0

CW Pump #14 Traveling Screen Spray Valve is Failed Closed and will not open.


OPERATOR ACTIONS


Event Description: CW Pump #14 Traveling Screen high differential level.

Time Position Applicant’s Actions or Behavior Notes BOP EVALUATE Swapping Circulating Water

Pumps To Use A Bay With Lower Screen Differential Level.

ADD. 5 Step 4.0 All CW Pumps are running.

BOP MONITOR For Entry Condition Into 0POP04-CR-0001, Loss of Condenser Vacuum.

ADD. 5 Step 5.0

Condenser Vacuum will be stable.

BOP CHECK Circulating Water Intake Free From Blockage And Debris. (RNO) • INITIATE actions to remove

blockage/debris. • IF Blockage And Debris can NOT be

removed, THEN secure affected CWP(s).

ADD. 5 Step 6.0

Crew will secure CW Pump #14.



OPERATOR ACTIONS


Event Description: PZR level channel LT-0465 fails low

Time Position Applicant’s Actions or Behavior Notes

RO Acknowledges and announces the following annunciators on 04M8: LETDN HX OUTL FLOW HI/LO (D-4) PRZR LEVEL DEV LO (D-6)

Annunciators listed are not inclusive.

SRO/RO Determines PZR Level Channel LT-0465 failed low. Performs immediate actions of 0POP04-RP-0002: • PLACES “CHG FLOW CONT FK-

0205” in Manual and controls PZR Level on Program.

Failed Channel is RC-LI-0465.

Immediate Action – RO Places CV-FV-0205 in manual and controls PZR Level on Program.

SRO (continuous)

Directs actions of 0POP04-RP-0002, Loss of Automatic Pressurizer Level Control.

RO PLACE "CHG FLOW CONT FK-0205" Controller In MANUAL {CP004}

0POP04-RP-0002, Loss of Automatic Pressurizer Level Control, Step 1.0 Immediate Action

RO ADJUST "CHG FLOW CONT FK-0205" To Maintain Pressurizer Program Level

Step 2.0

Immediate Action


OPERATOR ACTIONS



Time Position Required Operator Actions Notes RO VERIFY Letdown – IN SERVICE

(RNO) PERFORM the following: • ENSURE “LETDN ORIF HDR ISOL

FV-0011” is closed.• ENSURE “CHG FLOW CONT FK-

0205” in “MAN” and CLOSED.• OPEN Centrifugal Charging Pump

miniflow valve for operating pump:• CCP 1A(2A) “RECIRC FCV-

0201”• CCP 1B(2B) “RECIRC FCV-

0202”• MAINTAIN RCP seal injection

between• 6 and 13 gpm using “FLOW CONT• HCV-0218.”• ENSURE all letdown orifice isolation• valves are closed:

• “120-150 GPM ORIFICE ISOLVLV 1(2)-CV-FV-0012”

• “85-100 GPM ORIFICE ISOLVLV 1(2)-CV-FV-0013”

• “25-30 GPM ORIFICE ISOLVLV 1(2)-CV-MOV-0014”

• ENSURE “LETDN ISOL LCV-0465” is closed.

• ENSURE “LETDN ISOL LCV-0468” is closed.

• GO TO Step 4.0.

Step 3.0

Letdown will have isolated due to the failure of LT-0465.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes RO CHECK All Pressurizer Level Channels -

OPERABLE {CP004} (RNO) PERFORM the following: • POSITION Pressurizer level control

selector switch to remove failedchannel from service: {CP004}Failed Channel Select RC-LT-0465 L467/466 RC-LT-0466 L465/467 RC-LT-0467 L465/466

• POSITION Pressurizer level recorderselector switch to an operable channel.{CP005}

• PLACE Pressurizer “HTR CONT GRP1C(2C)” to ON. {CP004}

• IF normal letdown has isolated, THENPLACE excess letdown in service asnecessary per Addendum 3 to maintainPressurizer level on PressurizerProgram Level.

• NOTIFY I&C to bypass or trip thePressurizer low level for the failedchannel, using plant surveillanceprocedure listed in Addendum 4.

Step 4.0

Selects L467/466

Crew will begin placing Excess Letdown in service. See Page 11

Placing LT-0465 in TRIP or BYPASS will allow normal letdown to be placed back in service. However, it would realistically take I/C a couple of hours to do this.

RO CHECK All Tavg Channels –OPERABLE {CP005}

Step 5.0

RO CHECK Tavg – WITHIN 1.5°F OF Tref Step 6.0 RO CHECK Pressurizer Level - GREATER

THAN 17% Step 7.0

RO CHECK Normal Letdown – IN SERVICE (RNO) • PLACE normal letdown in service per

Addendum 5, Placing NormalLetdown In Service, to maintainPressurizer level.

• DO NOT CONTINUE with procedureuntil Addendum 5, Placing NormalLetdown In Service, is complete.

Step 8.0


NOTE: The Crew will stop at this point and wait on I/C. TSs may have to be looked at after the scenario. See Page 12 for TSs.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes RO CHECK CCW In Service To The Excess

Letdown Heat Exchanger 0POP04-RP-0002, Loss of Automatic Pressurizer Level Control, Addendum 3, Placing Excess Letdown in Service, Step 1.0

RO PLACE Excess Letdown “DIVERT FV-3123” In The “RCDT” Position

ADD. 3 Step 2.0

RO CHECK “EXCESS/NORMAL LETDN CROSS CONNECTION N1(2)CV-HS-0469” In The “CLOSE” Position

ADD. 3 Step 3.0 Will dispatch a Plant Operator

RO OPEN Excess Letdown Heat Exchanger Inlet Isolation Valve “LOOP D ISOL MOV-0083”

ADD. 3 Step 4.0

RO OPEN Excess Letdown Heat Exchanger Inlet Isolation Valve “ISOL MOV-0082”

ADD. 3 Step 5.0

RO MAINTAIN Both Of The Following Parameters While Flushing Excess Letdown Heat Exchanger: • Excess Letdown “HX OUTL TEMP

TI-0229” – LESS THAN 175°F• Excess Letdown “HX OUTL PRESS

PI-0228” – LESS THAN 145 psig

ADD. 3 Step 6.0

RO Slowly OPEN Excess Letdown “TEMP CONT HCV-0227” To Avoid Thermal Transients

ADD. 3 Step 7.0

RO ADJUST Excess Letdown And Seal Injection Flows To Maintain • Pressurizer level• RCDT level (8 – 92%)• RCDT pressure (LESS THAN 6 psig)

ADD. 3 Step 8.0

RO FLUSH Excess Letdown To The RCDT For At Least Six (6) Minutes

ADD. 3 Step 9.0

RO PERFORM One Of The Following: • PLACE excess letdown “DIVERT

FV-3123” in the “VCT” positionOR

• ENSURE excess letdown “DIVERTFV-3123” remains in the “RCDT”position

ADD. 3 Step 10.0 Will position FV-3123 to the VCT position.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes SRO REFER TO Addendum 7 For Applicable

Technical Specifications. TS 3.3.1.12 Action 6 Place the failed channel in the tripped condition within 72 hours.

SRO will check TS.

TS 3.3.3.5 and 3.3.3.6 are referenced but do NOT apply with only one Channel of PZR Water Level Inoperable.

TS 3.3.1.12 Action 6 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: a. For Functional Units with installed bypass test capability, the inoperable channel may be placedin bypass, and must be placed in the tripped condition within 72 hours. Note: A channel may be bypassed for up to 12 hours for surveillance testing per Specification 4.3.1.1, provided no more than one channel is in bypass at any time.


OPERATOR ACTIONS


Event Description: SG 1B controlling steam flow channel FT-0522 fails low.


BOP Acknowledges and announces the following annunciators on 06M3: SG 1B STM/FW FLOW MSMTCH (E-7)

This list of annunciators is not all inclusive.

SRO/BOP Determines SG 1B Controlling Steam Flow Channel FT-0522 failed low. Performs immediate actions of 0POP04-FW-0001: • PLACE any SG Feedwater Regulating

Valve(s) not properly responding in MANUAL AND ADJUST as necessary to restore affected SG NR level(s) to between 68% and 74%.

Failed Channel is MS-FT-0522. Immediate Action – BOP takes Manual control of SG 1B MFRV.

SRO (continuous)

Directs actions of 0POP04-FW-0001, Loss of Steam Generator Level Control.

BOP CHECK SG Feedwater Regulating Valve(s) - RESPONDING IN AUTOMATIC

0POP04-FW-0001, Loss of Steam Generator Level Control, Step 1.0

BOP CHECK SGFP Speed Controllers - RESPONDING IN AUTOMATIC

Step 2.0

BOP CHECK Main Feedwater Regulating Valves: • CHECK Main Feedwater Regulating

Valve(s) - IN SERVICE • CHECK Main Feedwater Regulating

Valve(s) - ANY IN MANUAL• CHECK Affected Main Feedwater

Regulating Valve(s) - RESPONDINGIN MANUAL

Step 3.0

BOP CHECK Low Power Feedwater Regulating Valves:

Step 4.0 LPFRVs are not in service.

BOP CHECK SGFP Master Speed Controller - IN MANUAL

Step 5.0 Will be in Auto and GO TO Step 7.0

BOP CHECK Individual SGFP Speed Controllers - ANY IN MANUAL

Step 7.0 Will be in Auto and GO TO Step 9.0


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP MONITOR Feedwater/Steam Header

DP: • GREATER THAN OR EQUAL TO DP

REQUIRED BY Addendum 1OR

• SGFP Master Speed Controller At 100%Demand In Auto

Step 9.0

BOP RESTORE Affected SG NR Level(s) To Between 68% And 74%

Step 10.0

BOP MONITOR SG NR Levels - GREATER THAN 20%

Step 11.0

BOP MONITOR SG NR Levels - LESS THAN 87.5%

Step 12.0

BOP CHECK SG NR Level Indicators - ALL OPERABLE

Step 13.0

BOP CHECK Feedwater Flow Transmitters - ALL OPERABLE

Step 14.0

BOP CHECK Steam Flow Transmitters - ALL OPERABLE (RNO) SELECT the unaffected steam flow channel for affected SG(s) level control.

Step 15.0

Steam Flow FT-0522 is failed low.

BOP CHECK Steam Pressure Transmitters - ALL OPERABLE

Step 16.0

BOP CHECK SG NR Levels - BETWEEN 68% And 74%

Step 17.0

BOP CHECK Main Feedwater Regulating And Low Power Feedwater Regulating Valves Automatic Control - OPERABLE

Step 18.0


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP CHECK Main Feedwater Regulating OR

Low Power Feedwater Regulating Valve(s) - IN AUTO

(RNO) WHEN SG levels return to between 68% and 74%, THEN PERFORM the following:

• PLACE in-service FeedwaterRegulating Valve(s) with operableAutomatic Control in Auto.

• MONITOR proper operation ofFeedwater Regulating Valve(s) in Auto.

Step 19.0

BOP CHECK SGFP Master Speed Controller - IN AUTO

Step 20.0

SRO TAKE Appropriate Actions Per Technical Specifications 3.3.1, 3.3.2, 3.3.3.6 and TRM 3.7.1.7.

Step 21.0

No TSs associated with Steam Flow Transmitters.

SRO NOTIFY I&C To Place The Affected Channel In Trip Or Bypass. REFER TO Addendum 2, Procedure List For The Appropriate Procedure.

Step 22.0

No TSs associated with Steam Flow Transmitters.

SRO INITIATE Corrective Actions For Failed Component

Step 23.0

Event #5 can be triggered on signal from the lead NRC Examiner.


OPERATOR ACTIONS


Event 6 Description: Loss of 480V LC E1B1.


RO Acknowledges and announces the following annunciators on 03M3: 480V LC E1B1 TRBL (E-5)

This list of annunciators is not all inclusive.

SRO/RO Determines a loss of power has occurred to Class 1E 480V LC E1B1.

SRO (continuous)

Directs actions of 0POP09-AN-03M3, E5, 480V LC E1B1 TRBL.

RO IF the alarm is due to a loss of the 4.16 KV

supply bus, THEN GO TO 0POP04-AE-0001, First Response To Loss of Any Or All 13.8 KV or 4.16 KV Bus.

0POP09-AN-03M3, E5, 480V LC E1B1 TRBL, Step 1

Just the Load Center is affected.

RO DISPATCH an Operator to check the following: • Ground fault lights on LC

E1B1(E2B1) - all lights on • Temperature gauge on LC

E1B1(E2B1) Transformer - less than 200 °C

• 480V LC E1B1(E2B1) supply breakerposition - closed

Step 2

480V LC E1B1 supply breaker will be open.

RO IF the cause of the alarm is a high transformer temperature, THEN ENSURE all available cooling fans are running.

Step 3

RO IF the cause of the alarm is a ground fault (Plant Computer point PLED0012 or local indication) OR transformer high temperature, THEN INITIATE a Condition Report to correct the problem.

Step 4


OPERATOR ACTIONS



Time Position Required Operator Actions Notes SRO If desired the SRO may cross-tie the load

center using 0POP02-AE-0001, AC Electrical Distribution Breaker Lineup, Section 7, Cross-Tie of Load Centers

Cross tying the Load Center will restore power, however, the TS for the 480 volt load center will still apply. (TS 3.8.3.1) See TSs on next page.

NOTE: The crew may elect to send a Plant Operator to put the E1B11 Battery Charger #2 in service first.

RO ENSURE loads for double ended load center being cross-tied which are listed in Addendum 2, Load Center Cross-tie and Load Reduction List, are removed PRIOR TO performing Cross-tie of a double ended load center.

0POP02-AE-0001, Section 7, Cross-Tie of Load Centers, Step 7.1

Will also refer to Addendum 2.

RO IF Normal Cross-tie of a Bus is desired, THEN PERFORM the following: • OPEN the applicable Load Center

Supply Breaker. • CLOSE the applicable Load Center

Crosstie Breaker. • IF the Load Center which is cross-tied

is a Class 1E Load Center, THEN PLACE the cross-tied Load Center’s open incoming breaker CRHS in PTL

Step 7.3 NOTE: Step 7.2 is NA

Event 6 can be triggered after SRO has checked TSs.

See TSs on next page.


OPERATOR ACTIONS




TS 3.4.4 Action d With 1 block valve inoperable, within 1 hour restore the block valves to Operable status or place the associated PORV in the closed position; within 72 hours restore the block valve to OPERABLE status or apply the requirements of the CRMP, otherwise be in at least HOT STANBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.

TS 3.8.2.1: c. Channel III 125-volt Battery Bank ElB11 (Unit I), E2B11 (Unit 2) and one of its two associated

full capacity chargers Action a: With one of the required battery banks inoperable, within 2 hours restore the inoperable battery bank to OPERABLE status or apply the requirements of the CRMP or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

TS 3.8.3.1: b. Train B A.C. ESF Busses consisting of:

1) 4160-Volt ESF Bus # E1B (Unit 1) , E2B (Unit 2), and2) 480-Volt ESF Busses # E1B1 and E1B2 (Unit 1), E2B1 and E2B2 (Unit 2) from respective

load center transformers.f. 120-Volt A. C. Vital Distribution Panel DP1203 energized from its associated inverter connected to

D.C. Bus # E1B11 * (Unit 1), E2B11* (Unit 2)Action a: With one of the required trains of AC. ESF busses not fully energized, within 8 hours reenergize the train or apply the requirements of the CRMP, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Action c: With one A.C. vital distribution panel either not energized from its associated inverter, or with the inverter not connected to its associated D.C. bus: (1) within 2 hours reenergize the A.C. distribution panel or apply the requirements of the CRMP, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours; and (2) within 24 hours reenergize the AC. vital distribution panels from its associated inverter connected to its associated D.C. bus or apply the requirements of the CRMP, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.


OPERATOR ACTIONS




TS 3.8.1.1 Action b will apply for ESF DG #12 Due to the ECW Pump and if Jacket Water and Lube Oil temperatures fall below 100ºF

With a standby diesel generator inoperable, demonstrate the OPERABILITY of the above-required A.C. offsite sources by performing Surveillance Requirement 4.8.1.1 .l .a within 1 hour and at least once per 8 hours thereafter. If the standby diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventive maintenance or testing, demonstrate the Operability of the remaining OPERABLE standby diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.2 for each such standby diesel generator separately within 8 hours, unless it can be demonstrated there is no common mode failure for the remaining diesel generator(s). Within 14 days restore the inoperable standby diesel generator to OPERABLE status or apply the requirements of the CRMP, or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours


OPERATOR ACTIONS


Event 6 Description: Main Generator Output Breaker trips open and inadvertent FWI. Event 7 Description: Main Turbine fails to auto trip on reactor trip. (Critical Task)

Time Position Required Operator Actions Notes ALL Respond to multiple alarms that come in

due to the Main Generator Output Breaker open and the inadvertent FWI.

ALL Determine that a Reactor Trip has occurred.

SRO (continuous)

Directs the actions of 0POP05-EO-EO00, Reactor Trip or Safety Injection.

RO (C)*

* - denotescritical

portion of step.

Completes immediate actions of 0POP05-EO-EO00 and determines: • Reactor is tripped• * Turbine has NOT automatically

tripped and RO will manually trip the Main Turbine.

• AC ESF Busses are energized except480V LC E1B1 if it was not placed onthe cross-tie breaker.

• SI may or may not have actuated –depends on how fast turbine gottripped – see ‘Notes’ to the right →

0POP05-EO-EO00, Reactor Trip or Safety Injection Steps 1-4.

RO will announce status of immediate action steps as he/she performs them. BOP Operator will monitor the plant and make an announcement of the Reactor trip.

The delay in tripping the Main Turbine after the Reactor has tripped may result in a large RCS over-cooling and depressurization which could result in a SI actuation. If this occurs, RCS pressure will quickly recover.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes SRO Directs/ensures the immediate actions of

EO00, Reactor Trip/SI have been completed by performing a procedure read through of them.

NOTE TO EXAMINER: • If an SI has occurred, continue with

the operator actions on this page.• If an SI has NOT occurred, go to Page

29 of this scenario guide for operatoractions.

AFW will automatically start immediately after the Rx trip due to SG level shrink.

Event # 8 consists of AFW Pump #14 tripping on overspeed while starting, AFW Pump #13 has the manual recirc valve open (will also trip if crew starts to close the AFW Reg valve) and AFW Pumps #12 & #11 trip on over current.

If SI did not actuate, the crew will transition to 0POP05-EO-ES01, Reactor Trip Response, and then transition to the Loss of Heat Sink FRP when all AFW is lost.


(Step 5) See Actions on Page 24-28


OPERATOR ACTIONS



Time Position Required Operator Actions Notes RO MONITOR If Containment Spray Is

Required: • Containment pressure ‑ GREATER

THAN 9.5 PSIG (QDPS)(RNO) • PERFORM the following:

• CHECK Containment pressure -HAS EXCEEDED 9.5 PSIG (CP - 18) • "PRESS PR‑ 0934"

OR • "EXTD RNG PRESS PR‑ 9759"

• IF containment pressure HASEXCEEDED 9.5 PSIG, THEN GOTO Step 6.b.

• IF containment pressure HASREMAINED LESS THAN 9.5PSIG, THEN GO TO Step 7.



6 and 13 gpm


RO MONITOR RCS Temperatures ‑• WITH ANY RCP RUNNING, RCS

TAVG STABLE AT OR TRENDINGTO 567°F


RCS TCOLD STABLE AT ORTRENDING TO 567°F

(Step 8)

RO CHECK Pressurizer Status: • PORVs ‑ CLOSED• Normal pressurizer spray valves -

CLOSED• Auxiliary spray valve - CLOSED• Excess letdown isolation valves -

CLOSED

(Step 9)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes RO MONITOR If RCPs Should Be Stopped:

• HHSI pump - AT LEAST ONERUNNING

• RCS pressure - LESS THAN 1430PSIG

(RNO) • GO TO Step 11

(Step 10) Reactor Coolant Pump Trip Criteria will probably NOT be met if AFW has been properly throttled.

RO VERIFY The Following Containment Isolation Valves – CLOSED • Seal return isolation valves• Containment atmosphere radiation


(Step 11)

RO CHECK If SG Secondary Pressure Boundary Intact.

(Step 12) No SG is Faulted.

RO CHECK If SG Tubes Are Intact. (Step 13) All SG Tubes are intact.

RO CHECK If RCS Is Intact: (Step 14) RCS is intact.

SRO A determination will be made to either stay in 0POP05-EO-EO00, Reactor Trip or SI, or transition to 0POP05-EO-ES11, SI Termination. In either case the Critical Safety Functions will be monitored and a transition will then be made to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink, as soon as Addendum 5 is complete.


If SI actuated, will not transition to a Functional Recovery Procedure until Addendum 5 is complete.


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP VERIFY FW isolation:

• SGFPTs – TRIPPED• SU SGFP – TRIPPED• VERIFY the following valves –

CLOSED • FWIVs• FWIBs• FW preheater bypass valves• FW regulating valves• Low power FW regulating valves• SG blowdown isolation valves• SG sample isolation valves

0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5, Verification of Equipment Operation.

(Step 1) This addendum is performed in parallel with Steps 5 to 14 of 0POP05-EO-EO00, Reactor Trip or Safety Injection.

NOTE: If 480 LC E1B1 was not re-energized then several RNO steps will be performed throughout Addendum 5.

SRO/BOP (C)

CHECK if main steamline should be isolated: • CHECK for any of the following

conditions:• Containment pressure – GREATER

THAN OR EQUAL TO 3 PSIGOR

• SG pressure (without low steamlinepressure SI blocked) - LESS THANOR EQUAL TO 735 PSIG


pressure SI blocked) - LOWERINGAT A RATE GREATER THANOR EQUAL TO 100 PSI/SEC,BYOBSERVANCE OF THESTEAMLINE PRESSURE RATEBISTABLES

(RNO) • GO TO Step 3 of this Addendum.

(Step 2)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP VERIFY AFW system status:

• Motor-driven pump – RUNNING• Turbine-driven pump - RUNNING

(Step 3) Crew should diagnose the loss of all AFW which creates a Red Path on the Heat Sink CSF even though a Red path is not indicated on the ICS or QDPS Computers. Implementation of the appropriate FRP cannot be done until Addendum 5 has been completed if an SI occurred.

BOP VERIFY AFW valve alignment - PROPER EMERGENCY ALIGNMENT

(Step 4)


(Step 5)

BOP VERIFY containment isolation phase A: • Phase A – ACTUATED• Phase A valves - CLOSED, REFER

TO ADDENDUM 1, PHASE AISOLATION VERIFICATION

(Step 6)

BOP VERIFY ECW status: • ECW pumps – RUNNING• ECW pump discharge isolation valves

- OPEN

(Step 7)


• RCFCs – RUNNING• Cooling water - TRANSFERRED TO

CCW

(Step 9)

BOP VERIFY SI pump status: • HHSI pumps – RUNNING• LHSI pumps – RUNNING

(Step 10)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP VERIFY SI valve alignment – PROPER

EMERGENCY ALIGNMENT (Step 11)


PSIG • HHSI pump flow – INDICATED• RCS pressure - LESS THAN 415

PSIG(RNO) • GO TO Step 13 of this Addendum.




– STOPPED• Supplemental purge supply and

exhaust fans – STOPPED• Purge Dampers - CLOSED

(Step 13)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP VERIFY ventilation actuation:

• Control room HVAC – OPERATINGIN EMERGENCY RECIRC

• EAB HVAC - OPERATING INEMERGENCY RECIRC

• FHB HVAC - OPERATING INEMERGENCY MODE

• FHB Exhaust Fans - ONLY TWOTRAINS OPERATING• Exhaust booster fans• Main exhaust fans


• IF three trains FHB exhaust fansrunning, THEN PLACE one trainFHB exhaust fans in PULL TOLOCK.


PERFORMING the following:• PLACE the outlet damper

Controller in manual• Manually close the outlet damper• VERIFY proper operation of filter

train in service• Essential chilled water pumps –

RUNNING• Essential chillers – RUNNING• ECCS pump room fan coolers –

RUNNING• AFW pump cubicle fans – RUNNING• FHB truck bay doors - CLOSED

(Step 14)


OPERATOR ACTIONS



Time Position Required Operator Actions Notes BOP NOTIFY Unit Supervisor that Addendum

5 is COMPLETE (Step 15)


(Step 16)



OPERATOR ACTIONS


Event 8 Description: Loss of Heat Sink and entry into FRH1 (Critical Task)


SRO Transitions to 0POP05-EO-ES01, Reactor Trip Response, but then straight to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink.

This procedure transition will apply if an SI DID NOT occur after the Reactor trip.

BOP CHECK If Secondary Heat Sink Is Required: • RCS pressure - GREATER THAN

ANY NON-FAULTED SGPRESSURE

• RCS wide range hot leg temperatures -GREATER THAN 350ºF

0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink, Step 1

The crew should first evaluate if a Secondary Heat Sink exists per the CIP of the procedure.

The plant conditions for this step will be present therefore a Secondary Heat Sink IS required.

RO (C)*

* - denotescritical

portion of step.

CHECK Secondary Heat Sink: • SG wide range level in at least three

intact SGs - GREATER THAN 50%[73%]

• Pressurizer pressure - LESS THAN2335 PSIG.

(RNO) • *TRIP all RCPs* • GO TO Step 10, OBSERVE

CAUTION prior to Step 10

Step 2

At this time, there will NOT be sufficient level in ≥ 3 SG’s so crew will have to implement an alternate method of RCS heat removal which will be Bleed and Feed.

These conditions are also on the procedure CIP therefore the crew may directly evaluate the conditions upon entering the procedure.

RO ACTUATE SI Step 10 SI may have actuated earlier due to the RCS cooldown after the Reactor trip and may have been reset. If so, the Manual SI Actuation switch can be used to re-actuate SI.


OPERATOR ACTIONS


Event 8 Description: Loss of Heat Sink and entry into FRH1 (Critical Task)

Time Position Required Operator Actions Notes RO (C)

VERIFY RCS Feed Path: • CHECK HHSI pumps - AT LEAST

ONE RUNNING• CHECK valve alignment for

operating pumps:• HHSI pumps suction from

RWST – OPEN• HHSI pumps discharge valves –

OPEN• HHSI cold leg injection valves –

OPEN

Step 11

Initiate RCS Feed and Bleed so that ECCS injection from at least one SI pump occurs, and the RCS depressurizes sufficiently for intermediate-head injection from a HHSI pump to occur prior to CETs rising to 1200ºF. NOTE: This task includes tripping RCPs to remove them as a heat source.

RO (C)

ESTABLISH RCS Bleed Path: • VERIFY power to BOTH

pressurizer PORV isolation valves –AVAILABLE

• VERIFY both pressurizer PORVisolation valves – OPEN

• OPEN both pressurizer PORVs

Step 12

SRO/RO (C)

Verify Adequate RCS Bleed Path: • Both Pressurizer PORV’s OPEN.• Both Pressurizer PORV’s Isolation

Valves OPEN.OR

• Open Rx Vessel Head Vent Valves:4 Isolation Valves and 2 Throttlevalves to give 2 vent paths.

Step 13

Terminate Scenario



POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/ UNSAT

SRO/RO MANUALLY TRIP THE MAIN TURBINE WHEN IT IS DETERMINED THAT IT FAILED TO AUTOMATICALLY TRIP.

Manually trip the main turbine before a severe ORANGE path challenge develops to either the subcriticality or the integrity CSF or before transition to 0POP05-EO-EC21, Uncontrolled Depressurization of all Steam Generators, whichever happens first.

SRO/RO TRIP RCPs, START AT LEAST ONE HHSI PUMP AND OPEN BOTH PZR PORVs.

Initiate RCS Feed and Bleed so that ECCS injection from at least one SI pump occurs, and the RCS depressurizes sufficiently for intermediate-head injection from a HHSI pump to occur prior to CETs rising to 1200ºF. NOTE: This task includes tripping RCPs to remove them as a heat source.



• Reactor Power is currently at 78%. BOL

• The previous crew was at step 7.51 of 0POP03-ZG-0005, Plant Startup to 100%, and holdpoints have been satisfied. During the previous power increase to 78% the crew was adding 40gallons of dilution water about every 30 minutes.

• The oncoming Crew is to recommence raising power.

• Reactor fuel is pre-conditioned.

• A line of thunderstorms is tracking from the north towards the site.

• CD Pump #13 is OOS for breaker maintenance. Expected return to service is 12 hours.

• SU SGFP #14 is OOS for breaker maintenance. Expected return to service is 12 hours.








LCO Actions:

NONE

of 7 ES-301 Transient and Event Checklist Form ES-301-5 FACILITY: SOUTH TEXAS PROJECT DATE OF EXAM: 09/28/2015 OPERATING TEST NO.: LOT 20 NRC

A P P L I C A N T

Crew A

E V E N T

T Y P E

Scenarios 1 3 4 5 T

O T A L

M I N I

M U

M(*) CREW POSITION CREW

POSITION CREW

POSITION CREW POSITION

R

I

U S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

RO

SRO-I

SRO-U

RX

1 1 2 1 1 0

NOR 0 1 1 1

I/C

3,4,5 2,4,5,7

7 4 4 2

MAJ

6 6 2 2 2 1 TS 3,4 2 0 2 2

RO

SRO-I

SRO-U

RX

1 1 2 1 1 0

NOR 0 1 1 1

I/C

4 2,3,4,5,8

6 4 4 2

MAJ

6 6 2 2 2 1 TS 3,5 2 0 2 2

RO

SRO-I

SRO-U

RX 1 1 1 1 0

NOR 2 1 1 1 1

I/C 3,5,

7,8 3,5

,8 7 4 4 2

MAJ 6 6 2 2 2 1 TS 0 0 2 2

RO

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2

Instructions: 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable

for RO applicants. ROs must serve in both the “at-the-controls (ATC)” and “balance-of-plant (BOP)” positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant’s competence count toward the minimum requirements specified for the applicant’s license level in the right-hand columns.

4. For licenses that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating controls.


A P P L I C A N T

Crew B

E V E N T

T Y P E

Scenarios 1 3 4 5 T

O T A L

M I N I

M U


POSITION CREW

POSITION CREW

POSITION

R

I

U S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

RO

SRO-I

SRO-U

RX

1 1 1 1 0

NOR 0 1 1 1

I/C

2,4,6

3,4,5

6 4 4 2

MAJ

5 6 2 2 2 1 TS 3,4 2 0 2 2

RO

SRO-I

SRO-U

RX

1 1 2 1 1 0

NOR 0 1 1 1

I/C

2,3,4,7 4 5 4 4 2

MAJ

5 6 2 2 2 1 TS 2,3 2 0 2 2

RO

SRO-I

SRO-U

RX 1 1 1 1 0

NOR 2 1 1 1 1

I/C 3,7 3,5,7,

8 6 4 4 2

MAJ 5 6 2 2 2 1 TS 0 0 2 2

RO

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2







A P P L I C A N T

Crew C

E V E N T

T Y P E

Scenarios 1 3 4 5 T

O T A L

M I N I

M U

M(*) CREW POSITION CREW POSITION CREW POSITION CREW

POSITION

R

I

U S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

RO

SRO-I

SRO-U

RX

1 1 1 1 0

NOR 0 1 1 1

I/C

2,4,6 3,4,5 6 4 4 2

MAJ 5 6 2 2 2 1

TS 3,4 2 0 2 2

RO

SRO-I

SRO-U

RX

1 1 2 1 1 0

NOR 0 1 1 1

I/C

2,3,4,7 4 5 4 4 2

MAJ

5 6 2 2 2 1 TS 2,3 2 0 2 2

RO

SRO-I

SRO-U

RX 1 1 1 1 0

NOR 2 1 1 1 1

I/C 3,7 3,5,7

,8 6 4 4 2

MAJ 5 6 2 2 2 1 TS 0 0 2 2

RO

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2







A P P L I C A N T

Crew D

E V E N T

T Y P E

Scenarios 1 3 4 5 T

O T A L

M I N I

M U

M(*) CREW

POSITION CREW

POSITION CREW POSITION CREW

POSITION

R

I

U S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

RO

SRO-I

SRO-U

RX

1 1 2 1 1 0

NOR 0 1 1 1

I/C

2,3,4,7 2,3,

4,5,8

9 4 4 2

MAJ

5 6 2 2 2 1 TS 2,3 3,5 4 0 2 2

RO

SRO-I

SRO-U

RX

1 1 2 1 1 0

NOR 0 1 1 1

I/C

3,7 2,4,5,7

6 4 4 2

MAJ

5 6 2 2 2 1 TS 0 0 2 2

RO

SRO-I

SRO-U

RX 1 1 1 1 0

NOR 0 1 1 1

I/C 2,4,6 3,5,

8 6 4 4 2

MAJ 5 6 2 2 2 1 TS 0 0 2 2

RO

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2







A P P L I C A N T

Crew E

E V E N T

T Y P E

Scenarios 1 3 4 5 T

O T A L

M I N I

M U

M(*) CREW POSITION CREW POSITION CREW

POSITION CREW

POSITION

R

I

U S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

RO

SRO-I

SRO-U

RX

1 1 2 1 1 0

NOR 0 1 1 1

I/C

2,3,4,7 2,4,

5,7 7 4 4 2

MAJ

5 6 2 2 2 1 TS 2,3 2 0 2 2

RO

SRO-I

SRO-U

RX 1 1 2 1 1 0

NOR 0 1 1 1

I/C 3,7 2,3,

4,5,8

7 4 4 2

MAJ 5 6 2 2 2 1 TS 3,5 2 0 2 2

RO

SRO-I

SRO-U

RX 1 1 1 1 0

NOR 0 1 1 1

I/C 2,4,6 3,5

,8 6 4 4 2

MAJ 5 6 2 2 2 1 TS 0 0 2 2

RO

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2







A P P L I C A N T

Crew

E V E N T

T Y P E

Scenarios 1 2 3 5 T

O T A L

M I N I

M U


POSITION CREW

POSITION CREW

POSITION

R

I

U S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

RO

SRO-I

SRO-U

RX

1 1 0

NOR 1 1 1

I/C

4 4 2

MAJ 2 2 1

TS 0 2 2

RO

SRO-I

SRO-U

RX

1 1 0

NOR 1 1 1

I/C

4 4 2

MAJ 2 2 1

TS 0 2 2

RO 7

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2

RO 8

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2







A P P L I C A N T

Crew

E V E N T

T Y P E

Scenarios 1 2 3 5 T

O T A L

M I N I

M U

M(*) CREW POSITION CREW POSITION CREW

POSITION CREW

POSITION

R

I

U S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

S R O

A T C

B O P

RO

SRO-I

SRO-U

RX

1 1 0

NOR 1 1 1

I/C

4 4 2

MAJ 2 2 1

TS 0 2 2

RO

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2

RO

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2

RO

SRO-I

SRO-U

RX 1 1 0

NOR 1 1 1

I/C 4 4 2

MAJ 2 2 1 TS 0 2 2






LOT 20 NRC Exam

ES-301 Competencies Checklist Form ES-301-6

Facility: South Texas Project Date of Examination: 09/28/2015 Operating Test No.: LOT 20 NRC APPLICANTS - CREW A

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

Competencies

SCENARIO SCENARIO

SCENARIO SCENARIO

1 3 4 5 1 3 4 5 1 3 4 5 1 3 4 5

Interpret/Diagnose Events and Conditions

1,3,4,5,

6

1,2,4,5,6,7

1,4,6

1,2,3,4,5,6,

8

2,3,5,6,7,8

1,3,5,6,

8

Comply With and Use Procedures (1)

1,3,4,5,

6

1,2,4,5,6,7

1,4,6

1,2,3,4,5,6,

8

2,3,5,6,7,8

1,3,5,6,

8

Operate Control Boards (2) N/A

1,2,4,5,6,7

1,4,6

1,2,3,4,5,6,

8

2,3,5,6,7,8

1,3,5,6,

8

Communicate and Interact ALL

1,2,4,5,6,7

1,4,6 ALL

2,3,5,6,7,8

1,3,5,6,

8

Demonstrate Supervisory Ability (3)

ALL N/A N/A ALL N/A N/A

Comply With and Use Tech. Specs. (3) 3,4 N/A N/A 3,5 N/A N/A

Notes: (1) Includes Technical Specification compliance for an RO. (2) Optional for an SRO-U. (3) Only applicable to SROs.

Instructions: Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

Page 1 of 7

LOT 20 NRC Exam


Facility: South Texas Project Date of Examination: 09/28/2015 Operating Test No.: LOT 20 NRC APPLICANTS - CREW B

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

Competencies

SCENARIO SCENARIO

SCENARIO SCENARIO

1 3 4 5 1 3 4 5 1 3 4 5 1 3 4 5

Interpret/Diagnose Events and Conditions 2,4,

5,6

1,3,4,5,

6

1,2,3,4,5,7

1,4,6 1,3,

5,7

2,3,5,6,7,8

Comply With and Use Procedures (1) 2,4,

5,6

1,3,4,5,

6

1,2,3,4,5,7

1,4,6 1,3,

5,7

2,3,5,6,7,8

Operate Control Boards (2) 2,4,

5,6 N/A N/A 1,4,6 1,3,

5,7

2,3,5,6,7,8

Communicate and Interact 2,4,

5,6 ALL ALL 1,4,6 1,3,

5,7

2,3,5,6,7,8


N/A ALL ALL N/A N/A N/A

Comply With and Use Tech. Specs. (3) N/A 3,4 2,3 N/A N/A N/A



Page 2 of 7

LOT 20 NRC Exam


Facility: South Texas Project Date of Examination: 09/28/2015 Operating Test No.: LOT 20 NRC APPLICANTS - CREW C

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

Competencies

SCENARIO SCENARIO

SCENARIO SCENARIO

1 3 4 5 1 3 4 5 1 3 4 5 1 3 4 5

Interpret/Diagnose Events and Conditions 2,4,

5,6

1,3,4,5,

6

1,2,3,4,5,7

1,4,6 1,3,

5,7

2,3,5,6,7,8

Comply With and Use Procedures (1) 2,4,

5,6

1,3,4,5,

6

1,2,3,4,5,7

1,4,6 1,3,

5,7

2,3,5,6,7,8

Operate Control Boards (2) 2,4,

5,6 N/A N/A 1,4,6 1,3,

5,7

2,3,5,6,7,8

Communicate and Interact 2,4,

5,6 ALL ALL 1,4,6 1,3,

5,7

2,3,5,6,7,8


N/A ALL ALL N/A N/A N/A

Comply With and Use Tech. Specs. (3) N/A 3,4 2,3 N/A N/A N/A



Page 3 of 7

LOT 20 NRC Exam


Facility: South Texas Project Date of Examination: 09/28/2015 Operating Test No.: LOT 20 NRC APPLICANTS - CREW D

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

Competencies

SCENARIO SCENARIO

SCENARIO SCENARIO

1 3 4 5 1 3 4 5 1 3 4 5 1 3 4 5


1,2,3,4,5,7

1,2,3,4,5,6,

8

1,3,5,7

1,2,4,5,6,7

2,4,5,6

1,3,5,6,

8


1,2,3,4,5,7

1,2,3,4,5,6,

8

1,3,5,7

1,2,4,5,6,7

2,4,5,6

1,3,5,6,

8


1,2,3,4,5,6,

8

1,3,5,7

1,2,4,5,6,7

2,4,5,6

1,3,5,6,

8

Communicate and Interact ALL ALL 1,3,

5,7 1,2,4,5,6,7

2,4,5,6

1,3,5,6,

8


ALL ALL N/A N/A N/A N/A

Comply With and Use Tech. Specs. (3) 2,3 3,5 N/A N/A N/A N/A



Page 4 of 7

LOT 20 NRC Exam


Facility: South Texas Project Date of Examination: 09/28/2015 Operating Test No.: LOT 20 NRC APPLICANTS - CREW E

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

Competencies

SCENARIO SCENARIO

SCENARIO SCENARIO

1 3 4 5 1 3 4 5 1 3 4 5 1 3 4 5


1,2,3,4,5,7

1,2,4,5,6,7

1,3,5,7

1,2,3,4,5,6,

8

2,4,5,6

1,3,5,6,

8


1,2,3,4,5,7

1,2,4,5,6,7

1,3,5,7

1,2,3,4,5,6,

8

2,4,5,6

1,3,5,6,

8


1,2,4,5,6,7

1,3,5,7

1,2,3,4,5,6,

8

2,4,5,6

1,3,5,6,

8

Communicate and Interact ALL

1,2,4,5,6,7

1,3,5,7 ALL 2,4,

5,6 1,3,5,6,

8


ALL N/A N/A ALL N/A N/A

Comply With and Use Tech. Specs. (3) 2,3 N/A N/A 3,5 N/A N/A



Page 5 of 7

LOT 20 NRC Exam


Facility: South Texas Project Date of Examination: 09/28/2015 Operating Test No.: LOT 20 NRC APPLICANTS - CREW

RO SRO-I SRO-U

RO SRO-I SRO-U

RO 7 SRO-I SRO-U

RO 8 SRO-I SRO-U

Competencies

SCENARIO SCENARIO

SCENARIO SCENARIO

1 3 4 5 1 3 4 5 1 3 4 5 1 3 4 5



Operate Control Boards (2)

Communicate and Interact


Comply With and Use Tech. Specs. (3)



Page 6 of 7

LOT 20 NRC Exam


Facility: South Texas Project Date of Examination: 09/28/2015 Operating Test No.: LOT 20 NRC APPLICANTS - CREW

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

RO SRO-I SRO-U

Competencies

SCENARIO SCENARIO

SCENARIO SCENARIO

1 3 4 5 1 3 4 5 1 3 4 5 1 3 4 5



Operate Control Boards (2)

Communicate and Interact


Comply With and Use Tech. Specs. (3)



Page 7 of 7

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