Text

Wolf Creek - 2015-11 - Proposed Operating Test
	ML16036A385
Person / Time
Site:	Wolf Creek
Issue date:	11/13/2015
From:	Vincent Gaddy; Operations Branch IV
To:	; Wolf Creek
References
	Download: ML16036A385 (357)
	v • d • e

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: SRAPE037 Task Title:

Determine the actions required for a specific level of S/G Tube Leakage. Job Performance Measure No:

RA1 Rev 0 K/A

Reference:

2.1.7 Ability

to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

Annunciator 61A, PROCESS RAD HIHI, and 61B, PROCESS RAD HI, are in alarm. GE RE

-92 has trended up to a value of 4.6E

-006 µci/cc. OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, Attachment C, is in progress. Surveys indicate that S/G 'D' has higher radiation readings than the other three S/Gs.

AIF 21D-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, is provided.

Task Standar d: At the completion of the JPM, the Applicant will have determined that a prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is required. Additional actions are to be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), and that a Plant cooldown to Mode 5 is required. Required Materials:

OFN BB-07A, Rev 17 A. Copy Of Form AIF 21D

-004-01-03. St raight Edge. Calculator.

General

References:

OFN BB-07A, Rev 17 A.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Initiating Cue:

Determine what actions are required per OFN BB-07A, STEAM GENERATOR TUBE LEAKAGE Time Critical Task:

NO Alternate Path:

NO Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

Provide a copy of AIF 21D-004-01-03 and OFN BB

-07A, attachment C. The Applicant can either use a straight edge, or the conversion factor formula, to determine the leak rate.

Performance Step:

1 Step C1. Action Level Table:

Leak Rate Required Actions Increased Monitoring Perform Step C2 Actions Action Level 1 Perform Step C3 Actions Action Level 2

Perform Step C4 Actions Action Level 3 gpd Perform Step C5 Actions Action Level 4 Perform Step C6 Actions Standard: Used AIF 21D

-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, to determine leak rate for a reading of 4.6E

-006 µci/cc on GE RE

-92. Determined 106 to 109 gpd leak rate per straight edge.

(4.6E-006 - 2.68E-08)/ 4.23E

-08 = 108.1 gpd Determine 107 to 109 gpd leak rate by conversion factor formula. Determined that Action Level 3, perform step C5 actions, is required. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Examiner NOTE:

Performance Step:

2 Step C5. IF leakage rate is greater than or equal to 100 gpd and less than 150 gpd (Action Level 3

- EPRI limit), THEN perform the following:

a. Go to step 10 and commence prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), while continuing with this attachment. Plant cooldown to Mode 5 is required.

Standard: Determined that plant shutdown as follows is required:

50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

, Mode 3 within next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), Cooldown to Mode 5.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Other items listed in step C5 are not required to satisfy the critical step of this JPM. If they are listed it will not affect the outcome of pass / fail Terminating cue:

The JPM is completed once the Applicant has determined that a prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), and that a Plant cooldown to Mode 5 is required.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

A1 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

Annunciator 61A, PROCESS RAD HIHI, and 61B, PROCESS RAD HI, are in alarm. GE RE

-92 has trended up to a value of 4.6E

-006 µci/cc. OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, Attachment C, is in progress. Surveys indicate that S/G 'D' has higher radiation readings than the other three S/Gs. AIF 21D

-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, is provided.

Initiating Cue:

Determine what actions are required per OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: SRE09001 Task Title:

EMG ES-04, Attachment A, Determination Of RCS Boron Concentration Based On Total Mass. Job Performance Measure No:

A2 Rev 0 K/A

Reference:

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. EMG ES

-04, Natural Circulation Cooldown, is in progress.

Task Standard:

At the completion of the JPM, the Applicant will have Determined RCS Boron Concentration Based On Total Mass.

Required Materials:

EMG ES-04, ATTACHMENT A, REV 19. NPIS PZR LEVEL PICTURE. CALCULATOR.

General

References:

EMG ES-04, Rev 19.

Initiating Cue:

The CRS directs you to perform Attachment A, Determination Of RCS Boron Concentration Based On Total Mass.

Chemistry sample results are as follows:

RCS Hot Leg Loop 1

- 1610 ppm RCS Hot Leg Loop 3

- 1590 ppm Letdown Line

- 1615 ppm PZR Concentration

- 1605 ppm Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Provide the Applicant with Attachment A, the NPIS PZR Level picture and a calculator.

Performance Step:

1 Step A1. Record Chemistry sample results:

a. RCS Concentrations:

o RCS Hot Leg Loop 1 o RCS Hot Leg Loop 3 o Letdown Line

b. PZR Concentration:

Standard: Recorded the chemistry samples results provided in the initial conditions on Attachment A.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

Performance Step:

2 Step A2. Determine PZR and RCS multipliers from the following table:

Standard: Determined from the supplied picture that the NPIS PZR Level is 39.5%. Determined from the table that the correct PZR Multiplier is 0.066. Determined from the table that the correct RCS Multiplier is 0.934. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

3 Step A3. Determine PZR contribution = A:

Standard: Calculated the value for the PZR contribution.

1605 X 0.066 = 105.93 Range of 103

- 106 Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Examiner NOTE:

Performance Step:

4 Step A4. Determine RCS contribution = B:

Standard: Calculated the value for the RCS concentration contribution.

1590 X 0.934 = 1485.06 Range of 1484

- 1486 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Use the EMG ES

-04, Attachment A Key, to compare with the Applicants results.

Performance Step:

5 Step A5. Determine RCS boron concentration based on total mass = C:

Standard: Calculated the RCS boron concentration based on total mass value. 105.93 + 1485.06 = 1590.99 Range of 1587

- 1592 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant has calculated the RCS boron concentration based on total mass

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

A2 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. EMG ES

-04, Natural Circulation Cooldown, is in progress.

Initiating Cue:

The CRS directs you to perform Attachment A, Determination Of RCS Boron Concentration Based On Total Mass.

Chemistry sample results are as follows:

RCS Hot Leg Loop 1

- 1610 ppm RCS Hot Leg Loop 3

- 1590 ppm Letdown Line

- 1615 ppm PZR Concentration

- 1605 ppm Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 6 Facility: WCGS Task No: Task Title:

Perform Surveillance Test for AFD Job Performance Measure No:

A3 Rev 0 K/A

Reference:

2.2.42 - Ability to recognize system parameters that are entry level conditions for T.S. Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

The Plant has been stable at 100%. The AFD Monitor Alarm is inoperable.

Task Standard:

Upon completion of this JPM, the Candidate will have determined that the Plant is in LCO 3.2.3 per Attachment A.

Required Materials:

STS SF-002, CORE AXIAL FLUX DIFFERENCE, Calculator General

References:

STS SF-002, CORE AXIAL FLUX DIFFERENCE Initiating Cue: The Control Room Supervisor has directed you to perform STS SF-002, section 8.0. All prerequisites have been performed.

The following data is present on plant instrumentation. All four NI channels are operable. N41 N42 N43 N44 % Power 95 95 95 96 % Flux Difference 15 20 Time Critical Task:

NO Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 6 Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 6 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step 8.1.1 Monitor Axial Flux Difference (AFD) by performing the following:

IF a Power Range NI is operable, THEN record POWER RANGE FLUX DIFF and POWER LEVEL data on ATTACHMENT A, AXIAL FLUX DIFFERENCE LOG, at least once per hour.

Standard: Go to Attachment A and enter the data provide on the cue sheet.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step 8.1.2 Compare the data recorded from each operable power range channel to the limits of Figure 2.5, Axial Flux Difference (AFD) of the COLR. Standard: Compare all four channels to the limits of Figure 2.5 of the COLR.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 6 Examiner NOTE:

Performance Step:

3 Step 8.1.3 Designate whether the indicated POWER RANGE FLUX DIFF is within the ACCEPTABLE OPERATION range of Figure 2.5, Axial Flux Difference (AFD) of the COLR for each operable channel on ATTACHMENT A, AXIAL FLUX DIFFERENCE LOG, by placing a check mark in the Yes (Y) or No (N) column, initialing, and dating.

Standard: Determine that N41 and N42 are in the acceptable region, determine that N43 and N44 are in the unacceptable region, and annotate the attachment accordingly Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 Step 8.1.2 IF the indicated POWER RANGE FLUX DIFF is outside the acceptable limits of Figure 2.5, Axial Flux Difference (AFD) of the COLR on two or more operable power range channels, THEN refer to Technical Specification 3.2.3.

Standard: Determine that the Plant is in LCO 3.2.3 and report to the Control Room Supervisor.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant has completed STS SF

-002 Attachment A and has handed in the paperwork.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 5 of 6 Verification of Completion Job Performance Measure No.

RA3 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

The Plant has been stable at 100%. The AFD Monitor Alarm is inoperable.

Initiating Cue:

The Control Room Supervisor has directed you to perform STS SF-002, section 8.0. All prerequisites have been performed.

The following data is present on plant instrumentation N41 N42 N43 N44 % Power 95 95 95 96 % Flux Difference 15 20 Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: EPLANS005 Task Title:

Determine maximum authorized emergency stay times for an individual.

Job Performance Measure No:

A4 Rev 0 K/A

Reference:

2.3.4 Knowledge

of radiation exposure limits under normal or emergency conditions.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. A steam generator tube rupture has occurred on 'A' S/G and AB PV

-001 is failed open. Difficulties closing ABV0018 due to binding occurred and HP made the operators leave the area due to high radiation. Two operators and a mechanic have volunteered to re

-enter Area 5 to attempt to close ABV0018 by loosening the packing and closing the valve.

Task Standard:

At the completion of the JPM, the Applicant will have determined the maximum authorized emergency stay times for each individual associated with isolating the ARV. (the minimum is the only critical part

) Required Materials:

EPF 06-013-02, REV 1. AP 25A

-001, REV 16A. CALCULATOR.

General

References:

EPF 06-013-02, Rev 1. AP 25A

-001, Rev 16A.

Initiating Cue:

Using the information on the EPF 06

-013-02, Emergency Exposure Authorization forms, determine for each individual the maximum stay time that will not violate the authorized exposure.

Document the maximum stay time in the comments section of the EPF form.

Time Critical Task:

NO Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Provide the Applicant with a copy of EPF 06

-013-02 for each individual and a calculator.

Verify results using the supplied Keys.

Performance Step:

1 Document the maximum stay time for Operator1 in the comment section.

Standard: Recognized the projected dose numbers for TEDE, Thyroid, and Extremities on EPF 06

-013-02. Documented the maximum stay time for Operator1 in the comment section.

TEDE: 9.44 R/1.39 R/Hr = 6.79 Hr Thyroid: 125R/14.4 R/Hr = 8.68 Hr Extremities: 94.16 R/289 R/Hr = 0.3258 Hr (19.548 min)

Range is 18

- 21 minutes Maximum stay time will be 18 - 21 minutes. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

Performance Step:

2 Document the maximum stay time for Operator2 in the comment section.

Standard: Recognized the projected dose numbers for TEDE, Thyroid, and Extremities on EPF 06

-013-02. Documented the maximum stay time for Operator2 in the comment section.

TEDE: 9.57 R/1.39 R/Hr = 6.88 Hr Thyroid: 125R/14.4 R/Hr = 8.68 Hr Extremities: 92.8 R/289 R/Hr = 0.321 Hr (19.26 min)

Range is 18

- 21 minutes Maximum stay time will be 18 - 21 minutes. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Examiner NOTE:

Performance Step:

3 Document the maximum stay time for the Mechanic in the comment section.

Standard: Recognized the projected dose numbers for TEDE, Thyroid, and Extremities on EPF 06

-013-02. Documented the maximum stay time for Operator1 in the comment section.

TEDE: 8.15 R/1.39 R/Hr = 5.86 Hr Thyroid: 125R/14.4 R/Hr = 8.68 Hr Extremities: 90 R/289 R/Hr = 0.311 Hr (18.66 min)

Range is 17

- 20 minutes Maximum stay time will be 17 - 20 minutes. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant has documented the maximum authorized stay times for each individual.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

RA4 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. A steam generator tube rupture has occurred on 'A' S/G and AB PV

-001 is failed open. Difficulties closing ABV0018 due to binding occurred and HP made the operators leave the area due to high radiation. Two operators and a mechanic have volunteered to re

-enter Area 5 to attempt to close ABV0018 by loosening the packing and closing the valve.

Initiating Cue:

Using the information on the EPF 06

-013-02, Emergency Exposure Authorization forms, determine the maximum stay time for each individual that will not violate the authorized exposure. Document the maximum stay time in the comments section of the EPF form.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: SRAPE037 Task Title:

Determine the actions required for a specific level of S/G Tube Leakage. Job Performance Measure No:

A5 Rev 0 K/A

Reference:

2.1.7 Ability

to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

Annunciator 61A, PROCESS RAD HIHI, and 61B, PROCESS RAD HI, are in alarm. GE RE

-92 has trended up to a value of 4.6E

-006 µci/cc. OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, Attachment C, is in progress. Surveys indicate that S/G 'D' has higher radiation readings than the other three S/Gs.

AIF 21D-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, is provided.

Task Standard:

At the completion of the JPM, the Applicant will have determined that a prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is required. Additional actions are to be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), and that a Plant cooldown to Mode 5 is required. Required Materials:

OFN BB-07A, Rev 17 A. Copy Of Form AIF 21D

-004-01-03. St raight Edge. Calculator.

General

References:

OFN BB-07A, Rev 17 A.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Initiating Cue:

Determine what actions are required per OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE Time Critical Task: NO Alternate Path:

NO Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

Provide a copy of AIF 21D

-004-01-03 and OFN BB

-07A, attachment C. The Applicant can either use a straight edge, or the conversion factor formula, to determine the leak rate.

Performance Step:

1 Step C1. Action Level Table:

Leak Rate Required Actions Increased Monitoring Perform Step C2 Actions Action Level 1 Perform Step C3 Actions Action Level 2

Perform Step C4 Actions Action Level 3 gpd Perform Step C5 Actions Action Level 4 Perform Step C6 Actions Standard: Used AIF 21D

-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, to determine leak rate for a reading of 4.6E

-006 µci/cc on GE RE

-92. Determined 106 to 109 gpd leak rate per straight edge.

(4.6E-006 - 2.68E-08)/ 4.23E

-08 = 108.1 gpd.

Determine 107 to 109 gpd leak rate by conversion factor formula. Determined that Action Level 3, perform step C5 actions, is required. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Examiner NOTE:

Performance Step:

2 Step C5. IF leakage rate is greater than or equal to 100 gpd and less than 150 gpd (Action Level 3

- EPRI limit), THEN perform the following:

a. Go to step 10 and commence prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), while continuing with this attachment. Plant cooldown to Mode 5 is required.

Standard: Determined that plant shutdown as follows is required:

50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Mode 3 within next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), Cooldown to Mode 5.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Other items listed in step C5 are not required to satisfy the critical step of this JPM. If they are listed it will not affect the outcome of pass / fail Terminating cue:

The JPM is completed once the Applicant has determined that a prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), and that a Plant cooldown to Mode 5 is required.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

A5 Examinee's Name:

Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

Annunciator 61A, PROCESS RAD HIHI, and 61B, PROCESS RAD HI, are in alarm. GE RE

-92 has trended up to a value of 4.6E

-006 µci/cc. OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, Attachment C, is in progress. Surveys indicate that S/G 'D' has higher radiation readings than the other three S/Gs. AIF 21D

-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, is provided.

Initiating Cue:

Determine what actions are required per OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 8 Facility: WCGS Task No: SRE09001 Task Title:

EMG ES-04, Attachment A, Determination Of RCS Boron Concentration Based On Total Mass. Job Performance Measure No:

A6 Rev 0 K/A

Reference:

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

You are the Control Room Supervisor. EMG ES-04, Natural Circulation Cooldown, is in progress. You have directed the Reactor Operator to perform Attachment A, Determination Of RCS Boron Concentration Based On Total Mass.

Reactor engineering has determined required minimum shutdown margin boron concentration to be 1600 ppm.

Task Standard:

At the completion of the JPM, the Applicant will have disapproved the Reactor Operator's calculations. The Applicant will recalculate the results and determine that the current boron concentration does not meet the required minimum shutdown margin concentration requirement.

Required Materials:

EMG ES-04, ATTACHMENT A, step 10, REV 19. NPIS PZR LEVEL PICTURE. CALCULATOR.

General

References:

EMG ES-04, Rev 19. STS RE

-004, Rev 30.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 8 Initiating Cue:

Review and approve / disapprove the Reactor Operator's calculations.

Determine if the current RCS boron concentration is greater than the required minimum shutdown margin concentration AND if any TS are applicable. Chemistry sample results are as follows:

RCS Hot Leg Loop 1

- 1610 ppm RCS Hot Leg Loop 3

- 1590 ppm Letdown Line

- 1615 ppm PZR Concentration

- 1605 ppm Document your results on EMG ES

-04, NATURAL CIRCULATION COOLDOWN, Attachment A.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 8 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Provide the Applicant with the Initial Attachment A, the Shutdown Margin Calculation, the NPIS PZR Level picture and a calculator.

Performance Step:

1 Step A1. Record Chemistry sample results:

a. RCS Concentrations:

o RCS Hot Leg Loop 1 o RCS Hot Leg Loop 3 o Letdown Line

b. PZR Concentration:

Standard: Recognized that the chemistry samples results provided in the initial conditions are NOT correctly documented.

Corrected the chemistry sample results.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Corrected values are documented on the Corrected EMG ES

-04 Attachment A form.

Appendix C 2 Form ES-C-1 Page 4 of 8 Examiner NOTE:

Performance Step:

2 Step A2. Determine PZR and RCS multipliers from the following table:

Standard: Determined from the supplied picture that the NPIS PZR Level is 39.5%. Determined from the table that the correct PZR Multiplier is 0.066. Determined from the table that the correct RCS Multiplier is 0.934. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Corrected values are documented on the Corrected EMG ES

-04 Attachment A form.

Examiner NOTE:

Performance Step:

3 Step A3. Determine PZR contribution = A:

Standard: Recognized that the incorrect value for the PZR concentration was used. Corrected the value and recalculated the result.

1605 X 0.066 = 105.93 Range of 103

- 106 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Corrected values are documented on the Corrected EMG ES

-04 Attachment A form.

Appendix C 2 Form ES-C-1 Page 5 of 8 Examiner NOTE:

Performance Step:

4 Step A4. Determine RCS contribution = B:

Standard: Recognized that the incorrect value for the RCS concentration was used. Corrected the value and recalculated the result.

1590 X 0.934 = 1485.06 Range of 1484 - 1486 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Corrected values are documented on the Corrected EMG ES

-04 Attachment A form.

Examiner NOTE:

Use the Corrected EMG ES-04, Attachment A, to compare with the Applicants results.

Performance Step:

5 Step A5. Determine RCS boron concentration based on total mass = C:

Standard: Recognized that the RCS boron concentration based on total mass value was incorrect.

Corrected the values and recalculated the result. 105.93 + 1485.06 = 1590.99 Range of 1587

- 1592 Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 8 Examiner NOTE:

Performance Step:

6 Step 10.c.

Check RCS Boron Concentration

- GREATER THAN COLD SHUTDOWN CONCENTRATION Standard: Recognized from Shutdown Margin Calculation that the RCS boron concentration based on total mass does NOT meet the required 1600 ppm boron concentration.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

7 Step Applicable TS. Standard: Recognized the unit is currently in TS 3.1.1, Shutdown Margin, Condition A, SDM not within limit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant recognized that the RCS boron concentration based on total mass does NOT meet the requir ed 1600 ppm boron concentration AND TS 3.1.1 condition A applies.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 7 of 8 Verification of Completion Job Performance Measure No.

A6 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Control Room Supervisor. EMG ES

-04, Natural Circulation Cooldown, is in progress. You have directed the Reactor Operator to perform Attachment A, Determination Of RCS Boron Concentration Based On Total Mass. Reactor engineering has determined required minimum shutdown margin boron concentration to be 1600 ppm

. Initiating Cue:

Review and approve / disapprove the Reactor Operator's calculations. Determine if the current RCS boron concentration is greater than the required minimum shutdown margin concentration AND if any TS are applicable.

Chemistry sample results are as follows:

RCS Hot Leg Loop 1

- 1610 ppm RCS Hot Leg Loop 3

- 1590 ppm Letdown Line

- 1615 ppm PZR Concentration

- 1605 ppm Document your results on EMG ES

-04, NATURAL CIRCULATION COOLDOWN, Attachment A.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 5 Facility: WCGS Task No: AP26C004001 Task Title:

Determine the Operability of BG HV-8357A and CCP A.

Job Performance Measure No:

A7 Rev 0 K/A

Reference:

2.2.37 Ability to determine operability and/or availability of safety related equipment.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

You are the Control Room Supervisor. The Reactor Operator has completed a partial STN BG

-202 for BG HV

-8357A. Task Standard:

At the completion of the JPM, the Applicant will have Determined that BG HV-8357A is INOPERABLE and that CCP A is OPERABLE. Required Materials:

STN BG-202, REV 1. TECHNICAL SPECIFICATIONS. TECHNICAL SPECIFICATIONS BASES.

General

References:

STN BG-202, Rev 1. Technical Specifications. Technical Specifications Bases. Initiating Cue:

Review STN BG

-202 and determine operability of the BG HV

-8357A and A CCP. Time Critical Task:

NO Alternate Path:

NO Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 2 of 5 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Provide the Applicant with the completed STN BG

-202, a copy of Technical Specifications, and a copy of Technical Specifications Bases.

Performance Step:

1 Step 8.4.6.

Review STN BG

-202 results.

Standard: Recognized that BG HV

-8357A failed the PIT requirement.

Determined that per required action 1 that BG HV

-8357A is INOPERABLE and that corrective actions are required.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step 7.2. Determine Operability per T.S. 3.5.2.

Standard: Determined per T.S. 3.5.2 Bases that the CCPs may be considered OPERABLE with its associated discharge to RCP seal throttle valve, BG

-HV-8357A, INOPERABLE

. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 5 Terminating cue:

The JPM is completed once the Applicant determines that BG HV-8357A is INOPERABLE, and A CCP is OPERABLE.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 4 of 5 Verification of Completion Job Performance Measure No.

A7 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Control Room Supervisor. The Reactor Operator has completed a partial STN BG

-202 for BG HV

-8357A. Initiating Cue:

Review STN BG

-202 and determine operability of the BG HV

-8357A and A CCP.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 6 Facility: WCGS Task No: Task Title:

Review a release permit for approval Job Performance Measure No:

A8 Rev 0 K/A

Reference:

2.3.6 Ability

to approve release permits Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

Today is 11 2015 at 2230. You are the Shift Manager. A containment purge to lower Containment pressure was initiated and stopped due to workload. The crew is preparing to re

-initiate the purge using the same permit. The Reactor Operator has prepared Purge Permit page 2 of 3 for the release.

Task Standard:

At the completion of this JPM, the Candidate will have documented that:

The RO inadvertently transposed the number for GTRE

-22/33 and GTRE

-31/32 when establishing the setpoints.

This permit has expired and cannot be used.

The reading for GTG 313 exceeds the restart limit and the purge cannot be reinitiated Required Materials:

APF -07B-001-09, CTMT Purge Release Permit General

References:

AP 07B-001, Radioactive Releases AI 07B- 024, Preparation of Containment Purge Permits APF-07B-001-09-08, Containment Purge Release Permit

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 6 Initiating Cue:

Review the permit for the purge re-initiation. Approve or disapprove the release and document any errors.

The following readings are indicated on the RM11 High Setpoint Low Setpoint GTRE-22/33 2.06 E -03 2.06 E -04 GTRE-31/32 1.00 E -03 3.34 E -05 Time Critical Task:

NO Alternate Path: NO Validation Time:

20 Minutes Appendix C 2 Form ES-C-1 Page 3 of 6 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step Check the release conditions Standard: Note that the RO transposed the number for GTRE

-22/33 and GTRE

-31/32 when establishing the setpoints.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step Check the special instructions Standard: Note that the permit has expired Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 6 Examiner NOTE:

Performance Step:

3 Step Check the Authorization Section, Release Data, and the continuation sheet Standard: Note that the reading for GTG 313 exceeds the allowable value for restart of the purge Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

After the Candidate has completed the review of the permit, documented the errors found, and handed the JPM in, the JPM is complete.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 5 of 6 Verification of Completion Job Performance Measure No.

A8 Examinee's Name:

Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

Today is 11 2015 at 2230. You are the Shift Manager. A containment purge to lower Containment pressure was initiated and stopped due to workload. The crew is preparing to re

-initiate the purge using the same permit. The Reactor Operator has prepared Purge Permit page 2 of 3 for the release.

Initiating Cue:

Review the permit for the purge re

-initiation. Approve or disapprove the release and document any errors.

The following readings are indicated on the RM11 High Setpoint Low Setpoint GTRE-22/3 3 2.06 E -03 2.06 E -04 GTRE-31/32 1.00 E -03 3.34 E -05 Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: EPLANS004 Task Title:

Make a Protective Action Recommendation.

Job Performance Measure No:

A9 Rev 0 K/A

Reference:

2.4.44 Knowledge of emergency plan protective action recommendations.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

A Site Area Emergency has been declared by the Control Room and the Immediate Notification form complete

d. You are the Off

-site Emergency Manager and the Dose Assessment Coordinator has provided you with a dose assessment (EDCP).

Task Standard:

At the completion of the JPM, the Applicant will have validated the EDCP and developed an accurate Emergency Notification form within 15 minutes of receiving the EDCP.

Required Materials:

EPP 06-001, Rev 22. EPP 06

-005, Rev 7. EPP 06

-006, Rev 9. EPP 06

-007, Rev 23. EPP 06

-012, Rev 14A. Initial Notification Form, CR

-00 1, NPIS Screen PRAD

, EDCP. Final Notification Form (Key), EOF

-001. General

References:

EPP 06-001, Rev 22. EPP 06

-005, Rev 7. EPP 06

-006, Rev 9. EPP 06

-007, Rev 23. EPP 06

-012, Rev 14A.

Initiating Cue:

Develop the appropriate Emergency Notification form. THIS IS A TIME CRITICAL TASK

. Time Critical Task:

YES Alternate Path:

NO Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Time Zero (T-0) for the 15 minute requirement to complete the Emergency Notification begins when the EDCP is provided. Performance Step:

1 Step 7.1.2 Determine the protective action recommendation(s) using ATTACHMENT A, PROTECTIVE ACTION RECOMMENDATION CHART OR the PROTECTIVE ACTION RECOMMENDATION CHART located in the emergency facilities.

o IF EDCP printout is not available, THEN use ATTACHMENT B, SUBZONES AFFECTED BY WIND DIRECTION, to determine the affected subzones.

OR o IF EDCP printout is not available, THEN use the correct isopleth for the current stability class to determine the affected subzones on the 10 mile EPZ map.

Standard: Recognized that an EDCP IS available.

Referred to Attachment A to determine that the Subzones on the EDCP are the correct ones for the Protective Action Recommendation (PAR).

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

This is a "PAR Only" notification. The Applicant will use the information on CR

-00 1 to fill in the classification information.

Use the provided key (EOF

-001) to determine the accuracy of the notification form. The form MUST be accurate in order to meet the standard. The following information is required to be accurate:

Message #, Status , Code Word , Type, Emergency Classification information , Met data , Release data , Protective action recommendation information, and Signature and date Performance Step:

2 Step 7.1.3 Indicate the protective action recommendation on EPF 06

-007-01, WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION.

1. Evacuation is the normal PAR made during emergencies. (3.1.6) 2. Shelter is the PAR made when known conditions exist that would make evacuation a greater hazard to the public. (3.1.6) 3. Once a PAR has been made, that PAR remains in effect until the event is terminated. All PARs made should be indicated on all notification forms once they are made.

Standard: Completed the form accurately.

Completed the form within 15 minutes of receiving the INITIAL EDCP. WHEN the Applicant provides the form, THEN document the stop time.

T-End Total Minutes:

WHEN the Applicant provides the form, THEN document the accuracy of the form.

The form is accurate:

The form is NOT accurate:

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Terminating cue:

The JPM is completed once the Emergency Notification form is filled out, signed and dated.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

A9 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

A Site Area Emergency has been declared by the Control Room and the Immediate Notification form completed. You are the Off

-site Emergency Manager and the Dose Assessment Coordinator has provided you with a dose assessment (EDCP).

Initiating Cue:

Develop the appropriate Emergency Notification for

m. THIS IS A TIME CRITICAL TASK

.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 9 Facility: WCGS Task No: APE024004 Task Title:

Establishing Alternate Boration Flow path starting at Step A7 of OFN BG-009, EMERGENCY BORATION. Job Performance Measure No:

P1 (AP) Rev 0 K/A

Reference:

APE 024 AA 1.20

- Ability to operate and or monitor the following as they apply to emergency boration

- Manual boration valve and indicators.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Initial Conditions:

The plant was in MODE 1. The Reactor has tripped but 3 control rods failed to fully insert. The Control room is currently implementing EMG ES

-02, REACTOR TRIP RESPONSE, and the RO is performing OFN BG

-009, EMERGENCY BORATION. Attempts to establish any Emergency Boration flow from the Control Room have failed. Task Standard:

Upon completion of this JPM the operator will have established Alternate Boration Flow through BG HV

-177 per OFN BG-009, EMERGENCY BORATION, Attachment A. Required Materials:

PPE appropriate for Auxiliary Building Watchstander. OFN BG-009, EMERGENCY BORATION General

References:

OFN BG-009, EMERGENCY BORATION, Rev 25 Initiating Cue:

You are the Aux Building Operator. The Control Room Supervisor directs you to perform Attachment 'A' beginning at step A7 of OFN BG

-009 and establish Manual Boration. Time Critical Task:

NO Alternate Path:

YES Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 2 of 9 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step A7.a Establish Manual Boration:

a. Pump Suction Isolation Valve.

o BG-DOORWAY) Standard: Examinee located valve BG

-V177 in the 'A' Safety Injection Pump Rm. (1974 el. Aux. bldg)

Examinee broke lock tab

Examinee turned handwheel counter

-clockwise Cue: After examinee describes Unlocking and Opening the valve:

CUE: Handwheel is turning Counter

-clockwise, stem is rising.

Stem is fully extended.

Score: SAT or UNSAT SAT or UNSAT Comment: BG-V177 is a diaphragm valve with rising stem.

Appendix C 2 Form ES-C-1 Page 3 of 9 Examiner NOTE:

ALTERNATE SUCCESS PATH

- Flow indicated will be zero on the gage. Performance Step:

2 Step A7.b Establish Manual Boration:

b. Check Normal Boration Flow

- GREATER THAN 30 GPM o BG FR-110 Red Pen RNO: Go to step A9.

Standard: Examinee should check if flow is >30 gpm by calling the Control Room Examinee went to step A9 Cue: After examinee contacts the Control Room to check flow:

CUE: "Flow indicates zero."

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

3 Step A9 P - o BG PDI-108 Standard: Examinee locates BG PDI

-108 on the 2000 el Aux bldg, Filter room hallway, on West wall.

Examinee read BG PDI

-108 Cue: After examinee locates indicator and explains checking for P: Note: Use pen or other pointing device to show where the needle is and let the examinee tell you what the indicator is reading.

CUE: Place pen or pointing device to the indicated pressure of 2 5 PSID Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 9 Examiner NOTE:

Performance Step:

4 Step A9 RNO a. Bypass Boric Acid Filter:

a. Open Boric Acid Filter Bypass Upstream Isolation Valve.

o BG-V173 - OPEN (1974' AUX ROOM A) Standard: Examinee locates BG

-V173 on the 1974 el Aux bldg. Valve is located in the 'A' BAT room on the South wall.

Examinee turned handwheel counter

-clockwise.

Cue: CUE: Handle is turning Counter

-clockwise, stem is rising.

The stem is fully extended.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

5 Step A9 RNO b. Bypass Boric Acid Filter:

b. Open Boric Acid Filter Bypass Downstream Isolation Valve.

o BG-V172 - , BORIC ACID TANK ROOM A) Standard: Examinee locates BG

-V172 on the 1974 el Aux bldg. Valve is located in the 'A' BAT room on the South wall.

Examinee turned handwheel counter-clockwise Cue: CUE: Handle is turning Counter

-clockwise, stem is rising.

The stem is fully extended.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 9 Examiner NOTE:

By closing this valve this starts the alternate boration flow to the RCS.

Performance Step:

6 Step A9 RNO c Bypass Boric Acid Filter:

c. Close boric acid filter to BAT "A" throttle valve.

o BG-V319 - TANK ROOM A)

Standard: Examinee locates BG

-V319 on the 1974 el Aux bldg. Valve is located in the 'A' BAT room on the South wall.

Examinee removed locking tab.

Examinee turned handwheel clockwise Cue: CUE: Handle is turning clockwise, stem is inserting.

The handle will no longer turn.

Stem is fully inserted.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

7 Step A9 RNO d. Bypass Boric Acid Filter:

d. Close Boric Acid Filter Inlet Isolation Valve.

o BG-V149 - Standard: Examinee locates BG

-149 on the 2000 el Aux bldg, Filter room hallway, above filter room.

Examinee removed lock tab.

Examinee turned reach rod handwheel clockwise.

Cue: CUE: Handwheel is turning clockwise Position indicator is moving downward.

Handwheel is turning with post indicator full down.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 9 Examiner NOTE:

Performance Step:

8 Step A9 RNO e. Bypass Boric Acid Filter:

e. Close Boric Acid Filter Outlet Isolation Valve.

o BG-V152 - Standard: Examinee locates BG

-152 on the 2000 el Aux bldg, Filter room hallway, above filter room. *Examinee removed lock tab

Examinee turned reach rod handwheel clockwise.

Cue: CUE: Handwheel is turning clockwise, the position indicator is moving downward.

The handwheel is turning with position indicator full down.

Score: SAT or UNSAT SAT or UNSAT Comment:

Examiner NOTE:

Performance Step:

9 Step A9 RNO f. Bypass Boric Acid Filter:

f. Direct Maintenance to change filter as soon as possible.

Standard: Cue: WHEN examinee contacts Control Room or Maintenance to change filter THEN: CUE: "Maintenance has been contacted to change filter."

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 9 Examiner NOTE:

Performance Step:

10 Step A10 Check If Alternate Boration Flow Has Been Established:

Normal Boration Flow

- GREATER THAN 30 GPM o BG FR-110 Red Pen OR

Emergency Boration Flow

- GREATER THAN 30 GPM o BG FI-183A Standard: Examinee contacts the Control Room Cue: After examinee contacts the Control Room:

CUE: Flow on BG FR-110 is 72 GPM Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed when flow is indicated on BG FR

-110 greater than 30 gpm. STOP TIME:

Appendix C 3 Form ES-C-1 Page 8 of 9 Verification of Completion Job Performance Measure No.

P1 (A P) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

The plant was in MODE 1. The Reactor has tripped but 3 control rods failed to fully insert. The Control room is currently implementing EMG ES

-02, REACTOR TRIP RESPONSE, and the RO is performing OFN BG

-009, EMERGENCY BORATION. Attempts to establish any Emergency Boration flow from the Control Room have failed. Initiating Cue:

You are the Aux Building Operator. The Control Room Supervisor directs you to perform Attachment 'A' beginning at step A7 of OFN BG

-009 and establish Manual Boration.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 9 Facility: WCGS Task No: APE068008 Task Title:

Perform the Turbine Bldg Operators actions of OFN RP

-017 to trip the RCPs and remove control power to the breakers. Job Performance Measure No:

P2 (TSA) Rev 0 K/A

Reference:

APE 068 AK3.18, Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation: Actions contained in EOP for control room evacuation emergency task Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the examinee:

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

Initial Conditions:

You are the operator designated to perform Turbine Building actions in OFN RP-017. The announcement to evacuate the control room and entry into OFN RP

-017 has just been made and the Reactor has been tripped.

Task Standard:

Upon completion of this JPM the Applicant will have tripped the RCPs locally and removed control power from the associated breakers.

Required Materials:

PPE appropriate for Turbine Building Watchstander. OFN RP 017, Attachment B, Rev 47, High security key for entry into the security cage for PK01 & PK02, OR pictures of PK41 and PK62.

General

References:

OFN RP-017, Rev 47

. AI 16-007, Rev 8A , AI 21-017 d, Rev 5A (PSA OPA-EVAC-CR) Initiating Cue:

Perform your designated OFN RP-017 actions through step B5. THIS IS A TIME SENSITIVE TASK. MINIMIZE YOUR VERBALIZATION

. Time Critical Task:

Yes Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 9 Alternate Path:

NO Validation Time:

7 Minutes Appendix C 2 Form ES-C-1 Page 3 of 9 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

FOR CONSISTENCY, START THE JPM FROM THE AREA NEXT TO THE ELEVATOR ON 2033' COMMUNICATIONS CORRIDOR. This step provides the cue to start the JPM. Start the stop watch. Performance Step:

1 Step 4.a. Announce the evacuation of the Control Room due to fire and entry into OFN RP

-017, using Plant Gaitronics handset.

Standard: Recognized requirement to perform OFN RP

-017 duties.

Cue: Cue: Announcement of control room evacuation due to OFN RP 017 entry and Reactor Trip.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 9 Examiner NOTE: Per AI 16-007, WCNOC Electrical Safety Manual, Operating the breaker locally with the door closed and latched requires natural fabric or FR clothing worn under Flash Suit (Coat, Pants and Hood). These are located in the emergency locker. The Applicant should simulate donning the apparel.

Steps B1 and B2 are immediate action steps.

Performance Step:

2 Step B1. Locally Trip RCPs:

o PA0107 For RCP A

- TRIPPED o PA0108 For RCP B

- TRIPPED o PA0205 For RCP C

- TRIPPED o PA0204 For RCP D

- TRIPPED Standard: Located emergency locker and donned Flash Suit.

Located RCP breakers.

Locally tripped all four RCPs by memory.

Cue: WHEN Applicant locates emergency locker and describes donning Flash Suit, THEN: Cue: Flash Suit donned.

WHEN Applicant locates breaker and simulates turning pistol grip counterclockwise, THEN: Cue: Green light lit, red light off, load clu nk noise heard.

Repeat cue for each breaker.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 9 Examiner NOTE:

Steps B1 and B2 are immediate action steps.

Performance Step:

3 Step B2. Proceed To 2033 Turbine And Obtain A Copy Of This Procedure Standard: Obtained procedure from emergency locker on 2033' level of Turbine Building.

Cue: WHEN Applicant describes acquiring the procedure, THEN: Provide a copy of the procedure to the Applicant.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 Step B3. Perform The following:

a. Obtain the following from emergency locker:

o Radio o Flashlight

b. Obtain pocket ion chambers and an RDD from the emergency locker for personnel entering the RCA:

o Low-Range PIC 0

-1000 mR o High-Range PIC 0

-5 R o RDD c. Select Channel 1 on radio. Standard: Obtained required equipment.

Cue: WHEN Applicant describes obtaining the proper equipment, THEN: Cue: Radio, flashlight, dosimetry, and radio have been obtained. Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 9 Examiner NOTE:

PK41 is located inside a security cage requiring a security key and permission to enter.

IF permission to enter the security cage was granted, THEN Applicant will simulate taking the breaker to OFF at panel PK41. OTHERWISE provide Picture 1 WHEN Applicant indicates where PK41 is located.

Performance Step:

5 Step B4. On PK41, Open Breaker For DC Control Power To PA01.

o PK4103 - OFF Standard: Entered security cage and located PK41.

Turned PK4103 to OFF.

Cue: WHEN Applicant simulates positioning handle down to the OFF position, THEN: Cue: Breaker indicates OFF.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 9 Examiner NOTE:

PK62 is located inside a security cage requiring a security key and permission to enter. IF permission to enter the security cage was granted, THEN Applicant will simulate taking the breaker to OFF at panel PK62. OTHERWISE provide Picture 2 WHEN Applicant indicates where PK62 is located.

Performance Step:

6 Step B5. On PK62, Open Breaker For DC Control Power To PA02.

o PK6204 - OFF Standard: Entered security cage and located PK62.

Turned PK6204 to OFF.

Cue: WHEN Applicant simulates positioning handle down to the OFF position, THEN: Cue: Breaker indicates OFF.

Stop the stop watch.

Record Time:

Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed when RCPs are tripped with control power removed.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 8 of 9 Verification of Completion Job Performance Measure No.

P2 (TSA) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

You are the operator designated to perform Turbine Building actions in OFN RP-017. The announcement to evacuate the control room and entry into OFN RP

-017 has just been made and the Reactor has been tripped.

Initiating Cue:

Perform your designated OFN RP

-017 actions through step B5. THIS IS A TIME SENSITIVE TASK. MINIMIZE YOUR VERBALIZATION.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 18 Facility: WCGS Task No: APE057007 Task Title:

Energize Bus NN01 from NN15.

Job Performance Measure No:

P3 - A Rev 0 K/A

Reference:

APE 057 AA1.01, Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual inverter swapping.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the examinee:

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

Initial Conditions:

The crew is responding to a loss of NN01, which was powered from inverter NN11 prior to the bus loss. NN11 bypass transformer did NOT energize NN01. Task Standard:

At the completion of the JPM, the Applicant will have energized bus NN01 from NN15 on the bypass transformer via the static switch

. Required Materials:

General

References:

OFN NN-021, Rev 25.

Initiating Cue:

The CRS has dispatched you to perform Attachment E, beginning with step E.4.3.3, to energize bus NN01 from NN15.

Inform the Control Room when NN01 is energized NN15 on the bypass transformer via the static switch.

The NN15 manual transfer switch Kirk Keys and NK79 transfer switch key are in your possession.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 2 of 18 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step E.4.3.3.

IF indicator light NN15 ALIGNED TO NK01 is NOT LIT, THEN ALIGN NN15 to NK01 as follows:

a. PLACE NK HS-15, NK01/NK03 TRANSFER SWITCH CONTROL HANDSWITCH in NK01 position.

o NK HS NK01 Standard: Located NK79.

Recognized indicator light NN15 ALIGNED TO NK01 is NOT LIT. Placed NK HS

-15 to NK01 position.

Cue: WHEN Applicant locates NN15 aligned to NK01 light, THEN: Cue: Light NOT lit.

WHEN Applicant describes inserting the key into NK HS

-15 and selecting NK01 position, THEN: Cue: Key is inserted. Key is turned in the NK01 direction.

Score: SAT or UNSAT SAT or UNS AT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 18 Examiner NOTE:

Performance Step:

2 Step E.4.3.4.

VERIFY indicator light NN15 ALIGNED TO NK01 is lit.

Standard: Verified indicator light NN15 aligned to NK01 lit.

Cue: WHEN Applicant locates light indicator, THEN: Cue: NN15 aligned to NK01 light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

3 Step E.4.3.5.

VERIFY SWING INV NN15 white pilot light is lit.

Standard: Located NN15.

Verified NN15 white pilot light lit.

Cue: WHEN Applicant locates pilot light, THEN: Cue: White pilot light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 18 Examiner NOTE:

Performance Step:

4 Step E.4.4.

STARTUP NN15 swing inverter as follows:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

5 Step E.4.4.1.

TEST NN15 lamps by depressing the PRESS TO TEST LIGHTS button while inspecting lamps.

a. PRESS TO TEST LIGHTS

- DEPRESSED b. LAMPS - ALL LIT Standard: Tested NN15 lamps.

Cue: WHEN Applicant locates press to test lights button and describes depressing button and inspecting lamps, THEN: Cue: Lamps all lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 18 Examiner NOTE:

Performance Step:

6 Step E.4.4.2.

CLOSE NN15 B1, DC INPUT BREAKER as follows:

a. DEPRESS and HOLD the PRECHARGE pushbutton.

o PRECHARGE BUTTON

- DEPRESSED and HELD

b. WHEN PRECHARGE light is lit, THEN CLOSE B1 breaker.

1) PRECHARGE LIGHT

- LIT 2) B1 - ON c. WHEN DC INPUT BREAKER CLOSED light is lit, THEN RELEASE PRECHARGE pushbutton.

1) DC INPUT BREAKER CLOSED

- LIT 2) PRECHARGE PUSHBUTTON

- RELEASED Standard: Depressed and held precharge pushbutton.

Placed NN15 B1 to on when precharge light lit.

Released precharge pushbutton when DC input breaker closed light lit.

Cue: WHEN Applicant locates and describes depressing and holding precharge button, THEN: Cue: Precharge button depressed and held. Precharge light lit.

WHEN Applicant locates and describes placing NN15 B1 to ON, THEN: Cue: Switch is in UP position. DC input breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 18 Examiner NOTE: Performance Step:

7 Step E.4.4.3.

RECORD DC INPUT VOLTS from NNEI0151.

o NNEI0151 volts __________VDC Standard: Recorded DC input voltage of 125 VDC

. Cue: WHEN Applicant locates NNEI0151 THEN: CUE: Point to the 125 VDC value. Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

8 Step E.4.4.4.

CLOSE NN15 B701, AC INPUT TO BYPASS CVT breaker.

o B701 - ON Standard: Placed NN15 B701 to ON.

Cue: WHEN Applicant locates and describes placing NN15 B701 to ON, THEN: Cue: Switch is in UP position. AC input to bypass CVT breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 18 Examiner NOTE:

Performance Step:

9 Step E.4.4.5. CLOSE NN15 B4, BYPASS INPUT TO STATIC SWITCH breaker. o B4 - ON Standard: Placed NN15 B4 to ON.

Cue: WHEN Applicant locates and describes placing NN15 B4 to ON, THEN: Cue: Switch is in UP position. Bypass input to static switch breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 Step E.4.4.6.

CLOSE NN15 B2, INVERTER OUTPUT breaker.

o B2 - ON Standard: Placed NN15 B2 to ON.

Cue: WHEN Applicant locates and describes placing NN15 B2 to ON, THEN: Cue: Switch is in UP position. Inverter output breaker RED light is lit. Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 18 Examiner NOTE:

Performance Step:

11 Step E.4.4.7.

RESET inverter alarms by pressing the ALARM RESET pushbutton.

o ALARM RESET

- PRESSED Standard: Reset alarms.

Cue: WHEN Applicant locates and describes depressing alarm reset, THEN: Cue: Alarm reset depressed.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

12 Step E.4.4.8.

VERIFY the following alarms clear.

o OVER TEMPERATURE

- CLEAR (RED) o DC LOW VOLTAGE

- CLEAR (RED) o DC HIGH VOLTAGE - CLEAR (RED) o OUT OF SYNC

- CLEAR (RED) o INVERTER OUTPUT LOW VOLTAGE

- CLEAR (RED) o FUSE BLOWN

- CLEAR (RED) Standard: Verified alarms clear.

Cue: WHEN Applicant locates and inspects alarms, THEN: Cue: Alarm lights NOT lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 18 Examiner NOTE:

Performance Step:

13 Step E.4.4.9.

WHEN NNEI0152 indicates between 112.1 VAC to 123.9 VAC, THEN continue. Standard: Recognized NNEI0152 indicated between 112.1 VAC to 123.9 VAC. Cue: WHEN Applicant locates NNEI0152, THEN: Cue: Point to the 120 VAC demarcation.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

14 Step E.5. At NN15, ensure NN15 static switch in bypass source supplying load position as follows:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 18 Examiner NOTE:

Performance Step:

15 Step E.5.1.

IF BYPASS SOURCE SUPPLYING LOAD light is NOT lit, THEN perform the following:

Standard: Recognized bypass source supplying load light is NOT lit. Cue: WHEN Applicant locates bypass source supplying load light, THEN: Cue: Light NOT lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

16 Step E.5.1.1 VERIFY NN15 IN SYNC light is lit.

Standard: Verified NN15 in sync light lit.

(GREEN) Cue: WHEN Applicant locates in sync light, THEN: Cue: Light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 18 Examiner NOTE:

Performance Step:

17 Step E.5.1.2.

DEPRESS NN15 BYPASS SOURCE TO LOAD pushbutton.

o BYPASS SOURCE TO LOAD

- DEPRESSED Standard: Depressed NN15 bypass source to load pushbutton.

Cue: WHEN Applicant locates and describes depressing bypass source to load pushbutton, THEN: Cue: Pushbutton depressed.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

18 Step E.5.1.3 Verify BYPASS SOURCE SUPPLYING LOAD

- LIT Standard: Verified bypass source supplying load light lit.

Cue: WHEN Applicant locates bypass source supplying load light, THEN: Cue: Light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 18 Examiner NOTE:

Performance Step:

19 Step E.6. PERFORM the following to energize NN01 or transfer load from NN11 to NN15, as applicable:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

20 Step E.6.1.

At NN15, UNLOCK BOTH Kirk Key locks.

o KIRK KEY LOCKS

- UNLOCKED Standard: Unlocked both Kirk Key locks.

Cue: WHEN Applicant locates the Kirk keys locks, describes inserting and turning the keys and describes the shafts retracting, THEN: Cue: Keys are inserted and turned; shafts are retracted.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 18 Examiner NOTE:

Performance Step:

21 Step E.6.2.

PLACE NN15 MANUAL TRANSFER SWITCH in AC OUTPUT TO NN011 position.

o MANUAL TRANSFER SWITCH

- AC OUTPUT TO INVERTER NN011 Standard: Placed NN15 manual transfer switch to NN01 position.

Cue: WHEN Applicant describes turning the transfer switch to the left, THEN: Cue: Switch is positioned to the left with the arrow pointing left. AC output to inverter NN011 amber light lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

22 Step E.6.3.

LOCK NN15 Kirk Key locks AND REMOVE the keys.

1. KIRK KEY LOCKS

- LOCKED 2. KEYS - REMOVED Standard: Locked Kirk Keys and removed keys.

Cue: WHEN Applicant describes turning the keys and describes the shafts extending and removing the keys, THEN: Cue: Keys are removed and shafts are extended.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 14 of 18 Examiner NOTE:

Performance Step:

23 Step E.6.4.

Inform Control Room that NN01 will be energized or transferred to NN15 on the bypass transformer, as applicable.

Standard: Contacted control room.

Cue: WHEN contacted THEN: Cue: Acknowledge report.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

24 Step E.6.5 At NN11, perform the following:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 15 of 18 Examiner NOTE:

Performance Step:

25 Step E.6.5.1.

PLACE NN11 MANUAL TRANSFER SWITCH in SWING INVERTER TO LOAD POSITION.

o MANUAL TRANSFER SWITCH

- SWING INVERTER TO LOAD Standard: Placed manual transfer switch to swing inverter to load position. Cue: WHEN Applicant locates NN11 manual transfer switch and describes selecting swing inverter to load position, THEN: Cue: Switch is positioned to the right with the arrow pointing to Swing Inverter To Load amber light lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

26 Step E.6.5.2 IF NN01 was energized from NN11 bypass transformer, THEN perform the following:

a. Place MAINTENANCE BYPASS SWITCH in NORMAL o MAINTENANCE BYPASS SWITCH

- NORMAL b. OPEN NN11 B701, AC INPUT TO BYPASS CVT breaker.

o NN11 B701

- OFF Standard: Recognized from initial conditions that NN01 was NOT energized from NN11 bypass transformer.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 16 of 18 Examiner NOTE:

Performance Step:

27 Step E.6.6.

Inform Control Room that NN01 is energized from NN15 on the bypass transformer via the static switch.

Standard: Reported NN01 energized from NN15 on the bypass transformer via the static switch.

Cue: WHEN contacted THEN: Cue: Acknowledge report.

Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once NN11 MANUAL TRANSFER SWITCH is in SWING INVERTER TO LOAD POSITION

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 17 of 18 Verification of Completion Job Performance Measure No.

P3 NN01 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

The crew is responding to a loss of NN01, which was powered from inverter NN11 prior to the bus loss. NN11 bypass transformer did NOT energize NN01. Initiating Cue:

The CRS has dispatched you to perform Attachment E, beginning with step E.4.3.3, to energize bus NN01 from NN15.

Inform the Control Room when NN01 is energized NN15 on the bypass transformer via the static switch.

The NN15 manual transfer switch Kirk Keys and NK79 transfer switch key are in your possession.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 18 Facility: WCGS Task No: APE057007 Task Title:

Energize Bus NN02 from NN16.

Job Performance Measure No:

P3-B Rev 0 K/A

Reference:

APE 057 AA1.01, Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual inverter swapping.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the examinee:

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

Initial Conditions:

The crew is responding to a loss of NN02, which was powered from inverter NN12 prior to the bus loss. NN12 bypass transformer did NOT energize NN02 Task Standard:

At the completion of the JPM, the Applicant will have energized bus NN02 from NN16 on the bypass transformer via the static switch.

Required Materials:

PPE appropriate for turbine building watchstander. OFN NN

-021, Rev 25.

General

References:

OFN NN-021, Rev 25.

Initiating Cue:

The CRS has dispatched you to perform Attachment G, beginning with step G.4.3.3, to energize bus NN02 from NN16.

Inform Control Room when NN02 is energized from NN16 on the bypass transformer via the static switch.

The NN16 manual transfer switch Kirk Keys and NK80 transfer switch key are in your possession.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

20 Minutes Appendix C 2 Form ES-C-1 Page 2 of 18 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step G.4.3.3.

IF indicator light NN16 ALIGNED TO NK02 is NOT LIT, THEN ALIGN NN16 to NK02 as follows:

a. PLACE NK HS

-16, NK02/NK04 TRANSFER SWITCH CONTROL HANDSWITCH in NK02 position.

o NK HS NK02 Standard: Located NK80.

Recognized indicator light NN16 ALIGNED TO NK02 is NOT LIT. Placed NK HS

-16 to NK02 position.

Cue: WHEN Applicant locates NN16 aligned to NK02 light, THEN: Cue: Light NOT lit.

WHEN Applicant describes inserting the key into NK HS

-16 and selecting NK02 position, THEN: Cue: Key is inserted. Key is turned in the NK02 direction.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 18 Examiner NOTE:

Performance Step:

2 Step G.4.3.4.

VERIFY indicator light NN16 ALIGNED TO NK02 is lit. Standard: Verified indicator light NN16 aligned to NK02 lit.

Cue: WHEN Applicant locates light indicator, THEN: Cue: NN16 aligned to NK02 light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

3 Step G.4.3.5.

VERIFY SWING INV NN16 white pilot light is lit.

Standard: Located NN16.

Verified NN16 white pilot light lit.

Cue: WHEN Applicant locates pilot light, THEN: Cue: White pilot light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 18 Examiner NOTE:

Performance Step:

4 Step G.4.4.

STARTUP NN16 swing inverter as follows:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

5 Step G.4.4.1.

TEST NN16 lamps by depressing the PRESS TO TEST LIGHTS button while inspecting lamps.

a. PRESS TO TEST LIGHTS

- DEPRESSED b. LAMPS - ALL LIT Standard: Tested NN16 lamps.

Cue: WHEN Applicant locates press to test lights button and describes depressing button and inspecting lamps, THEN: Cue: Lamps all lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 18 Examiner NOTE:

Performance Step:

6 Step G.4.4.2.

CLOSE NN16 B1, DC INPUT BREAKER as follows:

a. DEPRESS and HOLD the PRECHARGE pushbutton.

o PRECHARGE BUTTON

- DEPRESSED and HELD

b. WHEN PRECHARGE light is lit, THEN CLOSE B1 breaker.

1) PRECHARGE LIGHT

- LIT 2) B1 - ON c. WHEN DC INPUT BREAKER CLOSED light is lit, THEN RELEASE PRECHARGE pushbutton.

1) DC INPUT BREAKER CLOSED

- LIT 2) PRECHARGE PUSHBUTTON

- RELEASED Standard: Depressed and held precharge pushbutton.

Placed NN16 B1 to on when precharge light lit.

Released precharge pushbutton when DC input breaker closed light lit.

Cue: WHEN Applicant locates and describes depressing and holding precharge button, THEN: Cue: Precharge button depressed and held. Precharge light lit.

WHEN Applicant locates and describes placing NN16 B1 to ON, THEN: Cue: Switch is in UP position. DC input breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 18 Examiner NOTE:

Performance Step:

7 Step G.4.4.3.

RECORD DC INPUT VOLTS from NNEI0161.

o NNEI0161 volts __________VDC Standard: Recorded DC input voltage.

Cue: When applicant locates NNEI0161 then CUE: Point to the 125 VAC value.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

8 Step G.4.4.4.

CLOSE NN16 B701, AC INPUT TO BYPASS CVT breaker.

o B701 - ON Standard: Placed NN16 B701 to ON.

Cue: WHEN Applicant locates and describes placing NN16 B701 to ON, THEN: Cue: Switch is in UP position. AC input to bypass CVT breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 18 Examiner NOTE:

Performance Step:

9 Step G.4.4.5.

CLOSE NN16 B4, BYPASS INPUT TO STATIC SWITCH breaker. o B4 - ON Standard: Placed NN16 B4 to ON.

Cue: WHEN Applicant locates and describes placing NN16 B4 to ON, THEN: Cue: Switch is in UP position. Bypass input to static switch breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 Step G.4.4.6.

CLOSE NN16 B2, INVERTER OUTPUT breaker.

o B2 - ON Standard: Placed NN16 B2 to ON.

Cue: WHEN Applicant locates and describes placing NN16 B2 to ON, THEN: Cue: Switch is in UP position. Inverter output breaker RED light is lit. Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 18 Examiner NOTE:

Performance Step:

11 Step G.4.4.7.

RESET inverter alarms by pressing the ALARM RESET pushbutton.

o ALARM RESET

- PRESSED Standard: Reset alarms.

Cue: WHEN Applicant locates and describes depressing alarm reset, THEN: Cue: Alarm reset depressed.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

12 Step G.4.4.8.

VERIFY the following alarms clear.

o OVER TEMPERATURE

- CLEAR o DC LOW VOLTAGE

- CLEAR o DC HIGH VOLTAGE

- CLEAR o OUT OF SYNC

- CLEAR o INVERTER OUTPUT LOW VOLTAGE

- CLEAR o FUSE BLOWN

- CLEAR Standard: Verified alarms clear.

Cue: WHEN Applicant locates and inspects alarms, THEN: Cue: Alarm lights NOT lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 18 Examiner NOTE:

Performance Step:

13 Step G.4.4.9.

WHEN NNEI0162 indicates between 112.1 VAC to 123.9 VAC, THEN continue. Standard: Recognized NNEI0162 indicated between 112.1 VAC to 123.9 VAC. Cue: WHEN Applicant locates NNEI0162, THEN: Cue: Point to the 120 VAC value.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

14 Step G.5. At NN16, ensure NN16 static switch in bypass source supplying load position as follows:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 18 Examiner NOTE:

Performance Step:

15 Step G.5.1.

IF BYPASS SOURCE SUPPLYING LOAD light is NOT lit, THEN perform the following:

Standard: Recognized bypass source supplying load light is NOT lit. Cue: WHEN Applicant locates bypass source supplying load light, THEN: Cue: Light NOT lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

16 Step G.5.1.1 VERIFY NN16 IN SYNC light is lit.

Standard: Verified NN16 in sync light lit.

Cue: WHEN Applicant locates in sync light, THEN: Cue: Light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 18 Examiner NOTE:

Performance Step:

17 Step G.5.1.2.

DEPRESS NN16 BYPASS SOURCE TO LOAD pushbutton.

o BYPASS SOURCE TO LOAD

- DEPRESSED Standard: Depressed NN16 bypass source to load pushbutton.

Cue: WHEN Applicant locates and describes depressing bypass source to load pushbutton, THEN: Cue: Pushbutton depressed.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

18 Step G.5.1.3 Verify BYPASS SOURCE SUPPLYING LOAD

- LIT Standard: Verified bypass source supplying load light lit.

Cue: WHEN Applicant locates bypass source supplying load light, THEN: Cue: Light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 18 Examiner NOTE: Performance Step:

19 Step G.6. PERFORM the following to energize NN02 or transfer load from NN12 to NN16, as applicable:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

20 Step G.6.1.

At NN16, UNLOCK BOTH Kirk Key locks.

o KIRK KEY LOCKS

- UNLOCKED Standard: Unlocked both Kirk Key locks.

Cue: WHEN Applicant locates the Kirk keys locks, describes inserting and turning the keys and describes the shafts retracting, THEN: Cue: Keys are inserted and turned; shafts are retracted Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 18 Examiner NOTE:

Performance Step:

21 Step G.6.2.

PLACE NN16 MANUAL TRANSFER SWITCH in AC OUTPUT TO NN012 position.

o MANUAL TRANSFER SWITCH

- AC OUTPUT TO INVERTER NN012 Standard: Placed NN16 manual transfer switch to NN012 position.

Cue: WHEN Applicant describes turning the transfer switch to the left, THEN: Cue: Switch is positioned to the left with the arrow pointing left. AC output to inverter NN012 amber light lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

22 Step G.6.3.

LOCK NN16 Kirk Key locks AND REMOVE the keys.

1. KIRK KEY LOCKS

- LOCKED 2. KEYS - REMOVED Standard: Locked Kirk Keys and removed keys.

Cue: WHEN Applicant describes turning the keys and describes the shafts extending and removing the keys, THEN: Cue: Keys are removed and shafts are extended.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 14 of 18 Examiner NOTE:

Performance Step:

23 Step G.6.4.

Inform Control Room that NN02 will be energized or transferred to NN16 on the bypass transformer, as applicable.

Standard: Contacted control room.

Cue: WHEN contacted THEN: Cue: Acknowledge report.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

24 Step G.6.5 At NN12, perform the following:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 15 of 18 Examiner NOTE:

Performance Step:

25 Step G.6.5.1.

PLACE NN12 MANUAL TRANSFER SWITCH in SWING INVERTER TO LOAD POSITION.

o MANUAL TRANSFER SWITCH

- SWING INVERTER TO LOAD Standard: Placed manual transfer switch to swing inverter to load position. Cue: WHEN Applicant locates NN12 manual transfer switch and describes selecting swing inverter to load position, THEN: Cue: Switch is positioned to the right with the arrow pointing to Swing Inverter To Load amber light lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

26 Step G.6.5.2 IF NN02 was energized from NN12 bypass transformer, THEN perform the following:

a. Place MAINTENANCE BYPASS SWITCH in NORMAL o MAINTENANCE BYPASS SWITCH

- NORMAL b. OPEN NN12 B701, AC INPUT TO BYPASS CVT breaker.

o NN12 B701

- OFF Standard: Recognized from initial conditions that NN02 was NOT energized from NN12 bypass transformer.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 16 of 18 Examiner NOTE:

Performance Step:

27 Step G.6.6.

Inform Control Room that NN02 is energized from NN16 on the bypass transformer via the static switch.

Standard: Reported NN02 energized from NN16.

Cue: WHEN contacted THEN: Cue: Acknowledge report.

Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once NN1 2 MANUAL TRANSFER SWITCH is in SWING INVERTER TO LOAD POSITION.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 17 of 18 Verification of Completion Job Performance Measure No.

P3-B Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

The crew is responding to a loss of NN02, which was powered from inverter NN12 prior to the bus loss. NN12 bypass transformer did NOT energize NN02 Initiating Cue:

The CRS has dispatched you to perform Attachment G, beginning with step G.4.3.3, to energize bus NN02 from NN16. Inform Control Room when NN02 is energized from NN16 on the bypass transformer via the static switch.

The NN16 manual transfer switch Kirk Keys and NK80 transfer switch key are in your possession.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 15 Facility: WCGS Task No: 400011 Task Title:

Transfer From the NCP to a CCP. Job Performance Measure No:

S1 (AP) Rev 0 K/A

Reference:

004 A2.22, Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Mismatch of letdown and changing flows.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. The Plant is in MODE 1 with the Service loop on "B" Train.

Task Standard:

Upon completion of this JPM, the Applicant will re-establish charging from the NCP when CCP 'B' trips as BG FK-462 is lowered to < 40% output.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 15 Required Materials:

SYS BG-201, Rev 65 and ALR 00-042E, Rev 13 Simulator Setup:

IC 30 (or equivalent with yellow train CCW in service and CCP 'B' in standby) ENSURE NPIS trend for CCP 'B' is displayed.

SCN File: S1 (ASP).scn

S1 (ASP) ;CCP 'B' trips when BG FK

-462 is < 40%

{x01d124m<.4} ICM bkrNB00201 t:1

end file BOOTH: ENSURE NPIS trend for CCP B is closed before resetting into another JPM.

General References

SYS BG-201, Rev 65, ALR 00

-042E, Rev 13 Initiating Cue:

The Control Room Supervisor directs you to start the 'B' CCP and secure the NCP, per 6.2 of SYS BG

-201, to support maintenance on the NCP next shift. Prerequisites of SYS BG

-201 are complete. CCP "B" boron concentration is 20 ppm greater than RCS boron concentration

. Time Critical Task:

NO Alternate Path:

YES Validation Time:

20 Minutes Appendix C 2 Form ES-C-1 Page 3 of 15 Performance Information Denote critical steps with a check mark

() START TIME:

Examiner NOTE:

Performance Step:

1 STEP 6.2.1 IF the Boron Thermal Regeneration System is in service, THEN SHUTDOWN the BTRS in accordance with SYS BG

-205, BORON THERMAL REGENERATION SYSTEM OPERATION.

Standard: Recognized that BTRS is NOT in service and N/Ad step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 STEP 6.2.2 PLACE BG HIS

-129, CVCS DEMIN INLET DIVERT VLV to VCT. o BG HIS-129 - VCT Standard: Depressed the "VCT" pushbutton BG HIS-129 to lock it down.

VCT red light is lit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 15 Examiner NOTE:

This is a continuous action step (Maintain) and the Applicant may make adjustments throughout the JPM. Performance Step:

3 Step 6.2.3 MAINTAIN RCP Seal Injection flow between 8 and 13 gpm, by adjusting BG HC

-182, CHG HDR BACK PRESS CTRL:

o BG FR-157 - BETWEEN 8 AND 13 GPM o BG FR-156 - BETWEEN 8 AND 13 GPM o BG FR-155 - BETWEEN 8 AND 13 GPM o BG FR-154 - BETWEEN 8 AND 13 GPM Standard: Adjusted (if required) BG HC-182 to maintain seal injection 8

-13 gpm per pump.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 6.2.4 ENSURE BG FK

-121, CCP DISCH FLOW CTRL is in manual and set at 20%.

o BG FK-121 - IN MANUAL AND SET AT 20%

Standard: Verified BG FK

-121 set to MANUAL with 20% output.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 15 Examiner NOTE:

Performance Step:

5 STEP 6.2.5 ENSURE BG HV

-8111, CCP B RECIRC VLV is open, using BG HIS-8111, CCP B RECIRC VLV.

o BG HIS-8111 - OPEN Standard: Verified BG HIS-8111 Red light is lit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

6 STEP 6.2.6 ENSURE Component Cooling Water is being supplied to CCP B. Standard: EG HIS-22 and EG HIS

-24 Verified CCW pump B running by the Red light lit on the handswitch.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 15 Examiner NOTE:

Performance Step:

7 STEP 6.2.7 IF RCS temperature is greater than or equal to 200°F, THEN ENSURE BG-8483A, CCP A DISCH HDR FCV

-121 INLET ISO is locked closed.

o BG-8483A - LOCKED CLOSED Standard: Recognized blue placard indicates valve is locked closed OR Contacted the Aux Watch to verify BG-8483A is locked closed.

OR Asked CRS to check Locked Component Log.

Cue: IF contacted, THEN: Cue: (Building Watch) BG

-8483A is locked closed

. OR Cue: (CRS) Locked Component Log indicates BG

-8483A is locked closed

. Score: SAT or UNSAT SAT or UNSAT Comment: If an IV is requested reply: Another RO will perform IV.

Examiner NOTE:

Performance Step:

8 STEP 6.2.8 ENSURE CCP Discharge BG FCV

-121 isolated placard is attached to BG HIS

-1A handswitch.

Standard: Located placard on BG HIS

-1A handswitch.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 15 Examiner NOTE:

Performance Step:

9 STEP 6.2.9 ENSURE BG-8483C, CCP B DISCH HDR FCV

-121 INLET ISO is unlocked and open.

o BG-8483C - UNLOCKED/OPEN Standard: Recognized blue placard indicates valve is locked closed OR Contacted the Aux Watch to verify BG

-V8483C is unlocked open. OR Asked CRS to check Locked Component Log.

Cue: IF contacted, THEN: Cue: (Building Watch)

BG-8483C is unlocked open.

OR Cue: (CRS) Locked Component Log indicates BG

-8483C is unlocked open.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 STEP 6.2.10 ENSURE BG HIS

-2AX, CCP B AUX L-O PUMP is in auto.

o BG HIS-2AX - AUTO Standard: Verified BG HIS-2AX switch in AUTO and the Red light lit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 15 Examiner NOTE:

Performance Step:

11 STEP 6.2.11 Prior to starting CCP B, START and MONITOR a NPIS computer trend, (including the following points, and any other available and desired points that monitor pump operation) to ensure proper pump operation and system response: (3.1.4.3) o BGI0017 CHG PUMP B AMP o BGP0120 CHG HDR PRESS o BGF0121 CHG HDR FLOW Standard: Verified NPIS trend and data points available.

Cue: If asked to monitor NPIS cue: BOP will monitor NPIS Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

IF Applicant does not ask for direction, THEN provide Cue.

Performance Step:

12 6.2.12 IF desired, THEN RAISE Charging and Letdown flow, as follows: Standard: Asked CRS for direction.

Cue: Cue: Leave charging and letdown flow as is. Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 15 Examiner NOTE:

This is a reactivity step and Operator should indicate the need for a peer check (Management Expectation

- but not critical).

Performance Step:

13 STEP 6.2.13 -2A, CCP B.

o BG HIS-2A - NORMAL-AFTER-RUN Standard: Started the pump by turning the switch BG HIS-2A to RUN. Verified the Red light comes on and the Green light goes out.

Cue: Cue (If asked):

Acknowledge pump start.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

14 STEP 6.2.14 IF BG FK-462, NORMAL CHG PMP FLOW CTRL is in auto, THEN PLACE it in manual.

o BG FK-462 - MANUAL Standard: Placed BG FK

-462 in MANUAL verified red Manual light is lit Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 15 Examiner NOTE:

Per AP 21-001, Conduct Of Operations, Two handed control board operations may be performed with CRS permission. Two handed operation is the act of manipulating two controllers simultaneously.

Performance Step:

15 STEP 6.2.15 PERFORM the following simultaneously:

o LOWER BG FK

-462, NORMAL CHG PMP FLOW CTRL to 20% output.

o BG FK-462 - LOWERED TO 20%

o ADJUST BG FK-121, CCP DISCH FLOW CTRL, to maintain constant Charging header flow.

o BG FK-121 - ADJUSTED Standard: Requested two handed operation.

Used BG FK

-462 and BG FK

-121 and performed these actions in such a way to maintain a constant charging flow.

Cue: Cue (If asked): Acknowledge and give Permission for simultaneous board action.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 15 Examiner NOTE:

ALTERNATE SUCCESS PATH.

WHEN BG FK-462 controller output is < 40%, THEN CCP 'B' will trip.

Steps 1-3 of ALR 00 042E are Memory Action steps and the Applicant may perform them before receiving the ALR.

Performance Step:

16 Annunciator 00

-042E alarming.

Standard: Announce d Annunciator 42E and that CCP 'B' has tripped.

Cue: WHEN CCP 'B' trips AND ANN 42E is in alarm, THEN: Cue: Annunciator 42E is in alarm.

(only if applicant does not acknowledge)

WHEN applicant reports the CCP has tripped, THEN: Cue: Acknowledge report. Provide examinee with copy of ALR 00-042E and state "Perform the ALR."

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Steps 1 through 3 are Memory Action steps and can be performed without the procedure, but are NOT required to be done without the procedure.

Performance Step:

17 ALR 00-042E, STEP 1 Check Previously Running Pumps

- TRIPPED o BG HIS-1A for CCP A o BG HIS-2A For CCP B o BG HIS-3 for NCP Standard: Recognized that CCP 'B' has tripped.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 15 Examiner NOTE:

This step is a Memory Action step and can be performed without the procedure, but is NOT required to be done without the procedure.

Performance Step:

18 ALR 00-042E, STEP 2 Check Charging Pumps

- NONE RUNNING o BG HIS-1A for CCP A o BG HIS-2A For CCP B o BG HIS-3 For NCP Standard: Recognized that the NCP is still running by the Red light lit on BG HIS-3 and/or flow indicated on BG FI

-121A Performed RNO.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

This step is a Memory Action step and can be performed without the procedure, but is NOT required to be done without the procedure.

Performance Step:

19 ALR 00-042E, STEP 2 RNO a Perform the Following:

a. Adjust charging and letdown flow, as necessary, to maintain PZR level at program.

Standard: Adjusted BG FK

-462 as necessary to stabilize PZR level.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 15 Examiner NOTE:

Performance Step:

20 ALR 00-042E, STEP 2 RNO b Return to procedure and step in effect.

Standard: ALR 00-042E completed.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant has control of BG FK

-462 and is stabilizing PZR level

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 14 of 15 Verification of Completion Job Performance Measure No.

S1 (AP) Examinee's Name:

Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. The Plant is in MODE 1 with the Service loop on "B" Train.

Initiating Cue:

The Control Room Supervisor directs you to start the 'B' CCP and secure the NCP, per 6.2 of SYS BG

-201, to support maintenance on the NCP next shift. Prerequisites of SYS BG

-201 are complete. CCP "B" boron concentration is 20 ppm greater than RCS boron concentration

.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 12 Facility: WCGS Task No: APE026001 Task Title:

Respond to the loss of CCW flow to the Service Loop.

Job Performance Measure No:

S2 (AP) Rev 0 K/A

Reference:

APE 026 AK3.03, Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: Guidance actions contained in EOP for Loss of CCW.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. The Plant is stable in MODE 1. The 'B' CCW pump has tripped. 'D' CCW pump is tagged out.

Task Standard:

At the completion of the JPM, the Applicant will have tripped the reactor , tripped the RCPs, isolated letdown and reduced charging to the seals only.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 12 Required Materials:

OFN EG-004, Rev 18.

Simulator Setup:

IC 302 (IC 30 with malfunctions included)

Hang Test/Caution tag on EG HIS

-24 (D - CCW pump) SCN File S2 (ASP).scn (Included in IC)

S2 (ASP) ; Tagout 'D' CCW pump ICR bkrDPEG01D t: 2 d:0

EG HV-15 & 53 failed closed ICM movEGHV0015 t: 2 d:0 ICM movEGHV0053 t:2 d:0

'B' CCW pump tripped ICM bkrDPEG01B t: 1

End File General

References:

OFN EG-004, Rev 18.

Initiating Cue:

The Control Room Supervisor directs you to respond using OFN EG-004, CCW SYSTEM MALFUNCTIONS.

Time Critical Task:

NO Alternate Path:

YES Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 3 of 12 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 OFN EG-004 , Step 1. Check CCW Pumps

- ONE RUNNING IN EACH INTACT TRAIN Standard: Proceeded to RNO step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Per AP 21-001, Conduct Of Operations, an announcement is made when starting the pump.

Performance Step:

2 Step 1.a. RNO Start CCW Pump(s), as necessary, to establish one running in each intact train.

Standard: Started 'A' or 'C' CCW pump using handswitch e s EG HIS-21 or 23 Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 12 Examiner NOTE:

Performance Step:

3 Step 1.b. RNO IF a CCW Pump in the train aligned to the service loop can NOT be started AND alternate CCW train pump is operating, THEN shift service loop to alternate CCW train:

1) Open service loop CCW supply and return valves for train not supplying service loop.

EG ZL-15 And EG ZL

-53For Train A o EG HS-15

EG ZL-16 And EG ZL

-54 For Train B o EG HS-16 2) Close service loop CCW supply and return valves for train previously supplying service loop.

EG ZL-15 And EG ZL

-53 For Train A o EG HS-15

EG ZL-16 And EG ZL

-54 For Train B o EG HS-16 Standard: Attempted to open service loop supply and return valves and reported that EG HV

-15 and EG HV

-53 will NOT open Cue: If asked as the CRS cue: Continue with procedure Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 12 Examiner NOTE:

The Applicant may proceed directly to step 2 without performing RNO step 1.c.

Performance Step:

4 Step 1.c. RNO Ensure CCW aligned to the following:

o RCP Thermal Barriers o RHR, if required o Spent Fuel Pool Cooling Standard: Recognized this step CANNOT be done.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

ALTERNATE SUCCESS PATH Performance Step:

5 Step 2. Check Service Loop

- ALIGNED TO RUNNING CCW PUMP Standard: Recognized service loop CANNOT be aligned.

Proceeded to RNO step. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 12 Examiner NOTE:

Per AP 21-001, Conduct Of Operations, an announcement is made when tripping the reactor.

Performance Step:

6 Step 2.a. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Trip reactor.

Standard: Tripped the reactor.

Cue: Cue: Acknowledge reactor trip.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

The Applicant continues with the procedure. Immediate actions are performed by the rest of the crew.

Performance Step:

7 Step 2.b. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Stabilize the plant, using EMGs while continuing with this procedure.

Standard: Recognized that EMG E

-0 is entered.

Cue: Cue: Continue with the OFN while the crew responds to the reactor trip.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 12 Examiner NOTE:

Performance Step:

8 Step 2.c. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Trip RCPs.

Standard: Tripped all four RCPs.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Isolating excess letdown is NOT critical as it is NOT in service. The letdown orifice isolation valves must be closed in order to close BG HV

-459 and BG HV

-460. Performance Step:

9 Step 2.d. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Isolate letdown and excess letdown.

Standard: Closed letdown orifice isolation valves.

Closed BG HV

-459 and BG HV

-460. Recognized that excess letdown is NOT in service.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 12 Examiner NOTE:

Performance Step:

10 Step 2.e. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Isolate seal return flow.

BG HIS-8100

BG HIS-8112 Standard: Closed BG HV

-8100 and BG HV

-8112. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

BG HV-8109 is expected to open when charging flow is reduced to minimum.

Performance Step:

11 Step 2.f RNO IF no CCW Pump can supply service loop, THEN perform the following:

Reduce charging to minimum and charge only to the seals.

Standard: Adjusted BG FK

-462 to obtain charging flow to the seals only. Ensured 8 gpm minimum seal injection flow to each RCP.

Closed BG HC

-182. Cue: WHEN Applicant requests two handed operation for adjusting charging, THEN: Cue: Two handed operation is allowed.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 12 Examiner NOTE:

Performance Step:

12 Step 2.g. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Ensure charging supplied by the NCP or from CCP on the intact CCW Train.

Standard: Recognized that the NCP is supplying charging.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

13 Step 2.h. RNO IF no CCW Pump can supply service loop, THEN perform the following:

IF unable to supply CCW cooling to a safety train, THEN supply cooling to one train of CCP and SI Pump, using ATTACHMENT A, ALTERNATE COOLING FOR CCP AND SI PUMPS.

Standard: Recognized that 'A' train CCW is supplying cooling to 'A' train safety components, so step is NA.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 12 Examiner NOTE:

Performance Step:

14 Step 2.i. RNO Return to procedure and step in effect.

Standard: Returned to EMG E

-0. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the reactor is tripped, the RCPs are tripped, letdown is isolated, seal return flow is isolated and charging is reduced to minimum flow to the RCP seals.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 11 of 12 Verification of Completion Job Performance Measure No.

S2 (AP) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. The Plant is stable in MODE 1. The 'B' CCW pump has tripped. 'D' CCW pump is tagged out.

Initiating Cue:

The Control Room Supervisor directs you to respond using OFN EG

-004, CCW SYSTEM MALFUNCTIONS.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 12 Facility: WCGS Task No: E02001 Task Title:

Isolation of BIT IAW EMG ES

-03. Job Performance Measure No:

S3 Rev 0 K/A

Reference:

E02 EA1.1 Ability to operate and / or monitor the following as they apply to the (SI Termination): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. The crew has mitigated a fault on 'A' S/G and has entered EMG ES

-03, SI TERMINATION.

Task Standard:

At the end of the JPM, the Applicant will have aligned the CCPs for normal charging and isolated the BIT, restoring partial control of RCS pressure by reducing ECCS flow.

Required Materials:

EMG ES-03, SI TERMINATION, Rev 24.

Simulator Setup:

IC 301 (or equivalent; IC contains all malfunction, etc.)

SCN File S3.scn

S3 ; Steamline break on S/G 'A' IMF mAB03A f: 3.2e+006 r:60

Open BG-8483A For CCP A IRF rBG35A f: 100 r:30 k:1

Close BG

-8483C IRF rBG35C f:0 r:30 k:2

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 12 General

References:

EMG ES-03, SI TERMINATION, Rev 24.

Initiating Cue:

The CRS directs you to reduce ECCS flow IAW EMG ES

-03, SI TERMINATION, beginning at step 1.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 12 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step 1. Reset SI. o SB HS-42A o SB HS-43A Standard: Depressed both reset buttons.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Only the reset s of the containment isolation Phase A are critical. Performance Step:

2 Step 2. Reset Containment Isolation Phase A And Phase B:

o SB HS-56 For Phase A o SB HS-53 For Phase A o SB HS-55 For Phase B o SB HS-52 For Phase B Standard: Depressed CISA and CISB reset buttons.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 12 Examiner NOTE:

Performance Step:

3 Step 3. Verify Instrument Air Compressor Is Running:

Standard: Recognized Instrument Air Compressors already aligned.

Verified alignment.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE: Depending on how long the PORV has been cycling BB PK-455A may still be saturated and have an output less than 55%. Performance Step:

4 Step 4. Verify Instrument Air To Containment:

a. Check PZR PRESS MASTER CTRL Output

- LESS THAN 55% o BB PK-455A b. Open INST AIR SPLY CTMT ISO VLV.

o KA HIS-29 Standard: Ensured BB PK

-455A output less than 55%.

Opened KA HIS

-29. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 12 Examiner NOTE:

Only step 5.b. is critical. It is expected that the CCP with the blue placard attached is stopped.

Performance Step:

5 Step 5. Reduce Charging Flow:

a. Check Shutdown Sequencers

- NOT ACTUATED o Annunciator 00

-018C, NF039A S/D SEQ ACTUATED

- CLEAR o Annunciator 00

-021C, NF039B S/D SEQ ACTUATED

- CLEAR b. Stop all but one CCP and place in standby.

BG HIS-1A OR

BG HIS-2A Standard: Verified Shutdown Sequencers not actuated.

Stopped CCP with blue placard attached and left in normal after stop.

Cue: Cue (if asked):

Stop the CCP with the blue placard attached.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

6 Step 6. Check If NCP Should Be Stopped:

a. CCPs - ANY RUNNING

b. Stop NCP. o BG HIS-3 Standard: Recognized that the NCP was stopped previously.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 12 Examiner NOTE:

Pressure will be fluctuating as the PORV cycles.

Performance Step:

7 Step 7. Check RCS Pressure

- STABLE OR INCREASING Standard: Recognized RCS Pressure trend is stable for conditions.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

CCW is already aligned. Performance Step:

8 Step 8. Verify CCW To Service Loop:

Standard: Verified CCW alignment to Service Loop.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: CCW is currently aligned to service loop no actions are required Appendix C 2 Form ES-C-1 Page 7 of 12 Examiner NOTE:

CCW is already aligned.

Performance Step:

9 Step 9. Verify CCW To Containment:

Standard: Verified CCW alignment to Containment.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: CCW is currently aligned to containment no actions are required Examiner NOTE:

CCW is already aligned.

Performance Step:

10 Step 10. Verify RCP Thermal Barrier Cooling:

Standard: Verified RCP Thermal Barrier cooling.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: RCP thermal barrier cooling is aligned no actions are required

Appendix C 2 Form ES-C-1 Page 8 of 12 Examiner NOTE:

Performance Step:

11 Step 11. Align CCPs For Normal Charging:

a. Check CCPs

- AT LEAST ONE RUNNING

BG HIS-1A

BG HIS-2A b. Check CCP Discharge To Charging Header Isolation Valve For Running CCP

- OPEN

BG-8483A For CCP A (1974' AUX BLDG, CCP A ROOM)

BG-8483C For CCP B (1974' AUX BLDG, CCP B ROOM) c. Reset CCP Recirc Valves.

o BG HS-8110 o BG HS-811 1 d. Open CCP Recirc Valves.

o BG HIS-8110 o BG HIS-8111 Standard: Verified CCP running.

Verified CCP discharge isolation valve open by one of the following:

Contacted local operator, Asked CRS to check locked valve log, OR Absence of blue placard.

Depressed CCP recirc valve reset buttons.

Opened CCP recirc valves.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 12 Examiner NOTE:

One of the valves, BG HV

-8146 or 8147, will already be open and the other will be closed.

Performance Step:

12 Step 12. Align Charging System:

a. Throttle CCP Discharge Flow Control valve to 7% open.

o BG FK-121 b. Close Charging Header Back Pressure Control valve.

o BG HC-182 c. Open Charging Pumps To Regenerative Heat Exchanger Containment Isolation valves.

o BG HIS-8105 o BG HIS-8106 d. Align Regenerative Heat Exchanger To Loop Cold Leg valves, to establish only one open.

BG HIS-8146 For Loop 1

BG HIS-8147 For Loop 4 Standard: Throttled BG FK

-121 to ~ 7% open.

Closed BG HC-182. Opened BG HIS

-8105 and 8106.

Verified BG HIS

-8146 or 8147 open.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 12 Examiner NOTE:

Closing either the BIT Inlet valves OR the BIT Outlet valves , meets the critical task.

Performance Step:

13 Step 13. Isolate BIT:

a. Close BIT Inlet Valves.

o EM HIS-8803A o EM HIS-8803B b. Close BIT Outlet Valves.

o EM HIS-8801A o EM HIS-8801B Standard: Closed BIT Inlet and Outlet valves.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the BIT Inlet and Outlet valves are closed.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 11 of 12 Verification of Completion Job Performance Measure No.

S3 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. The crew has mitigated a fault on 'A' S/G and has entered EMG ES

-03, SI TERMINATION.

Initiating Cue:

The CRS directs you to reduce ECCS flow IAW EMG ES

-03, SI TERMINATION, beginning at step 1.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 10 Facility: WCGS Task No: 4100003 Task Title:

Respond to failed open steam dumps. Job Performance Measure No:

S4 (AP) Rev 0 K/A

Reference:

041 A4.08, Ability to manually operate and/or monitor in the control room: Steam dump valves.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator; GEN 00

-002 is in progress and step 6.21.3.3 has been completed. An extra Reactor Operator is monitoring SG levels. Task Standard:

At the completion of the JPM, the Applicant will have mitigated the effects of the failure of AB PT

-507 on the steam dump system AND placed ARVs in auto with 1125 psig setpoint

. Required Materials:

SYS AB-120, Rev 32.

General

References:

SYS AB-120, Rev 32. AP 21

-001, Rev 72.

Initiating Cue:

The CRS directs you to align the Steam Dumps and ARVs for automatic operation as required by step 6.21.3.4 of GEN 00

-002 using SYS AB

-120 step 6.2. Time Critical Task:

NO Alternate Path:

YES Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 2 of 10 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step 6.2. Align Steam Dump System For Operation Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step 6.2.1.

Set STEAM HDR PRESS CTRL potentiometer at 7.28 (1092 psig). o AB PK-507 - SET AT 7.28 Standard: Adjusted the potentiometer clockwise until it indicated 7.28 turns. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 10 Examiner NOTE:

Performance Step:

3 Step 6.2.2.

Place STEAM DUMP SEL switch to steam pressure.

o AB US-500Z - STEAM PRESSURE Standard: Located AB US

-500Z Verified the Steam Pressure position (right).

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 Step 6.2.3.

Place STEAM DUMP BYPASS INTERLOCK switches to BYP/INTLK and spring return on.

o AB HS SELECTED TO BYPASS INTERLOCK o AB HS SELECTED TO BYPASS INTERLOCK Standard: Located AB HS

-63 Actuated to the BYP/INTLK position (right) and allowed to spring return to ON.

Red flag. Located AB HS

-64 Actuated to the BYP/INTLK position (right) and allowed to spring return to ON.

Red flag. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 10 Examiner NOTE:

Performance Step:

5 Step 6.2.4.

Verify STEAM DUMP CTRL BYPASS light is lit.

o AB HL LIT Standard: Located AB HL

-81 Verified White light lit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

6 Step 6.2.5.

Place STEAM DUMP COOLDOWN CTRL in auto.

o AB UK AUTO Standard: Located AB UK

-33 Depressed the AUTO PB.

Verified steam dump cooldown valves closed.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 10 Examiner NOTE:

ALTERNATE SUCCESS PATH AB PI-507 fails high when AB PK

-507 taken to AUTO at this step and the cooldown dump valves will open.

Per AP 21-001, Conduct of Operations, In the event of a failure of a controller where manual control must be taken, the CRS shall immediately be made aware of the status after manual control is established.

Performance Step:

7 Step 6.2.6.

Place STEAM HDR PRESS CTRL in auto. o AB PK-507 - AUTO Standard: Located AB PK

-507 Determined the status of the system:

WHEN AB PK

-507 is placed in AUTO, THEN noted that steams dumps OPENED.

Depressed the MANUAL PB on AB PK

-507 to regain control.

Depressed the down arrow to close valves OR Turned either or both BYP/INTLK switches (AB HK

-63 and 64) to OFF. OR Depressed the MANUAL PB on AB UK

-33 to regain control. Manipulated joystick to left to CLOSE steam dump valves.

Monitored Steam Dump valve CLOSURE on AB ZI

-34, AB ZI-45 and AB ZI-41. Reported failure to CRS.

Cue: WHEN the failure is reported, THEN: Cue: Acknowledge failure (and actions).

Cue: The WC SRO will report the instrument failure.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 10 Examiner NOTE:

Performance Step:

8 Step 6.2.7.

Set SG STEAM DUMP TO ATMS CTRLS at 1125 psig.

o AB PIC-1A - SET AT 1125 PSIG o AB PIC-2A - SET AT 1125 PSIG o AB PIC-3A - SET AT 1125 PSIG o AB PIC-4A - SET AT 1125 PSIG Standard: Located ARV Manipulated thumbwheel upward direction until the pointer indicated 1125 psig.

AB PIC-1A - SET AT 1125 PSIG Located ARV Manipulated thumbwheel upward direction until the pointer indicated 1125 psig.

AB PIC-2A - SET AT 1125 PSIG.

Located ARV Manipulated thumbwheel upward direction until the pointer indicated 1125 psig.

AB PIC-3A - SET AT 1125 PSIG.

Located ARV Manipulated thumbwheel upward direction until the pointer indicated 1125 psig.

AB PIC-4A - SET AT 1125 PSIG.

Cue: IF Applicant requests peer check or verification, THEN: Cue: Acknowledge request.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 10 Examiner NOTE:

Performance Step:

9 Step 6.2.8.

Place SG STEAM DUMP TO ATMS CTRLS in auto.

o AB PIC-1A - AUTO o AB PIC-2A - AUTO o AB PIC-3A - AUTO o AB PIC-4A - AUTO Standard: Located ARV Placed AB PIC

-1A ARV controller in auto by depressing the AUTO PB. AUTO White light lit.

Located ARV Placed AB PIC

-2A ARV controller in auto by depressing the AUTO PB. AUTO White light lit.

Located ARV.

Placed AB PIC

-3A ARV controller in auto by depressing the AUTO PB. AUTO White light lit.

Located ARV Placed AB PIC

-4A ARV controller in auto by depressing the AUTO PB. AUTO White light lit.

Cue: IF Applicant requests peer check or verification, THEN: Cue: Acknowledge request.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 10 Examiner NOTE:

Performance Step:

10 Step 6.2.9.

Section 6.2, Align Steam Dump System For Operation, complete. Standard: Reported to the CRS that the step is not complete due to instrument failure.

Cue: WHEN the report is made, as CRS, THEN: Cue: The WC SRO will report the instrument failure.

Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the steam dumps are closed following the malfunction AND ARVs are set at 1125 psig and in auto

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 9 of 10 Verification of Completion Job Performance Measure No.

S4 (AP) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator; GEN 00

-002 is in progress and step 6.21.3.3 has been completed. An extra Reactor Operator is monitoring SG levels. Initiating Cue:

The CRS directs you to align the Steam Dumps and ARVs for automatic operation as required by step 6.21.3.4 of GEN 00

-002 using SYS AB

-120 step 6.2.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 20 Facility: WCGS Task No: EPE055002 Task Title:

Restore power to NB02 using the SBO diesels.

Job Performance Measure No:

S5 (AP) Rev 0 K/A

Reference:

EPE 055 EA2.03, Ability to determine or interpret the following as they apply to a Station Blackout: Actions necessary to restore power.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. 'B' EDG OOS for governor replacement. Severe weather has caused a loss of offsite power. The reactor tripped. The crew entered EMG C

-0, LOSS OF ALL AC POWER. Power has been restored to the switchyard.

XNB01 transformer and NB01 bus has sustained damage and ar e unavailable.

Task Standard:

At the completion of the JPM, the Applicant will have placed safeguards equipment in PTL prior to energizing NB02 from the SBO diesels.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 20 Required Materials:

OFN N B-030, REV 33A. SYS KU

-122, REV 5

. Simulator Setup:

IC 304 (IC 30 with malfunctions etc.)

Place Test/Caution tag on KJ HS

-10 8A SCN File S5.scn

S5 (ASP)

Tagout 'A' EDG scn SimGroup

\TAGDGB ; XNB01 Fault 30 IMF mNB06A i:

-1 f:-1 ; Loss of offsite power 35 IMF mSY01 i:

-1 f:-1 ; NB01 fault 40 IMF mNB03 i:

-1 f:-1 ; Re store power to west bus from the Benton line 4 4 DMF mSY01 4 5 IRF rSY01 f:1

Breaker NB0209 fails to close 47 ICM bkrNB00209 t: 2

Shutdown 'A' EDG 48 scn SimGroup

\SHTDNDGA {Key[1]} scn SimGroup

\NF39B 8N28 OFF ; End File General

References:

OFN NB-030, Rev 33A. SYS KU-122, Rev 5

. Initiating Cue:

The CRS directs you to energize NB02 AC emergency bus from offsite power using OFN NB

-030, LOSS OF AC EMERGENCY BUS NB01 (NB02), beginning at step B14.

Inform the CRS when NB02 is re

-energized.

Time Critical Task: NO Alternate Path:

YES Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 20 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step B14. Check NB02 Bus Status: o Annunciator 00

-021A, NB02 BUS LOCKOUT

- CLEAR Standard: Recognized that annunciator 00

-021A is clear.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

NOTE: From the initial conditions, the 'B' EDG is OOS. Applicant may NOT contact the local operator for this step as it has no relev a nce at this time.

Performance Step:

2 Step B15. Check NB02 EDG Status:

o Annunciator 502

-07D, GENERATOR PROTECTIVE RELAY - CLEAR Standard: Contacted local watchstander for status.

Cue: WHEN contacted, THEN: Cue: Annunciator 502

-07D is clear.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 20 Examiner NOTE:

Performance Step:

3 Step B16. Check Emergency Diesel NE02

- RUNNING Standard: Recognize from initial conditions that 'B' EDG is OOS.

Proceeded to step B16 RNO.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 Step B16. RNO Perform the following:

a. IF SM/CRS directs that NB02 be energized from a source other than the diesel, THEN go to:

Step B19 for normal offsite power via XNB02

Step B21 for alternate offsite power via XNB01

Step B24 for SBO Diesel Generators Standard: Recognize from initial conditions that NB02 is to be energized from offsite power.

Recognized that the normal offsite power supply is the only one available.

Proceeded to step B19.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 20 Examiner NOTE:

Performance Step:

5 Step B19. Check Normal Offsite Power Supply

- AVAILABLE a. Check Annunciator 00

-022A, XNB02 XFMR LOCKOUT

- CLEAR b. Check ESF Transformer XNB02

- ENERGIZED BY OFFSITE POWER Standard: Recognized that annunciator 00

-022A is clear.

Recognized that XNB02 is energized from offsite power.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 20 Examiner NOTE:

ALTERNATE SUCCESS PATH Performance Step:

6 B20. Reenergize NB02 From Normal Offsite Power Supply:

a. Place NB02 Normal Supply Sync Transfer switch to ON position. o NB HS-8 b. Place 4.16 KV BUS NB02 SYNC

-SCOPE SEL to Main FDR BRKR position.

o NB HS-11 c. Check BUS NB02 VOLTAGE INCOMING SOURCE

- NORMAL o NB EI-29 d. Close NB02 Normal Supply Breaker NB0209.

o NB HIS-4 Standard: Placed NB HS

-8 to ON. Placed NB HS

-11 to Main FDR BRKR position.

Checked NB EI

-29 voltage NORMAL

. Recognized that NB HIS

-4 failed to close. Reported failure to CRS.

Cue: WHEN Applicant reports failure of NB HIS

-4, THEN: Cue: I will contact electrical maintenance. Continue efforts to restore power to NB02.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 20 Examiner NOTE:

Performance Step:

7 Step B20 Reenergize NB02 From Normal Offsite Power Supply:

e. Place NB02 Normal Supply Sync Transfer switch to OFF o NB HS-8 f. Place 4.16 KV Bus NB01 Sync

-Scope SEL to OFF.

o NB HS-11 g. Check NB02

- Energized g. RNO Go To step B21 Standard: Recognized NB02 is not energized

. Proceeded to step B21

. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

8 Step B 21 Check Alternate Offsite Power Supply

- Available a. Check plant in mode

- 5, 6, or defueled a.RNO Go to step B24 Standard: Proceeded to step B24.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 20 Examiner NOTE:

Performance Step:

9 B24. Reenergize NB02 From SBO Diesel Generators:

o Reenergize NB02 per SYS KU

-122, ENERGIZING NB02 FROM STAION BLACKOUT DIESEL GENERATORS Standard: Recognize that SYS KU

-122 will be used to reenergize NB02.

Located SYS KU

-122. Cue: WHEN Applicant locates SYS KU

-122, THEN provide copy of SYS KU-122. Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 SYS KU-122, Step 6.1 Energizing NB02 From SBO DGs Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 20 Examiner NOTE:

Panel NF039B is NOT available in the simulator.

After providing the cue, direct the booth operator to select Key 1. Performance Step:

11 Step 6.1.1 In NF039B, ROTATE power switch NF39B 8N28

-1, on bottom panel, to off.

o NF39B 8N28 OFF Standard: Ensured NF39B 8N28

-1 OFF. Cue: WHEN the Applicant starts to proceed behind the control room panels, THEN: Cue: I will contact the BOP to place switch in OFF.

WHEN booth operator action is completed, THEN: Cue: NF39B 8N28

-1 is OFF. Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

12 Step 6.1.2 ENSURE the following handswitches in pull

-to-lock: Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 20 Examiner NOTE:

Pump will start when bus is reenergized if not placed in PTL. Performance Step:

13 Step 6.1.2 Component 1.

AL HIS-22A, MD AFP B.

o AL HIS-22A - PULL-TO-LOCK Standard: Placed AL HIS-22A in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Pump will start when bus is reenergized if not placed in PTL. Performance Step:

14 Step 6.1.2 Component 2.

BG HIS-2A, CCP B.

o BG HIS-2A - PULL-TO-LOCK Standard: Placed BG HIS

-2A in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 20 Examiner NOTE:

Performance Step:

15 Step 6.1.2 Component 3.

EN HIS-9, CTMT SPRAY PUMP B.

o EN HIS PULL-TO-LOCK Standard: Placed EN HIS

-9 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

16 Step 6.1.2 Component 4.

EJ HIS-2, RHR PUMP B.

o EJ HIS PULL-TO-LOCK Standard: Placed EJ HIS

-2 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 20 Examiner NOTE:

Performance Step:

17 Step 6.1.2 Component 5.

EM HIS-5, SI PUMP B.

o EM HIS PULL-TO-LOCK Standard: Placed EM HIS

-5 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

18 Step 6.1.2 Component 6.

EG HIS-22, CCW PUMP B.

o EG HIS PULL-TO-LOCK Standard: Placed EG HIS

-22 in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 20 Examiner NOTE:

Performance Step:

19 Step 6.1.2 Component 7.

EG HIS-24, CCW PUMP D.

o EG HIS PULL-TO-LOCK Standard: Placed EG HIS

-24 in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

20 Step 6.1.2 Component 8.

GN HIS-9, CTMT COOLER FAN B.

o GN HIS PULL-TO-LOCK Standard: Placed GN HIS

-9 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 14 of 20 Examiner NOTE:

Performance Step:

21 Step 6.1.2 Component 9.

GN HIS-17, CTMT COOLER FAN D.

o GN HIS PULL-TO-LOCK Standard: Placed GN HIS

-17 in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

22 Step 6.1.2 Component

10. GK HIS-40, CTRL RM A/C UNIT 4B FAN & DAMPER.

o GK HIS PULL-TO-LOCK Standard: Placed GK HIS

-40 in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 15 of 20 Examiner NOTE:

Performance Step:

23 Step 6.1.2 Component

11. GK HIS-103, CLASS I/E ELEC EQUIP A/C UNIT 5B.

o GK HIS-103 - PULL-TO-LOCK Standard: Placed GK HIS

-103 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

24 Step 6.1.2 Component

12. EF HIS-56A, ESW PUMP B.

o EF HIS-56A - PULL-TO-LOCK Standard: Placed EF HIS

-56A in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 16 of 20 Examiner NOTE:

Performance Step:

25 Step 6.1.2 Component

13. Feeder Breakers:

o NB HIS-4, NB02 NORM SPLY BKR NB0209.

o NB HIS PULL-TO-LOCK Standard: Placed NB HIS

-4 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

26 Step 6.1.2 Component

14. Feeder Breakers:

o NB HIS-5, NB02 ALT SPLY BKR NB0212.

o NB HIS PULL-TO-LOCK Standard: Placed NB HIS

-5 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 17 of 20 Examiner NOTE:

Performance Step:

27 Step 6.1.2 Component

15. Feeder Breakers:

o NE HIS-26, NB02 EMERG SPLY BKR NB0211.

o NE HIS PULL-TO-LOCK Standard: Recognized NE HIS

-26 is already in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

28 Step 6.1.3 Direct an operator to perform Attachment A, Starting SB ODGs for NB02. Standard: Contacted the Site Watch to perform SYS KU

-122, Attachment A, for energizing NB02 from the SBO DGs.

Cue: CUE: When contacted as the site watch, acknowledge request.

After site watch contacted:

CUE: Report back from the site watch that NB02 is energized from the SBO DGs.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 18 of 20 Examiner NOTE:

Performance Step:

29 Step 6.1.4 WHEN the operator confirms that NB02 has been energized from the SBO DGs per Attachment A, Starting SBO DGs for NB02, THEN return to procedure and step in affect.

Standard: Applicant recognized that NB02 was energized by the SBO DGs and reported to CRS NB02 is re- energized.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed when all listed handswitches are in PTL and the CRS is informed NB02 is energized from SBO DGs.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 19 of 20 Verification of Completion Job Performance Measure No.

S5 (A P) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. 'B' EDG OOS for governor replacement. Severe weather has caused a loss of offsite power. The reactor tripped. The crew entered EMG C

-0, LOSS OF ALL AC POWER. Power has been restored to the switchyard. XNB01 transformer and NB01 bus has sustained damage and are unavailable.

Initiating Cue:

The CRS directs you to energize NB02 AC emergency bus from offsite power using OFN NB

-030, LOSS OF AC EMERGENCY BUS NB01 (NB02), beginning at step B14. Inform the CRS when NB02 is re

-energized.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 5 Facility: WCGS Task No: 2700003 Task Title:

Start the Containment Atmospheric Control System IAW SYS GR

-120. Job Performance Measure No:

S6 Rev 0 K/A

Reference:

027 A4.01, Ability to manually operate and/or monitor in the control room: CIRS controls. Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. A Containment entry will be made next shift and HP has requested operating the Containment Atmospheric Control System to reduce the Containment airborne concentrations of radioiodine and particulates.

Task Standard:

At the completion of the JPM, the Containment Atmospheric Control System will be in service.

Required Materials:

SYS GR-120, REV 3.

General

References:

SYS GR-120, Rev 3.

Initiating Cue:

The CRS directs you to start both containment Atmospheric Control System fans IAW SYS GR

-120. All of the Prerequisites are met.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

5 Minutes Appendix C 2 Form ES-C-1 Page 2 of 5 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 6.1.1 IF directed by SM/CRS to start CTMT ATMS CTRL SYS A FAN & DAMPER, THEN PLACE GR HIS

-10, CTMT ATMS CTRL SYS A FAN &

DAMPER to normal

-after-run. o GR HIS NORMAL-AFTER-RUN Standard: Started CTMT ATMS CTRL SYS A FAN.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 6.1.2 IF directed by SM/CRS to start CTMT ATMS CTRL SYS B FAN & DAMPER, THEN PLACE GR HIS

-20, CTMT ATMS CTRL SYS B FAN & DAMPER to normal

-after-run. o GR HIS NORMAL-AFTER-RUN Standard: Started CTMT ATMS CTRL SYS B FAN. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 5 Examiner NOTE:

Performance Step:

3 6.1.3 Section 6.1, Startup Of Containment Atmospheric Control System, complete.

Standard: Completed Procedure.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed when the Containment Atmospheric Control System is in service.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 4 of 5 Verification of Completion Job Performance Measure No.

S6 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. A Containment entry will be made next shift and HP has requested operating the Containment Atmospheric Control System to reduce the Containment airborne concentrations of radioiodine and particulates.

Initiating Cue:

The CRS directs you to start both containment Atmospheric Control System fans IAW SYS GR-120. All of the Prerequisites are met.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 8 Facility: WCGS Task No: 1300010 Task Title:

Complete Attachment A Pre Test and Post Test Alignments for STS IC

-601A, SLAVE RELAY TEST K601 TRAIN A SAFETY INJECTION.

Job Performance Measure No:

S7 Rev 0 K/A

Reference:

013 A3.02, Ability to monitor automatic operation of the ESFAS including: Operation of actuated equipment.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

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

Initial Conditions:

You are the Reactor Operator. STS IC

-601A, SLAVE RELAY TEST K601 TRAIN A SAFETY INJECTION, is in progress. All prerequisites have been completed.

Task Standard: At the completion of the JPM, the Applicant will have determined component status per STS IC

-601A, Attachment A, is SAT.

Required Materials:

STS IC-601A, REV 15.

General

References:

STS IC-601A, Rev 15.

Initiating Cue:

The CRS directs you to assist I&C in completing STS IC-601A. Complete steps 8.1 and 8.2.6, I&C will perform the remainder of the procedure, including IVs. Time Critical Task:

NO Alternate Path:

NO Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 2 of 8 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step 8.1.1 Ensure all PREREQUISITES have been met.

Standard: Recognized from initial conditions that prerequisites have been completed.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step 8.1.2 Record initial condition by circling the status of the equipment listed in the AS FOUND ALIGN column of ATTACHMENT A, DATA SHEET.

[3.2.1] Standard: Circled appropriate equipment status in the as found alignment column of Attachment A.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 8 Examiner NOTE:

Performance Step:

3 Step 8.1.3 Place ESF PANEL SA066X MODE SEL in check/pull

-to-lock. o SA HS CHECK/PULL

-TO-LOCK Standard: Placed ESF PANEL SA066X MODE SEL in check/pull

-to-lock. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 8 Examiner NOTE:

Performance Step:

4 Step 8.1.4 Verify components are aligned per ATTACHMENT A, DATA SHEET: 1. Align equipment in accordance with PRE

-TEST ALIGN. column. 2. Check SA066X indications are in accordance with PRE

-TEST ALIGN. column.

Standard: Placed GL HIS-1 to stop.

Recognized that GG HIS

-38 was already in stop position.

Placed GG HIS

-39 to stop.

Recognized that GL HIS

-30 was already in stop position.

Placed GL HIS

-31 to stop.

Recognized that GG HIS

-15A was already in stop position.

Pushed and held open pushbutton for GG HIS

-41 until opened.

Pushed and held open pushbutton for GG HIS

-40 until opened.

Recognized that GL HIS

-32 was already in open position.

Checked SA066X indications are in accordance with PRE

-TEST ALIGN. column.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 8 Examiner NOTE:

Performance Step:

5 Step 8.1.5 Section 8.1, PRE

-TEST ALIGNMENT, complete.

Standard: Initialed and dated.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Steps 8.2.1 through 8.2.5 are performed by the I&

C technician.

Direct the booth operator to insert KEY 1.

Performance Step:

6 Steps 8.2.1 through 8.2.5 TEST PERFORMANCE Standard: Applicant recognized that I&C will complete steps 8.2.1 thru 8.2.5 Cue: CUE: I&C will complete steps 8.2.1 thru 8.2.5 After applicant has informed I&C to complete steps CUE: Steps 8.2.1 thru 8.2.5 are complete.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 8 Examiner NOTE:

When step 8.2.6 is completed, the JPM is completed.

Performance Step:

7 Step 8.2.6 Ensure proper component status by performing the following steps for the POST TEST ALIGN. column of ATTACHMENT A, DATA SHEET and circling Sat (S) or Unsat (U):

o Equipment is in the listed position.

o SA066X lights are in accordance with listed condition.

Standard: Verified GG HIS

-15A indicated running.

Verified 7

-5 white light lit.

Circled S for SAT.

Verified GG HIS

-40 indicated closed.

Verified 8-5 white light lit.

Circled S for SAT.

Verified GL HIS

-32 indicated closed.

Verified 3

-7 white light lit.

Circled S for SAT.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once Attachment A Post Test Alignment, step 8.2.6, has been completed

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 7 of 8 Verification of Completion Job Performance Measure No.

S7 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. STS IC

-601A, SLAVE RELAY TEST K601 TRAIN A SAFETY INJECTION, is in progress. All prerequisites have been completed.

Initiating Cue:

The CRS directs you to assist I&C in completing STS IC

-601A. Complete steps 8.1 and 8.2.6, I&C will perform the remainder of the procedure, including IVs.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 19 Facility: WCGS Task No: APE037006 Task Title:

Change GE RE

-92 setpoints on RM-11R for S/G tube leak.

Job Performance Measure No:

S8 Rev 0 K/A

Reference:

APE 037 AA1.04, Ability to operate and / or monitor the following as they apply to the Steam Generator Tube Leak: Condensate air ejector exhaust radiation monitor and failure indicator.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. The plant is operating at 100% power. The crew has entered OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE. GE RE-92 is in Alert with a reading of 1.00 E

- Task Standard:

At the completion of the JPM, the Applicant will have changed the setting for the Alert setpoint to 1.42 E

-06 + 0.1 E

-6.37E- Required Materials:

OFN BB-07A, REV 17A. SYS SP-121, REV 25A. AIF 21D

-004-01 REV 3 (PROVIDE COMPLETED COPY). CALCULATOR. STRAIGHT EDGE.

Simulator Setup:

IC 30 SCN File S5.scn ;S5 ;Set GE RE

-092 to 1e-006 IMF mSP10G f:1e

-006 ;end file Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 19 General

References:

OFN BB-07A, Rev 17A. SYS SP-121, Rev 25A. AIF 21D

-004-01 Rev 3 (Provide completed copy).

Initiating Cue:

The Control Room Supervisor directs you to perform step 7.c of OFN BB-07A, STEAM GENERATOR TUBE LEAKAGE, to change GE RE

-92 setpoints using AIF 21D-004-01, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE. Adjust the alert setpoint to 10 GPD above the current reading on the RM

-11R. Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes BOOTH/FLOOR: MUST ensure RM

-11R setpoints for GE RE

-92 are returned to their NORMAL values in-between Candidates. MUST ensure Supervisory Key is in NORMAL position in

-between Candidates. Ensure 150 GPD value correct on RM

-11R placard prior to starting JPM.

Appendix C 2 Form ES-C-1 Page 3 of 19 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 OFN BB-07A, Step 7.c.

Using the Setpoint Adjustment And Conversion Graphs From Grab Sample Results, the Conversion Factor formula on the graph or the Setpoint Adjustment And Conversion Graphs From Theoretical Monitor Response, adjust BM RE

-25, GE RE-92 and SJ RE

-02 rad monitor setpoints, as follows:

1) Adjust the alarm setpoint to 150 gpd.

2) Adjust the alert setpoint to above the current baseline reading. Standard: Recognized from initial conditions that AIF 21D

-004-01, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, will be used.

Located current AIF 21D

-004-01 form in COAF book.

Located current copy of SYS SP

-121, OPERATION OF THE G.A. MONITOR SYSTEM.

Cue: WHEN Applicant locates current AIF 21D

-004-01, THEN provide copy of graph.

WHEN Applicant locates current revision of SYS SP

-121, THEN provide copy of procedure.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 19 Examiner NOTE: Write down the value that the Applicant determines is equivalent to 150 GPD.

IF Applicant uses the Conversion Factor at the top of the form, THEN: Alarm Setpoint

= (150)(4.23E

-08) + 2.68E

-08 Alarm Setpoint

= 6.37E-06 + IF Applicant used a straight edge on the graph, THEN: Alarm Setpoint

= 6.4E-06 + Performance Step:

2 Step 7.c.1)

Determine from the Theoretical Monitor Response Graph the new alarm setpoint.

Standard: Determined new setting for 150 GPD using AIF 21D

-004-01. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 19 Examiner NOTE:

Write down the value that the Applicant determines is equivalent to 33 GPD.

IF Applicant uses the Conversion Factor at the top of the form, THEN: GPD = (1.00E 2.68E-08)/4.23E-08 GPD = 23 GPD.

New Alarm Setpoint

= (33)(4.23E-08) + 2.68E

-08. Alarm Setpoint

= 1.42 E-06 + 0.1 E- IF Applicant used a straight edge on the graph, THEN: Alarm Setpoint

= 1.4 E-06 + Performance Step:

3 Step 7.c.2)

Determine from the Theoretical Monitor Response Graph the new alert setpoint based on current reading.

Standard: Recognized from initial conditions that current reading is 1.00E

- Recognize from initiating cues that the new setting is to be 10 GPD higher than current reading.

Determined new Alert setting using AIF 21D

-004-01. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 SYS SP-121, Step 6.3 Channel Item & Release Setpoint Operations Using RM

-11R Standard: Determined correct step to use to change GE RE

-92 setpoints.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 19 Examiner NOTE:

Performance Step:

5 Step 6.3.1.

To change the value of a Supervisor RM

-80 Database Channel Item, perform the following:

Standard: Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Examiner NOTE:

Step 6.1.2 is a common task that the Applicant may do without consulting the procedure.

Performance Step:

6 Step 6.3.1.1 Select the desired channel per step 6.1.2.

Standard: Referred back to step 6.1.2.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 19 Examiner NOTE:

Performance Step:

7 Step 6.1.2.

WHEN desired grid is displayed, THEN select desired channel, as follows:

1. Key in the three digit Channel Identification Number displayed on the grid.

2. Press the SEL key.

3. Check the selected channel outlined in white.

Standard: Displayed grid 1.

Keyed in 925 for GE RE

-92. Pressed SEL key.

Verified correct channel selected. Returned to step 6.3.1 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

8 Step 6.3.1.2.

Place Supervisor Master Key in the key slot and turn it to SUPERVISOR position.

Standard: Selected supervisory position.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 19 Examiner NOTE:

Performance Step:

9 Step 6.3.1.3.

Press the LIT key.

Standard: Pressed LIT key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 Step 6.3.1.4.

Press the Grid 5 key.

Standard: Pressed grid 5 key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

11 Step 6.3.1.5.

Press the SEL key.

Standard: Pressed SEL key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 19 Examiner NOTE:

Performance Step:

12 Step 6.3.1.6.

Verify the Supervisor RM

-80 Database Screen is displayed.

Standard: Verified supervisory RM

-80 database screen is displayed.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Examiner NOTE:

Performance Step:

13 Step 6.3.1.7. Press the minus (-) key. Standard: Pressed the minus key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 19 Examiner NOTE:

The channel item for Alert setpoint is 010. The channel item for Hi (Alarm) setpoint is 009.

Performance Step:

14 Step 6.3.1.8.

Key in the desired Channel Item number.

Standard: Keyed in either 10 or

09. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

15 Step 6.3.1.9.

Press the SEL key.

Standard: Pressed SEL key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 19 Examiner NOTE:

Performance Step:

16 Step 6.3.1.10.

Check the selected Channel Item is backlit.

Standard: Checked channel item backlit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Monitor the Applicant closely and write down the value entered. Use this value for providing the step 6.3.1.13 Cue. The values keyed in should be 1, 4, 2, -, 0, 6 (+ 0.2) for channel item 010 and 6, 3, 7, -, 0, 6 (+ 0.2) for channel item 009. The Applicant should use the numbers determined in OFN BB-07A. Performance Step:

17 Step 6.3.1.11. Key in the desired Channel Item value in the correct format.

Example: 5.79E

-5 is keyed in as 5, 7, 9, -, 0, 5. Standard: Keyed in channel item value.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 19 Examiner NOTE:

Performance Step:

18 Step 6.3.1.12.

Press the ENTER key.

Standard: Pressed the enter key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

19 Step 6.3.1.13. A message area will appear at the bottom of the screen, a. IF the data in the message area is correct, THEN press the ENTER key and proceed to step 6.3.1.14.

b. IF the data in the message area is incorrect, THEN press the CLEAR key and return to step 6.3.1.11.

Standard: IF data is correct, THEN; Pressed enter key.

IF data is incorrect, THEN: Pressed clear key and returned to step 6.3.1.11.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 19 Examiner NOTE: Performance Step:

20 Step 6.3.1.14.

IF the entry is accepted, THEN the message at the bottom of the CRT will indicate value accepted and the value for that item will be updated in the RM

-80 Column and the Master Column.

Standard: Recognized that next channel item requires updated and returned to step 6.3.1.7.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

The Channel Item number may be advanced by depressing the SEL key.

Performance Step:

21 Step 6.3.1.7.

Press the minus (-) key. Standard: Pressed the minus key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 14 of 19 Examiner NOTE:

The channel item for Alert setpoint is 010. The channel item for Hi (Alarm) setpoint is 009.

Performance Step:

22 Step 6.3.1.8.

Key in the desired Channel Item number.

Standard: Keyed in either 10 or

09. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

23 Step 6.3.1.9.

Press the SEL key.

Standard: Pressed SEL key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 15 of 19 Examiner NOTE:

Performance Step:

24 Step 6.3.1.10.

Check the selected Channel Item is backlit.

Standard: Checked channel item backlit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Monitor the Applicant closely and write down the value entered. Use this value for providing the step 6.3.1.13 Cue. The values keyed in should be 1, 4, 2, -, 0, 6 (+ 0.2) for channel item 010 and 6, 3, 7, -, 0, 6 (+ 0.2) for channel item 009. The Applicant should use the numbers determined in OFN BB-07A. Performance Step:

25 Step 6.3.1.11. Key in the desired Channel Item value in the correct format.

Example: 5.79E

-5 is keyed in as 5, 7, 9, -, 0, 5. Standard: Keyed in channel item value.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 16 of 19 Examiner NOTE:

Performance Step:

26 Step 6.3.1.12.

Press the ENTER key.

Standard: Pressed the enter key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

27 Step 6.3.1.13. A message area will appear at the bottom of the screen, a. IF the data in the message area is correct, THEN press the ENTER key and proceed to step 6.3.1.14.

b. IF the data in the message area is incorrect, THEN press the CLEAR key and return to step 6.3.1.11.

Standard: IF data is correct, THEN; Pressed enter key.

IF data is incorrect, THEN: Pressed clear key and returned to step 6.3.1.11.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 17 of 19 Examiner NOTE: Performance Step:

28 Step 6.3.1.14.

IF the entry is accepted, THEN the message at the bottom of the CRT will indicate value accepted and the value for that item will be updated in the RM

-80 Column and the Master Column.

Standard: Completed updating channel items.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

29 Step 6.3.1.16.

WHEN no further changes are desired, THEN turn the Supervisor Master Key to the NORMAL position.

Standard: Turned key to normal position.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once setpoint changes have been made. NOTE: As the same actions are done to change the second setpoint, IF the examiner is satisfied that the Applicant will complete the task after the first setpoint is changed, THEN the JPM may be terminated.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 18 of 19 Verification of Completion Job Performance Measure No.

S8 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. The plant is operating at 100% power. The crew has entered OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE. GE RE-92 is in Alert with a reading of 1.00 E

- Initiating Cue:

The Control Room Supervisor directs you to perform step 7.c of OFN BB-07A, STEAM GENERATOR TUBE LEAKAGE, to change GE RE

-92 setpoints using AIF 21D-004-01, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE. Adjust the alert setpoint to 10 GPD above the current reading on the RM-11R.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 1 of 5 Rev 3 Facili t y: Wolf Creek Scenari o No.: 1 (New) O p-Tes t No.: Nov 2015 E x a miners: Opera tors: I ni t ia l Condi tions: 100% power, MOL, 'B' MDAFWP OOS for scheduled maintenance

. IC 30 Turno ver: T.S. 3.7.5 Condition B entered based on B MDAFW pump OOS. Expected return is 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Hold current power level.

E vent N o. M a l f. N o. E v ent T y p e* E vent Descr ip t io n 1. C (ATC SRO) NCP flow control valve failure low (BG FK

-462) 2. I (BOP SRO) Main feedwater header pressure detector (AE PI-508) failure high. 3. I (ATC SRO) TS (SRO) PZR level channel (BB LI-459) fails high over 30 seconds.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 2 of 5 Rev 3 4. R (ATC) TS (SRO) N (BOP SRO) Dropped rod and recovery.

5. M (ALL) Rod ejection resulting in a LOCA.

6. C (BOP) Turbine fails to trip in auto, one MSIV fails to close in auto (Note: With the turbine failing to auto trip AND one MSIV failing to auto close the component failure for the BOP will be mitigated by either manually tripping the turbine or manually closing the one open MSIV to prevent uncontrolled RCS cooldown)

7. NB01 bus faults and locks out.

(drives CT 1 for both the loss of feed and for only one train of safety related equipment available)

8. C (ALL) Turbine-driven Auxiliary Feedwater Pump (TDAFWP) fails to start due to broke trip throttle valve at the time of the reactor trip. CT1: Establish AUX feed flow (from the NSAFP) to at least ONE intact S/G at a flow rate great enough that core exit temperatures are stable or decreasing AND level in at least ONE S/G is increasing, prior to bleed and feed criteria being met.

9. Normal Charging Pump (NCP) trips on motor overload.

(this drives CT 2 with the loss of the B train CCP)

10. C (ALL) B train CCP fails to auto start (manual start available) on the SI following the small break LOCA.

CT 2: Establish flow from at least one Charging pump by the completion of EMG E-0, Attachment F.

(B CCW pump trips on reactor trip with an auto start of the D CCW pump, this is to check if the crew ensures a CCW pump is running in the same train as the CCP that will be started)

(N)ormal, (R)eacti v i t y , (I)nstrument, (C)omponent, (M)ajor A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 3 of 5 Rev 3 Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Malfunctions after EOP entry (1

-2) 3 (events 6, 8 , 10) 2. Abnormal events (2

-4) 3 (events 1,2,3

) 3. Major transients (1

-2) 1 (event 5) 4. EOPs entered/requiring substantive actions (1

-2) 1 (EMG E-1) 5. EOP contingencies requiring substantive actions (0

-2) 1 (EMG FR-H1) 6. EOP based Critical tasks (2

-3) 2 (events 8,10) 7. Critical Task Justification References CT 1: Establish AUX feed flow (from the NSAFP

) to at least ONE intact S/G at a flow rate great enough that core exit temperatures are stable or decreasing AND level in at least ONE S/G is increasing, prior to bleed and feed criteria being met. SAFETY SIGNIFICANCE

-- Failure to establish feedwater flow to any SG results in the crew having to rely upon the lower-priority action of establishing RCS bleed and feed to minimize core uncovery. This constitutes incorrect performance that fails to prevent "degradation of any barrier to fission product release."

BD EMG FR-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Rev 15, step 8 and 17 CT 2: Establish flow from at least one Charging pump b y the completion of EMG E-0, Attachment F

. (note: with a CCP in an ECCS line up, meaning after an SI actuation signal, there is no control of flow since all the flow is directed to the BIT header and flow rate is determined by RCS pressure)

The acceptable results obtained in the FSAR analysis of a small

-break LOCA are predicated on the assumption of minimum ECCS pumped injection. The flow rate values assumed for minimum pumped injection are based on operation of one each of the following ECCS pumps: Charging/SI pump (HP plants only), high

-head SI pump, and low-head SI pump.

BD EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Rev 26a, step F5

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 4 of 5 Rev 3 SCENARIO #

1 NARRATIVE Turnover: Scenario starts out at 100% power MOL. Motor Dri ven AFW p ump 'A' was tagged out for mainte n a nce activities 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ago

. Tec hnical Sp e cificati on (TS) 3.7.5, AFW system, Condit ion B.1 (r estore AFW train to OPERABLE in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) w as ent e re d. Expected return is 4 8 h ours. Event 1:

NCP flow control valve fails low (BG FK

-462). The failure will cause the running charging pump (NCP) to lower flow which will cause annunciator 41A, SEAL INJ TO RCP FLOW LO, 42A, CHG LINE FLOW HILO, and 42E, CHARGING PMP TROUBLE, to come in. The crew will enter 42 E as this will correct the problem. The RO will place BG FK

-462 in manual and restore charging flow to normal. SRO will direct the ALR to mitigate this failure.

Event 2: Main feedwater header pressure detector AE PI-508 failure high.

The failure causes the MFP speed to slow. The BOP will take manual control of MFP Turbine Master Speed Controller, FC SK-509A , and restore feed pump speed to normal value. SRO will direct OFN SB-008 , INSTRUMENT MALFUNCTIONS, Attachmen t B , STEAM OR FEEDWATER HEADER PRESSURE CHANNEL MALFUNCTION, for mitigation of the failure.

Event 3: PZR level channel BB LI

-459 fails hi over 30 seconds.

This will cause multiple alarms and PZR indicated level to rise. The crew identifies and diagnoses the level channel failure and enters OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment J, PZR LEVEL CHANNEL MALFUNCTION, to mitigate the instrument failure. TS are identified by the SRO and 3.3.1, Reactor Trip System Instrumentation, Condition A and M is entered off of table 3.3.1

-1 Function 9.

Event 4: Dropped rod and recovery.

Control rod H8 will suffer a stationary gripper failure and fall into the core. The SRO will direct recovery of the rod once the reason for the failure is resolved. The ATC will withdraw the rod OFN SF

-011, REALIGNMENT OF DROPPED RODS AND ROD CONTROL MALFUNCTIONS. SRO will enter 3.1.4, Rod Group Alignment Limits, Conditions A and B. QPTR and AFD will be monitored to determine if the T.S. limit is exceeded.

Event 5: Rod ejection resulting in a LOCA. The reactor will either be tripped manually by the crew or auto on low PZR pressure forcing the crew to enter EMG E

-0, REACTOR TRIP OR SAFETY INJECTION.

Event 6: Turbine fails to trip in auto, one MSIV fails to close in auto. BOP will either trip the turbine in manual OR close MSIVs (using AB HS

-79, and 80 OR AB HIS

-14, for the MSIV respectively). This action will be directed by EMG E

-0, REACTOR TRIP OR SAFETY INJECTION, step 2 RNO (Note: With the turbine failing to auto trip AND one MSIV failing to auto close the component failure for the BOP will be mitigated by either manually tripping the turbine or manually closing the one open MSIV to prevent uncontrolled RCS cooldown)

Event 7: At the time of the reactor trip NB0 1 bus faults and locks out.

Since this is a bus lockout the NE0 1 output breaker will not close when the EDG is up to speed and voltage as normal. This will cause a loss of all safety related A train equipment, including '

A' MDAFWP and '

A' CCP. Event 8: At the time of the reactor trip the TDAFWP fails to start due to broke trip throttle valve

. During the performance of EMG E

-0, REACTOR TRIP OR SAFETY INJECTION, the crew will diagnosis a loss of all AFW due to the 'A' MDAFWP being tagged out, loss of NB0 1 (loss of 'A' MDAFWP), and the failure of the TDAFWP to start due to broke trip throttle valve. The crew will complete the immediate actions of E-0 and will transition to EMG FR

-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, to start the NSAFP. CT1: Establish AUX feed flow (from the NSAFP) to at least ONE intact S/G prior to bleed and feed criteria being met.

Event 9: At the time of the reactor trip the NCP trips on motor overload. (This drives CT 2 with the loss of the 'B' train CCP)

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 5 of 5 Rev 3 Event 10: On the SI following the reactor trip the B train CCP fails to auto start (manual start available)

. CT 2: Establish flow from at least one Charging pump by the completion of EMG E

-0, Attachment F.

(B CCW pump trips on reactor trip with an auto start of the D CCW pump, this is to check if the crew ensures a CCW pump is running in the same train as the CCP that will be started)

Crew continues from EMG FR-H1 back to E-0 then to EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT. The crew will continue in E

-1 until SI is reset after which the scenario can be terminated

. Procedures entered:

ALR 042E, CHARGING PMP TROUBLE OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment B, STEAM OR FEEDWATER HEADER PRESSURE CHANNEL MALFUNCTION OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment J, PZR LEVEL CHANNEL MALFUNCTION OFN SF-011, REALIGNMENT OF DROPPED RODS AND ROD CONTROL MALFUNCTIONS EMG E-0, REACTOR TRIP OR SAFETY INJECTION EMG FR-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT

Scenario file:

ILO Scenario 1 scn SimGroup

\Tag B MDAFW

turbine fails to trip in auto IMF mAC02B i

-1 f:-1 ;MSIVs fail to close in auto IMF mSA27AB07 i:

-1 f:-1 ;NCP trip on reactor trip

{jpplsi} ICM bkrPB00301 t:1 d:0

B CCP fails to start in auto IMF mBG27B i

-1 f:-1 ;trip a B CCW on reactor trip

{jpplsi} ICM bkrDPEG01B t:1 d:0

NCP flow control valve fails closed in auto

- ATC IMF mBG25A f:

-50 r:10 k:1

Main feedwater header pressure detector AE PI

-508 fails high

- BOP ICM trAEPT0508 t:2 d:0 k:2

PZR level channel 459 fails hi over 30 seconds

- ATC IMF mBB22A f:100 r:30 k:3

Control rod H8 stationary gripper failure

- ATC IMF mSF04H8 f:1 k:4

{Key[5]} DMF mSF04H8 IRF rSF05 f:1 k:6

Ejected rod during recovery. NB01 faults on SIS. TDAF pump broke IMF mSF05H8 f: 800 k:7

{jpplsi} IMF mNB03 IMF mAL02 i:

-1 f:-1 ;Establish flow from Non

-Safety Related AFW Pump

{Key[8]} scn SimGroup

\Start PAP01

close TDAFP steam drains

Key 9 ;end A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 1 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 1 E v en t Descrip tion: NCP flow control valve fails low (BG FK-462) T ime Po sitio n Simulator operator: Insert Key 1 at the lead examiners direction.

Diagnostics: PZR (RCS) pressure lowers, charging flow lowers Annunciators: 38A, 41A, 42A CREW Diagnose charging flow low, PZR level lowering 42A, CHG LINE FLOW HILO ATC (Memory action step)

1. Check charging pumps

- any running

- YES BG HIS-1a for CCP A BG HIS-2A for CCP B BG HIS-3 for NCP 2. Check charging header flow

- greater than 150 gpm

- NO 2. RNO go to step 6

6. Check charging header flow

- less than 45 gpm - YES 7. Check PZR level

- at program value

- NO 7. RNO perform the following

a. RNO Place running charging pump flow controller in manual and adjust charging flow, as necessary, to establish PZR level at program value.

BG FK-121 for CCP BG FK-462 for NCP - YES 8. Check letdown is isolated

- NO 8. RNO Go to step 10

10. Check letdown heat exchanger outlet temperature

- less than 130F - YES 11. Check charging header flow and letdown flow

- balanced - YES 12. Verify CCP adequate flow

a. Check CCPs any running

- NO b. Go to step 13

13. Return to procedure and step in effect.

Simulator Operator: If contacted as WWM, acknowledge requests. If contacted as Call Supt., acknowledge status.

Event termination: After the crew has placed the NCP flow controller in manual or at the direction of the lead examiner.

Simulator Operator: Insert Key 2 at direction of Lead Examiner.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 2 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 2 E v en t Descrip tion: Main feedwater header pressure detector AE PI

-508 failure high.

T ime Po sitio n Simulator operator: Insert Key 2 at the direction of the lead examiner.

Diagnostics: MFP speed will lower, all S/G levels will begin to lower, possible S/G level deviation alarms. Annunciators 108B, 109B, 110B, 111B CREW Diagnose S/G level ALL going down, slowing MFP speed. BOP will take manual control of the master MFP speed controller and restore speed to pre event values (approximately 5075 rpm). Crew will determine that AE PI-508, Feedwater Header Pressure detector, has failed high.

BOP (Memory action step) OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment B.

1. B1. Verify proper main feedwater pump speed control

- NO 1. B1 RNO a. Place MFP turbine master speed CTRL in manual.

FC-SK-509A 1. B1 RNO b. Control pump speed to programmed feedwater DP in accordance with programmed value. (refer to figure 1)

FC-SK-509A 1. B1 RNO c. IF MFP turbine master speed CTRL will not control in manual then use individual MFP speed controllers.

CREW Enter OFN SB-008, INSTRUMENT MALFUNCTIONS SRO, BOP 1. Check for malfunction:

Check if secondary system instrument channel is malfunctioning:

a. Perform appropriate attachment for malfunctioning channel from table below:

Variable Channels Attachment Steam or Feedwater Header pressure (AB,AE) P-507 P-508 Attachment B CREW SRO, BOP Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, ATTACHMENT B, STEAM OR FEEDWATER HEADER PRESSURE CHANNEL MALFUNCTION.

1. B1. Verify proper main feedwater pump speed control

- NO 1. B1 RNO a. Place MFP turbine master speed CTRL in manual.

FC-SK-509A 1. B1 RNO b. Control pump speed to programmed feedwater DP in accordance with programmed value. (refer to figure 1)

FC-SK-509A 1. B1 RNO c. IF MFP turbine master speed CTRL will not control in manual then use individual MFP speed controllers.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 3 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 2 E v en t Descrip tion: Main feedwater header pressure detector AE PI

-508 failure high.

T ime Po sitio n SRO, BOP 2. B2. Verify steam header pressure channel malfunction:

Steam header pressure

- abnormally higher OR Steam header pressure

- abnormally lower than S/G pressure OR Steam dump pressure control demand signal

- abnormal demand for existing plant conditions (refer to figure 2)

2. B2 RNO. Go to step B10 SRO, BOP 10. B10. Verify feedwater header pressure channel malfunction:

Feed header pressure

- abnormally high or low OR Steam header/Feedwater header DP

- abnormal for existing plant power (refer to figure 1)

11. B11. Request I&C to repair the failed channel.

Simulator Operator: If contacted as WWM, acknowledge requests. If contacted as Call Supt., acknowledge status.

Event termination: After the crew has placed the master MFP speed controller in manual and controlled S/G level or at the direction of the lead examiner.

Simulator Operator: Insert Key 3 at direction of Lead Examiner.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 4 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 3 E v en t Descrip tion: PZR level channel BB LI

-459 fails hi gh over 60 seconds.

T ime Po sitio n Simulator Operator: Insert Key 3 at direction of Lead Examiner.

Diagnostics: BB LI

-459 level channel rising, charging flow lowering, PZR heaters on, RCS pressure rising. Annunciators: 32D, 41A, 42A, 83C CREW Diagnose the rising PZR level channel, heaters on, charging flow low Crew could enter ALR 00

-032D prior to entering the OFN.

SRO, ATC ALR 00-32D, PZR HI LEV DEV HTRS ON.

1. Check controlling PZR level channel

- 5% greater than program level - YES 2. Check for instrument failure:

a. Check controlling PZR level channel

- within 6% of remaining channels BBLI-459A BB LI-461 BB LI-460A 2. RNO.1. If failed PZR level channel is selected on PZR LEV CTRL SEL switch, then select alternate level channel BB LS-459D 2. RNO.2. Go to OFN SB

-008, INSTRUMENT MALFUNCTIONS, step 1. CREW Enters OFN S B-008, INSTRUMENT MALFUNCTIONS

1. Check for malfunction:

Check if reactor coolant system instrument channel is malfunctioning or controller is malfunctioning:

b. Perform appropriate attachment for malfunctioning channel from table below:

Variable Channels Attachment PZR level L-459, L-460, L-461 Attachment J CREW Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, ATTACHMENT J , PZR LEVEL CHANNEL MALFUNCTION.

SRO, RO 1. J1. Identify failed instrument channel: a. Compare pressurizer level indications to confirm a pressurizer level channel failure:

BB LI-459A BB LI-460A BB LI-461

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 5 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 3 E v en t Descrip tion: PZR level channel BB LI

-459 fails hi gh over 60 seconds.

T ime Po sitio n SRO, ATC 2. J2. Ensure alternate pressurizer level channel on PZR LEV CTRL SEL switch is selected BB LS-459D 3. J3. Check failed pressurizer level channel failed low

- NO 3. J3.RNO Go to step J8 SRO, ATC 8. J8. Monitor pressurizer level response to ensure proper control

8. J8 RNO If PZR level is not maintained, then perform the following:

a. Place charging/letdown control in manual

b. Manually control PZR level to level appropriate for plant power

c. Notify SM/CRS Note: RO may place charging in manual to fine tune PZR level and then go back to auto.

9. J9. Check failed PZR level channel

- not used for recorder

- NO 9. J9 RNO. Select alternate pressurizer level channel as input to recorder. 10. J10. Monitor The Following Technical Specification LCOs And Comply With Action Statements, As Appropriate:

3.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION, Table 3.3.1

-1, Function 9 3.3.4, REMOTE SHUTDOWN INSTRUMENTATION, Table 3.3.4-1, Function 12 3.3.3, ACCIDENT MONITORING INSTRUMENTATION, Table 3.3.3

-1, Function 11

. NOTE: SRO will enter TS 3.3.1 Cond A, M

11. J11. Place Appropriate Reactor Trip/Safeguards Bistables For Failed Level Channel In TRIPPED Mode:

NOTE: At Wolf Creek the bistables will not be tripped to allow I&C to troubleshoot.

12. J12. Request I&C to repair failed channel.

Simulator Operator: If contacted as WWM, acknowledge requests. If contacted as Call Supt., acknowledge status.

Event termination: After the crew has selected an operable channel for PZR level or at the direction of the lead examiner.

Simulator Operator: Insert Key 4 at direction of Lead Examiner.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 6 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 4 E v en t Descrip tion: Dropped rod and recovery T ime Po sitio n Simulator Operator: Insert Key 4 at direction of Lead Examiner.

Diagnostics: Rod H8 (center rod) will drop in and give a red bottom light, on the DRPI panel Rod Deviation lights on for 1, R, and 2, RCS pressure will lower to DNB, reactor power will lower, main generator load will lower, RCS temperature lowering Annunciators: 80C, 81B, 82F CREW Diagnose the rod drop by a red bottom light, on the DRPI panel Rod Deviation lights on for 1, R, and 2, RCS pressure will lower, reactor power will lower, main generator load will lower, RCS temperature lowering.

Crew could enter annunciator ALR 081B, ROD AT BOTTOM.

SRO, ATC ALR 081B, ROD AT BOTTOM

1. Determine affected rod

a. Check DRPI

- one rod bottom light lit

- YES 2. Verify dropped rod

a. Check Tave

- decreasing BB TR-412 - YES b. Check nuclear instrumentation for flux abnormalities

- NO 3. Check reactor critical - YES 4. Go to OFN SF

-011, REALIGNMENT OF DROPPED, MISALIGNED ROD (S) AND ROD CONTROL MALFUNCTIONS, step 1. SRO, ATC Enters OFN SF

-011, REALIGNMENT OF DROPPED, MISALIGNED ROD (S) AND ROD CONTROL MALFUNCTIONS.

1. Check two or more rods dropped

- NO 1. RNO Go to step 3

3. Verify no load rejection in progress:

a. Generator load MW

- stable or increasing

- YES b. Generator current ref (MW)

- stable or increasing

- YES 4. Stop rod motion:

a. Place ROD BANK AUTO/MAN SEL switch in MAN SE HS-9 b. Verify rod motion stopped

5. Stabilize plant: a. Stop any plant operations requiring rod motion.

b. Adjust turbine load, as necessary, to maintain Tavg within 3°F of Tref. c. Stop any unnecessary borations or dilutions.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 7 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 4 E v en t Descrip tion: Dropped rod and recovery T ime Po sitio n SRO, ATC 6. Check for dropped rod Rod bottom light

- lit - YES Any of the following annunciators

- lit 00-81B, rod at bottom

- YES 7. Verify dropped rod

a. Check reactor critical

- YES b. Check Tave

- decreasing BB TR-412 - YES c. Check nuclear instrumentation for flux abnormalities

8. Refer to the following applicable TS 3.1.4, Rod Group Alignment Limits 3.1.5, Shutdown Bank Insertion Limits 3.1.6, Control Bank Insertion Limits 3.2.3, Axial Flux Difference 3.2.4, Quadrant Power Tilt Ratio NOTE: SRO will enter TS 3.1.4 Cond A, B , 3.1.6 Cond A, B 3.2.3 - I assume this is met, but need to verify on the simulator.

3.2.4 - I assume this is met because it is the center rod, but need to verify on the simulator.

9. Within 1 Hour And At Least Once Every 12 Hours While The Rod Is Misaligned, Perform STS RE

-004, SHUTDOWN MARGIN DETERMINATION Simulator Operator: If contacted as WWM, acknowledge requests. If contacted as Call Supt., acknowledge status.

Simulator Operator: Call control room as I&C and report that the cause of the dropped rod was a blown fuse which has been replaced. No other issues were found. CREW 10. Cause of the dropped rod found and corrected

- YES 11. Check if rod can be moved at normal rate:

Rod misaligned by less than 12 steps - NO Rod misaligned for less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

- YES 12. Prepare to retrieve dropped rod:

a. Place ROD BANK AUTO/MAN SEL switch to the bank with the dropped rod SE HS RO b. Direct I&C to locally verify rod bank selected by SE HS-9 is aligned properly, by light indications on associated cabinets

c. At lift coil disconnect panel, place all lift coil disconnect switches for other rods in affected bank to ROD DISCONNECTED position. - BOP d. At lift coil disconnect panel, place all lift coil disconnect switches for other rods in affected bank to ROD DISCONNECTED position.

Group step counter

- BOP A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 8 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 4 E v en t Descrip tion: Dropped rod and recovery T ime Po sitio n Simulator Operator: If contacted as I&C, acknowledge requests. Report back light indications have been verified.

CREW e. At step counter for affected group, open window and reset affected group step counter by hand to zero.

- BOP 13. Adjust turbine load, as necessary to maintain Tave within 3F of Tref. - BOP 14. Withdraw affected rod

a. Check dropped rod

- in shutdown group

- NO 14. RNO at pulse to analog converter cabinet, hold AUTO

-MANUAL switch in MANUAL Standard: Crew will call the Aux Building watch to go and hold switch in manual. Simulator Operator: When contacted as the Aux Building watch to hold the P to A converter switch in MANUAL, acknowledge request Simulator Operator: Insert Key 5 and call back and inform the control room that the switch is in manual. CREW b. Ensure only affected rod move during withdrawal

c. Withdraw dropped rod until operating step counter reaches group step position recorded in step 12.d.

d. Verify affected rod bank DRPI

- equals dropped rod DRPI

e. Check dropped rod

- in shutdown group

- NO f. At the pulse to analog converter cabinet, release auto/man switch. Simulator Operator: When contacted as the Turbine Building watch to release the P to A converter switch in acknowledge request.

Simulator Operator: After request made to release P to A converter switch insert Key 6 (delete Key 5)

Event termination: After the crew has started withdrawing the dropped rod or at the direction of the lead examiner.

Simulator Operator: Insert Key 7 at direction of Lead Examiner.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 9 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 5 , 6, 7 E v en t Descrip tion: Rod ejection resulting in a LOCA T ime Po sitio n Simulator Operator: Insert Key 7 for rod ejection Diagnostics: RCS pressure lowering in an uncontrolled manor, rod light for rod H8 top and bottom light lit and no lit between

Annunciators: Many, reactor trip after the SI CREW Diagnose the RCS pressure lowering rapidly, possible auto reactor trip on low PZR pressure (crew could see the pressure down fast and trip and SI manually) CREW Enter EMG E

-0, REACTOR TRIP OR SAFETY INJECTION.

NOTE: Foldout page items located on page 15 ATC, BOP Perform immediate actions 1. Verify reactor trip

a. Check all rod bottom lights

- lit - YES b. Check reactor trip breakers and bypass breakers

- open - YES SB ZL-1 SB ZL-2 SB ZL-3 SB ZL-4 c. Check intermediate range neutron flux

- decreasing

- YES SE NI-35B (gamma metrics)

SE NI-36B (gamma metrics)

NOTE: Turbine will fail to trip in auto and one MSIV will fail to close if steam line pressure lowers to 615 psig.

2. Verify turbine trip

a. Check main stop valves all closed

- NO a. RNO perform the following

a. RNO Manually trip turbine

- YES a. RNO If turbine will not trip then close main steam isolation valves and main steam bypass valves AB HS-79 AB HS-80 3. Check AC emergency busses

- at least one energized

- YES NOTE: NB01 will not be energized due to the bus lock out

4. Check if safety injection is actuated a. Check any indication SI is actuated

- lit Annunciator 00

-030A NF039A LOCA SEQ ACTUATED

- LIT - YES Annunciator 00

-031A NF039B LOCA SEQ ACTUATED

- LIT - YES ESFAS status panel SIS section

- any white lights lit

- YES A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 10 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 5 , 6, 7 E v en t Descrip tion: Rod ejection resulting in a LOCA Partial trip status permissive/block status panel

- SI red light lit

- YES b. Check both trains of SI actuated Ann 00-030A NF039A LOCA SEQ ACTUATED

- LIT - YES Ann 00-031A NF039B LOCA SEQ ACTUATED

- LIT - YES NOTE: The SRO will now perform a verification of the immediate actions by performing a read through of the steps provided above.

CREW 5. Check if SI is required SI was manually actuated and was required

- YES Containment pressure is currently or has been

- greater than or equal to 3.5 psig RCS pressure is currently or has been

- less than or equal to 1830 psig

- YES Any SG pressure is currently or has been less than or equal to 615

6. Verify automatic actions using attachment F, automatic signal verification NOTE: Attachment F actions are located in this guide, page 11

7. Check main generator breakers and exciter breaker

- open - YES MA ZL-3A MA ZL-4A MA ZL-2 8. Check total AFW flow

- greater than 270,000 lbm/hr

- NO a. RNO IF S/G narrow range level in at least one S/G is greater than 6% [29%], THEN control feed flow to maintain narrow range level and go to Step 9

- NO b. Manually start pumps and align valves as necessary to establish greater than 270,000 lbm/hr AFW flow.

c. IF total AFW flow greater than 270,000 lbm/hr can NOT be established, THEN perform the following:

1. Direct operator to monitor Critical Safety Functions using EMG F

-0, CRITICAL SAFETY FUNCTION STATUS TREES (CSFST).

2. Ensure BIT Inlet AND Outlet Valves are open EM HIS-8803A EM HIS-8803B EM HIS-8801A EM HIS-8801B 3. Continue with Attachment F and Go to EMG FR

-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 11 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 5 , 6, 7 E v en t Descrip tion: Rod ejection resulting in a LOCA NOTE: Attachment F actions ATC or BOP F1. Check AC emergency busses energized NB01 - energized

- NO o Depress Start/Stop pushbutton for EDG A o KJ HS-8A NB02 - energized

- YES F2. Verify feedwater isolation

a. Main feedwater pumps tripped

- YES Annunciator 00

-120A, MFP A trip

- lit - YES Annunciator 00

-123A, MFP B trip

- lit - YES b. Main feedwater reg valves closed

- YES AE ZL-510 for S/G A AE ZL-520 for S/G B AE ZL-530 for S/G C AE ZL-540 for S/G D

c. Main feedwater reg bypass valves closed

- YES AE ZL-550 for S/G A AE ZL-560 for S/G B AE ZL-570 for S/G C AE ZL-580 for S/G D

d. Main feedwater isolation valves closed

- YES AE HIS-39 for S/G A AE HIS-40 for S/G B AE HIS-41 for S/G C AE HIS-42 for S/G D

e. Main feedwater chemical injections valves closed

- YES AE HIS-43 for S/G A AE HIS-44 for S/G B AE HIS-45 for S/G C AE HIS-46 for S/G D

f. Check ESFAS status panel SGBSIS section all white lights lit

-YES Red train Yellow train F3. Verify containment isolation phase A

a. Check ESFAS status panel CISA section all white lights lit

- NO Red train - no power Yellow train F4. Verify AFW pumps running

a. Check motor driven AFW pumps both running

- NO a. RNO Manually start pumps AL HIS 22A

- no power AL HIS-23A - tagged out NOTE: No AFW pumps will start since NB01 is not powered (A MDAFWP) and B MDAFWP is tagged out.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 12 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 5 , 6, 7 E v en t Descrip tion: Rod ejection resulting in a LOCA

b. Check turbine driven AFW pump running

b. RNO Perform the following

1. Check if turbine driven AFW pump should be running At least 2/4 S/G narrow range level channels on 2/4 S/Gs - LESS THAN 23.5% OR Loss of NB01 voltage has occurred OR Loss of NB02 voltage has occurred OR AMSAC actuation

2. IF turbine driven AFW pump should be running, THEN manually open steam supply valves:

AB HIS-5A AB HIS-6A FC HIS-312A NOTE: TDAFWP has a broke trip throttle valve and will not start

F5. Verify ECCS pumps running

a. Check CCPs both running

- NO a. RNO manually start pumps BG HIS1A - no power BG HIS-2A - YES CT2: Establish flow from at least one Charging pump by the completion of EMG E

-0, Attachment F.

b. Check SI pumps both running

- NO b. RNO manually start pumps EM HIS no power EM HIS-5 c. Check RHR pumps both running

- NO c. RNO manually start pumps EJ HIS no power EJ HIS-2 F6. Verify CCW alignment

a. Check CCW pumps one running in each train

- NO a. RNO manually start CCW pumps as necessary to establish one running in each train EG HIS-21 or EG HIS

-23 for red train

- no power EG HIS-22 or EG HIS

-24 for yellow train

- running b. Check one pair of CCW service loop supply and return valves for an operating CCW pump open EG ZL-15 AND EG ZL no power EG ZL-16 AND EG ZL YES F7. Check ESW pumps both running

- NO a. RNO Manually start pumps EF HIS-55A - no power EF HIS-56A - running F8. Check containment fan coolers running in slow speed

- YES/NO a. RNO Perform the following for each containment cooler fan that is still running in fast or is not running

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 13 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 5 , 6, 7 E v en t Descrip tion: Rod ejection resulting in a LOCA Place Containment Cooler Fan Speed Selector switches in Slow.

o GN HS-5 for cooler 1A

- no power o GN HS-9 for cooler 1B o GN HS-13 for cooler 1C

- no power o GN HS-17 for cooler 1D Manually start containment cooler fan o GN HIS-5 for cooler 1A

- no power o GN HIS-9 for cooler 1B o GN HIS-13 for cooler 1C

- no power o GN HIS-17 for cooler 1D F9. Verify containment purge isolation

a. Check ESFAS status panel CPIS section all white lights lit

- NO Red train Yellow train

a. RNO perform the following

1. If containment purge isolation has not actuated, then manually actuate containment purge isolation SA HS no power SA HS-15 2. IF any CPIS component NOT properly aligned, THEN manually align component.

3. IF component(s) can NOT be manually aligned, THEN locally isolate instrument air to affected containment penetration. Refer to ATTACHMENT C, VALVES CLOSED BY CONTAINMENT PURGE ISOLATION SIGNAL. F10. Verify both trains of control room ventilation isolation

a. Check ESFAS status panel CRVIS section all white lights lit

- NO Red train Yellow train

a. RNO perform the following

1. If control room ventilation isolation has not actuated, then manually actuate control room ventilation isolation SA HS no power SA HS-13 2. IF any CRVIS component NOT properly aligned, THEN manually align associated component

3. IF neither train of CRVIS is in service, THEN establish one in service train of CRVIS using SYS GK

-122, MANUAL CRVIS LINE

-UP - NO 4. IF only one train of CRVIS can be placed in service, THEN within 90 minutes, isolate out of service train using SYS GK-122, MANUAL CRVIS LINE

-UP b. Ensure control room outer door closed

- YES

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 14 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 5 , 6, 7 E v en t Descrip tion: Rod ejection resulting in a LOCA F11. Verify main steamline isolation no required

a. Check containment pressure has remained less than 17 psig GN PR-934 - YES b. Check either condition below satisfied

- YES Low steamline pressure SI not blocked and steamline pressure has remained greater than 615 psig OR Low steamline pressure SI blocked and steamline pressure rate has remained less than 100 psi/50 sec F12. Verify containment spray not required

a. Containment pressure has remained less than 27 psig

- YES Annunciator 00

-59A, CSAS not lit Annunciator 00

-59B, CISB not lit GN PR-934 F13. Verify ECCS flow

a. Check centrifugal charging pumps to boron injection tank flow meters flow indicated EM FI-917A - no power EM FI-917B - YES b. Check RCS pressure less than 1725

- YES/NO NOTE: Depending how long the crew takes to get here pressure could be lower so steps may or may not be performed (this does not change any outcomes of the scenario)

b. NO - RNO go to step 14 OR

b. YES - then continue to c

c. Check SI pump discharge flow meters flow indicated EM FI-918 - no power EM FI-922 - YES d. Check RCS pressure less than 325 psig

- NO d. RNO go to step F14 F14. Verify AFW valves properly aligned

a. Check ESFAS status panel AFAS section all white lights lit

- NO b. Check white train ESFAS status panel AFAS section all white lights lit

- NO If any AFAS section component not properly aligned, then manually align associated component to establish desired AFAS lineup F15. Verify SI valves properly aligned

a. Check ESFAS status panel SIS section system level white lights all lit - NO Red train Yellow train RNO If any SIS section component not properly aligned, then manually align associated component to establish proper SIS lineup F16. Check if NCP should be stopped

a. CCPs any running

- YES b. Stop NCP BG HIS placed switch in STOP

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 15 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 5 , 6, 7 E v en t Descrip tion: Rod ejection resulting in a LOCA F17. Dispatch Operator To Locally Close The Following Terry Turbine Steam Drains:

FC-V048 (2000' TDAFW Pump Room)

FC-V070 (2000' TDAFW Pump Room)

FC-V089 (2000' TDAFW Pump Room)

F18. Return to procedure and step in effect Simulator Operator: When contacted to close Terry Turbine steam drains, acknowledge request and insert Key 9 EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Foldout page items ANY 1. RCP TRIP CRITERIA

- IF all conditions listed below occur, THEN trip all RCPs: RCS pressure

- LESS THAN 1400 PSIG CCPs or SI pumps

- AT LEAST ONE RUNNING Operator controlled cooldown

- NOT IN PROGRESS NOTE: RCS pressure may or may not get this low it depends of if the crew actuates SI early or the auto does it.

7. RCS TEMPERATURE CONTROL IF a Loss-Of-Offsite Power has occurred, THEN close MSIVs. o AB HS-79 o AB HS-80 IF no RCPs are running AND off

-site power is available, THEN select STM PRESS mode on the steam dumps.

o AB US-500Z IF RCS C/L temperature is less than 557°F AND decreasing, THEN control total feed flow to limit RCS cooldown. o Maintain total feed flow greater than 270,000 lbm/hr until narrow range is greater than 6% [29%] in at least one S/G.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 16 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 8, 9, 10 E v en t Descrip tion: Loss of all AFW FR procedure entry T ime Po sitio n EMG FR-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK CREW 1. Check if secondary heat sink is required

a. RCS pressure greater than any no faulted SG pressure

- YES b. RCS hot leg temperature greater than 350 °F - YES 2. Check If RCS Bleed And Feed

- NOT REQUIRED

a. Check wide range level in at least two SG greater than or equal to 12% [28%]

- YES AE L I-501, SG A WR LEV AE LI-502, SG B WR LEV AE LI-503, SG C WR LEV AE LI-504, SG D WR LEV

3. Try to establish AFW flow to at least on SG

a. Check ESFAS status panel SGBSIS section all white lights lit

- YES Red train Yellow train

b. Check control room indications for cause of AFW failure CST Level Motor Driven AFW Pump Power Supply Turbine Driven AFW Pump Steam Supply AFW Valve Alignment

c. Try to restore AFW flow

4. Check total flow to SG greater than 270,000 lbm/hr

- NO 4. RNO perform the following

a. IF feed flow to at least one S/G can be verified, THEN perform the following:

Maintain flow to restore S/G level to greater than 6% [29%].

WHEN S/G level is greater than 6% [29%], THEN return to procedure and step in effect.

Go to step 6

- NO b. IF feed flow can NOT be verified to at least one S/G, THEN perform the following Dispatch operator to locally restore AFW flow.

IF all AFW flow has been lost, THEN close AFW throttle valves to prevent inadvertent feedwater addition to a hot/dry S/G. Go to step 6

6. Reduce heat input to RCS

a. Stop all RCPs BB HIS-37 For RCP A BB HIS-38 For RCP B BB HIS-39 For RCP C BB HIS-40 For RCP D

b. Turn off all PZR heaters BB HIS-50 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 17 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 8, 9, 10 E v en t Descrip tion: Loss of all AFW FR procedure entry T ime Po sitio n EMG FR-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK BB HIS-51A BB HIS-52A ANY 7. Establish SG pressure control

a. Check condenser available

- YES C lit MSIV - open Circulating water pumps running

b. Place steam header pressure control in manual AB PK-507 c. Manually set Steam Header Pressure Control output to zero. AB PK-507 d. Place Steam Dump Select Switch in STEAM PRESS position. AB US-500Z e. Place steam header pressure control in automatic AB PK-507 8. Establish flow from non

-safety related AFW pump

a. Start non-safety related AFW Pump per SYS AP

-122, NON-SAFETY AUX FEED PUMP OPERATION.

CT1: Establish AUX feed flow (from the NSAFP) to at least ONE intact S/G at a flow rate great enough that core exit temperatures are stable or decreasing AND level in at least ONE S/G is increasing, prior to bleed and feed criteria being met.

NOTE: Crew will dispatch the local operator to start the non

-safety AFWP , page 18 of this guide

b. Open TD AFWP Flow Control Valves to establish AFW flow to S/Gs.

c. Go to step 17

17. Check SG levels

a. Check RCS bleed and feed not established

- YES b. Check narrow range level in at least one SG greater that 6% [29] - NO

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 18 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 8, 9, 10 E v en t Descrip tion: Loss of all AFW FR procedure entry T ime Po sitio n EMG FR-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK

b. RNO perform the following Verify flow to SGs o Core exit temperatures stable or decreasing o Level in at least one SG increasing Wide range OR Narrow range IF feedwater flow to at least one S/G can NOT be verified, THEN go to step 18.

- NO IF feedwater flow to at least one S/G verified, THEN maintain flow to restore narrow range level to greater than 6% [29%] while returning to procedure and step in effect.

- YES NOTE: The crew will have the non

-safety AFWP by this time and will return to E

-0 step 9 SYS AP-122, NON-SAFETY AUX FEED PUMP OPERATION ATC or BOP Dispatch local operator to start the non

-safety AFWP 6.1.1. IF Condensate Storage Tank Level (CST) level cannot be maintained greater than 5%, THEN PERFORM ATTACHMENT A, Establishing Alternate AFW Water Supply.

- NO 6.1.2. PLACE AD LIC79B, COND HOTWELL M/U LEV CTRL in manual and close.

AD LIC79B MANUAL/CLOSED

6.1.3. Locally

START NSAFP per ATTACHMENT B, NSAFP Local Operations to feed SGs with NSAFP.

6.1.4. RETURN

to the EMG/OFN in use.

6.1.5. Section

6.1, Starting NSAFP, complete.

Simulator Operator: When contacted as the building watch to start non

-safety AFWP, acknowledge request. Put in key 8 Simulator Operator: When the file to start the non

-safety AFWP has completed call back to control room and inform them the non

-safety AFWP is running.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 19 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 10 E v en t Descrip tion: Continuation of EMG E

-0 after return from FR

-H1 T ime Po sitio n EMG E-0, REACTOR TRIP OR SAFETY INJECTION, step 9 CREW 9. Check RCS cold leg temperatures Stable at or trending to 557F for condenser steam dumps or SG ARVs - YES Stable at or trending to a range of 553F to 557F for SG ARVs if recovering from an inadvertent SI

10. Establish SG pressure control

a. Check condenser available

- YES C-9 lit MSIV - open Circulating water pumps running

b. Place steam header pressure control in manual AB PK-507 c. Manually set steam header pressure control output to zero AB PK-507 d. Place steam dump select switch in steam pressure position AB US-500Z e. Place steam header pressure control in automatic AB PK-507 11. Check PZR PORVs

a. Check PZR PORVs closed

- YES BB HIS-455A BB HIS-456A b. Power to block valves

- YES BB HIS-8000A BB HIS-8000B c. RCS pressure less than 2185 psig

- YES 12. Check normal PZR spray valves closed

- YES BB ZL-455B BB ZL-455C 13. Check PZR safety valves closed

- YES BB ZL-8010A BB ZL-8010B BB ZL-8010C 14. Check if RCPs should be stopped

a. Check RCPs any running

- NO a. RNO go to step 15

15. Direct Operator To Monitor Critical Safety Functions Using EMG F-0, CRITICAL SAFETY FUNCTION STATUS TREES (CSFST).

NOTE: SRO will direct operator to monitor CSFST Evaluator: Acknowledge request to monitor CSFST

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 20 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 10 E v en t Descrip tion: Continuation of EMG E

-0 after return from FR

-H1 T ime Po sitio n 16. Check if SG are not faulted

a. Check pressures in all SG No SG pressure decreasing in an uncontrolled manner - YES No SG completely depressurized

- YES 17. Check if SG tubes are intact Check SG levels not increasing in an uncontrolled manner -YES o Narrow range o Wide range Condenser air discharge radiation normal before isolation GEG 925 - YES SG blowdown and sample radiation normal before isolation o BML 256 - YES o SJL 026 - YES Turbine driven auxiliary feedwater pump exhaust radiation normal o FCT 381 - YES SG steamline radiation normal o ABS 114 for S/G A o ABS 113 for S/G B o ABS 112 for S/G C o ABS 111 for S/G D

18. Check if RCS is intact in containment Containment radiation normal before isolation

- NO GTP 311 GTI 312 GTG 313 GTP 321 GTI 322 GTG 323 GTA 591 GTA 601 Containment pressure normal

- NO GN PI-934 GN PI-935 GN PI-936 GN PI-937 GT PDI-40 GN PR-934 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 21 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 10 E v en t Descrip tion: Continuation of EMG E

-0 after return from FR

-H1 T ime Po sitio n CREW Containment sump level normal

- NO EJ LI-7 EJ LI-8 EJ LR-6 LF LI-9 LF LI-10 18. RNO perform the following

a. Ensure BIT inlet and outlet valves are open EM HIS-8803A EM HIS-8803 EM HIS-8801A EM HIS-8801B b. Go to EMG E

-1, LOSS OF REACTOR OR SECONDARY COOLANT, step 1

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 22 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 11 E v en t Descrip tion: Transition to EMG E

-1, LOSS OF REACTOR OR SECONDARY COOLANT, step 1 T ime Po sitio n CREW 1. Check if RCPs should be stopped

a. Check RCPs any running

- NO a. RNO go to step 2

2. Check if SG are not faulted

- YES a. Check pressure in all SG No SG pressure decreasing in an uncontrolled manner No SG completely depressurized

3. Check intact SG level

a. Check NR level intact least one SG greater than 6% [29%]

- YES/NO a. RNO Maintain total feed flow greater than 270,000 lbm/hr, until NR level greater than 6% [29%] in at least one SG NOTE: SG levels may or may not be recovered at this time

b. Control feed flow to maintain narrow range level in all SG between 6% [29%] and 50%

4. Reset SI SB HS-42A SB HS-43A 5. Reset containment isolation phase A and B SB HS-56 For Phase A SB HS-53 For Phase A SB HS-55 For Phase B SB HS-52 For Phase B NOTE: The scenario may be terminated by the lead examiner anytime after step 4 is completed.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 1 of 5 Rev 1 Facili t y: Wolf Creek Scenari o No.: 2 (New) O p-Tes t No.: Nov 2015 E x a miners: Opera tors: I ni t ia l Condi tions: Rx is at 1

-2%, EOL, with no equipment OOS

. 'A' MFP is running IC-859, 103D and E on white board Turno ver: Continue to raise power to between 5

- 10% power and hold.

E vent N o. M a l f. N o. E vent T y p e* E vent Descr ip t i o n 1. R (ATC) N (BOP SRO) Raise power to 5

- 10%. 2. I (ATC SRO) TS (SRO) Loop A Primary RTD (411C

- THOT) fails high.

3. I (BOP , SRO) TS (SRO) 'A' S/G level channel (AE LI

-551) fails low.

4. I (ATC, SRO) TS (SRO) Power Range Channel (SE NI

-43) failure upscale to 80% over 15 seconds.

5. C (BOP SRO) TS (SRO) 'B' S/G ARV fails open (manual control available).

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 2 of 5 Rev 1 6. M (ALL) 'A' S/G fault inside CTMT. CT 1: Isolate all AFW flow to the faulted SG (A) within 10 minutes of the break using AL HK

-8A AND AL HK

-7A (AFW flow control valves from TD and MD pumps to A S/G). 7. I (ATC) SIS fails to auto initiate.

CT 2: Manually actuate SI (SB HS-27 & 28) after auto SI actuation criteria are met prior to transition out of EMG E

-0 8. C (BOP) The MSIVs fail to auto close.

CT 3: Isolate the faulted SG from the non

-faulted SGs (depress AB HS-79 or AB HS

-80) before ANY RCS Cold Leg temperatures reach 240F or before transition to EMG C

-21 , EMG C-21, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS

. * (N)ormal, (R)eacti v i t y , (I)nstrument, (C)omponent, (M)ajor A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 3 of 5 Rev 1 Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Malfunctions after EOP entry (1

-2) 2 (event 7 ,8) 2. Abnormal events (2

-4) 4 (event 2,3,4 ,5) 3. Major transients (1

-2) 1 (event 6

) 4. EOPs entered/requiring substantive actions (1

-2) 2 (E-2, ES-03) 5. EOP contingencies requiring substantive actions (0

-2) 0 6. EOP based Critical tasks (2

-3) 3 (events 6,7 ,8) 7. Critical Task Justification References CT 1: Isolate all AFW flow to the faulted SG (A) within 10 minutes of the break using AL HK-8A AND AL HK

-7A (AFW flow control valves from TD and MD pumps to A S/G).

Limit CTMT peak pressure which would challenge the containment barrier. USAR 6.2.1.4.1.12 AND AI 21-016, OPERATOR TIME CRITICAL ACTIONS VALIDATION, Rev 10, TCA (1-17) CT 2: Manually actuate SI (SB HS-27 & 28) after auto SI actuation criteria are met prior to transition out of EMG E

-0. Failure to do so will violate the facility license and make FSAR assumptions invalid for accident analysis. USAR 15.1.5 CT 3: Isolate the faulted SG 'A' from the non

-faulted SGs (depress AB HS-79 or AB HS

-80) before ANY RCS Cold Leg temperatures reach 240F or before transition to EMG C

-21 , EMG C-21, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS

. T he excessive cooldown would result in a PTS concern.

BD-EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Rev 26A.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 4 of 5 Rev 1 SCENARIO #

2 NARRATIVE Initial conditions: Rx is between 1 and 2%, EOL, with no equipment OOS

. Turnover: Ready for GEN 00

-003, step 6.11.2.Reactor Power stable between 5% and 10% while continuing with this procedure.

Event 1: The crew will raise power to 5

- 10% using GEN 00

-step 6.11.2 and then hold.

Even t 2: Loop A Primary RTD (411C

- THOT) fails high.

The crew will mitigate using OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment L, NARROW RANGE RTD MALFUNCTION. No immediate actions are required due to the low power level. SRO will direct the procedure. The ATC will select out the failed channel. The SRO will enter T.S. 3.3.1, Reactor Trip System Instrumentation. Condition A and E. Event 3: 'A' S/G level channel (AE LI-551) fails low. The crew will mitigate using OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachmen t F. The BOP will initially take manual control of the MFW regulating bypass valve and control S/G level.

Automatic control will be restored once an alternate control channel is selected. The SRO will enter T.S. 3.3.1, Reactor Trip System Instrumentation, Condition A and E and 3.3.2, Engineered Safety feature Actuation System Instrumentation, Conditions A, D and I. The SRO will monitor T.S. 3.3.3, Post Accident Monitoring Instrumentation and 3.3.4, Remote Shutdown System

. Event 4: Power Range Channel (SE NI-43) failure upscale to 80% over 15 seconds.

The ATC will check no runback in progress and then ensure rods are in manual (rods should be in manual due to power level). The crew will diagnose the failure and enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment R and bypass the failed channel. The SRO will enter TS 3.3.1 , Reactor Trip System Instrumentation, Condition A, D, E, S, and T.

Event 5: 'B' S/G ARV fails open (manual control available). The BOP will either notice that the ARV is open and inform the SRO and close the valve in manual, or, if he does not see the open ARV will lower main turbine load to lower reactor power to less than 100%. The crew should enter OFN A B-041, STEAMLINE OR FEEDLINE LEAK, as entry conditions are met. There will be no alarms for this event. The crew will close the open ARV per procedure. SRO will enter TS 3.7.4, Atmospheric Relief Valves, Condition A. Event 6: 'A' S/G fault in side CTMT. The crew will notice CTMT conditions changing, power rising, and will trip the reactor. The crew will enter and perform EMG E

-0, REACTOR TRIP OR SAFETY INJECTION. The crew will transition to EMG E-2, FAULTED STEAM GENERATOR ISOLATION, for the mitigation of the faulted S/G.

CT 1: Isolate all AFW flow to the faulted SG (A) within 10 minutes of the break using AL HK-8A AND AL HK

-7A (AFW flow control valves from TD and MD pumps to A S/G).

Event 7: SIS fails to auto initiate.

The crew must recognize the requirement for SIS and manually initiate both trains. This will be performed by the ATC. CT 2: Manually actuate SI (SB HS-27 & 28) after auto SI actuation criteria are met prior to transition out of EMG E

-0. Event 8: The MSIVs fail to auto close on the low steam line pressure signal

. The BOP will be required --80. CT 3: Isolate the faulted SG from the non

-faulted SGs (depress AB HS-79 or AB HS

-80) before ANY RCS Cold Leg temperatures reach 240F or before transition to EMG C

-21, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS

. The crew will complete EMG E

-2 and then transition to EMG ES

-03, SI TERMINATION. After the crew stops all but one CCP, at step 5, the scenario may be terminated by the chief examiner.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 5 of 5 Rev 1 Procedures entered:

OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment L, NARROW RANGE RTD MALFUNCTION OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment FMALFUNCTION OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment R, POWER RANGE NEUTRON FLUX OFN AB-041, STEAMLINE OR FEEDLINE LEAK EMG E-0, REACTOR TRIP OR SAFETY INJECTION EMG E-2, FAULTED STEAM GENERATOR ISOLATION EMG ES-03, SI TERMINATION

Scenario file:

ILO Scenario 2

RTD fails low 411C IMF mBB01E f: 636 r:15 k:1

AE LI-551 fails low

- BOP IMF mAE15A4 f:0 r:60 k:2

power range N

-43 fails hi to 80%

IMF mSE03C f:80 k:3

B ARV fails open manual control available IMF mAB07B f: 100 r:30 k:4

A SG fault inside ctmt IMF mAB03A f: 7.36e+006 r:30 k:5

SIS fails to auto initiate IMF mSA14A f: 1 IMF mSA14B f:1

MSIVs fail to auto close

IMF mSA24A f:1 IMF mSA24B f:1

end file A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 1 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 1 E v en t Descrip tion: Raise power to 5

- 10%. T ime Po sitio n GEN 00-003, Step 6.11.2, ENTER MODE 1

. SRO Provides bounding order for the power increase, including the reactivity brief for rod withdrawal.

RO 6.11.2 ENTER MODE 1, as follows:

1. Reactor Power stable between 5% and 10% while continuing with this procedure.

BOP 6.11.2 ENTER MODE 1, as follows:

2. pressure. 3. ass Valves are Operating between 40% and 60%.

SRO 6.11.2 ENTER MODE 1, as follows:

4. 3 of 4 Power Range channels indicate greater than 5% Reactor Power, o entered MODE 1.

o Insert Key1 at the direct A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 2 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 2 E v en t Descrip tion: - THOT T ime Po sitio n Key 1 - T Setpoint indication-- , 066B, 067D, 068D, 69D 066B , 1. a. - -step 1. BOP -. - o - -. - o -9 -3. SRO 1.

a. T-411, T-421, T-431 , T-441 SRO, BOP - , . - o - - o -9 SRO, BOP a. - o - RNO: a.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 3 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 2 E v en t Descrip tion: - THOT T ime Po sitio n a. failure: 1 T - -412 T itches: o BB TS- o BB TS-412T o -9 Note: Rods are in Manual per GEN 00

-003. SRO, BOP -- - o - SRO, BOP - ON o -63 o -64 SRO, BOP SRO, BOP o -411E SRO o 3.3.1- - RNO: plant conditions allow, a. o -9 b. ( o -2 c. Tavg is w o -9 Note: -

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 4 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 2 E v en t Descrip tion: - THOT T ime Po sitio n SRO, BOP - o - NOT RED troubleshoot.

SRO Spare SRO ering Key 2 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 5 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 3 E v en t Descrip tion: - T ime Po sitio n Key 2 Diagnostics: --551 trending down.

-517, ---550 output trending towards 100% open.

-551 SRO, BOP - 1.

OR

Greater Than 70%

SRO, BOP - 2. - a. - * -519 * -551 1. * -510 * -550 - Manual 2. * -510 * -550 - 3. -step 1. -3. 1.

Malfunctioning:

a.

---539 , ---552 , --554 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 6 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 3 E v en t Descrip tion: - T ime Po sitio n SRO, BOP - . a. -517 -518 -519 -551 SRO, BOP - .

- * - * - * - SRO, BOP - . 1. - * -550 - Manual * -560 * -570 * -580 2. establ * -550- * -560 * -570 * -580 SRO, BOP Switch: * - * - * - * - SRO, BOP - * -550 - * -560 * -570 * -580 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 7 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 3 E v en t Descrip tion: - T ime Po sitio n SRO, BOP iate: o 3.3.1- E - o - - o 3.3.4- o 3.3.3- SRO, BOP troubleshoot.

SRO, BOP * -517 * -528 * -537 * -548 RNO: SRO, BOP SRO, BOP SRO, BOP t Key 3 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 8 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t N o.: 4 E v en t Descrip tion: - T ime Po sitio n Key 3 --43B trends up to 80%.

1. RNO: Go to Step 3.

3. a. - o -41B o -42B o -43B - NOT Good o -44B 1. 2. Refer to Technical Specification 3.3.1 Table 3.3.1-1 3. -Step 1. -3. 1.

Malfunctioning:

a.

Power Range N-41, N-42 , N-43, N-44 R A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 9 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t N o.: 4 E v en t Descrip tion: - T ime Po sitio n - R. R1. * * - * - NOT o o * - *

Overpower Rod Stop

Drawer - *

SRO, BOP -R. R2. - o - -R. R3. o -9 R4. a. following Turn thchannel.

channel. Turn the Rod Stop Bypass switch to the failed power range b. following:

power range channel.

R5. o -9 N-003. R6.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 10 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t N o.: 4 E v en t Descrip tion: - T ime Po sitio n R7. Recording On OPT Recorder: o OPT Recorder recorder. R8. -- R9. Verify QPTR Operability:

a. Greater Than 50%.

RNO: a. Go to step R10.

R10. o 3.3.1- (T.S. 3.3.1, , E, S, T, - o 3.2.4.2 o R11. R12. troubleshoot.

R13. R14. R15. control power fuses have been pulled and T.S. have been identified or at the Key 4 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 11 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 5 E v en t Descrip tion: T ime Po sitio n Key 4 at the direction Diagnostics: Reactor Power slowly increasingslowly decreasing

, levels spike, 108B, 109B, 110B, 111B Diagnoses R erature going slowly is lit with green light out.

- - - -41B - -42B - -43B - -44B - SRO, BOP - - - o 00-065D - - SRO, BOP - -114 - SRO, BOP 5. - -- -- NO Take Manual control and close

-- --

b. Refer to Tech Spec 3.7.4.

clos or at the Key 5 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 12 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n Key 5 at the direction of

, . B, 110B, 111B roaching 3.5 psig

- 1. Verify reactor trip

a. - lit - b. nd bypass breakers

- open - -1 -2 -3 -4 c. - decreasing

- - - 2. Verify turbine trip

a. - y busses - at least one energized

- BOP

--80 CT 3: Isolate the faulted SG 'A' from the non

-faulted SGs (depress AB HS-79 or AB HS

-80) before ANY RCS Cold Leg temperatures reach 240F or before transition to EMG C

-21 , EMG C-21, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS

.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 13 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n BOP CT 1: Isolate all AFW flow to the faulted SG (A) within 10 minutes of the break using AL HK

-8A AND AL HK

-7A (AFW flow control valves from TD and MD pumps to A S/G).

c. Maintain total feed flow greater than 270,000 lb

a. - lit -- - NO -- - NO - any white lights lit

- NO - light lit

- NO n the left

-these steps.

- - 6. -27 o -28 CT 2: Manually actuate SI (SB HS-27 & 28) after auto SI actuation criteria are met prior to transition out of EMG E

-0. b. -- - -- - 5. -

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 14 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n

- greater than or equal to 3.5 psig

- - less than or equal to 1830 psig - equal to 615

6. verification NOTE: 16 7. - open - - - -2 8. - - - NO

Stable at or tren following:

ose the Main Turbine Stop and o -134 80 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 15 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n a. - - - OPEN - b. -507 c. -507 - e. -507

- - - - - b. Power to block valves

- - - -8000B - - - 12. - -455B - - - 13. - - - -8010B - - -

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 16 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n

- - - - - - OR - - SRO -0, SRO, BOP

- - - -8803 B -880 1 -880 1B Go to EMG E

-2 , , Step 1. EMG E-

NB01 - energized

- NB02 - energized

- a. ped - -- lit - -- lit - b. Main feedwater reg valves closed

- - - - -

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 17 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n c. Main feedwater reg bypass valves closed

- - - - - d. Main feedwater isolation valves closed

- - - - - e. osed - - - - - f. - Red train - - a. Red train

- - a. - b. -

- - - - - - a. - Red train - - a. -

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 18 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n Red train - -

a. GN PR-934 - b. - - OR rate 1.

2. - -

a. - - - GN PR-934 a. on tank flow -- -917B - b. - c. -918 - -922 - d. - NO d.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 19 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n

a. - NO b. n all white lights lit

- a.

all lit - Red train - - a. - b. - - - EMG E-2, Enters EMG E

-2, SRO, BOP

- - o - - - - - - - - - -- -- -- -- - -- -- -- -- SRO, BOP on south end of Turbine Building.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 20 of 26 O p-Tes t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n 2. RNO a. Go to Step 3.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 21 of 26 O p-T es t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n SRO. BOP

- OR - OR - -- Manually closed

- - - - SRO, BOP

- -- - -- - -- d. Mai- --

- - -

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 22 of 26 O p-T es t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n - -- - --

8. a. Power To Block Valves

- - -8000B - - - - 9. - pressures.

-- - - - - - - - - ing - - RESET - - - -40 70 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 23 of 26 O p-T es t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n - - - - - - - -

- OPEN OPEN OPEN - - - c. - -40 d. - Opened 44 e. - OPEN OPEN OPEN f. R RESET Switches

- - - 12. - o GEG 925 A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 24 of 26 O p-T es t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n b. - - - - 13. - - NO 13. RNO a. Go to step 14.

- b. Secondary heat sink:

- - OR - - - - - e. Go to EMG ES

- EMG ES- Enters EMG ES

- 1. NOTE: -2.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 25 of 26 O p-T es t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n S- -

2. - - - - NOTE: SRO -2. - OPEN OPEN OPEN - - - g. - -40 h. - Opened 44 i. - OPEN OPEN OPEN - - - - - b. -29 5. Reduce A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 26 of 26 O p-T es t No.: Nov. 2015 Scenari o No.: 2 E v en t No.: 6, 7, 8 E v en t Descrip tion: close T ime Po sitio n - -- -- - OR - Scenario -

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 1 of 6 Rev 1 Facili t y: Wolf Creek Scenari o No.: 3 (New) O p-Tes t No.: Nov 2015 E x a miners: Opera tors: I ni t ia l Condi tions: 100% power, MOL. Service Water pump 'B' is tagged out for maintenance.

IC 30 Turno ver: Maintain 100% power. Thunderstorm warning is in effect.

T.R 3.7.8, Service Water System, Condition A , is in effect for the B service water pump maintenance.

E vent N o. M a l f. N o. E vent T y p e* E vent Descr ip t io n 1. C (ATC SRO) TR (SRO) Service Water pump 'C' trips.

2. C (BOP SRO) Main feedwater regulating valve (AE FK-530) will fail closed in automatic over a 2 minute period.

3. I (ATC SRO) T S (SRO) PZR pressure channel (BB PI-457) fails low.

4. I (BOP SRO) TS (SRO) HP Turbine 1st stage pressure (AC PT

-505) fails low causing rods to step in.

5. R (ATC) N (BOP SRO) Abnormal condenser vacuum requiring load decrease

. 6. M (ALL) 500 gpm SGTR in 'B' S/G

- PRA#5. 7. Loss of off

-site power when reactor is tripped

- PRA#1 (drives CT1 to start at least one EDG)

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 2 of 6 Rev 1 8. MSIVs fail open and cannot be closed.

(drives EMG C

-31, SGTR WITH LOSS OF REACTOR COOLANT

- SUBCOOLED RECOVERY DESIRED procedure entry) 9. C (ATC) Both EDGs fail to auto start.

CT 1: Manual start of at least one EDG prior to placing safeguards equipment in pull

-to-lock in step 15 of EMG C

-0 10. C (BOP) 'B' MDAFW throttle valve (AL HK-9A) fails open.

CT 2: Terminate AFW to the Ruptured B S/G within 18 min of safety injection initiation.

(N)ormal, (R)eacti v i t y , (I)nstrument, (C)omponent, (M)ajor A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 3 of 6 Rev 1 Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Malfunctions after EOP entry (1

-2) 2 (events 9,10

) 2. Abnormal events (2

-4) 4 (events 1,2,3,4)

3. Major transients (1

-2) 1 (event 6)

4. EOPs entered/requiring substantive actions (1

-2) 1 (E-3) 5. EOP contingencies requiring substantive actions (0

-2) 1 (C-31) 6. EOP based Critical tasks (2

-3) 2 (events 9,10)

7. Critical Task Justification References CT: Manual start of at least one EDG prior to placing safeguards equipment in pull

-to-lock in step 15 of EMG C

-0. Failure to energize an ac emergency bus constitutes mis

-operation or incorrect crew performance in which the crew does not prevent "degraded -

emergency power capacity." Failure to perform the critical task also results in needless "degradation of any barrier to fission product release," specifically of the RCS barrier at the point of the RCP seals.

BD-EMG E-0 , REACTOR TRIP OR SAFETY INJECTION, Rev 26A. CT: Terminate AFW to the Ruptured B S/G within 18 min of safety injection

. TCA USAR 15.6.3, NE 05

-0037 (prevent overfill of the ruptured S/G). AI 21-016, OPERATOR TIME CRITICAL ACTIONS VALIDATION, Rev 10.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 4 of 6 Rev 1 SCENARIO #

3 NARRATIVE Turnover: Scenario starts with the unit at 100% power. Service Water pump 'B' is tagged out for maintenance, not expected to return this shift. The crew is to maintain 100% power. A Thunderstorm warning is in effect. T.R 3.7.8, Service Water System, Condition A, has been entered due to the 'B' service water pump

. Event 1: Service Water pump 'C' trips.

The Low Flow pump cannot increase service water pressure enough - PRA #3. The crew will put both ESW trains in service IAW ALR 00-008B, SERV WTR PRESS HILO. SRO enters T.R 3.7.8, Service Water System, Conditions B and C

. Condition A was already in effect for Service Water pump 'B'.

Event 2: Main feedwater regulating valve (AE FK-530) will fail closed in automatic over a 2 minute period. The crew will mitigate the event using ALR 00

-110A, SG C LEV HI/LO or ALR 00-110B, SG C LEV DEV. The BOP will place AE FV

-530 in manual and restore level to program as directed by the SRO. The BOP will maintain manual control of 'C' steam generator level.

Event 3: PZR pressure channel (BB PI-457) fails low.

The crew will perform OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment K, PZR PRESSURE MALFUNCTIONS. The ATC will place the PZR master controller in manual, control pressure, and then select an alternate control channel. The SRO will direct placing the PZR master controller back in auto once pressure is stabilized. SRO will enter T.S. 3.3.1, Reactor Trip System Instrumentation, Conditions A, E, and M, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Conditions A, D, and L. Event 4: HP Turbine 1st stage pressure (AC PT-505) fails low causing rods to step in.

The ATC will place rods in manual after verifying no turbine runback. The BOP will identify the failure and the crew will enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment D

, TURBINE IMPULSE PRES SURE CHANNEL MALFUNCTION, to select an alternate channel for control. SRO will enter TS 3.3.1 , Reactor Trip System Instrumentation, Condition A and T. Event 5: Abnormal condenser vacuum requiring load decrease using OFN AF-025, UNIT LIMITATIONS, ATTACHMENT F, LOSS OF CONDENSER VACUUM. Crew will reduce turbine loading using GEN 00

-004, POWER OPERATION or OFN MA-038, RAPID PLANT SHUTDOWN

. Event 6: 500 gpm SGTR in 'B' S/G - PRA#5. The crew will notice RCS pressure lowering and or 'B' S/G MFRV more closed compared to the non

-affected S/Gs. The crew will trip the reactor or an auto SI will trip the reactor. Crew will perform EMG E

-0, REACTOR TRIP OR SAFETY INJECTION

. SRO may try and enter OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, which will have the crew trip if PZR level cannot be maintained.

Event 7: At the time of the reactor trip a Loss of off

-site power

- PRA#1. (drives CT1 to start at least one EDG)

Event 8: MSIVs fail open and cannot be closed.

(drives EMG C

-31, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED procedure entry)

Event 9: Both EDGs fail to auto start. The ATC will start both EDGs per immediate action steps of EMG E-0, REACTOR TRIP OR SAFETY INJECTION.

CT 1: Manual start of at least one EDG prior to placing safeguards equipment in pull

-to-lock in step 15 of EMG C

-0.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 5 of 6 Rev 1 Event 10: 'B' MDAFW throttle valve (AL HK-9A) fails open. Once the crew determines the 'B' S/G is ruptured per foldout page of EMG E

-0, REACTOR TRIP OR SAFETY INJECTION, the BOP will isolate the 'B' S/G. The BOP will stop the 'A' MDAFW P and dispatch an operator to locally isolate AL HV

-9. After the local operator closes AL HV

-9 the BOP will restart the 'A' MDAFWP. CT 2: Terminate AFW to the Ruptured B S/G within 18 min of safety injection initiation. The crew will continue in EMG E-0 then transition to EMG E

-3, STEAM GENERATOR TUBE RUPTURE, and finally to EMG C

-31, SGTR WITH LOSS OF REACTOR COOLANT

- SUBCOOLED RECOVERY DESIRED. After the crew restores instrument air the scenario may be terminated by the chief examiner.

Procedures entered:

ALR 00-008B, SERV WTR PRESS HILO ALR 00-110A, SG C LEV HI/LO OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment K, PZR PRESSURE MALFUNCTIONS OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment D, TURBINE IMPULSE PRESSURE CHANNEL MALFUNCTION OFN AF-025, UNIT LIMITATIONS, ATTACHMENT F, LOSS OF CONDENSER VACUUM EMG E-0, REACTOR TRIP OR SAFETY INJECTION EMG E-3, STEAM GENERATOR TUBE RUPTURE EMG C-31, SGTR WITH LOSS OF REACTOR COOLANT

- SUBCOOLED RECOVERY DESIRED

Scenario file:

ILO Scenario 3

Service Water pump 'C' trips requiring start of ESW pumps

- PRA #3 - ATC ICM bkrWS01PC t:1 d:0 k:1

S/G C FW CTRL VLV AEFV530 AUTO CTL SIG CARD FAILURE

- BOP IMF mAE08C f:15 r:30 k:2

PZR pressure channel 457 fails low

- ATC IMF mBB21C f:1692 r:60 k:3

PIMP failure ICM trACPT0505 t: 1 d:0 k:4

Abnormal condenser vacuum requiring load decrease. SROI/ATC

- R, BOP - N IMF mAD01 f:50 k:5

{P24115A.CurrValue>4.5} MMF mAD01 f:30

{P24115A.CurrValue>5.5} MMF mAD01 f:4

Loss of off

-site power when reactor is tripped.

{jpplp4} IMF mSY01 i:

-1 f:-1 ;500 gpm SGTR in 'B' S/G.

IMF mBB02B f:500 r:120 k:6

MSIVs fail open and cannot be closed.

ICM vmodABHV0011 t:1 d:0 ICM vmodABHV0014 t:1 d:0

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 6 of 6 Rev 1 ICM vmodABHV0017 t:1 d:0 ICM vmodABHV0020 t:1 d:0

EDGs fail to auto start.

IMF mNE02A i:

-1 f:-1 IMF mNE02B i:

-1 f:-1 ;'B' MDAFW valve fails open.

ICM vmodALHV0009 t:1 d:0 IRF rAL13 f:0 d:300 r:120 k:7

Close TDAFWP steam inl et IRF rAB04A f: 0 d:60 r:10 k:8

Close B SG low point drain IRF rAB03B f: 0 d:60 r:10

end file A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 1 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 1 E v en t Descrip tion: 'C' Service water pump trips T ime Po sitio n Simulator Operator: Insert key 1 at the lead examiners direction Diagnostics:

Only one service water pump is running, service water pumps discharge pressure lowering, lowering amps on C service water pump Annunciators: 8B, 9B CREW, ATC Diagnose that the one of the service water pumps has tripped.

Annunciator 9B will be entered SRO, ATC 9B, SERVICE WATER PUMP TRIP

1. Determine affected service water pump

a. Check service water pumps at least one tripped 1HS-WS001A For Pump A 1HS-WS002A For Pump B 1HS-WS003A For Pump C

- YES 1HS-WS004A For Low Flow Pump

2. Check liquid waste release using service water system for dilution flow not in progress

- NO 3. Start STBY service water pumps as necessary to establish discharge pressure greater than 85 psig

- NO 1HS-WS001A For Pump A 1HS-WS002A For Pump B 1HS-WS003A For Pump C 1HS-WS004A For Low Flow Pump NOTE: The low flow pump is available to start. The crew may not attempt to start it, if they recognize that it will not be sufficient for maintaining system pressure.

3. RNOa. Perform the following to put the required ESW trains inservice.

a. Open ESW to UHS EF HIS OPEN (TRN A)

EF HIS OPEN (TRN B)

b. Close ESW to service water system valves EF HIS CLOSED(TRN A)

EF HIS CLOSED(TRN A)

EF HIS CLOSED(TRN B)

c. Start ESW pump EF HIS-55A (PUMP A)

EF HIS-56A (PUMP B)

d. Close service water/ESW cross connect valves EF HIS CLOSED(TRN A)

EF HIS CLOSED(TRN A)

EF HIS CLOSED(TRN B)

e. Refer to SYS EF

-200, OPERATION OF THE ESW SYSTEM 4. Notify Electrical Maintenance To Determine And Correct Cause Of A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 2 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 1 E v en t Descrip tion: 'C' Service water pump trips T ime Po sitio n Service Water Pump Trip Event termination: After the crew places ESW trains in service or at the direction of the lead examiner insert key 2 Simulator Operator: Insert key 2

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 3 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 2 E v en t Descrip tion: C S/G MFRV closes in auto to 15% (manual control available)

T ime Po sitio n Simulator Operator: Insert key 2 at the lead examiners direction Diagnostics: C S/G level will lower, MFRV will close Annunciators: 110B, 110C CREW, BOP ALR 00-110B SG C LEV DEV (Memory action steps 1-3) 1. Check SG C controlling level channel

- NO 5% greater than program level OR 5% less than program level

2. Check instruments operating properly

- YES SG C controlling level channel within 6% of remaining SG C NR level channels o AE LI-539 o AE LI-553 SG C controlling steam pressure channel within 100 psig of remaining channels o AB PI-534A o AB PI-535A SG C controlling feedwater flow channel within 0.2 MPPH of other channel SG C controlling steam flow channel within 0.2 MPPH of other channel. 3. Restore SG C level to program value

a. Check feedwater control valve inservice to feed SG C

- YES o AE FK-530 b. Place feedwater control valve in manual

c. Adjust feedwater control valve as necessary to maintain program value

4. Check secondary plant conditions stable

- YES 5. Check for SG C tube leakage

- NO SG C level increasing in an uncontrolled manner OR Unexpected rise in SG C level

5. RNO return to procedure and step in effect Event termination: After the crew has the C S/G MFRV in manual or at the direction of the lead examiner insert key 3 Simulator Operator: Insert key 3

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 4 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 3 E v en t Descrip tion: PZR pressure channel BB PI

-457 fails low T ime Po sitio n Simulator Operator: Insert key 3 at the lead examiners direction Diagnostics: PZR pressure rises Annunciators: 33C CREW, ATC ALR 00-033C, PZR PRESS LO HTRS ON (Memory action steps 1

-5) 1. Check PZR pressure less than 2210 psig

- YES (failed instrument)

BB PI-455A BB PI-456 BB PI-457 - YES BB PI-458 2. Check backup heaters energized

- YES 3. Check for instrument failure

- YES a. Check PZR pressure channels within 50 psig of each other - NO o BB PI-455A o BB PI-456 o BB PI-457 o BB PI-458 a. RNO 1 place PZR pressure master CTRL in manual and control pressure

o BB PK-445A - manual b. RNO 2 go to OFN SB

-008, INSTRUMENT MALFUNCTIONS, step 1 CREW Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS

1. Check for malfunction:

Check if reactor coolant system instrument channel is malfunctioning or controller is malfunctioning:

a. Perform appropriate attachment for malfunctioning channel from table below:

Variable Channels Attachment PZR pressure P-455, P-456, P-457, P-458 Attachment K CREW Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, ATTACHMENT K, PZR PRESSURE MALFUNCTION. (Memory action steps 1

-4) SRO, ATC 1. K1. Identify failed instrument channel

a. Compare PZR pressure indications to confirm a PZR pressure channel failure

- YES o BB PI-455A o BB PI-456 o BB PI-457 o BB PI-458 2. K2. Check failed PZR pressure channel selected on PZR pressure control selector switch

- YES o BB PS-455F A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 5 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 3 E v en t Descrip tion: PZR pressure channel BB PI

-457 fails low T ime Po sitio n SRO, ATC 3. K3. Place PZR pressure master controller in manual and control pressure. o BB PS-455A 4. K4. Select alternate PZR pressure channel on PZR pressure control selector switch o BB PS-455F (P455/P456 or P455/P458)

5. K5. Take the following actions as appropriate to stop pressure control transient

a. Check PZR spray valves responding correctly

b. Check PZR control heaters operable

c. Ensure PZR PORV closed

- YES o BB HIS-455A o BB HIS-456A 6. K6. Return PZR pressure control to auto o Spray Valves o Control Heaters o Backup Heaters (using SYS BB

-203) as desired o Open PORV Block Valves o Pressurizer Pressure Control

7. K7. Monitor PZR pressure response to ensure proper control

8. K8. Check failed PZR pressure channel not selected on PZR pressure recorder selector

- NO o BB PS-455G 9. K9. Check failed pressure channel not selected on OPDT/OTDT loop recorder selector switch

- NO o SC TS-411E 10. K10. Monitor the following TS LCOs and comply with action statements as appropriate

3.3.1 Conditions

A, E and M

- 72 hrs 3.3.2 Conditions A, D, and L

- 1hr. 11. K11. Place Appropriate Reactor Trip/Safeguards Bistables For Failed Pressure Channel In TRIPPED Mode:

12. K12. Request I&C to repair the failed channel Event termination: After the crew has selected an alternate controlling pressure channel and the SRO has determined TS or at the direction of the lead examiner insert key 4 Simulator Operator: Insert key 4

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 6 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 4 E v en t Descrip tion: AC PI-505 (HP turbine impulse channel) failure low T ime Po sitio n Simulator Operator: Insert key 4 at the lead examiners direction Diagnostics: Rods inserting in auto, AC PI

-505 indicating 0 psig, power lowering Annunciators: 82B CREW Enter OFN SB-008, INSTRUMENT MALFUNCTIONS

1. Check for malfunction:

Check if secondary system instrument channel is malfunctioning:

a. Perform appropriate attachment for malfunctioning channel from table below:

Variable Channels Attachment Turbine impulse pressure P-505 P-506 Attachment D ATC, BOP Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, ATTACHMENT C, TURBINE IMPULSE PRESSURE CHANNEL MALFUNCTION. (Memory action steps 1

-2) 1. D1. Identify failed instrument channel

a. Compare HP turbine 1 st stage pressure indications to confirm a pressure channel failure AC PI-505 AC PI-506 b. Determine which channel is failed by comparing actual indications with expected indications using table below:

2. D2. Place rod bank auto/man selector in manual SE HS-9 3. D3. Check failed HP turbine 1 st stage pressure channel selected on HP turbine 1 st stage pressure selector switch

- YES AC PS-505Z 4. D4. Select Alternate HP TURBINE 1ST STG PRESS Channel, Using HP TURB 1ST STG PRESS SEL Switch.

a. AC PS-505Z b. Check Tref indication normal - YES NPIS point BBT096A BB TR-412 5. D5. Check Tavg within 1F of Tref

6. D6. Place rod bank auto/man selector in auto SE HS-9 7. D7. Place steam dump bypass interlock to off AB HS-63 AB HS-64 8. D8. Monitor od control response to ensure proper control

9. D9. Check C-7 loss of load interlock not lit

- NO A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 7 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 4 E v en t Descrip tion: AC PI-505 (HP turbine impulse channel) failure low T ime Po sitio n SRO, BOP 10. D10. Select steam pressure mode

a. Set steam header pressure control to 7.28 AB PK-507 b. Place steam dump selector in steam pressure mode AB US-500Z 11. D11. Place steam dump bypass interlock to on AB HS-63 AB HS-64 12. D12. Monitor the following TS for LCOs and comply with action statements as appropriate

3.3.1 Condition

A and T

- 1 hr. 13. D13. Place the trip/safeguards bistables for failed channel in tripped mode Event termination: After the crew has an alternate impulse channel selected and rods are back in auto or at the direction from the lead examiner insert key 5 Simulator Operator: Insert key 5

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 8 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 5 E v en t Descrip tion: Abnormal condenser vacuum requiring a load decrease T ime Po sitio n Simulator Operator: Insert key 5 at the lead examiners direction Diagnostics: Loss of condenser vacuum (all), electrical load lowering Annunciators: 115D, TSC graphics orange condenser vacuum indications, red turbine manual action alarm CREW Enter OFN A F-025, UNIT LIMITATIONS

1. Determine applicable step

f. Check condenser vacuum normal

- NO f. RNO go to attachment F, Loss of condenser vacuum CREW OFN A F-025, UNIT LIMITATIONS, Attachment F, LOSS OF CONDENSER VACUUM

1. F1. Check LP turbine exhaust pressure

a. Less than or equal to 5" as indicated on graphic display 5551

- NO COND A PRESS COND B PRESS COND C PRESS

b. IF exhaust pressure is higher than normal for current plant conditions, THEN dispatch personnel to check for air inleakage, while continuing with step F4.

NOTE: If the crew gets here and vacuum has not yet degraded to 5" or more the crew may go to step F1b. If not they will go to step F2.

2. F2. Check turbine power greater than 30%

- YES 3. F3. Check the following parameters

a. Check LP turbine exhaust pressure is operating in the normal operating region per figure 2

- NO a. RNO. Reduce turbine load per GEN 00

-004, POWER OPERATION, or OFN MA

-038, RAPID PLANT SHUTDOWN, as necessary to establish LP turbine pressure within the normal operating region per figure 2 while continuing with step F4 4. Check circ water system normal

- YES Lead Examiner: Prompt SRO from the SM that the unit load is to be lowered using OFN MA

-038, RAPID PLANT SHUTDOWN, reduce load at 3%/minute, in automatic, using Open loop.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 9 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 5 E v en t Descrip tion: Abnormal condenser vacuum requiring a load decrease CREW Enters OFN MA

-038, RAPID PLANT SHUTDOWN

1. Determine turbine unloading method to be used

a. Check desired unloading rate less than or equal to 65 MW/minute

- YES b. Check automatic turbine unloading desired

c. From graphic 5551 turbine control system operation panel load control section select method of load control as directed by CRS/SM First stage pressure Megawatts Open loop 2. Reduce turbine load in automatic

a. From graphic 5551 turbine control system operation panel setpoints section reduce turbine load Select change Enter target MW Enter rate Select go b. Maintain desired turbine unloading rate.

c. Go to step 4

4. Borate RCS and adjust control rods as necessary to maintain the following Target Tavg/Tref temperature error between 0F and +5F Control rods above the rod insertion limits

5. Energize PZR backup heaters BB HIS-51A BB HIS-52A 6. Check PZR PORVs

a. RCS pressure less than 2335 psig

- YES b. PZR PORVs closed

- YES c. RCS pressure greater than 2185 psig

- YES d. PORV block valves open

- YES 7. Check PZR pressure stable at or trending to 2235 psig

- YES 8. Check PZR level stable at or trending to program level

- YES 9. Check SG levels controlling between 45% and 55%

- YES 10. Notify HP to perform the following Monitor RCS and other connecting systems for increasin g radiation levels due to unplanned crud burst Notify all personnel in the affected areas

11. Check if sampling is required

a. Check if one of the following conditions is met Thermal power change greater than 15% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

- YES b. Direct chemistry to take samples per AP 02-007, ABNORMAL CONDITIONS GUIDELINES.

Simulator Operator: When contacted as HP acknowledge request, when contacted as Chemistry acknowledge request.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 10 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 5 E v en t Descrip tion: Abnormal condenser vacuum requiring a load decrease Event termination: When the crew has lowered approximately 5% power or at the direction from the lead examiner enter key 6 Simulator Operator: Enter key 6

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 11 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 6, 7, 8, 9, 10 E v en t Descrip tion: 500 gpm SGTR in B S/G T ime Po sitio n Simulator Operator: Insert key 6 at the lead examiners direction Diagnostics: B S/G level rise (until MFRV closes), MFRV closed more than the other S/G, Rad alarms on RM11, RCS pressure lowering Annunciators: 61A, 61B CREW Based on RCS pressure lowering in an uncontrolled manor the crew may choose to SI and enter EMG E

-0, REACTOR TRIP OR SAFETY INJECTION. The crew may try to enter OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, which off of foldout page the crew will maximize charging which will not correct the issue and will be directed to EMG E-0. CREW Enter EMG E

-0, REACTOR TRIP OR SAFETY INJECTION Perform immediate actions

1. Verify reactor trip

a. Check all rod bottom lights - lit - YES b. Check reactor trip breakers and bypass breakers

- open - YES SB ZL-1 SB ZL-2 SB ZL-3 SB ZL-4 c. Check intermediate range neutron flux

- decreasing

- YES SE NI-35B (gamma metrics)

SE NI-36B (gamma metrics)

2. Verify turbine trip

a. Check main stop valves all closed

- YES 3. Check AC emergency busse s - at least one energized

- NO 3. RNOa. Depress start/reset pushbutton for any stopped diesel generator KJ HS-8A for EDG A KJ HS-108A for EDG B

3. RNOb. If at least one AC emergency bus is now energized then go to step 4 NOTE: Both EDGs will fail to auto start on the SI but can be started manually from the control room by the ATC operator.

CT: Manual start of at least one EDG prior to placing safeguards equipment in pull

-to-lock in step 15 of EMG C

-0. CREW 4. Check if SI is actuated

a. Check any indication SI is actuated

- lit Annunciator 00

-030A NF039A LOCA SEQ ACTUATED

- LIT - YES Annunciator 00

-031A NF039B LOCA SEQ ACTUATED

- LIT - YES ESFAS status panel SIS section

- any white lights lit

- YES A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 12 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 6, 7, 8, 9, 10 E v en t Descrip tion: 500 gpm SGTR in B S/G T ime Po sitio n Partial trip status permissive/block status panel

- SI red light lit

- YES b. Check both trains of SI actuated

- YES Ann 00-030A, NF039A LOCA SEQ ACTUATED

- LIT Ann 00-031A, NF039A LOCA SEQ ACTUATED

- LIT NOTE: The SRO will now perform a verification of the immediate actions by performing a read through of the steps provided above.

CREW 5. Check if SI is required SI was manually actuated and was required

- YES/NO Containment pressure is currently or has been

- greater than or equal to 3.5 psig

- NO RCS pressure is currently or has been

- less than or equal to 1830 psig

- YES Any SG pressure is currently or has been less than or equal to 615

- NO 6. Verify auto actions using attachment F, auto signal verification

7. Check main generator breakers and exciter breaker

- open - YES MA ZL-3A MA ZL-4A MA ZL-2 8. Check total AFW flow greater than 270,000 lbm/hr

- YES NOTE: Attachment F actions are on page 15.

NOTE: Foldout page item #7 to throttle AFW flow will be performed and the B MDAFWP flow control valve will fail open. This is also the SG that the SGTR is on.

The crew may stop the A MDAFWP and throttle closed the TDAFWP flow control valves to stop feeding the B SG as long as total AFW flow is maintained greater than 270,000 lbm/hr until at least one SG NR level is greater than 6%.

Simulator Operator: When contacted as building watch to go close B MDAFWP flow control valve acknowledge request. Report back that the valve has been isolated.

CT: Terminate AFW to the Ruptured B S/G within 18 min of safety injection

. CREW 9. Check RCS cold leg temperatures Stable at or trending to 557F for condenser steam dumps or SG ARVs

- YES Stable at or trending to a range of 553F to 557F for SG ARVs if recovering from an inadvertent SI

10. Establish SG pressure control

a. Check condenser available - NO C-9 lit MSIV open

- YES Circ water pumps running

- NO a. RNO use SG ARVs

a. RNO Go to step 11

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 13 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 6, 7, 8, 9, 10 E v en t Descrip tion: 500 gpm SGTR in B S/G T ime Po sitio n NOTE: Foldout page item #7 will have the crew close MSIVs with the loss of offsite power but they will not close. This failure drives the crew to a contingency procedure later in the scenario.

CREW 11. Check PZR PORVs

a. Check PZR PORVs closed

- YES BB HIS-455A BB HIS456B

b. Power to block valves available

- YES BB HIS-8000A BB HIS-8000B CREW c. RCS pressure less than 2185 psig

- YES 12. Check normal PR spray valves closed

- YES BB ZL-455B BB ZL-455C 13. Check PZR safety valves closed

- YES BB ZL8010A BB ZL8010B BB ZL8010C

14. Check if RCPs should be stopped

a. Check RCPs any running

- NO go to step 15

15. Direct Operator To Monitor Critical Safety Functions Using EMG F-0, CRITICAL SAFETY FUNCTION STATUS TREES (CSFST).

16. Check if SG are not faulted

- YES a. Check pressure in all SG No SG pressure decreasing in an uncontrolled manner No SG completely depressurized

17. Check if SG tubes are intact

- NO Check SG levels not increasing in an uncontrolled manne r Condenser air discharge rad normal before iso o GEG 925 SG blowdown and sample rad normal before iso o BML 256 o SJL 026 TDAFWP exhaust rad normal SG steamline rad normal o ABS 114 for S/G A o ABS 113 for S/G B o ABS 112 for S/G C o ABS 111 for S/G D 17. RNOa. Direct HP to survey steamlines in area 5 of the Aux building b. Ensure BIT inlet and outlet valves are open o EM HIS-8803A o EM HIS-8803B o EM HIS-8801A A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 14 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 6, 7, 8, 9, 10 E v en t Descrip tion: 500 gpm SGTR in B S/G T ime Po sitio n o EM HIS-8801B CREW c. Check SG B or C ruptured

- YES o Dispatch operator to locally close steam supply to TDAFWP from ruptured SG o AB-V085 for SG B o AB-V087 for SG C Simulator Operator: When contacted as building watch to close AB

-V085 acknowledge request. Report back that the valve is closed

d. Go to EMG E

-3, STEAM GENERATOR TUBE RUPTURE, step 1 NOTE: EMG E

-3 steps on page 18

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 15 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: F E v en t Descrip tion: EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Attachment F T ime Po sitio n ATC, BOP F1. Check AC emergency busses energized NB01 - energized

- YES/NO o Depress Start/Stop pushbutton for EDG A o KJ HS-8A NB02 - energized

- YES/NO o Depress Start/Stop pushbutton for EDG B o KJ HS-108A F2. Verify feedwater isolation

a. Main feedwater pumps tripped

- YES Annunciator 00

-120A, MFP A trip

- lit - YES Annunciator 00

-123A, MFP B trip

- lit - YES b. Main feedwater reg valves closed

- YES AE ZL-510 for S/G A AE ZL-520 for S/G B AE ZL-530 for S/G C AE ZL-540 for S/G D c. Main feedwater reg bypass valves closed

- YES AE ZL-550 for S/G A AE ZL-560 for S/G B AE ZL-570 for S/G C AE ZL-580 for S/G D

d. Main feedwater isolation valves closed

- YES AE HIS-39 for S/G A AE HIS-40 for S/G B AE HIS-41 for S/G C AE HIS-42 for S/G D

e. Main feedwater chemical injections valves closed

- YES AE HIS-43 for S/G A AE HIS-44 for S/G B AE HIS-45 for S/G C AE HIS-46 for S/G D

f. Check ESFAS status panel SGBSIS section all white lights lit

-YES Red train Yellow train F3. Verify containment isolation phase A a. Check ESFAS status panel CISA section all white lights lit

- YES Red train Yellow train F4. Verify AFW pumps running

a. Check motor driven AFW pumps both running

- YES b. Check TDAFWP running

- YES A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 16 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: F E v en t Descrip tion: EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Attachment F T ime Po sitio n ATC, BOP F5. Verify ECCS pumps running

a. Check CCPs both running

- YES b. Check SI pumps both running

- YES c. Check RHR pumps both running

- YES F6. Verify CCW alignment

a. Check CCW pumps one running in each train

- YES b. Check one pair of CCW service loop supply and return valves for an operating CCW pump

- open - YES F7. Check ESW pumps both running

- YES F8. Check containment fan coolers running is slow speed

- YES F9. Verify containment purge iso

- YES a. Check ESFAS status panel CPIS section all white lights lit Red train Yellow train F10. Verify both trains of control room ventilation iso

- YES a. Check ESFAS status panel CRVIS section all white lights lit

- YES Red train Yellow train

b. Ensure control room outer door closed F11. Verify main steam line iso not required

- YES a. Check containment pressure has remained less than 17 psig

b. Check either conditions below satisfied Low steamline pressure SI not blocked and steamline pressure has remained greater than 615 psig

- YES F12. Verify containment spray not required

- YES a. Containment pressure has remained less than 27 psig F13. Verify ECCS flow

a. Check CCP to boron injections tank flow meters flow indicated

- YES EM FI-917A EM FI-917B b. Check RCS pressure less than 1725 psig

- YES c. Check SI pump discharge flow meters flow indicated

- YES EM FI-918 EM FI-922 d. Check RCS pressure less than 325 psig

- NO d. RNO go to step 14 F14. Verify AFW valves properly aligned

- YES/NO a. Check ESFAS status panel AFAS section all white lights lit

b. Check white train ESFAS status panel AFAS section all white lights lit F14. RNO if any AFAS section component not properly aligned then manually align associated component to establish desired AFAS lineup.

NOTE: If the crew has not sent the building watch out to isolate the B MDAFWP flow control valve this is where the procedure will catch the failed open valve and close it.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 17 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: F E v en t Descrip tion: EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Attachment F T ime Po sitio n Simulator Operator: When/If contacted to close the B MDAFWP flow control valve acknowledge request. Report back the valve has been closed.

ATC, BOP F15. Verify SI valves properly aligned

a. Check ESFAS status panel SIS section system level white lights all lit - YES Red train Yellow train F16. Check if NCP should be stopped

a. CCPs any running

b. Stop NCP BG HIS-3 F17. Dispatch Operator To Locally Close The Following Terry Turbine Steam Drains:

FC-V048 (2000' TDAFW Pump Room)

FC-V070 (2000' TDAFW Pump Room)

FC-V089 (2000' TDAFW Pump Room)

Simulator Operator: When contacted to close TD steam drains acknowledge request. Report back that drains have been closed.

F18. Return to procedure and step in effect

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 18 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 6 E v en t Descrip tion: EMG E-3, STEAM GENERATOR TUBE RUPTURE T ime Po sitio n CREW EMG E-3, STEAM GENERATOR TUBE RUPTURE 1. Check if RCPs should be stopped

a. Check any RCPs running

- NO a. RNO observe caution prior to step 2 go to step 2

2. Identify ruptured SG Level increasing in an uncontrolled manner OR High turbine driven AFW exhaust radiation OR o FCT 381 High rad from and SG steamline rad monitor OR o ABS 114 For S/G A o ABS 113 For S/G B o ABS 112 For S/G C o ABS 111 For S/G D High rad from any SG steamline survey OR High rad from any SG sample NOTE: By this time the crew will have identified the ruptured SG as B.

3. Isolate flow from the ruptured SG

a. Adjust ruptured SG ARV controller setpoint to 1160 psig

b. Check ruptured SG ARV closed

- YES c. Locally close steam supply to Turbine Driven AFW Pump from ruptured S/G(s).

AB-V085 For S/G B (MAIN STEAM ENCLOSURE BELOW GRATING)

AB-V087 For S/G C (MAIN STEAM ENCLOSURE BELOW GRATING)

d. Locally isolate main steamline low point drain valve(s) from ruptured S/G(s).

Close AB-V062 For S/G A (MAIN STEAM ENCLOSURE BELOW GRATING)

Close AB-V072 For S/G B (MAIN STEAM ENCLOSURE BELOW GRATING)

Close AB-V082 For S/G C (MAIN STEAM ENCLOSURE BELOW GRATING)

Close AB-V052 For S/G D (MAIN STEAM ENCLOSURE BELOW GRATING)

Simulator Operator: When contacted to close valves acknowledge request. Report back valves are closed. 4. Verify blowdown lower and upper sampling isolated on ruptured SG a. AG blowdown CTMT iso valves closed

- YES BM HIS-1A For S/G A BM HIS-2A For S/G B BM HIS-3A For S/G C BM HIS-4A For S/G D

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 19 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 6 E v en t Descrip tion: EMG E-3, STEAM GENERATOR TUBE RUPTURE

b. SG upper sample iso valves closed

- YES BM HIS-19 For S/G A BM HIS-20 For S/G B BM HIS-21 For S/G C BM HIS-22 For S/G D

c. SG lower sample iso valves closed

- YES BM HIS-35 For S/G A BM HIS-36 For S/G B BM HIS-37 For S/G C BM HIS-38 For S/G D

5. Isolate steamline on ruptured SG

a. Close main steamline iso valve

- NO AB HIS-14 For S/G A AB HIS-17 For S/G B AB HIS-20 For S/G C AB HIS-11 For S/G D

b. Ensure main steamline iso bypass valves closed

- NO AB ZL-15A For S/G A AB ZL-18A For S/G B AB ZL-21A For S/G C AB ZL-12A For S/G D

1. RNO ensure main steamline iso valves closed

- NO AB HS-79 AB HS-80 2. RNO if ruptured SG MSIV is not closed or MSIV associated with at least one intact SG is not closed then in SA075A or SA075B disconnect A and B solenoid fuses (4 fuses total) for the affected valve (s) Fuses for AB HV

-14 Fuses for AB HV

-17 Fuses for AB HV

-20 Fuses for AB HV-11 Lead Evaluator: The crew will send an operator behind the panels to remove this fuses (these are not modeled in the simulator). After the operator goes behind the panel and he describes what action he will perform, inform the operator that the fus e s have been removed but the valves DID NOT close.

3. Perform the following:

a. Ensure MS ISO BYPASS VLVS CTRL is in MAN with 0% output.

AB HIK MAN/0% b. IF all MSIV Bypass Valves are NOT closed, THEN locally close:

AB HV-15 (MAIN STEAM ENCLOSURE ABOVE GRATING) AB HV-18 (MAIN STEAM ENCLOSURE ABOVE GRATING) AB HV-21 (MAIN STEAM ENCLOSURE ABOVE GRATING) AB HV-12 (MAIN STEAM ENCLOSURE ABOVE GRATING)

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 20 of 21 O p-Tes t No.: Nov. 2015 Scenari o No.: 3 E v en t No.: 6 E v en t Descrip tion: EMG E-3, STEAM GENERATOR TUBE RUPTURE

4. IF ruptured S/G MSIV is NOT closed, THEN perform the following:

a. Isolate steam header, using Attachment A, MAIN STEAM HEADER ISOLATION

- CONTROL ROOM, while continuing with this procedure.

b. Direct operator to locally isolate steam header, using Attachment B, MAIN STEAM HEADER ISOLATION

- LOCAL 5. Use intact SG ARVs for steam dump 6. IF at least one S/G MSIV and its associated Bypass Valve are NOT closed, THEN go to EMG C

-31, SGTR WITH LOSS OF REACTOR COOLANT

- SUBCOOLED RECOVERY DESIRED, Step 1.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 21 of 21 O p-Tes t No.: Nov. 201 5 Scenari o No.: 3 E v en t No.: 6 E v en t Descrip tion: EMG C-31, SGTR WITH LOSS OF REACTOR COOLANT

- SUBCOOLED RECOVERY DESIRED T ime Po sitio n CREW EMG C-31, SGTR WITH LOSS OF REACTOR COOLANT

- SUBCOOLED RECOVERY DESIRED

1. Reset SI SB HS-42A SB HS-43A 2. Reset CTMT iso Phase A and B SB HS-56 For Phase A SB HS-53 For Phase A SB HS-55 For Phase B SB HS-52 For Phase B

3. Verify Instrument air compressor is running

a. Ensure at least one ESW train to air compressor valve is open

- YES EF HIS-43 EF HIS-44 b. Check air compressor breaker reset switch associated with open ESW valves closed KA HIS-3C KA HIS-2C c. Check INST air pressure greater than 105 psig KA PI-40 d. Check neither ESW to air compressor valve locally opened EF HV-43 EF HV-44 e. Check both ESW train to air compressor valves open EF HIS-43 EF HIS-44 f. Check both air compressor breaker reset switches closed KA HIS-3C KA HIS-2C 4. Verify instrument air to CTMT

a. Check PZR pressure master CTRL output less than 55%

- YES BB PK-455A b. Open INST air supply CTMT iso valve KA HIS-29 Scenario termination: After the crew enters C

-31 and takes an action or at the direction of the lead examiner the scenario is completed Simulator Operator: Place the simulator in freeze.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 1 of 5 Rev 1 Facili t y: Wolf Creek Scenari o No.: 4 (New) O p-Tes t No.: Nov 2015 E x a miners: Opera tors: I ni t ia l Condi tions: 100% power. EDG 'A' is OOS.

Maintain power stable.

IC 30 Turno ver: T.S. 3.8.1, AC Sources Operating, Condition B

, for EDG 'A' OOS. E vent N o. M a l f. N o. E vent T y p e* E vent Descr ip t io n 1. I (ATC SRO) TS (SRO) Power range NI (SE NI-42B) fails high.

2. I (BOP SRO) TS (SRO) Steam generator pressure channel (AB PI-54 5) failure high.

3. C (ATC BOP SRO) TS (SRO) Loss of NN02 Instrument bus.

4. R (ATC) TS (SRO) N (BOP SRO) Loss of Wolf Creek

-Benton 345 kV offsite line.

5. M (A LL) Inadvertent SI 'B' Train.

CT 1: Isolate BIT inlet and outlet valves within 8 minutes from initiation

. 6. 'B' EDG fails to start in auto and manual

7. C (ATC SRO) Loss of all AC.

CT 2: Energize either NB01 or NB02 using SYS KU-121 or SYS KU

-122 before core cooling requirements specified in EMG C-0 Step 29 are no longer met. * (N)ormal, (R)eacti v i t y , (I)nstrument, (C)omponent, (M)ajor A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 2 of 5 Rev 1 Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Malfunctions after EOP entry (1

-2) 1 (event 6)

2. Abnormal events (2

-4) 3 (events 1,2,3)

3. Major transients (1

-2) 1 (event 5)

4. EOPs entered/requiring substantive actions (1

-2) 1 (event 5 EMG ES

-03) 5. EOP contingencies requiring substantive actions (0

-2) 1 (EMG C-0) 6. EOP based Critical tasks (2-3) 2 (events 5,7

) 7. Critical Task Justification References CT 1: Isolate BIT inlet and outlet valves within 8 minutes from ECCS initiation

. TCA USAR 15.5.1; Terminate ECCS injection following an inadvertent ECCS operation event (Close BIT inlet and outlet isolation valves) within 8 minutes from initiation.

AI 21-016, OPERATOR TIME CRITICAL ACTIONS VALIDATION, Rev 10. CT 2: Energize either NB01 or NB02 using SYS KU

-121 or SYS KU-122 before core cooling requirements specified in EMG C-0 Step 29 are no longer met

. Energizing at least one NB bus in a timely manner ensures RCS integrity does not become an issue. BD-EMG C-0, LOSS OF ALL AC POWER, Rev 21.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 3 of 5 Rev 1 SCENARIO #

4 NARRATIVE Turnover: 100% power. EDG 'A' is OOS.

Maintain power stable. T.S. 3.8.1, AC Sources Operating, Condition B for EDG 'A' OOS. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months remain to restore EDG 'A' to operable condition.

Event 1: Power range NI (SE NI

-42B) fails high.

The ATC will have to determine that there is no turbine runback in progress and place rods in manual to stop inward rod motion. The crew will diagnose the failure and enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment R, POWER RANGE NEUTRON FLUX CHANNEL MALFUNCTION. ALR 00-078A, 82A, and 83C will come in and they could use any of these to get to the OFN as well. T he crew bypasses the channel and restores rods to auto. The SRO will determine TS 3.3.1, Reactor Trip System Instrumentation, Condition A, D, E, S, and T

. Event 2: Steam generator pressure channel (AB PI

-5 4 5) failure high.

The crew could notice steam flow from the 'A' S/G indicating higher than the other S/G or level rising. ALR 00

-108B, SG A LEV DEV, will come in. This will have the crew place the MFRV in manual and control level. The SRO will enter OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment C, SG PRESSURE CHANNEL MALFUNCTION, which will perform the same actions plus have the crew select an alternate steam pressure channel for control. The SRO will enter TS 3.3.2, Engineered Safety Features Actuation System Instrumentation, Condition A and D. Event 3: Loss NN02 Instrument bus.

The SRO will direct OFN NN

-021, LOSS OF VITAL 120 VAC INSTRUMENT BUS, Attachment B, LOSS OF VITAL INSTRUMENT BUS NN02 (WHITE TRAIN)

. The ATC will select the alternate PZR pressure channel for control, adjusting pressure control as needed and then select an alternate channel for PZR level control. The BOP will select the red train instruments for S/G level and steam flow. Once the alternate channels are selected, the NN02 bus may be reenergize

d. SRO will enter TS 3.8.7, Inverters Operating, Condition A, TS 3.3.1, Reactor Trip System Instrumentation, Condition A, S, and T, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Condition A and L for the NN bus

. Event 4:

Loss of Wolf Creek

-Benton 345 kV offsite line

. The crew will enter OFN AF-025, UNIT LIMITATIONS, Attachment A , U N IT LOAD LIMITS, reducing unit load to less than 800 MWE NET (845 MWE GROSS). SRO will enter T.S. 3.8.1, AC Sources Operating, Conditions A and E as the 'A' EDG is also OOS. 3.8.1, AC Sources Operating, Condition B was in effect at turnover

. SRO will also enter TR 3.8.1 , Offsite Power System Transmission Network, Condition A.

Event 5: Inadvertent SI 'B' Train.

The crew will enter EMG E-0, REACTOR TRIP OR SAFETY INJECTION. The crew will actuate both trains of SI and then reset SI and continue with the procedure.

CT 1: Isolate BIT inlet and outlet valves within 8 minutes from initiation

. Event 6: 'B' EDG fails to start in auto and manual.

(drives the CT2 with the loss of both EDGs)

Event 7: Loss of all AC (PRA). The crew will enter EMG C-0 , LOSS OF ALL AC POWER. The crew will be able to restore power from the SBO diesels to either NB bus using OFN NB

-030, LOSS OF AC EMERGENCY BUS NB01 (NB02). The OFN will direct the crew to SYS KU

-121, ENERGIZING NB01 FROM STATION BLACKOUT DIESEL GENERATORS. Only one safeguards bus can be energized by the SBO diesels at a time.

CT 2: Energize either NB01 or NB02 using SYS KU

-121 or SYS KU

-122 before monitoring RCS integrity is required.

The crew will energize an NB bus then continue with EMG C

-0, LOSS OF ALL AC POWER, and then transition to EMG CS-0 1 , LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED. After the crew restarts instrument air the scenario may be terminated by the chief examiner.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 4 of 5 Rev 1 Procedures entered:

OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment R, POWER RANGE NEUTRON FLUX CHANNEL MALFUNCTION OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment C, SG PRESSURE CHANNEL MALFUNCTION OFN NN-021, LOSS OF VITAL 120 VAC INSTRUMENT BUS, Attachment B, LOSS OF VITAL INSTRUMENT BUS NN02 (WHITE TRAIN)

OFN AF-025, UNIT LIMITATIONS, Attachment A, UNIT LOAD LIMITS EMG E-0, REACTOR TRIP OR SAFETY INJECTION EMG C-0, LOSS OF ALL AC POWER o OFN NB-030, LOSS OF AC EMERGENCY BUS NB01 (NB02) o SYS KU-121, ENERGIZING NB01 FROM STATION BLACKOUT DIESEL GENERATORS EMG CS-01, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED Scenario file:

ILO Scenario 4

Tag out 'A' EDG scn SimGroup

\TAGDGA {jb061a}DMF mSP18P

power range N

-42 fails hi IMF mSE03B f:120 r:10 k:1

Ab PI-545 fails hi D SG IMF mAB01D2 f: 1313 r:10 k:2

loss of NN02

IRF rNN02B f:0 k:3 IRF rNN02C f:0 k:3

give the crew NN02 back

modify rNN02B to close

Loss of Wolf Creek

-Benton 345 kV offsite line IMF mSY03F i:

-1 f:-1 k:4 ;Inadvertent SI, train 'B' IMF mSA01B i:

-1 f:-1 k:5 ;Loss of all AC IMF mSY01 i:

-1 f:-1 k:6 IMF mNE01B f:0

close RCP seals scn SimGroup

\ ;Energize NB01 from SBO diesels

{Key[9]}scn SimGroup

\NF39A 8N28 OFF {Key[10]}scn SimGroup

\SBO Start and Energize NB01 ;Energize NB02 from SBO diesels

{Key[11]}scn SimGroup

\NF39B 8N28 OFF A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 5 of 5 Rev 1 {Key[12]}scn SimGroup

\SBO Start and Energize NB02

end file A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 1 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 1 E v en t Descrip tion: Power range NI, SE NI

-42B, fails high Ensure PZR level channel selected to L459/L461 prior to start of scenario T ime Po sitio n Simulator Operator: At the discretion of the lead examiner enter key 1 Diagnostics: Rods inserting, power lowering, RCS pressure lowering Annunciators: 78A, 82A, 83C ATC, BOP Reports control rods are moving in.

NOTE: Steps 1 through 3 of OFN SB

-008, Attachment R, are Memory Actions steps and may be performed prior to procedure entry.

(Memory action steps from OFN SB

-008, INSTRUMENT MALFUNCTIONS)

1. Reports SE NI

-42B failing high

2. Reports no load rejection

3. Places Rod Bank AUTO/MAN Sel Switch, SE HS

-9, in Manual SRO Enters and Directs OFN SB

-008, INSTRUMENT MALFUNCTIONS 1. Check for malfunction:

Check If Nuclear Instrumentation System Channel Is Malfunctioning:

Perform appropriate attachment for malfunctioning channel from table below:

Variable Channels Attachment Power Range SE N-42 Attachment R CREW OFN SB-008, INSTRUMENT MALFUNCTIONS , Attachment R

1. R1. Reports SE NI

-42B failing high

2. R2. Reports no load rejection

3. R3. Places Rod Bank AUTO/MAN Sel Switch, SE HS

-9, in Manual 4. R4. Bypasses Failed Power Range Flux Channel:

a. On the Detector Current Comparator Drawer (N50) perform the following

1. Turns the Upper Section switch to the fail ed power range flux channel, position 42.

2. On the Detector Current Comparator Drawer, turns the Lower Section switch to the fail ed power range flux channel, position 42.

3. On the Detector Current Comparator Drawer, turns the Power Mismatch Bypass switch to the fail ed power range flux channel, position 42.

4. On the Detector Current Comparator Drawer, turns the Rod Stop Bypass switch to the fail ed power range flux channel, position 42.

b. On the Comparator and Rate Drawer (N37/46), perform the following

1. Turns the Comparator Channel Defeat switch to the fail ed power range channel, position 42.

5. R5. Check ROD BANK AUTO/MAN SEL Switch, SE HS

-9, in A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 2 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 1 E v en t Descrip tion: Power range NI, SE NI

-42B, fails high Ensure PZR level channel selected to L459/L461 prior to start of scenario T ime Po sitio n Auto - NO 5. RNO When Tavg is within 1 degree of Tref

, places Rod Control switch, SE HS

-9, in auto.

6. R6. Monitor Rod Control System response to ensure proper control. 7. R7. Checks Failed Power Range Flux Channel not used for recording on OPdT/OTdT Recorder.

8. Verify operability of annunciator 00-79C, RPI DEV OR PR TILT, using STN RJ

-001, VERIFICATION OF OPERABILITY OF COMPUTER PROCESSES

9. R9. Verify QPTR operability

a. Check reactor power greater than 50%

- YES b. Check reactor power greater than 75%

- YES c. Perform SYS SR

-200, MOVABLE INCORE DETECTOR OPERATION every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to verify QPTR is within limits. 10. R10. Monitor The Following Technical Specification LCOs And Comply With Action Statements, As Appropriate:

NOTE: 3.3.1 Conditions A, D, E, S, and T

11. R11. Pull Control Power Fuses In Power Range Drawer For Failed Power Range Flux Channel. (Procedure allows for not pulling fuses, for INC T/S)

Simulator Operator: If contacted as WWM acknowledge report, if contacted as Call Sup acknowledge report Event termination: After the SRO completes TS or at the discretion of the lead examiner go to the next event. Simulator Operator: Enter key 2

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 3 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 2 E v en t Descrip tion: Steam generator pressure channel, AB PI

-545, fails high T ime Po sitio n Simulator Operator: Insert key 2 Diagnostics: D SG level lowering, steam flow/feedflow mismatch Annunciators: 111B, 111C BOP (Memory action steps) ALR 00-111B 1. Check SG D controlling level channel 5% greater than program

- NO 5% less than program level

- NO 2. Check instruments operating properly

a. SG D controlling level channel within 6% of remaining channels o AE LI-549 o AE LI-554 b. SG D controlling steam pressure channel within 100 psig of remaining channels o AB PI-544A - YES o AB PI-545A - NO a. RNO Perform the following

a. RNO Place MFRV in manual o AE FK-540 o AE LK-580 b. RNO adjust MFRV as necessary to establish SG level at program value o AE FK-540 o AE LK-580 c. Go to OFN SB

-008, INSTRUMENT MALFUNCTIONS OFN SB-008, INSTRUMENT MALFUNCTIONS CREW SRO, BOP Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS

1. Check for malfunction:

Check if secondary system instrument channel is malfunctioning:

a. Perform appropriate attachment for malfunctioning channel from table below:

1. C1. Identify the failed instrument channel Compare SG pressure indications to confirm SG pressure channel failure o AB PI-545A For S/G D

2. C2. Check if failed SG pressure channel used for feedwater control a. Identify steam flow channel compensated by failed pressure channel from table F-543 Variable Channels Attachment Steam pressure P-545 Attachment C

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 4 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 2 E v en t Descrip tion: Steam generator pressure channel, AB PI

-545, fails high T ime Po sitio n SRO, BOP b. Check steam flow channel associated with failed steam pressure channel selected on SG steam flow channel select switch - YES 3. C3. Check MFRV in control - YES a. Place affected SG MFRV in manual AE FK-540 b. Adjust affected SG MFRV as necessary to establish SG level at program AE FK-540 4. C4. Select alternate steam flow channel on SG steam flow channel sel switch AB FS-542C 5. C5. Restore affected SG MFRV to auto 6. C6. Monitor The Following Technical Specifications LCOs And Comply With Action Statements, As Appropriate:

3.3.2 Conditions

A and D Simulator Operator: If contacted as WWM acknowledge report, if contacted as Call Sup acknowledge report Event termination: After SRO has TS complete or at the discretion of the lead examiner insert key 3 Simulator Operator: Insert key 3

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 5 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 3 E v en t Descrip tion: Loss of NN02 due to cleaner bumped open breaker T ime Po sitio n Simulator Operator: At the discretion of the lead examiner insert key 3 Diagnostics: Multiple alarms, SB069 will show columns of white lights for the NN02 powered equipment.

Annunciators: Multiple, 26A CREW Diagnose loss of NN02 CREW ATC, BOP (Memory action steps for both the OFN and ALR)

Enters OFN NN

-021, LOSS OF VITAL 120 VAC INSTRUMENT BUS

1. Loss of NN01 or NN02 with control rods inserting

- NO 1. RNO: Go to step 2

2. Ensure SG control systems are using unaffected channels

a. BOP Selects away from all white channels Steam Flow Channel Selector Switches: AB FS

-512C, AB FS-522C, AB FS

-532C, AB FS

-542C and SG Level Selector Switches: AE LS

-519C, AE LS

-529C, AE LS

-539C, AE LS

-549C. 3. Ensure PZR control is selected to unaffected channels

a. Check pressurizer pressure channel affect. YES

b. Place Pressurizer Master Controller in Manual BB PK

-455A c. RO select alternate channel BB PS

-455F d. Adjust Pressurizer Master Controller to restore pressure to normal. BB PK

-455A e. Return Pressurizer Master Controller to auto, as direct by CRS. BB PK

-455A 4. Ensure PZR level control is selected to unaffected channels PZR unaffected NOTE: Crew will dispatch building watch to NN02 to determine cause Simulator Operator: When contacted as building watch to investigate the NN02 loss, acknowledge request. CREW 5. Check RWST switchover has occurred

- NO RNO Go to step 7

7. Stabilize plant

a. Stop any plant operations requiring rod motion

b. Adjust turbine load as necessary to maintain Tave within 3F of Tref 8. Go to appropriate attachment Loss of NN02 Attachment B

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 6 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 3 E v en t Descrip tion: Loss of NN02 due to cleaner bumped open breaker T ime Po sitio n CREW OFN NN-021, LOSS OF VITAL 120 VAC INSTRUMENT BUS, Attachment B CREW 1. B1. Defeat RCS temperature control for loop 2

a. Position loop Tavg control signal to T422 BB TS 412T

b. Position loop DT control signal to T421 BB TS-411F 2. B2. Ensure AC PT

-505 selected AC PS-505Z 3. B3. Lock SG B ARV manual drive lever in closed position AB PIC-2A 4. B4. Determine NN02 status

a. Check NN02 bus no apparent damage

- YES Ensure NN02 normal feeder breaker closed o NN0201 closed

- NO Simulator Operator: Call back as the building watch and report that 'A maintenance worker bumped the DC input breaker open and the inverter did not transfer to its bypass source. No damage to the bus'. Simulator Operator: When the crew asks you to ENSURE the NN02 normal feeder breaker is closed then close it and report back that it is closed (modify the remote to close the normal breaker)

5. B5. Check NN02 powered from inverter prior to bus loss

a. Check inverter NN12 system output volts normal NNEI0122 112.1 VAC to 123.9 VAC

- YES 9. B9. Check applicable TS

3.3.1 Condition

A,S and T 3.3.2 Condition A and L 3.8.7 Condition A

3.8.9 Condition

C (during the time the NN bus was de

-energized Event termination:

After SRO has TS determined or at the direction from the lead examiner insert key 4 Simulator Operator: Insert key 4

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 7 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 4 E v en t Descrip tion: Loss of Wolf Creek Benton line T ime Po sitio n Simulator Operator: Insert key4 Diagnostics: Breakers for Benton line change to green (breakers open)

Annunciators: None Simulator Operator: Call from the TSO and report that you have lost the Benton line and have no time line as to restoration.

CREW Enters OFN AF-025, UNIT LIMITATIONS NOTE: Step 1

-13 can be performed in any order.

Crew will determine that steps 1

-13 do not apply go to step 13

13. Check for conditions requiring unit load reduction

a. Determine maximum unit load, using Attachment A

, Unit Load Limits. 345 kV Offsite Supply Condition requiring load reduction Maximum unit load Loss of one 345 kV offsite line Reduce unit load to less than 800 MWE NET (845 MWE gross) as directed by TSO

b. Reduce unit load as necessary to satisfy load limits using the appropriate procedure OFN MA-038, RAPID PLANT SHUTDOWN NOTE: SRO will enter TR 3.8.1, Offsite Power System Transmission Network, Condition A

. Lead examiner: Prompt SRO from the SM that the unit load is to be lowered using OFN MA

-038, RAPID PLANT SHUTDOWN, reduce load at 3%/minute, in automatic, using Open loop.

CREW Enters OFN MA

-038, RAPID PLANT SHUTDOWN

1. Determine turbine unloading method to be used

a. Check desired unloading rate less than or equal to 65 MW/minute

- YES b. Check automatic turbine unloading desired

c. From graphic 5551 turbine control system operation panel load control section select method of load control as directed by CRS/SM First stage pressure Megawatts Open loop 2. Reduce turbine load in automatic

a. From graphic 5551 turbine control system operation panel setpoints section reduce turbine load Select change Enter target MW Enter rate

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 8 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 4 E v en t Descrip tion: Loss of Wolf Creek Benton line T ime Po sitio n Select go CREW NOTE: The crew should lower to 800MWE, at 3%/minute

b. Maintain desired turbine unloading rate.

c. Go to step 4

4. Borate RCS and adjust control rods as necessary to maintain the following Target Tavg/Tref temperature error between 0F and +5F Control rods above the rod insertion limits

5. Energize PZR backup heaters BB HIS-51A BB HIS-52A 6. Check PZR PORVs

a. RCS pressure less than 2335 psig

- YES b. PZR PORVs closed

- YES c. RCS pressure greater than 2185 psig

- YES d. PORV block valves open

- YES 7. Check PZR pressure stable at or trending to 2235 psig

- YES 8. Check PZR level stable at or trending to program level

- YES 9. Check SG levels controlling between 45% and 55% - YES 10. Notify HP to perform the following Monitor RCS and other connecting systems for increasing radiation levels due to unplanned crud burst Notify all personnel in the affected areas

11. Check if sampling is required

a. Check if one of the following conditions is met Thermal power change greater than 15% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

- YES b. Direct chemistry to take samples per AP 02

-007, ABNORMAL CONDITIONS GUIDELINES.

Simulator Operator: When contacted as HP acknowledge request, when contacted as Chemistry acknowledge request.

Event termination: When the crew has lowered approximately 5% power or at the direction from the lead examiner enter key 5 Simulator Operator: Enter key 5

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 9 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 5 , 6 E v en t Descrip tion: Inadvertent train B SI EMG E-0, REACTOR TRIP OR SAFETY INJECTION T ime Po sitio n Simulator Operator: Insert key 5 Diagnosis: Reactor trip, only one train of SI Annunciators: Many CREW Enter EMG E

-0, REACTOR TRIP OR SAFETY INJECTION Perform immediate actions

1. Verify reactor trip

a. Check all rod bottom lights

- lit - YES b. Check reactor trip breakers and bypass breakers

- open - YES SB ZL-1 SB ZL-2 SB ZL-3 SB ZL-4 c. Check intermediate range neutron flux

- decreasing

- YES SE NI-35B (gamma metrics)

SE NI-36B (gamma metrics)

2. Verify turbine trip

a. Check main stop valves all closed

- YES 3. Check AC emergency busses

- at least one energized

- YES Simulator Operator: If contacted as the building watch to investigate the B EDG acknowledge request. Report back that Generator Protective relay is in alarm. The failure of the B EDG is Event 6.

4. Check if safety injection is actuated

a. Check any indication SI is actuated

- lit Annunciator 00

-030A NF039A LOCA SEQ ACTUATED

- LIT - YES Annunciator 00

-031A NF039B LOCA SEQ ACTUATED

- LIT - YES ESFAS status panel SIS section

- any white lights lit

- YES Partial trip status permissive/block status panel

- SI red light lit

- YES b. Check both trains of SI actuated

- NO Ann 00-030A NF039A LOCA SEQ ACTUATED

- LIT - NO Ann 00-031A NF039B LOCA SEQ ACTUATED

- LIT - YES b. RNO Actuate both trains of SI SB HS-27 SB HS-28 NOTE: The SRO will now perform a verification of the immediate actions by performing a read through of the steps provided above.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 10 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 5 , 6 E v en t Descrip tion: Inadvertent train B SI EMG E-0, REACTOR TRIP OR SAFETY INJECTION CREW 5. Check if SI is required SI was manually actuated and was required

- NO Containment pressure is currently or has been

- greater than or equal to 3.5 psig

- NO RCS pressure is currently or has been

- less than or equal to 1830 psig

- NO Any SG pressure is currently or has been less than or equal to 615

- NO a. RNO perform the following

a. Reset SI SB HS-42A SB HS-43A b. If one or both trains of SI failed to reset

- they reset

c. If condenser steam dumps are available then ensure steam dumps control RCS temperature Tavg at 557F Tavg mode Tcold at 557F steam pressure mode

d. If condenser steam dumps are not available then adjust at least one SG ARV to maintain RCS cold leg temperatures less than or equal to 557F

e. Close BIT inlet valves EM HIS-8803A EM HIS-8803B f. Close BIT outlet valves BB HIS-8801A BB HIS-8801B CT 1: Isolate BIT inlet and outlet valves within 8 minutes from ECCS initiation.

g. If any CCP is running then stop NCP BG HIS-3 Event termination: After the crew has the BIT inlet and outlet valves closed or at the direction of the lead examiner insert key 6 Simulator Operator: Insert key 6

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 11 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 7 E v en t Descrip tion: EMG C-0, LOSS OF ALL AC POWER T ime Po sitio n Simulator Operator: If contacted as TSO report back that you will investigate the loss of power to the Wolf Creek switchyard.

CREW EMG C-0, LOSS OF ALL AC POWER (Immediate action steps are 1 and 2)

1. Verify reactor trip

- performed in E

-0 2. Verify turbine trip

- performed in E

-0 3. Check main generator breaker and exciter breaker open

- YES 4. Check if RCS is isolated a. Check RCS letdown to regen heat exchanger valves closed

- YES BG HIS 459 BG HIS-460 b. Check PZR PORVs closed

- YES c. Check reactor coolant to excess letdown heat exchanger valves closed

- YES d. Check reactor vessel head vent at least one valve closed in each train

- YES e. Dispatch operator to locally close RCS and PZR sample line isolation valves SJ-V054 (2000' AUX BLDG, NORTH PIPE PEN ROOM ON MEZZANINE)

SJ-V057 (2000' AUX BLDG, NORTH PIPE PEN ROOM IN CORNER FURTHEST FROM DOOR)

SJ-V103 (2000' AUX BLDG, SOUTH PIPE PEN ROOM ON MEZZANINE)

Simulator Operator: When called to close valves acknowledge request. Report back that the valves are closed

5. Check total AFW flow greater than 270,000 lbm/hr

- YES 6. Check emergency oil pumps

a. Emergency seal oil pumps running - YES b. MFP emergency lube oil pumps both running

- YES c. Main Turbine Emergency Bearing Oil Pump running

-YES CREW 7. Evaluate availability of AC emergency busses

a. Check NB01 for faults

- YES Annunciator 00

-18A not lit

b. Check NB02 for faults Annunciator 00-21A not lit

c. Check NB bus status at least one available

- YES 8. Evaluate availability of EDGs

a. Check EDG A electrical status

- tagged out

b. Check EDG B electrical status Annunciator 502

-7D not lit

- NO RNO dispatch electrical maintenance to evaluate EDG B

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 12 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 7 E v en t Descrip tion: EMG C-0, LOSS OF ALL AC POWER T ime Po sitio n Simulator Operator: If contacted as TSO report back that you will investigate the loss of power to the Wolf Creek switchyard.

Simulator Operator: When contacted as electrical maintenance acknowledge request.

c. Check EDG electrical status at least one available associated with an available NB bus

- NO RNO go to step 10

10. Check AC emergency busses both energized

- NO 10. RNO.a. manually energize AC emergency bus

b. If either emergency bus cannot be energized then perform the following

- recognized neither EDG is running Try to energize affected AC emergency buses from any available power supply while continuing with this procedure o Refer to OFN NB

-030, LOSS OF AC EMERGENCY BUS NB01 OR NB02

11. Check if AC power has been restored

a. Check AC emergency busses at least one energized

- NO a. RNO observe caution prior to step 15 and continue with step 15 NOTE: Steps for starting the SBO EDGs are on page 14 of this guide.

15. Place the following switches in pull to lock position MD AFP A o AL HIS-23A MD AFP B o AL HIS-22A CCP A o BG HIS-1A CCP B o BG HIS-2A CTMT SPRAY PUMP B o EN HIS-9 RHR PUMP B o EJ HIS-2 SI PUMP B.

o EM HIS-5 SI PUMP A.

o EM HIS-4 RHR PUMP A o EJ HIS-1 CTMT SPRAY PUMP A o EN HIS-3 CCW PUMP B o EG HIS-22 CCW PUMP D o EG HIS-24 CCW PUMP A

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 13 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 7 E v en t Descrip tion: EMG C-0, LOSS OF ALL AC POWER T ime Po sitio n Simulator Operator: If contacted as TSO report back that you will investigate the loss of power to the Wolf Creek switchyard.

o EG HIS-21 CCW PUMP C o EG HIS-23 CTMT COOLER FAN B o GN HIS-9 CTMT COOLER FAN D o GN HIS-17 CTMT COOLER FAN A o GN HIS-5 CTMT COOLER FAN C o GN HIS-13 CTRL RM A/C UNIT 4A FAN & DAMPER o GK HIS-29 CLASS I/E ELEC EQUIP A/C UNIT 5A o GK HIS-100 CTRL RM A/C UNIT 4B FAN &

DAMPER o GK HIS-40 CLASS I/E ELEC EQUIP A/C UNIT 5B o GK HIS-103 CREW 16. Dispatch personnel to locally close valve to isolate RCP seals Simulator Operator: When called to isolate RCP seals acknowledge request. Insert key 13 and after file runs through report back that all RCP seals are isolated NOTE: While the crew is performing the rest of the steps of C

-0 another operator will be working on OFN NB-030. EMG C-0, LOSS OF ALL AC POWER foldout page items

2. Power restoration criteria

- if power if restored to an AC emergency bus during performance of steps 15 to 40 then go to step 40.

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 14 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 7 E v en t Descrip tion: OFN NB-030, LOSS OF AC EMERGENCY BUS NB01 OR NB02 T ime Po sitio n CREW OFN NB-030, LOSS OF AC EMERGENCY BUS NB01 OR NB02

1. Check AC emergency buses at least one energized

- NO 1. RNO if entering this procedure from EMG C

-0 then go to the desired attachment Attachment A step A14 Attachment B step B14 Lead examiner: Cue the SRO that you want NB02 energized first B14. Check NB02 status Annunciator 00

-21A clear

- YES B15. Check NB02 EDG status Annunciator 502

-07D clear

- NO Dispatch electrical maintenance

- previously done B16. Check emergency EDG NB02 running

- NO RNO if SM/CRS directs that NB02 be energized from a source other than the diesel than go to Step B24 for SBO diesel generators B24. Reenergize NB02 from SBO diesel generators Reenergize NB02 per SYS KU

-122, ENERGIZING NB02 FROM STATION BLACKOUT DIESEL GENERATORS NOTE: Crew will dispatch the site watch to start the SBO diesels and put them on the bus Simulator Operator: When contacted to start the SBO diesels acknowledge request. Insert key 11 and 12. Call control room back after file is complete and inform them that NB02 is energized from the SBO diesels B25. check NB02 energized

- YES B26. check OFN NB

-034 or EMG C

-0 is not in effect RNO return to procedure and step in effect NOTE: The crew may have performed other steps in C

-0 but at this point they will be going to step 40 off of foldout page EMG C-0, LOSS OF ALL AC POWER

40. Check if AC emergency power is restored

a. Check AC emergency busses at least one energized

- YES 41. Stabilize SG pressures

a. Set SG ARV controllers to auto maintain existing SG pressures b. Control total steam flow as necessary to maintain SG pressures stable

42. Check SI reset

- NO 42. RNO reset SI SB HS42A SB HS-43A 43. Check the following equipment loaded on energized AC emergency busses

A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 15 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 7 E v en t Descrip tion: OFN NB-030, LOSS OF AC EMERGENCY BUS NB01 OR NB02 T ime Po sitio n CREW a. ESW Pump. EF HIS-55A For Red Train EF HIS-56A For Yellow Train

b. 480 volt 1E busses NG01 For Red Train NG03 For Red Train NG02 For Yellow Train NG04 For Yellow Train

c. Battery chargers NK-21 For Red Train NK-23 For Red Train NK-22 For Yellow Train NK-24 For Yellow Train

d. Instrumentation and control power NN01 For Red Train NN03 For Red Train NN02 For Yellow Train NN04 For Yellow Train

e. Emergency lighting f. Communications CT 2: Energize either NB01 or NB02 using SYS KU

-121 or SYS KU

-122 before core cooling requirements specified in EMG C-0 Step 29 are no longer met

. 44. Reenergize DC loads supplied by energized busses

a. Check that no NK batteries were disconnected

- YES b. Dispatch operator to locally reenergize any AC and DC loads shed 45. Reenergize non class 1E battery chargers from energized busses PK-24 for red train PK-24 for yellow train

46. Restore power to security inverters from energized busses

a. Coordinate power restoration with security

b. Energize battery chargers PK-21 red train PK-22 yellow train

47. Verify red train ESW

- not energized

48. Verify yellow train ESW

a. Check NB02 energized

- YES b. Check yellow train ESW valve alignment

- all correct

49. Check terry turbine steam drains isolated FC-V048 (2000' TDAFW Pump Room)

- CLOSED FC-V070 (2000' TDAFW Pump Room) - CLOSED FC-V089 (2000' TDAFW Pump Room) - CLOSED 50. Select recovery procedure

a. Check RCS subcooling greater than 30F

b. Check PZR level greater than 6%

c. Check ECCS flow not indicated

d. Go to EMG CS

-01, LOSS OF ALL AC POWER RECOVERY A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 16 of 16 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 7 E v en t Descrip tion: OFN NB-030, LOSS OF AC EMERGENCY BUS NB01 OR NB02 T ime Po sitio n WITHOUT SI REQUIRED, step 1 O p-Tes t No.: Nov. 2015 Scenari o No.: 4 E v en t No.: 7 E v en t Descrip tion: EMG CS-01, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, step 1 T ime Po sitio n CREW EMG CS-01, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, step 1

1. Check seal water injection filters inlet isolations closed BG-V101 BG-V105 NOTE: Crew dispatches building watch to check filters

2. Check RCP Thermal Barriers Isolated:

a. CCW pumps all stopped

- YES b. CCW return from RCS isolation valves outside CTMT and CCW from RCS CTMT isolation valve bypass both closed

- YES 3. Check CTMT isolation phase A not actuated

- NO 3. RNO reset CTMT phase A

4. Verify instrument air compressor is running Scenario termination: After the crew resets CISA or at the direction of the lead evaluator freeze the simulator.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 1 of 5 Rev 1 Facili t y: Wolf Creek Scenari o No.: 5 (New) O p-Tes t No.: Nov 2015 E x a miners: Opera tors: I ni t ia l Condi tions: 100% power MOL.

IC 29, Ensure blue placard is on the B CCP.

Turno ver: E vent N o. M a l f. N o. E vent T y p e* E vent Descr ip t io n 1. R (ATC) N (BOP SRO) Lower power to 90% due to grid instability per TSO.

2. I (BOP SRO) Steam header pressure channel (AB PI

-507) failure high.

3. C (ATC SRO) Trip of the Normal Charging Pump (NCP). 4. I (BOP SRO) TS (SRO) 'D' S/G level channel (AE LI

-549) fails high

. 5. I (RO SRO) TS (SRO) VCT channel (BG LI-185) failure low.

6. Earthquake followed by a lockout on NB0 2 and trip of Both MFPs. 7. M (ATC BOP SRO) Failure of the reactor to trip ATWS. CT1: Isolate the main turbine from the S/G within 30 seconds to prevent uncovering S/G tubes.

8. C (ATC BOP SRO) Small break LOCA (4") from the 'A' loop cold leg

.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 2 of 5 Rev 1 9. C (ANY) Failure of the 'B' SI P to start on the LOCA sequencer.

CT 2: Start at least one SIP before RVLIS Natural Circ. Range is

< 45% to prevent core uncovery.

(N)ormal, (R)eacti v i t y , (I)nstrument, (C)omponent, (M)ajor A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 3 of 5 Rev 1 Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Malfunctions after EOP entry (1

-2) 3 (events 7,8 ,9) 2. Abnormal events (2

-4) 4 (events 2,3,4 ,5) 3. Major transients (1

-2) 1 (event 6) 4. EOPs entered/requiring substantive actions (1

-2) 1 (EMG E-1) 5. EOP contingencies requiring substantive actions (0

-2) 1 (EMG FR-S1) 6. EOP based Critical tasks (2

-3) 2 (events 7 , 9) 7. Critical Task Justification References CT1: Isolate the main turbine from the S/G within 30 seconds to prevent uncovering S/G tubes. The turbine is tripped to prevent an uncontrolled cooldown of the RCS due to steam flow that the turbine would require. For an ATWS event where a loss of normal feedwater has occurred, analyses have shown that a turbine trip is necessary within 30

seconds to maintain S/G inventory.

BD EMG FR-S1, RESPONSE TO NUCLEAR POWER GENERATION / ATWS, Rev

13. CT2: Start at least one SIP before RVLIS Natural Circ. Range is < 45% to prevent core uncovery. If the SIPs are not started, core uncovery will occur and the fuel will be damaged.

BD-EMG FR-C2, RESPONSE TO DEGRADED CORE COOLING, Rev 11 BD-EMG F-0 Rev 13A (page 29)

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 4 of 5 Rev 1 SCENARIO #

5 NARRATIVE Turnover: 100% power MOL.

Event 1: TSO request Wolf Creek lower power to 90% due to grid issues.

Event 2: Steam header pressure channel (AB PI

-507) failure high.

The crew will notice reactor power rising, MFP speed rising, generator load lowering, and S/G levels rising. The crew will enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment B, STEAM OR FEEDWATER HEADER PRESSURE CHANNEL MALFUNCTION. The BOP will place the MFP turbine master speed controller in manual and lower speed to program Dp using figure 1 of the OFN.

Event 3: Trip of the Normal Charging Pump (NCP).

The crew will respond using alarm response ALR 00-042A, CHG LINEFLOW HILO and/or ALR 00-042E, CHARGING PMP TROUBLE. The ATC will isolate letdown, then restore normal charging and letdown using CCP 'A'.

Event 4: 'D' S/G level channel (AE LI

-549) fails high

. The crew will mitigate using OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment F, S/G LEVEL CHANNEL MALFUNCTION. The BOP will initially take manual control of the MFW regulating bypass valve and control S/G level.

Automatic control will be restored once an alternate control channel is selected. The SRO will enter T.S. 3.3.1, Reactor Trip System Instrumentation, Condition A and E and 3.3.2, Engineered Safety feature Actuation System Instrumentation, Conditions A and D. The SRO will monitor T.S. 3.3.3, Post Accident Monitoring Instrumentation and 3.3.4, Remote Shutdown System

. Event 5: VCT channel (BG LI-185) failure low.

This will cause a VCT to RWST swap over. The SRO will direct entry into OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment U, VCT LEVEL CHANNEL MALFUN CTION, to reopen the valve and then open the valve breaker. The SRO will enter TR 3.1.9, Boration Injection System Operating, Condition A, TS 3.5.2, ECCS Systems Operating, Condition A.

Event 6: Earthquake. NB02 (safeguards) bus lock s out and both MFP trip. The crew will observe S/G levels lowering, RCS pressure rising, and generator load rising. The crew will enter EMG E

-0, REACTOR TRIP OR SAFETY INJECTION, and attempt to trip the reactor from both control room switches.

Event 7: Failure of the reactor to trip ATWS. The crew will transition to EMG FR

-S1, RESPONSE TO NUCLEAR PWR GENERATION / ATWS. The ATC will insert control rods in manual and the BOP will manually trip the main turbine. CT1: Isolate the main turbine from the S/G within 30 seconds to prevent uncovering S/G tubes. Event 8: Small break LOCA (4") from the 'A' loop cold leg.

After the crew transitions back to EMG E

-0 from EMG FR

-S1, the LOCA will be inserted. SI will auto actuate.

Event 9: Failure of the 'B' SI P to start on the LOCA sequencer.

The crew will start the 'B' SI pump either on direction from the SRO or per EMG E

-0, REACTOR TRIP OR SAFETY INJECTION, Attachment F, AUTOMATIC SIGNAL VERIFICATION. This action is required since NB01 is locked out and this will be the only SI pump running.

CT 2: Start at least one SIP before RVLIS Natural Circ. Range is < 45% to prevent core uncovery.

The crew will continue in EMG E

-0 until a transition is made to EMG E

-1, LOSS OF REACTOR OR SECONDARY COOLANT.

After the crew resets SI the scenario may be terminated by the chief examiner.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 5 of 5 Rev 1 Procedures entered:

OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment B, STEAM OR FEEDWATER HEADER PRESSURE CHANNEL MALFUNCTION ALR 00-042A, CHG LINE FLOW HILO and/or ALR 00-042E, CHARGING PMP TROUBLE OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment F, S/G LEVEL CHANNEL MALFUNCTION OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment U, VCT LEVEL CHANNEL MALFUNCTION EMG E-0, REACTOR TRIP OR SAFETY INJECTION EMG FR-S1, RESPONSE TO NUCLEAR PWR GENERATION / ATWS EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT Scenario file:

ILO Scenario 5

failure of A SI pump to auto start IMF mEM01A i

-1 f:-1 ;steam header pressure AB PI

-507 failure high ICM trABPT0507 t:2 d:0 k:1

NCP trips ICM bkrPB00301 t: 1 d:0 k:2

D SG level AE LI

-549 fails high IMF mAE15D3 f:101 r:30 k:3

VCT level BG LI

-185 fails low ICM trBGLT0185 t:1 d:0 k:4

breaker for 112C ICR movBGLCV0112C t: 0 d:0 k:5

breaker for 112e

ICR movBNLCV0112E t:0 d:0 k:6

trip of both MFPs IMF mSF17A i

-1 f:-1 IMF mSF17B i:

-1 f:-1 ;failure of reactor to trip in auto and manual IMF mFC01A i:

-1 f:-1 k:7 IMF mFC01B i:

-1 f:-1 k:7 ;NB02 bus lockout IMF mNB04 i:

-1 f:-1 k:7 ;earthquake

IMF mSG01 f:60 k:7

LOCA after back in E

-0 IMF mBB06A f:4 k:8

end file Page 1 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _Nov 2015_ Scenario No.:

5 Event No.: _

1___ Event

Description:

Lower power to 90% due to grid instability per TSO.

Time Position Applicant's Actions or Behavior SRO Directs performance of GEN 00

-004 to reduce turbine load.

Crew 1. 6.2.1 BEGIN performance of ATTACHMENT D, GEN 00

-004 Continuous Action Steps Crew 2. 6.2.2 IF power reduction is in preparation for shutdown, THEN perform the following while continuing with this procedure:

The crew should recognized this step is N/A ATC 3. 6.2.3 IF Control Rods are NOT parked at 228 steps: The crew should recognized this step is N/A SRO 4. 6.2.4 DIRECT Health Physics to:

1. Monitor RCS and other connecting systems for increasing Radiation levels due to unplanned crud burst.

2. Notify all personnel in the affected areas. ATC 5. 6.2.5 ENSURE Pressurizer Backup Heaters are energized per SYS BB-203, PRESSURIZER BACKUP HEATER OPERATIONS, as follows:

For normal load decrease, ENERGIZE one set of Pressurizer Backup Heaters

To ENSURE Pressurizer Pressure does not decrease, ENERGIZE both sets of Pressurizer Backup Heaters ATC 6. 6.2.6 IF Reactor Power is greater than 60%, THEN BEGIN lowering Reactor Power to 60%

using ATTACHMENT F, Actions To Change Turbine Load while continuing with this procedure.

Page 2 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.:

1 Event

Description:

Lower power to 90% due to grid instability per TSO.

Time Position Applicant's Actions or Behavior SRO Directs performance of GEN 00

-004, ATTACHMENT F.

BOP 1. F.1 PERFORM the following to change Turbine load, as directed by SM/CRS:

F.1.1 IF decreasing load in response to a secondary transient

that has been pre-briefed during the start of shift reactivity

brief, THEN perform the following:

BOP F.1.2 IF changing load using CHANGE or TRIM, THEN perform the following:

1. THEN SELECT the appropriate Load Control Mode from Graphic 5551, LOAD CONTROL section, as follows:

a. SELECT the SELECT/DESELECT pushbutton.

b. IF MEGAWATT or FIRST STAGE PRESSURE is selected, THEN from popup 7053, SELECT OPEN LOOP. c. IF Load Control Mode still needs to be changed, THEN from popup 7053, SELECT the desired Load Control Mode.

FIRST STAGE PRESSURE

MEGAWATT

2. From Graphic 5551, SETPOINTS section, SELECT one of the following:

CHANGE

TRIM BOP should select CHANGE as the turbine load must be reduced 10%

Page 3 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: _

1___ Event

Description:

Lower power to 90% due to grid instability per TSO.

Time Position Applicant's Actions or Behavior BOP 3. IF CHANGE was selected, THEN PERFORM the following:

a At popup 7055, ENTER the desired MW in the TARGET field. b. At the MW TARGET section of popup 7055, SELECT ENTER. c. At the SETPOINTS section of Graphic 5551, VERIFY the MW entered is displayed in the TARGET field.

d. IF Turbine Load is being raised, THEN PERFORM the following:

Step N/A as turbine load is being lowered.

e. IF Turbine Load is being lowered, THEN PERFORM the following:

1) In the RATE

- DEC. field of popup 7055, ENTER the desired rate of decrease.

2) At the RATE

- DEC TARGET section of popup 7055, SELECT ENTER.

3) From Graphic 5551, SETPOINTS section, VERIFY the rate of decrease entered is displayed in the DEC RATE field.

f. From Graphic 5551, SETPOINTS section, SELECT GO to commence Turbine Load changes.

g. From Graphic 5551, SETPOINTS section, VERIFY the value in the CURRENT REF field changes to match the TARGET value as load is changing. CREW ATTACHMENT D NOTE: The crew will use Attachment D for the continuous action steps for the power reduction. Steps are not listed here.

Event termination: After the crew has reduced turbine load 5% or at the discretion of the Lead Examiner. Simulator operator: Insert Key 1 at the lead examiners direction.

Page 4 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: __

2___ Event

Description:

Steam header pressure channel (AB PI

-507) failure high.

Time Position Applicant's Actions or Behavior Simulator operator:

Insert Key 1 at the direction of the lead examiner.

Diagnostics:

MFP speed will raise, all S/G levels will begin to increase, possible S/G level deviation alarms. Annunciators:

108B, 109B, 110B, 111B CREW Diagnose S/G level ALL going up, increasing MFP speed. BOP will take manual control of the master MFP speed controller and restore speed to pre event values (approximately 5075 rpm). Crew will determine that AB PI-507, Steam Header Pressure detector, has failed high.

BOP (Memory action step) OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment B.

1. B1. Verify proper main feedwater pump speed control

- NO 1. B1 RNO a. Place MFP turbine master speed CTRL in manual.

FC-SK-509A 1. B1 RNO b. Control pump speed to programmed feedwater DP in accordance with programmed value. (refer to figure 1)

FC-SK-509A 1. B1 RNO c. IF MFP turbine master speed CTRL will not control in manual then use individual MFP speed controllers.

CREW Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, Rev 43 SRO, BOP 1. Check for malfunction:

Check if secondary system instrument channel is malfunctioning:

a. Perform appropriate attachment for malfunctioning channel from table below:

Variable Channels Attachment Steam or Feedwater Header pressure (AB,AE) P-507 P-508 Attachment B

Page 5 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: _

2___ Event

Description:

Steam header pressure channel (AB PI

-507) failure high.

Time Position Applicant's Actions or Behavior CREW SRO, BOP Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, ATTACHMENT B, STEAM OR FEEDWATER HEADER PRESSURE CHANNEL MALFUNCTION.

1. B1. Verify proper main feedwater pump speed control

- NO 1. B1. RNO a. Place MFP turbine master speed CTRL in manual.

FC-SK-509A 1. B1. RNO b. Control pump speed to programmed feedwater DP in accordance with programmed value. (refer to figure 1)

FC-SK-509A 1. B1. RNO c. IF MFP turbine master speed CTRL will not control in manual then use individual MFP speed controllers.

SRO, BOP 2. B2. Verify steam header pressure channel malfunction:

Steam header pressure

- abnormally higher OR Steam header pressure

- abnormally lower than S/G pressure OR Steam dump pressure control demand signal

- abnormal demand for existing plant conditions (refer to figure 2) SRO, BOP 3. B3. Check STEAM DUMP SEL Switch

- IN STEAM PRESSURE MODE - NO o AB US-500Z No - RNO: go to B6 SRO, BOP 4. B6. Place STEAM HDR PRESS CTRL In

- MANUAL o AB PK-507 SRO 5. B7. Request I&C To Repair Failed Channel Simulator Operator: If contacted as WWM, acknowledge requests. If contacted as Call Supt., acknowledge status.

Event termination: After the crew has placed the master MFP speed controller in manual and controlled S/G level or at the direction of the lead examiner.

Simulator Operator: Insert Key 2 at direction of Lead Examiner.

Page 6 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: _

3___ Event

Description:

Trip of the Normal Charging Pump (NCP).

Time Position Applicant's Actions or Behavior Simulator operator: Insert Key 2 at the direction of the lead examiner.

Diagnostics:

Pressurizer level going down, Charging flow low Annunciators:

041A, 042A, 042E CREW Diagnose NCP has tripped and refer to ALR 00-042A or 42E.

ATC (Memory action step) ALR 00

-042A, CHG LINE FLOW HILO

1. Check Charging Pumps

- Any Running

BG HIS-1A For CCP A

- NO

BG HIS-2A For CCP B

- NO

BG HIS-3 For NCP - NO 1. RNO Perform the following:

a. Close Letdown Orifice Isolation valves.

o BG HIS-8149AA o BG HIS-8149BA o BG HIS-8149CA b. Go to ALR 00

-042E, CHARGING PMP TROUBLE.

ATC (Memory action step s) ALR 00-042 E , CHARGING PMP TROUBLE

1. Check Previously Running Charging Pump

- TRIPPED o BG HIS-1A For CCP A o BG HIS-2A For CCP B o BG HIS-3 For NCP - YES 2. Check Charging Pump s - NONE RUNNING o BG HIS-1A For CCP A o BG HIS-2A For CCP B o BG HIS-3 For NCP 3. Close Letdown Orifice Isolation valves.

o BG HIS-8149AA o BG HIS-8149BA o BG HIS-8149CA Page 7 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: __

3__ Event

Description:

Trip of the Normal Charging Pump (NCP).

Time Position Applicant's Actions or Behavior SRO ALR 00-042 E , CHARGING PMP TROUBLE

4. Contact Electrical Maintenance To Determine Cause Of Pump Trip. Simulator Operator: If contacted as WWM, acknowledge requests. If contacted as Call Supt., acknowledge status.

SRO, ATC 5. Establish Charging Flow:

a. Check RCS Temperature

- GREATER THAN 350

°F b. Start CCP Aligned for normal charging

BG HIS-1A For CCP A

BG HIS-2A For CCP B

c. Go to step 6.

SRO, ATC 6. Ensure RCP Seal Injection

- BETWEEN 8 GPM AND 13 GPM TO EACH RCP o BG FR-157 For RCP A o BG FR-156 For RCP B o BG FR-155 For RCP C o BG FR-154 For RCP D

Page 8 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: _

3__ Event

Description:

Trip of the Normal Charging Pump (NCP).

Time Position Applicant's Actions or Behavior SRO, ATC 7. Reestablish Letdown:

a. Adjust Charging flow to maintain flow greater than Letdown flow, while maintaining RCP Seal Injection flow between 8 gpm and 13 gpm.

BG FK-121

BG FK-462

BG HC-182 b. Check RCS Letdown To Regen HX valves open.

o BG HIS-459 - YES o BG HIS-460 - YES c. Place Letdown HX Outlet Pressure Control in manual.

o BG PK-131 d. Open Letdown HX Outlet Pressure Control between 90% and 100%. o BG PK-131 e. Open desired Letdown Orifice Isolation Valve(s).

BG HIS-8149AA

BG HIS-8149BA

BG HIS-8149CA f. Adjust Letdown HX Outlet Pressure Control to establish Letdown HX Outlet Pressure between 340 psig and 360 psig.

o BG PI-131 g. Place Letdown HX Outlet Pressure Control in auto.

o BG PK-131 SRO, ATC 8. Check Charging Header Flow And Letdown Flow

- BALANCED SRO, ATC 9. Verify CCP Adequate Flow:

a. Check CCPs

- RUNNING

BG HIS-1A For CCP A

BG HIS-2A For CCP B

b. Check CCP Recirc Valve

- OPEN

BG HIS-8110 For CCP A

BG HIS-8111 For CCP B

Page 9 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: _

3___ Event

Description:

Trip of the Normal Charging Pump (NCP).

Time Position Applicant's Actions or Behavior SRO 10. Ensure Compliance With Technical Specifications And TRM

a. Check Plant

- IN MODES 1, 2 OR 3

b. Refer to TR 3.1.9 and Technical Specification 3.5.2.

Event termination: After the crew has balanced charging and letdown flows or at the direction of the lead examiner.

Simulator Operator: Insert Key 3 at direction of Lead Examiner.

Page 10 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: _

4___ Event

Description:

'D' S/G level channel (AE LI

-549) fails high.

_________________________________________________________________________________

Time Position Applicant's Actions or Behavior Simulator operator: Insert Key 3 at the direction of the lead examiner.

Diagnostics:

"D" Steam Generator Level going down, "D" Main Feed Reg Valve going close, "D" S/G Level deviation.

Annunciators:

111B CREW Diagnose "D" S/G level going down, "D" Main Feed Reg Valve closing. BOP will take Manual control of the "D" Main Feed Reg Valve and Stabilize level. Crew will determine AE LI

-549 has failed high.

BOP (Memory action steps) ALR 00

-111B, SG D LEV DEV

1. Check Steam Generator D Controlling Level Channel :

5% GREATER THAN PROGRAM LEVEL OR

5% LESS THAN PROGRAM LEVEL

- YES 2. Check Instruments

- OPERATING PROPERLY o Steam Generator D Controlling Level Channel

- WITHIN 6% OF REMAINING S/G D NARROW RANGE LEVEL CHANNELS

AE LI-549 - NO

AE LI-554 2. RNO Perform the Following:

a. Place Feedwater Reg Valve or Feedwater Reg Bypass Control Valve in Manual.

AE FK-540

AE LK-580 b. Adjust Feedwater Reg Valve or Feedwater Reg Bypass Control Valve, as necessary, to establish Steam Generator level at program value.

AE FK-540

AE LK-580 c. Go to OFN SB

-008, INSTRUMENT MALFUNCTIONS, step 1.

Page 11 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: _

4___ Event

Description:

'D' S/G level channel (AE LI

-549) fails high.

_________________________________________________________________________________

Time Position Applicant's Actions or Behavior CREW Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, Rev 43 SRO, BOP 1. Check for malfunction:

Check if secondary system instrument channel is malfunctioning:

a. Perform appropriate attachment for malfunctioning channel from table below:

S/G Level (AE)

CONTROL CHANNELS L-519, L-529, L-539, L-549 L-551, L-552, L-553, L-554 ATTACHMENT F PROTECTION CHANNELS L-517, L-518, L-527, L-528 L-537, L-538, L-547, L-548 WIDE RANGE CHANNELS L-501, L-502, L-503, L-504 CREW SRO, BOP Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, ATTACHMENT F, S/G LEVEL CHANNEL MALFUNCTION

1. F1. Identify Failed Narrow Range S/G Level Instrument Channel:

a. Compare narrow range S/G level indications to confirm a narrow range S/G level channel failure:

2. F2. Check Failed S/G Level Channel Selected On SG LEV CHANNEL SEL Switch:

AE LS-549C 3. F3. Check Main Feed Reg Valves In Control:

a. Place Affected SG MFW REG VLV CTRL

- IN MANUAL

AE FK-540 b. Adjust affected S/G MFW REG VLV CTRL, as necessary, to establish Steam Generator level at program:

AE FK-540 Page 12 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: _

4___ Event

Description:

'D' S/G level channel (AE LI

-549) fails high.

Time Position Applicant's Actions or Behavior SRO, BOP 4. F4. Select Alternate S/G Level Channel On SG LEV CHANNEL SEL switch:

AE LS-549C SRO, BOP 5. F5. Check Main Feed Reg Valves In Control:

a. Restore affected S/G MFW REG VLV CTRL To

- AUTO

AE FK-540 SRO 6. F6. Monitor The Following Technical Specifications For LCOs And Comply With Action Statements, As Appropriate:

o 3.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION, Table 3.3.1-1, Function 14 o 3.3.2, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM

INSTRUMENTATION, Table 3.3.2

-1, Functions 5.c And 6.d o 3.3.4, REMOTE SHUTDOWN INSTRUMENTATION, Table 3.3.4

-1, Function 8 o 3.3.3, ACCIDENT MONITORING INSTRUMENTATION, Table 3.3.3-1, Function 13 NOTE: SRO will enter TS 3.3.1 Cond A, E and 3.3.2 Cond A, D, I Simulator Operator: If contacted as WWM, acknowledge requests. If contacted as Call Supt., acknowledge status.

Event termination: After the crew has selected an operable channel for S/G level and place it in AUTO or at the direction of the lead examiner.

Simulator Operator: Insert Key 4 at direction of Lead Examiner.

Page 13 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: _

_5___ Event No.: _

5___ Event

Description:

VCT channel (BG LI

-185 ) failure low.

_________________________________________________________________________________

Time Position Applicant's Actions or Behavior Simulator operator: Insert Key 4 at the direction of the lead examiner.

Diagnostics:

VCT suction swaps to the RWST Annunciators:

ESFAS Status panel alarms

, 58B CREW Diagnose VCT suction valves have swapped to the RWST Suction valves. Determines that BG LI

-185 has failed low.

CREW Enters OFN SB

-008, INSTRUMENT MALFUNCTIONS, Rev 43 SRO, ATC 1. Check for malfunction:

Check if VCT Level Control is malfunctioning:

a. Compare VCT level channel indications to confirm VCT Level Channel Failure: o BG LI-112 o BG LI-185 - YES o BG LK-149F o BGL0149 b. Go to Attachment U, VCT LEVEL CHANNEL MALFUNCTION.

CREW SRO, ATC Enter OFN SB

-008, INSTRUMENT MALFUNCTIONS, ATTACHMENT U, VCT LEVEL MALFUNCTIO N 1. U1. Check Failed VCT Level Channel Identified As:

L-185 SRO, ATC 2. U2. Check VCT Level Channel

- FAILING LOW

L-185 Page 14 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: _

5___ Event No.: __

5__ Event

Description:

VCT channel (BG LI

-185 ) failure low.

Time Position Applicant's Actions or Behavior SRO, ATC 3. U3. Check RWST Switchover Has Occurred:

a. Either VCT OUTLET VLV closed.

BG HIS-112B

BG HIS-112C - YES b. Either CCP SUCT FROM RWST open.

BN HIS-112D

BN HIS-112E - YES SRO, ATC 4. U4. Isolate Letdown:

a. Close LTDN ORIFICE VLVs.

o BG HIS-8149AA o BG HIS-8149BA o BG HIS-8149CA b. Adjust CHG HDR BACK PRESS CTRL To 0%.

o BG HC-182 c. Ensure CCP A, CCP B, Or NCP

- AT LEAST ONE RUNNING

d. Establish 32 gpm seal injection flow.

o BG FK-121 o BG FK-462 SRO, ATC 5. U5. Check VCT Level

- GREATER THAN 5%

SRO, ATC 6. U6. Check Failed VCT Level Channel Identified As:

o L-112 6. U6. RNO Go To Step U9.

SRO, ATC 9. U9. Check Failed VCT Level Channel Identified As:

o L-185 Page 15 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: _

5___ Event No.: __

5__ Event

Description:

VCT channel (BG LI

-185 ) failure low.

Time Position Applicant's Actions or Behavior SRO, ATC 10. U 10. Open VCT OUTLET VLV:

a. Station Turbine Building operator, to open breaker NG0 2 AF R 2 when valve is open.

b. On RL001, open VCT OUTLET VLV.

o BG HIS-112 C c. WHEN valve indicates open, THEN direct Turbine Building operator, to open BGLCV112 C VOLUME CONTROL TANK OUTLET ISOLATION VALVE breaker.

o NG0 2 AF R 2 d. Locally Ensure VCT LOW LEVEL ISOLATION Valve

- FULL OPEN o BG LCV-112 C (2000' AUX BLDG, VCT VLV ROOM)

Simulator Operator: When contacted as the Turbine Building watch to go to NG01AFF2.

Simulator Operator:

Report as Turbine Watch that you are at NG01AFF2.

Simulator Operator: When contacted as the Turbine Building watch to Open NG01AFF2, Key 5. Simulator Operator:

Report as Turbine Watch that NG01AFF2 is OPEN.

Simulator Operator: When contacted as the Auxiliary Building watch acknowledge request.

Simulator Operator:

Report as Auxiliary Building Watch that BN LCV

-112C is OPEN.

Page 16 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: _

5___ Event No.:

__5__ Event

Description:

VCT channel (BG LI

-185 ) failure low.

Time Position Applicant's Actions or Behavior SRO, ATC 11. U 11. Close CCP B SUCT FROM RWST Valve:

a. Locally close BN LCV

-112 E at breaker NG0 2 A HR3, by depressing the close pushbutton.

b. WHEN valve indicates closed, THEN open BNLCV112 E RWST TO CHARGING PUMP VALVE breaker.

o NG0 2 AHR3

c. Locally Ensure CHARGING PUMPS SUCTION FROM RWST Valve - FULL CLOSED o BN LCV-112 E (1974' AUX BLDG, A CCP ROOM)

d. Refer to applicable TRM (boration) and TS (ECCS) sections: o TR 3.1.9 o TR 3.1.10 o TS 3.5.2 o TS 3.5.3 NOTE: SRO will enter TS 3.5.2 Cond A Simulator Operator: When contacted as the Turbine Building watch acknowledge the request

. Simulator Operator:

KEY 6; Report as Turbine Watch that you closed BN LCV-112 E at breaker NG01A E F1 and have opened NG0 2 A HR3. Simulator Operator: When contacted as the Auxiliary Building watch acknowledge request.

Simulator Operator:

Report as Auxiliary Building Watch that BN LCV-112 E is closed. Event termination: After the crew has realigned RWST and VCT suction valves or at the direction of the lead examiner.

Simulator Operator: Insert Key 7 at direction of Lead Examiner.

Page 17 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: __

6__ Event

Description:

Earthquake followed by a lockout on NB02 and trip of Both MFPs

. Time Position Applicant's Actions or Behavior Simulator operator: Insert Key 7 at the direction of the lead examiner.

Diagnostics:

Floor shaking, Reports from security, Alarms Annunciators:098E, 098D, 019A, 120A, 123A CREW Diagnoses floor shaking, NB02 lockout alarm and Main Feed Pump trip alarms. CREW May trip the reactor on decreasing Steam Generator levels before the Auto trip setpoint is reached.

Event Termination: When the crew recognizes the reactor will not trip.

Page 18 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5___ Event No.: _

7___ Event

Description:

Failure of the reactor to trip ATWS Time Position Applicant's Actions or Behavior Diagnostics:

Rods do not drop into the core when lo

-lo Steam Generator level is reached or when the manual trip switches are turn ed t o TRIP. Annunciators:

CREW (Immediate Actions) Enters EMG E-0, REACTOR TRIP OR SAFETY INJECTION 1. Verify Reactor Trip

a. Check all rod bottom lights

- lit 1. RNO 1. Manually trip reactor.

SB HS-1

SB HS-42 1. RNO 2. IF reactor power is greater than or equal to 5% OR intermediate range power is increasing, THEN go to EMG FR-S1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, Step 1.

CREW Enters EMG FR

-S1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.

ATC, BOP (Immediate Actions) EMG FR

-S1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.

1. Verify Reactor Trip

b. Check all rod bottom lights

- lit 1. RNO 1. Manually trip reactor.

SB HS-1

SB HS-42 1. RNO 2. IF reactor will NOT trip, THEN perform the following:

a) Insert control rods in Manual.

b) Manually deenergize rod drive motor generators:

1) Open the following breakers:

o PG HIS-16 o PG HIS-18 2) WHEN all rod bottom lights are lit OR reactor power is less than 5% with a negative Intermediate Range SUR, THEN close the following breakers:

o PG HIS-16 o PG HIS-18 3) Continue with step 2.

Page 19 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: __

5__ Event No.: __

7__ Event

Description:

Failure of the reactor to trip ATWS Time Position Applicant's Actions or Behavior BOP 2. Verify turbine trip

a. Check main stop valves

- all closed CT 2. RNO a. Perform the following:

1) Manually Trip the Turbine

2) IF turbine will NOT trip, THEN close main steam isolation valves and main steam bypass valves.

AB HS-79

AB HS-80 CT1: Isolate the main turbine from the S/G within 30 seconds to prevent uncovering S/G tubes.

SRO, BOP 3. Verify AFW Pumps Running:

a. Check motor driven AFW pumps

- BOTH RUNNING o AL HIS-22A o AL HIS-23A b. Check turbine driven AFW pump

- RUNNING SRO, BOP 4. Check Main Generator Breakers And Exciter Breaker

- OPEN o MA ZL-3A o MA ZL-4A o MB ZL-2 SRO, ATC 5. Check SI - NOT IN PROGRESS o CCPs - ALIGNED FOR NORMAL CHARGING o SI pumps

- NONE RUNNING IN INJECTION MODE o RHR pumps

- NONE RUNNING IN INJECTION MOD Page 20 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: _

5_ Event No.: __

7__ Event

Description:

Failure of the reactor to trip ATWS Time Position Applicant's Actions or Behavior SRO, ATC 6. Initiate Emergency Boration Of RCS:

a. Ensure one of the following pumps is running:

BG HIS-1A for CCP A

BG HIS-2A for CCP B

BG HIS-3 for NCP b. Align boration flow path:

1) Ensure boric acid transfer pumps

- AT LEAST ONE RUNNING

BG HIS-5A

BG HIS-6A 2) Open Emergency Borate To Charging Pump Suction valve o BG HIS-8104 SRO, ATC 7. Verify Charging Flow Path:

a. Ensure Charging Pumps To Regenerative Heat Exchanger Containment Isolation valves

- OPEN o BG HIS-8105 o BG HIS-8106 b. Ensure Regenerative Heat Exchanger To Loop Cold Leg valves

- ONLY ONE OPEN

BG HIS-8146 for Loop 1 OR

BG HIS-8147 for Loop 4

c. Adjust charging flow to maintain pressurizer level

BG FK-121 for CCP OR

BG FK-462 for NCP

d. Adjust Charging Header Back Pressure Control as necessary to establish between 8 gpm and 13 gpm seal injection flow to each RCP o BG HC-182 SRO, ATC 8. Check Emergency Borate Flow

- GREATER THAN 30 GPM o BG FI-183A SRO, ATC 9. Check PZR Pressure

- LESS THAN 2335 PSIG

Page 21 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: _

5___ Event No.: __

7__ Event

Description:

Failure of the reactor to trip ATWS Time Position Applicant's Actions or Behavior ATC, BOP 10. Verify Containment Purge Isolation:

a. Check ESFAS status panel CPIS section

- ALL WHITE LIGHTS LIT o Yellow train SRO, ATC (Continuous Action)

11. Check Safety Injection Not Actuated:

o Annunciator 00

-030A, NF039A LOCA SEQ ACTUATED

- CLEAR AND o Annunciator 00

-031A, NF039B LOCA SEQ ACTUATED

- CLEAR AND o ESFAS status panel SIS section

- NO WHITE LIGHTS LIT AND o Partial Trip Status Permissive/Block status panel

- SI RED LIGHT NOT LIT ATC, BOP 12. Check If The Following Trips Have Occurred:

a. Reactor trip o Check reactor trip breakers and bypass breakers

- OPEN o SB ZL-1 o SB ZL-2 o SB ZL-3 o SB ZL-4 b. Turbine trip o Check Main Stop Valves

- ALL CLOSED SRO, ATC (Continuous Action)

13. Verify Reactor Subcritical:

a. Power range channels [GAMMA METRICS]

- LESS THAN 5%

b. Intermediate range channels

- NEGATIVE STARTUP RATE [GAMMA METRICS

- STABLE OR DECREASING]

c. Go to Step 25

Page 22 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.: __

7__ Event

Description:

Failure of the reactor to trip ATWS _________________________________________________________________________________

_________________________________________________________________________________

Time Position Applicant's Actions or Behavior SRO, ATC 25. Continue Boration Until Adequate Shutdown Margin Is Obtained ATC, BOP 26. Check CRDM Fans

- ALL AVAILABLE RUNNING o GN HIS-42 o GN HIS-43 o GN HIS-44 SRO 27. Determine Return Procedure

a. Check EMG FR

-S1, RESPONSE TO NUCLEAR POWER GENERATION/ATWT

- ENTERED FROM EMG E-0, REACTOR TRIP OR SAFETY INJECTION

1) Check SI signal NOT present.

o Go to EMG E

-0, REACTOR TRIP OR SAFETY INJECTION, Step 1 CREW Enters EMG E

-0, REACTOR TRIP OR SAFETY INJECTION Event termination: After the crew has transitioned to EMG E

-0 or at the direction of the lead examiner.

Simulator Operator: Insert Key 8 at direction of Lead Examiner.

Page 23 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.: _

5___ Event No.: __

8 , 9__ Event

Description:

Small break LOCA (4") from the 'A' loop cold leg and 'B' SIP fails to start

. Time Position Applicant's Actions or Behavior Simulator operator: Insert Key 8 at the direction of the lead examiner.

Diagnostics:

Pressurizer Level lowering and RCS Pressure lowering in an uncontrolled manner

Annunciators:

Numerous CREW Diagnose the RCS pressure lowering rapidly, possible auto reactor trip on low PZR pressure (crew could see the pressure down fast and trip and SI manually) CREW Enter EMG E

-0, REACTOR TRIP OR SAFETY INJECTION.

Step 1 NOTE: The SRO will read through the Immediate Actions as they have already been performed.

ATC, BOP 1. Verify reactor trip

a. Check all rod bottom lights

- lit - YES b. Check reactor trip breakers and bypass breakers

- open - YES SB ZL-1 SB ZL-2 SB ZL-3 SB ZL-4 c. Check intermediate range neutron flux

- decreasing

- YES SE NI-35B (gamma metrics)

SE NI-36B (gamma metrics)

2. Verify turbine trip

a. Check main stop valves all closed

- YES 3. Check AC emergency busses

- at least one energized

- YES NOTE: NB02 will not be energized due to the bus lock out

4. Check if safety injection is actuated

a. Check any indication SI is actuated

- lit Annunciator 00

-030A NF039A LOCA SEQ ACTUATED

- LIT - YES Annunciator 00

-031A NF039B LOCA SEQ ACTUATED

- LIT - YES ESFAS status panel SIS section

- any white lights lit

- YES Partial trip status permissive/block status panel

- SI red light lit

- YES Page 24 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.: __

8 , 9__ Event

Description:

Small break LOCA (4") from the 'A' loop cold leg and "B" SIP fails to start

. Time Position Applicant's Actions or Behavior

b. Check both trains of SI actuated Ann 00-030A NF039A LOCA SEQ ACTUATED

- LIT - YES Ann 00-031A NF039B LOCA SEQ ACTUATED

- LIT - NO CREW 5. Check if SI is required SI was manually actuated and was required

- YES Containment pressure is currently or has been

- greater than or equal to 3.5 psig RCS pressure is currently or has been

- less than or equal to 1830 psig

- YES Any SG pressure is currently or has been less than or equal to 615

6. Verify automatic actions using attachment F, automatic signal verification NOTE: Attachment F actions are located in this guide, page 27 7. Check main generator breakers and exciter breaker

- open - YES MA ZL-3A MA ZL-4A MA ZL-2 8. Check total AFW flow

- greater than 270,000 lbm/hr

- YES 9. Check RCS Cold Leg Temperatures:

Stable at or trending to 557°F for condenser steam dumps or S/G ARVs - YES

Stable at or trending to a range of 553°F to 557°F for S/G ARVs if recovering from an inadvertent SI

10. Establish S/G Pressure Control:

a. Check condenser

- AVAILABLE o C-9 LIT o MSIV - OPEN o Circulating water pumps

- RUNNING b. Place Steam Header Pressure Control in Manual o AB PK-507 c. Manually set Steam Header Pressure Control output to zero o AB PK-507 d. Place Steam Dump Select Switch in STEAM PRESS position o AB US-500Z e. Place Steam Header Pressure Control in Automatic o AB PK-507 Page 25 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.: __

8 , 9__ Event

Description:

Small break LOCA (4") from the 'A' loop cold leg and "B" SIP fails to start

. Time Position Applicant's Actions or Behavior CREW 11. Check PZR PORVs

a. Check PZR PORVs

- CLOSED o BB HIS-455A - YES o BB HIS-456A - YES b. Power to block valves

- AVAILABLE o BB HIS-8000A - NO o BB HIS-8000B - YES c. RCS pressure

- LESS THAN 2185 PSIG

- YES 12. Check Normal PZR Spray Valves

- CLOSED o BB ZL-455B - YES o BB ZL-455C - YES 13. Check PZR Safety Valves

- CLOSED o BB ZL-8010A - YES o BB ZL-8010B - YES o BB ZL-8010C - YES CREW 14. Check If RCPs Should Be Stopped:

a. Check RCPs

- ANY RUNNING

- YES b. Check RCS pressure

- LESS THAN 1400 PSIG

- YES c. Check ECCS pumps

- AT LEAST ONE RUNNING

CCP - YES OR

SI pump d. Check operator controlled cooldown

- NOT IN PROGRESS

- YES e. Stop all RCPs SRO 15. Direct Operator To Monitor Critical Safety Functions Using EMG F

-0, CRITICAL SAFETY FUNCTION STATUS TREES (CSFST).

CREW 16. Check If S/Gs Are Not Faulted:

a. Check pressures in all S/Gs

- o NO S/G PRESSURE DECREASING IN AN UNCONTROLLED MANNER o NO S/G COMPLETELY DEPRESSURIZED

Page 26 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.: __

8 , 9__ Event

Description:

Small break LOCA (4") from the

'A' loop cold leg and "B" SIP fails to start

. Time Position Applicant's Actions or Behavior CREW 17. () Check If S/G Tubes Are Intact:

o Check S/G Levels

- NOT INCREASING IN AN UNCONTROLLED MANNER o Condenser air discharge radiation

- NORMAL BEFORE ISOLATION -YES o GEG 925 o S/G blowdown and sample radiation

- NORMAL BEFORE ISOLATION -YES o BML 256 o SJL 026 o Turbine driven auxiliary feedwater pump exhaust radiation

- NORMAL -YES o FCT 381 o S/G steamline radiation

- NORMAL -YES o ABS 114 for S/G A o ABS 113 for S/G B o ABS 112 for S/G C o ABS 111 for S/G D CREW 18. Check If RCS Is Intact in Containment:

o Containment radiation

- NORMAL BEFORE ISOLATION

- NO o GTP 311 o GTI 312 o GTG 313 o GTP 321 o GTI 322 o GTG 323 o GTA 591 o GTA 601 18. RNO Perform the following:

a. Ensure BIT Inlet AND Outlet Valves are open o EM HIS-8803A o EM HIS-8803 B o EM HIS-880 1 A o EM HIS-880 1B b. Go to EMG E

-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

Page 27 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.: __

8 ,9__ Event

Description:

Small break LOCA (4") from the 'A' loop cold leg and "B" SIP fails to start

. Time Position Applicant's Actions or Behavior NOTE: Attachment F actions ATC or BOP F1. Check AC emergency busses energized NB01 - energized

- YES NB02 - energized

- NO F2. Verify feedwater isolation

a. Main feedwater pumps tripped

- YES Annunciator 00

-120A, MFP A trip

- lit - YES Annunciator 00

-123A, MFP B trip - lit - YES b. Main feedwater reg valves closed

- YES AE ZL-510 for S/G A AE ZL-520 for S/G B AE ZL-530 for S/G C AE ZL-540 for S/G D

c. Main feedwater reg bypass valves closed

- YES AE ZL-550 for S/G A AE ZL-560 for S/G B AE ZL-570 for S/G C AE ZL-580 for S/G D d. Main feedwater isolation valves closed

- YES AE HIS-39 for S/G A AE HIS-40 for S/G B AE HIS-41 for S/G C AE HIS-42 for S/G D

e. Main feedwater chemical injections valves closed

- YES AE HIS-43 for S/G A AE HIS-44 for S/G B AE HIS-45 for S/G C AE HIS-46 for S/G D

f. Check ESFAS status panel SGBSIS section all white lights lit

-YES Red train - YES Yellow train

- NO F3. Verify containment isolation phase A

a. Check ESFAS status panel CISA section all white lights lit Red train

- YES Yellow train

- NO F4. Verify AFW pumps running

a. Check motor driven AFW pumps both running

- NO a. RNO Manually start pumps AL HIS 22A

- YES AL HIS-23A - NO b. Check turbine driven AFW pump running

- YES Page 28 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.: __8, 9__ Event

Description:

Small break LOCA (4") from the 'A' loop cold leg and "B" SIP fails to start

. Time Position Applicant's Actions or Behavior ATC or BOP F5. Verify ECCS pumps running Check CCPs both running

- NO RNO manually start pumps BG HIS-1A - YES BG HIS-2A - NO Check SI pumps both running

- NO CT b. RNO manually start pumps EM HIS NO started then YES EM HIS NO CT2: Start at least one SIP before RVLIS Natural Circ. Range is < 45% to prevent core uncovery. Check RHR pumps both running

- NO RNO manually start pumps EJ HIS YES EJ HIS NO F6. Verify CCW alignment Check CCW pumps one running in each train

- NO RNO manually start CCW pumps as necessary to establish one running in each train EG H IS-21 or EG HIS-23 for red train

- YES EG HIS-22 or EG H IS-24 for yellow train

- NO Check one pair of CCW service loop supply and return valves for an operating CCW pump open EG ZL-15 AND EG ZL YES EG ZL-16 AND EG ZL NO F7. Check ESW pumps both running - NO RNO Manually start pumps EF HIS-55A - YES EF HIS-56A - NO F8. Check containment fan coolers running in slow speed

- YES/NO RNO Perform the following for each containment cooler fan that is still running in fast or is not running Place Containment Cooler Fan Speed Selector switches in Slow o GN HS-5 for cooler 1A

- YES o GN HS-9 for cooler 1B

- NO o GN HS-13 for cooler 1C

- YES o GN HS-17 for cooler 1D

- NO Manually start containment cooler fan o GN HIS-5 for cooler 1A

- YES o GN HIS-9 for cooler 1B

- NO o GN HIS-13 for cooler 1C

- YES o GN HIS-17 for cooler 1D

- NO Page 29 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.: __8, 9__ Event

Description:

Small break LOCA (4") from the 'A' loop cold leg and "B" SIP fails to start

. Time Position Applicant's Actions or Behavior ATC or BOP F9. Verify containment purge isolation

a. Check ESFAS status panel CPIS section all white lights lit

- NO Red train - YES Yellow train

- NO a. RNO perform the following

1. If containment purge isolation has not actuated, then manually actuate containment purge isolation SA HS YES SA HS NO 2. IF any CPIS component NOT properly aligned, THEN manually align component.

3. IF component(s) can NOT be manually aligned, THEN locally isolate instrument air to affected containment penetration. Refer to ATTACHMENT C, VALVES CLOSED BY CONTAINMENT PURGE ISOLATION SIGNAL. F10. Verify both trains of control room ventilation isolation

a. Check ESFAS status panel CRVIS section all white lights lit

- NO Red train - YES Yellow train

- NO a. RNO perform the following

1. If control room ventilation isolation has not actuated, then manually actuate control room ventilation isolation SA HS YES SA HS NO 2. IF any CRVIS component NOT properly aligned, THEN manually align associated component

3. IF neither train of CRVIS is in service, THEN establish one in service train of CRVIS using SYS GK

-122, MANUAL CRVIS LINE

-UP - NO 4. IF only one train of CRVIS can be placed in service, THEN within 90 minutes, isolate out of service train using SYS GK-122, MANUAL CRVIS LINE

-UP b. Ensure control room outer door closed

- YES F11. Verify main steamline isolation no required

a. Check containment pressure has remained less than 17 psig GN PR-934 - YES b. Check either condition below satisfied

- YES Low steamline pressure SI not blocked and steamline pressure has remained greater than 615 psig OR Low steamline pressure SI blocked and steamline pressure rate has remained less than 100 psi/50 sec

Page 30 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.: __8, 9__ Event

Description:

Small break LOCA (4") from the 'A' loop cold leg and "B" SIP fails to start

. Time Position Applicant's Actions or Behavior ATC or BOP F12. Verify containment spray not required

a. Containment pressure has remained less than 27 psig

- YES Annunciator 00

-59A, CSAS not lit Annunciator 00

-59B, CISB not lit GN PR-934 F13. Verify ECCS flow

a. Check centrifugal charging pumps to boron injection tank flow meters flow indicated EM FI-917A - YES EM FI-917B - NO b. Check RCS pressure less than 1725

- YES/NO NOTE: Depending how long the crew takes to get here pressure could be lower so steps may or may not be performed (this does not change any outcomes of the scenario)

b. NO - RNO go to step 14 OR

b. YES - then continue to c

c. Check SI pump discharge flow meters flow indicated EM FI-918 - YES EM FI-922 - NO d. Check RCS pressure less than 325 psig

- NO d. RNO go to step F14 F14. Verify AFW valves properly aligned

a. Check ESFAS status panel AFAS section all white lights lit

- NO b. Check white train ESFAS status panel AFAS section all white lights lit

- NO If any AFAS section component not properly aligned, then manually align associated component to establish desired AFAS lineup F15. Verify SI valves properly aligned

a. Check ESFAS status panel SIS section system level white lights all lit - NO Red train - YES Yellow train

- NO RNO If any SIS section component not properly aligned, then manually align associated component to establish proper SIS lineup F16. Check if NCP should be stopped

a. CCPs any running

- YES b. Stop NCP - NCP tripped

Page 31 of 31 Rev 0 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: ____ Scenario No.:

5 Event No.: __8, 9__ Event

Description:

Small break LOCA (4") from the 'A' loop cold leg and "B" SIP fails to start

. Time Position Applicant's Actions or Behavior ATC or BOP F17. Dispatch Operator To Locally Close The Following Terry Turbine Steam Drains:

FC-V048 (2000' TDAFW Pump Room)

FC-V070 (2000' TDAFW Pump Room)

FC-V089 (2000' TDAFW Pump Room)

F18. Return to procedure and step in effect Simulator Operator: When contacted to close Terry Turbine steam drains, acknowledge request.

EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT CREW Enters EMG E

-1, LOSS OF REACTOR OR SECONDARY COOLANT CREW 1. Check If RCPs Should Be Stopped:

a. Check RCPs

- ANY RUNNING

- NO 1. RNO a. Go to Step 2.

2. Check If S/Gs Are Not Faulted:

a. Check pressures in all S/Gs

- o NO S/G PRESSURE DECREASING IN AN UNCONTROLLED MANNER o NO S/G COMPLETELY DEPRESSURIZED

3. Check Intact S/G Levels:

a. Check Narrow Range Level In at Least One S/G

- GREATER THAN 6% [29%].

b. Control feed flow to maintain narrow range level in all S/Gs between 6% [29%] and 50%

4. Reset SI o SB HS-42A o SB HS-43A Scenario Termination: After SI is reset or at the discretion of the Lead Examiner.

Simulator Operator: At the direction from the lead examiner place the simulator in freeze.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: SRAPE037 Task Title:

Determine the actions required for a specific level of S/G Tube Leakage. Job Performance Measure No:

RA1 Rev 0 K/A

Reference:

2.1.7 Ability

to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

Annunciator 61A, PROCESS RAD HIHI, and 61B, PROCESS RAD HI, are in alarm. GE RE

-92 has trended up to a value of 4.6E

-006 µci/cc. OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, Attachment C, is in progress. Surveys indicate that S/G 'D' has higher radiation readings than the other three S/Gs.

AIF 21D-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, is provided.

Task Standar d: At the completion of the JPM, the Applicant will have determined that a prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is required. Additional actions are to be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), and that a Plant cooldown to Mode 5 is required. Required Materials:

OFN BB-07A, Rev 17 A. Copy Of Form AIF 21D

-004-01-03. St raight Edge. Calculator.

General

References:

OFN BB-07A, Rev 17 A.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Initiating Cue:

Determine what actions are required per OFN BB-07A, STEAM GENERATOR TUBE LEAKAGE Time Critical Task:

NO Alternate Path:

NO Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

Provide a copy of AIF 21D-004-01-03 and OFN BB

-07A, attachment C. The Applicant can either use a straight edge, or the conversion factor formula, to determine the leak rate.

Performance Step:

1 Step C1. Action Level Table:

Leak Rate Required Actions Increased Monitoring Perform Step C2 Actions Action Level 1 Perform Step C3 Actions Action Level 2

Perform Step C4 Actions Action Level 3 gpd Perform Step C5 Actions Action Level 4 Perform Step C6 Actions Standard: Used AIF 21D

-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, to determine leak rate for a reading of 4.6E

-006 µci/cc on GE RE

-92. Determined 106 to 109 gpd leak rate per straight edge.

(4.6E-006 - 2.68E-08)/ 4.23E

-08 = 108.1 gpd Determine 107 to 109 gpd leak rate by conversion factor formula. Determined that Action Level 3, perform step C5 actions, is required. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Examiner NOTE:

Performance Step:

2 Step C5. IF leakage rate is greater than or equal to 100 gpd and less than 150 gpd (Action Level 3

- EPRI limit), THEN perform the following:

a. Go to step 10 and commence prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), while continuing with this attachment. Plant cooldown to Mode 5 is required.

Standard: Determined that plant shutdown as follows is required:

50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

, Mode 3 within next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), Cooldown to Mode 5.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Other items listed in step C5 are not required to satisfy the critical step of this JPM. If they are listed it will not affect the outcome of pass / fail Terminating cue:

The JPM is completed once the Applicant has determined that a prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), and that a Plant cooldown to Mode 5 is required.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

A1 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

Annunciator 61A, PROCESS RAD HIHI, and 61B, PROCESS RAD HI, are in alarm. GE RE

-92 has trended up to a value of 4.6E

-006 µci/cc. OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, Attachment C, is in progress. Surveys indicate that S/G 'D' has higher radiation readings than the other three S/Gs. AIF 21D

-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, is provided.

Initiating Cue:

Determine what actions are required per OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: SRE09001 Task Title:

EMG ES-04, Attachment A, Determination Of RCS Boron Concentration Based On Total Mass. Job Performance Measure No:

A2 Rev 0 K/A

Reference:

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. EMG ES

-04, Natural Circulation Cooldown, is in progress.

Task Standard:

At the completion of the JPM, the Applicant will have Determined RCS Boron Concentration Based On Total Mass.

Required Materials:

EMG ES-04, ATTACHMENT A, REV 19. NPIS PZR LEVEL PICTURE. CALCULATOR.

General

References:

EMG ES-04, Rev 19.

Initiating Cue:

The CRS directs you to perform Attachment A, Determination Of RCS Boron Concentration Based On Total Mass.

Chemistry sample results are as follows:

RCS Hot Leg Loop 1

- 1610 ppm RCS Hot Leg Loop 3

- 1590 ppm Letdown Line

- 1615 ppm PZR Concentration

- 1605 ppm Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Provide the Applicant with Attachment A, the NPIS PZR Level picture and a calculator.

Performance Step:

1 Step A1. Record Chemistry sample results:

a. RCS Concentrations:

o RCS Hot Leg Loop 1 o RCS Hot Leg Loop 3 o Letdown Line

b. PZR Concentration:

Standard: Recorded the chemistry samples results provided in the initial conditions on Attachment A.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

Performance Step:

2 Step A2. Determine PZR and RCS multipliers from the following table:

Standard: Determined from the supplied picture that the NPIS PZR Level is 39.5%. Determined from the table that the correct PZR Multiplier is 0.066. Determined from the table that the correct RCS Multiplier is 0.934. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

3 Step A3. Determine PZR contribution = A:

Standard: Calculated the value for the PZR contribution.

1605 X 0.066 = 105.93 Range of 103

- 106 Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Examiner NOTE:

Performance Step:

4 Step A4. Determine RCS contribution = B:

Standard: Calculated the value for the RCS concentration contribution.

1590 X 0.934 = 1485.06 Range of 1484

- 1486 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Use the EMG ES

-04, Attachment A Key, to compare with the Applicants results.

Performance Step:

5 Step A5. Determine RCS boron concentration based on total mass = C:

Standard: Calculated the RCS boron concentration based on total mass value. 105.93 + 1485.06 = 1590.99 Range of 1587

- 1592 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant has calculated the RCS boron concentration based on total mass

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

A2 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. EMG ES

-04, Natural Circulation Cooldown, is in progress.

Initiating Cue:

The CRS directs you to perform Attachment A, Determination Of RCS Boron Concentration Based On Total Mass.

Chemistry sample results are as follows:

RCS Hot Leg Loop 1

- 1610 ppm RCS Hot Leg Loop 3

- 1590 ppm Letdown Line

- 1615 ppm PZR Concentration

- 1605 ppm Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 6 Facility: WCGS Task No: Task Title:

Perform Surveillance Test for AFD Job Performance Measure No:

A3 Rev 0 K/A

Reference:

2.2.42 - Ability to recognize system parameters that are entry level conditions for T.S. Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

The Plant has been stable at 100%. The AFD Monitor Alarm is inoperable.

Task Standard:

Upon completion of this JPM, the Candidate will have determined that the Plant is in LCO 3.2.3 per Attachment A.

Required Materials:

STS SF-002, CORE AXIAL FLUX DIFFERENCE, Calculator General

References:

STS SF-002, CORE AXIAL FLUX DIFFERENCE Initiating Cue: The Control Room Supervisor has directed you to perform STS SF-002, section 8.0. All prerequisites have been performed.

The following data is present on plant instrumentation. All four NI channels are operable. N41 N42 N43 N44 % Power 95 95 95 96 % Flux Difference 15 20 Time Critical Task:

NO Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 6 Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 6 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step 8.1.1 Monitor Axial Flux Difference (AFD) by performing the following:

IF a Power Range NI is operable, THEN record POWER RANGE FLUX DIFF and POWER LEVEL data on ATTACHMENT A, AXIAL FLUX DIFFERENCE LOG, at least once per hour.

Standard: Go to Attachment A and enter the data provide on the cue sheet.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step 8.1.2 Compare the data recorded from each operable power range channel to the limits of Figure 2.5, Axial Flux Difference (AFD) of the COLR. Standard: Compare all four channels to the limits of Figure 2.5 of the COLR.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 6 Examiner NOTE:

Performance Step:

3 Step 8.1.3 Designate whether the indicated POWER RANGE FLUX DIFF is within the ACCEPTABLE OPERATION range of Figure 2.5, Axial Flux Difference (AFD) of the COLR for each operable channel on ATTACHMENT A, AXIAL FLUX DIFFERENCE LOG, by placing a check mark in the Yes (Y) or No (N) column, initialing, and dating.

Standard: Determine that N41 and N42 are in the acceptable region, determine that N43 and N44 are in the unacceptable region, and annotate the attachment accordingly Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 Step 8.1.2 IF the indicated POWER RANGE FLUX DIFF is outside the acceptable limits of Figure 2.5, Axial Flux Difference (AFD) of the COLR on two or more operable power range channels, THEN refer to Technical Specification 3.2.3.

Standard: Determine that the Plant is in LCO 3.2.3 and report to the Control Room Supervisor.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant has completed STS SF

-002 Attachment A and has handed in the paperwork.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 5 of 6 Verification of Completion Job Performance Measure No.

RA3 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

The Plant has been stable at 100%. The AFD Monitor Alarm is inoperable.

Initiating Cue:

The Control Room Supervisor has directed you to perform STS SF-002, section 8.0. All prerequisites have been performed.

The following data is present on plant instrumentation N41 N42 N43 N44 % Power 95 95 95 96 % Flux Difference 15 20 Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: EPLANS005 Task Title:

Determine maximum authorized emergency stay times for an individual.

Job Performance Measure No:

A4 Rev 0 K/A

Reference:

2.3.4 Knowledge

of radiation exposure limits under normal or emergency conditions.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. A steam generator tube rupture has occurred on 'A' S/G and AB PV

-001 is failed open. Difficulties closing ABV0018 due to binding occurred and HP made the operators leave the area due to high radiation. Two operators and a mechanic have volunteered to re

-enter Area 5 to attempt to close ABV0018 by loosening the packing and closing the valve.

Task Standard:

At the completion of the JPM, the Applicant will have determined the maximum authorized emergency stay times for each individual associated with isolating the ARV. (the minimum is the only critical part

) Required Materials:

EPF 06-013-02, REV 1. AP 25A

-001, REV 16A. CALCULATOR.

General

References:

EPF 06-013-02, Rev 1. AP 25A

-001, Rev 16A.

Initiating Cue:

Using the information on the EPF 06

-013-02, Emergency Exposure Authorization forms, determine for each individual the maximum stay time that will not violate the authorized exposure.

Document the maximum stay time in the comments section of the EPF form.

Time Critical Task:

NO Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Provide the Applicant with a copy of EPF 06

-013-02 for each individual and a calculator.

Verify results using the supplied Keys.

Performance Step:

1 Document the maximum stay time for Operator1 in the comment section.

Standard: Recognized the projected dose numbers for TEDE, Thyroid, and Extremities on EPF 06

-013-02. Documented the maximum stay time for Operator1 in the comment section.

TEDE: 9.44 R/1.39 R/Hr = 6.79 Hr Thyroid: 125R/14.4 R/Hr = 8.68 Hr Extremities: 94.16 R/289 R/Hr = 0.3258 Hr (19.548 min)

Range is 18

- 21 minutes Maximum stay time will be 18 - 21 minutes. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

Performance Step:

2 Document the maximum stay time for Operator2 in the comment section.

Standard: Recognized the projected dose numbers for TEDE, Thyroid, and Extremities on EPF 06

-013-02. Documented the maximum stay time for Operator2 in the comment section.

TEDE: 9.57 R/1.39 R/Hr = 6.88 Hr Thyroid: 125R/14.4 R/Hr = 8.68 Hr Extremities: 92.8 R/289 R/Hr = 0.321 Hr (19.26 min)

Range is 18

- 21 minutes Maximum stay time will be 18 - 21 minutes. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Examiner NOTE:

Performance Step:

3 Document the maximum stay time for the Mechanic in the comment section.

Standard: Recognized the projected dose numbers for TEDE, Thyroid, and Extremities on EPF 06

-013-02. Documented the maximum stay time for Operator1 in the comment section.

TEDE: 8.15 R/1.39 R/Hr = 5.86 Hr Thyroid: 125R/14.4 R/Hr = 8.68 Hr Extremities: 90 R/289 R/Hr = 0.311 Hr (18.66 min)

Range is 17

- 20 minutes Maximum stay time will be 17 - 20 minutes. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant has documented the maximum authorized stay times for each individual.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

RA4 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. A steam generator tube rupture has occurred on 'A' S/G and AB PV

-001 is failed open. Difficulties closing ABV0018 due to binding occurred and HP made the operators leave the area due to high radiation. Two operators and a mechanic have volunteered to re

-enter Area 5 to attempt to close ABV0018 by loosening the packing and closing the valve.

Initiating Cue:

Using the information on the EPF 06

-013-02, Emergency Exposure Authorization forms, determine the maximum stay time for each individual that will not violate the authorized exposure. Document the maximum stay time in the comments section of the EPF form.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: SRAPE037 Task Title:

Determine the actions required for a specific level of S/G Tube Leakage. Job Performance Measure No:

A5 Rev 0 K/A

Reference:

2.1.7 Ability

to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

Annunciator 61A, PROCESS RAD HIHI, and 61B, PROCESS RAD HI, are in alarm. GE RE

-92 has trended up to a value of 4.6E

-006 µci/cc. OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, Attachment C, is in progress. Surveys indicate that S/G 'D' has higher radiation readings than the other three S/Gs.

AIF 21D-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, is provided.

Task Standard:

At the completion of the JPM, the Applicant will have determined that a prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is required. Additional actions are to be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), and that a Plant cooldown to Mode 5 is required. Required Materials:

OFN BB-07A, Rev 17 A. Copy Of Form AIF 21D

-004-01-03. St raight Edge. Calculator.

General

References:

OFN BB-07A, Rev 17 A.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Initiating Cue:

Determine what actions are required per OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE Time Critical Task: NO Alternate Path:

NO Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

Provide a copy of AIF 21D

-004-01-03 and OFN BB

-07A, attachment C. The Applicant can either use a straight edge, or the conversion factor formula, to determine the leak rate.

Performance Step:

1 Step C1. Action Level Table:

Leak Rate Required Actions Increased Monitoring Perform Step C2 Actions Action Level 1 Perform Step C3 Actions Action Level 2

Perform Step C4 Actions Action Level 3 gpd Perform Step C5 Actions Action Level 4 Perform Step C6 Actions Standard: Used AIF 21D

-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, to determine leak rate for a reading of 4.6E

-006 µci/cc on GE RE

-92. Determined 106 to 109 gpd leak rate per straight edge.

(4.6E-006 - 2.68E-08)/ 4.23E

-08 = 108.1 gpd.

Determine 107 to 109 gpd leak rate by conversion factor formula. Determined that Action Level 3, perform step C5 actions, is required. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Examiner NOTE:

Performance Step:

2 Step C5. IF leakage rate is greater than or equal to 100 gpd and less than 150 gpd (Action Level 3

- EPRI limit), THEN perform the following:

a. Go to step 10 and commence prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), while continuing with this attachment. Plant cooldown to Mode 5 is required.

Standard: Determined that plant shutdown as follows is required:

50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Mode 3 within next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), Cooldown to Mode 5.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Other items listed in step C5 are not required to satisfy the critical step of this JPM. If they are listed it will not affect the outcome of pass / fail Terminating cue:

The JPM is completed once the Applicant has determined that a prompt and controlled plant shutdown to less than or equal to 50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , be in Mode 3 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ), and that a Plant cooldown to Mode 5 is required.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

A5 Examinee's Name:

Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

Annunciator 61A, PROCESS RAD HIHI, and 61B, PROCESS RAD HI, are in alarm. GE RE

-92 has trended up to a value of 4.6E

-006 µci/cc. OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE, Attachment C, is in progress. Surveys indicate that S/G 'D' has higher radiation readings than the other three S/Gs. AIF 21D

-004-01-03, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, is provided.

Initiating Cue:

Determine what actions are required per OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 8 Facility: WCGS Task No: SRE09001 Task Title:

EMG ES-04, Attachment A, Determination Of RCS Boron Concentration Based On Total Mass. Job Performance Measure No:

A6 Rev 0 K/A

Reference:

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

You are the Control Room Supervisor. EMG ES-04, Natural Circulation Cooldown, is in progress. You have directed the Reactor Operator to perform Attachment A, Determination Of RCS Boron Concentration Based On Total Mass.

Reactor engineering has determined required minimum shutdown margin boron concentration to be 1600 ppm.

Task Standard:

At the completion of the JPM, the Applicant will have disapproved the Reactor Operator's calculations. The Applicant will recalculate the results and determine that the current boron concentration does not meet the required minimum shutdown margin concentration requirement.

Required Materials:

EMG ES-04, ATTACHMENT A, step 10, REV 19. NPIS PZR LEVEL PICTURE. CALCULATOR.

General

References:

EMG ES-04, Rev 19. STS RE

-004, Rev 30.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 8 Initiating Cue:

Review and approve / disapprove the Reactor Operator's calculations.

Determine if the current RCS boron concentration is greater than the required minimum shutdown margin concentration AND if any TS are applicable. Chemistry sample results are as follows:

RCS Hot Leg Loop 1

- 1610 ppm RCS Hot Leg Loop 3

- 1590 ppm Letdown Line

- 1615 ppm PZR Concentration

- 1605 ppm Document your results on EMG ES

-04, NATURAL CIRCULATION COOLDOWN, Attachment A.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 8 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Provide the Applicant with the Initial Attachment A, the Shutdown Margin Calculation, the NPIS PZR Level picture and a calculator.

Performance Step:

1 Step A1. Record Chemistry sample results:

a. RCS Concentrations:

o RCS Hot Leg Loop 1 o RCS Hot Leg Loop 3 o Letdown Line

b. PZR Concentration:

Standard: Recognized that the chemistry samples results provided in the initial conditions are NOT correctly documented.

Corrected the chemistry sample results.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Corrected values are documented on the Corrected EMG ES

-04 Attachment A form.

Appendix C 2 Form ES-C-1 Page 4 of 8 Examiner NOTE:

Performance Step:

2 Step A2. Determine PZR and RCS multipliers from the following table:

Standard: Determined from the supplied picture that the NPIS PZR Level is 39.5%. Determined from the table that the correct PZR Multiplier is 0.066. Determined from the table that the correct RCS Multiplier is 0.934. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Corrected values are documented on the Corrected EMG ES

-04 Attachment A form.

Examiner NOTE:

Performance Step:

3 Step A3. Determine PZR contribution = A:

Standard: Recognized that the incorrect value for the PZR concentration was used. Corrected the value and recalculated the result.

1605 X 0.066 = 105.93 Range of 103

- 106 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Corrected values are documented on the Corrected EMG ES

-04 Attachment A form.

Appendix C 2 Form ES-C-1 Page 5 of 8 Examiner NOTE:

Performance Step:

4 Step A4. Determine RCS contribution = B:

Standard: Recognized that the incorrect value for the RCS concentration was used. Corrected the value and recalculated the result.

1590 X 0.934 = 1485.06 Range of 1484 - 1486 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Corrected values are documented on the Corrected EMG ES

-04 Attachment A form.

Examiner NOTE:

Use the Corrected EMG ES-04, Attachment A, to compare with the Applicants results.

Performance Step:

5 Step A5. Determine RCS boron concentration based on total mass = C:

Standard: Recognized that the RCS boron concentration based on total mass value was incorrect.

Corrected the values and recalculated the result. 105.93 + 1485.06 = 1590.99 Range of 1587

- 1592 Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 8 Examiner NOTE:

Performance Step:

6 Step 10.c.

Check RCS Boron Concentration

- GREATER THAN COLD SHUTDOWN CONCENTRATION Standard: Recognized from Shutdown Margin Calculation that the RCS boron concentration based on total mass does NOT meet the required 1600 ppm boron concentration.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

7 Step Applicable TS. Standard: Recognized the unit is currently in TS 3.1.1, Shutdown Margin, Condition A, SDM not within limit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant recognized that the RCS boron concentration based on total mass does NOT meet the requir ed 1600 ppm boron concentration AND TS 3.1.1 condition A applies.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 7 of 8 Verification of Completion Job Performance Measure No.

A6 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Control Room Supervisor. EMG ES

-04, Natural Circulation Cooldown, is in progress. You have directed the Reactor Operator to perform Attachment A, Determination Of RCS Boron Concentration Based On Total Mass. Reactor engineering has determined required minimum shutdown margin boron concentration to be 1600 ppm

. Initiating Cue:

Review and approve / disapprove the Reactor Operator's calculations. Determine if the current RCS boron concentration is greater than the required minimum shutdown margin concentration AND if any TS are applicable.

Chemistry sample results are as follows:

RCS Hot Leg Loop 1

- 1610 ppm RCS Hot Leg Loop 3

- 1590 ppm Letdown Line

- 1615 ppm PZR Concentration

- 1605 ppm Document your results on EMG ES

-04, NATURAL CIRCULATION COOLDOWN, Attachment A.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 5 Facility: WCGS Task No: AP26C004001 Task Title:

Determine the Operability of BG HV-8357A and CCP A.

Job Performance Measure No:

A7 Rev 0 K/A

Reference:

2.2.37 Ability to determine operability and/or availability of safety related equipment.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

You are the Control Room Supervisor. The Reactor Operator has completed a partial STN BG

-202 for BG HV

-8357A. Task Standard:

At the completion of the JPM, the Applicant will have Determined that BG HV-8357A is INOPERABLE and that CCP A is OPERABLE. Required Materials:

STN BG-202, REV 1. TECHNICAL SPECIFICATIONS. TECHNICAL SPECIFICATIONS BASES.

General

References:

STN BG-202, Rev 1. Technical Specifications. Technical Specifications Bases. Initiating Cue:

Review STN BG

-202 and determine operability of the BG HV

-8357A and A CCP. Time Critical Task:

NO Alternate Path:

NO Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 2 of 5 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Provide the Applicant with the completed STN BG

-202, a copy of Technical Specifications, and a copy of Technical Specifications Bases.

Performance Step:

1 Step 8.4.6.

Review STN BG

-202 results.

Standard: Recognized that BG HV

-8357A failed the PIT requirement.

Determined that per required action 1 that BG HV

-8357A is INOPERABLE and that corrective actions are required.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step 7.2. Determine Operability per T.S. 3.5.2.

Standard: Determined per T.S. 3.5.2 Bases that the CCPs may be considered OPERABLE with its associated discharge to RCP seal throttle valve, BG

-HV-8357A, INOPERABLE

. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 5 Terminating cue:

The JPM is completed once the Applicant determines that BG HV-8357A is INOPERABLE, and A CCP is OPERABLE.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 4 of 5 Verification of Completion Job Performance Measure No.

A7 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Control Room Supervisor. The Reactor Operator has completed a partial STN BG

-202 for BG HV

-8357A. Initiating Cue:

Review STN BG

-202 and determine operability of the BG HV

-8357A and A CCP.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 6 Facility: WCGS Task No: Task Title:

Review a release permit for approval Job Performance Measure No:

A8 Rev 0 K/A

Reference:

2.3.6 Ability

to approve release permits Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

Today is 11 2015 at 2230. You are the Shift Manager. A containment purge to lower Containment pressure was initiated and stopped due to workload. The crew is preparing to re

-initiate the purge using the same permit. The Reactor Operator has prepared Purge Permit page 2 of 3 for the release.

Task Standard:

At the completion of this JPM, the Candidate will have documented that:

The RO inadvertently transposed the number for GTRE

-22/33 and GTRE

-31/32 when establishing the setpoints.

This permit has expired and cannot be used.

The reading for GTG 313 exceeds the restart limit and the purge cannot be reinitiated Required Materials:

APF -07B-001-09, CTMT Purge Release Permit General

References:

AP 07B-001, Radioactive Releases AI 07B- 024, Preparation of Containment Purge Permits APF-07B-001-09-08, Containment Purge Release Permit

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 6 Initiating Cue:

Review the permit for the purge re-initiation. Approve or disapprove the release and document any errors.

The following readings are indicated on the RM11 High Setpoint Low Setpoint GTRE-22/33 2.06 E -03 2.06 E -04 GTRE-31/32 1.00 E -03 3.34 E -05 Time Critical Task:

NO Alternate Path: NO Validation Time:

20 Minutes Appendix C 2 Form ES-C-1 Page 3 of 6 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step Check the release conditions Standard: Note that the RO transposed the number for GTRE

-22/33 and GTRE

-31/32 when establishing the setpoints.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step Check the special instructions Standard: Note that the permit has expired Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 6 Examiner NOTE:

Performance Step:

3 Step Check the Authorization Section, Release Data, and the continuation sheet Standard: Note that the reading for GTG 313 exceeds the allowable value for restart of the purge Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

After the Candidate has completed the review of the permit, documented the errors found, and handed the JPM in, the JPM is complete.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 5 of 6 Verification of Completion Job Performance Measure No.

A8 Examinee's Name:

Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

Today is 11 2015 at 2230. You are the Shift Manager. A containment purge to lower Containment pressure was initiated and stopped due to workload. The crew is preparing to re

-initiate the purge using the same permit. The Reactor Operator has prepared Purge Permit page 2 of 3 for the release.

Initiating Cue:

Review the permit for the purge re

-initiation. Approve or disapprove the release and document any errors.

The following readings are indicated on the RM11 High Setpoint Low Setpoint GTRE-22/3 3 2.06 E -03 2.06 E -04 GTRE-31/32 1.00 E -03 3.34 E -05 Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 7 Facility: WCGS Task No: EPLANS004 Task Title:

Make a Protective Action Recommendation.

Job Performance Measure No:

A9 Rev 0 K/A

Reference:

2.4.44 Knowledge of emergency plan protective action recommendations.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom X Simulator Plant Read to the examinee:

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

Initial Conditions:

A Site Area Emergency has been declared by the Control Room and the Immediate Notification form complete

d. You are the Off

-site Emergency Manager and the Dose Assessment Coordinator has provided you with a dose assessment (EDCP).

Task Standard:

At the completion of the JPM, the Applicant will have validated the EDCP and developed an accurate Emergency Notification form within 15 minutes of receiving the EDCP.

Required Materials:

EPP 06-001, Rev 22. EPP 06

-005, Rev 7. EPP 06

-006, Rev 9. EPP 06

-007, Rev 23. EPP 06

-012, Rev 14A. Initial Notification Form, CR

-00 1, NPIS Screen PRAD

, EDCP. Final Notification Form (Key), EOF

-001. General

References:

EPP 06-001, Rev 22. EPP 06

-005, Rev 7. EPP 06

-006, Rev 9. EPP 06

-007, Rev 23. EPP 06

-012, Rev 14A.

Initiating Cue:

Develop the appropriate Emergency Notification form. THIS IS A TIME CRITICAL TASK

. Time Critical Task:

YES Alternate Path:

NO Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 7 Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 7 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Time Zero (T-0) for the 15 minute requirement to complete the Emergency Notification begins when the EDCP is provided. Performance Step:

1 Step 7.1.2 Determine the protective action recommendation(s) using ATTACHMENT A, PROTECTIVE ACTION RECOMMENDATION CHART OR the PROTECTIVE ACTION RECOMMENDATION CHART located in the emergency facilities.

o IF EDCP printout is not available, THEN use ATTACHMENT B, SUBZONES AFFECTED BY WIND DIRECTION, to determine the affected subzones.

OR o IF EDCP printout is not available, THEN use the correct isopleth for the current stability class to determine the affected subzones on the 10 mile EPZ map.

Standard: Recognized that an EDCP IS available.

Referred to Attachment A to determine that the Subzones on the EDCP are the correct ones for the Protective Action Recommendation (PAR).

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 7 Examiner NOTE:

This is a "PAR Only" notification. The Applicant will use the information on CR

-00 1 to fill in the classification information.

Use the provided key (EOF

-001) to determine the accuracy of the notification form. The form MUST be accurate in order to meet the standard. The following information is required to be accurate:

Message #, Status , Code Word , Type, Emergency Classification information , Met data , Release data , Protective action recommendation information, and Signature and date Performance Step:

2 Step 7.1.3 Indicate the protective action recommendation on EPF 06

-007-01, WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION.

1. Evacuation is the normal PAR made during emergencies. (3.1.6) 2. Shelter is the PAR made when known conditions exist that would make evacuation a greater hazard to the public. (3.1.6) 3. Once a PAR has been made, that PAR remains in effect until the event is terminated. All PARs made should be indicated on all notification forms once they are made.

Standard: Completed the form accurately.

Completed the form within 15 minutes of receiving the INITIAL EDCP. WHEN the Applicant provides the form, THEN document the stop time.

T-End Total Minutes:

WHEN the Applicant provides the form, THEN document the accuracy of the form.

The form is accurate:

The form is NOT accurate:

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 7 Terminating cue:

The JPM is completed once the Emergency Notification form is filled out, signed and dated.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 6 of 7 Verification of Completion Job Performance Measure No.

A9 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

A Site Area Emergency has been declared by the Control Room and the Immediate Notification form completed. You are the Off

-site Emergency Manager and the Dose Assessment Coordinator has provided you with a dose assessment (EDCP).

Initiating Cue:

Develop the appropriate Emergency Notification for

m. THIS IS A TIME CRITICAL TASK

.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 9 Facility: WCGS Task No: APE024004 Task Title:

Establishing Alternate Boration Flow path starting at Step A7 of OFN BG-009, EMERGENCY BORATION. Job Performance Measure No:

P1 (AP) Rev 0 K/A

Reference:

APE 024 AA 1.20

- Ability to operate and or monitor the following as they apply to emergency boration

- Manual boration valve and indicators.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Initial Conditions:

The plant was in MODE 1. The Reactor has tripped but 3 control rods failed to fully insert. The Control room is currently implementing EMG ES

-02, REACTOR TRIP RESPONSE, and the RO is performing OFN BG

-009, EMERGENCY BORATION. Attempts to establish any Emergency Boration flow from the Control Room have failed. Task Standard:

Upon completion of this JPM the operator will have established Alternate Boration Flow through BG HV

-177 per OFN BG-009, EMERGENCY BORATION, Attachment A. Required Materials:

PPE appropriate for Auxiliary Building Watchstander. OFN BG-009, EMERGENCY BORATION General

References:

OFN BG-009, EMERGENCY BORATION, Rev 25 Initiating Cue:

You are the Aux Building Operator. The Control Room Supervisor directs you to perform Attachment 'A' beginning at step A7 of OFN BG

-009 and establish Manual Boration. Time Critical Task:

NO Alternate Path:

YES Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 2 of 9 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step A7.a Establish Manual Boration:

a. Pump Suction Isolation Valve.

o BG-DOORWAY) Standard: Examinee located valve BG

-V177 in the 'A' Safety Injection Pump Rm. (1974 el. Aux. bldg)

Examinee broke lock tab

Examinee turned handwheel counter

-clockwise Cue: After examinee describes Unlocking and Opening the valve:

CUE: Handwheel is turning Counter

-clockwise, stem is rising.

Stem is fully extended.

Score: SAT or UNSAT SAT or UNSAT Comment: BG-V177 is a diaphragm valve with rising stem.

Appendix C 2 Form ES-C-1 Page 3 of 9 Examiner NOTE:

ALTERNATE SUCCESS PATH

- Flow indicated will be zero on the gage. Performance Step:

2 Step A7.b Establish Manual Boration:

b. Check Normal Boration Flow

- GREATER THAN 30 GPM o BG FR-110 Red Pen RNO: Go to step A9.

Standard: Examinee should check if flow is >30 gpm by calling the Control Room Examinee went to step A9 Cue: After examinee contacts the Control Room to check flow:

CUE: "Flow indicates zero."

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

3 Step A9 P - o BG PDI-108 Standard: Examinee locates BG PDI

-108 on the 2000 el Aux bldg, Filter room hallway, on West wall.

Examinee read BG PDI

-108 Cue: After examinee locates indicator and explains checking for P: Note: Use pen or other pointing device to show where the needle is and let the examinee tell you what the indicator is reading.

CUE: Place pen or pointing device to the indicated pressure of 2 5 PSID Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 9 Examiner NOTE:

Performance Step:

4 Step A9 RNO a. Bypass Boric Acid Filter:

a. Open Boric Acid Filter Bypass Upstream Isolation Valve.

o BG-V173 - OPEN (1974' AUX ROOM A) Standard: Examinee locates BG

-V173 on the 1974 el Aux bldg. Valve is located in the 'A' BAT room on the South wall.

Examinee turned handwheel counter

-clockwise.

Cue: CUE: Handle is turning Counter

-clockwise, stem is rising.

The stem is fully extended.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

5 Step A9 RNO b. Bypass Boric Acid Filter:

b. Open Boric Acid Filter Bypass Downstream Isolation Valve.

o BG-V172 - , BORIC ACID TANK ROOM A) Standard: Examinee locates BG

-V172 on the 1974 el Aux bldg. Valve is located in the 'A' BAT room on the South wall.

Examinee turned handwheel counter-clockwise Cue: CUE: Handle is turning Counter

-clockwise, stem is rising.

The stem is fully extended.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 9 Examiner NOTE:

By closing this valve this starts the alternate boration flow to the RCS.

Performance Step:

6 Step A9 RNO c Bypass Boric Acid Filter:

c. Close boric acid filter to BAT "A" throttle valve.

o BG-V319 - TANK ROOM A)

Standard: Examinee locates BG

-V319 on the 1974 el Aux bldg. Valve is located in the 'A' BAT room on the South wall.

Examinee removed locking tab.

Examinee turned handwheel clockwise Cue: CUE: Handle is turning clockwise, stem is inserting.

The handle will no longer turn.

Stem is fully inserted.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

7 Step A9 RNO d. Bypass Boric Acid Filter:

d. Close Boric Acid Filter Inlet Isolation Valve.

o BG-V149 - Standard: Examinee locates BG

-149 on the 2000 el Aux bldg, Filter room hallway, above filter room.

Examinee removed lock tab.

Examinee turned reach rod handwheel clockwise.

Cue: CUE: Handwheel is turning clockwise Position indicator is moving downward.

Handwheel is turning with post indicator full down.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 9 Examiner NOTE:

Performance Step:

8 Step A9 RNO e. Bypass Boric Acid Filter:

e. Close Boric Acid Filter Outlet Isolation Valve.

o BG-V152 - Standard: Examinee locates BG

-152 on the 2000 el Aux bldg, Filter room hallway, above filter room. *Examinee removed lock tab

Examinee turned reach rod handwheel clockwise.

Cue: CUE: Handwheel is turning clockwise, the position indicator is moving downward.

The handwheel is turning with position indicator full down.

Score: SAT or UNSAT SAT or UNSAT Comment:

Examiner NOTE:

Performance Step:

9 Step A9 RNO f. Bypass Boric Acid Filter:

f. Direct Maintenance to change filter as soon as possible.

Standard: Cue: WHEN examinee contacts Control Room or Maintenance to change filter THEN: CUE: "Maintenance has been contacted to change filter."

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 9 Examiner NOTE:

Performance Step:

10 Step A10 Check If Alternate Boration Flow Has Been Established:

Normal Boration Flow

- GREATER THAN 30 GPM o BG FR-110 Red Pen OR

Emergency Boration Flow

- GREATER THAN 30 GPM o BG FI-183A Standard: Examinee contacts the Control Room Cue: After examinee contacts the Control Room:

CUE: Flow on BG FR-110 is 72 GPM Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed when flow is indicated on BG FR

-110 greater than 30 gpm. STOP TIME:

Appendix C 3 Form ES-C-1 Page 8 of 9 Verification of Completion Job Performance Measure No.

P1 (A P) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

The plant was in MODE 1. The Reactor has tripped but 3 control rods failed to fully insert. The Control room is currently implementing EMG ES

-02, REACTOR TRIP RESPONSE, and the RO is performing OFN BG

-009, EMERGENCY BORATION. Attempts to establish any Emergency Boration flow from the Control Room have failed. Initiating Cue:

You are the Aux Building Operator. The Control Room Supervisor directs you to perform Attachment 'A' beginning at step A7 of OFN BG

-009 and establish Manual Boration.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 9 Facility: WCGS Task No: APE068008 Task Title:

Perform the Turbine Bldg Operators actions of OFN RP

-017 to trip the RCPs and remove control power to the breakers. Job Performance Measure No:

P2 (TSA) Rev 0 K/A

Reference:

APE 068 AK3.18, Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation: Actions contained in EOP for control room evacuation emergency task Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the examinee:

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

Initial Conditions:

You are the operator designated to perform Turbine Building actions in OFN RP-017. The announcement to evacuate the control room and entry into OFN RP

-017 has just been made and the Reactor has been tripped.

Task Standard:

Upon completion of this JPM the Applicant will have tripped the RCPs locally and removed control power from the associated breakers.

Required Materials:

PPE appropriate for Turbine Building Watchstander. OFN RP 017, Attachment B, Rev 47, High security key for entry into the security cage for PK01 & PK02, OR pictures of PK41 and PK62.

General

References:

OFN RP-017, Rev 47

. AI 16-007, Rev 8A , AI 21-017 d, Rev 5A (PSA OPA-EVAC-CR) Initiating Cue:

Perform your designated OFN RP-017 actions through step B5. THIS IS A TIME SENSITIVE TASK. MINIMIZE YOUR VERBALIZATION

. Time Critical Task:

Yes Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 9 Alternate Path:

NO Validation Time:

7 Minutes Appendix C 2 Form ES-C-1 Page 3 of 9 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

FOR CONSISTENCY, START THE JPM FROM THE AREA NEXT TO THE ELEVATOR ON 2033' COMMUNICATIONS CORRIDOR. This step provides the cue to start the JPM. Start the stop watch. Performance Step:

1 Step 4.a. Announce the evacuation of the Control Room due to fire and entry into OFN RP

-017, using Plant Gaitronics handset.

Standard: Recognized requirement to perform OFN RP

-017 duties.

Cue: Cue: Announcement of control room evacuation due to OFN RP 017 entry and Reactor Trip.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 9 Examiner NOTE: Per AI 16-007, WCNOC Electrical Safety Manual, Operating the breaker locally with the door closed and latched requires natural fabric or FR clothing worn under Flash Suit (Coat, Pants and Hood). These are located in the emergency locker. The Applicant should simulate donning the apparel.

Steps B1 and B2 are immediate action steps.

Performance Step:

2 Step B1. Locally Trip RCPs:

o PA0107 For RCP A

- TRIPPED o PA0108 For RCP B

- TRIPPED o PA0205 For RCP C

- TRIPPED o PA0204 For RCP D

- TRIPPED Standard: Located emergency locker and donned Flash Suit.

Located RCP breakers.

Locally tripped all four RCPs by memory.

Cue: WHEN Applicant locates emergency locker and describes donning Flash Suit, THEN: Cue: Flash Suit donned.

WHEN Applicant locates breaker and simulates turning pistol grip counterclockwise, THEN: Cue: Green light lit, red light off, load clu nk noise heard.

Repeat cue for each breaker.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 9 Examiner NOTE:

Steps B1 and B2 are immediate action steps.

Performance Step:

3 Step B2. Proceed To 2033 Turbine And Obtain A Copy Of This Procedure Standard: Obtained procedure from emergency locker on 2033' level of Turbine Building.

Cue: WHEN Applicant describes acquiring the procedure, THEN: Provide a copy of the procedure to the Applicant.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 Step B3. Perform The following:

a. Obtain the following from emergency locker:

o Radio o Flashlight

b. Obtain pocket ion chambers and an RDD from the emergency locker for personnel entering the RCA:

o Low-Range PIC 0

-1000 mR o High-Range PIC 0

-5 R o RDD c. Select Channel 1 on radio. Standard: Obtained required equipment.

Cue: WHEN Applicant describes obtaining the proper equipment, THEN: Cue: Radio, flashlight, dosimetry, and radio have been obtained. Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 9 Examiner NOTE:

PK41 is located inside a security cage requiring a security key and permission to enter.

IF permission to enter the security cage was granted, THEN Applicant will simulate taking the breaker to OFF at panel PK41. OTHERWISE provide Picture 1 WHEN Applicant indicates where PK41 is located.

Performance Step:

5 Step B4. On PK41, Open Breaker For DC Control Power To PA01.

o PK4103 - OFF Standard: Entered security cage and located PK41.

Turned PK4103 to OFF.

Cue: WHEN Applicant simulates positioning handle down to the OFF position, THEN: Cue: Breaker indicates OFF.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 9 Examiner NOTE:

PK62 is located inside a security cage requiring a security key and permission to enter. IF permission to enter the security cage was granted, THEN Applicant will simulate taking the breaker to OFF at panel PK62. OTHERWISE provide Picture 2 WHEN Applicant indicates where PK62 is located.

Performance Step:

6 Step B5. On PK62, Open Breaker For DC Control Power To PA02.

o PK6204 - OFF Standard: Entered security cage and located PK62.

Turned PK6204 to OFF.

Cue: WHEN Applicant simulates positioning handle down to the OFF position, THEN: Cue: Breaker indicates OFF.

Stop the stop watch.

Record Time:

Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed when RCPs are tripped with control power removed.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 8 of 9 Verification of Completion Job Performance Measure No.

P2 (TSA) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

You are the operator designated to perform Turbine Building actions in OFN RP-017. The announcement to evacuate the control room and entry into OFN RP

-017 has just been made and the Reactor has been tripped.

Initiating Cue:

Perform your designated OFN RP

-017 actions through step B5. THIS IS A TIME SENSITIVE TASK. MINIMIZE YOUR VERBALIZATION.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 18 Facility: WCGS Task No: APE057007 Task Title:

Energize Bus NN01 from NN15.

Job Performance Measure No:

P3 - A Rev 0 K/A

Reference:

APE 057 AA1.01, Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual inverter swapping.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the examinee:

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

Initial Conditions:

The crew is responding to a loss of NN01, which was powered from inverter NN11 prior to the bus loss. NN11 bypass transformer did NOT energize NN01. Task Standard:

At the completion of the JPM, the Applicant will have energized bus NN01 from NN15 on the bypass transformer via the static switch

. Required Materials:

General

References:

OFN NN-021, Rev 25.

Initiating Cue:

The CRS has dispatched you to perform Attachment E, beginning with step E.4.3.3, to energize bus NN01 from NN15.

Inform the Control Room when NN01 is energized NN15 on the bypass transformer via the static switch.

The NN15 manual transfer switch Kirk Keys and NK79 transfer switch key are in your possession.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 2 of 18 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step E.4.3.3.

IF indicator light NN15 ALIGNED TO NK01 is NOT LIT, THEN ALIGN NN15 to NK01 as follows:

a. PLACE NK HS-15, NK01/NK03 TRANSFER SWITCH CONTROL HANDSWITCH in NK01 position.

o NK HS NK01 Standard: Located NK79.

Recognized indicator light NN15 ALIGNED TO NK01 is NOT LIT. Placed NK HS

-15 to NK01 position.

Cue: WHEN Applicant locates NN15 aligned to NK01 light, THEN: Cue: Light NOT lit.

WHEN Applicant describes inserting the key into NK HS

-15 and selecting NK01 position, THEN: Cue: Key is inserted. Key is turned in the NK01 direction.

Score: SAT or UNSAT SAT or UNS AT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 18 Examiner NOTE:

Performance Step:

2 Step E.4.3.4.

VERIFY indicator light NN15 ALIGNED TO NK01 is lit.

Standard: Verified indicator light NN15 aligned to NK01 lit.

Cue: WHEN Applicant locates light indicator, THEN: Cue: NN15 aligned to NK01 light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

3 Step E.4.3.5.

VERIFY SWING INV NN15 white pilot light is lit.

Standard: Located NN15.

Verified NN15 white pilot light lit.

Cue: WHEN Applicant locates pilot light, THEN: Cue: White pilot light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 18 Examiner NOTE:

Performance Step:

4 Step E.4.4.

STARTUP NN15 swing inverter as follows:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

5 Step E.4.4.1.

TEST NN15 lamps by depressing the PRESS TO TEST LIGHTS button while inspecting lamps.

a. PRESS TO TEST LIGHTS

- DEPRESSED b. LAMPS - ALL LIT Standard: Tested NN15 lamps.

Cue: WHEN Applicant locates press to test lights button and describes depressing button and inspecting lamps, THEN: Cue: Lamps all lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 18 Examiner NOTE:

Performance Step:

6 Step E.4.4.2.

CLOSE NN15 B1, DC INPUT BREAKER as follows:

a. DEPRESS and HOLD the PRECHARGE pushbutton.

o PRECHARGE BUTTON

- DEPRESSED and HELD

b. WHEN PRECHARGE light is lit, THEN CLOSE B1 breaker.

1) PRECHARGE LIGHT

- LIT 2) B1 - ON c. WHEN DC INPUT BREAKER CLOSED light is lit, THEN RELEASE PRECHARGE pushbutton.

1) DC INPUT BREAKER CLOSED

- LIT 2) PRECHARGE PUSHBUTTON

- RELEASED Standard: Depressed and held precharge pushbutton.

Placed NN15 B1 to on when precharge light lit.

Released precharge pushbutton when DC input breaker closed light lit.

Cue: WHEN Applicant locates and describes depressing and holding precharge button, THEN: Cue: Precharge button depressed and held. Precharge light lit.

WHEN Applicant locates and describes placing NN15 B1 to ON, THEN: Cue: Switch is in UP position. DC input breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 18 Examiner NOTE: Performance Step:

7 Step E.4.4.3.

RECORD DC INPUT VOLTS from NNEI0151.

o NNEI0151 volts __________VDC Standard: Recorded DC input voltage of 125 VDC

. Cue: WHEN Applicant locates NNEI0151 THEN: CUE: Point to the 125 VDC value. Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

8 Step E.4.4.4.

CLOSE NN15 B701, AC INPUT TO BYPASS CVT breaker.

o B701 - ON Standard: Placed NN15 B701 to ON.

Cue: WHEN Applicant locates and describes placing NN15 B701 to ON, THEN: Cue: Switch is in UP position. AC input to bypass CVT breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 18 Examiner NOTE:

Performance Step:

9 Step E.4.4.5. CLOSE NN15 B4, BYPASS INPUT TO STATIC SWITCH breaker. o B4 - ON Standard: Placed NN15 B4 to ON.

Cue: WHEN Applicant locates and describes placing NN15 B4 to ON, THEN: Cue: Switch is in UP position. Bypass input to static switch breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 Step E.4.4.6.

CLOSE NN15 B2, INVERTER OUTPUT breaker.

o B2 - ON Standard: Placed NN15 B2 to ON.

Cue: WHEN Applicant locates and describes placing NN15 B2 to ON, THEN: Cue: Switch is in UP position. Inverter output breaker RED light is lit. Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 18 Examiner NOTE:

Performance Step:

11 Step E.4.4.7.

RESET inverter alarms by pressing the ALARM RESET pushbutton.

o ALARM RESET

- PRESSED Standard: Reset alarms.

Cue: WHEN Applicant locates and describes depressing alarm reset, THEN: Cue: Alarm reset depressed.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

12 Step E.4.4.8.

VERIFY the following alarms clear.

o OVER TEMPERATURE

- CLEAR (RED) o DC LOW VOLTAGE

- CLEAR (RED) o DC HIGH VOLTAGE - CLEAR (RED) o OUT OF SYNC

- CLEAR (RED) o INVERTER OUTPUT LOW VOLTAGE

- CLEAR (RED) o FUSE BLOWN

- CLEAR (RED) Standard: Verified alarms clear.

Cue: WHEN Applicant locates and inspects alarms, THEN: Cue: Alarm lights NOT lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 18 Examiner NOTE:

Performance Step:

13 Step E.4.4.9.

WHEN NNEI0152 indicates between 112.1 VAC to 123.9 VAC, THEN continue. Standard: Recognized NNEI0152 indicated between 112.1 VAC to 123.9 VAC. Cue: WHEN Applicant locates NNEI0152, THEN: Cue: Point to the 120 VAC demarcation.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

14 Step E.5. At NN15, ensure NN15 static switch in bypass source supplying load position as follows:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 18 Examiner NOTE:

Performance Step:

15 Step E.5.1.

IF BYPASS SOURCE SUPPLYING LOAD light is NOT lit, THEN perform the following:

Standard: Recognized bypass source supplying load light is NOT lit. Cue: WHEN Applicant locates bypass source supplying load light, THEN: Cue: Light NOT lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

16 Step E.5.1.1 VERIFY NN15 IN SYNC light is lit.

Standard: Verified NN15 in sync light lit.

(GREEN) Cue: WHEN Applicant locates in sync light, THEN: Cue: Light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 18 Examiner NOTE:

Performance Step:

17 Step E.5.1.2.

DEPRESS NN15 BYPASS SOURCE TO LOAD pushbutton.

o BYPASS SOURCE TO LOAD

- DEPRESSED Standard: Depressed NN15 bypass source to load pushbutton.

Cue: WHEN Applicant locates and describes depressing bypass source to load pushbutton, THEN: Cue: Pushbutton depressed.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

18 Step E.5.1.3 Verify BYPASS SOURCE SUPPLYING LOAD

- LIT Standard: Verified bypass source supplying load light lit.

Cue: WHEN Applicant locates bypass source supplying load light, THEN: Cue: Light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 18 Examiner NOTE:

Performance Step:

19 Step E.6. PERFORM the following to energize NN01 or transfer load from NN11 to NN15, as applicable:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

20 Step E.6.1.

At NN15, UNLOCK BOTH Kirk Key locks.

o KIRK KEY LOCKS

- UNLOCKED Standard: Unlocked both Kirk Key locks.

Cue: WHEN Applicant locates the Kirk keys locks, describes inserting and turning the keys and describes the shafts retracting, THEN: Cue: Keys are inserted and turned; shafts are retracted.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 18 Examiner NOTE:

Performance Step:

21 Step E.6.2.

PLACE NN15 MANUAL TRANSFER SWITCH in AC OUTPUT TO NN011 position.

o MANUAL TRANSFER SWITCH

- AC OUTPUT TO INVERTER NN011 Standard: Placed NN15 manual transfer switch to NN01 position.

Cue: WHEN Applicant describes turning the transfer switch to the left, THEN: Cue: Switch is positioned to the left with the arrow pointing left. AC output to inverter NN011 amber light lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

22 Step E.6.3.

LOCK NN15 Kirk Key locks AND REMOVE the keys.

1. KIRK KEY LOCKS

- LOCKED 2. KEYS - REMOVED Standard: Locked Kirk Keys and removed keys.

Cue: WHEN Applicant describes turning the keys and describes the shafts extending and removing the keys, THEN: Cue: Keys are removed and shafts are extended.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 14 of 18 Examiner NOTE:

Performance Step:

23 Step E.6.4.

Inform Control Room that NN01 will be energized or transferred to NN15 on the bypass transformer, as applicable.

Standard: Contacted control room.

Cue: WHEN contacted THEN: Cue: Acknowledge report.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

24 Step E.6.5 At NN11, perform the following:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 15 of 18 Examiner NOTE:

Performance Step:

25 Step E.6.5.1.

PLACE NN11 MANUAL TRANSFER SWITCH in SWING INVERTER TO LOAD POSITION.

o MANUAL TRANSFER SWITCH

- SWING INVERTER TO LOAD Standard: Placed manual transfer switch to swing inverter to load position. Cue: WHEN Applicant locates NN11 manual transfer switch and describes selecting swing inverter to load position, THEN: Cue: Switch is positioned to the right with the arrow pointing to Swing Inverter To Load amber light lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

26 Step E.6.5.2 IF NN01 was energized from NN11 bypass transformer, THEN perform the following:

a. Place MAINTENANCE BYPASS SWITCH in NORMAL o MAINTENANCE BYPASS SWITCH

- NORMAL b. OPEN NN11 B701, AC INPUT TO BYPASS CVT breaker.

o NN11 B701

- OFF Standard: Recognized from initial conditions that NN01 was NOT energized from NN11 bypass transformer.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 16 of 18 Examiner NOTE:

Performance Step:

27 Step E.6.6.

Inform Control Room that NN01 is energized from NN15 on the bypass transformer via the static switch.

Standard: Reported NN01 energized from NN15 on the bypass transformer via the static switch.

Cue: WHEN contacted THEN: Cue: Acknowledge report.

Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once NN11 MANUAL TRANSFER SWITCH is in SWING INVERTER TO LOAD POSITION

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 17 of 18 Verification of Completion Job Performance Measure No.

P3 NN01 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

The crew is responding to a loss of NN01, which was powered from inverter NN11 prior to the bus loss. NN11 bypass transformer did NOT energize NN01. Initiating Cue:

The CRS has dispatched you to perform Attachment E, beginning with step E.4.3.3, to energize bus NN01 from NN15.

Inform the Control Room when NN01 is energized NN15 on the bypass transformer via the static switch.

The NN15 manual transfer switch Kirk Keys and NK79 transfer switch key are in your possession.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 18 Facility: WCGS Task No: APE057007 Task Title:

Energize Bus NN02 from NN16.

Job Performance Measure No:

P3-B Rev 0 K/A

Reference:

APE 057 AA1.01, Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual inverter swapping.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance X Actual Performance Classroom Simulator Plant X Read to the examinee:

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

Initial Conditions:

The crew is responding to a loss of NN02, which was powered from inverter NN12 prior to the bus loss. NN12 bypass transformer did NOT energize NN02 Task Standard:

At the completion of the JPM, the Applicant will have energized bus NN02 from NN16 on the bypass transformer via the static switch.

Required Materials:

PPE appropriate for turbine building watchstander. OFN NN

-021, Rev 25.

General

References:

OFN NN-021, Rev 25.

Initiating Cue:

The CRS has dispatched you to perform Attachment G, beginning with step G.4.3.3, to energize bus NN02 from NN16.

Inform Control Room when NN02 is energized from NN16 on the bypass transformer via the static switch.

The NN16 manual transfer switch Kirk Keys and NK80 transfer switch key are in your possession.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

20 Minutes Appendix C 2 Form ES-C-1 Page 2 of 18 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step G.4.3.3.

IF indicator light NN16 ALIGNED TO NK02 is NOT LIT, THEN ALIGN NN16 to NK02 as follows:

a. PLACE NK HS

-16, NK02/NK04 TRANSFER SWITCH CONTROL HANDSWITCH in NK02 position.

o NK HS NK02 Standard: Located NK80.

Recognized indicator light NN16 ALIGNED TO NK02 is NOT LIT. Placed NK HS

-16 to NK02 position.

Cue: WHEN Applicant locates NN16 aligned to NK02 light, THEN: Cue: Light NOT lit.

WHEN Applicant describes inserting the key into NK HS

-16 and selecting NK02 position, THEN: Cue: Key is inserted. Key is turned in the NK02 direction.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 18 Examiner NOTE:

Performance Step:

2 Step G.4.3.4.

VERIFY indicator light NN16 ALIGNED TO NK02 is lit. Standard: Verified indicator light NN16 aligned to NK02 lit.

Cue: WHEN Applicant locates light indicator, THEN: Cue: NN16 aligned to NK02 light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

3 Step G.4.3.5.

VERIFY SWING INV NN16 white pilot light is lit.

Standard: Located NN16.

Verified NN16 white pilot light lit.

Cue: WHEN Applicant locates pilot light, THEN: Cue: White pilot light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 18 Examiner NOTE:

Performance Step:

4 Step G.4.4.

STARTUP NN16 swing inverter as follows:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

5 Step G.4.4.1.

TEST NN16 lamps by depressing the PRESS TO TEST LIGHTS button while inspecting lamps.

a. PRESS TO TEST LIGHTS

- DEPRESSED b. LAMPS - ALL LIT Standard: Tested NN16 lamps.

Cue: WHEN Applicant locates press to test lights button and describes depressing button and inspecting lamps, THEN: Cue: Lamps all lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 18 Examiner NOTE:

Performance Step:

6 Step G.4.4.2.

CLOSE NN16 B1, DC INPUT BREAKER as follows:

a. DEPRESS and HOLD the PRECHARGE pushbutton.

o PRECHARGE BUTTON

- DEPRESSED and HELD

b. WHEN PRECHARGE light is lit, THEN CLOSE B1 breaker.

1) PRECHARGE LIGHT

- LIT 2) B1 - ON c. WHEN DC INPUT BREAKER CLOSED light is lit, THEN RELEASE PRECHARGE pushbutton.

1) DC INPUT BREAKER CLOSED

- LIT 2) PRECHARGE PUSHBUTTON

- RELEASED Standard: Depressed and held precharge pushbutton.

Placed NN16 B1 to on when precharge light lit.

Released precharge pushbutton when DC input breaker closed light lit.

Cue: WHEN Applicant locates and describes depressing and holding precharge button, THEN: Cue: Precharge button depressed and held. Precharge light lit.

WHEN Applicant locates and describes placing NN16 B1 to ON, THEN: Cue: Switch is in UP position. DC input breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 18 Examiner NOTE:

Performance Step:

7 Step G.4.4.3.

RECORD DC INPUT VOLTS from NNEI0161.

o NNEI0161 volts __________VDC Standard: Recorded DC input voltage.

Cue: When applicant locates NNEI0161 then CUE: Point to the 125 VAC value.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

8 Step G.4.4.4.

CLOSE NN16 B701, AC INPUT TO BYPASS CVT breaker.

o B701 - ON Standard: Placed NN16 B701 to ON.

Cue: WHEN Applicant locates and describes placing NN16 B701 to ON, THEN: Cue: Switch is in UP position. AC input to bypass CVT breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 18 Examiner NOTE:

Performance Step:

9 Step G.4.4.5.

CLOSE NN16 B4, BYPASS INPUT TO STATIC SWITCH breaker. o B4 - ON Standard: Placed NN16 B4 to ON.

Cue: WHEN Applicant locates and describes placing NN16 B4 to ON, THEN: Cue: Switch is in UP position. Bypass input to static switch breaker RED light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 Step G.4.4.6.

CLOSE NN16 B2, INVERTER OUTPUT breaker.

o B2 - ON Standard: Placed NN16 B2 to ON.

Cue: WHEN Applicant locates and describes placing NN16 B2 to ON, THEN: Cue: Switch is in UP position. Inverter output breaker RED light is lit. Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 18 Examiner NOTE:

Performance Step:

11 Step G.4.4.7.

RESET inverter alarms by pressing the ALARM RESET pushbutton.

o ALARM RESET

- PRESSED Standard: Reset alarms.

Cue: WHEN Applicant locates and describes depressing alarm reset, THEN: Cue: Alarm reset depressed.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

12 Step G.4.4.8.

VERIFY the following alarms clear.

o OVER TEMPERATURE

- CLEAR o DC LOW VOLTAGE

- CLEAR o DC HIGH VOLTAGE

- CLEAR o OUT OF SYNC

- CLEAR o INVERTER OUTPUT LOW VOLTAGE

- CLEAR o FUSE BLOWN

- CLEAR Standard: Verified alarms clear.

Cue: WHEN Applicant locates and inspects alarms, THEN: Cue: Alarm lights NOT lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 18 Examiner NOTE:

Performance Step:

13 Step G.4.4.9.

WHEN NNEI0162 indicates between 112.1 VAC to 123.9 VAC, THEN continue. Standard: Recognized NNEI0162 indicated between 112.1 VAC to 123.9 VAC. Cue: WHEN Applicant locates NNEI0162, THEN: Cue: Point to the 120 VAC value.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

14 Step G.5. At NN16, ensure NN16 static switch in bypass source supplying load position as follows:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 18 Examiner NOTE:

Performance Step:

15 Step G.5.1.

IF BYPASS SOURCE SUPPLYING LOAD light is NOT lit, THEN perform the following:

Standard: Recognized bypass source supplying load light is NOT lit. Cue: WHEN Applicant locates bypass source supplying load light, THEN: Cue: Light NOT lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

16 Step G.5.1.1 VERIFY NN16 IN SYNC light is lit.

Standard: Verified NN16 in sync light lit.

Cue: WHEN Applicant locates in sync light, THEN: Cue: Light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 18 Examiner NOTE:

Performance Step:

17 Step G.5.1.2.

DEPRESS NN16 BYPASS SOURCE TO LOAD pushbutton.

o BYPASS SOURCE TO LOAD

- DEPRESSED Standard: Depressed NN16 bypass source to load pushbutton.

Cue: WHEN Applicant locates and describes depressing bypass source to load pushbutton, THEN: Cue: Pushbutton depressed.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

18 Step G.5.1.3 Verify BYPASS SOURCE SUPPLYING LOAD

- LIT Standard: Verified bypass source supplying load light lit.

Cue: WHEN Applicant locates bypass source supplying load light, THEN: Cue: Light is lit.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 18 Examiner NOTE: Performance Step:

19 Step G.6. PERFORM the following to energize NN02 or transfer load from NN12 to NN16, as applicable:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

20 Step G.6.1.

At NN16, UNLOCK BOTH Kirk Key locks.

o KIRK KEY LOCKS

- UNLOCKED Standard: Unlocked both Kirk Key locks.

Cue: WHEN Applicant locates the Kirk keys locks, describes inserting and turning the keys and describes the shafts retracting, THEN: Cue: Keys are inserted and turned; shafts are retracted Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 18 Examiner NOTE:

Performance Step:

21 Step G.6.2.

PLACE NN16 MANUAL TRANSFER SWITCH in AC OUTPUT TO NN012 position.

o MANUAL TRANSFER SWITCH

- AC OUTPUT TO INVERTER NN012 Standard: Placed NN16 manual transfer switch to NN012 position.

Cue: WHEN Applicant describes turning the transfer switch to the left, THEN: Cue: Switch is positioned to the left with the arrow pointing left. AC output to inverter NN012 amber light lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

22 Step G.6.3.

LOCK NN16 Kirk Key locks AND REMOVE the keys.

1. KIRK KEY LOCKS

- LOCKED 2. KEYS - REMOVED Standard: Locked Kirk Keys and removed keys.

Cue: WHEN Applicant describes turning the keys and describes the shafts extending and removing the keys, THEN: Cue: Keys are removed and shafts are extended.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 14 of 18 Examiner NOTE:

Performance Step:

23 Step G.6.4.

Inform Control Room that NN02 will be energized or transferred to NN16 on the bypass transformer, as applicable.

Standard: Contacted control room.

Cue: WHEN contacted THEN: Cue: Acknowledge report.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

24 Step G.6.5 At NN12, perform the following:

Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 15 of 18 Examiner NOTE:

Performance Step:

25 Step G.6.5.1.

PLACE NN12 MANUAL TRANSFER SWITCH in SWING INVERTER TO LOAD POSITION.

o MANUAL TRANSFER SWITCH

- SWING INVERTER TO LOAD Standard: Placed manual transfer switch to swing inverter to load position. Cue: WHEN Applicant locates NN12 manual transfer switch and describes selecting swing inverter to load position, THEN: Cue: Switch is positioned to the right with the arrow pointing to Swing Inverter To Load amber light lit.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

26 Step G.6.5.2 IF NN02 was energized from NN12 bypass transformer, THEN perform the following:

a. Place MAINTENANCE BYPASS SWITCH in NORMAL o MAINTENANCE BYPASS SWITCH

- NORMAL b. OPEN NN12 B701, AC INPUT TO BYPASS CVT breaker.

o NN12 B701

- OFF Standard: Recognized from initial conditions that NN02 was NOT energized from NN12 bypass transformer.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 16 of 18 Examiner NOTE:

Performance Step:

27 Step G.6.6.

Inform Control Room that NN02 is energized from NN16 on the bypass transformer via the static switch.

Standard: Reported NN02 energized from NN16.

Cue: WHEN contacted THEN: Cue: Acknowledge report.

Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once NN1 2 MANUAL TRANSFER SWITCH is in SWING INVERTER TO LOAD POSITION.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 17 of 18 Verification of Completion Job Performance Measure No.

P3-B Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Read to the examinee:

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

Initial Conditions:

The crew is responding to a loss of NN02, which was powered from inverter NN12 prior to the bus loss. NN12 bypass transformer did NOT energize NN02 Initiating Cue:

The CRS has dispatched you to perform Attachment G, beginning with step G.4.3.3, to energize bus NN02 from NN16. Inform Control Room when NN02 is energized from NN16 on the bypass transformer via the static switch.

The NN16 manual transfer switch Kirk Keys and NK80 transfer switch key are in your possession.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 15 Facility: WCGS Task No: 400011 Task Title:

Transfer From the NCP to a CCP. Job Performance Measure No:

S1 (AP) Rev 0 K/A

Reference:

004 A2.22, Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Mismatch of letdown and changing flows.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. The Plant is in MODE 1 with the Service loop on "B" Train.

Task Standard:

Upon completion of this JPM, the Applicant will re-establish charging from the NCP when CCP 'B' trips as BG FK-462 is lowered to < 40% output.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 15 Required Materials:

SYS BG-201, Rev 65 and ALR 00-042E, Rev 13 Simulator Setup:

IC 30 (or equivalent with yellow train CCW in service and CCP 'B' in standby) ENSURE NPIS trend for CCP 'B' is displayed.

SCN File: S1 (ASP).scn

S1 (ASP) ;CCP 'B' trips when BG FK

-462 is < 40%

{x01d124m<.4} ICM bkrNB00201 t:1

end file BOOTH: ENSURE NPIS trend for CCP B is closed before resetting into another JPM.

General References

SYS BG-201, Rev 65, ALR 00

-042E, Rev 13 Initiating Cue:

The Control Room Supervisor directs you to start the 'B' CCP and secure the NCP, per 6.2 of SYS BG

-201, to support maintenance on the NCP next shift. Prerequisites of SYS BG

-201 are complete. CCP "B" boron concentration is 20 ppm greater than RCS boron concentration

. Time Critical Task:

NO Alternate Path:

YES Validation Time:

20 Minutes Appendix C 2 Form ES-C-1 Page 3 of 15 Performance Information Denote critical steps with a check mark

() START TIME:

Examiner NOTE:

Performance Step:

1 STEP 6.2.1 IF the Boron Thermal Regeneration System is in service, THEN SHUTDOWN the BTRS in accordance with SYS BG

-205, BORON THERMAL REGENERATION SYSTEM OPERATION.

Standard: Recognized that BTRS is NOT in service and N/Ad step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 STEP 6.2.2 PLACE BG HIS

-129, CVCS DEMIN INLET DIVERT VLV to VCT. o BG HIS-129 - VCT Standard: Depressed the "VCT" pushbutton BG HIS-129 to lock it down.

VCT red light is lit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 15 Examiner NOTE:

This is a continuous action step (Maintain) and the Applicant may make adjustments throughout the JPM. Performance Step:

3 Step 6.2.3 MAINTAIN RCP Seal Injection flow between 8 and 13 gpm, by adjusting BG HC

-182, CHG HDR BACK PRESS CTRL:

o BG FR-157 - BETWEEN 8 AND 13 GPM o BG FR-156 - BETWEEN 8 AND 13 GPM o BG FR-155 - BETWEEN 8 AND 13 GPM o BG FR-154 - BETWEEN 8 AND 13 GPM Standard: Adjusted (if required) BG HC-182 to maintain seal injection 8

-13 gpm per pump.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 6.2.4 ENSURE BG FK

-121, CCP DISCH FLOW CTRL is in manual and set at 20%.

o BG FK-121 - IN MANUAL AND SET AT 20%

Standard: Verified BG FK

-121 set to MANUAL with 20% output.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 15 Examiner NOTE:

Performance Step:

5 STEP 6.2.5 ENSURE BG HV

-8111, CCP B RECIRC VLV is open, using BG HIS-8111, CCP B RECIRC VLV.

o BG HIS-8111 - OPEN Standard: Verified BG HIS-8111 Red light is lit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

6 STEP 6.2.6 ENSURE Component Cooling Water is being supplied to CCP B. Standard: EG HIS-22 and EG HIS

-24 Verified CCW pump B running by the Red light lit on the handswitch.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 15 Examiner NOTE:

Performance Step:

7 STEP 6.2.7 IF RCS temperature is greater than or equal to 200°F, THEN ENSURE BG-8483A, CCP A DISCH HDR FCV

-121 INLET ISO is locked closed.

o BG-8483A - LOCKED CLOSED Standard: Recognized blue placard indicates valve is locked closed OR Contacted the Aux Watch to verify BG-8483A is locked closed.

OR Asked CRS to check Locked Component Log.

Cue: IF contacted, THEN: Cue: (Building Watch) BG

-8483A is locked closed

. OR Cue: (CRS) Locked Component Log indicates BG

-8483A is locked closed

. Score: SAT or UNSAT SAT or UNSAT Comment: If an IV is requested reply: Another RO will perform IV.

Examiner NOTE:

Performance Step:

8 STEP 6.2.8 ENSURE CCP Discharge BG FCV

-121 isolated placard is attached to BG HIS

-1A handswitch.

Standard: Located placard on BG HIS

-1A handswitch.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 15 Examiner NOTE:

Performance Step:

9 STEP 6.2.9 ENSURE BG-8483C, CCP B DISCH HDR FCV

-121 INLET ISO is unlocked and open.

o BG-8483C - UNLOCKED/OPEN Standard: Recognized blue placard indicates valve is locked closed OR Contacted the Aux Watch to verify BG

-V8483C is unlocked open. OR Asked CRS to check Locked Component Log.

Cue: IF contacted, THEN: Cue: (Building Watch)

BG-8483C is unlocked open.

OR Cue: (CRS) Locked Component Log indicates BG

-8483C is unlocked open.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 STEP 6.2.10 ENSURE BG HIS

-2AX, CCP B AUX L-O PUMP is in auto.

o BG HIS-2AX - AUTO Standard: Verified BG HIS-2AX switch in AUTO and the Red light lit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 15 Examiner NOTE:

Performance Step:

11 STEP 6.2.11 Prior to starting CCP B, START and MONITOR a NPIS computer trend, (including the following points, and any other available and desired points that monitor pump operation) to ensure proper pump operation and system response: (3.1.4.3) o BGI0017 CHG PUMP B AMP o BGP0120 CHG HDR PRESS o BGF0121 CHG HDR FLOW Standard: Verified NPIS trend and data points available.

Cue: If asked to monitor NPIS cue: BOP will monitor NPIS Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

IF Applicant does not ask for direction, THEN provide Cue.

Performance Step:

12 6.2.12 IF desired, THEN RAISE Charging and Letdown flow, as follows: Standard: Asked CRS for direction.

Cue: Cue: Leave charging and letdown flow as is. Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 15 Examiner NOTE:

This is a reactivity step and Operator should indicate the need for a peer check (Management Expectation

- but not critical).

Performance Step:

13 STEP 6.2.13 -2A, CCP B.

o BG HIS-2A - NORMAL-AFTER-RUN Standard: Started the pump by turning the switch BG HIS-2A to RUN. Verified the Red light comes on and the Green light goes out.

Cue: Cue (If asked):

Acknowledge pump start.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

14 STEP 6.2.14 IF BG FK-462, NORMAL CHG PMP FLOW CTRL is in auto, THEN PLACE it in manual.

o BG FK-462 - MANUAL Standard: Placed BG FK

-462 in MANUAL verified red Manual light is lit Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 15 Examiner NOTE:

Per AP 21-001, Conduct Of Operations, Two handed control board operations may be performed with CRS permission. Two handed operation is the act of manipulating two controllers simultaneously.

Performance Step:

15 STEP 6.2.15 PERFORM the following simultaneously:

o LOWER BG FK

-462, NORMAL CHG PMP FLOW CTRL to 20% output.

o BG FK-462 - LOWERED TO 20%

o ADJUST BG FK-121, CCP DISCH FLOW CTRL, to maintain constant Charging header flow.

o BG FK-121 - ADJUSTED Standard: Requested two handed operation.

Used BG FK

-462 and BG FK

-121 and performed these actions in such a way to maintain a constant charging flow.

Cue: Cue (If asked): Acknowledge and give Permission for simultaneous board action.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 15 Examiner NOTE:

ALTERNATE SUCCESS PATH.

WHEN BG FK-462 controller output is < 40%, THEN CCP 'B' will trip.

Steps 1-3 of ALR 00 042E are Memory Action steps and the Applicant may perform them before receiving the ALR.

Performance Step:

16 Annunciator 00

-042E alarming.

Standard: Announce d Annunciator 42E and that CCP 'B' has tripped.

Cue: WHEN CCP 'B' trips AND ANN 42E is in alarm, THEN: Cue: Annunciator 42E is in alarm.

(only if applicant does not acknowledge)

WHEN applicant reports the CCP has tripped, THEN: Cue: Acknowledge report. Provide examinee with copy of ALR 00-042E and state "Perform the ALR."

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Steps 1 through 3 are Memory Action steps and can be performed without the procedure, but are NOT required to be done without the procedure.

Performance Step:

17 ALR 00-042E, STEP 1 Check Previously Running Pumps

- TRIPPED o BG HIS-1A for CCP A o BG HIS-2A For CCP B o BG HIS-3 for NCP Standard: Recognized that CCP 'B' has tripped.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 15 Examiner NOTE:

This step is a Memory Action step and can be performed without the procedure, but is NOT required to be done without the procedure.

Performance Step:

18 ALR 00-042E, STEP 2 Check Charging Pumps

- NONE RUNNING o BG HIS-1A for CCP A o BG HIS-2A For CCP B o BG HIS-3 For NCP Standard: Recognized that the NCP is still running by the Red light lit on BG HIS-3 and/or flow indicated on BG FI

-121A Performed RNO.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

This step is a Memory Action step and can be performed without the procedure, but is NOT required to be done without the procedure.

Performance Step:

19 ALR 00-042E, STEP 2 RNO a Perform the Following:

a. Adjust charging and letdown flow, as necessary, to maintain PZR level at program.

Standard: Adjusted BG FK

-462 as necessary to stabilize PZR level.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 15 Examiner NOTE:

Performance Step:

20 ALR 00-042E, STEP 2 RNO b Return to procedure and step in effect.

Standard: ALR 00-042E completed.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the Applicant has control of BG FK

-462 and is stabilizing PZR level

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 14 of 15 Verification of Completion Job Performance Measure No.

S1 (AP) Examinee's Name:

Examiner's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. The Plant is in MODE 1 with the Service loop on "B" Train.

Initiating Cue:

The Control Room Supervisor directs you to start the 'B' CCP and secure the NCP, per 6.2 of SYS BG

-201, to support maintenance on the NCP next shift. Prerequisites of SYS BG

-201 are complete. CCP "B" boron concentration is 20 ppm greater than RCS boron concentration

.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 12 Facility: WCGS Task No: APE026001 Task Title:

Respond to the loss of CCW flow to the Service Loop.

Job Performance Measure No:

S2 (AP) Rev 0 K/A

Reference:

APE 026 AK3.03, Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: Guidance actions contained in EOP for Loss of CCW.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. The Plant is stable in MODE 1. The 'B' CCW pump has tripped. 'D' CCW pump is tagged out.

Task Standard:

At the completion of the JPM, the Applicant will have tripped the reactor , tripped the RCPs, isolated letdown and reduced charging to the seals only.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 12 Required Materials:

OFN EG-004, Rev 18.

Simulator Setup:

IC 302 (IC 30 with malfunctions included)

Hang Test/Caution tag on EG HIS

-24 (D - CCW pump) SCN File S2 (ASP).scn (Included in IC)

S2 (ASP) ; Tagout 'D' CCW pump ICR bkrDPEG01D t: 2 d:0

EG HV-15 & 53 failed closed ICM movEGHV0015 t: 2 d:0 ICM movEGHV0053 t:2 d:0

'B' CCW pump tripped ICM bkrDPEG01B t: 1

End File General

References:

OFN EG-004, Rev 18.

Initiating Cue:

The Control Room Supervisor directs you to respond using OFN EG-004, CCW SYSTEM MALFUNCTIONS.

Time Critical Task:

NO Alternate Path:

YES Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 3 of 12 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 OFN EG-004 , Step 1. Check CCW Pumps

- ONE RUNNING IN EACH INTACT TRAIN Standard: Proceeded to RNO step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Per AP 21-001, Conduct Of Operations, an announcement is made when starting the pump.

Performance Step:

2 Step 1.a. RNO Start CCW Pump(s), as necessary, to establish one running in each intact train.

Standard: Started 'A' or 'C' CCW pump using handswitch e s EG HIS-21 or 23 Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 12 Examiner NOTE:

Performance Step:

3 Step 1.b. RNO IF a CCW Pump in the train aligned to the service loop can NOT be started AND alternate CCW train pump is operating, THEN shift service loop to alternate CCW train:

1) Open service loop CCW supply and return valves for train not supplying service loop.

EG ZL-15 And EG ZL

-53For Train A o EG HS-15

EG ZL-16 And EG ZL

-54 For Train B o EG HS-16 2) Close service loop CCW supply and return valves for train previously supplying service loop.

EG ZL-15 And EG ZL

-53 For Train A o EG HS-15

EG ZL-16 And EG ZL

-54 For Train B o EG HS-16 Standard: Attempted to open service loop supply and return valves and reported that EG HV

-15 and EG HV

-53 will NOT open Cue: If asked as the CRS cue: Continue with procedure Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 12 Examiner NOTE:

The Applicant may proceed directly to step 2 without performing RNO step 1.c.

Performance Step:

4 Step 1.c. RNO Ensure CCW aligned to the following:

o RCP Thermal Barriers o RHR, if required o Spent Fuel Pool Cooling Standard: Recognized this step CANNOT be done.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

ALTERNATE SUCCESS PATH Performance Step:

5 Step 2. Check Service Loop

- ALIGNED TO RUNNING CCW PUMP Standard: Recognized service loop CANNOT be aligned.

Proceeded to RNO step. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 12 Examiner NOTE:

Per AP 21-001, Conduct Of Operations, an announcement is made when tripping the reactor.

Performance Step:

6 Step 2.a. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Trip reactor.

Standard: Tripped the reactor.

Cue: Cue: Acknowledge reactor trip.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

The Applicant continues with the procedure. Immediate actions are performed by the rest of the crew.

Performance Step:

7 Step 2.b. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Stabilize the plant, using EMGs while continuing with this procedure.

Standard: Recognized that EMG E

-0 is entered.

Cue: Cue: Continue with the OFN while the crew responds to the reactor trip.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 12 Examiner NOTE:

Performance Step:

8 Step 2.c. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Trip RCPs.

Standard: Tripped all four RCPs.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Isolating excess letdown is NOT critical as it is NOT in service. The letdown orifice isolation valves must be closed in order to close BG HV

-459 and BG HV

-460. Performance Step:

9 Step 2.d. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Isolate letdown and excess letdown.

Standard: Closed letdown orifice isolation valves.

Closed BG HV

-459 and BG HV

-460. Recognized that excess letdown is NOT in service.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 12 Examiner NOTE:

Performance Step:

10 Step 2.e. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Isolate seal return flow.

BG HIS-8100

BG HIS-8112 Standard: Closed BG HV

-8100 and BG HV

-8112. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

BG HV-8109 is expected to open when charging flow is reduced to minimum.

Performance Step:

11 Step 2.f RNO IF no CCW Pump can supply service loop, THEN perform the following:

Reduce charging to minimum and charge only to the seals.

Standard: Adjusted BG FK

-462 to obtain charging flow to the seals only. Ensured 8 gpm minimum seal injection flow to each RCP.

Closed BG HC

-182. Cue: WHEN Applicant requests two handed operation for adjusting charging, THEN: Cue: Two handed operation is allowed.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 12 Examiner NOTE:

Performance Step:

12 Step 2.g. RNO IF no CCW Pump can supply service loop, THEN perform the following:

Ensure charging supplied by the NCP or from CCP on the intact CCW Train.

Standard: Recognized that the NCP is supplying charging.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

13 Step 2.h. RNO IF no CCW Pump can supply service loop, THEN perform the following:

IF unable to supply CCW cooling to a safety train, THEN supply cooling to one train of CCP and SI Pump, using ATTACHMENT A, ALTERNATE COOLING FOR CCP AND SI PUMPS.

Standard: Recognized that 'A' train CCW is supplying cooling to 'A' train safety components, so step is NA.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 12 Examiner NOTE:

Performance Step:

14 Step 2.i. RNO Return to procedure and step in effect.

Standard: Returned to EMG E

-0. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the reactor is tripped, the RCPs are tripped, letdown is isolated, seal return flow is isolated and charging is reduced to minimum flow to the RCP seals.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 11 of 12 Verification of Completion Job Performance Measure No.

S2 (AP) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. The Plant is stable in MODE 1. The 'B' CCW pump has tripped. 'D' CCW pump is tagged out.

Initiating Cue:

The Control Room Supervisor directs you to respond using OFN EG

-004, CCW SYSTEM MALFUNCTIONS.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 12 Facility: WCGS Task No: E02001 Task Title:

Isolation of BIT IAW EMG ES

-03. Job Performance Measure No:

S3 Rev 0 K/A

Reference:

E02 EA1.1 Ability to operate and / or monitor the following as they apply to the (SI Termination): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. The crew has mitigated a fault on 'A' S/G and has entered EMG ES

-03, SI TERMINATION.

Task Standard:

At the end of the JPM, the Applicant will have aligned the CCPs for normal charging and isolated the BIT, restoring partial control of RCS pressure by reducing ECCS flow.

Required Materials:

EMG ES-03, SI TERMINATION, Rev 24.

Simulator Setup:

IC 301 (or equivalent; IC contains all malfunction, etc.)

SCN File S3.scn

S3 ; Steamline break on S/G 'A' IMF mAB03A f: 3.2e+006 r:60

Open BG-8483A For CCP A IRF rBG35A f: 100 r:30 k:1

Close BG

-8483C IRF rBG35C f:0 r:30 k:2

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 12 General

References:

EMG ES-03, SI TERMINATION, Rev 24.

Initiating Cue:

The CRS directs you to reduce ECCS flow IAW EMG ES

-03, SI TERMINATION, beginning at step 1.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 12 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step 1. Reset SI. o SB HS-42A o SB HS-43A Standard: Depressed both reset buttons.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Only the reset s of the containment isolation Phase A are critical. Performance Step:

2 Step 2. Reset Containment Isolation Phase A And Phase B:

o SB HS-56 For Phase A o SB HS-53 For Phase A o SB HS-55 For Phase B o SB HS-52 For Phase B Standard: Depressed CISA and CISB reset buttons.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 12 Examiner NOTE:

Performance Step:

3 Step 3. Verify Instrument Air Compressor Is Running:

Standard: Recognized Instrument Air Compressors already aligned.

Verified alignment.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE: Depending on how long the PORV has been cycling BB PK-455A may still be saturated and have an output less than 55%. Performance Step:

4 Step 4. Verify Instrument Air To Containment:

a. Check PZR PRESS MASTER CTRL Output

- LESS THAN 55% o BB PK-455A b. Open INST AIR SPLY CTMT ISO VLV.

o KA HIS-29 Standard: Ensured BB PK

-455A output less than 55%.

Opened KA HIS

-29. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 12 Examiner NOTE:

Only step 5.b. is critical. It is expected that the CCP with the blue placard attached is stopped.

Performance Step:

5 Step 5. Reduce Charging Flow:

a. Check Shutdown Sequencers

- NOT ACTUATED o Annunciator 00

-018C, NF039A S/D SEQ ACTUATED

- CLEAR o Annunciator 00

-021C, NF039B S/D SEQ ACTUATED

- CLEAR b. Stop all but one CCP and place in standby.

BG HIS-1A OR

BG HIS-2A Standard: Verified Shutdown Sequencers not actuated.

Stopped CCP with blue placard attached and left in normal after stop.

Cue: Cue (if asked):

Stop the CCP with the blue placard attached.

Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

6 Step 6. Check If NCP Should Be Stopped:

a. CCPs - ANY RUNNING

b. Stop NCP. o BG HIS-3 Standard: Recognized that the NCP was stopped previously.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 12 Examiner NOTE:

Pressure will be fluctuating as the PORV cycles.

Performance Step:

7 Step 7. Check RCS Pressure

- STABLE OR INCREASING Standard: Recognized RCS Pressure trend is stable for conditions.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

CCW is already aligned. Performance Step:

8 Step 8. Verify CCW To Service Loop:

Standard: Verified CCW alignment to Service Loop.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: CCW is currently aligned to service loop no actions are required Appendix C 2 Form ES-C-1 Page 7 of 12 Examiner NOTE:

CCW is already aligned.

Performance Step:

9 Step 9. Verify CCW To Containment:

Standard: Verified CCW alignment to Containment.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: CCW is currently aligned to containment no actions are required Examiner NOTE:

CCW is already aligned.

Performance Step:

10 Step 10. Verify RCP Thermal Barrier Cooling:

Standard: Verified RCP Thermal Barrier cooling.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: RCP thermal barrier cooling is aligned no actions are required

Appendix C 2 Form ES-C-1 Page 8 of 12 Examiner NOTE:

Performance Step:

11 Step 11. Align CCPs For Normal Charging:

a. Check CCPs

- AT LEAST ONE RUNNING

BG HIS-1A

BG HIS-2A b. Check CCP Discharge To Charging Header Isolation Valve For Running CCP

- OPEN

BG-8483A For CCP A (1974' AUX BLDG, CCP A ROOM)

BG-8483C For CCP B (1974' AUX BLDG, CCP B ROOM) c. Reset CCP Recirc Valves.

o BG HS-8110 o BG HS-811 1 d. Open CCP Recirc Valves.

o BG HIS-8110 o BG HIS-8111 Standard: Verified CCP running.

Verified CCP discharge isolation valve open by one of the following:

Contacted local operator, Asked CRS to check locked valve log, OR Absence of blue placard.

Depressed CCP recirc valve reset buttons.

Opened CCP recirc valves.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 12 Examiner NOTE:

One of the valves, BG HV

-8146 or 8147, will already be open and the other will be closed.

Performance Step:

12 Step 12. Align Charging System:

a. Throttle CCP Discharge Flow Control valve to 7% open.

o BG FK-121 b. Close Charging Header Back Pressure Control valve.

o BG HC-182 c. Open Charging Pumps To Regenerative Heat Exchanger Containment Isolation valves.

o BG HIS-8105 o BG HIS-8106 d. Align Regenerative Heat Exchanger To Loop Cold Leg valves, to establish only one open.

BG HIS-8146 For Loop 1

BG HIS-8147 For Loop 4 Standard: Throttled BG FK

-121 to ~ 7% open.

Closed BG HC-182. Opened BG HIS

-8105 and 8106.

Verified BG HIS

-8146 or 8147 open.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 12 Examiner NOTE:

Closing either the BIT Inlet valves OR the BIT Outlet valves , meets the critical task.

Performance Step:

13 Step 13. Isolate BIT:

a. Close BIT Inlet Valves.

o EM HIS-8803A o EM HIS-8803B b. Close BIT Outlet Valves.

o EM HIS-8801A o EM HIS-8801B Standard: Closed BIT Inlet and Outlet valves.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the BIT Inlet and Outlet valves are closed.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 11 of 12 Verification of Completion Job Performance Measure No.

S3 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. The crew has mitigated a fault on 'A' S/G and has entered EMG ES

-03, SI TERMINATION.

Initiating Cue:

The CRS directs you to reduce ECCS flow IAW EMG ES

-03, SI TERMINATION, beginning at step 1.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 10 Facility: WCGS Task No: 4100003 Task Title:

Respond to failed open steam dumps. Job Performance Measure No:

S4 (AP) Rev 0 K/A

Reference:

041 A4.08, Ability to manually operate and/or monitor in the control room: Steam dump valves.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator; GEN 00

-002 is in progress and step 6.21.3.3 has been completed. An extra Reactor Operator is monitoring SG levels. Task Standard:

At the completion of the JPM, the Applicant will have mitigated the effects of the failure of AB PT

-507 on the steam dump system AND placed ARVs in auto with 1125 psig setpoint

. Required Materials:

SYS AB-120, Rev 32.

General

References:

SYS AB-120, Rev 32. AP 21

-001, Rev 72.

Initiating Cue:

The CRS directs you to align the Steam Dumps and ARVs for automatic operation as required by step 6.21.3.4 of GEN 00

-002 using SYS AB

-120 step 6.2. Time Critical Task:

NO Alternate Path:

YES Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 2 of 10 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step 6.2. Align Steam Dump System For Operation Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step 6.2.1.

Set STEAM HDR PRESS CTRL potentiometer at 7.28 (1092 psig). o AB PK-507 - SET AT 7.28 Standard: Adjusted the potentiometer clockwise until it indicated 7.28 turns. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 10 Examiner NOTE:

Performance Step:

3 Step 6.2.2.

Place STEAM DUMP SEL switch to steam pressure.

o AB US-500Z - STEAM PRESSURE Standard: Located AB US

-500Z Verified the Steam Pressure position (right).

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 Step 6.2.3.

Place STEAM DUMP BYPASS INTERLOCK switches to BYP/INTLK and spring return on.

o AB HS SELECTED TO BYPASS INTERLOCK o AB HS SELECTED TO BYPASS INTERLOCK Standard: Located AB HS

-63 Actuated to the BYP/INTLK position (right) and allowed to spring return to ON.

Red flag. Located AB HS

-64 Actuated to the BYP/INTLK position (right) and allowed to spring return to ON.

Red flag. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 10 Examiner NOTE:

Performance Step:

5 Step 6.2.4.

Verify STEAM DUMP CTRL BYPASS light is lit.

o AB HL LIT Standard: Located AB HL

-81 Verified White light lit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

6 Step 6.2.5.

Place STEAM DUMP COOLDOWN CTRL in auto.

o AB UK AUTO Standard: Located AB UK

-33 Depressed the AUTO PB.

Verified steam dump cooldown valves closed.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 10 Examiner NOTE:

ALTERNATE SUCCESS PATH AB PI-507 fails high when AB PK

-507 taken to AUTO at this step and the cooldown dump valves will open.

Per AP 21-001, Conduct of Operations, In the event of a failure of a controller where manual control must be taken, the CRS shall immediately be made aware of the status after manual control is established.

Performance Step:

7 Step 6.2.6.

Place STEAM HDR PRESS CTRL in auto. o AB PK-507 - AUTO Standard: Located AB PK

-507 Determined the status of the system:

WHEN AB PK

-507 is placed in AUTO, THEN noted that steams dumps OPENED.

Depressed the MANUAL PB on AB PK

-507 to regain control.

Depressed the down arrow to close valves OR Turned either or both BYP/INTLK switches (AB HK

-63 and 64) to OFF. OR Depressed the MANUAL PB on AB UK

-33 to regain control. Manipulated joystick to left to CLOSE steam dump valves.

Monitored Steam Dump valve CLOSURE on AB ZI

-34, AB ZI-45 and AB ZI-41. Reported failure to CRS.

Cue: WHEN the failure is reported, THEN: Cue: Acknowledge failure (and actions).

Cue: The WC SRO will report the instrument failure.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 10 Examiner NOTE:

Performance Step:

8 Step 6.2.7.

Set SG STEAM DUMP TO ATMS CTRLS at 1125 psig.

o AB PIC-1A - SET AT 1125 PSIG o AB PIC-2A - SET AT 1125 PSIG o AB PIC-3A - SET AT 1125 PSIG o AB PIC-4A - SET AT 1125 PSIG Standard: Located ARV Manipulated thumbwheel upward direction until the pointer indicated 1125 psig.

AB PIC-1A - SET AT 1125 PSIG Located ARV Manipulated thumbwheel upward direction until the pointer indicated 1125 psig.

AB PIC-2A - SET AT 1125 PSIG.

Located ARV Manipulated thumbwheel upward direction until the pointer indicated 1125 psig.

AB PIC-3A - SET AT 1125 PSIG.

Located ARV Manipulated thumbwheel upward direction until the pointer indicated 1125 psig.

AB PIC-4A - SET AT 1125 PSIG.

Cue: IF Applicant requests peer check or verification, THEN: Cue: Acknowledge request.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 10 Examiner NOTE:

Performance Step:

9 Step 6.2.8.

Place SG STEAM DUMP TO ATMS CTRLS in auto.

o AB PIC-1A - AUTO o AB PIC-2A - AUTO o AB PIC-3A - AUTO o AB PIC-4A - AUTO Standard: Located ARV Placed AB PIC

-1A ARV controller in auto by depressing the AUTO PB. AUTO White light lit.

Located ARV Placed AB PIC

-2A ARV controller in auto by depressing the AUTO PB. AUTO White light lit.

Located ARV.

Placed AB PIC

-3A ARV controller in auto by depressing the AUTO PB. AUTO White light lit.

Located ARV Placed AB PIC

-4A ARV controller in auto by depressing the AUTO PB. AUTO White light lit.

Cue: IF Applicant requests peer check or verification, THEN: Cue: Acknowledge request.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 10 Examiner NOTE:

Performance Step:

10 Step 6.2.9.

Section 6.2, Align Steam Dump System For Operation, complete. Standard: Reported to the CRS that the step is not complete due to instrument failure.

Cue: WHEN the report is made, as CRS, THEN: Cue: The WC SRO will report the instrument failure.

Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once the steam dumps are closed following the malfunction AND ARVs are set at 1125 psig and in auto

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 9 of 10 Verification of Completion Job Performance Measure No.

S4 (AP) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator; GEN 00

-002 is in progress and step 6.21.3.3 has been completed. An extra Reactor Operator is monitoring SG levels. Initiating Cue:

The CRS directs you to align the Steam Dumps and ARVs for automatic operation as required by step 6.21.3.4 of GEN 00

-002 using SYS AB

-120 step 6.2.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 20 Facility: WCGS Task No: EPE055002 Task Title:

Restore power to NB02 using the SBO diesels.

Job Performance Measure No:

S5 (AP) Rev 0 K/A

Reference:

EPE 055 EA2.03, Ability to determine or interpret the following as they apply to a Station Blackout: Actions necessary to restore power.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. 'B' EDG OOS for governor replacement. Severe weather has caused a loss of offsite power. The reactor tripped. The crew entered EMG C

-0, LOSS OF ALL AC POWER. Power has been restored to the switchyard.

XNB01 transformer and NB01 bus has sustained damage and ar e unavailable.

Task Standard:

At the completion of the JPM, the Applicant will have placed safeguards equipment in PTL prior to energizing NB02 from the SBO diesels.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 20 Required Materials:

OFN N B-030, REV 33A. SYS KU

-122, REV 5

. Simulator Setup:

IC 304 (IC 30 with malfunctions etc.)

Place Test/Caution tag on KJ HS

-10 8A SCN File S5.scn

S5 (ASP)

Tagout 'A' EDG scn SimGroup

\TAGDGB ; XNB01 Fault 30 IMF mNB06A i:

-1 f:-1 ; Loss of offsite power 35 IMF mSY01 i:

-1 f:-1 ; NB01 fault 40 IMF mNB03 i:

-1 f:-1 ; Re store power to west bus from the Benton line 4 4 DMF mSY01 4 5 IRF rSY01 f:1

Breaker NB0209 fails to close 47 ICM bkrNB00209 t: 2

Shutdown 'A' EDG 48 scn SimGroup

\SHTDNDGA {Key[1]} scn SimGroup

\NF39B 8N28 OFF ; End File General

References:

OFN NB-030, Rev 33A. SYS KU-122, Rev 5

. Initiating Cue:

The CRS directs you to energize NB02 AC emergency bus from offsite power using OFN NB

-030, LOSS OF AC EMERGENCY BUS NB01 (NB02), beginning at step B14.

Inform the CRS when NB02 is re

-energized.

Time Critical Task: NO Alternate Path:

YES Validation Time:

15 Minutes Appendix C 2 Form ES-C-1 Page 3 of 20 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step B14. Check NB02 Bus Status: o Annunciator 00

-021A, NB02 BUS LOCKOUT

- CLEAR Standard: Recognized that annunciator 00

-021A is clear.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

NOTE: From the initial conditions, the 'B' EDG is OOS. Applicant may NOT contact the local operator for this step as it has no relev a nce at this time.

Performance Step:

2 Step B15. Check NB02 EDG Status:

o Annunciator 502

-07D, GENERATOR PROTECTIVE RELAY - CLEAR Standard: Contacted local watchstander for status.

Cue: WHEN contacted, THEN: Cue: Annunciator 502

-07D is clear.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 20 Examiner NOTE:

Performance Step:

3 Step B16. Check Emergency Diesel NE02

- RUNNING Standard: Recognize from initial conditions that 'B' EDG is OOS.

Proceeded to step B16 RNO.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 Step B16. RNO Perform the following:

a. IF SM/CRS directs that NB02 be energized from a source other than the diesel, THEN go to:

Step B19 for normal offsite power via XNB02

Step B21 for alternate offsite power via XNB01

Step B24 for SBO Diesel Generators Standard: Recognize from initial conditions that NB02 is to be energized from offsite power.

Recognized that the normal offsite power supply is the only one available.

Proceeded to step B19.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 20 Examiner NOTE:

Performance Step:

5 Step B19. Check Normal Offsite Power Supply

- AVAILABLE a. Check Annunciator 00

-022A, XNB02 XFMR LOCKOUT

- CLEAR b. Check ESF Transformer XNB02

- ENERGIZED BY OFFSITE POWER Standard: Recognized that annunciator 00

-022A is clear.

Recognized that XNB02 is energized from offsite power.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 20 Examiner NOTE:

ALTERNATE SUCCESS PATH Performance Step:

6 B20. Reenergize NB02 From Normal Offsite Power Supply:

a. Place NB02 Normal Supply Sync Transfer switch to ON position. o NB HS-8 b. Place 4.16 KV BUS NB02 SYNC

-SCOPE SEL to Main FDR BRKR position.

o NB HS-11 c. Check BUS NB02 VOLTAGE INCOMING SOURCE

- NORMAL o NB EI-29 d. Close NB02 Normal Supply Breaker NB0209.

o NB HIS-4 Standard: Placed NB HS

-8 to ON. Placed NB HS

-11 to Main FDR BRKR position.

Checked NB EI

-29 voltage NORMAL

. Recognized that NB HIS

-4 failed to close. Reported failure to CRS.

Cue: WHEN Applicant reports failure of NB HIS

-4, THEN: Cue: I will contact electrical maintenance. Continue efforts to restore power to NB02.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 20 Examiner NOTE:

Performance Step:

7 Step B20 Reenergize NB02 From Normal Offsite Power Supply:

e. Place NB02 Normal Supply Sync Transfer switch to OFF o NB HS-8 f. Place 4.16 KV Bus NB01 Sync

-Scope SEL to OFF.

o NB HS-11 g. Check NB02

- Energized g. RNO Go To step B21 Standard: Recognized NB02 is not energized

. Proceeded to step B21

. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

8 Step B 21 Check Alternate Offsite Power Supply

- Available a. Check plant in mode

- 5, 6, or defueled a.RNO Go to step B24 Standard: Proceeded to step B24.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 20 Examiner NOTE:

Performance Step:

9 B24. Reenergize NB02 From SBO Diesel Generators:

o Reenergize NB02 per SYS KU

-122, ENERGIZING NB02 FROM STAION BLACKOUT DIESEL GENERATORS Standard: Recognize that SYS KU

-122 will be used to reenergize NB02.

Located SYS KU

-122. Cue: WHEN Applicant locates SYS KU

-122, THEN provide copy of SYS KU-122. Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 SYS KU-122, Step 6.1 Energizing NB02 From SBO DGs Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 20 Examiner NOTE:

Panel NF039B is NOT available in the simulator.

After providing the cue, direct the booth operator to select Key 1. Performance Step:

11 Step 6.1.1 In NF039B, ROTATE power switch NF39B 8N28

-1, on bottom panel, to off.

o NF39B 8N28 OFF Standard: Ensured NF39B 8N28

-1 OFF. Cue: WHEN the Applicant starts to proceed behind the control room panels, THEN: Cue: I will contact the BOP to place switch in OFF.

WHEN booth operator action is completed, THEN: Cue: NF39B 8N28

-1 is OFF. Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

12 Step 6.1.2 ENSURE the following handswitches in pull

-to-lock: Standard: Proceeded with step.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 20 Examiner NOTE:

Pump will start when bus is reenergized if not placed in PTL. Performance Step:

13 Step 6.1.2 Component 1.

AL HIS-22A, MD AFP B.

o AL HIS-22A - PULL-TO-LOCK Standard: Placed AL HIS-22A in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Pump will start when bus is reenergized if not placed in PTL. Performance Step:

14 Step 6.1.2 Component 2.

BG HIS-2A, CCP B.

o BG HIS-2A - PULL-TO-LOCK Standard: Placed BG HIS

-2A in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 20 Examiner NOTE:

Performance Step:

15 Step 6.1.2 Component 3.

EN HIS-9, CTMT SPRAY PUMP B.

o EN HIS PULL-TO-LOCK Standard: Placed EN HIS

-9 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

16 Step 6.1.2 Component 4.

EJ HIS-2, RHR PUMP B.

o EJ HIS PULL-TO-LOCK Standard: Placed EJ HIS

-2 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 20 Examiner NOTE:

Performance Step:

17 Step 6.1.2 Component 5.

EM HIS-5, SI PUMP B.

o EM HIS PULL-TO-LOCK Standard: Placed EM HIS

-5 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

18 Step 6.1.2 Component 6.

EG HIS-22, CCW PUMP B.

o EG HIS PULL-TO-LOCK Standard: Placed EG HIS

-22 in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 20 Examiner NOTE:

Performance Step:

19 Step 6.1.2 Component 7.

EG HIS-24, CCW PUMP D.

o EG HIS PULL-TO-LOCK Standard: Placed EG HIS

-24 in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

20 Step 6.1.2 Component 8.

GN HIS-9, CTMT COOLER FAN B.

o GN HIS PULL-TO-LOCK Standard: Placed GN HIS

-9 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 14 of 20 Examiner NOTE:

Performance Step:

21 Step 6.1.2 Component 9.

GN HIS-17, CTMT COOLER FAN D.

o GN HIS PULL-TO-LOCK Standard: Placed GN HIS

-17 in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

22 Step 6.1.2 Component

10. GK HIS-40, CTRL RM A/C UNIT 4B FAN & DAMPER.

o GK HIS PULL-TO-LOCK Standard: Placed GK HIS

-40 in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 15 of 20 Examiner NOTE:

Performance Step:

23 Step 6.1.2 Component

11. GK HIS-103, CLASS I/E ELEC EQUIP A/C UNIT 5B.

o GK HIS-103 - PULL-TO-LOCK Standard: Placed GK HIS

-103 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

24 Step 6.1.2 Component

12. EF HIS-56A, ESW PUMP B.

o EF HIS-56A - PULL-TO-LOCK Standard: Placed EF HIS

-56A in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 16 of 20 Examiner NOTE:

Performance Step:

25 Step 6.1.2 Component

13. Feeder Breakers:

o NB HIS-4, NB02 NORM SPLY BKR NB0209.

o NB HIS PULL-TO-LOCK Standard: Placed NB HIS

-4 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

26 Step 6.1.2 Component

14. Feeder Breakers:

o NB HIS-5, NB02 ALT SPLY BKR NB0212.

o NB HIS PULL-TO-LOCK Standard: Placed NB HIS

-5 in PTL. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 17 of 20 Examiner NOTE:

Performance Step:

27 Step 6.1.2 Component

15. Feeder Breakers:

o NE HIS-26, NB02 EMERG SPLY BKR NB0211.

o NE HIS PULL-TO-LOCK Standard: Recognized NE HIS

-26 is already in PTL.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

28 Step 6.1.3 Direct an operator to perform Attachment A, Starting SB ODGs for NB02. Standard: Contacted the Site Watch to perform SYS KU

-122, Attachment A, for energizing NB02 from the SBO DGs.

Cue: CUE: When contacted as the site watch, acknowledge request.

After site watch contacted:

CUE: Report back from the site watch that NB02 is energized from the SBO DGs.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 18 of 20 Examiner NOTE:

Performance Step:

29 Step 6.1.4 WHEN the operator confirms that NB02 has been energized from the SBO DGs per Attachment A, Starting SBO DGs for NB02, THEN return to procedure and step in affect.

Standard: Applicant recognized that NB02 was energized by the SBO DGs and reported to CRS NB02 is re- energized.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed when all listed handswitches are in PTL and the CRS is informed NB02 is energized from SBO DGs.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 19 of 20 Verification of Completion Job Performance Measure No.

S5 (A P) Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. 'B' EDG OOS for governor replacement. Severe weather has caused a loss of offsite power. The reactor tripped. The crew entered EMG C

-0, LOSS OF ALL AC POWER. Power has been restored to the switchyard. XNB01 transformer and NB01 bus has sustained damage and are unavailable.

Initiating Cue:

The CRS directs you to energize NB02 AC emergency bus from offsite power using OFN NB

-030, LOSS OF AC EMERGENCY BUS NB01 (NB02), beginning at step B14. Inform the CRS when NB02 is re

-energized.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 5 Facility: WCGS Task No: 2700003 Task Title:

Start the Containment Atmospheric Control System IAW SYS GR

-120. Job Performance Measure No:

S6 Rev 0 K/A

Reference:

027 A4.01, Ability to manually operate and/or monitor in the control room: CIRS controls. Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. A Containment entry will be made next shift and HP has requested operating the Containment Atmospheric Control System to reduce the Containment airborne concentrations of radioiodine and particulates.

Task Standard:

At the completion of the JPM, the Containment Atmospheric Control System will be in service.

Required Materials:

SYS GR-120, REV 3.

General

References:

SYS GR-120, Rev 3.

Initiating Cue:

The CRS directs you to start both containment Atmospheric Control System fans IAW SYS GR

-120. All of the Prerequisites are met.

Time Critical Task:

NO Alternate Path:

NO Validation Time:

5 Minutes Appendix C 2 Form ES-C-1 Page 2 of 5 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 6.1.1 IF directed by SM/CRS to start CTMT ATMS CTRL SYS A FAN & DAMPER, THEN PLACE GR HIS

-10, CTMT ATMS CTRL SYS A FAN &

DAMPER to normal

-after-run. o GR HIS NORMAL-AFTER-RUN Standard: Started CTMT ATMS CTRL SYS A FAN.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 6.1.2 IF directed by SM/CRS to start CTMT ATMS CTRL SYS B FAN & DAMPER, THEN PLACE GR HIS

-20, CTMT ATMS CTRL SYS B FAN & DAMPER to normal

-after-run. o GR HIS NORMAL-AFTER-RUN Standard: Started CTMT ATMS CTRL SYS B FAN. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 5 Examiner NOTE:

Performance Step:

3 6.1.3 Section 6.1, Startup Of Containment Atmospheric Control System, complete.

Standard: Completed Procedure.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed when the Containment Atmospheric Control System is in service.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 4 of 5 Verification of Completion Job Performance Measure No.

S6 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. A Containment entry will be made next shift and HP has requested operating the Containment Atmospheric Control System to reduce the Containment airborne concentrations of radioiodine and particulates.

Initiating Cue:

The CRS directs you to start both containment Atmospheric Control System fans IAW SYS GR-120. All of the Prerequisites are met.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 8 Facility: WCGS Task No: 1300010 Task Title:

Complete Attachment A Pre Test and Post Test Alignments for STS IC

-601A, SLAVE RELAY TEST K601 TRAIN A SAFETY INJECTION.

Job Performance Measure No:

S7 Rev 0 K/A

Reference:

013 A3.02, Ability to monitor automatic operation of the ESFAS including: Operation of actuated equipment.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

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

Initial Conditions:

You are the Reactor Operator. STS IC

-601A, SLAVE RELAY TEST K601 TRAIN A SAFETY INJECTION, is in progress. All prerequisites have been completed.

Task Standard: At the completion of the JPM, the Applicant will have determined component status per STS IC

-601A, Attachment A, is SAT.

Required Materials:

STS IC-601A, REV 15.

General

References:

STS IC-601A, Rev 15.

Initiating Cue:

The CRS directs you to assist I&C in completing STS IC-601A. Complete steps 8.1 and 8.2.6, I&C will perform the remainder of the procedure, including IVs. Time Critical Task:

NO Alternate Path:

NO Validation Time:

10 Minutes Appendix C 2 Form ES-C-1 Page 2 of 8 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 Step 8.1.1 Ensure all PREREQUISITES have been met.

Standard: Recognized from initial conditions that prerequisites have been completed.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

2 Step 8.1.2 Record initial condition by circling the status of the equipment listed in the AS FOUND ALIGN column of ATTACHMENT A, DATA SHEET.

[3.2.1] Standard: Circled appropriate equipment status in the as found alignment column of Attachment A.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 3 of 8 Examiner NOTE:

Performance Step:

3 Step 8.1.3 Place ESF PANEL SA066X MODE SEL in check/pull

-to-lock. o SA HS CHECK/PULL

-TO-LOCK Standard: Placed ESF PANEL SA066X MODE SEL in check/pull

-to-lock. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 8 Examiner NOTE:

Performance Step:

4 Step 8.1.4 Verify components are aligned per ATTACHMENT A, DATA SHEET: 1. Align equipment in accordance with PRE

-TEST ALIGN. column. 2. Check SA066X indications are in accordance with PRE

-TEST ALIGN. column.

Standard: Placed GL HIS-1 to stop.

Recognized that GG HIS

-38 was already in stop position.

Placed GG HIS

-39 to stop.

Recognized that GL HIS

-30 was already in stop position.

Placed GL HIS

-31 to stop.

Recognized that GG HIS

-15A was already in stop position.

Pushed and held open pushbutton for GG HIS

-41 until opened.

Pushed and held open pushbutton for GG HIS

-40 until opened.

Recognized that GL HIS

-32 was already in open position.

Checked SA066X indications are in accordance with PRE

-TEST ALIGN. column.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 8 Examiner NOTE:

Performance Step:

5 Step 8.1.5 Section 8.1, PRE

-TEST ALIGNMENT, complete.

Standard: Initialed and dated.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Steps 8.2.1 through 8.2.5 are performed by the I&

C technician.

Direct the booth operator to insert KEY 1.

Performance Step:

6 Steps 8.2.1 through 8.2.5 TEST PERFORMANCE Standard: Applicant recognized that I&C will complete steps 8.2.1 thru 8.2.5 Cue: CUE: I&C will complete steps 8.2.1 thru 8.2.5 After applicant has informed I&C to complete steps CUE: Steps 8.2.1 thru 8.2.5 are complete.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 8 Examiner NOTE:

When step 8.2.6 is completed, the JPM is completed.

Performance Step:

7 Step 8.2.6 Ensure proper component status by performing the following steps for the POST TEST ALIGN. column of ATTACHMENT A, DATA SHEET and circling Sat (S) or Unsat (U):

o Equipment is in the listed position.

o SA066X lights are in accordance with listed condition.

Standard: Verified GG HIS

-15A indicated running.

Verified 7

-5 white light lit.

Circled S for SAT.

Verified GG HIS

-40 indicated closed.

Verified 8-5 white light lit.

Circled S for SAT.

Verified GL HIS

-32 indicated closed.

Verified 3

-7 white light lit.

Circled S for SAT.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once Attachment A Post Test Alignment, step 8.2.6, has been completed

. STOP TIME:

Appendix C 3 Form ES-C-1 Page 7 of 8 Verification of Completion Job Performance Measure No.

S7 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts: Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. STS IC

-601A, SLAVE RELAY TEST K601 TRAIN A SAFETY INJECTION, is in progress. All prerequisites have been completed.

Initiating Cue:

The CRS directs you to assist I&C in completing STS IC

-601A. Complete steps 8.1 and 8.2.6, I&C will perform the remainder of the procedure, including IVs.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 1 of 19 Facility: WCGS Task No: APE037006 Task Title:

Change GE RE

-92 setpoints on RM-11R for S/G tube leak.

Job Performance Measure No:

S8 Rev 0 K/A

Reference:

APE 037 AA1.04, Ability to operate and / or monitor the following as they apply to the Steam Generator Tube Leak: Condensate air ejector exhaust radiation monitor and failure indicator.

Examinee: NRC Examiner:

Facility Evaluator:

Date: Method of testing:

Simulated Performance Actual Performance X Classroom Simulator X Plant Read to the examinee:

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

Initial Conditions:

You are the Reactor Operator. The plant is operating at 100% power. The crew has entered OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE. GE RE-92 is in Alert with a reading of 1.00 E

- Task Standard:

At the completion of the JPM, the Applicant will have changed the setting for the Alert setpoint to 1.42 E

-06 + 0.1 E

-6.37E- Required Materials:

OFN BB-07A, REV 17A. SYS SP-121, REV 25A. AIF 21D

-004-01 REV 3 (PROVIDE COMPLETED COPY). CALCULATOR. STRAIGHT EDGE.

Simulator Setup:

IC 30 SCN File S5.scn ;S5 ;Set GE RE

-092 to 1e-006 IMF mSP10G f:1e

-006 ;end file Appendix C Job Performance Measure Worksheet Form ES-C-1 Page 2 of 19 General

References:

OFN BB-07A, Rev 17A. SYS SP-121, Rev 25A. AIF 21D

-004-01 Rev 3 (Provide completed copy).

Initiating Cue:

The Control Room Supervisor directs you to perform step 7.c of OFN BB-07A, STEAM GENERATOR TUBE LEAKAGE, to change GE RE

-92 setpoints using AIF 21D-004-01, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE. Adjust the alert setpoint to 10 GPD above the current reading on the RM

-11R. Time Critical Task:

NO Alternate Path:

NO Validation Time:

15 Minutes BOOTH/FLOOR: MUST ensure RM

-11R setpoints for GE RE

-92 are returned to their NORMAL values in-between Candidates. MUST ensure Supervisory Key is in NORMAL position in

-between Candidates. Ensure 150 GPD value correct on RM

-11R placard prior to starting JPM.

Appendix C 2 Form ES-C-1 Page 3 of 19 Performance Information Denote critical steps with a check mark () START TIME:

Examiner NOTE:

Performance Step:

1 OFN BB-07A, Step 7.c.

Using the Setpoint Adjustment And Conversion Graphs From Grab Sample Results, the Conversion Factor formula on the graph or the Setpoint Adjustment And Conversion Graphs From Theoretical Monitor Response, adjust BM RE

-25, GE RE-92 and SJ RE

-02 rad monitor setpoints, as follows:

1) Adjust the alarm setpoint to 150 gpd.

2) Adjust the alert setpoint to above the current baseline reading. Standard: Recognized from initial conditions that AIF 21D

-004-01, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE, will be used.

Located current AIF 21D

-004-01 form in COAF book.

Located current copy of SYS SP

-121, OPERATION OF THE G.A. MONITOR SYSTEM.

Cue: WHEN Applicant locates current AIF 21D

-004-01, THEN provide copy of graph.

WHEN Applicant locates current revision of SYS SP

-121, THEN provide copy of procedure.

Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 4 of 19 Examiner NOTE: Write down the value that the Applicant determines is equivalent to 150 GPD.

IF Applicant uses the Conversion Factor at the top of the form, THEN: Alarm Setpoint

= (150)(4.23E

-08) + 2.68E

-08 Alarm Setpoint

= 6.37E-06 + IF Applicant used a straight edge on the graph, THEN: Alarm Setpoint

= 6.4E-06 + Performance Step:

2 Step 7.c.1)

Determine from the Theoretical Monitor Response Graph the new alarm setpoint.

Standard: Determined new setting for 150 GPD using AIF 21D

-004-01. Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 5 of 19 Examiner NOTE:

Write down the value that the Applicant determines is equivalent to 33 GPD.

IF Applicant uses the Conversion Factor at the top of the form, THEN: GPD = (1.00E 2.68E-08)/4.23E-08 GPD = 23 GPD.

New Alarm Setpoint

= (33)(4.23E-08) + 2.68E

-08. Alarm Setpoint

= 1.42 E-06 + 0.1 E- IF Applicant used a straight edge on the graph, THEN: Alarm Setpoint

= 1.4 E-06 + Performance Step:

3 Step 7.c.2)

Determine from the Theoretical Monitor Response Graph the new alert setpoint based on current reading.

Standard: Recognized from initial conditions that current reading is 1.00E

- Recognize from initiating cues that the new setting is to be 10 GPD higher than current reading.

Determined new Alert setting using AIF 21D

-004-01. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

4 SYS SP-121, Step 6.3 Channel Item & Release Setpoint Operations Using RM

-11R Standard: Determined correct step to use to change GE RE

-92 setpoints.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 6 of 19 Examiner NOTE:

Performance Step:

5 Step 6.3.1.

To change the value of a Supervisor RM

-80 Database Channel Item, perform the following:

Standard: Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Examiner NOTE:

Step 6.1.2 is a common task that the Applicant may do without consulting the procedure.

Performance Step:

6 Step 6.3.1.1 Select the desired channel per step 6.1.2.

Standard: Referred back to step 6.1.2.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 7 of 19 Examiner NOTE:

Performance Step:

7 Step 6.1.2.

WHEN desired grid is displayed, THEN select desired channel, as follows:

1. Key in the three digit Channel Identification Number displayed on the grid.

2. Press the SEL key.

3. Check the selected channel outlined in white.

Standard: Displayed grid 1.

Keyed in 925 for GE RE

-92. Pressed SEL key.

Verified correct channel selected. Returned to step 6.3.1 Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

8 Step 6.3.1.2.

Place Supervisor Master Key in the key slot and turn it to SUPERVISOR position.

Standard: Selected supervisory position.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 8 of 19 Examiner NOTE:

Performance Step:

9 Step 6.3.1.3.

Press the LIT key.

Standard: Pressed LIT key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

10 Step 6.3.1.4.

Press the Grid 5 key.

Standard: Pressed grid 5 key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

11 Step 6.3.1.5.

Press the SEL key.

Standard: Pressed SEL key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 9 of 19 Examiner NOTE:

Performance Step:

12 Step 6.3.1.6.

Verify the Supervisor RM

-80 Database Screen is displayed.

Standard: Verified supervisory RM

-80 database screen is displayed.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Examiner NOTE:

Performance Step:

13 Step 6.3.1.7. Press the minus (-) key. Standard: Pressed the minus key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 10 of 19 Examiner NOTE:

The channel item for Alert setpoint is 010. The channel item for Hi (Alarm) setpoint is 009.

Performance Step:

14 Step 6.3.1.8.

Key in the desired Channel Item number.

Standard: Keyed in either 10 or

09. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

15 Step 6.3.1.9.

Press the SEL key.

Standard: Pressed SEL key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 11 of 19 Examiner NOTE:

Performance Step:

16 Step 6.3.1.10.

Check the selected Channel Item is backlit.

Standard: Checked channel item backlit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Monitor the Applicant closely and write down the value entered. Use this value for providing the step 6.3.1.13 Cue. The values keyed in should be 1, 4, 2, -, 0, 6 (+ 0.2) for channel item 010 and 6, 3, 7, -, 0, 6 (+ 0.2) for channel item 009. The Applicant should use the numbers determined in OFN BB-07A. Performance Step:

17 Step 6.3.1.11. Key in the desired Channel Item value in the correct format.

Example: 5.79E

-5 is keyed in as 5, 7, 9, -, 0, 5. Standard: Keyed in channel item value.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 12 of 19 Examiner NOTE:

Performance Step:

18 Step 6.3.1.12.

Press the ENTER key.

Standard: Pressed the enter key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

19 Step 6.3.1.13. A message area will appear at the bottom of the screen, a. IF the data in the message area is correct, THEN press the ENTER key and proceed to step 6.3.1.14.

b. IF the data in the message area is incorrect, THEN press the CLEAR key and return to step 6.3.1.11.

Standard: IF data is correct, THEN; Pressed enter key.

IF data is incorrect, THEN: Pressed clear key and returned to step 6.3.1.11.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 13 of 19 Examiner NOTE: Performance Step:

20 Step 6.3.1.14.

IF the entry is accepted, THEN the message at the bottom of the CRT will indicate value accepted and the value for that item will be updated in the RM

-80 Column and the Master Column.

Standard: Recognized that next channel item requires updated and returned to step 6.3.1.7.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

The Channel Item number may be advanced by depressing the SEL key.

Performance Step:

21 Step 6.3.1.7.

Press the minus (-) key. Standard: Pressed the minus key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 14 of 19 Examiner NOTE:

The channel item for Alert setpoint is 010. The channel item for Hi (Alarm) setpoint is 009.

Performance Step:

22 Step 6.3.1.8.

Key in the desired Channel Item number.

Standard: Keyed in either 10 or

09. Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

23 Step 6.3.1.9.

Press the SEL key.

Standard: Pressed SEL key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 15 of 19 Examiner NOTE:

Performance Step:

24 Step 6.3.1.10.

Check the selected Channel Item is backlit.

Standard: Checked channel item backlit.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Monitor the Applicant closely and write down the value entered. Use this value for providing the step 6.3.1.13 Cue. The values keyed in should be 1, 4, 2, -, 0, 6 (+ 0.2) for channel item 010 and 6, 3, 7, -, 0, 6 (+ 0.2) for channel item 009. The Applicant should use the numbers determined in OFN BB-07A. Performance Step:

25 Step 6.3.1.11. Key in the desired Channel Item value in the correct format.

Example: 5.79E

-5 is keyed in as 5, 7, 9, -, 0, 5. Standard: Keyed in channel item value.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 16 of 19 Examiner NOTE:

Performance Step:

26 Step 6.3.1.12.

Press the ENTER key.

Standard: Pressed the enter key.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

27 Step 6.3.1.13. A message area will appear at the bottom of the screen, a. IF the data in the message area is correct, THEN press the ENTER key and proceed to step 6.3.1.14.

b. IF the data in the message area is incorrect, THEN press the CLEAR key and return to step 6.3.1.11.

Standard: IF data is correct, THEN; Pressed enter key.

IF data is incorrect, THEN: Pressed clear key and returned to step 6.3.1.11.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment:

Appendix C 2 Form ES-C-1 Page 17 of 19 Examiner NOTE: Performance Step:

28 Step 6.3.1.14.

IF the entry is accepted, THEN the message at the bottom of the CRT will indicate value accepted and the value for that item will be updated in the RM

-80 Column and the Master Column.

Standard: Completed updating channel items.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Examiner NOTE:

Performance Step:

29 Step 6.3.1.16.

WHEN no further changes are desired, THEN turn the Supervisor Master Key to the NORMAL position.

Standard: Turned key to normal position.

Cue: Score: SAT or UNSAT SAT or UNSAT Comment: Terminating cue:

The JPM is completed once setpoint changes have been made. NOTE: As the same actions are done to change the second setpoint, IF the examiner is satisfied that the Applicant will complete the task after the first setpoint is changed, THEN the JPM may be terminated.

STOP TIME:

Appendix C 3 Form ES-C-1 Page 18 of 19 Verification of Completion Job Performance Measure No.

S8 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: Response: Result: Satisfactory/Unsatisfactory Examiner's signature and date:

Appendix C 3 Form ES-C-1 Initial Conditions:

You are the Reactor Operator. The plant is operating at 100% power. The crew has entered OFN BB

-07A, STEAM GENERATOR TUBE LEAKAGE. GE RE-92 is in Alert with a reading of 1.00 E

- Initiating Cue:

The Control Room Supervisor directs you to perform step 7.c of OFN BB-07A, STEAM GENERATOR TUBE LEAKAGE, to change GE RE

-92 setpoints using AIF 21D-004-01, SETPOINT ADJUSTMENT AND CONVERSION GRAPHS FROM THEORETICAL MONITOR RESPONSE. Adjust the alert setpoint to 10 GPD above the current reading on the RM-11R.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 1 of 5 Rev 3 Facili t y: Wolf Creek Scenari o No.: 1 (New) O p-Tes t No.: Nov 2015 E x a miners: Opera tors: I ni t ia l Condi tions: 100% power, MOL, 'B' MDAFWP OOS for scheduled maintenance

. IC 30 Turno ver: T.S. 3.7.5 Condition B entered based on B MDAFW pump OOS. Expected return is 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Hold current power level.

E vent N o. M a l f. N o. E v ent T y p e* E vent Descr ip t io n 1. C (ATC SRO) NCP flow control valve failure low (BG FK

-462) 2. I (BOP SRO) Main feedwater header pressure detector (AE PI-508) failure high. 3. I (ATC SRO) TS (SRO) PZR level channel (BB LI-459) fails high over 30 seconds.

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 2 of 5 Rev 3 4. R (ATC) TS (SRO) N (BOP SRO) Dropped rod and recovery.

5. M (ALL) Rod ejection resulting in a LOCA.

6. C (BOP) Turbine fails to trip in auto, one MSIV fails to close in auto (Note: With the turbine failing to auto trip AND one MSIV failing to auto close the component failure for the BOP will be mitigated by either manually tripping the turbine or manually closing the one open MSIV to prevent uncontrolled RCS cooldown)

7. NB01 bus faults and locks out.

(drives CT 1 for both the loss of feed and for only one train of safety related equipment available)

8. C (ALL) Turbine-driven Auxiliary Feedwater Pump (TDAFWP) fails to start due to broke trip throttle valve at the time of the reactor trip. CT1: Establish AUX feed flow (from the NSAFP) to at least ONE intact S/G at a flow rate great enough that core exit temperatures are stable or decreasing AND level in at least ONE S/G is increasing, prior to bleed and feed criteria being met.

9. Normal Charging Pump (NCP) trips on motor overload.

(this drives CT 2 with the loss of the B train CCP)

10. C (ALL) B train CCP fails to auto start (manual start available) on the SI following the small break LOCA.

CT 2: Establish flow from at least one Charging pump by the completion of EMG E-0, Attachment F.

(B CCW pump trips on reactor trip with an auto start of the D CCW pump, this is to check if the crew ensures a CCW pump is running in the same train as the CCP that will be started)

(N)ormal, (R)eacti v i t y , (I)nstrument, (C)omponent, (M)ajor A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 3 of 5 Rev 3 Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Malfunctions after EOP entry (1

-2) 3 (events 6, 8 , 10) 2. Abnormal events (2

-4) 3 (events 1,2,3

) 3. Major transients (1

-2) 1 (event 5) 4. EOPs entered/requiring substantive actions (1

-2) 1 (EMG E-1) 5. EOP contingencies requiring substantive actions (0

-2) 1 (EMG FR-H1) 6. EOP based Critical tasks (2

-3) 2 (events 8,10) 7. Critical Task Justification References CT 1: Establish AUX feed flow (from the NSAFP

) to at least ONE intact S/G at a flow rate great enough that core exit temperatures are stable or decreasing AND level in at least ONE S/G is increasing, prior to bleed and feed criteria being met. SAFETY SIGNIFICANCE

-- Failure to establish feedwater flow to any SG results in the crew having to rely upon the lower-priority action of establishing RCS bleed and feed to minimize core uncovery. This constitutes incorrect performance that fails to prevent "degradation of any barrier to fission product release."

BD EMG FR-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Rev 15, step 8 and 17 CT 2: Establish flow from at least one Charging pump b y the completion of EMG E-0, Attachment F

. (note: with a CCP in an ECCS line up, meaning after an SI actuation signal, there is no control of flow since all the flow is directed to the BIT header and flow rate is determined by RCS pressure)

The acceptable results obtained in the FSAR analysis of a small

-break LOCA are predicated on the assumption of minimum ECCS pumped injection. The flow rate values assumed for minimum pumped injection are based on operation of one each of the following ECCS pumps: Charging/SI pump (HP plants only), high

-head SI pump, and low-head SI pump.

BD EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Rev 26a, step F5

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 4 of 5 Rev 3 SCENARIO #

1 NARRATIVE Turnover: Scenario starts out at 100% power MOL. Motor Dri ven AFW p ump 'A' was tagged out for mainte n a nce activities 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ago

. Tec hnical Sp e cificati on (TS) 3.7.5, AFW system, Condit ion B.1 (r estore AFW train to OPERABLE in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) w as ent e re d. Expected return is 4 8 h ours. Event 1:

NCP flow control valve fails low (BG FK

-462). The failure will cause the running charging pump (NCP) to lower flow which will cause annunciator 41A, SEAL INJ TO RCP FLOW LO, 42A, CHG LINE FLOW HILO, and 42E, CHARGING PMP TROUBLE, to come in. The crew will enter 42 E as this will correct the problem. The RO will place BG FK

-462 in manual and restore charging flow to normal. SRO will direct the ALR to mitigate this failure.

Event 2: Main feedwater header pressure detector AE PI-508 failure high.

The failure causes the MFP speed to slow. The BOP will take manual control of MFP Turbine Master Speed Controller, FC SK-509A , and restore feed pump speed to normal value. SRO will direct OFN SB-008 , INSTRUMENT MALFUNCTIONS, Attachmen t B , STEAM OR FEEDWATER HEADER PRESSURE CHANNEL MALFUNCTION, for mitigation of the failure.

Event 3: PZR level channel BB LI

-459 fails hi over 30 seconds.

This will cause multiple alarms and PZR indicated level to rise. The crew identifies and diagnoses the level channel failure and enters OFN SB

-008, INSTRUMENT MALFUNCTIONS, Attachment J, PZR LEVEL CHANNEL MALFUNCTION, to mitigate the instrument failure. TS are identified by the SRO and 3.3.1, Reactor Trip System Instrumentation, Condition A and M is entered off of table 3.3.1

-1 Function 9.

Event 4: Dropped rod and recovery.

Control rod H8 will suffer a stationary gripper failure and fall into the core. The SRO will direct recovery of the rod once the reason for the failure is resolved. The ATC will withdraw the rod OFN SF

-011, REALIGNMENT OF DROPPED RODS AND ROD CONTROL MALFUNCTIONS. SRO will enter 3.1.4, Rod Group Alignment Limits, Conditions A and B. QPTR and AFD will be monitored to determine if the T.S. limit is exceeded.

Event 5: Rod ejection resulting in a LOCA. The reactor will either be tripped manually by the crew or auto on low PZR pressure forcing the crew to enter EMG E

-0, REACTOR TRIP OR SAFETY INJECTION.

Event 6: Turbine fails to trip in auto, one MSIV fails to close in auto. BOP will either trip the turbine in manual OR close MSIVs (using AB HS

-79, and 80 OR AB HIS

-14, for the MSIV respectively). This action will be directed by EMG E

-0, REACTOR TRIP OR SAFETY INJECTION, step 2 RNO (Note: With the turbine failing to auto trip AND one MSIV failing to auto close the component failure for the BOP will be mitigated by either manually tripping the turbine or manually closing the one open MSIV to prevent uncontrolled RCS cooldown)

Event 7: At the time of the reactor trip NB0 1 bus faults and locks out.

Since this is a bus lockout the NE0 1 output breaker will not close when the EDG is up to speed and voltage as normal. This will cause a loss of all safety related A train equipment, including '

A' MDAFWP and '

A' CCP. Event 8: At the time of the reactor trip the TDAFWP fails to start due to broke trip throttle valve

. During the performance of EMG E

-0, REACTOR TRIP OR SAFETY INJECTION, the crew will diagnosis a loss of all AFW due to the 'A' MDAFWP being tagged out, loss of NB0 1 (loss of 'A' MDAFWP), and the failure of the TDAFWP to start due to broke trip throttle valve. The crew will complete the immediate actions of E-0 and will transition to EMG FR

-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, to start the NSAFP. CT1: Establish AUX feed flow (from the NSAFP) to at least ONE intact S/G prior to bleed and feed criteria being met.

Event 9: At the time of the reactor trip the NCP trips on motor overload. (This drives CT 2 with the loss of the 'B' train CCP)

A ppend i x D Scenar i o O utli ne Fo r m ES-D-1 Page 5 of 5 Rev 3 Event 10: On the SI following the reactor trip the B train CCP fails to auto start (manual start available)

. CT 2: Establish flow from at least one Charging pump by the completion of EMG E

-0, Attachment F.

(B CCW pump trips on reactor trip with an auto start of the D CCW pump, this is to check if the crew ensures a CCW pump is running in the same train as the CCP that will be started)

Crew continues from EMG FR-H1 back to E-0 then to EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT. The crew will continue in E

-1 until SI is reset after which the scenario can be terminated

. Procedures entered:

ALR 042E, CHARGING PMP TROUBLE OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment B, STEAM OR FEEDWATER HEADER PRESSURE CHANNEL MALFUNCTION OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment J, PZR LEVEL CHANNEL MALFUNCTION OFN SF-011, REALIGNMENT OF DROPPED RODS AND ROD CONTROL MALFUNCTIONS EMG E-0, REACTOR TRIP OR SAFETY INJECTION EMG FR-H1, RESPONSE TO LOSS OF SECONDARY HEAT SINK EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT

Scenario file:

ILO Scenario 1 scn SimGroup

\Tag B MDAFW

turbine fails to trip in auto IMF mAC02B i

-1 f:-1 ;MSIVs fail to close in auto IMF mSA27AB07 i:

-1 f:-1 ;NCP trip on reactor trip

{jpplsi} ICM bkrPB00301 t:1 d:0

B CCP fails to start in auto IMF mBG27B i

-1 f:-1 ;trip a B CCW on reactor trip

{jpplsi} ICM bkrDPEG01B t:1 d:0

NCP flow control valve fails closed in auto

- ATC IMF mBG25A f:

-50 r:10 k:1

Main feedwater header pressure detector AE PI

-508 fails high

- BOP ICM trAEPT0508 t:2 d:0 k:2

PZR level channel 459 fails hi over 30 seconds

- ATC IMF mBB22A f:100 r:30 k:3

Control rod H8 stationary gripper failure

- ATC IMF mSF04H8 f:1 k:4

{Key[5]} DMF mSF04H8 IRF rSF05 f:1 k:6

Ejected rod during recovery. NB01 faults on SIS. TDAF pump broke IMF mSF05H8 f: 800 k:7

{jpplsi} IMF mNB03 IMF mAL02 i:

-1 f:-1 ;Establish flow from Non

-Safety Related AFW Pump

{Key[8]} scn SimGroup

\Start PAP01

close TDAFP steam drains

Key 9 ;end A ppend i x D R equ ired Opera t or A c ti ons Fo r m ES-D-2 Rev 0 Page 1 of 22 O p-Tes t No.: Nov. 2015 Scenari o No.: 1 E v en t No.: 1 E v en t Descrip tion: NCP flow control valve fails low (BG FK-462) T ime Po sitio n Simulator operator: Insert Key 1 at the lead examiners direction.