Text

11 Final Operating Test
	ML21020A095
Person / Time
Site:	Palo Verde
Issue date:	12/10/2020
From:	Greg Werner; Operations Branch IV
To:	; Arizona Public Service Co
References
	Download: ML21020A095 (200)
	v • d • e

Administrative Topics Outline Facility: PVNGS Date of Examination: 11/30/20 Examination Level SRO Operating Test Number: 2020 NRC Administrative Topic Type Code* Describe Activity to be Performed (see Note)

Determine the active/inactive status of 3 licensed JPM:

operators (A1) M, R KA: 2.1.1 IR: 4.2 Determine the required shutdown based on SGTL JPM:

indications (A2) N, R KA: 2.1.7 IR: 4.7 JPM: Pressurizer Head Vent surveillance and LCO 3.4.12 (A3) N, R KA: 2.2.22 IR: 4.7 Determine hold points for work in a HRA and required JPM:

approval to continue work (A4) D, R KA: 2.3.4 IR: 3.7 JPM: EAL Classification FS1.1 (A5) N, R KA: 2.4.41 IR: 4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (1) ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (4) ( 1)

(P)revious 2 exams (0) ( 1; randomly selected) 2020 PVNGS NRC Initial Exam ES-301-1 SRO Admin JPM Outline Rev 0

Administrative Topics Outline Task Summary A1 The applicant is provided a list of all watches stood by three licensed operators during the previous quarter. The applicant must compare the watches stood by each individual to the requirements in 40DP-9OP02, Conduct of Shift Operations, and determine whether or not each of their licenses are active for the current quarter. This is a modified JPM.

A2 The applicant will be directed to determine the required shutdown based on SGTL indications per 40AO-9ZZ02, Excessive RCS Leakrate, Appendix F, Steam Generator Tube Leak Guidelines. This is a new JPM.

A3 The applicant will be directed to evaluate the results of surveillance 73ST-9XI24, Reactor and Pressurizer Vent Valves - Inservice Test and determine the operability of Pressurizer Head Vents in accordance with LCO 3.4.12. Based on the number of inoperable Pressurizer vent paths the applicant will determine the required actions and associated completion times. This is a new JPM.

A4 The applicant will be directed to determine the expected dose for a job in a High Radiation Area, hold points for the job, what approval is needed to exceed limits, and which of the Auxiliary Operators listed will perform the job. This is a bank JPM.

A5 The applicant will be directed to classify an emergency event using EP-0901, Classifications, and the EAL classification charts. This is a new JPM.

2020 PVNGS NRC Initial Exam ES-301-1 SRO Admin JPM Outline Rev 0

2020 PVNGS NRC Initial Exam JPM A1 JPM INFORMATION TASK: 1290020301 - Conduct of Shift Operations Determined that Operators #1 and #2 DO NOT have an active license and Operator #3 TASK STANDARD:

DOES have an active license as of July 1.

K/A: G 2.1.1 RATING: RO: 3.8 SRO: 4.2 POSITION(S): RO/SRO VALIDATION TIME: 10 minutes

REFERENCES:

40DP-9OP02, Conduct of Shift Operations LOCATION: SIMULATOR PLANT CLASSROOM X TIME CRITICAL: NO ALTERNATE PATH: NO PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: Brian Garrettson DATE: 7/21/2020 VALIDATED BY: Brian Garrettson DATE: 7/31/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a PVAR to be written, remediation, and re-evaluation. PVAR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM A1 PROCEDURES/MATERIALS:

40DP-9OP02, Conduct of Shift Operations, Section 4.8.4, Licensed Operator Watchstanding Proficiency.

This JPM was written using Revision 72 of 40DP-9OP02, Conduct of Shift Operations. This JPM may be used with later revisions if it is verified that the later revision does not affect the Steps/Standards of the JPM.

INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Today is July 1, 2020 You are reviewing the license status of 3 licensed operators based on watches stood in the previous quarter Operator # 1 received his SRO license on September 10 of 2018 Operator # 2 received her SRO license on September 10 of 2018 Operator # 3 received his SRO license on November 15 of 2019 All operators are current in LOCT INITIATING CUE:

Using the provided list of watches stood by each of the 3 operators in the previous quarter, determine whether or not each of their licenses is active or not active as of July 1 per Palo Verde administrative procedural requirements Document your answers below by circling the status of each operator license as of July 1.

2020 PVNGS NRC Initial Exam JPM A1 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM A1 JPM START TIME:

JPM Step: 1

Determine if Operator # 1 license is active July 1.

Standard: Determined that Operator # 1s license IS NOT active on July 1.

Answer Explanation:

An SRO license is considered active if they stand a minimum of five 12-hour shifts in the previous quarter. Per step 4.8.4.5 of 40DP-9OP02, Conduct of Shift Operations, at least one of those shifts must be in the CRS or SM position, the other shifts can be in a TS required RO position. However, the other shifts will not be counted if stood in the STA position. Therefore the SRO license is inactive.

Comments (required for UNSAT):

SAT UNSAT JPM Step: 2

Determine if Operator # 2s license is active on July 1.

Standard: Determined that Operator # 2s license IS NOT active on July 1.

Answer Explanation:

An SRO license is considered active if they stand a minimum of 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months in the previous quarter, which Operator # 2 completed, however partial shifts cannot be credited (per step 4.8.4.5 bullet 5), therefore, even though the 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months were met, the requirement for five 12-hour shifts was not. Therefore the SRO license is inactive.

Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM A1 JPM Step: 3

Determine if Operator # 3s license is active on July 1.

Standard: Determined that Operator # 3s license IS active on July 1.

Answer Explanation:

An SRO license is considered active if they stand a minimum of five 12-hour shifts in the previous quarter. Per step 4.8.4.5 of 40DP-9OP02, Conduct of Shift Operations, at least one of those shifts must be in the CRS or SM position, however the other 5 shifts can be in a TS required RO position. Therefore the SRO license remains active.

Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM A1 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 4/20/16 6 JPM created.

1 7/21/20 6 JPM modified to use on the 2020 NRC Exam REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

EXAMINEE INITIAL CONDITIONS:

Today is July 1, 2020 You are reviewing the license status of 3 licensed operators based on watches stood in the previous quarter Operator # 1 received his SRO license on September 10 of 2018 Operator # 2 received her SRO license on September 10 of 2018 Operator # 3 received his SRO license on November 15 of 2019 All operators are current in LOCT INITIATING CUE:

Using the provided list of watches stood by each of the 3 operators in the previous quarter, determine whether or not each of their licenses is active or not active as of July 1 per Palo Verde administrative procedural requirements.

Document your answers below by circling the status of each operator license as of July 1.

Operator # 1 License: Active / Inactive Operator # 2 License: Active / Inactive Operator # 3 License: Active / Inactive EXAMINEE

2020 PVNGS NRC Initial Exam JPM A2 JPM INFORMATION TASK: L498457 - Direct actions from the Abnormal Operating Procedures TASK STANDARD: Determined MODE 3 entry is required by 1800 K/A: G 2.1.7 RATING: RO: 4.4 SRO: 4.7 POSITION(S): SRO VALIDATION TIME: 5 minutes 40AO-9ZZ02 Excessive RCS Leakrate, Appendix F, Steam Generator Tube

REFERENCES:

Leak Guidelines Technical Specifications LOCATION: SIMULATOR PLANT CLASSROOM X TIME CRITICAL: NO ALTERNATE PATH: NO PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: Brian Garrettson DATE: 7/22/2020 VALIDATED BY: Brian Garrettson DATE: 7/31/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a PVAR to be written, remediation, and re-evaluation. PVAR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM A2 PROCEDURES/MATERIALS:

40AO-9ZZ02 Excessive RCS Leakrate, Appendix F, Steam Generator Tube Leak Guidelines Technical Specifications This JPM was written using Revision 19 of 40AO-9ZZ02 Excessive RCS Leakrate. This JPM may be used with later revisions if it is verified that the later revision does not affect the Steps/Standards of the JPM.

INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power RU-141 and RU-142 are available A Steam Generator Tube Leak develops on Steam Generator #2 The following is a timeline of SG #2 leakrates between from 0800 to 1200:

Time SG #2 Leak Rate 0800 (SGTL started) 55 gpd 0900 75 gpd 1000 100 gpd 1100 125 gpd 1200 150 gpd INITIATING CUE:

Based on the above timeline and per plant procedural requirements:

o MODE 3 entry is REQUIRED no later than __________.

2020 PVNGS NRC Initial Exam JPM A2 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM A2 JPM START TIME:

JPM Step: 1

Determine when MODE 3 entry is required Standard: Determined MODE 3 entry is required by 1800 Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM A2 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 7/22/20 6 JPM created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM A2 EXAMINEE INITIAL CONDITIONS:

Unit 1 is operating at 100% power RU-141 and RU-142 are available A Steam Generator Tube Leak develops on Steam Generator #2 The following is a timeline of SG #2 leakrates between from 0800 to 1200:

Time SG #2 Leak Rate 0800 (SGTL started) 55 gpd 0900 75 gpd 1000 100 gpd 1100 125 gpd 1200 150 gpd INITIATING CUE:

Based on the above timeline and per plant procedural requirements:

o MODE 3 entry is REQUIRED no later than __________.

EXAMINEE

2020 PVNGS NRC Initial Exam JPM A3 JPM INFORMATION TASK: 1280010202 - Review the results of surveillance tests Determined that 3 of 4 Pressurizer Vent paths are INOPERABLE. Determined the TASK STANDARD: REQUIRED ACTION is to restore vent paths to OPERABLE status and the COMPLETION TIME is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months K/A: G 2.2.40 RATING: RO: 3.4 SRO: 4.7 POSITION(S): SRO VALIDATION TIME: 15 minutes 73ST-9XI24, Reactor and Pressurizer Vent Valves - Inservice Test

REFERENCES:

Technical Specifications Technical Specifications Basis LOCATION: SIMULATOR PLANT CLASSROOM X TIME CRITICAL: NO ALTERNATE PATH: NO PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: Brian Garrettson DATE: 4/27/2020 VALIDATED BY: Brian Garrettson DATE: 5/1/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a PVAR to be written, remediation, and re-evaluation. PVAR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM A3 PROCEDURES/MATERIALS:

73ST-9XI24, Reactor and Pressurizer Vent Valves - Inservice Test Technical Specifications Technical Specifications Basis This JPM was written using Revision 22 of 73ST-9XI24, Reactor and Pressurizer Vent Valves -

Inservice Test. This JPM may be used with later revisions if it is verified that the later revision does not affect the Steps/Standards of the JPM.

INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Unit 3 is in MODE 4 Pressurizer pressure is 410 psia The crew is performing 73ST-9XI24, Reactor and Pressurizer Vent Valves - Inservice Test, Section 6.1, Pressurizer Vent Valve Stroke Timing for RCA-HV-103, RCB-HV-105, RCA-HV-106, RCB-HV-108, and RCB-HV-109 During the test all valves stroked full open and full closed SATISFACTORILY The following stroke times were recorded for each valve:

Stroke Time (seconds)

Valve Open Closed RCA-HV-103 1.9 2.3 RCB-HV-105 1.8 1.8 RCA-HV-106 2.2 3.1 RCB-HV-108 1.8 1.9 RCB-HV-109 1.7 1.9 INITIATING CUE:

How many, if any, Pressurizer Vent PATHS are INOPERABLE?

Per Technical Specifications, what, if any, is the REQUIRED ACTION and associated COMPLETION TIME from the results of the surveillance assuming use of the Front-Stop Completion Time?

2020 PVNGS NRC Initial Exam JPM A3 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM A3 JPM START TIME:

JPM Step: 1

How many, if any, Pressurizer Vent PATHS are INOPERABLE Standard: Determined that 3 of 4 Pressurizer vent paths are INOPERABLE Comments (required for UNSAT):

SAT UNSAT JPM Step: 2

Per LCO 3.4.12, Pressurizer Vents, what, if any, is the REQUIRED ACTION and associated COMPLETION TIME from the results of the surveillance Standard: Determined the REQUIRED ACTION is to restore vent paths to OPERABLE status and the COMPLETION TIME is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM A3 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 7/22/20 6 Created JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM A3 EXAMINEE INITIAL CONDITIONS:

Unit 3 is in MODE 4 Pressurizer pressure is 410 psia The crew is performing 73ST-9XI24, Reactor and Pressurizer Vent Valves - Inservice Test, Section 6.1, Pressurizer Vent Valve Stroke Timing for RCA-HV-103, RCB-HV-105, RCA-HV-106, RCB-HV-108, and RCB-HV-109 During the test all valves stroked full open and full closed SATISFACTORILY The following stroke times were recorded for each valve:

Stroke Time (seconds)

Valve Open Closed RCA-HV-103 1.9 2.3 RCB-HV-105 1.8 1.8 RCA-HV-106 2.2 3.1 RCB-HV-108 1.8 1.9 RCB-HV-109 1.7 1.9 INITIATING CUE:

Complete the highlighted portions of the Surveillance How many, if any, Pressurizer Vent PATHS are INOPERABLE?

Per Technical Specifications, what, if any, is the REQUIRED ACTION and associated COMPLETION TIME from the results of the surveillance assuming use of the Front-Stop Completion Time?

EXAMINEE

2020 PVNGS NRC Initial Exam JPM A4 JPM INFORMATION TASK: L392178 - Perform the duties of the Emergency Coordinator Determined that Operator #1 will be used for the evolution. Determined that Emergency Coordinator authorization will be required when the operator has been in TASK STANDARD:

the area for 6.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months or 1815. Determined the required posting for the room is High Radiation Area.

K/A: G 2.3.4 RATING: RO: 3.2 SRO: 3.7 POSITION(S): SRO VALIDATION TIME: 10 minutes 75DP-9RP01, Radiation Exposure and Access Control

REFERENCES:

75RP-0RP01, Radiological Posting and Labeling EP-0905, Protective Actions LOCATION: SIMULATOR PLANT CLASSROOM X TIME CRITICAL: NO ALTERNATE PATH: NO PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: Brian Garrettson DATE: 7/22/2020 VALIDATED BY: Brian Garrettson DATE: 7/31/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a PVAR to be written, remediation, and re-evaluation. PVAR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM A4 PROCEDURES/MATERIALS:

75DP-9RP01, Radiation Exposure and Access Control 75RP-0RP01, Radiological Posting and Labeling EP-0905, Protective Actions This JPM was written using Revision 22 of 75DP-9RP01, Revision 36 of 75RP-0RP01, and Revision 10 of EP-0905. This JPM may be used with later revisions if it is verified that the later revision does not affect the Steps/Standards of the JPM.

INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

A LOCA is in progress in Unit 2 Auxiliary Building There is manual valve in the Auxiliary Building that will isolate the leak The dose rate in the area is 800 mrem/hr Per EP-0905, Protective Actions, it has been determined that the leak isolation will be Protecting Valuable Property 3 potential Auxiliary Operators have been selected to perform the isolation All 3 operators have the same lifetime cumulative dose Data for the Auxiliary Operators able to do the work is:

o Operator #1 - 50 years old male o Operator #2 - 25 year old female o Operator #3 - 40 year old male INITIATING CUE:

You are the Emergency Coordinator Determine the following:

o Which Auxiliary Operator will be selected for the evolution?

o If the Auxiliary Operator is sent into the Auxiliary Building at 1200, when will Emergency Coordinator authorization be required to continue work per EP-0905, Protective Actions Section 6.7?

o What is the required radiological posting for the room in which the task will be performed? (i.e., Radiation Area, High Radiation Area, Very High Radiation Area, or Locked High Radiation Area)

2020 PVNGS NRC Initial Exam JPM A4 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM A4 JPM START TIME:

JPM Step: 1

Determine which operator will be selected for the evolution Standard: Determined that Operator #1 will be used for the evolution because personnel greater than 45 years old should receive primary consideration Comments (required for UNSAT):

SAT UNSAT JPM Step: 2

Determine when Emergency Coordinator authorization is required Standard: Determined that Emergency Coordinator authorization will be required when the operator has been in the area for 6.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months or 1815 5 REM per event requires Emergency Coordinator authorization The area is 800 mREM/hr 5/0.8 = 6.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months Comments (required for UNSAT):

SAT UNSAT JPM Step: 3

Determine the radiological posting for the room Standard: Determined the required posting for the room is High Radiation Area Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM A4 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 8/1/17 6 Created JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM A4 EXAMINEE INITIAL CONDITIONS:

A LOCA is in progress in Unit 2 Auxiliary Building There is manual valve in the Auxiliary Building that will isolate the leak The dose rate in the area is 800 mrem/hr Per EP-0905, Protective Actions, it has been determined that the leak isolation will be Protecting Valuable Property 3 potential Auxiliary Operators have been selected to perform the isolation All 3 operators have the same lifetime cumulative dose Data for the Auxiliary Operators able to do the work is:

o Operator #1 - 50 years old male o Operator #2 - 25 year old female o Operator #3 - 40 year old male INITIATING CUE:

You are the Emergency Coordinator Determine the following:

o Which Auxiliary Operator will be selected for the evolution?

o If the Auxiliary Operator is sent into the Auxiliary Building at 1200, when will Emergency Coordinator authorization be required to continue work per EP-0905, Protective Actions Section 6.7?

o What is the required radiological posting for the room in which the task will be performed? (i.e., Radiation Area, High Radiation Area, Very High Radiation Area, or Locked High Radiation Area)

Selected Auxiliary Operator: Operator # 1 / Operator # 2 / Operator # 3 Time Emergency Coordinator authorization required: __________________

Radiological Posting: ________________

EXAMINEE

2020 PVNGS NRC Initial Exam JPM A5 JPM INFORMATION TASK: 1290240302 - Classify an event in accordance with the Emergency Plan TASK STANDARD: Classified FS1.1 within 15 minutes K/A: G 2.4.41 RATING: RO: 2.9 SRO: 4.4 POSITION(S): SRO VALIDATION TIME: 15 minutes EP-0901, Classifications

REFERENCES:

EAL Hot Chart LOCATION: SIMULATOR PLANT CLASSROOM X TIME CRITICAL: YES ALTERNATE PATH: NO PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: Brian Garrettson DATE: 7/22/2020 VALIDATED BY: Brian Garrettson DATE: 7/31/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a PVAR to be written, remediation, and re-evaluation. PVAR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM A5 PROCEDURES/MATERIALS:

EP-0901, Classifications EAL Hot Chart This JPM was written using Revision 13 of EP-0901, Classifications. This JPM may be used with later revisions if it is verified that the later revision does not affect the Steps/Standards of the JPM.

INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Unit 1 was tripped due to a Large Break LOCA SIAS/CIAS/MSIS/CSAS have actuated Containment pressure is 12 psig and rising A CS pump tripped Containment spray flow is 4500 gpm Containment Hydrogen concentration is 5.0% and rising Both Steam Generators are being fed with AFB-P01 RU-148 is 7.0E+04 mR/hr RU-149 is 8.0E+04 mR/hr RVLMS indicates 0% in the plenum INITIATING CUE:

Classify the event in progress in progress THIS IS A TIME CRITICAL JPM

2020 PVNGS NRC Initial Exam JPM A5 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM A5 JPM START TIME:

JPM Step: 1

Classify the event in accordance with EP-0901, Classification and the EAL Hot Chart Standard: Classified FS1.1 within 15 minutes Time Start:_________

Time Stop:__________

Answer Explanation:

Fuel Clad Barrier Potential Loss - RVLMS < 21% plenum RCS Barrier Loss - An automatic or manual ECCS (SIAS) actuation required by an unisolable RCS Leak Containment Barrier Potential Loss - Containment Hydrogen Concentration

> 4.9%

Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM A5 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 7/22/20 6 Created JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM A5 EXAMINEE INITIAL CONDITIONS:

Unit 1 was tripped due to a Large Break LOCA SIAS/CIAS/MSIS/CSAS have actuated Containment pressure is 12 psig and rising A CS pump tripped Containment spray flow is 4500 gpm Containment Hydrogen concentration is 5.0% and rising Both Steam Generators are being fed with AFB-P01 RU-148 is 7.0E+04 mR/hr RU-149 is 8.0E+04 mR/hr RVLMS indicates 0% in the plenum INITIATING CUE:

Classify the event in progress THIS IS A TIME CRITICAL JPM Classification: ______________________

EXAMINEE

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 Facility: PVNGS Date of Examination: 11/30/20 Exam Level: SRO-I Operating Test No.: 2020 NRC Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1 (029 EA1.12) ECC Directed Turbine Unloading - ATWS A, D, S 1 S2 (006 A3.08) Verify Recirculation Actuation Signal actuation A, D, EN, L, S 2 S3 (009 EA1.09) Isolate High Pressure Seal Cooler Leak A, L, N, S 3 S4 (035 A2.01) Appendix 33, SG 1 Level Reduction Checklist A, D, L, S 4P S5 (E06 EA1.1) Appendix 44, Feeding With the Condensate Pumps L, N, S 4S S6 (058 AA2.03) Respond to a Loss of Class Control Power during A, N, S 6 EDG Load Run S7 (012 A2.02) Set CEAC inoperability flags in the Core Protection N, S 7 Calculators following a Loss of Instrument Bus Power In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P1 (064 A1.03) Manual Control of EDG Jacket Water Temperature A, N 6 P2 (068 AA1.01) Operate ADVs at the RSD Panel D, E 4S P3 (033 A2.02) Leak in Fuel Pool Cooling Heat Exchanger, Swap N, R 8 Fuel Pool Cooling Heat Exchangers 1 of 3 2020 PVNGS NRC Initial Exam ES-301-2 SRO JPM Outline Rev 0

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for SRO-I (A)lternate path 4-6 (6)

(C)ontrol room (D)irect from bank 8 (4)

(E)mergency or abnormal in-plant 1 (1)

(EN)gineered safety feature 1 (control room system) (1)

(L)ow Power / Shutdown 1 (4)

(N)ew or (M)odified from bank including 1(A) 2 (6 - 3A)

(P)revious 2 exams 3 (randomly selected) (0)

(R)CA 1 (1)

(S)imulator NRC JPM Examination Summary Description S1 The applicant will be directed to perform a 100MW turbine load reduction per 40AO-9ZZ25, ECC Directed Turbine Unloading, Appendix A, Load Reduction. During the load reduction, the Main Turbine will trip and a RPCB signal will automatically occur. On the RPCB, one Subgroup of CEAs will fail to insert resulting in an automatic Reactor Trip signal. The Reactor will fail to automatically trip, requiring the applicant to recognize the ATWS condition and take action to manually trip the Reactor. This is a time-critical, alternate path, modified JPM covered by Safety Function 1.

S2 The applicant will be directed to perform 40EP-9EO03, LOCA, step 58, verification of RAS actuation. The applicant will determine that not all RAS actuated equipment automatically aligned to their actuated position and will take contingency actions in response to this condition. The applicant will have to identify the Train B ESF pump suction valve from containment, SIB-UV-675, did not open and stop the Train B HPSI and Train B CS Pumps. This is a time critical, alternate path, bank JPM covered by Safety Function 2.

S3 The applicant will be directed to perform 40EP-9EO03, LOCA, step 10, isolation of a High Pressure Seal Cooler (HPSC) Leak. The applicant will stop all four RCPs, close the NC Containment Isolation Valves, isolate Controlled Bleedoff from the RCPs, direct an area operator to energize the HPSC Isolation Valves for the affected HPSC, then close the associated HPSC Isolation Valves from the Control Room. The applicant will determine that one the Controlled Bleedoff isolation valve for the affected RCP failed to close and will isolate bleedoff by closing the upstream isolation valves and the bleedoff relief valve isolation valve. This is an alternate path, bank JPM covered by Safety Function 3.

2 of 3 2020 PVNGS NRC Initial Exam ES-301-2 SRO JPM Outline Rev 0

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 S4 The applicant will be directed to perform Appendix 33, SG 1 Level Reduction Checklist to control SG 1 level following a SG Tube Rupture. The applicant will take action to place High Rate SG Blowdown in service to the Condenser by operating valves from the Control Room and lower SG #1 level. However one of valves that must be opened must be bypassed in the field prior to operating in the Control Room to prevent severe water hammer and potential pipe damage locally in the field. This is an alternate path, bank JPM covered by Safety Function 4P. This JPM is directly related to PVNGS operating experience related to industrial safety.

S5 The applicant will be directed to perform Appendix 44, Feeding With the Condensate Pumps. The applicant will establish a flow path for feed directly from the Condensate Pumps and perform a controlled depressurization of the SG to re-establish feed flow.

This is a new JPM covering Safety Function 4S.

S6 The applicant will be directed to reduce load on the A EDG and disconnect the A EDG from PBA-S03 following a EDG load run. When the applicant commences the load reduction, PKA-M41, Train A Class DC Control Power Bus, will de-energize due to a fault. This will result in the A EDG tripping however the EDG output breaker will remain closed due to the loss of control power. The applicant will diagnose the failure and direct an area operator to locally open the A EDG output breaker to prevent damage to the A EDG. This is an alternate path, new JPM covered by Safety Function 6.

S7 The applicant will be directed to set INOP flags for CEAC 2 in the Core Protection Calculators following a loss of power to PNC-D27 per 40AO-9ZZ13, Loss of Class Instrument or Control Power. The applicant will locate the correct CPC point ID, set the Function Enable keyswitch to ENABLED, and set a value of 2 in each CPC module.

This is a new JPM covered by Safety Function 7.

P1 The applicant will be directed to take manual control of Train A EDG Jacket Water temperature per 40OP-9DG01, Emergency Diesel Generator A Section 6.11.5. Once taking manual control the applicant will recognize that temperature is lowering and must start the Jacket Water Circ Pump and ensure that Jacket Water Warmup Heater is in auto. This is an alternate path, new JPM covered by Safety Function 6.

P2 The applicant will be directed to perform ADV operations per 40AO-9ZZ18, Shutdown Outside the Control Room, Appendix D, ADV Operation to stabilize temperature after the CR was evacuated due to hot particle contamination. The applicant will take Local control of ADVs at the Remote Shutdown Panel and stabilize RCS temperature. This a bank JPM covered by Safety Function 4S.

P3 The applicant will be directed to swap Spent Fuel Pool heat exchangers due to a leak on the in-service heat exchanger per 40OP-9PC01, Fuel Pool Cooling. The applicant will perform a valve lineup to place the B Fuel Pool heat exchanger in service and remove the A Fuel Pool heat exchanger from service. This a new JPM covered by Safety Function 8.

3 of 3 2020 PVNGS NRC Initial Exam ES-301-2 SRO JPM Outline Rev 0

2020 PVNGS NRC Initial Exam JPM P1 JPM INFORMATION TASK: 489751 - Perform System Alignments Performed procedure for taking EDG Jacket Water Cooling to Manual. Determined that Jacket Water temperature is 123°F and lowering by taking DGN-TI-25, TASK STANDARD:

Temperature Indication to position 6, and simulated starting the DG A Jacket Water Circ Pump.

K/A: 064 A1.04 RATING: RO: 2.8 SRO: 2.9 POSITION(S): RO / SRO VALIDATION TIME: 10 minutes

REFERENCES:

40OP-9DG01, Emergency Diesel Generator A LOCATION: SIMULATOR PLANT X CLASSROOM TIME CRITICAL: NO ALTERNATE PATH: YES PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: Brian Garrettson DATE: 08/31/2020 VALIDATED BY: Brian Garrettson DATE: 09/03/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM P1 PROCEDURES/MATERIALS:

40OP-9DG01, Emergency Diesel Generator A This JPM was written using Revision 80. This JPM may be performed using future revisions of 40OP-9DG01, Emergency Diesel Generator A, provided the steps of the JPM are unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

IN-PLANT JPMS ONLY:

Operation of in-plant equipment is to be SIMULATED ONLY. DO NOT operate any equipment.

Notify the Shift Manager when in-plant JPMs are being performed.

Inform the Control Room staff of any discovered deficiencies Comply with the REP. If it is not possible to enter an area it may be permissible to discuss the equipment and operation with evaluator. DO NOT enter Contaminated Areas or High Radiation Areas.

INITIAL CONDITIONS:

A EDG is in standby Automatic control of jacket water temperature is not working INITIATING CUE:

CRS has directed performing 40OP-9DG01, Emergency Diesel Generator A, step 6.11.5 Manual Control of Temperature

2020 PVNGS NRC Initial Exam JPM P1 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM P1 JPM START TIME:

JPM Step: 1 Ensure Train A Diesel Generator is in Standby Standard: Determined from the initiating cue that the A EDG is in standby Comments (required for UNSAT):

SAT UNSAT JPM Step: 2 Ensure BOTH of the following handswitches are aligned as follows:

DGA-HS-27, DG A J.W. Warmup Heater, is placed to AUTO DGA-HS-21, DG A Jacket Water Circ Pump is placed in AUTO/STOP Standard: Checked the following handswitches are in the following alignment:

DGA-HS-27, DG A J.W. Warmup Heater is in AUTO Examiner Cue: When the examinee checks DGA-HS-27, DG A J.W. Warmup Heater is in AUTO:

The switch is in the right position Comments (required for UNSAT):

SAT UNSAT JPM Step: 3 Ensure BOTH of the following handswitches are aligned as follows:

DGA-HS-27, DG A J.W. Warmup Heater, is placed to AUTO DGA-HS-21, DG A Jacket Water Circ Pump is placed in AUTO/STOP Standard: Checked the following handswitches are in the following alignment:

DGA-HS-21, DG A Jacket Water Circ Pump is in AUTO/STOP Examiner Cue: When the examinee checks DGA-HS-21, DG A Jacket Water Circ Pump is in AUTO/STOP:

The switch is in the left position, green light is ON, red light is OFF Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM P1 JPM Step: 4 Ensure BOTH of the following MCC Breakers are closed:

PHA-M3325, Ckt Bkr for A DG Jacket Water Circ Pump DGA-P01 PHA-3109, Ckt Bkr for A DG Jacket Water Heater DGA-M01 Standard: Checked the following MCC breakers are closed:

PHA-M3325, Ckt Bkr for A DG Jacket Water Circ Pump DGA-P01 Examiner Cue: When the examinee checks PHA-M3325, Ckt Bkr for A DG Jacket Water Circ Pump DGA-P01 closed, inform them:

The Aux Building Operator is standing by at PHA-M33 When the examinee contacts the Aux Building Operator to check the status of PHA-M3325, inform them:

PHA-M3325, A DG Jacket Water Circ Pump DGA-P01 breaker is closed Comments (required for UNSAT):

SAT UNSAT JPM Step: 5 Ensure BOTH of the following MCC Breakers are closed:

PHA-M3325, Ckt Bkr for A DG Jacket Water Circ Pump DGA-P01 PHA-3109, Ckt Bkr for A DG Jacket Water Heater DGA-M01 Standard: Checked the following MCC breakers are closed:

PHA-3109, Ckt Bkr for A DG Jacket Water Heater DGA-M01 Examiner Cue: When the examinee checks PHA-3109, Ckt Bkr for A DG Jacket Water Heater DGA-M01 closed:

The breaker switch is in the vertical position Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM P1 Examiner Note: The following steps represent the alternate path portion of the JPM JPM Step: 6

If BOTH of the following:

DGN-TI-25, Temperature Indication, Position 6, Jacket Water temperature, is approaching 170°F DGN-TI-25, Temperature Indication, Position 6, Jacket Water temperature, is rising THEN place DGA-HS-27, DG A J.W. Warmup Heater to OFF Standard: Simulated placing DGN-TI-25, Temperature Indication to position 6, Jacket Water temperature and determined that Jacket Water Temperature is lowering and no action is required for approaching 170°F Examiner Cue: When the examinee simulates placing DGN-TI-25 to position 6, use a pointer device to show that temperature is 123°F and lowering Comments (required for UNSAT):

SAT UNSAT JPM Step: 7

If BOTH of the following:

DGN-TI-25, Temperature Indication, Position 6, Jacket Water temperature, is approaching 120°F DGN-TI-25, Temperature Indication, Position 6, Jacket Water temperature, is falling Standard: Determined that temperature is approaching 120°F from the previous step Examiner Cue: When the examinee simulates placing DGN-TI-25 to position 6, use a pointer device to show that temperature is 123°F and lowering Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM P1 JPM Step: 8

THEN perform the following:

Place DGA-HS-21, DG A Jacket Water Circ Pump, to START Standard: Placed DGA-HS-21, DG A Jacket Water Circ Pump, to START Examiner Cue: When the examinee simulates placing DGA-HS-21, DG A Jacket Water Circ Pump, to START:

The switch is in the right position, red light is ON, green light is OFF Inform the examinee that ANY SWITCH NOT IN AUTO alarm is in on the annunciator panel Comments (required for UNSAT):

SAT UNSAT JPM Step: 9 THEN perform the following:

Ensure DGA-HS-27, DG A J.W. Warmup Heater, is placed to AUTO Standard: Checked DGA-HS-27 DG A J.W. Warmup Heater is in AUTO Examiner Cue: When the examinee checks DGA-HS-27, DG A J.W. Warmup Heater is in AUTO:

Examiner Note: The heater will automatically energize at 120°F The switch is in the right position, green light is ON, red light is OFF.

This JPM is complete Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM P1 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 000 08/31/2020 6 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM P1 EXAMINEE INITIAL CONDITIONS:

A EDG is in standby Automatic control of jacket water temperature is not working INITIATING CUE:

CRS has directed performing 40OP-9DG01, Emergency Diesel Generator A, step 6.11.5 Manual Control of Temperature EXAMINEE

2020 PVNGS NRC Initial Exam JPM P2 JPM INFORMATION 1250270101 - Respond to an event requiring entry into the Shutdown Outside the TASK:

Control Room AOP Performed procedure for transferring and controlling SG pressure from the RSD panel.

Simulated placing switches to OPEN PERM, simulated pressing the LOCAL TASK STANDARD: pushbutton on the ADV Controller(s), simulated adjusting the position demand to at least 30% to open the valve, and observed the ADV open to 30% and SG pressure lowering K/A: 068 AK3.06 RATING: RO: 3.9 SRO: 4.3 POSITION(S): RO / SRO VALIDATION TIME: 10 minutes

REFERENCES:

40AO-9ZZ18, Shutdown Outside Control Room LOCATION: SIMULATOR PLANT X CLASSROOM TIME CRITICAL: NO ALTERNATE PATH: NO PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: Brian Garrettson DATE: 08/20/2020 VALIDATED BY: Brian Garrettson DATE: 09/03/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM P2 PROCEDURES/MATERIALS:

40AO-9ZZ18, Shutdown Outside Control Room This JPM was written using Revision 21. This JPM may be performed using future revisions of 40AO-9ZZ18, Shutdown Outside Control Room provided the steps of the JPM are unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

IN-PLANT JPMS ONLY:

Operation of in-plant equipment is to be SIMULATED ONLY. DO NOT operate any equipment.

Notify the Shift Manager when in-plant JPMs are being performed.

Inform the Control Room staff of any discovered deficiencies Comply with the REP. If it is not possible to enter an area it may be permissible to discuss the equipment and operation with evaluator. DO NOT enter Contaminated Areas or High Radiation Areas.

INITIAL CONDITIONS:

The Control Room has been evacuated due to hot particle contamination The SBCS was not controlling in automatic and an MSIS was initiated Pressure in both Steam Generators is 1205 psig and slowly rising INITIATING CUE:

CRS has directed you to operate ADVs on the Train A remote shutdown panel to control SG pressures within a band of 1140 - 1200 psia per 40AO-9ZZ18, Shutdown Outside Control Room, Appendix D, ADV Operations

2020 PVNGS NRC Initial Exam JPM P2 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM P2 JPM START TIME:

JPM Step: 1 Ensure the output of the ADV Controller(s) that will be used is at minimum:

SGA-HIC-179B SGA-HIC-184B SGB-HIC-178B SGB-HIC-185B Standard: Determined that the output of the ADV Controller(s) that will be used were at minimum Examiner Cue: When the examinee checks the outputs of the Train A ADV Controllers, use a pointer device to show that the output signal is 0 Comments (required for UNSAT):

SAT UNSAT JPM Step: 2

IF SGA-HV-179 will be operated, THEN place BOTH of the following switches to OPEN PERM SGA-HS-179C SGC-HS-179D Standard: Simulated placing switches to OPEN PERM Examiner Cue: When the examinee simulates operating both switches to the OPEN PERM position, inform them for each switch manipulation:

Green light OFF, red light ON Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM P2 JPM Step: 3

IF SGA-HV-184 will be operated, THEN place BOTH of the following switches to OPEN PERM SGA-HS-184C SGC-HS-184D Standard: Simulated placing switches to OPEN PERM Examiner Cue: When the examinee simulates operating both switches to the OPEN PERM position, inform them for each switch manipulation:

Green light OFF, red light ON Comments (required for UNSAT):

SAT UNSAT JPM Step: 4 IF SGB-HV-178 will be operated, THEN place BOTH of the following switches to OPEN PERM SGB-HS-178C SGD-HS-178D Standard: Determined step is N/A Comments (required for UNSAT):

SAT UNSAT JPM Step: 5 IF SGB-HV-185 will be operated, THEN place BOTH of the following switches to OPEN PERM SGB-HS-185C SGD-HS-185D Standard: Determined this step is N/A Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM P2 JPM Step: 6

Perform the following for the ADV(s) to be operated:

Press the LOCAL pushbutton on the ADV Controller(s)

Standard: Simulated pressing the LOCAL pushbutton on the ADV Controller(s).

Examiner Cue: When the examinee presses the LOCAL pushbutton for each controller, inform them:

The CR white light is OFF, the LOCAL white light is ON Comments (required for UNSAT):

SAT UNSAT JPM Step: 7

Perform the following for the ADV(s) to be operated:

Adjust the position demand to at least 30%

Standard: Simulated adjusting the position demand to at least 30% to open the valve Examiner Cue: Using a pointer device, indicate that the position demand signal is at 30%

for each controller and inform them:

The green and red lights are BOTH lit for each of the ADVs Comments (required for UNSAT):

SAT UNSAT JPM Step: 8 Perform the following for the ADV(s) to be operated:

WHEN the ADV opens, THEN adjust valve position as needed to control RCS heat removal rate Standard: Observed the ADVs open to 30% and SG pressure lowering Examiner Cue: Once each ADV opens to 30%, SG pressures will start to lower and further adjustments are not needed. After indicating the ADVs are at 30%, inform them:

This JPM is complete Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM P2 JPM STOP TIME:

RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 001 08/27/08 3, 6 Revision 6 of 40AO-9ZZ18 Appendix D, enhanced Initiating CUE, and new JPM 002 08/20/20 6 Minor changes to Initiating Cue and Examiner Cues.

Used for the 2020 NRC Exam REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM P2 EXAMINEE INITIAL CONDITIONS:

The Control Room has been evacuated due to hot particle contamination The SBCS was not controlling in automatic and an MSIS was initiated Pressure in both Steam Generators is 1205 psig and slowly rising INITIATING CUE:

CRS has directed you to operate ADVs on the Train A remote shutdown panel to control SG pressures within a band of 1140 - 1200 psia per 40AO-9ZZ18, Shutdown Outside Control Room, Appendix D, ADV Operations EXAMINEE

2020 PVNGS NRC Initial Exam JPM P3 JPM INFORMATION TASK: 1250530301 - Respond to a loss of Spent Fuel Pool level Performed procedure for placing the B SFP Cooling HX in service. Simulated closing PCB-V018, Train B Fuel Pool Cooling Pump Discharge Valve, simulated opening PCE-028, Fuel Pool Cooling Trains Cross-tie Valve, simulated closing PCA-V027, TASK STANDARD:

Train A Fuel Pool Cooling Heat Exchanger Outlet Valve, Simulated throttling PCA-V014, PCA-P01 Discharge Valve, to maintain between 45 psig and 55 psig as read on PCN-PI-009, Fuel Pool Cool Pump 1 Dischg Local Panel K/A: 033 A2.03 RATING: RO: 3.1 SRO: 3.5 POSITION(S): RO / SRO VALIDATION TIME: 12 minutes

REFERENCES:

40OP-9PC01, Fuel Pool Cooling LOCATION: SIMULATOR PLANT X CLASSROOM TIME CRITICAL: NO ALTERNATE PATH: NO PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: Brian Garrettson DATE: 08/25/2020 VALIDATED BY: Brian Garrettson DATE: 09/03/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM P3 PROCEDURES/MATERIALS:

40OP-9PC01, Fuel Pool Cooling This JPM was written using Revision 16. This JPM may be performed using future revisions of 40OP-9PC01, Fuel Pool Cooling provided the steps of the JPM are unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

IN-PLANT JPMS ONLY:

Operation of in-plant equipment is to be SIMULATED ONLY. DO NOT operate any equipment.

Notify the Shift Manager when in-plant JPMs are being performed.

Inform the Control Room staff of any discovered deficiencies Comply with the REP. If it is not possible to enter an area it may be permissible to discuss the equipment and operation with evaluator. DO NOT enter Contaminated Areas or High Radiation Areas.

INITIAL CONDITIONS:

There is an ISOLABLE leak on the in service A Fuel Pool Heat Exchanger The A Fuel Pool Cooling Pump is in service Spent Fuel Pool temperature is 110°F and slowly rising at a rate of 1°F/20 minutes INITIATING CUE:

The CRS directs you to perform 40OP-9PC01, Fuel Pool Cooling Section 6.7, Swapping From Fuel Pool HX A to HX B With Fuel Pool Cooling Pump A In Service to isolate the leak Steps 6.7.1 - 6.7.4 are complete There is an operator stationed at PCN-PI-009, Fuel Pool Cool Pump 1 Discharge Local Panel with a radio when PCA-P01 Discharge Valve is throttled for pressure indication

2020 PVNGS NRC Initial Exam JPM P3 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM P3 JPM START TIME:

JPM Step: 1 Check PCB-P01, Fuel Pool Cooling Pump B, not running per Section 6.17.6, Checking PCB-P01, Fuel Pool Cooling Pump B, Not running Standard: Determined from the intial conditions that PCB-P01 is powered from its normal source PGB-L36 52-C4 and checked that PCB-HS-8, Fuel Pool Cooling Pump 2, is in Stop Examiner Cue: When the examinee checks PCB-HS-8, Fuel Pool Cooling Pump 2, is in STOP, inform them:

The switch is in the vertical position, green light is ON, red light is OFF Comments (required for UNSAT):

SAT UNSAT JPM Step: 2

Close PCB-V018, Train B Fuel Pool Cooling Pump Discharge Valve Standard: Simulated closing PCB-V018, Train B Fuel Pool Cooling Pump Discharge Valve Examiner Cue: When the examinee simulates closing PCB-V018, Train B Fuel Pool Cooling Pump Discharge Valve, inform them:

The valve handwheel is in the full clockwise position, the valve stem is fully inserted Comments (required for UNSAT):

SAT UNSAT JPM Step: 3

Open PCE-028, Fuel Pool Cooling Trains Cross-tie Valve Procedure Note: Control the opening of PCE-V028 to avoid rapid pressure equalization Standard: Simulated opening PCE-028, Fuel Pool Cooling Trains Cross-tie Valve Examiner Cue: When the examinee simulates closing PCE-028, Fuel Pool Cooling Trains Cross-tie Valve:

The valve handwheel is in the full counter-clockwise position, the valve stem is fully withdrawn Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM P3 JPM Step: 4

Close PCA-V027, Train A Fuel Pool Cooling Heat Exchanger Outlet Valve Standard: Simulated closing PCA-V027, Train A Fuel Pool Cooling Heat Exchanger Outlet Valve Examiner Cue: When the examinee simulates closing PCA-V027, Train A Fuel Pool Cooling Heat Exchanger Outlet Valve:

The valve handwheel is in the full clockwise position, the valve stem is fully inserted Comments (required for UNSAT):

SAT UNSAT JPM Step: 5 IF Fuel Pool temperature is in excess of 145°F, THEN perform the following Review Limitation Step 3.2.4 Consider additional cooling by placing Shutdown Cooling in service per 40OP-9PC05, Augmentation of Fuel Pool Cooling With Shutdown Cooling Standard: Determined that the step is N/A Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM P3 JPM Step: 6

Throttle PCA-V014, PCA-P01 Discharge Valve, to maintain between 45 psig and 55 psig as read on PCN-PI-009, Fuel Pool Cool Pump 1 Dischg Local Panel Standard: Simulated throttling PCA-V014, PCA-P01 Discharge Valve, to maintain between 45 psig and 55 psig as read on PCN-PI-009, Fuel Pool Cool Pump 1 Dischg Local Panel Examiner Cue: The examinee will contact the operator at PCN-PI-009 when they are ready to throttle the discharge valve. When contacted, inform them:

PCN-PI-009, Fuel Pool Cooling Pump Discharge pressure indicates 40 psig When the examinee simulates throttling PCA-V014, PCA-P01 Discharge Valve in the CLOSE direction, inform them:

PCN-PI-009, Fuel Pool Cooling Pump Discharge pressure indicates 50 psig If the examinee stops throttling once pressure is 50 psig, inform them:

This JPM is complete Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM P3 JPM STOP TIME:

RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 000 08/25/2020 6 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM P3 EXAMINEE INITIAL CONDITIONS:

There is an ISOLABLE leak on the in service A Fuel Pool Heat Exchanger The A Fuel Pool Cooling Pump is in service Spent Fuel Pool temperature is 110°F and slowly rising at a rate of 1°F/20 minutes INITIATING CUE:

The CRS directs you to perform 40OP-9PC01, Fuel Pool Cooling Section 6.7, Swapping From Fuel Pool HX A to HX B With Fuel Pool Cooling Pump A In Service to isolate the leak Steps 6.7.1 - 6.7.4 are complete There is an operator stationed at PCN-PI-009, Fuel Pool Cool Pump 1 Discharge Local Panel with a radio when PCA-P01 Discharge Valve is throttled for pressure indication EXAMINEE

2020 PVNGS NRC Initial Exam JPM S1 JPM INFORMATION 1250800201 - Respond to an event requiring entry into the ECC Directed Turbine TASK:

Loading AOP Removed CEDMCS from Auto Sequential, lowered the local auto setpoint to ~ 20 psi above actual indicated pressure, placed SGN-PIC-1010 in LOCAL/AUTO, inserted a TASK STANDARD: Manual Permissive signal on SBCS Valves 1001 and 1004, and commenced the turbine unloading using the Load Set Potentiometer within 11 minutes of the start of the JPM, and tripped the Reactor within 2 minutes of the Main Turbine trip K/A: 029 EA1.12 RATING: RO: 4.1 SRO: 4.0 POSITION(S): RO / SRO VALIDATION TIME: 10 minutes

REFERENCES:

40AO-9ZZ25, ECC Directed Turbine Unloading LOCATION: SIMULATOR X PLANT CLASSROOM TIME CRITICAL: YES ALTERNATE PATH: YES PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: John Rodgers DATE: 4/2/2020 VALIDATED BY: Brian Garrettson DATE: 8/6/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM S1 SIMULATOR SETUP:

IC: 20 SIMULATOR SCENARIO FILES, MALFUNCTIONS, REMOTE FUNCTIONS, ETC. FOR SETUP:

COMMAND DESCRIPTION mfRD03F CEA 89 Stuck mfTC13 k:1 Turbine Trip ATWS scenario Prevents auto trip and manual trip at B05 INSTRUCTIONS FOR SETUP:

Reset to IC-20 (or load JPM from IC-601 - if IC-601 is used, JPM setup steps are complete)

Insert the malfunctions listed above Place the Pressurizer in Boron Equalization using all pressurizer backup heaters REQUIRED CONDITIONS:

CEDMCS in Auto Sequential Pressurizer in boron equalization

2020 PVNGS NRC Initial Exam JPM S1 PROCEDURES/MATERIALS:

40AO-9ZZ25, ECC Directed Turbine Unloading This JPM was written using Revision 13 of ZZ25. This JPM may be performed using future revisions of 40AO-9ZZ25 provided the associated steps of the procedure remain unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power The ECC has directed PVNGS to reduce site MW loading by 100 MW The CRS has entered 40AO-9ZZ25, ECC Directed Turbine Unloading, and determined that Unit 1 will perform the 100 MW load reduction Appendix D, Initial Actions, has been completed INITIATING CUE:

The CRS directs you to reduce Main Turbine load by 100 MW per 40AO-9ZZ25, ECC Directed Turbine Unloading, Appendix A, Load Reduction 3 minutes have elapsed since the ECC directed the turbine unloading Steps 1-3 of Appendix A have been completed Start on step 4 THIS IS A TIME CRITICAL JPM

2020 PVNGS NRC Initial Exam JPM S1 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM S1 JPM START TIME:

JPM Step: 1 Record Main Generator Gross MW using ANY of the following:

ERFDADS/PMS point MAJ1 Any alternate point Standard: Recorded Main Generator Gross MW Comments (required for UNSAT):

SAT UNSAT JPM Step: 2 Record the position of the Load Limit Potentiometer Standard: Recorded the position of the Load Limit Potentiometer Comments (required for UNSAT):

SAT UNSAT JPM Step: 3

Ensure CEDMCS is NOT in Auto Sequential Standard: Placed CEDMCS Mode Select Switch in a position OTHER THAN Auto Sequential (AS)

Comments (required for UNSAT):

SAT UNSAT JPM Step: 4

Lower the Local Auto setpoint (black pen) on SGN-PIC-1010, SBCS Master, to 20 psi above the indicated actual pressure (red pen)

Standard: Lowered the Local Auto setpoint to ~ 20 psi above the indicated actual pressure using the controller thumbwheel Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S1 JPM Step: 5

Perform the following to place SGN-PIC-1010, SBCS Master Control, in Local Auto:

Place the controller in MANUAL Select the controller to LOCAL Place the controller in AUTO Standard: Placed SGN-PIC-1010 in MANUAL by depressing the MAN pushbutton, placed the controller in LOCAL by selecting the Remote/Local switch to L, and placed the controller back in AUTO by depressing the AUTO pushbutton Comments (required for UNSAT):

SAT UNSAT JPM Step: 6 Ensure no Auto Demand signals are present for any SBCVs Standard: Verified no Auto Demand signals are present for any SBCVs Comments (required for UNSAT):

SAT UNSAT JPM Step: 7

Give BOTH of the following a Manual Permissive:

SGN-PV-1001, Valve 1 SGN-PV-1004, Valve 4 Standard: Inserted a manual permissive on SGN-PV-1001 and 1004 by placing handswitches SGN-HS-1001 and SGN-HS-1004 to MANUAL Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S1 JPM Step: 8

Commence turbine unloading by the amount determined in Section 3.0, Step 5, using the Load Limit Set Potentiometer Standard: Commenced the turbine unloading by rotating the Load Limit Set Potentiometer in the counter-clockwise direction within 11 minutes of the start of the JPM Examiner Note: JPM Start Time: __________

Time Turbine Load Reduction Commenced: __________

Time Elapsed (must be 11 minutes): __________

Examiner Note: When the applicant commences the turbine load reduction, direct the driver to INITIATE KEY 1 Comments (required for UNSAT):

SAT UNSAT Examiner Note: The following step represents the alternate path portion of the JPM JPM Step: 9

Manually trip the Reactor in response to the multiple valid Reactor trip signals and failure of the Reactor to automatically trip Standard: Manually tripped the Reactor from the Control Room (by opening MG Set Feeder Breakers L03 and L10 on B01) within 2 minutes of the ATWS Time of ATWS: __________

Time of Reactor Trip: __________

Elapsed Time (must be 120 seconds): __________

Examiner Cue: When the applicant has tripped the Reactor, Another operator will perform Standard Post Trip Actions. This JPM is complete Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM S1 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 4/2/2020 6 JPM created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM S1 EXAMINEE INITIAL CONDITIONS:

Unit 1 is operating at 100% power The ECC has directed PVNGS to reduce site MW loading by 100 MW The CRS has entered 40AO-9ZZ25, ECC Directed Turbine Unloading, and determined that Unit 1 will perform the 100 MW load reduction Appendix D, Initial Actions, has been completed INITIATING CUE:

The CRS directs you to reduce Main Turbine load by 100 MW per 40AO-9ZZ25, ECC Directed Turbine Unloading, Appendix A, Load Reduction 3 minutes have elapsed since the ECC directed the turbine unloading Steps 1-3 of Appendix A have been completed Start on step 4 THIS IS A TIME CRITICAL JPM EXAMINEE

2020 PVNGS NRC Initial Exam JPM S2 JPM INFORMATION TASK: 1240040301 - Implement LOCA instructions and contingencies Stopped the HPSI and CS pumps on loop with failed containment sump suction valve, TASK STANDARD: closed CHA-HV-531 and CHB-HV-530 within 5 minutes of starting the JPM, and closed SIB-UV-667.

K/A: 006 A3.08 RATING: RO: 4.2 SRO: 4.3 POSITION(S): RO / SRO VALIDATION TIME: 7 minutes

REFERENCES:

40EP-9EO03, Loss of Coolant Accident LOCATION: SIMULATOR X PLANT CLASSROOM TIME CRITICAL: YES ALTERNATE PATH: YES PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: John Rodgers DATE: 8/15/2020 VALIDATED BY: Brian Garrettson DATE: 8/20/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM S2 SIMULATOR SETUP:

IC: 20 SIMULATOR SCENARIO FILES, MALFUNCTIONS, REMOTE FUNCTIONS, ETC. FOR SETUP:

COMMAND DESCRIPTION mfTH01A f:100 LOOP 1A LOCA - COLD LEG at 100% severity cmMVRH04SIBUV675_6 Mechanical seizure of Containment Sump Isolation Valve SIB-UV-675 cmMVSI01SIBUV667_5 Automatic close signal failure: HPSI Pump to RWT Iso Valve SIB-UV-667 INSTRUCTIONS FOR SETUP:

Reset to IC-20 (or load JPM from IC-602)

Insert a Large Break LOCA (mfTH01A f:100)

Insert a seizure of SIB-UV-675 in the closed position (cmMVRH04SIBUV675_6)

Insert a failure of SIB-UV-667 to auto close on the RAS (cmMVSI01SIBUV667_5)

Allow the reactor to automatically trip or manually trip the reactor Trip all 4 RCPs Allow Refueling Water Tank level to lower to Recirculation Actuation Signal (RAS) setpoint (9.4%)

o NOTE: You will receive a RAS in approximately 20-30 minutes.

When RAS initiates, GO TO FREEZE After the cue has been read, GO TO RUN REQUIRED CONDITIONS:

RAS actuated

2020 PVNGS NRC Initial Exam JPM S2 PROCEDURES/MATERIALS:

40OP-9EO03, LOCA This JPM was written using Revision 44 of 40EP-9EO03, LOCA. This JPM may be performed using future revisions of 40EP-9EO03 provided the associated steps of the procedure remain unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

A large break LOCA has occurred in Unit 1 The CRS has entered 40EP-9EO03, Loss of Coolant Accident A Recirculation Actuation Signal (RAS) has just actuated and Step 57 of 40EP-9EO03, Loss of Coolant Accident has just been completed INITIATING CUE:

The CRS has directed you to perform 40EP-9EO03, Loss of Coolant Accident, Step 58, a through d THIS IS A TIME CRITICAL JPM

2020 PVNGS NRC Initial Exam JPM S2 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM S2 JPM START TIME:

Examiner Note When the cue is read to the examinee, they have 5 minutes to complete JPM step 5 (close CHA-HV-531 and CHB-HV-530).

Start Time:____________

JPM Step: 1 IF a RAS has actuated, THEN perform the following:

Ensure that both LPSI Pumps are stopped Standard: Verified both LPSI pumps have stopped Comments (required for UNSAT):

SAT UNSAT Examiner Note: The following step represents the alternate path portion of the JPM.

JPM Step: 2 IF a RAS has actuated, THEN perform the following:

Ensure that the ESF pump suction has shifted to the containment Standard: Determined that the B ESF pump suction valves from containment did open with the exception of SIB-UV-675, and transitioned to contingency step 58.b.1 Examiner Note: The examinee should attempt to open SIB-UV-675 on B02, but the valve will not open. Failing to attempt to open SIB-UV-675 does NOT constitute a Critical Step failure Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S2 JPM Step: 3* IF any ESF pump suctions can NOT be shifted to the containment sump, THEN perform the following:

IF ANY HPSI Pump is running with its associated Containment suction closed, THEN stop the affected HPSI Pump.

Standard: Stopped HPSI pump B by taking the handswitch SIB-HS-2 on B02 to START to pick up the override, then to STOP to stop the pump Comments (required for UNSAT):

SAT UNSAT JPM Step: 4* IF any ESF pump suctions can NOT be shifted to the containment sump, THEN perform the following:

IF ANY CS Pump is running with its associated Containment suction closed, THEN stop the affected CS Pump Standard: Stopped CS pump B by taking the handswitch SIB-HS-6 on B02 to START to pick up the override, then to STOP to stop the pump Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S2 JPM Step: 5* Close BOTH of the following valves:

CHA-HV-531, RWT to Train A Safety Injection Valve CHB-HV-530, RWT to Train B Safety Injection Valve Standard: Closed both CHA-HV-531, and CHB-HV-530 within 5 minutes of the start of the JPM.

Time JPM start: _________

Time CHA-HV-531 and CHB-HV-530 closed: _________

Elapsed Time (must be 5 minutes): __________

Comments (required for UNSAT):

SAT UNSAT JPM Step: 6

Ensure ALL of the following valves are closed:

SIA-UV-666, HPSI A Pump Recirc Valve SIA-UV-664, Containment Spray Pump A Recirc Valve SIA-UV-669, LPSI Pump A Recirc Valve SIB-UV-667, HPSI B Pump Recirc Valve SIB-UV-665, CS Pump B Recirc Valve SIB-UV-668, LPSI Pump B Recirc Valve Standard: Closed SIB-UV-667 and ensured all of the other above valves are closed.

Examiner Cue When the examinee has ensured all the above valves are closed:

This JPM is complete.

Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM S2 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 01 4/18/2016 3 Changes to procedure numbering and order of actions in step 58; changes to JPM format.

02 8/15/2020 6 Updated JPM format, updated to rev 44 of LOCA REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM S2 EXAMINEE INITIAL CONDITIONS:

A large break LOCA has occurred in Unit 1 The CRS has entered 40EP-9EO03, Loss of Coolant Accident A Recirculation Actuation Signal (RAS) has just actuated and Step 57 of 40EP-9EO03, Loss of Coolant Accident has just been completed INITIATING CUE:

The CRS has directed you to perform 40EP-9EO03, Loss of Coolant Accident, Step 58, a through d THIS IS A TIME CRITICAL JPM EXAMINEE

2020 PVNGS NRC Initial Exam JPM S3 JPM INFORMATION TASK: 1250020401 - Respond to an RCS to NC Leak Stopped RCP 1A and 2A, closed NCB-UV-401, NCA-UV-402, and NCB-UV-403, isolated Controlled Bleedoff from all 4 RCPs using CHB-UV-505 or CHA-UV-506, TASK STANDARD:

and CHA-HV-507, and closed HP Seal Cooler Isolation Valves RCN-HV-447 and RCN-HV-451 K/A: 009 EA1.09 RATING: RO: 3.6 SRO: 3.6 POSITION(S): RO / SRO VALIDATION TIME: 5 minutes 40EP-9EO03, LOCA

REFERENCES:

Appendix 36, RCP HP Seal Cooler Breaker List LOCATION: SIMULATOR X PLANT CLASSROOM TIME CRITICAL: NO ALTERNATE PATH: YES PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: John Rodgers DATE: 8/15/2020 VALIDATED BY: Brian Garrettson DATE: 8/20/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM S3 SIMULATOR SETUP:

IC: 20 or any at power IC SIMULATOR SCENARIO FILES, MALFUNCTIONS, REMOTE FUNCTIONS, ETC. FOR SETUP:

COMMAND DESCRIPTION cmHXCV14RCEE05B_2 f:100 HPSC Leak on RCP 1B cmMVCV14RCEHV431_6 RCP 1B Controlled Bleedoff Valve FTC crB4CV14RCNHV447_1 f:CLOSE k:1 crB4CV14RCNHV451_1 f:CLOSE k:2 INSTRUCTIONS FOR SETUP:

Reset to IC-20 (or load JPM from IC-603 - if IC-603 is used, JPM setup steps are complete with the exception of the remote functions for 447 and 451)

Insert malfunctions listed above Manually trip the Reactor Manually initiate SIAS and CIAS Stop RCPs 1B and 2B REQUIRED CONDITIONS:

Ensure keys are removed from CHA-HS-507, RCN-HS-447, and RCN-HS-451 NOTE: The driver should pull up the remote functions for RCN-HV-447 and 451 in preparation for closing since remote functions will not snap in the IC

2020 PVNGS NRC Initial Exam JPM S3 PROCEDURES/MATERIALS:

40EP-9EO03, LOCA 40EP-9EO10-036, Appendix 36 - RCP HP Seal Cooler Breaker List This JPM was written using Revision 44 of 40EP-9EO03 and Revision 0 of 40EP-9EO10-036.

This JPM may be performed using future revisions of 40EP-9EO03 and 40EP-9EO10-036 provided the associated steps of the procedure remain unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Unit 1 spuriously tripped from 100% power During SPTAs, a HPSC leak developed on the 1B RCP SIAS and CIAS were manually actuated RCP 1B and RCP 2B have been stopped The CRS has entered 40EP-9EO03, LOCA NC Surge Tank Level high alarm is in INITIATING CUE:

The CRS directs you to perform 40EP-9EO03, LOCA, Step 10, a through e An AO is standing by in the field to energize the HP Seal Cooler Isolation Valves

2020 PVNGS NRC Initial Exam JPM S3 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM S3 JPM START TIME:

JPM Step: 1

Stop all RCPs Standard: Stopped the 1A and 2A RCPs using the RCP handswitches on B04 Comments (required for UNSAT):

SAT UNSAT JPM Step: 2

Close the Nuclear Cooling Water Containment Isolation Valves Standard: Closed NCB-UV-401, NCA-UV-402, and NCB-UV-403 at B07 Comments (required for UNSAT):

SAT UNSAT Examiner Note: The following step represents the alternate path portion of the JPM JPM Step: 3

Isolate controlled bleedoff from the RCPs Standard: Attempted to isolate controlled bleedoff by taking RCN-HS-430/431/432/433 to close, recognized that RCH-HS-431 failed to close, and isolated controlled bleedoff via alternate means by taking handswitches CHB-HS-505 or CHA-HS-506, and keyswitch CHA-HS-507 to close NOTE: When examinee recognizes that RCN-HS-431 failed to close the valve, it is not necessary to attempt to close RCN-HS-430/432/433. Any of those valves failing to close requires use of 505 or 506, and 507. Closing 505 or 506, and 507 is the critical portion of this step Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S3 JPM Step: 4

Energize the RCP HP Cooler Isolation Valves for ANY leaking RCP High Pressure Cooler(s). REFER TO Appendix 36, RCP HP Seal Cooler Breaker List Standard: Directed an AO to close the breakers for the 1B RCP HP Seal Cooler Isolation Valves, NHN-M1004 and NHN-M1005 Examiner Cue: When the AO is directed to close NHN-M1004 and NHN-M1005:

Direct the Driver to INITIATE KEY 1 and/or KEY 2 as appropriate, then report NHN-M1004 and NHN-M1005 are closed when the VPI is illuminated on B04 Comments (required for UNSAT):

SAT UNSAT JPM Step: 5

Close the RCP HP Cooler Isolation Valves for ANY leaking High Pressure Cooler(s)

Standard: Closed 1B RCP HP Seal Cooler Isolation Valves RCN-HV-447 and RCN-HV-451 Examiner Cue: When the examinee has closed RCN-HV-447 and RCN-HV-451:

Another operator will continue this procedure. This JPM is complete Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM S3 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 8/15/2020 6 JPM created 1 11/30/2020 6 Clarified the required valves needed to isolated Controlled Bleedoff in the task standard and JPM step 3.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM S3 EXAMINEE INITIAL CONDITIONS:

Unit 1 spuriously tripped from 100% power During SPTAs, a HPSC leak developed on the 1B RCP SIAS and CIAS were manually actuated RCP 1B and RCP 2B have been stopped The CRS has entered 40EP-9EO03, LOCA NC Surge Tank Level high alarm is in INITIATING CUE:

The CRS directs you to perform 40EP-9EO03, LOCA, Step 10, a through e An AO is standing by in the field to energize the HP Seal Cooler Isolation Valves EXAMINEE

2020 PVNGS NRC Initial Exam JPM S4 JPM INFORMATION TASK: 0010030401 - Perform a SG 1 (2) high rate blowdown to the main condenser Placed the Blowdown Path Selector to OFF, directed an AO to open the SG Blowdown Isolation Valve (500Q) bypass valves, opened SGB-UV-500Q, directed opening SCN-TASK STANDARD:

V088, SCN-V099, SCN-V071, and SCN-V072, placed the Blowdown Rate Selector in HIGH RATE, and commenced SG blowdown to the condenser K/A: 035 A2.01 RATING: RO: 4.5 SRO: 4.6 POSITION(S): RO / SRO VALIDATION TIME: 10 minutes

REFERENCES:

Appendix 33, Steam Generator 1 Level Reduction Checklist LOCATION: SIMULATOR X PLANT CLASSROOM TIME CRITICAL: NO ALTERNATE PATH: YES PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: John Rodgers DATE: 8/15/2020 VALIDATED BY: Brian Garrettson DATE: 8/20/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM S4 SIMULATOR SETUP:

IC: 20 SIMULATOR SCENARIO FILES, MALFUNCTIONS, REMOTE FUNCTIONS, ETC. FOR SETUP:

COMMAND DESCRIPTION IMF mfTH06A f:50 SG #1 Tube Rupture IRF rfWD29 f:OPEN IRF rfWD30 f:OPEN INSTRUCTIONS FOR SETUP:

Reset to IC-20 (or load JPM from IC-604)

Insert the above malfunctions/remote functions Close all Blowdown Containment Isolation Valves (500P, 500Q, 500R, and 500S)

Trip the reactor Initiate SIAS/CIAS Stop one RCP in each loop Lower Thot to < 540°F and isolate SG #1 per SA 113 Use Aux Feed to raise level in SG#1 to 70% NR When SG#1 level reaches 70%, modify mfTH06A to f:5 Acknowledge all alarms Go to FREEZE After the cue is read, go to RUN REQUIRED CONDITIONS:

SG #1 isolated SG #1 level ~ 70% NR

2020 PVNGS NRC Initial Exam JPM S4 PROCEDURES/MATERIALS:

40EP-9EO10-033, Appendix 33, SG 1 Level Reduction Checklist This JPM was written using Revision 1. This JPM may be performed using future revisions of 40EP-9EO10-033 provided the associated steps of the procedure remain unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Unit 1 was tripped due to a SGTR on SG #1 SG #1 has been isolated SG #1 NR level is approximately 70%

INITIATING CUE:

The CRS directs you to reduce SG #1 level to 50-55% Narrow Range using 40EP-EO10-033, Appendix 33, Steam Generator 1 Level Reduction Checklist

2020 PVNGS NRC Initial Exam JPM S4 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM S4 JPM START TIME:

JPM Step: 1

Place SCN-HS-1, SG 1 Blowdown Path Selector in OFF Standard: Placed SCN-HS-1 in OFF Comments (required for UNSAT):

SAT UNSAT JPM Step: 2 Ensure SGA-UV-500P, SG 1 Common Upstream Isolation, is open Standard: Overrode and opened SGA-UV-500P Comments (required for UNSAT):

SAT UNSAT JPM Step: 3 Ensure SGE-HV-47, SG 1 Downcomer Blowdown Isolation is closed Standard: Ensured SGE-HV-47 is closed Examiner Note: It takes ~ 2 minutes for this valve to close Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S4 JPM Step: 4 Ensure that ONE of the following valves is open:

SGE-HV-43, SG 1 Hot Leg Isolation SGE-HV-41, SG 1 Cold Leg Isolation Standard: Opened EITHER SGE-HV-43 or SGE-HV-41 Examiner Note: It takes ~ 2 minutes for these valves to open Examiner Cue: If the examinee asks the CRS which valve to use:

What do you recommend? and concur with whichever valve they recommend.

Comments (required for UNSAT):

SAT UNSAT Examiner Note: The following steps represent the alternate path portion of the JPM JPM Step: 5 Check that SGB-UV-500Q, SG 1 Common Downstream Isolation, is open Standard: Determined that SGB-UV-500Q is NOT open and proceeded to the contingency actions Examiner Note: Opening this valve prior to the bypass valves being opened is a safety hazard in the Turbine Building and constitutes failure of the JPM Comments (required for UNSAT):

SAT UNSAT JPM Step: 6

Perform the following to open SGB-UV-500Q:

Direct an operator to perform the following: (100' MSSS NW Corner) o Unlock and open SGE-V293, SGB-UV-500Q BYPASS HDR INLET ISOL VALVE.

Standard: Directed an operator to unlock and open SGE-V293 Examiner Cue: When directed to unlock and open SGE-V293, report:

SGE-V293 is unlocked and open.

Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S4 JPM Step: 7

Perform the following to open SGB-UV-500Q:

Direct an operator to perform the following: (100' MSSS NW Corner) o Open SGE-V267, SGB-UV-500Q BYPASS HDR OUTLET ISOL VALVE.

Standard: Directed an operator to open SGE-V267.

Examiner Cue: When directed to open SGE-V267, report:

SGE-V267 is open.

Comments (required for UNSAT):

SAT UNSAT JPM Step: 8

Perform the following to open SGB-UV-500Q:

Direct an operator to perform the following: (100' MSSS NW Corner) o Slowly open SGE-VA33, SGB-UV-500Q BYPASS HEADER THROTTLE VALVE.

Standard: Directed an operator to open SGE-VA33 Examiner Cue: When directed to unlock and open SGE-VA33, report:

SGE-VA33 is open.

Comments (required for UNSAT):

SAT UNSAT JPM Step: 9

Open SGB-UV-500Q, SG 1 Common Downstream Isolation Standard: Overrode and opened SGB-UV-500Q Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S4 JPM Step: 10 Direct an operator to close ALL of the following valves:

SGE-V293 SGE-V267 SGE-VA33 Standard: Directed an operator to close SGE-V293, V267, and VA33.

Examiner Cue: When directed to close SGE-V293, V267, and VA33, report:

SGE-V293, V267, and VA33 are all closed.

Comments (required for UNSAT):

SAT UNSAT JPM Step: 11

Direct an operator to open ALL of the following valves: (100' Turbine Bldg between Heater Drain Tanks)

SCN-V088, SCN-HV-018C OUTLET ISOLATION VALVE (S/G #1 HIGH RATE B/D TO CONDENSER)

Standard: Directed an operator to open SCN-V088 Examiner Cue: When directed to open SCN-V088, report:

SCN-V088 is open.

Comments (required for UNSAT):

SAT UNSAT JPM Step: 12

Direct an operator to open ALL of the following valves: (100' Turbine Bldg between Heater Drain Tanks)

SCN-V099, SCN-HV-018C INLET ISOLATION VALVE (S/G #1 HIGH RATE B/D TO CONDENSER)

Standard: Directed an operator to open SCN-V099 Examiner Cue: When directed to open SCN-V099, report:

SCN-V099 is open.

Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S4 JPM Step: 13

Direct an operator to open ALL of the following valves: (100' Turbine Bldg between Heater Drain Tanks)

SCN-V071, SCN-HV-018B OUTLET ISOLATION VALVE (S/G #1 ABNOR RATE B/D TO CONDENSER)

Standard: Directed an operator to open SCN-V071 Examiner Cue: When directed to open SCN-V071, report:

SCN-V071 is open.

Comments (required for UNSAT):

SAT UNSAT JPM Step: 14

Direct an operator to open ALL of the following valves: (100' Turbine Bldg between Heater Drain Tanks)

SCN-V072, SCN-HV-018B INLET ISOLATION VALVE (S/G #1 ABNOR RATE B/D TO CONDENSER)

Standard: Directed an operator to open SCN-V072 Examiner Cue: When directed to open SCN-V072, report:

SCN-V072 is open.

Comments (required for UNSAT):

SAT UNSAT JPM Step: 15

Place SCN-HS-18, SG 1 Blowdown Rate Selector, in HIGH RATE Standard: Placed SCN-HS-18 in HIGH RATE Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S4 JPM Step: 16

Maintain SG level by performing the following:

Place SCN-HS-1, SG 1 Blowdown Path Selector in COND WHEN SG 1 reaches the desired level, THEN place SCN-HS-1, SG 1 Blowdown Path Selector, in OFF Standard: Placed SCN-HS-1 in COND and monitors SG level.

Examiner Cue: Once level begins to lower in SG#1:

This JPM is complete.

Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM S4 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 4/14/09 6 New JPM 1 8/10/10 6 Revised for Audit 2 8/28/10 6 Changed JPM number 3 10/25/16 6 JPM Format Change 4 8/15/2020 6 Updated to current procedure rev REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM S4 EXAMINEE INITIAL CONDITIONS:

Unit 1 was tripped due to a SGTR on SG #1 SG #1 has been isolated SG #1 NR level is approximately 70%

INITIATING CUE:

The CRS directs you to reduce SG #1 level to 50-55% Narrow Range using 40EP-EO10-033, Appendix 33, Steam Generator 1 Level Reduction Checklist EXAMINEE

2020 PVNGS NRC Initial Exam JPM S5 JPM INFORMATION TASK: 1240024201 - Perform SA 44 Feeding with Condensate Pumps Fast closed all Economizer FWIVs, closed the SG #2 Downcomer Valves, fast closed TASK STANDARD: the SG #1 MSIVs, depressurized SG #1 using the ADV(s), and commenced feeding SG

1 using the Condensate Pump(s)

K/A: CE E06 EA1.1 RATING: RO: 4.0 SRO: 3.9 POSITION(S): RO / SRO VALIDATION TIME: 15 minutes

REFERENCES:

40EP-9EO10-044, Feeding With Condensate Pumps LOCATION: SIMULATOR X PLANT CLASSROOM TIME CRITICAL: NO ALTERNATE PATH: NO PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: John Rodgers DATE: 8/15/2020 VALIDATED BY: Brian Garrettson DATE: 8/20/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM S5 SIMULATOR SETUP:

IC: 20 SIMULATOR SCENARIO FILES, MALFUNCTIONS, REMOTE FUNCTIONS, ETC. FOR SETUP:

COMMAND DESCRIPTION AFN-P01 OOS Scenario Remove AFN-P01 from service mfFW22 AFA-P01 overspeed trip mfED11C LOP on PBB-S04 rfEG21 f:STOP Emergency Stop B EDG mfMC01A f:100 Degraded vacuum A shell mfMC01B f:100 Degraded vacuum B shell mfMC01C f:100 Degraded vacuum C shell Low SG and PZR pressure reset buttons Continuously reset MSIS and SIAS setpoints overridden to RESET INSTRUCTIONS FOR SETUP:

Reset to IC-20 (or load JPM from IC-605)

Insert the malfunctions listed above Hand OOS tags on AFN-P01 When the Reactor trips, stabilize the plant per SPTAs Emergency stop the B EDG Trip all 4 RCPs Close the SG Blowdown CIVs and all SG Sample Valves Start the E Charging Pump Operate Aux Spray as needed to maintain RCS pressure 2225-2275 psia REQUIRED CONDITIONS:

Malfunctions and remote functions listed above inserted Reactor tripped All RCPs stopped A and E Charging Pumps running RCS pressure 2225-2275 psia All SG Blowdown CIVs and SG Sample Valves closed Low SG pressure and low Pressurizer pressure RESET pushbuttons on B05 overridden to RESET

2020 PVNGS NRC Initial Exam JPM S5 PROCEDURES/MATERIALS:

40EP-9EO10-044, Feeding With Condensate Pumps This JPM was written using Revision 0. This JPM may be performed using future revisions of 40EP-9EO10-044 provided the associated steps of the procedure remain unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Unit 1 tripped due to a complete loss of vacuum AFN-P01 is OOS PBB-S04 is de-energized due to a bus fault The B EDG has been emergency stopped AFA-P01 tripped on overspeed and cannot be reset The CRS has transitioned to 40EP-9EO06, Loss of All Feedwater INITIATING CUE:

The CRS directs you to restore feed to SG #1 using SG Downcomer Control Valve, SGN-FV-1113, per Appendix 44, Feeding With The Condensate Pumps Another operator will lower MSIS and SIAS setpoints as needed, and another operator will perform Appendix 5, RCS and Pressurizer Cooldown Log, during the evolution

2020 PVNGS NRC Initial Exam JPM S5 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM S5 JPM START TIME:

JPM Step: 1 IF SG #1 was selected, THEN perform the following:

Ensure BOTH SG 1 Downcomer Isolation Valves are open:

o SGA-UV-172 o SGB-UV-130 Standard: Verified both SGA-UV-172 and SGB-UV-130 are open Comments (required for UNSAT):

SAT UNSAT JPM Step: 2 IF SG #1 was selected, THEN perform the following:

Place SG 1 Downcomer Control Valve in MANUAL and close SGN-FV-1113 Standard: Placed SGN-FV-1113 in MANUAL and lowered the output to zero to close the valve Comments (required for UNSAT):

SAT UNSAT JPM Step: 3 IF SG #1 was selected, THEN perform the following:

Ensure SGN-HV-1142, SG 1 Downcomer Block Valve, is open Standard: Verified SGN-HV-1142 is open Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S5 JPM Step: 4 IF SG #1 was selected, THEN perform the following:

Ensure SGN-HV-1143, SG 1 Downcomer Bypass Valve, is closed Standard: Verified SGN-FV-1143 is closed Comments (required for UNSAT):

SAT UNSAT JPM Step: 5

IF SG #1 was selected, THEN perform the following:

IF a MSIS has NOT occurred, THEN fast close ALL of the Economizer FWIVs:

o SG 1 SGA-UV-174 SGB-UV-132 o SG 2 SGA-UV-177 SGB-UV-137 Standard: Fast Closed SGA-UV-174, SGB-UV-132, SGA-UV-177, and SGB-UV-137 using the Economizer FWIV Fast Close pushbuttons on B06 Comments (required for UNSAT):

SAT UNSAT JPM Step: 6 IF SG #1 was selected, THEN perform the following:

IF using the Downcomer Bypass Valve to feed SG 1, THEN ensure SGN-HV-1142, SG 1 Downcomer Block Valve, is closed Standard: Marked step as N/A since the Downcomer Flow Control Valve will be used Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S5 JPM Step: 7

IF SG #1 was selected, THEN perform the following:

Ensure BOTH SG 2 Downcomer valves are closed:

o SGN-HV-1144, SG 2 Downcomer Block Valve o SGN-HV-1145, SG 2 Downcomer Bypass Valve Standard: Ensured SGN-HV-1144 and SGN-HV-1145 are closed Comments (required for UNSAT):

SAT UNSAT JPM Step: 8 IF SG #1 was selected, THEN perform the following:

GO TO Step 4 Standard: Proceeded to Step 4 Comments (required for UNSAT):

SAT UNSAT JPM Step: 9 (Step 4) Ensure at least ONE set of the following High Pressure Feedwater Heater isolation valves are open:

HP Heater Train A o FWN-HV-73 o FWN-HV-101 HP Heater Train B o FWN-HV-74 o FWN-HV-102 Standard: Verified one set of HP Heater Train valves are open Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S5 JPM Step: 10 Ensure BOTH of the FWPTs are tripped by using the following:

FTN-HS-51 for FWPT A FTN-HS-52 for FWPT B Standard: Ensured BOTH FWPTs are tripped (both pumps are already tripped, but the examinee may still depress the trip pushbuttons)

Comments (required for UNSAT):

SAT UNSAT JPM Step: 11 Check BOTH FWPT Miniflow Valves are closed from the Control Room:

FWN-FV-1 FWN-FV-2 Standard: Verified FWN-FV-1 and FWN-FV-2 are closed Comments (required for UNSAT):

SAT UNSAT JPM Step: 12 Ensure at least ONE of the FWPT Discharge Valves are open from the Control Room:

FWN-HV-31 FWN-HV-32 Standard: Verified FWN-HV-31 OR FWN-HV-32 is open Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S5 JPM Step: 13 Ensure at least ONE set of the following Low Pressure Feedwater Heater isolation valves are open:

LP Heater Train A o CDN-UV-214A o CDN-UV-214B LP Heater Train B o CDN-UV-215A o CDN-UV-215B LP Heater Train C o CDN-UV-216A o CDN-UV-216B Standard: Verified at least one set of LP Heater Train valves is open Comments (required for UNSAT):

SAT UNSAT JPM Step: 14 IF ANY Condensate Pumps are running, THEN GO TO Step 11 Standard: Proceeded to Step 11 Comments (required for UNSAT):

SAT UNSAT JPM Step: 15 (Step 11) IF RCS makeup is required, THEN perform the following:

Start all available charging pumps Minimize letdown flow Start one HPSI Pump Open at least one HPSI Injection Valve Standard: Checked pressurizer level to determine whether or not RCS makeup is required Examiner Cue: If examinee determines RCS makeup is desired and attempts to take action:

Another operator will maintain RCS inventory, continue with Appendix 44 Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S5 JPM Step: 16 IF a MSIS or SIAS has NOT initiated, THEN lower or bypass the automatic initiation setpoint(s) for MSIS or SIAS as the cooldown and depressurization continues Standard: Determined that another operator is responsible for lowering MSIS and SIAS setpoints from the initiating cue Comments (required for UNSAT):

SAT UNSAT JPM Step: 17 Perform Appendix 5, RCS and Pressurizer Cooldown Log Standard: Determined that another operator will perform Appendix 5 from the initiating cue Comments (required for UNSAT):

SAT UNSAT JPM Step: 18

IF SG 1 was selected, THEN perform the following:

Fast close SG 1 MSIVs by using the following pushbuttons:

o SGA-HS-251 o SGB-HS-253 Standard: Fast closed the SG #1 MSIVs by depressing SGA-HS-251 OR SGB-HS-253 Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S5 JPM Step: 19

IF SG 1 was selected, THEN perform the following:

Lower SG 1 pressure below the condensate pump discharge pressure using SG 1 ADVs Standard: Commenced lowering SG #1 pressure by opening at least one SG #1 ADV To open SGA-HIC-184A:

Placed SGA-HS-184A in OPEN PERM Placed SGC-HS-184B in OPEN PERM Raised output on SG1 Line 1 ADV using the thumbwheel on SGA-HIC-184A To open SGB-HIC-178A:

Placed SGB-HS-178A in OPEN PERM Placed SGD-HS-178B in OPEN PERM Raised output on SG1 Line 2 ADV using the thumbwheel on SGB-HIC-178A Comments (required for UNSAT):

SAT UNSAT JPM Step: 20 IF SG 1 was selected, THEN perform the following:

Maintain SG 2 pressure less than 1200 psia Standard: Verified SG #2 pressure remains less than 1200 psia (pressure is being maintained by SBCS valves 1007 and 1008 in automatic)

Comments (required for UNSAT):

SAT UNSAT JPM Step: 21 IF SG 1 was selected, THEN perform the following:

IF SG 1 is dry, THEN maintain feed flow rate of less than or equal to 1000 gpm Standard: Checked SG #1 level and determined SG #1 is NOT dry Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S5 Examiner Note: Feed flow will commence when SG #1 pressure is ~ 625 psia and SGN-FV-1113 has been throttled open JPM Step: 22

IF SG 1 was selected, THEN perform the following:

IF using SG 1 Downcomer Control Valve, THEN throttle open SGN-FV-1113 Standard: Throttled open SGN-FV-1113 to align a flowpath for the Condensate Pumps to inject into SG #1 Examiner Cue: When feed flow has been established to SG #1:

This JPM is complete Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM S5 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 8/15/2020 6 JPM created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM S5 EXAMINEE INITIAL CONDITIONS:

Unit 1 tripped due to a complete loss of vacuum AFN-P01 is OOS PBB-S04 is de-energized due to a bus fault The B EDG has been emergency stopped AFA-P01 tripped on overspeed and cannot be reset The CRS has transitioned to 40EP-9EO06, Loss of All Feedwater INITIATING CUE:

The CRS directs you to restore feed to SG #1 using SG Downcomer Control Valve, SGN-FV-1113, per Appendix 44, Feeding With The Condensate Pumps Another operator will lower MSIS and SIAS setpoints as needed, and another operator will perform Appendix 5, RCS and Pressurizer Cooldown Log, during the evolution EXAMINEE

2020 PVNGS NRC Initial Exam JPM S6 JPM INFORMATION TASK: 0650010501 - Remotely start, manually load and unload a diesel generator Commenced lowering EDG loading to 3.6-4.4 MW, stabilized the load reduction TASK STANDARD: between 3.6-4.4 MW, and directed an AO to locally open the A EDG Output Breaker within 5 minutes of the loss of PKA-M41 K/A: 058 AA2.03 RATING: RO: 3.5 SRO: 3.9 POSITION(S): RO / SRO VALIDATION TIME: 10 minutes

REFERENCES:

40OP-9DG01, Emergency Diesel Generator A LOCATION: SIMULATOR X PLANT CLASSROOM TIME CRITICAL: YES ALTERNATE PATH: YES PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: John Rodgers DATE: 8/15/2020 VALIDATED BY: Brian Garrettson DATE: 8/20/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM S6 SIMULATOR SETUP:

IC: 20 SIMULATOR SCENARIO FILES, MALFUNCTIONS, REMOTE FUNCTIONS, ETC. FOR SETUP:

COMMAND DESCRIPTION mfED16A k:1 Loss of PKA-M41 crB2EG02PBAS03B_3 f:OPEN Locally open the A EDG Output Breaker INSTRUCTIONS FOR SETUP:

Reset to IC-20 (or load JPM from IC-606)

Place the A EDG on PBA-S03 and raise MW loading to ~5.2 MW REQUIRED CONDITIONS:

A EDG loaded onto PBA-S03 and loaded to ~5.2 MW NOTE: The driver should have the remote function for local operation of PBA-S03B pulled up and ready for execution prior to each performance of the JPM

2020 PVNGS NRC Initial Exam JPM S6 PROCEDURES/MATERIALS:

40OP-9DG01, Emergency Diesel Generator A This JPM was written using Revision 80 of 40OP-9DG01. This JPM may be performed using future revisions of 40OP-9DG01 provided the associated steps of the procedure remain unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power The A EDG is running fully loaded for a Normal Run The A EDG has been loaded to 5.2 MW for the past 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months INITIATING CUE:

The CRS directs you to unload the A EDG per 40OP-9DG01, Emergency Diesel Generator A, Section 6.7, Unloading Train A Diesel Generator

2020 PVNGS NRC Initial Exam JPM S6 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM S6 JPM START TIME:

JPM Step: 1 Reduce Train A Diesel Generator load per Appendix G - Loading and Unloading Schedule Standard: Referred to Appendix G to determine rate of load reduction and load stabilization times Comments (required for UNSAT):

SAT UNSAT Procedure Note: It is beneficial to control thermal distribution during shutdown It is recommended to gradually reduce load JPM Step: 2 (From Appendix G) Observe MW loading and duration per the Table before lowering to the next increment Examiner Note: Data from the table referenced in this step:

Design Load % MW MW Allowable Minimum Range Duration 110 6.05 5.775-6.05 None 100 5.4 5.0-5.5 210 minutes*

10 minutes 75 4.0 3.6-4.4 5 minutes 50 2.7 2.3-3.1 5 minutes 25 1.4 1.0-1.8 5 minutes

210 minutes is the recommended cumulative run time at 100% of design load.

If the Diesel Generator was operated at greater than 100% of design load, it should be operated for a minimum of 10 minutes at 100% of design load before additional load reduction Standard: Determined that EDG loading should be stabilized and maintained between 3.6-4.4 MW for at least 5 minutes Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S6 JPM Step: 3

Commence reducing load on the A EDG per the Appendix G unloading table (from 100% to 75% load)

Standard: Commenced reducing load on the A EDG by lowering speed on the A EDG using handswitch PEA-SC-G01, and paused the load reduction when A EDG MW loading is between 3.6-4.4 MW Examiner Cue: When the applicant has lowered A EDG load to between 3.6-4.4 MW:

A EDG MW load has been stable for 5 minutes Comments (required for UNSAT):

SAT UNSAT Examiner Note: When the applicant commences the next phase of EDG load reduction, direct the driver to INITIATE KEY 1, loss of PKA-M41. The following steps represent the alternate path portion of the JPM JPM Step: 4

Commence reducing load on the A EDG per the Appendix G unloading table (from 75% to 50% load)

Standard: Commenced reducing load on the A EDG, diagnosed the subsequent loss of PKA-M41, and addressed EITHER ARP 1A04A or AOP 40AO-9ZZ13, Loss of Class Instrument or Control Power Comments (required for UNSAT):

SAT UNSAT JPM Step: 5 (From ARP 1A04A) IF panel PKA-M41, Class 125VDC Control Center has lost power, THEN GO TO 40AO-9ZZ13, Loss of Class Instrument or Control Power Standard: Referred to 40AO-9ZZ13, Loss of Class Instrument or Control Power (examinee may go directly to the AOP)

Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S6 JPM Step: 6 * (From 40AO-9ZZ13) IF DG A was paralleled with offsite power when this event occurred, THEN direct an operators to locally open PBA-S03B, DG A Output Breaker Standard: Directed an AO to locally open PBA-S03B within 5 minutes of the loss of PKA-M41 Time PKA-M41 was lost: __________

Time AO directed to open PBA-S03B (must be 5 minutes): __________

Examiner Cue: When the examinee directs an AO to locally open PBA-S03B, the driver will locally open PBA-S03B When PBA-S03B has been opened:

This JPM is complete Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM S6 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 8/15/2020 6 JPM created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM S6 EXAMINEE INITIAL CONDITIONS:

Unit 1 is operating at 100% power The A EDG is running fully loaded for a Normal Run The A EDG has been loaded to 5.2 MW for the past 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months INITIATING CUE:

The CRS directs you to unload the A EDG per 40OP-9DG01, Emergency Diesel Generator A, Section 6.7, Unloading Train A Diesel Generator EXAMINEE

2020 PVNGS NRC Initial Exam JPM S7 JPM INFORMATION L392057 - Respond to an event requiring entry into the Loss of Class Instrument or TASK:

Control Power AOP Navigated to the Change Addressable Constants screen, located tag name CEANOP, set a value of 2, enabled the Function Enable keyswitch, set the new value of 2 for the TASK STANDARD:

CEANOP addressable constant, and returned the Function Enable keyswitch back to OFF K/A: 012 A2.02 RATING: RO: 3.6 SRO: 3.9 POSITION(S): RO / SRO VALIDATION TIME: 7 minutes

REFERENCES:

40AO-9ZZ13, Loss of Class Instrument or Control Power LOCATION: SIMULATOR X PLANT CLASSROOM TIME CRITICAL: NO ALTERNATE PATH: NO PRA/SRA RELATED: NO APPROVALS DEVELOPED/REVISED BY: John Rodgers DATE: 8/15/2020 VALIDATED BY: Brian Garrettson DATE: 8/20/2020 TECH OPERATIONS REVIEW: N/A APPROVAL: N/A E-PLAN TRAINING REVIEW: N/A APPROVAL: N/A Only required for E-Plan JPMs EVALUATION EXAMINEE: DATE:

EVALUATOR: GRADE (circle): SAT / UNSAT*

START: STOP: TOTAL TIME: minutes

A grade of UNSAT for E-Plan JPMs requires a CR to be written, remediation, and re-evaluation. CR #

Issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form EP-0800 and forwarded to the Emergency Preparedness organization for resolution.

2020 PVNGS NRC Initial Exam JPM S7 SIMULATOR SETUP:

IC: 20 SIMULATOR SCENARIO FILES, MALFUNCTIONS, REMOTE FUNCTIONS, ETC. FOR SETUP:

COMMAND DESCRIPTION mfED12C Loss of PNC-D27 INSTRUCTIONS FOR SETUP:

Reset to IC-20 (or load JPM from IC-607)

Insert malfunction listed above Place CEDMCS in STANDBY REQUIRED CONDITIONS:

NOTE: Ensure paper which may print after examinee presses PRINT SCREEN is collected after each JPM NOTE: Ensure TAG NAME ARM1 is selected on all CPCs prior to each run of the JPM

2020 PVNGS NRC Initial Exam JPM S7 PROCEDURES/MATERIALS:

40AO-9ZZ13, Loss of Class Instrument or Control Power This JPM was written using Revision 31. This JPM may be performed using future revisions of 40AO-9ZZ13 provided the associated steps of the procedure remain unaffected INFORMATION PRESENTED TO EXAMINEE:

ALL JPMS:

You may use any source of information normally available (procedures, prints, OAPs, etc.).

Classroom instruction materials (Lesson Plans, System Training Manuals, PowerPoint presentations, classroom notes, etc.) are not permitted to be used.

If there is a question regarding reference material desired to be used, ask evaluator prior to seeking reference.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power A loss of PNC-D27 has just occurred The CRS has entered 40AO-9ZZ13, Loss of Class Instrument or Control Power INITIATING CUE:

The CRS directs you to perform Step 5 of 40AO-9ZZ13, Loss of Class Instrument or Control Power, to set INOP flags for CEAC 2 in all operable CPCs

2020 PVNGS NRC Initial Exam JPM S7 INFORMATION FOR EVALUATOR USE:

An asterisk (*) denotes a Critical Step. Failure of a Critical Step will result in an UNSAT evaluation.

At the discretion of the Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM.

Any step marked UNSAT requires comments.

If this is the first JPM of the set, then ensure the examinee has been briefed.

Step sequence is not critical unless noted or will prevent the Task Standard from being met.

2020 PVNGS NRC Initial Exam JPM S7 JPM START TIME:

Examiner Note: The same process would be repeated on the 3 operable CPCs, however for the purpose of the JPM, the JPM can be stopped after the examinee has completed the task on any one CPC JPM Step: 1

IF ANY CPC is energized, AND NOT in bypass, THEN perform the following to set the CEAC 2 INOP flag in ALL OPERABLE CPCs:

From the Directory page, Touch the Addressable Constants button Standard: Pressed the Directory icon, then the Addressable Constants icon on the CPC screen Comments (required for UNSAT):

SAT UNSAT JPM Step: 2

IF ANY CPC is energized, AND NOT in bypass, THEN perform the following to set the CEAC 2 INOP flag in ALL OPERABLE CPCs:

From the Addressable Constants page, Touch the Change Addressable Constants button Standard: Pressed the Change Addressable Constants icon on the CPC screen Comments (required for UNSAT):

SAT UNSAT JPM Step: 3

IF ANY CPC is energized, AND NOT in bypass, THEN perform the following to set the CEAC 2 INOP flag in ALL OPERABLE CPCs:

Select CEANOP (#0062) in the Enter Tag Name field by using the pull down menu button Standard: Pressed the drop down icon, located the CEANOP and pressed the CEANOP icon on the CPC screen Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S7 JPM Step: 4 IF ANY CPC is energized, AND NOT in bypass, THEN perform the following to set the CEAC 2 INOP flag in ALL OPERABLE CPCs:

Touch the Print Screen button Standard: Touched the Print Screen icon on the CPC screen Comments (required for UNSAT):

SAT UNSAT JPM Step: 5

IF ANY CPC is energized, AND NOT in bypass, THEN perform the following to set the CEAC 2 INOP flag in ALL OPERABLE CPCs:

Enter the following value in the Enter Value field by inserting the curson and touching the appropriate keys from the displayed keyboard:

o CEAC 2 inoperable: CPC Pt ID 0062 = 2 Standard: Touched the screen in the Enter Value box and entered a value of 2 on the CPC screen Comments (required for UNSAT):

SAT UNSAT Procedure Note: The SET VALUE Button will be highlighted in yellow by the calculator software when the Function Enable keyswitch is placed in the ENABLED position JPM Step: 6

IF ANY CPC is energized, AND NOT in bypass, THEN perform the following to set the CEAC 2 INOP flag in ALL OPERABLE CPCs:

Enable the Set Value Function by placing the Function Enable keyswitch to the ENABLED position Standard: Rotated the OM Function Enable keyswitch clockwise 90° to the ENABLE position Comments (required for UNSAT):

SAT UNSAT

2020 PVNGS NRC Initial Exam JPM S7 JPM Step: 7

IF ANY CPC is energized, AND NOT in bypass, THEN perform the following to set the CEAC 2 INOP flag in ALL OPERABLE CPCs:

Touch the SET VALUE button Standard: Touched the SET VALUE icon on the CPC screen Comments (required for UNSAT):

SAT UNSAT JPM Step: 8

IF ANY CPC is energized, AND NOT in bypass, THEN perform the following to set the CEAC 2 INOP flag in ALL OPERABLE CPCs:

Set the Function Enable keyswitch to the OFF position to disable the Set Value function Standard: Rotated the OM Function Enable keyswitch counter-clockwise 90° to the OFF position Comments (required for UNSAT):

SAT UNSAT JPM Step: 9 IF ANY CPC is energized, AND NOT in bypass, THEN perform the following to set the CEAC 2 INOP flag in ALL OPERABLE CPCs:

Verify that the new value of the addressable constant is correct by reading the displayed current value below the Tag Name Standard: Confirmed that a value of 2 is displayed below the CEANOP tag name Examiner Cue: When the examinee has confirmed that a value of 2 is displayed below the CEANOP tag name:

Another operator will continue with this procedure, this JPM is complete Comments (required for UNSAT):

SAT UNSAT JPM STOP TIME:

2020 PVNGS NRC Initial Exam JPM S7 RECORD OF REVISIONS REVISION # REVISION DATE REASON COMMENTS 0 8/15/2020 6 JPM created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

2020 PVNGS NRC Initial Exam JPM S7 EXAMINEE INITIAL CONDITIONS:

Unit 1 is operating at 100% power A loss of PNC-D27 has just occurred The CRS has entered 40AO-9ZZ13, Loss of Class Instrument or Control Power INITIATING CUE:

The CRS directs you to perform Step 5 of 40AO-9ZZ13, Loss of Class Instrument or Control Power, to set INOP flags for CEAC 2 in all operable CPCs EXAMINEE

Appendix D Scenario Outline Form ES-D-1 Facility: Palo Verde Scenario: 1 Test: 2020 NRC Exam Examiners: Operators:

Initial Conditions: 100% power, MOC, AFA-P01 OOS Turnover: Maintain 100% power Event Number Event Type* Event Description 1 I (CRS, BOP), TS Steam Generator #2 Flow transmitter RCD-PDT-125D fails (CRS) low 2 C (All), TS (CRS) Inadvertent Train A CSAS / Loss of Letdown 3 C (All), TS (CRS) MFP Trip 4 M (All) ESD inside Containment 5 C (CRS, BOP) MSIS fails to auto actuate 6 C (OATC) Train B Containment Spray Pump trips (A CS Pump anti-pumped)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Actual Target Quantitative Attributes 6 Total malfunctions (5-8) 2 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 1 Major transients (1-2) 1 EOPs entered requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 3 Critical tasks (2-3)

PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Scenario Event Summary Form ES-D-1 NRC Exam Scenario # 1 2020 NRC Exam Scenario # 1 Overview Event 1 Steam Generator #2 Flow transmitter RCD-PDT-125D will fail low. The crew will address the ARP and validate actual Steam Generator flow using alternate indications. The CRS will address Technical Specifications for the failed transmitter and direct the crew to bypass the affected RPS bistables.

Event 2 An inadvertent Train A CSAS will occur. The crew will verify that an actual CSAS is not required and the CRS will enter 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations. The CRS will direct the crew to stop Train A CS flow by stopping the A CS Pump and closing the CS header isolation valve. The CRS will direct the restoration of NC flow by opening NCA-UV-402, NCW Containment Downstream Return Isolation Valve. The Train A CSAS will also result in a loss of letdown. The CRS will enter 40AO-9ZZ05, Loss of Charging or Letdown, and direct the crew to either restore letdown or establish conditions for extended loss of Letdown.

Event 3 A MFP will trip causing a RPCB. The CRS will enter 40AO-9ZZ09, Reactor Power Cutback (Loss of Feedpump) and the crew will verify that all parameters are restoring.

The CRS will direct the crew to remove RPCB from service.

Event 4 An ESD inside containment will require a manual Reactor trip. The CRS will enter 40EP-9EO01, Standard Post Trip Actions. After the Reactor Trip, a vacuum breaker valve will fail open causing the B MFP to trip.

Event 5 SIAS and CIAS will actuate but MSIS will fail to auto-actuate and will require a manual actuation.

Event 6 B CS Pump will trip and A CS Pump will require a manual start due to being anti-pumped during the inadvertent CSAS. The CS header isolation valve will be manually opened due to being overridden and closed during the inadvertent CSAS PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Critical Task Summary Form ES-D-1 NRC Exam Scenario # 1 Critical Task # 1: When the Main Steam Isolation setpoints are exceeded, ensure Main Steam Isolation has actuated within 15 minutes of exceeding the MSIS setpoint (Containment pressure -

3 psig OR SG Pressure Low - 960 psia - whichever is reached first)

Safety Significance: MSIS ensures acceptable consequences during an MSLB or FWLB (between the steam generator and the main feedwater check valve) either inside or outside containment. MSIS isolates both steam generators if either generator indicates a low pressure condition or a high level condition or if a high containment pressure condition exists. This prevents an excessive rate of heat extraction and subsequent cooldown of the RCS during these events. The 15 minute time requirement is based on the time that it takes to complete a round of Safety Function Status Checks since SPTAs is the first check on all safety functions. Normally 30 minutes is the time requirement for ESFAS failures, however since this failure will affect 4 Safety Functions, prompt action is expected from Operations Management.

Cueing: The crew should recognize the failure of MSIS to actuate when containment pressure exceeds 3 psig OR when either SG pressure lowers to less than 960 psia (both are setpoints for MSIS).

Measurable Performance Indicator: The crew will have to manually actuate MSIS by taking the four handswitches for each ESFAS channel actuation (on B05) to the actuate position. This can be confirmed by the red MSIS lights on the vertical section of B05 as well as the actuation logic lights for each actuation extinguishing on the horizontal section of B05.

Performance Feedback: The crew will have indication of successful actuations by observing the red SIAS/CIAS/MSIS lights on the vertical section of B05 as well as the actuation logic lights for each actuation extinguishing on the horizontal section of B05, as well as by observing the actuated equipment for each ESFAS actuation going to its actuated position.

This Critical Task and the 15 minute time requirement meets Operations Management expectations for an Operating Crew PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Critical Task Summary Form ES-D-1 NRC Exam Scenario # 1 Critical Task # 2: When the Containment Spray Actuation setpoint is exceeded, ensure adequate Containment Cooling to meet Safety Function requirements within 30 minutes of exceeding the CSAS setpoint (Containment pressure - 8.06 psig)

Safety Significance: Potential degradation of any barrier to fission product release. Failure to maintain containment temperature and pressure control may challenge containment integrity. The 30 minute time requirement is based on 15 minutes (time requirement to complete Safety Function Status Checks) to diagnose the loss of Containment Spray, and 15 minutes for mitigating actions Cueing: In addition to the procedural cue, the crew may use indications of Containment pressure, Containment temperature, Containment fan coolers, Containment Spray pumps, and Containment Spray flow to provide cue to perform elements of this task.

Measurable Performance Indicator: The task is identified by at least one member of the crew manipulating the controls to establish Containment Spray flow. If Containment pressure is > 8.5 psig, the crew should ensure a CSAS is actuated and at least one CS header is delivering > 4350 gpm on at least one header.

Performance Feedback: The task provides feedback by observing 4350 gpm on B02 and ERFDADS flow indicators and Containment pressure lowering.

This Critical Task and the 30 minute time requirement meets Operations Management expectations for an Operating Crew PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Critical Task Summary Form ES-D-1 NRC Exam Scenario # 1 Critical Task # 3: Ensure all RCPs are secured within 30 minutes of the Train B CSAS actuation (either manual or automatic actuation)

Safety Significance: Potential degradation of any barrier to fission product release. Failure to perform this task may result in the failure of the RCP seals on RCPs which are operating and not satisfying the respective RCP operating limits Cueing: Although initially cued by the CSAS alarm, the operators will be cued to perform this task by a procedural step in SPTAs. They will also be cued by abnormal RCP operation, such as temperature alarms, seal pressures, cooling water flow, etc.

Measurable Performance Indicator: The task is identified by at least one member of the crew manipulating the controls to stop the RCPs. The trip of the RCPs should be within 30 minutes of the loss of NC.

Performance Feedback: The crew will observe red lights off and green lights on on all of the RCP handswitches as well as 0 amps indicated on each RCP.

This Critical Task and the 30 minute time requirement meets Operations Management expectations for an Operating Crew NOTE: (Per NUREG-1021 Appendix D) If an operator or the Crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a Critical Task identified in the post-scenario review PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 1 Driver Setup Instructions Reset to IC-20 Run scenario file NRC Scenario # 1 Hang OOS tags on AFA-P01, place protected placards over AFB-P01 and AFN-P01 PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 1 Event Type Malf # Description Final Initiator rfFW59 AFA-P01 OOS TRIP rfFW60B OFF rfFW57 CLOSE crB4FW08AFAHV32_1 OPEN crB4FW08AFAUV37_1 OPEN crB5FW08AFCHV33_1 OPEN crB5FW08AFCUV36_1 OPEN crB4MS13SGAUV134_1 OPEN crB4MS13SGAUV138_1 OPEN 1 MF cmTRRX09RCDPDT125D_1 SG #2 Flow 0 Key 1 Transmitter 125D Fails Low 2 MF mfRP06G1 Inadvertent Train A Key 2 CSAS mfRP06G2 3 Loss of Letdown (due to CSAS) 4 MF mfFW17A A MFP Trip 5 MF mrTH01C ESD Inside Ramp to Key 5 Containment on SG 30

2 MF cmAVMC01CDNHV45C_1 C Vacuum Breaker Rx Trip opens 6 MF cmSRRP01IRMSISAB1_2 MSIS Fails to Auto cmSRRP01IRMSISAB2_2 Actuate cmSRRP01IRMSISAB3_2 cmSRRP01IRMSISAB4_2 cmSRRP01IRMSISAC1_2 cmSRRP01IRMSISAC2_2 cmSRRP01IRMSISAC3_2 cmSRRP01IRMSISAC4_2 cmSRRP01IRMSISAD1_2 cmSRRP01IRMSISAD2_2 cmSRRP01IRMSISAD3_2 cmSRRP01IRMSISAD4_2 cmSRRP01IRMSISBC1_2 cmSRRP01IRMSISBC2_2 PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 1 cmSRRP01IRMSISBC3_2 cmSRRP01IRMSISBC4_2 cmSRRP01IRMSISBD1_2 cmSRRP01IRMSISBD2_2 cmSRRP01IRMSISBD3_2 cmSRRP01IRMSISBD4_2 cmSRRP01IRMSISCD1_2 cmSRRP01IRMSISCD2_2 cmSRRP01IRMSISCD3_2 cmSRRP01IRMSISCD4_2 7 MF MfRH01B B Containment Spray Pump Trips PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Crew Turnover Sheet Form ES-D-1 NRC Exam Scenario # 1 Plant Conditions:

Unit 1 is operating at 100% power, MOC There are no personnel inside Containment Equipment Out of Service:

AFA-P01 was taken out of service last shift for preventative maintenance o LCO 3.7.5 Condition A and B has been entered o AFB-P01 and AFN-P01 are protected Planned Shift Activities:

Maintain 100% power PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 1 Page 10 of 22 Event

Description:

SG #2 Flow Transmitter RCD-PDT-125D fails low Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 1, RCD-PDT-125D fails low Indications available:

5A12C LO RC FLOW SG 2 CH TRIP alarm Examiner Note: The following steps are from the B05A Alarm Response Procedure alarm window 5A12C:

Procedure Note:

The following Technical Specifications may be impacted:

o LCO 3.3.1, Reactor Protection System (RPS) Instrumentation - Operating o LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits o LCO 3.4.4, RCS Loops - MODES 1 and 2 o LCO 3.4.5, RCS Loops - MODE 3 o LCO 3.4.6, RCS Loops - MODE 4 BOP Compare ALL of the following instrumentation to confirm the alarm: (B05)

RCA-PDI-115A, R0 SG 2 DP PDT-125A RCB-PDI-115B, R0 SG 2 DP PDT-125B RCC-PDI-115C, R0 SG 2 DP PDT-125C RCD-PDI-115D, R0 SG 2 DP PDT-125D BOP If the alarm is confirmed to be invalid, THEN perform the following:

IF BOTH of the following conditions exist:

o The cause of the channel trip is unknown o Time for troubleshooting is available THEN notify I&C to troubleshoot the channel setpoint prior to placing channel in bypass.

Place ANY affected channel in BYPASS at the associated Plant Protection System cabinet:

SBA-C01, Plant Protection Sys cabinet SBB-C01, Plant Protection Sys cabinet SBC-C01, Plant Protection Sys cabinet SBD-C01, Plant Protection Sys cabinet Examiner Note: The following steps are from 40OP-9SB02, Plant Protection System Bypass Operations, Section 6.1, Placing PPS Channel Parameters in Bypass:

Procedure Note:

PPS bypass operations are performed at the PPS system cabinets SBA-C01, SBB-C01, SBC-C01, SBD-C01.

BOP REFER TO Appendix A - PPS (RPS/ESFAS), Parameters, Indicators, LCOs/TLCOs.

BOP Select the channel to be placed in bypass:

D BOP Select the parameter(s) to be placed in bypass:

15 - SG-2 LO FLOW BOP Request the SM/CRS enter and log the appropriate LCO/TLCO required actions.

PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 1 Page 11 of 22 Event

Description:

SG #2 Flow Transmitter RCD-PDT-125D fails low Time Position Applicant Actions Technical Specifications:

LCO 3.3.1, Reactor Protection System (RPS) Instrumentation - Operating, Condition A o Place channel in bypass or trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore channel to OPERABLE status prior to entering MODE 2 following next MODE 5 entry BOP Place the selected parameter(s) in bypass.

OATC Perform Independent Verifications per 02DP-0ZZ01, Verification of Plant Activities.

Examiner Note: When the crew has placed parameter in bypass and the CRS has addressed Technical Specifications, or at the lead evaluators discretion, proceed to Event 2, Inadvertent Train A CSAS.

PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 2 Page 12 of 22 Event

Description:

Inadvertent Train A CSAS Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 2, Inadvertent Train A CSAS Indications available:

Multiple alarms RCP Low Flow alarms (Loss of NC to RCPs)

All Train A Safety Injection components will start and begin spray in containment Examiner Note: The following steps are from 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations, Section 5.0 CSAS:

Procedure Note:

Overriding or anti-pumping equipment disables automatic operation of the equipment on a valid PPS-ESFAS actuation. Depending on plant conditions, this action may make the equipment inoperable.

OATC IF BOTH of the following:

Any Containment Spray Pump is running The running Containment Spray Pump in NOT being used for SDC THEN perform the following:

IF SIAS has NOT actuated, THEN place the Containment Spray Pump hand switch in STOP to anti-pump the CS Pump IF SIAS has actuated, THEN override and stop the Containment Spray Pump Procedure Caution:

Attempting to close the Containment Spray Header Isolation Valves while the valves are stroking to their actuated position may trip the valve breaker on overload and allow continued spray flow by gravity drain.

OATC Override and close all open Containment Spray Header Isolation Valves (SIA-UV-672 is the only Spray Header valve that opened)

Procedure Note:

Opening the NC Containment Supply Isolation Valve prior to opening the NC Containment Return Isolation Valves may result in lifting the NC reliefs in Containment.

BOP Open ANY of the following as needed to restore Nuclear Cooling Water to Containment:

NCA-UV-402, NCW Containment Downstream Return Isolation Valve NCB-UV-403, NCW Containment Upstream Return Isolation Valve NCB-UV-401, NCW Containment Upstream Supply Isolation Valve OATC IF BOTH of the following:

Seal Injection is NOT in service Cooling water is NOT restored to ANY operating RCP within 3 minutes of the initial loss THEN perform the following:

Ensure the reactor is tripped Stop all of the RCPs Isolate controlled bleedoff PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 2 Page 13 of 22 Event

Description:

Inadvertent Train A CSAS Time Position Applicant Actions OATC IF BOTH of the following:

Seal Injection is in service Cooling water is NOT restore to ANY operating RCP within 10 minutes of the initial loss:

THEN perform the following:

Ensure the reactor is tripped Stop all of the RCPs Isolate controlled bleedoff OATC IF IAA-UV-2, Outside Ctmt Isolation Valve, has closed, THEN perform the following:

IF ANY of the following valves have failed closed:

o CHA-UV-516 o CHB-UV-515 o SGA-UV-500P o SGB-UV-500R THEN place the handswitch(es) for the failed valve(s) to CLOSE Override and open IAA-UV-2 Ensure Pressurizer sprays are operating to control pressurizer pressure OATC IF letdown is isolated, THEN perform the following:

Ensure no more than one Charging Pump is running PERFORM 40AO-9ZZ05, Loss of Charging or Letdown OATC IF BOTH of the following:

Any Control Room Essential AHUs started It is desired to stop the running Control Room Essential AHUs THEN override and stop the running fans OATC IF RCP Seal Bleedoff isolated to the VCT, THEN override and open the closed RCP Seal Bleedoff Isolation Valves BOP IF SG Blowdown is isolated, THEN perform the following:

Inform Chemistry that Blowdown is isolated PERFORM 40OP-9SG03, Operating the SG Blowdown System, to restore blowdown OATC IF a CS Pump needs to be started, THEN perform the following:

IF SIAS has NOT actuated, THEN perform the following:

o Inform an operator that the CS Pump breaker will close upon restoration of control power o Direct the operator to cycle control power to the CS Pump breaker(s)

IF SIAS actuated while the CS Pump(s) were stopped, THEN perform the following:

o Place the CS Pump handswitch to START and release the switch o Place the CS Pump handswitch to START PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 2 Page 14 of 22 Event

Description:

Inadvertent Train A CSAS Time Position Applicant Actions OATC Perform the following:

PERFORM Appendix C, PPS-ESFAS Check, Step 2 and Step 3, to check that equipment actuated as expected Document components that failed to actuate in the Control Room Log Ensure compliance with TS for components that failed to actuate or were overridden CRS Ensure compliance with BOTH of the following:

LCO 3.3.5, ESFAS Instrumentation LCO 3.3.6, ESFAS Logic and Manual Trip Technical Specifications:

LCO 3.3.6, Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip, Condition D o Restore channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months LCO 3.4.16, RCS Leakage Detection Instrumentation, Condition A o Perform SR 3.4.14.1 once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and restore containment sump monitor to OPERABLE status within 30 days LCO 3.6.3, Containment Isolation Valves, Condition A o Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND verify the affected penetration flow path is isolated once per 31 days following isolation for isolation devices outside containment and prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment LCO 3.6.6, Containment Spray System, Condition A o Restore containment spray train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO 3.5.3, ECCS - Operating, Condition B (If HPSI/LPSI pumps are overridden and stopped) o Restore train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO 3.7.11, Control Essential Filtration System (CREFS), Condition A (If Control Room Essential AHU fans are overridden and stopped).

o Restore CREFS train to OPERABLE status within 7 days BOP IF the CSAS will NOT be reset at this time, THEN PERFORM Appendix C, PPS-ESFAS Check, Step 4.1 OATC Override and align equipment as directed by the CRS OATC Circle the as left condition of all components listed in the appropriate attachment PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 2 Page 15 of 22 Event

Description:

Inadvertent Train A CSAS Time Position Applicant Actions PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 2 Page 16 of 22 Event

Description:

Inadvertent Train A CSAS Time Position Applicant Actions Examiner Note: The CRS may implement 40AO-9ZZ05, Loss of Charging or Letdown while performing 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations concurrently. The following steps are from 40AO-9ZZ05, Loss of Charging or Letdown:

OATC IF BOTH of the following occur at any time during this procedure:

Pressurizer level lowers to 33%

Restoration of charging is NOT impending THEN trip the Reactor OATC IF BOTH of the following conditions are met:

The CRS determines seal injection and charging are to be stopped Pressurizer level is rising and 56% level will be challenged THEN perform the following:

Place all Charging Pumps in PULL TO LOCK Ensure controlled bleedoff is isolated on all standby RCPs prior to Seal 2 outlet temperature exceeding 250°F Close the Seal Injection Flow Control Valves IF the unit is in MODE 1, 2, or 3, THEN ensure compliance with LCO 3.4.9, Pressurizer PERFORM Appendix C, Extended Operations Without Letdown, to adjust PZR level, Seal Injection, or VCT level Examiner Note: When the crew has changed Blowdown constants and the CRS has addressed Technical Specifications, or at the lead evaluators discretion, proceed to Event 3, A MFP Trip.

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 3 Page 17 of 22 Event

Description:

A MFP Trip Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 3, A MFP Trip Indications available:

6A03A FWPT A TRIP alarm Reactor Power Cutback Examiner Note: The following steps are from 40AO-9ZZ09, Reactor Power Cutback (Loss of Feedpump OATC IF reactor power was 74% or more, THEN perform the following:

Check that RPCB LOFP has actuated Check that CEA subgroups 4, 5, and 22 have inserted OATC IF reactor power was less than 74%, THEN check that CEAs are inserting as needed to match reactor and turbine power BOP Check Main Turbine Setback - Runback has lowered Main Turbine load to 65%

or less OATC IF any CEA deviates from its subgroup by greater than 6.6 inches, AND ANY CEA Reg Group are below the Transient Insertion Limits, THEN perform the following:

Trip the reactor GO TO SPTAs CRS Direct the STA to PERFORM Appendix D, Status Check RPCB Loss of Feedpump BOP IF BOTH Feed Pumps trip, THEN perform the following:

Trip the reactor GO TO SPTAs BOP Raise the Speed Bias on the operating Main Feed Pump to zero or more BOP Restore and maintain SG levels 45-60% NR CRS Check that BOTH of the following are being maintained in automatic:

RRS is adjusting CEAs to restore Tave/Tref +/- 3°F SBCS opens if required to control main steam pressure at setpoint CRS IF steaming to atmosphere, THEN inform RP and the RMS technician BOP IF condenser hotwell level is less than 41 inches, THEN direct an operator to maintain the condenser hotwell level 41 inches or more using ANY of the following:

Hotwell makeup and reject controllers CDN-HCV-154 CDN-HCV-155 BOP IF reactor power is 70% or less and stable, THEN perform the following:

IF the RPCB AUTO ACTUATE OUT OF SERVICE pushbutton is NOT lit, THEN press the AUTO ACTUATE OUT OF SERVICE pushbutton IF the RPCB TEST RESET pushbutton is NOT lit, THEN press the TEST RESET pushbutton BOP Perform a lamp test to ensure the LOAD LIMIT LIMITING light illuminates BOP Reduce the load limit potentiometer until the potentiometer has positive control of the Main Turbine control valves PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 3 Page 18 of 22 Event

Description:

A MFP Trip Time Position Applicant Actions OATC IF a RPCB has dropped CEA subgroups, AND BOTH of the following conditions are met:

CEA motion is only required to compensate for Xenon buildup Main Turbine load limiting light is on THEN place CEDMCS in MANUAL SEQUENTIAL BOP Monitor CPC Point ID 0187, CPC ASI - Aux Trip BOP IF ALL of the following conditions are met:

CPC Pt ID 0187 indicates greater than +/- 0.45 CPC Pt ID 0187 is trending to +/- 0.5 CPC Aux Trip on ASI is still possible THEN perform the following:

Trip the reactor GO TO SPTAs OATC Start boron equalization of the pressurizer by performing the following:

Energize pressurizer backup heaters as necessary Lower the setpoint on RCN-PIC-100, Pressurizer Pressure Controller, to 2220 psia Examiner Note: To override the Pressurizer heaters, Pressurizer pressure needs to be >2225 psia. Also, the crew will use non-class backup heaters and may or may not energize class backup heaters.

BOP Adjust Feedwater Control System DP as needed to maintain feed stability using Feedwater Pump Turbine Speed Setpoint Control:

FWPT A: SGN-FIC-1107 FWPT B: SGN-FIC-1108 CRS IF COLSS is operable, THEN perform the following:

IF DNBR POL is being exceeded, THEN declare LCO 3.2.4, DNBR, NOT met and comply with the LCO actions IF LPD POL is being exceeded, THEN declare LCO 3.2.1, LHR, NOT met and comply with the LCO actions Technical Specifications:

During validations only LCO 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) was exceeding its Technical Specification value (if power indicated at Power Operating Limits [POLs]on B04 is exceeding the DNBR limit, than this LCO is not met) o LCO 3.2.4 Departure From Nucleate Boiling Ratio (DNBR), Condition A Restore the DNBR to within limit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months BOP IF the post cutback xenon build-in results in Tavg dropping 5°F below Tref, THEN lower turbine load as necessary to maintain the Tavg/Tref mismatch between -

5°F and -3°F Examiner Note: When the crew has placed the Pressurizer in Boron Equalization and the CRS has addressed Technical Specifications, or at the lead evaluators discretion, proceed to Event 4, ESD Inside of Containment.

PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 4,5,6 Page 19 of 22 Event

Description:

ESD Inside of Containment / MSIS fails to auto actuate / B Containment Spray Pump trip Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 4, ESD Inside of Containment Indications available:

Reactor power rising Containment pressure rising Steam Generator pressures lowering Examiner Note: The Reactor will automatically trip on High Containment pressure if the crew does not manually trip before exceeding setpoints. When the Reactor trips, the C Main Condenser Vacuum breaker will fail open causing the B MFP to trip. The following steps are from 40EP-9EO01, Standard Post Trip Actions:

BOP Determine that Reactivity Control acceptance criteria are met:

Check that reactor power is dropping Check that startup rate is negative Check that full strength CEAs are inserted Check that the Main Turbine is tripped OATC Determine the Maintenance of Vital Auxiliaries acceptance criteria are met:

Check the Main Generator output breakers are open Check that station loads have transferred to offsite electrical power such that BOTH of the following conditions are met:

All vital and non-vital AC buses are powered All vital and non-vital DC buses are powered OATC Determine that RCS Inventory Control acceptance criteria are met:

Check that pressurizer level meets BOTH of the following:

10-65%

Trending as expected to 33-53%

(CA) Restore and maintain pressurizer level to 33-53%

by any of the following:

Operation of PLCS Manual operation of Charging Pumps and Letdown Control Valves Check that the RCS is 24°F or more subcooled (CA) IF the RCS is less than 24F subcooled, THEN stop all RCPs Check that BOTH of the following are in service to all RCPs:

Seal injection Nuclear Cooling Water (CA) Isolate controlled bleedoff from ANY RCP(s) as appropriate. REFER TO 40AO-9ZZ04, RCP Emergencies, Appendix E, Control Board B04 Label PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 4,5,6 Page 20 of 22 Event

Description:

ESD Inside of Containment / MSIS fails to auto actuate / B Containment Spray Pump trip Time Position Applicant Actions OATC Determine that RCS Pressure Control acceptance criteria are met:

Pressurizer pressure is 1837-2285 psia Pressurizer pressure is trending as expected to 2225-2275 psia (CA) Restore and maintain pressurizer pressure to the normal control band by ANY of the following:

Operation of PPCS Manual operation of pressurizer heaters and spray valves (CA) IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated (CA) IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop (CA) IF pressurizer pressure drops below the RCP NPSH limits, THEN stop all RCPs. REFER TO Appendix 2, Figures OATC Determine that Core Heat Removal acceptance criteria is met:

At least one RCP is operating Loop delta-T is less than 10°F RCS is 24°F or more subcooled BOP Determine that RCS Heat Removal acceptance criteria are met:

Check that at least one SG meets BOTH of the following:

Level is 35% WR or more Feedwater is restoring or maintaining level 45-60% NR (CA) Restore and maintain level in at least one SG 45-60% NR Check that Tc is 560-570°F (CA) IF Tc is greater than 570°F, THEN perform the following:

Ensure that feedwater is being restored to at least one SG Restore Tc to 560-570°F using SBCS or ADVs (CA) IF Tc is less than 560°F, THEN perform the following:

Ensure feed flow is NOT excessive Ensure SG Blowdown is isolated Restore Tc to 560-570°F using SBCS or ADVs IF MSIS has actuated AND the cooldown terminates, THEN stabilize Tc using ADVs IF AFAS has actuated AND at least one SG level is 10%

WR or more, THEN override and throttle Auxiliary Feedwater to maintain Tc 560-570°F Check that SG pressure is 1140-1200 psia (CA) IF SG pressure drops to the MSIS setpoint, THEN ensure MSIS has actuated (CA) IF SG pressure is less than 1140 psia, THEN perform the following:

Ensure the SBCS valves are closed Ensure the ADVs are closed (CA) IF SG pressure is greater than 1200 psia, THEN restore and maintain SG pressure to less than 1200 psia using SBCS or ADVs PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 4,5,6 Page 21 of 22 Event

Description:

ESD Inside of Containment / MSIS fails to auto actuate / B Containment Spray Pump trip Time Position Applicant Actions Critical Task # 1:

When the Main Steam Isolation setpoints are exceeded, ensure Main Steam Isolation has actuated within 15 minutes of exceeding the MSIS setpoint (Containment pressure - 3 psig OR SG Pressure Low - 960 psia - whichever is reached first)

SAT / UNSAT OATC Determine that Containment Isolation acceptance criteria are met:

Check that containment pressure is less than 2.5 psig (CA) IF containment pressure is 3 psig or more, THEN ensure that CIAS has been initiated Check BOTH of the following conditions:

No abnormal containment area activity No abnormal steam plant activity OATC Determine that Containment Temperature and Pressure Control acceptance criteria are met:

Check that containment temperature is less than 117°F Check that containment pressure is less than 2.5 psig (CA) IF containment pressure is 3 psig or more, THEN ensure that CIAS has been initiated (CA) IF containment pressure is 8.5 psig or more, THEN perform the following:

Ensure CSAS is actuated Ensure at least one Containment Spray header flow is greater than 4350 gpm Stop all of the operating RCPs Ensure RCP controlled bleedoff is isolated Critical Task # 2:

When the Containment Spray Actuation setpoint is exceeded, ensure adequate Containment Cooling to meet Safety Function requirements within 30 minutes of exceeding the CSAS setpoint (Containment pressure - 8.06 psig)

SAT / UNSAT Critical Task # 3:

Ensure all RCPs are secured within 30 minutes of the Train B CSAS actuation (either manual or automatic actuation)

SAT / UNSAT CRS Diagnose the event(s) in progress and GO TO the appropriate procedure PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 1 Event # 4,5,6 Page 22 of 22 Event

Description:

ESD Inside of Containment / MSIS fails to auto actuate / B Containment Spray Pump trip Time Position Applicant Actions Examiner Note: The CRS will determine that an ESD inside of Containment is in progress.

Stabilization of TCOLD will most likely have been completed during SPTAs. The CRS will enter 40EP-9EO05, ESD.

Examiner Note: When all RCPs have been stopped, TCOLD is stabilized, and once the CRS has entered 40EP-9EO05, Excess Steam Demand, or at lead evaluators discretion, the scenario may be terminated PVNGS 2020 NRC Scenario # 1 Rev 2

Appendix D Scenario Outline Form ES-D-1 Facility: Palo Verde Scenario: 3 Test: 2020 NRC Exam Examiners: Operators:

Initial Conditions: 100%, MOC, AFA-P01 OOS Turnover: Maintain 100% power Event Number Event Type* Event Description 1 I (CRS, BOP), TS Containment Pressure Transmitter HCA-PI-351A fails high (CRS) 2 I (OATC) Pressurizer Pressure Transmitter 100X fails low 3 C (CRS, OATC) Letdown Line Leak 4 C (CRS, OATC) Extended Loss of Letdown 5 C (CRS, BOP) C Condenser Air Removal Pump Trip 6 C (CRS, OATC), RCS Leak TS (CRS) 7 M (All) SBLOCA 8 C (OATC) B HPSI sheared shaft, A HPSI fails to auto-start

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Actual Target Quantitative Attributes 7 Total malfunctions (5-8) 1 Malfunctions after EOP entry (1-2) 5 Abnormal events (2-4) 1 Major transients (1-2) 1 EOPs entered requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Scenario Event Summary Form ES-D-1 NRC Exam Scenario # 3 2020 NRC Exam Scenario # 3 Overview Event 1 Containment Pressure Transmitter HCA-PI-351A will fail high. The crew will address the ARP and validate actual Containment pressure using alternate indications. The CRS will address Technical Specifications for the failed transmitter and direct the crew to bypass the affected RPS bistables.

Event 2 Pressurizer Pressure Transmitter 100X will fail low. The crew will address the ARP and validate the failed transmitter. The crew will restore Pressurizer pressure control by transferring the Pressurizer pressure control channel selector to channel Y.

Event 3 A 30 gpm leak will occur in the Auxiliary Building. The crew will address the ARP and 40AO-9ZZ02 Excessive RCS Leakrate and isolate Letdown.

Event 4 The CRS will enter 40AO-9ZZ05 Loss of Charging or Letdown and direct the crew to establish conditions for extended loss of Letdown.

Event 5 C Condenser Air Removal Pump will trip on overcurrent. The crew will address the ARP, start the D Condenser Air Removal Pump and align the suction to the Main Condenser.

Event 6 A small 20 gpm RCS leak will occur. The CRS will enter 40AO-9ZZ02, Excessive RCS Leakrate. After addressing Technical Specifications, the leak will increase and the CRS will direct the crew to start all available Charging Pumps and isolate Letdown. The leakrate will exceed Charging pump capacity and the CRS will direct a manual Reactor trip.

Event 7 The CRS will enter 40EP-9EO01, Standard Post Trip Actions. When SIAS actuates, the B HPSI pump will have a sheared shaft and A HPSI will fail to auto-start. After SPTAs are complete, the CRS will transition to 40EP-9EO03 and direct the crew to place Hydrogen Analyzers in service.

PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 3 Critical Task # 1: When the Safety Injection Actuation setpoint is exceeded (Start time is when Pressurizer pressure - 1837 psia OR Containment pressure - 3 psig), ensure adequate Safety Injection flow to meet Safety Function requirements within 30 minutes of exceeding the SIAS setpoint.

Safety Significance: This is based on a degraded core cooling system. Inadequate SI flow may result in loss of Subcooled margin and/or core uncovery, and increases the risk of core damage. The 30 minute time requirement is based on 15 minutes (time requirement to complete Safety Function Status Checks) to diagnose the loss of HPSI flow, and 15 minutes for mitigating actions Cueing: Board indications will provide the initial cue that the crew has lost the required SI flow.

Procedural direction will provide the cue to initiate SI flow. Safety Function Status Check is also a possible cue to the crew that they have lost a safety function.

Measurable Performance Indicator: The crew will restore SI flow by manually starting the HPSI pump that failed to auto-start (A HPSI pump).

Performance Feedback: When the crew has started the A HPSI pump there will be indication of HPSI flow on B02 analog indicators and ERFDADS digital indicators.

This Critical Task and the 30 minutes time requirement meets Operations Management expectations for an Operating Crew Critical Task # 2: Place both Hydrogen Analyzers in service within 30 minutes of the LOCA Basis for CT bounding criteria: Placing all available Hydrogen Analyzers in service within 30 minutes of the start of a LOCA is listed in the PVNGS Time Critical Action Program (TCA-55) and is based on the PVNGS UFSAR section 6.2.5.2.1.

Safety Significance: Per the PVNGS UFSAR, Hydrogen Analyzers must be placed in service within 30 minutes of a LOCA. The crew must be aware of hydrogen concentration inside containment to ensure the Containment Temperature and Pressure Control safety function is met, to determine when hydrogen recombiners or hydrogen purge must be placed in service, and to monitor potential EAL escalation criteria based on containment hydrogen levels.

Cueing: The crew will have procedural direction to place Hydrogen Analyzers in service per 40EP-9EO03, LOCA.

Measurable Performance Indicator: The crew will open the inside and outside containment isolation valve for the Hydrogen Analyzers and place the Power/Control handswitch for each analyzer to the ANALYZE position. The H2 analyzers must be in service within 30 minutes of the LOCA.

Performance Feedback: The crew will have indication of the CIVs being open as indicated by a red light on each valve and the red ANALYZE light being illuminated on each Hydrogen Analyzer.

This Critical Task and the 30 minutes time requirement meets Operations Management expectations for an Operating Crew PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 3 NOTE: (Per NUREG-1021 Appendix D) If an operator or the Crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a Critical Task identified in the post-scenario review Driver Setup Instructions Reset to IC-20 Run scenario file NRC Scenario # 3 Hang OOS tags on AFA-P01, place protected placards over AFB-P01 and AFN-P01 PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 3 Event Type Malf # Description Final Initiator rfFW59 AFA-P01 OOS TRIP rfFW60B OFF rfFW57 CLOSE crB4FW08AFAHV32_1 OPEN crB4FW08AFAUV37_1 OPEN crB5FW08AFCHV33_1 OPEN crB5FW08AFCUV36_1 OPEN crB4MS13SGAUV134_1 OPEN crB4MS13SGAUV138_1 OPEN 1 MF cmTRCH05HCAPT351A_1 Containment Pressure 20 Key 1 Instrument 351A Fails High 2 MF cmTRRC03RCNPT100X_1 Pressurizer Pressure 1500 Key 2 Transmitter 100X Fails Low 3 MF mfCV04 Letdown Leak 3 Key 3 4 Loss of Letdown 5 MF cmDPMC03ARNP01C_6 C Condenser Air Key 5 Removal Pump Trip 6 MF mfTH01A RCS Leak .01 Key 6 7 MF mfTH01A SBLOCA 0.12 8 MF cmCPSI01SIBP02_6 'B' HPSI Trips, 'A' cmCPSI01SIAP02_5 HPSI FTAS PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Crew Turnover Sheet Form ES-D-1 NRC Exam Scenario # 3 Plant Conditions:

Unit 1 is operating at 100% power, MOC There are no personnel inside Containment Equipment Out of Service:

AFA-P01 was taken out of service last shift for preventative maintenance o LCO 3.7.5 Condition A and B has been entered o AFB-P01 and AFN-P01 are protected Planned Shift Activities:

Maintain 100% power PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 1 Page 7 of 20 Event

Description:

Containment Pressure Transmitter HCA-PI-351A fails high Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 1, HCA-PI-351A fails high Indications available:

5A06C HI CNTMT PRESS CH TRIP alarm Examiner Note: The following steps are from the B05A Alarm Response Procedure alarm window 5A06C:

Procedure Note:

The following Technical Specifications may be impacted:

o LCO 3.3.1, Reactor Protection System (RPS) Instrumentation - Operating o LCO 3.3.5 Engineered Safety Features Actuation System (ESFAS)

Instrumentation o LCO 3.6.4, Containment Pressure BOP Compare ALL of the following instrumentation to confirm the alarm: (B05)

HCA-PI-351A, Containment Pressure HCB-PI-351B, Containment Pressure HCC-PI-351C, Containment Pressure HCD-PI-351D, Containment Pressure BOP If the alarm is confirmed to be invalid, THEN place any affected channel in BYPASS at the associated Plant Protection System (PPS) cabinet::

SBA-C01, Plant Protection Sys cabinet SBB-C01, Plant Protection Sys cabinet SBC-C01, Plant Protection Sys cabinet SBD-C01, Plant Protection Sys cabinet Examiner Note: The following steps are from 40OP-9SB02, Plant Protection System Bypass Operations, Section 6.1, Placing PPS Channel Parameters in Bypass:

Procedure Note:

PPS bypass operations are performed at the PPS system cabinets SBA-C01, SBB-C01, SBC-C01, SBD-C01.

BOP REFER TO Appendix A - PPS (RPS/ESFAS), Parameters, Indicators, LCOs/TLCOs.

BOP Select the channel to be placed in bypass:

A BOP Select the parameter(s) to be placed in bypass:

13 - Containment Pressure High BOP Request the SM/CRS enter and log the appropriate LCO/TLCO required actions.

Technical Specifications:

LCO 3.3.1, Reactor Protection System (RPS) Instrumentation - Operating, Condition A o Place channel in bypass or trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore channel to OPERABLE status prior to entering MODE 2 following next MODE 5 entry LCO 3.3.5, Engineered Safety Features Actuation System (ESFAS) Instrumentation, Condition A o Place channel in bypass or trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore channel to OPERABLE status prior to entering MODE 2 following next MODE 5 entry BOP Place the selected parameter(s) in bypass.

PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 1 Page 8 of 20 Event

Description:

Containment Pressure Transmitter HCA-PI-351A fails high Time Position Applicant Actions OATC Perform Independent Verifications per 02DP-0ZZ01, Verification of Plant Activities.

Examiner Note: When the crew has placed the parameter in bypass and the CRS has addressed Technical Specifications, or at the lead evaluators discretion, proceed to Event 2, Pressurizer Pressure Transmitter 100X fails low PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 2 Page 9 of 20 Event

Description:

Pressurizer Pressure Transmitter 100X fails low Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 2, Pressurizer Pressure Transmitter 100X fails low Indications available:

4A01B PZR PRESS HI-LO alarm All Pressurizer heaters energize Pressurizer pressure rising Examiner Note: The following steps are from the B04A Alarm Response Procedure alarm window 4A01B:

Procedure note:

Pressure dropping below 2100 psia will cause a step change reduction in CPC DNBR Margin (approx. 0.15) possibly resulting in CPC DNBR pre-trips or trips OATC Check BOTH of the following pressure instruments:

RCN-PR-100, L) Pressure PT-100X RCN-PR-100, R) Pressure PT-100Y OATC IF ONE of the following controlling channels is failed:

RCN-PR-100, L) Pressure PT-100X THEN place RCN-HS-100, Pressure Control Channel X/Y Selector, to the unaffected channel (100Y)

OATC IF ANY of the following Pressurizer proportional heater handswitches indicate the tripped condition:

RCN-HS-100-1, Proportional Heaters Bank RCN-HS-100-2, Proportional Heaters Bank THEN take BOTH of the following Pressurizer proportional heater handswitches to ON:

RCN-HS-100-1, Proportional Heaters Bank RCN-HS-100-2, Proportional Heaters Bank Examiner Note: When the crew has switched RCN-HS-100 to 100Y and reset Pressurizer proportional heaters, or at the lead evaluators discretion, proceed to Event 3, Letdown line leak PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 3 Page 10 of 20 Event

Description:

Letdown line leak Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 3, Letdown line leak Indications available:

2B01A ESF EQPT RMS LVL HI alarm ERFDADS will indicate approximately 30 gpm leakrate Letdown control valves throttling closed RU-9, Auxiliary Building Lower Level Ventilation Exhaust alarm RU-156, 100-foot Auxiliary Building West Penetration Area Monitor RU-157, 120-foot Auxiliary Building West Penetration Area Monitor RU-153, 100-foot West Auxiliary Building Area Monitor Examiner Note: The following steps are from the B02B Alarm Response Procedure alarm window 2B01A:

OATC Direct an Auxiliary Operator to perform the following:

Confirm the alarm Determine the cause of the alarm OATC IF the Auxiliary Operator identifies leakage, THEN direct the Auxiliary Operator to isolate the leakage Driver Cue: When directed to investigate for a leak in the Auxiliary Building, wait 5 minutes and report:

There is a significant leak In the 80 foot West Mechanical Penetration room. It is located on letdown piping because there was steam issuing from the pipe.

If directed to manually isolate the leak, report I am currently outside of the room and I dont think it is safe for me to re-enter the room.

Examiner Note: The following steps are from 40AO-9ZZ02, Excessive RCS Leakrate:

OATC IF pressurizer level is lowering, AND additional makeup is required, THEN ensure all available Charging Pumps are running OATC IF all available Charging Pumps are running, AND pressurizer level is lowering, THEN isolate letdown CRS Ensure the event is being classified Procedure Note:

Appendix I, LCO Required Action Tracker, is reference use, and may be performed by CRS, but should be provided to the SM or STA to be used as a guide to the LCO required actions CRS Initiate Appendix I, LCO Required Action Tracker CRS IF the unit is in Mode 1-4, THEN ensure compliance with LCO 3.4.14, RCS Operational Leakage (REFER TO Appendix I, LCO Required Action Tracker)

CRS Direct Chemistry to perform 74DP-9ZZ05, Abnormal Occurrence Checklist CRS Notify Radiation Protection that an RCS leak exists PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 3 Page 11 of 20 Event

Description:

Letdown line leak Time Position Applicant Actions OATC Determine the leakrate using ANY of the following:

Appendix A, 15 Minute Leak Rate Calculation Appendix B, ERFDADS Calculation of RCS Water Inventory 40ST-9RC05, Manual Calculation of RCS Water Inventory 40ST-9RC08, OAP Calculation of RCS Water Inventory CRS Attempt to identify the source of the leakage BOP Direct an operator to walkdown charging and letdown piping OATC IF a leak in Letdown is indicated, THEN perform the following:

IF the leak rate is such that letdown temperature can be lowered prior to isolation, THEN perform the following:

o Reduce letdown flow using RCN-LIC-110 in manual to lower letdown temperature o WHEN Regenerative Heat Exchanger Letdown Temperature is less than 180°F as indicated on CHN-TI-221, THEN isolate letdown Letdown will be isolated using one of the following valves CHB-UV-515 CHA-UV-516 CHB-UV-523 IF the leak rate is such that letdown should be isolated as quickly as possible, OR leak location warrants no further cooling, THEN isolate letdown PERFORM 40AO-9ZZ05, Loss of Charging or Letdown Examiner Note: All validation crews isolated letdown without cooling it down PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 4 Page 12 of 20 Event

Description:

Loss of Letdown Time Position Applicant Actions Examiner Note: Once the crew isolates Letdown, the CRS will enter 40AO-9ZZ05, Loss of Charging or Letdown. The following steps are from 40AO-9ZZ05, Loss of Charging or Letdown:

OATC IF BOTH of the following occur at any time during this procedure:

Pressurizer level lowers to 33%

Restoration of charging is NOT impending THEN trip the Reactor OATC IF BOTH of the following conditions are met:

The CRS determines seal injection and charging are to be stopped Pressurizer level is rising and 56% level will be challenged THEN perform the following:

Place all Charging Pumps in PULL TO LOCK Ensure controlled bleedoff is isolated on all standby RCPs prior to Seal 2 outlet temperature exceeding 250°F Close the Seal Injection Flow Control Valves IF the unit is in MODE 1, 2, or 3, THEN ensure compliance with LCO 3.4.9, Pressurizer PERFORM Appendix C, Extended Operations Without Letdown, to adjust PZR level, Seal Injection, or VCT level Examiner Note: When the crew has performed has isolated seal injection and the CRS has addressed Technical Specifications, or at the lead evaluators discretion, proceed to Event 5, C Main Condenser Air Removal Pump trip.

PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 5 Page 13 of 20 Event

Description:

C Main Condenser Air Removal Pump Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 5, C Main Condenser Air Removal Pump trip Indications available:

7A01A Condenser Air Removal System Trouble Examiner Note: The following steps are from 40AL-9RK7A, Panel B07A Alarm Responses alarm window 7A01A:

BOP Determine the affected Air Removal Pump using the hand switch indicator lights on panel B07:

ARN-HS-25, Cond Air Removal Pmp A ARN-HS-26, Cond Air Removal Pmp B ARN-HS-27, Cond Air Removal Pmp C ARN-HS-28, Cond Air Removal Pmp D BOP IF ANY of the following conditions exist:

ARN-P01A, A Air Removal Vacuum Pump, is stopped ARN-P01B, B Air Removal Vacuum Pump, is stopped ARN-P01C, C Air Removal Vacuum Pump, is stopped THEN perform the following:

Ensure ARN-P01D, D Air Removal Vacuum Pump, running Open ONE Condenser suction valve as directed by the SM/CRS o ARN-UV-014, using ARN-HS-014, Cond A Air Removal Suction Vlv o ARN-UV-015, using ARN-HS-015, Cond B Air Removal Suction Vlv o ARN-UV-016, using ARN-HS-016, Cond C Air Removal Suction Vlv BOP Direct an Auxiliary Operator to investigate the cause of the trip:

ARN-P01C - NGN-L01C4 - TB 140 ft Driver Cue: When directed to investigate the cause of C Condenser Air Removal Pump, wait 3 minutes and report:

The C Condenser Removal Pump is not running and the motor is warm to the touch When directed to investigate the C Condenser Air Removal Pump breaker, wait 5 minutes and report:

The C Condenser Removal Pump breaker is tripped with an 86 lockout Examiner Note: When the crew has started the D Air Removal pump and aligned it to the Main Condenser, or at the lead evaluators discretion, proceed to Event 6, A RCS Leak.

PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 6 Page 14 of 20 Event

Description:

RCS Leak Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 6, RCS Leak (~20 gpm)

Indications available:

Letdown Control Valves closing Containment Sump levels rising Containment humidity rising RU-1, Containment Atmosphere radiation alarm OATC IF pressurizer level is lowering, AND additional makeup is required, THEN ensure all available Charging Pumps are running OATC IF all available Charging Pumps are running, AND pressurizer level is lowering, THEN isolate letdown CRS Ensure the event is being classified Procedure Note:

Appendix I, LCO Required Action Tracker, is reference use, and may be performed by CRS, but should be provided to the SM or STA to be used as a guide to the LCO required actions CRS Initiate Appendix I, LCO Required Action Tracker Technical Specifications:

LCO 3.4.14, RCS Operational LEAKAGE, Condition A & B o Reduce LEAKAGE to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months o Required Action and associated Completion Time of Condition A not met, be in MODE 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND be in MODE 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months CRS IF the unit is in Mode 1-4, THEN ensure compliance with LCO 3.4.14, RCS Operational Leakage (REFER TO Appendix I, LCO Required Action Tracker)

CRS Direct Chemistry to perform 74DP-9ZZ05, Abnormal Occurrence Checklist CRS Notify Radiation Protection that an RCS leak exists OATC Determine the leakrate using ANY of the following:

Appendix A, 15 Minute Leak Rate Calculation Appendix B, ERFDADS Calculation of RCS Water Inventory 40ST-9RC05, Manual Calculation of RCS Water Inventory 40ST-9RC08, OAP Calculation of RCS Water Inventory Examiner Note: Validation crews used ERFDADS Leak Rate Determination. The following steps are from Appendix B, ERFDADS Leak Rate Determination:

OATC Ensure Tc is constant OATC Check that pressurizer pressure is stable between 2235 psia and 2265 psia OATC Ensure Chemistry is NOT drawing samples from the RCS or CVCS OATC Ensure that ONE of the following conditions exist:

Letdown is aligned to the VCT Letdown is isolated OATC Ensure that ONE of the following conditions exist:

Charging pump suction is aligned to the VCT Charging pumps are stopped PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 4 Page 15 of 20 Event

Description:

Loss of Letdown Time Position Applicant Actions OATC Place CHN-FIC-210X, Reactor Makeup Water to VCT, in MANUAL with zero output OATC Place CHN-FIC-210Y, Boric Acid Makeup to VCT, in MANUAL with zero output OATC Place CHN-HS-527, Make-up to Charging Pumps (VCT Bypass) Valve in CLOSED OATC When CHN-UV-527 indicates closed, Then place CHN-HS-210, Makeup Mode Select Switch, in MANUAL OATC Select the RCS LEAK RATE box on the SPDS Overview screen OATC Select the TREND-1 button on the Analog Point Attributes screen for point SPDS5047 OATC Ensure both of the following on the trend screen for SPDS5047 Range (-20) to 80 gpm Trend length 30 mins OATC If conditions (such as leakrate getting worse) require restoration of VCT Makeup prior to completing data collection, then go to step 18 OATC Allow the trend to run for at least 15 minutes, or until VCT level has lowered to 15%

OATC Step 18: Restore VCT makeup by performing the following:

Place CHN-HS-210 in AUTO Place CHN-HS-527 in OPEN/AUTO Place CHN-FIC-210X in AUTO Place CHN-FIC-210Y in AUTO Examiner Note: When the CRS has evaluated Technical Specifications, or at the lead evaluators discretion proceed to Event 7, Small Break LOCA PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 7,8 Page 16 of 20 Event

Description:

Small Break LOCA / B HPSI Pump Trip, A HPSI Pump FTAS Time Position Applicant Actions Driver Cue: When directed increase RCS Leak Rate, mfTH01A, severity to 0.12 (~240 gpm)

Examiner Note: When the leakrate increases to the point where all Charging Pumps are running with letdown isolated and Pressurizer level continues to lower, the crew will manually trip the Reactor. The following steps are from 40EP-9EO01, Standard Post Trip Actions:

BOP Determine that Reactivity Control acceptance criteria are met:

Check that reactor power is dropping Check that startup rate is negative Check that full strength CEAs are inserted Check that the Main Turbine is tripped OATC Determine the Maintenance of Vital Auxiliaries acceptance criteria are met:

Check the Main Generator output breakers are open Check that station loads have transferred to offsite electrical power such that BOTH of the following conditions are met:

All vital and non-vital AC buses are powered All vital and non-vital DC buses are powered OATC Determine that RCS Inventory Control acceptance criteria are met:

Check that pressurizer level meets BOTH of the following:

10-65%

Trending as expected to 33-53%

(CA) Restore and maintain pressurizer level to 33-53%

by any of the following:

Operation of PLCS Manual operation of Charging Pumps and Letdown Control Valves Check that the RCS is 24°F or more subcooled (CA) IF the RCS is less than 24F subcooled, THEN stop all RCPs Check that BOTH of the following are in service to all RCPs:

Seal injection Nuclear Cooling Water (CA) Isolate controlled bleedoff from ANY RCP(s) as appropriate. REFER TO 40AO-9ZZ04, RCP Emergencies, Appendix E, Control Board B04 Label OATC Determine that RCS Pressure Control acceptance criteria are met:

Pressurizer pressure is 1837-2285 psia Pressurizer pressure is trending as expected to 2225-2275 psia (CA) Restore and maintain pressurizer pressure to the normal control band by ANY of the following:

Operation of PPCS Manual operation of pressurizer heaters and spray valves (CA) IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated (CA) IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop (CA) IF pressurizer pressure drops below the RCP NPSH limits, THEN stop all RCPs. REFER TO Appendix 2, Figures PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 7 Page 17 of 20 Event

Description:

Small Break LOCA Time Position Applicant Actions Examiner Note: B HPSI pumps shaft will shear and A HPSI pump will fail to autostart. The crew will manually start A HPSI pump.

Critical Task # 1:

When the Safety Injection Actuation setpoint is exceeded (Start time is when Pressurizer pressure - 1837 psia OR Containment pressure - 3 psig), ensure adequate Safety Injection flow to meet Safety Function requirements within 30 minutes of exceeding the SIAS setpoint.

SAT / UNSAT OATC Determine that Core Heat Removal acceptance criteria is met:

At least one RCP is operating Loop delta-T is less than 10°F RCS is 24°F or more subcooled BOP Determine that RCS Heat Removal acceptance criteria are met:

Check that at least one SG meets BOTH of the following:

Level is 35% WR or more Feedwater is restoring or maintaining level 45-60% NR (CA) Restore and maintain level in at least one SG 45-60% NR Check that Tc is 560-570°F (CA) IF Tc is greater than 570°F, THEN perform the following:

Ensure that feedwater is being restored to at least one SG Restore Tc to 560-570°F using SBCS or ADVs (CA) IF Tc is less than 560°F, THEN perform the following:

Ensure feed flow is NOT excessive Ensure SG Blowdown is isolated Restore Tc to 560-570°F using SBCS or ADVs IF MSIS has actuated AND the cooldown terminates, THEN stabilize Tc using ADVs IF AFAS has actuated AND at least one SG level is 10%

WR or more, THEN override and throttle Auxiliary Feedwater to maintain Tc 560-570°F Check that SG pressure is 1140-1200 psia (CA) IF SG pressure drops to the MSIS setpoint, THEN ensure MSIS has actuated (CA) IF SG pressure is less than 1140 psia, THEN perform the following:

Ensure the SBCS valves are closed Ensure the ADVs are closed (CA) IF SG pressure is greater than 1200 psia, THEN restore and maintain SG pressure to less than 1200 psia using SBCS or ADVs PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 7 Page 18 of 20 Event

Description:

Small Break LOCA Time Position Applicant Actions OATC Determine that Containment Isolation acceptance criteria are met:

Check that containment pressure is less than 2.5 psig (CA) IF containment pressure is 3 psig or more, THEN ensure that CIAS has been initiated Check BOTH of the following conditions:

No abnormal containment area activity No abnormal steam plant activity OATC Determine that Containment Temperature and Pressure Control acceptance criteria are met:

Check that containment temperature is less than 117°F Check that containment pressure is less than 2.5 psig (CA) IF containment pressure is 3 psig or more, THEN ensure that CIAS has been initiated (CA) IF containment pressure is 8.5 psig or more, THEN perform the following:

Ensure CSAS is actuated Ensure at least one Containment Spray header flow is greater than 4350 gpm Stop all of the operating RCPs Ensure RCP controlled bleedoff is isolated CRS Diagnose the event(s) in progress and GO TO the appropriate procedure Examiner Note: The CRS will determine that a Small Break LOCA inside of Containment is in progress. The CRS will enter 40EP-9EO03, Loss of Coolant Accident. The following steps are from 40EP-9EO03, Loss of Coolant Accident:

CRS Monitor the SFSCs by performing the following:

Check that the Safety Function Status Check acceptance criteria are satisfied Ensure that the Steam Generator Sample valves are open Direct chemistry to perform 74DP-9ZZ05, Abnormal Occurrence Checklist CRS Ensure the event is being classified.

CRS Open the Placekeeper and enter the EOP Entry Time.

OATC If pressurizer pressure drops to the SIAS setpoint, then check that SIAS is actuated.

OATC IF SIAS has actuated, THEN perform the following:

Check that the HPSI and LPSI Pumps have started Check that safety injection flow is adequate. Refer to Appendix 2, Figures PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 7 Page 19 of 20 Event

Description:

Small Break LOCA Time Position Applicant Actions OATC IF SIAS has actuated, THEN perform the following:

IF it is determined that RWT level may lower to less than 73% during the event, OR it is desired to align Charging Pump suction through an alternate suction path, THEN PERFORM ONE of the following:

Appendix 10, Charging Pump Alternate Suction to the RWT /

Restoration Appendix 11, Charging Pump Alternate Suction to the SFP /

Restoration If RWT level is above 73%, and it is desired to align Charging Pump suction through CHE-HV-536 or CHN-UV-514, Then perform Appendix 103, RCS Makeup/Emergency Boration.

OATC IF pressurizer pressure remains below the SIAS setpoint, THEN perform the following:

Ensure ONE RCP is stopped in each loop.

IF RCS subcooling is less than 24°F [44°F], THEN ensure all RCPs are stopped.

OATC If any RCPs are operating, then perform Appendix 16, RCP Trip Criteria and check the RCP operating limits satisfied.

OATC IF pressurizer pressure remains below the SIAS setpoint, THEN perform the following:

Ensure ONE RCP is stopped in each loop.

IF RCS subcooling is less than 24°F [44°F], THEN ensure all RCPs are stopped.

OATC PERFORM Appendix 117, Placing Hydrogen Analyzers In Service.

BOP If containment pressure is 3 psig or more, then check CIAS is actuated.

BOP If CIAS has actuated, then perform the following:

Check that an isolation valve is closed for each containment penetration required to be closed OATC IF the following conditions exist:

The Containment Spray Pump(s) are operating on the miniflow(s)

Containment pressure is not expected to exceed 8.5 psig within one hour of the CS Pump start THEN stop the Containment Spray Pump(s).

The following steps are from 40EP-9EO10-117, Appendix 117: Placing Hydrogen Analyzers in Service:

OATC Perform the following to place Hydrogen Analyzer Train A in service:

Open HPA-UV-1, Containment Isolation Valve Open HPA-HV-7A/7B, Containment Isolation Valves Place handswitch HPA-HS-9A, Power/Control, in the ANALYZE position OATC Perform the following to place Hydrogen Analyzer Train B in service:

Open HPA-UV-2, Containment Isolation Valve Open HPA-HV-8A/8B, Containment Isolation Valves Place handswitch HPA-HS-10A, Power/Control, in the ANALYZE position PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 3 Event # 7 Page 20 of 20 Event

Description:

Small Break LOCA Time Position Applicant Actions Critical Task # 2:

Place both Hydrogen Analyzers in service within 30 minutes of the LOCA Start time is when all available charging pumps running and letdown isolated _________

End time is when both Hydrogen Analyzer switches in the Analyze position __________

SAT / UNSAT Examiner Note: When the crew has placed both Hydrogen Analyzer in service, or at lead evaluators discretion, the scenario may be terminated PVNGS 2020 NRC Scenario # 3 Rev 2

Appendix D Scenario Outline Form ES-D-1 Facility: Palo Verde Scenario: 4 Test: 2020 NRC Exam Examiners: Operators:

Initial Conditions: 2%, BOC Turnover: Maintain power at 2%

Event Number Event Type* Event Description 1 TS (CRS) RU-1 fails high 2 I (OATC) Seal Injection controller CHN-FIC-242 fails to 100%

3 C (CRS, BOP), TS Inadvertent B AFAS-1 (CRS) 4 I (All) TT-111Y fails high 5 M (All) SGTR ramped over 5 minutes 6 10 minutes after the Reactor trip an ESD occurs on the ruptured SG outside of Containment 7 C (OATC) One CEA stuck out on the Reactor trip

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Actual Target Quantitative Attributes 7 Total malfunctions (5-8) 2 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 1 Major transients (1-2) 1 EOPs entered requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Scenario Event Summary Form ES-D-1 NRC Exam Scenario # 4 2020 NRC Exam Scenario # 4 Overview Event 1 Containment Atmosphere Radiation Monitor RU-1 fails high. The crew will address the ARP and the CRS will address Technical Specifications.

Event 2 RCP 1B Seal Injection Flow controller CHN-FIC-242 fails to 100% causing the associated valve to close. The crew will address the ARP and take manual control of the controller and re-open the valve.

Event 3 A Train B inadvertent AFAS occurs. The CRS will enter 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations. The crew will take action to stop feeding SG #1 with AFB-P01 to prevent overfeeding and Reactor power to rise.

Event 4 Loop 1A Temperature Transmitter TT-111Y fails high causing all charging pumps to causing letdown flow to lower and pressurizer level to rise. The crew will address the ARP and the CRS will enter 40AO-9ZZ16, RRS Malfunction. The crew will take manual control of Pressurizer level and stabilize level. The CRS will direct the crew to select the unaffected Tavg on the Reactor Regulating System panel Event 5 A SGTR occurs on SG #1. The leak will be ~ 400 gpm and will ramp in over 5 minutes. The CRS will enter 40AO-9ZZ02, Excessive RCS Leakrate, and direct the crew to start all available Charging Pumps and isolate Letdown. The leakrate will exceed Charging pump capacity and the CRS will direct a manual Reactor trip.

Event 6 10 minutes after the Reactor trip an ESD occurs on the ruptured SG #1 outside of Containment. The CRS will enter 40EP-9EO09, Functional Recovery, and crew will feed SG #1 1360-1600 gpm.

Event 7 During the Reactor trip, one CEA will not insert into the core and the CRS will direct borating the RCS per 40EP-9EO10-103, Appendix 103: RCS Makeup / Emergency Boration PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 4 Critical Task # 1: Commence borating to the RCS at a rate of 26 gpm within 15 minutes of the reactor trip due to less than all full-strength CEAs being fully inserted.

Safety Significance: Per the Time Critical Action Program, commence emergency boration (MODES 3 -

5) within 15 minutes due to minimum shutdown margin less than limit in COLR. With less than all full strength CEAs fully inserted, the SDM is assumed to be less than minimum required. Justification for the 15 minutes is from 40DP-9ZZ04, Time Critical Action Program. Justification for the 26 gpm limit is from Technical Specification Bases for LCO 3.1.1, SDM - Reactor Trip Breakers Open.

Cueing: The crew will have indication of the stuck CEA from the Rod Bottom Light for the CEA failing to illuminate on the trip as well as the CPDS (CEA Position Display System) indicating one CEA failed to insert on the reactor trip.

Measurable Performance Indicator: The crew will align Charging Pump suction from the Refueling Water Tank (RWT) and ensure adequate Charging Pump flow of greater than or equal to 26 gpm. The crew will have to manually start a Charging Pump to achieve the minimum required boration flow of 26 gpm. Additionally, the crew will need to start at least one Charging Pump per step 4 of SPTAs for inventory control as well as to utilize Auxiliary Spray to control RCS pressure. Adequate boration flow can also be seen using the CVCS System Diagram using an ERFDADS computer display.

Performance Feedback: The crew will have indication of boration flow by ensuring the Charging Pump suction has been aligned to the Refueling Water Tank and Charging Pump flow is 26 gpm.

This Critical Task and the 15 minute time requirement meets Operations Management expectations for an Operating Crew PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 4 Critical Task # 2: Establish a feedrate of 1360-1600 gpm to SG #1 prior to exiting HR-2, RCS and Core Heat Removal, SG with SI.

Safety Significance: An event in which a SG has a tube leak or rupture concurrently with an unisolable steam leak to atmosphere will result in a radioactive release to the atmosphere. A feedrate of 1360-1600 gpm to the affected SG is performed in order to expeditiously establish sufficient inventory in the affected SG to ensure the U-tubes are covered (~ 45% NR), thus minimizing the release to the environment.

Cueing: The crew will have indication of SG tube leakage on SG #1 prior to the reactor trip from ERFDADS indicating a rising leakrate and SG #1 level rising. There will be no immediate Rad Monitor alarms because RU-142 measures N-16 and power is 2%. Once entering an EOP, the crew can also get confirmation from chemistry. The ESD outside of containment will be indicated steam flow on SG #1 rising and pressure on SG #1 lowering.

Measurable Performance Indicator: The crew will align 2 AFW pumps to supply feedwater to SG #1 for a total of 1360-1600 gpm, per step 15 of 40EP-9EO09, Functional Recovery, HR-2, SG with SI.

Performance Feedback: Total feed flow to the affected SG will be available using any ERFDADS computer terminal.

This Critical Task and establishing feed to the Ruptured/Faulted SG prior to exiting the FRP Success Path requirement meets Operations Management expectations for an Operating Crew NOTE: (Per NUREG-1021 Appendix D) If an operator or the Crew significantly deviates from or fails to follow procedures that affect the maintenance of basic safety functions, those actions may form the basis of a Critical Task identified in the post-scenario review PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 4 Driver Setup Instructions Reset to IC-8 Run scenario file NRC Scenario # 4 After the simulator is taken to Run, ensure that each SG is being fed at ~ 250 gpm Ensure that Tavg is 565 + 0.5°F by adjusting SBCS master controller PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Driver Set-Up Instructions Form ES-D-1 NRC Exam Scenario # 4 Event Type Malf # Description Final Initiator 1 MF mfRM01G RU-1 Fails High Key 1 2 MF cmCNCV04CHNFIC242_2 Seal Injection Controller 100 Key 2 Failure 3 MF mfRP06L1 Inadvertent 'B' AFAS-1 Key 3 mfRP06L2 4 MF cmTRRX05RCNTT111Y Temperature Transmitter 650 Key 4 111Y Fails High 5 MF mfTH06A SGTR on SG #1 Ramp to Key 5 40 6 MF mfMS03A Rx Trip ESD Outside Containment 10

+10 min 7 MF mfRD03K 1 Stuck CEA PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Crew Turnover Sheet Form ES-D-1 NRC Exam Scenario # 4 Plant Conditions:

Unit 1 is operating at 2% power BOC The pressurizer is in boron equalization Steam Generator level bands is 30-50% being fed with AFN-P01 via downcomer bypass valves There are no personnel in containment Equipment Out of Service:

None Planned Shift Activities:

Maintain 2% power PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 1 Page 8 of 19 Event

Description:

Containment Atmosphere Radiation Monitor RU-1 fails high Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 1, Containment Atmosphere Radiation Monitor RU-1 fails high Available indications:

RMS RU-1 alarm RMS RU-1 indicates a step increase high The following steps are from 74AL-9SQ01, Radiation Monitoring System Alarm Validation and

Response

BOP IF ANY of the following:

Channel 1 alarms Channel 2 alarms Channel 3 alarms THEN perform the following actions:

Notify RP of the alarm IF ANY of the following:

o The particulate channel indicates an increase in RCS leak rate (that is increasing radioactivity trend) o The gas channel indicates an increase in RCS leak rate (that is, increasing radioactivity trend)

THEN perform an RCS water inventory balance per 40ST-9RC02, ERFDADS (Preferred) Calculation of RCS Water Inventory Procedure Note:

The noble gas and particulate channels are Reactor Coolant System (RCS) leak detection channels required by Technical Specification 3.4.16. Alarm setpoints are set to alert personnel to a significant increase in RCS leakage. The iodine channel is used to only alert personnel to increased iodine levels for the purpose of keeping personnel exposure As Low As Reasonably Achievable (ALARA). The iodine channel is not used for indication of increased RCS leak rate Driver Cue: When contacted as RP/Effluents to report the status of RU-1, wait 1 minute and report:

RU-1 radiation monitor has failed PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 1 Page 9 of 19 Event

Description:

Containment Atmosphere Radiation Monitor RU-1 fails high Time Position Applicant Actions Technical Specifications:

LCO 3.4.16, RCS Leakage Detection Instrumentation, Condition B o Analyze grab samples of the containment atmosphere once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR perform SR 3.4.14.1 once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , AND restore required containment atmosphere radioactivity monitor to OPERABLE status within 30 days Examiner Note: When the CRS has evaluated Technical Specifications, or at the lead evaluators discretion, proceed to Event 2 Seal Injection Controller CHN-FIC-242 fails to 100%

PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 2 Page 10 of 19 Event

Description:

Seal Injection Controller CHN-FIC-242 fails to 100%

Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 2, Seal Injection Controller CHN-FIC-242 fails to 100%

Available indications:

3A11B RCP SEAL INJ FLOW HI-HI OR LO alarm Examiner Note: The crew may mitigate the event using the ARP or AOP. The following steps are from 40AL-9RK3A, Panel B03A Alarm Responses alarm window 3A11B:

OATC Check ALL of the following controllers:

CHN-FIC-241, Seal Inj to Reac Clnt Pmp 1A CHN-FIC-242, Seal Inj to Reac Clnt Pmp 1B CHN-FIC-243, Seal Inj to Reac Clnt Pmp 2A CHN-FIC-244, Seal Inj to Reac Clnt Pmp 2B Procedure Note:

If only a single charging pump is available and running, then closing CHB-HV-255 may prevent a loss of letdown on high temperature OATC If both of the following:

SM/CRS directs Power is available to CHB-HV-0255, Seal Injection Containment Isolation THEN close CHB-HV-0255, Seal Injection Containment Isolation, using CHB-HS-255, RCP SEAL INJ SPLY HDR ISOL VLV OATC Perform the following for the alarming seal injection controller:

Place the alarming seal injection controller in MANUAL Adjust the alarming seal injection controller to establish seal injection flow between 6 gpm and 7.5 gpm (preferred flow of 6.6 gpm)

OATC If the SM/CRS directs adjusting charging flow backpressure, THEN adjust CHN-PDIC-240, Charging Line to RC Loop 2A DP Control, to achieve between 2430 psig and 2500 psig on CHA-PI-212, Charging Pumps Dsch Header Pressure Driver Cue: If directed to report CHN-PDIS-241 pressure, wait 3 minutes and report:

RCP Seal Injection filter differential pressure CHN-PDIS-241 is 10 psid Examiner Note: The following step is from 40AO-9ZZ04, Reactor Coolant Pump Emergencies, Section 4.0:

OATC IF Seal Injection is in service, THEN adjust flow to 6.0 to 7.5 gpm Examiner Note: When Seal Injection Controller CHN-FIC-242 has been restored, OR at the lead evaluators discretion, proceed to Event 3 Inadvertent Train B AFAS-1 PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 3 Page 11 of 19 Event

Description:

Inadvertent Train B AFAS Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 3, Inadvertent Train B AFAS-1 Available indications:

Multiple alarms AFB-P01 will commence feeding SG #1 Reactor power rising The following steps are from 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations:

BOP Override and operate Auxiliary Feedwater Valves as needed to control SG level The BOP will override and close the following valves:

AFB-HV-30 AFB-UV-34 BOP IF AFA-P01 is running, perform the following:

Inform RP and the RMS technician of steaming to atmosphere IF AFA-P01 speed is less than 1000 rpm for greater than 5 minutes, THEN trip AFA-P01 by pressing AFA-HS-54A, Essential STM Driven AFW Pump Manual Trip BOP IF SG Blowdown is isolated, THEN perform the following:

Inform Chemistry that Blowdown is isolated IF COLSS is operable, THEN PERFORM 40OP-9SG03, Operating the SG Blowdown System, to insert zero for BOTH of the following constants in the CMC and PC:

o NKBMF1 o NKBMF2 OATC Perform the following:

PERFORM Appendix C, PPS-ESFAS Check, Step 2 and Step 3 to check that equipment actuated as expected Document components that failed to actuate in the Control Room Log Ensure compliance with TS for components that failed to actuate or were overridden Driver Cue: If I&C contacted to assist in troubleshooting the Inadvertent AFAS (the fuses will not indicate blown because there is no power), coordinate with the lead instructor, wait 5 minutes, enter the Control Room and inform the CRS:

Train B AFAS-1 fuses 65 and 75 are blown CRS Ensure compliance with BOTH of the following:

LCO 3.3.5, ESFAS Instrumentation LCO 3.3.6, ESFAS Logic and Manual Trip Technical Specifications:

LCO 3.3.6, Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip, Condition D o Restore channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months LCO 3.7.5, Auxiliary Feedwater (AFW) System, Condition B o Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 3 Page 12 of 19 Event

Description:

Inadvertent Train B AFAS Time Position Applicant Actions OATC IF the AFAS will NOT be reset at this time, THEN PERFORM Appendix C, PPS-ESFAS Check, Step 4.1 OATC Override and align equipment as directed by the CRS OATC Circle the as left condition of all components listed in the appropriate attachment Examiner Note: When the CRS has evaluated Technical Specifications, or at the lead evaluators discretion, proceed to Event 4 TCOLD Transmitter TT-111Y fails high PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 4 Page 13 of 19 Event

Description:

TCOLD Transmitter TT-111Y fails high Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 4, TCOLD Transmitter TT-111Y fails high Available Indications:

4A06A RC LOOPS TEMP HI alarm Letdown flow control valves closing Pressurizer level rising The following steps are from 40AO-9ZZ16, RRS Malfunctions:

OATC Ensure that CEDMCS is NOT in Auto Sequential OATC Check that pressurizer level is trending to the proper setpoint for reactor power Contingency Actions:

IF RCN-LIC-110, Pressurizer Level Control, is in Remote Auto, THEN transfer RCN-LIC-110 to MANUAL Ensure RCN-LIC-110 is in ONE of the following:

o Local Auto o Manual Maintain pressurizer level 33 to 53%

Ensure adequate charging flow for present plant conditions IF letdown isolates, THEN PERFORM 40AO-9ZZ05, Loss of Charging or Letdown OATC Determine the failed instrument by observing ALL of the following:

RCN-TT-111Y RCN-TT-121Y RCN-TT-111X RCN-TT-121X RCN-TR-100 BOP If BOTH of the following:

ALL of the following are NOT identified as failed instruments:

o RCN-TT-111Y o RCN-TT-121Y o RCN-TT-111X o RCN-TT-121X RCN-TR-100 indicates a failed instrument in the Tavg circuit THEN perform Attachment C-2, Determining the Failed Tavg Instrument CRS Determine the impact of the failure OATC IF RRS is selected to ONE of the following:

Average The affected instrument THEN perform the following:

IF RCN-LIC-110 is in Remote Auto, THEN transfer RCN-LIC-110 to MANUAL Ensure RCN-LIC-110 is in ONE of the following:

o Local Auto o Manual Perform Appendix C, Operation of the Reactor Regulating System, to select the unaffected instrument at the RRS Test Panel PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 4 Page 14 of 19 Event

Description:

TCOLD Transmitter TT-111Y fails high Time Position Applicant Actions OATC Check that Tavg/Tref mismatch is 3°F or less OATC Place CEDMCS in the desired mode of operation (Manual Sequential)

OATC IF Remote Automatic operation of the PLCS is desired, THEN perform the following:

Ensure RCN-LIC-110, Pressurizer Level Control, is in MANUAL Transfer RCN-LIC-110, Pressurizer Level Control, to Remote Automatic Examiner Note: When the crew checks DVM voltages, they will not be within the range provided in the procedure. The values in the procedure are for 100% power. The following steps are from 40AO-9ZZ16, RRS Malfunctions, Appendix C:

BOP IF a temperature instrument has failed, THEN perform the following:

Press the TEST PROBE pushbutton Check that DVM voltage indicates zero volts Press the DVM pushbutton that corresponds to the Tavg to be selected Record voltage indicated on the DVM for the selected Tavg (4.3V)

Check that DVM voltage recorded represents the normal Tavg for the current power level WHEN evaluation of DVM voltage is complete, THEN press the TEST PROBE pushbutton to disconnect the DVM from the input Place the Tavg input selector switch to the selected input (Tavg Loop 2)

Inform the CRS of the status of the RRS panel Examiner Note: When the BOP has informed the CRS that Loop 2 TAVE has been selected at the RRS panel (Do not wait for the crew to place LIC-110 in Remote/Auto) or at the lead evaluators discretion, proceed to Event 5 SGTR PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 5,6,7 Page 15 of 19 Event

Description:

SGTR / Stuck CEA / ESD on Ruptured SG Time Position Applicant Actions Driver Cue: When directed, INITIATE KEY 5, SGTR Available indications:

Pressurizer level lowering SG #1 level rising Driver Cue: If contacted as chemistry to sample both Steam Generators, ensure that SG sample valves are open, wait 5 minutes and report:

There is indication of Steam Generator tube leakage on SG #1. SG #2 is at background Examiner Note: The following steps are from 40AO-9ZZ02, Excessive RCS Leakrate:

OATC IF pressurizer level is lowering, AND additional makeup is required, THEN ensure all available Charging Pumps are running OATC IF all available Charging Pumps are running, AND pressurizer level is lowering, THEN isolate letdown CRS IF ALL of the following conditions exist:

All available Charging Pumps are operating Letdown is isolated Pressurizer level is lowering THEN perform the following:

Ensure that the Reactor is tripped GO TO 40EP-9EO01, Standard Post Trip Actions Examiner Note: When the leakrate increases to the point where all Charging Pumps are running with letdown isolated and Pressurizer level continues to lower, the crew will manually trip the Reactor. The following steps are from 40EP-9EO01, Standard Post Trip Actions:

BOP Determine that Reactivity Control acceptance criteria are met:

Check that reactor power is dropping Check that startup rate is negative Check that full strength CEAs are inserted (CA) Borate the RCS until adequate SDM is established using Appendix 103, RCS Makeup/Emergency Boration Check that the Main Turbine is tripped The following steps are from 40EP-9EO10-103, Appendix 103: RCS Makeup / Emergency Boration:

OATC Set the boric acid makeup flow rate on CHN-FIC-210Y, Boric Acid Makeup to VCT Flow Control, to less than or equal to 40 gpm OATC Set the Target makeup volume (gallons) on CHN-FQIS-210Y, Boric Acid Makeup Totalized Flow Control, to a minimum of 5000 gallons OATC Place CHN-HS-210, Makeup Mode Select Switch, in BORATE OATC Check one Boric Acid Makeup Pump is running OATC Ensure CHN-UV-527, Makeup to CHRG PMPS (VCT Bypass), is open OATC If the left pushbutton on CHN-FQIS-210Y indicates End, THEN press the End pushbutton PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 5,6,7 Page 16 of 19 Event

Description:

SGTR / Stuck CEA / ESD on Ruptured SG Time Position Applicant Actions OATC If the left pushbutton on CHN-FQIS-210Y indicates Reset, THEN press the Reset pushbutton OATC Ensure at least one Charging Pump is running OATC Ensure at least one of the running Charging Pumps is operating with handswitch in AFTER START OATC Press the Start pushbutton on CHN-FQIS-210Y OATC Check for BOTH of the following:

CHN-FIC-210X indicates no Reactor Makeup Water flow (CHN-FV-210X closed)

Proper flow indicated on CHN-FIC-210Y OATC Adjust the boric acid makeup setpoint on CHN-FIC-210Y to greater than or equal to 44 gpm Critical Task # 1:

Commence borating to the RCS at a rate of 26 gpm within 15 minutes of the reactor trip due to less than all full-strength CEAs being fully inserted.

SAT / UNSAT The following steps are a continuation of 40EP-9EO01, Standard Post Trip Actions BOP Determine the Maintenance of Vital Auxiliaries acceptance criteria are met:

Check the Main Generator output breakers are open Check that station loads have transferred to offsite electrical power such that BOTH of the following conditions are met:

All vital and non-vital AC buses are powered All vital and non-vital DC buses are powered Examiner Note: The Main Generator output breakers will remain closed because Motor Operator Disconnect PL-910 is open PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 5,6,7 Page 17 of 19 Event

Description:

SGTR / Stuck CEA / ESD on Ruptured SG Time Position Applicant Actions OATC Determine that RCS Inventory Control acceptance criteria are met:

Check that pressurizer level meets BOTH of the following:

10-65%

Trending as expected to 33-53%

(CA) Restore and maintain pressurizer level to 33-53%

by any of the following:

Operation of PLCS Manual operation of Charging Pumps and Letdown Control Valves Check that the RCS is 24°F or more subcooled (CA) IF the RCS is less than 24F subcooled, THEN stop all RCPs Check that BOTH of the following are in service to all RCPs:

Seal injection Nuclear Cooling Water (CA) Isolate controlled bleedoff from ANY RCP(s) as appropriate. REFER TO 40AO-9ZZ04, RCP Emergencies, Appendix E, Control Board B04 Label OATC Determine that RCS Pressure Control acceptance criteria are met:

Pressurizer pressure is 1837-2285 psia Pressurizer pressure is trending as expected to 2225-2275 psia (CA) Restore and maintain pressurizer pressure to the normal control band by ANY of the following:

Operation of PPCS Manual operation of pressurizer heaters and spray valves (CA) IF pressurizer pressure drops to the SIAS setpoint, THEN ensure that SIAS is actuated (CA) IF pressurizer pressure remains below the SIAS setpoint, THEN stop ONE RCP in each loop (CA) IF pressurizer pressure drops below the RCP NPSH limits, THEN stop all RCPs. REFER TO Appendix 2, Figures OATC Determine that Core Heat Removal acceptance criteria is met:

At least one RCP is operating Loop delta-T is less than 10°F RCS is 24°F or more subcooled PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 5,6,7 Page 18 of 19 Event

Description:

SGTR / Stuck CEA / ESD on Ruptured SG Time Position Applicant Actions BOP Determine that RCS Heat Removal acceptance criteria are met:

Check that at least one SG meets BOTH of the following:

Level is 35% WR or more Feedwater is restoring or maintaining level 45-60% NR (CA) Restore and maintain level in at least one SG 45-60% NR Check that Tc is 560-570°F (CA) IF Tc is greater than 570°F, THEN perform the following:

Ensure that feedwater is being restored to at least one SG Restore Tc to 560-570°F using SBCS or ADVs (CA) IF Tc is less than 560°F, THEN perform the following:

Ensure feed flow is NOT excessive Ensure SG Blowdown is isolated Restore Tc to 560-570°F using SBCS or ADVs IF MSIS has actuated AND the cooldown terminates, THEN stabilize Tc using ADVs IF AFAS has actuated AND at least one SG level is 10%

WR or more, THEN override and throttle Auxiliary Feedwater to maintain Tc 560-570°F Check that SG pressure is 1140-1200 psia (CA) IF SG pressure drops to the MSIS setpoint, THEN ensure MSIS has actuated (CA) IF SG pressure is less than 1140 psia, THEN perform the following:

Ensure the SBCS valves are closed Ensure the ADVs are closed (CA) IF SG pressure is greater than 1200 psia, THEN restore and maintain SG pressure to less than 1200 psia using SBCS or ADVs OATC Determine that Containment Isolation acceptance criteria are met:

Check that containment pressure is less than 2.5 psig (CA) IF containment pressure is 3 psig or more, THEN ensure that CIAS has been initiated Check BOTH of the following conditions:

No abnormal containment area activity No abnormal steam plant activity PVNGS 2020 NRC Scenario # 4 Rev 2

Appendix D Operator Actions Form ES-D-2 Operating Test: NRC Scenario # 4 Event # 5,6,7 Page 19 of 19 Event

Description:

SGTR / Stuck CEA / ESD on Ruptured SG Time Position Applicant Actions OATC Determine that Containment Temperature and Pressure Control acceptance criteria are met:

Check that containment temperature is less than 117°F Check that containment pressure is less than 2.5 psig (CA) IF containment pressure is 3 psig or more, THEN ensure that CIAS has been initiated (CA) IF containment pressure is 8.5 psig or more, THEN perform the following:

Ensure CSAS is actuated Ensure at least one Containment Spray header flow is greater than 4350 gpm Stop all of the operating RCPs Ensure RCP controlled bleedoff is isolated CRS Diagnose the event(s) in progress and GO TO the appropriate procedure Examiner Note: If the crew does not immediately diagnose SGTR, a chemistry sample will be requested at the beginning of each EOP.

Driver Cue: If contacted as chemistry to sample both Steam Generators or to perform 74DP-9ZZ05, Abnormal Occurrence Checklist, ensure the CR has opened SG sample valves, wait 5 minutes and report:

There is indication of Steam Generator tube leakage on SG #1. SG #2 is at background Examiner Note: 10 minutes after the Reactor is tripped, an unisolable ESD will occur on SG #1.

The CRS will diagnose 2 events in progress and enter 40EP-9EO09, Functional Recovery. For a faulted/ruptured SG, the CRS will go directly to the following trigger step in 40EP-9EO09, Functional Recovery (to achieve a 1360-1600 gpm feedrate, the BOP will either us AFA-P01 or re-energize panels that were load shed on SIAS and use AFB-P01 combined with AFN-P01):

BOP IF the SG with the tube rupture also has an ESD, AND it is uncontrollably steaming to atmosphere, THEN ensure at least ONE of the following conditions is met:

The affected SG has level being restored by feedwater flow 1360-1600 gpm The affected SG has level 45-60% NR with feedwater available to maintain level Critical Task # 2:

Establish a feedrate of 1360-1600 gpm to SG #1 prior to exiting HR-2, RCS and Core Heat Removal, SG with SI SAT / UNSAT When the crew has commenced feeding SG #1 at 1360-1600 gpm and level is rising, or at lead evaluators discretion, the scenario may be terminated PVNGS 2020 NRC Scenario # 4 Rev 2

ES-301 Transient and Event Checklist Form ES-301-5 Facility: PVNGS Date of Exam: 11/30/2020 Operating Test No.: 2020 A E Scenarios P V 1 2 (spare) 3 4 T M P E O I L N CREW POSITION CREW POSITION CREW POSITION CREW POSITION T N I T S O B S O B S O B S O B I C A R A O R A O R A O R A O M A T L O T P O T P O T P O T P U N Y C C C C M(*)

T P E R I U RX - - - - - - 0 1 NOR - - - - - - 0 1 I/C 2,4,5, 3,5,6 1,3,4, I1 2,3,6 6,7 7 1,4,5 5,6 3,4 10 4 MAJ 4 8 8 8 7 5,6 4 2 TS - 2,5 - - 1,6 - 2 2 RX - - - 0 1 NOR - - - 0 1 I/C 1,2,3, 2,3,4, I2 5 6,8 1,3,4 12 4 MAJ 4 7 5,6 4 2 TS - - 1,3 2 2 RX - - - 0 1 NOR - - - 0 1 I/C 1,2,3, I3 5 1,5 2,3,7 9 4 MAJ 4 7 5,6 4 2 TS 1,2,3 - - 3 2 RX - - - 0 1 NOR - - - 0 1 I/C 1,3,4, I4 2,3,6 5,6 3,4 10 4 MAJ 4 7 5,6 4 2 TS - 1,6 - 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

2020 PVNGS NRC Initial Exam Form ES-301-5 Rev 2

ES-301 Transient and Event Checklist Form ES-301-5 Facility: PVNGS Date of Exam: 11/30/2020 Operating Test No.: 2020 A E Scenarios P V 1 2 (spare) 3 4 T M P E O I L N CREW POSITION CREW CREW POSITION CREW POSITION T N I T POSITION I

C A S O B S O B S O B S O B M A T L R A O R A O R A O R A O U N Y O T P O T P O T P O T P M(*)

T P E C C C C R I U RX - - - 0 1 NOR - - - 0 1 I/C 1,2,3, 2,3,4,6 I5 5 ,8 1,3,4 12 4 MAJ 4 7 5,6 4 2 TS - - 1,3 2 2 RX - - - 0 1 NOR - - - 0 1 I/C 1,2,3, I6 5 1,5 2,3,7 9 4 MAJ 4 7 5,6 4 2 TS 1,2,3 - - 3 2 RX - - - 0 1 NOR - - - 0 1 I7 I/C 2,3,6 1,3,4,5,6 3,4 10 4 MAJ 4 7 5,6 4 2 TS - 1,6 - - 2 2 RX - - - 0 1 NOR - - - 0 1 I/C 1,2,3, 2,3,4,6 I8 5 ,8 1,3,4 12 4 MAJ 4 7 5,6 4 2 TS - - 1,3 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

2020 PVNGS NRC Initial Exam Form ES-301-5 Rev 2

ES-301 Transient and Event Checklist Form ES-301-5 Facility: PVNGS Date of Exam: 11/30/2020 Operating Test No.: 2020 A E Scenarios P V 1 2 (spare) 3 4 T M P E O I L N CREW POSITION CREW CREW POSITION CREW POSITION T N I T POSITION I

C A S O B S O B S O B S O B M A T L R A O R A O R A O R A O U N Y O T P O T P O T P O T P M(*)

T P E C C C C R I U RX - - - 0 1 NOR - - - 0 1 I9 I/C 1,2,3,5 1,5 2,3,7 9 4 MAJ 4 7 5,6 4 2 TS 1,2,3 - - 3 2 RX - - - 0 1 NOR - - - 0 1 I/C 2,3, I10 6 1,3,4,5,6 3,4 10 4 MAJ 4 7 5,6 4 2 TS - 1,6 - 2 2 RX - - - 0 1 NOR - - - 0 1 I/C 2,3,4 I11 1,2,3,5

,6,8 1,3,4 12 4 MAJ 4 7 5,6 4 2 TS - - 1,3 2 2 RX - - - 0 1 NOR - - - 0 1 I12 I/C 1,2,3,5 1,5 2,3,7 9 4 MAJ 4 7 5,6 4 2 TS 1,2,3 - - 3 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

2020 PVNGS NRC Initial Exam Form ES-301-5 Rev 2

ES-301 Transient and Event Checklist Form ES-301-5 Facility: PVNGS Date of Exam: 11/30/2020 Operating Test No.: 2020 A E Scenarios P V 1 2 (spare) 3 4 T M P E O I L N CREW POSITION CREW POSITION CREW POSITION CREW POSITION T N I T S O B S O B S O B S O B I C A R A O R A O R A O R A O M A T L O T P O T P O T P O T P U N Y C C C C M(*)

T P E R I U RX - - 0 1 NOR - - 0 1 I/C 1,3,4, I13 5,6 2,3,7 8 4 MAJ 7 5,6 3 2 TS 1,6 - 2 2 RX - - 0 1 NOR - - 0 1 I/C 2,3,4, I14 6,8 1,3,4 8 4 MAJ 7 5,6 3 2 TS - 1,3 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

2020 PVNGS NRC Initial Exam Form ES-301-5 Rev 2

ES-301 Competencies Checklist Form ES-301-6 Facility: PVNGS Date of Examination: 11/30/2020 Operating Test No.: 2020 APPLICANTS RO RO RO RO SRO-I 1 SRO-I 2 SRO-I 3 SRO-I 4 SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 2,3, ALL 3,4, 2,3, 2,3, ALL ALL 1,5, 2,3, 2,3, ALL 3,4,5, 4,6 5,6 4,5. 4,6, 7 5,6, 4,6 6 and Conditions 7 7,8 7 Comply with and 2,3, ALL 3,4, 2,3, 2,3, ALL ALL 1,5, 2,3, 2,3, ALL 3,4,5, 4,6 5,6 4,5, 4,6, 7 5,6, 4,6 6 Use Procedures (1) 7 7,8 7 Operate Control 2,3, ALL 3,4, 2,3, 2,3, ALL ALL 1,5, 2,3, 2,3, ALL 3,4,5, 4,6 5,6 4,5, 4,6, 7 5,6, 4,6 6 Boards (2) 7 7,8 7 Communicate ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL and Interact Demonstrate Supervisory ALL ALL ALL ALL Ability (3)

Comply with and 1,6 1,3 1,2, 1,6 3

Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES 303 1 and ES 303 3 describe the competency rating factors.)

ES-301 Competencies Checklist Form ES-301-6 Facility: PVNGS Date of Examination: 11/30/2020 Operating Test No.: 2020 APPLICANTS RO RO RO RO SRO-I 5 SRO-I 6 SRO-I 7 SRO-I 8 SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 2,3, 2,3, ALL ALL 1,5, 2,3,5 2,3, ALL 3,4, 2,3, 2,3, ALL 4,5. 4,6, 7 ,6,7 4,6 5,6 4,5. 4,6, and Conditions 7 7,8 7 7,8 Comply with and 2,3, 2,3, ALL ALL 1,5, 2,3,5 2,3, ALL 3,4, 2,3, 2,3, ALL 4,5, 4,6, 7 ,6,7 4,6 5,6 4,5, 4,6, Use Procedures (1) 7 7,8 7 7,8 Operate Control 2,3, 2,3, ALL ALL 1,5, 2,3,5 2,3, ALL 3,4, 2,3, 2,3, ALL 4,5, 4,6, 7 ,6,7 4,6 5,6 4,5, 4,6, Boards (2) 7 7,8 7 7,8 Communicate ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL and Interact Demonstrate Supervisory ALL ALL ALL ALL Ability (3)

Comply with and 1,3 1,2, 1,6 1,3 3

Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

ES-301 Competencies Checklist Form ES-301-6 Facility: PVNGS Date of Examination: 11/30/2020 Operating Test No.: 2020 APPLICANTS RO RO RO RO SRO-I 9 SRO-I 10 SRO-I 11 SRO-I 12 SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events ALL 1,5,7 2,3,5, 2,3, ALL 3,4, 2,3, 2,3, AL ALL 1,5, 2,3,5, 6,7 4,6 5,6 4,5. 4,6, L 7 6,7 and Conditions 7 7,8 Comply with and ALL 1,5,7 2,3,5, 2,3, ALL 3,4, 2,3, 2,3, AL ALL 1,5, 2,3,5, 6,7 4,6 5,6 4,5, 4,6, L 7 6,7 Use Procedures (1) 7 7,8 Operate Control ALL 1,5,7 2,3,5, 2,3, ALL 3,4, 2,3, 2,3, AL ALL 1,5, 2,3,5, 6,7 4,6 5,6 4,5, 4,6, L 7 6,7 Boards (2) 7 7,8 Communicate ALL ALL ALL ALL ALL ALL ALL ALL AL ALL ALL ALL L

and Interact Demonstrate Supervisory ALL ALL AL ALL L

Ability (3)

Comply with and 1,2, 1,6 1,3 1,2, 3 3 Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

ES-301 Competencies Checklist Form ES-301-6 Facility: PVNGS Date of Examination: 11/30/2020 Operating Test No.: 2020 APPLICANTS RO RO RO RO SRO-I 13 SRO-I 14 SRO-I SRO-I SRO-U SRO-U SRO-U SRO-U Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events ALL 3,4, 2,3,4 ALL 5,6 ,6,7, and Conditions 8 Comply with and ALL 3,4, 2,3,4 ALL 5,6 ,6,7, Use Procedures (1) 8 Operate Control ALL 3,4, 2,3,4 ALL 5,6 ,6,7, Boards (2) 8 Communicate ALL ALL ALL ALL and Interact Demonstrate Supervisory ALL ALL Ability (3)

Comply with and 1,6 1,3 Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

ML21020A095

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