Text

2015-06 Final Operating Test
	ML15167A548
Person / Time
Site:	Comanche Peak
Issue date:	06/05/2015
From:	Vincent Gaddy; Operations Branch IV
To:	; Luminant Generation Co
References
	Download: ML15167A548 (331)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: CPNPP Units 1 and 2 Date of Examination: June 2015 Examination Level: RO SRO Operating Test Number: NRC Administrative Topic Type Code* Describe activity to be performed (See Note) 2.1.23 Ability to perform specific system and integrated plant procedures during all modes Conduct of Operations of plant operation. (4.3).

(RA1) M,R JPM: Perform Power Change Worksheet Calculation. (RO1302B) 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo Conduct of Operations operation, maintenance of active license (RA2) N,R status, 10CFR55, etc. (3.3).

JPM: Determine RO License Status. (RO5001) 2.2.12 Knowledge of surveillance procedures. (3.7).

Equipment Control (RA3) D,R JPM: Perform Axial Flux Difference Surveillance.

(RO1808) 2.3.11 Ability to control radiation releases. (3.8).

Radiation Control (RA4) M,R JPM: Determine Maximum Allowable Venting Time. (RO7030A)

Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

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

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

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

ES-301-1 CPNPP 2015 NRC RO Administratives Topics Outline

ES-301 Administrative Topics Outline Form ES-301-1 Task Summary RA1 The applicant will determine boron/dilution requirements to lower power from 100% to 50% equilibrium per IPO-003A, Power Operations, Attachment 3, Power Change Worksheet. The calculations include Power Defect, Rod Worth, Xenon Worth, change in Boron concentration and boration/dilution quantity. The critical steps are to determine the reactivity change for power defect, the rod position change, equilibrium xenon, and the total reactivity change for these parameters, the required change in boron concentration, and the amount of boration needed.

This is a modified bank JPM.

RA2 The applicant will be presented with a detailed record (in table form) of watch standing and other activities performed by 3 individual Reactor Operators over a period of 4 to 6 weeks. The applicant will be required to analyze the work records of these three operators, and apply the guidance of ODA-315, Licensed Operator Maintenance Tracking, to evaluate and determine if the RO license status is active or inactive for each of the three operators. The critical steps are to determine that the RO licenses for two of the three operators are NOT active.

This is a new JPM.

RA3 The applicant will be presented with Power Range Nuclear Instrument Axial Flux Difference data and will perform a manual Axial Flux Difference calculation using OPT-403, Axial Flux Difference. The critical steps are to determine whether at least 3 of 4 PR FLUX channels are within the Acceptable Operation region of NUC-204-6, Axial Flux Difference as a Function of Rated Thermal Power. This is a direct from bank JPM.

RA4 The applicant will determine the maximum allowable venting time for venting the reactor vessel using FRI-0.3A, Response to Voids in Reactor Vessel, Attachment

5. Critical steps include various stages of the calculation, including the final determination of allowable venting time. This is a modified bank JPM.

ES-301-1 CPNPP 2015 NRC RO Administratives Topics Outline

ES-301 Administrative Topics Outline Form ES-301-1 Facility: CPNPP Units 1 and 2 Date of Examination: June 2015 Examination Level: RO SRO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (See Note) Code*

2.1.25 Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc. (4.2).

(SA1) D,R JPM: Loss of RHR Time / Tech Specs. (SO1101) 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, Conduct of Operations such as medical requirements, no-solo (SA2) N,R operation, maintenance of active license status, 10CFR55, etc. (3.8).

JPM: Determine SRO License Status.

2.2.23 Ability to track Technical Specification Equipment Control limiting conditions for operations. (4.6).

(SA3) M,R JPM: Complete Manual LCOAR for Motor Driven AFW Pump. (SO1024D) 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

Radiation Control (3.7).

(SA4) D,R JPM: Select Volunteer for Emergency Exposure.

(SO1142A) 2.4.44 Knowledge of emergency plan protective Emergency action recommendations. (4.4).

Procedures/Plan M,P,R (SA5) JPM: Determine Protective Action Recommendations. (SO1140A)

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

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

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

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

ES-301-1 CPNPP 2015 NRC SRO Administrative Topics Outline

ES-301 Administrative Topics Outline Form ES-301-1 Task Summary SA1 The applicant is presented with Loss of RHR conditions and then uses ABN-104, Residual Heat Removal System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure to determine Time to Saturation, Time to Core Uncovery, and Containment Closure Time. The critical steps are to determine Time to Saturation, Time to Core Uncovery, Containment Closure Time, and identify any Technical Specification required actions associated with the loss of the standby RHR pump. This is a direct from bank JPM.

SA2 The applicant is presented with a detailed record (in table form) of watch standing and other activities performed by 3 individual Senior Reactor Operators over a period of 4 to 6 weeks. The applicant will be required to analyze the work records of these three operators, and apply the guidance of ODA-315, Licensed Operator Maintenance Tracking, to evaluate and determine if the SRO license status is active or inactive for each of the three operators. The critical steps are to determine that the SRO licenses for two of the three operators are NOT active.

This is a new JPM.

SA3 The applicant will be presented with conditions involving a Motor Driven AFW pump which is removed from service and will use ODA-308, LCO Tracking Program, and Technical Specification 3.7.5 Auxiliary Feedwater System, to complete a Manual LCOAR. The critical steps consist of various determinations on the Manual LCOAR form, including correct information in required fields to pass the JPM. This is a modified bank JPM.

SA4 The applicant is given accident conditions involving the need for a volunteer to attempt a lifesaving activity. Using the guidance in EPP-305, Emergency Exposure Guidelines and Personnel Dosimetry, the applicant will evaluate a series of potential volunteers and select the preferred volunteer from this list.

The critical steps are evaluation and elimination of volunteers who do not meet the criteria required for the activity, and then final selection of the preferred volunteer. This is a direct from bank JPM.

ES-301-1 CPNPP 2015 NRC SRO Administrative Topics Outline

ES-301 Administrative Topics Outline Form ES-301-1 Task Summary SA5 The applicant will determine the appropriate Protective Action Recommendations for an emergency. This JPM is designated as a "P" because a form of it was used on the 2013 NRC exam. This JPM will be modified to include different conditions, including severity and meteorological parameters. The "random selection" aspect was performed due to limited topics available for SRO A.4 category, the fact that this JPM meets the requirements of NUREG-1021, and to avoid overlap with the Audit Exam. The critical steps will include several determinations the SRO must make, such as release duration, core damage, and identification of affected sectors. This is a modified bank JPM.

ES-301-1 CPNPP 2015 NRC SRO Administrative Topics Outline

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA1 Task #RO1302 K/A#2.1.23 4.3 / 4.4

Title:

Perform Power Change Worksheet Calculation Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 has been operating at 100% power for several weeks.

A power ramp to 80% is planned during the next 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Current RCS boron concentration is 925 ppm.

Current rod height is Control Bank D at 215 steps.

Cycle 18 Core Burnup is 10000 MWD/MTU.

Boric Acid Batch Tank X-01 and X-02 are both at 7450 ppm.

Current Date/Time is 5/1/15 at 1200.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

DETERMINE boron / dilution required and the target CBD position using IPO-003A, Power Operations, Attachment 3, Power Change Worksheet.

Xenon worth and AFD control strategies may be ignored.

Task Standard: CALCULATED the Volume of Boron required and the CBD approximate final position per IPO-003A, Attachment 3.

Required Materials: IPO-003A, Power Operations, Rev. 29-2.

TDM-201A, CVCS Calculations/Blended Flow, Rev. 6.

The Nuclear Design and Core Physics Characteristics of the Comanche Peak Nuclear Power Plant Unit 1 Cycle 18, Rev. October 2014.

Validation Time: 40 minutes Time Critical: N/A Completion Time: ________ minutes Page 1 of 8 NRC RA1 (RO1302B)

Appendix C JPM WORKSHEET Form ES-C-1 Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 8 NRC RA1 (RO1302B)

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

IPO-003A, Power Operations.

Attachment 3, Power Change Worksheet.

TDM-201A, CVCS Calculations/Blended Flow The Nuclear Design and Core Physics Characteristics of the Comanche Peak Nuclear Power Plant Unit 1 Cycle 18 Page 3 of 8 NRC RA1 (RO1302B)

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Complete Calculation Heading Information Standard: ENTERED information provided in Initial Conditions at top of each page.

Unit 1 Cycle 18 Date 5/1/15 Time 1200 Comment: SAT UNSAT Perform Step: 2 Obtain Current Plant Conditions.

Standard: RECORDED Current Plant Conditions:

A.1 RCS Boron 925 ppm A.2 Power Level 100% RTP A.3 CBD Position 215 steps A.4 Core Burnup 10000 MWD/MTU A.5 Burnup Range CHECKED MOL Comment: SAT UNSAT Perform Step: 3 Estimate Target CBD Position.

Target Power Level Standard: RECORDED Target Power Level B.1 80% RTP Comment: SAT UNSAT Page 4 of 8 NRC RA1 (RO1302B)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Estimate Target CBD Position.

IF planning a Power DECREASE (B.1 < A.2), THEN B.2 =

Standard: CALCULATED A.3 + [B.1 - A.2] x [A.4 + 8000] / 12000 215 + [80 - 100] x [10000 + 8000] / 12000 B.2 Target CBD Position = 185 steps Comment: SAT UNSAT Perform Step: 5 Power Defect Reactivity Change.

Determine change in Reactivity due to Power Defect, based on current RCS Boron, using: NDR Table 5.2 for MOL Standard: CALCULATED C.1 Absolute Value of Power Defect at Current Power Level [A.2]

= 1728 pcm.

C.2 Absolute Value of Power Defect at Target Power Level [B.1]

= 1418 pcm.

C.3 ) Power Defect = [C.1] - [C.2] = 1728 - 1418 = 310 pcm Comment: SAT UNSAT Perform Step: 6 Control Rod Motion Reactivity Change.

Determine change in Reactivity due to Control Rod Motion, using:

NDR Figure 5.17 for MOL Standard: CALCULATED D.1 Absolute Value of CBD Integral Worth at Current CBD Position [A.3] = 10 +/- 5 pcm.

D.2 Absolute Value of CBD Integral Worth at Target CBD Position

[B.2] = 90 +/- 5 pcm.

D.3 ) Control Rod Worth = [D.1] - [D.2] = 10 - 90 = -80 +/- 10 pcm Comment: SAT UNSAT Page 5 of 8 NRC RA1 (RO1302B)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Determine Reactivity Worth Required from Boron Adjustment.

Standard: CALCULATED E.1 ) Boron Worth = [D.3 + C.3] x [-1] = -80 + 310 = -230 +/- 10 pcm Comment: SAT UNSAT Perform Step: 8 Determine Integral Boron Worth at Current Conditions. For this section, utilize the following NRDR table. NDR Table 5.11 for MOL.

Standard: DETERMINED F.1 Integral Boron Worth at [A.1] pmm = -8176.5 ppm Comment: SAT UNSAT Perform Step: 9 Determine Target RCS Boron Value.

Standard: CALCULATED G.1 Target Integral Boron Worth = [F.1] + [E.1] = -8176.5 + -230 =

-8406.5 +/- 10 pcm G.2 Target RCS Boron Value = 952 +/- 5 ppm Comment: SAT UNSAT Perform Step: 10 Determine RCS Boration / Dilution Volume Check appropriate method for RCS Boron Change Standard: H.1 CHECKED Boration Volume Comment: SAT UNSAT Perform Step: 11 Determine RCS Boration / Dilution Volume Volume Required Standard: CALCULATED Volume Required H.2 Volume = 65804 [ln(7450 - 925) / (7450 - 952)]

H.2 Volume = 273 +/- 50 gal.

Comment: SAT UNSAT Page 6 of 8 NRC RA1 (RO1302B)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 12 Summary of Results Volume Required Standard: COMPLETED the Summary of Results I To change power immediately from [A.2] to [B.1], it is estimated that [H.2] gallons of [H.1] will be required, and CBD final position will be approximately [B.2] steps.

I To change power immediately from 100 to 80, it is estimated that 273 +/- 50 gallons of BOR will be required, and CBD final position will be approximately 185 steps.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 7 of 8 NRC RA1 (RO1302B)

Appendix C JPM CUE SHEET Form ES-C-1 Initial Given the following conditions:

Conditions: Unit 1 has been operating at 100% power for several weeks.

A power ramp to 80% is planned during the next 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Current RCS boron concentration is 925 ppm.

Current rod height is Control Bank D at 215 steps.

Cycle 18 Core Burnup is 10000 MWD/MTU.

Boric Acid Batch Tank X-01 and X-02 are both at 7450 ppm.

Current Date/Time is 5/1/15 at 1200.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

DETERMINE boron / dilution required and the target CBD position using IPO-003A, Power Operations, Attachment 3, Power Change Worksheet.

Xenon worth and AFD control strategies may be ignored.

Page 8 of 8 NRC RA1 (RO1302B)

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA2 Task # RO5001 K/A # 2.1.4 3.3 / 3.8

Title:

Determine Licensed Operator License Status Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Today is April 6, 2015.

Three Licensed Reactor Operators are available to be assigned as the Unit 1, Reactor Operator for the oncoming shift.

Given the first quarter shifts worked as recorded in the Unit and Station Logs.

Both Units maintained 100% RTP during the first quarter.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

DETERMINE which Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status) o RO A Active Inactive o RO B Active Inactive o RO C Active Inactive Task Standard: DETERMINED license status of each RO.

Required Materials: ODA-315, Licensed Operator Maintenance Tracking, Rev. 7-0.

ODA-315-1, Active License Status Form, Rev. 8.

Validation Time: 5 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 NRC RA2 (RO5001)

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

ODA-315, Licensed Operator Maintenance Tracking.

ODA-315-1, Active License Status Form Work History Log Handout Page 2 of 6 NRC RA2 (RO5001)

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 DETERMINE which Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status)

Standard: DETERMINED RO A has only stood four 12-hour watches which qualify as the 3/31/15 watch was not completed in the previous quarter and does not count. CIRCLED Inactive for RO A.

Comment: SAT UNSAT Perform Step: 2 DETERMINE which Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status)

Standard: DETERMINED RO B has stood five 12-hour watches which qualify as the RO or BOP. CIRCLED Active for RO B.

Comment: SAT UNSAT Perform Step: 3 DETERMINE which Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status)

Standard: DETERMINED RO C has only stood four 12-hour watches which qualify as the 3/13/15 watch was only 8-hours and does not count. CIRCLED Inactive for RO C.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 3 of 6 NRC RA2 (RO5001)

Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 NRC RA2 (RO5001)

Appendix C JPM STEPS Form ES-C-1 CPNPP 2015 NRC RA2 Handout RO 1st Quarter Shifts Worked DATE RO A RO B RO C 3/3/2015 U1 RO: 0600-1830 3/4/2015 U2 RO: 0600-1830 3/5/2015 U1 BOP: 0600-1830 U2 RO: 1800-0630 3/6/2015 U2 BOP: 0600-1830 U2 RO: 1800-0630 3/7/2015 U2 RO: 0600-1830 3/12/2015 U1 BOP: 0600-1830 3/13/2015 U1 RO: 0600-1530 3/14/2015 U1 RO: 1800-0630 3/19/2015 U2 RO: 1800-0630 3/24/2015 U1 BOP: 0600-1830 3/25/2015 U1 BOP: 0600-1830 3/30/2015 U2 BOP: 1800-0630 3/31/2015 U1 BOP: 1800-0630 Page 5 of 6 NRC RA2 (RO5001)

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Today is April 6, 2015.

Three Licensed Reactor Operators are available to be assigned as the Unit 1, Reactor Operator for the oncoming shift.

Given the first quarter shifts worked as recorded in the Unit and Station Logs.

Both Units maintained 100% RTP during the first quarter.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

DETERMINE which Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status) o RO A Active Inactive o RO B Active Inactive o RO C Active Inactive Page 6 of 6 NRC RA2 (RO5001)

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA3 Task # RO1808 K/A # 2.2.12 3.7 / 4.1

Title:

Perform Axial Flux Difference Surveillance Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Today is 3/15/15.

Unit 1 is at 80% power.

The Axial Flux Difference (AFD) alarm was declared INOPERABLE over 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago.

Power Range Nuclear Instrument AFD data was collected for several hours last shift.

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C % RTP 0800 14% 16% 17% 16% 80%

0830 14% 17% 17% 16% 80%

0900 15% 17% 17% 16% 80%

0930 15% 17% 17% 16% 80%

1000 16% 19% 19% 17% 80%

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

PERFORM OPT-403, Axial Flux Difference.

ENTER the Power Range Nuclear Instrument AFD data onto OPT-403-1, AFD Data Sheet.

RECORD findings in the Discrepancies/Comments Section of OPT-403-1.

The NDR Verification has been performed for the NUC-204-6 Form.

Task Standard: Utilizing OPT-403, performed Axial Flux Difference surveillance and recorded findings on Form OPT-403-1.

Required Materials: OPT-403, Axial Flux Difference, Rev. 12.

OPT-403-1, AFD Data Sheet, Rev. 11.

NUC-204-6, Axial Flux Difference As a Function of Rated Thermal Power, Unit 1 Cycle 18, 3/02/15.

Page 1 of 6 NRC RA3 (RO1808)

Appendix C JPM WORKSHEET Form ES-C-1 Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 6 NRC RA3 (RO1808)

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

OPT-403, Axial Flux Difference.

OPT-403-1, AFD Data Sheet.

NUC-204-6, Axial Flux Difference As a Function of Rated Thermal Power.

Page 3 of 6 NRC RA3 (RO1808)

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Record the following data for the affected unit:

8.1 & 8.1.1 Unit 1 or 2 as applicable Standard: CIRCLED Unit 1 on OPT-403-1.

Comment: SAT UNSAT Perform Step: 2 Record the following data for the affected unit:

8.1 & 8.1.2 Date Standard: ENTERED Date on OPT-403-1.

Comment: SAT UNSAT Perform Step: 3 Record the following data:

8.2 & 8.2.1 Time Standard: ENTERED Time on OPT-403-1.

Comment: SAT UNSAT Perform Step: 4 Record the following data:

8.2 & 8.2.2 PR FLUX for each operable excore detector Standard: RECORDED PR FLUX for each operable excore detector on OPT-403-1 from JPM Cue Sheet.

Comment: SAT UNSAT Perform Step: 5 Record the following data:

8.2 & 8.2.3 Percent Rated Thermal Power (RTP)

Standard: RECORDED Percent Rated Thermal Power on OPT-403-1.

Comment: SAT UNSAT Page 4 of 6 NRC RA3 (RO1808)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 Perform the following to determine PR FLUX status and record:

8.3 & 8.3.A Verify at least 3 of 4 PR FLUX channels are within the Acceptable Operation region (Doghouse Region) of NUC-204-6 Axial Flux Difference as a Function of Rated Thermal Power.

Standard: DETERMINED PR FLUX status and RECORDED and INITIALED on OPT-403-1. Status is ACCEPTABLE OPERATION for Times 0800 to 0930 and CIRCLED YES, NOT ACCEPTABLE OPERATION for Time 1000 and CIRCLED NO.

Comment: SAT UNSAT Perform Step: 7 Perform the following to determine PR FLUX status and record:

8.3 & 8.3.B Repeat Steps 8.2 and 8.3 at least once per thirty (30) minutes.

Standard: REPEATED Steps 8.2 and 8.3 at least once per thirty (30) minutes on OPT-403-1. DETERMINED PR FLUX status and RECORDED and INITIALED on OPT-403-1. Status is ACCEPTABLE OPERATION for Times 0800 to 0930 and CIRCLED YES, NOT ACCEPTABLE OPERATION for Time 1000 and CIRCLED NO.

Comment: SAT UNSAT Perform Step: 8 Record findings in the Discrepancies/Comments Section of OPT-403-1.

Standard: RECORDED findings in the Discrepancies / Comments Section of OPT-403-1.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 NRC RA3 (RO1808)

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Today is 3/15/15.

Unit 1 is at 80% power.

The Axial Flux Difference (AFD) alarm was declared INOPERABLE over 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago.

Power Range Nuclear Instrument AFD data was collected for several hours last shift.

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C % RTP 0800 14% 16% 17% 16% 80%

0830 14% 17% 17% 16% 80%

0900 15% 17% 17% 16% 80%

0930 15% 17% 17% 16% 80%

1000 16% 19% 19% 17% 80%

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

PERFORM OPT-403, Axial Flux Difference.

ENTER the Power Range Nuclear Instrument AFD data onto OPT-403-1, AFD Data Sheet.

RECORD findings in the Discrepancies/Comments Section of OPT-403-1.

The NDR Verification has been performed for the NUC-204-6 Form.

Page 6 of 6 NRC RA3 (RO1808)

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA4 Task #RO7030 K/A# 2.3.11 3.8 / 4.3

Title:

Respond to Voids in Reactor Vessel Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 has experienced a SBLOCA.

FRI-0.3A, Response to Voids in Reactor Vessel is in progress.

RCS pressure is 950 psig.

Containment pressure is 10.3 psig.

Containment temperature is 135 °F.

Containment H2 concentration is 2% in Dry Air..

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

Calculate the maximum venting time in accordance with FRI-0.3A, Attachment 5, Instructions for Determining Venting Time.

Task Standard: CALCULATED the Maximum Venting Time per FRI-0.3A, Attachment 5.

Required Materials: FRI-0.3A, Response to Voids in Reactor Vessel, Rev. 8-4.

Validation Time: 12 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 5 NRC RA4 (RO7030A)

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

FRI-0.3A, Response to Voids in Reactor Vessel.

Attachment 5, Instructions for Determining Venting Time.

Page 2 of 5 NRC RA4 (RO7030A)

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Determine Containment Volume at STP = A A = (2,985,000 ft3) x [(Containment Pressure in PSIG + 14.7) /

14.7 psia] x [492 °R / (Containment temperature in °F + 460)]

Standard: CALCULATED Containment Volume at STP A = (2,985,000 ft3) x [(10.3 + 14.7) / 14.7 psia] x [492 °R / (135 +

460)]

A = 4197736 ft3 Comment: SAT UNSAT Perform Step: 2 Determine Maximum Hydrogen volume that can be vented = B.

Standard: CALCULATED Maximum Hydrogen Volume B= (3.0% - Containment Hydrogen Concentration ) x A / 100%

B = (3.0 - 2.0) x 4197736 / 100 B = 41977 ft3 Comment: SAT UNSAT Perform Step: 3 Determine Hydrogen flow rate as a function of RCS pressure = C.

a. Check RCS pressure.

B. Using the Hydrogen Flow Rate As a Function of Pressure Curve, read hydrogen flow rate.

Standard: DETERMINED using RCS pressure of 950 psig and Hydrogen Flow Rate As a Function of Pressure Curve C = 3000 scfm Comment: SAT UNSAT Page 3 of 5 NRC RA4 (RO7030A)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Calculate maximum vent time:

Maximum venting time = B / C minutes Standard: CALCULATED 41977 / 3000 14 +/- 0.5 minutes Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 NRC RA4 (RO7030A)

Appendix C JPM CUE SHEET Form ES-C-1 Initial Given the following conditions:

Conditions: Unit 1 has experienced a SBLOCA.

FRI-0.3A, Response to Voids in Reactor Vessel is in progress.

RCS pressure is 950 psig.

Containment pressure is 10.3 psig.

Containment temperature is 135 °F.

Containment H2 concentration is 2% in Dry Air..

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

Calculate the maximum venting time in accordance with FRI-0.3A, Attachment 5, Instructions for Determining Venting Time.

Page 5 of 5 NRC RA4 (RO7030A)

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA1 Task # SO1101 K/A # 2.1.25 3.9 / 4.2

Title:

Determine Loss of RHR Time Limitations and Evaluate Technical Specifications Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

JPM Cue Sheet #1 Unit 2 is in MODE 5 with water level in the Reactor Vessel at 49 above the Core Plate.

All Pressurizer Safety Valves have been removed.

Reactor Coolant System temperature is 140ºF.

The Reactor was shutdown on April 1st at 0000 after operating at 100%

power for the last 550 days.

Today is April 7th and the Unit experienced a Loss of Residual Heat Removal cooling at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months .

Initiating Cue: The Shift Manager directs you to PERFORM the following:

JPM Cue Sheet #1 CALCULATE the following times per ABN-104, Residual Heat Removal System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure:

DETERMINE Time to Saturation ________

DETERMINE Time to Core Uncovery ________

DETERMINE Both Containment Closure Times:

Thermal Environment Limiting ________

Radiological Environment Limiting ________

Page 1 of 7 CPNPP NRC 2015 SA1 (SO1101)

Appendix C JPM WORKSHEET Form ES-C-1 Initial Conditions: Given the following conditions:

JPM Cue Sheet #2 Unit 2 is in MODE 5 with water level in the Reactor Vessel at 49 above the Core Plate.

All Pressurizer Safety Valves have been removed.

Both Residual Heat Removal Pumps cannot be started.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

JPM Cue Sheet #2 IDENTIFY any Technical Specification CONDITIONS and REQUIRED ACTION associated with the loss of both Residual Heat Removal Pumps.

CONDITION REQUIRED ACTION LCO & CONDITION REQUIRED ACTION # & Action Task Standard: DETERMINED Time to Saturation, Time to Core Uncovery, And Containment Closure Time following a Loss of Residual Heat Removal System per ABN-104 and IDENTIFIED any Limiting Conditions for Operations associated with a loss of the standby Residual Heat Removal Pump per Technical Specifications.

Required Materials: ABN-104, Residual Heat Removal System Malfunction, Rev. 9-1.

CPNPP Technical Specifications Units 1 and 2, Amendment 162.

Validation Time: 20 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 7 CPNPP NRC 2015 SA1 (SO1101)

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with JPM Cue Sheet #1 and a copy of:

ABN-104, Residual Heat Removal Malfunction.

Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory.

Attachment 19, Available Time for Containment Closure.

When JPM Cue Sheet #1 is completed, PROVIDE JPM Cue Sheet #2 and a copy of:

CPNPP Technical Specifications - Units 1 and 2.

Page 3 of 7 CPNPP NRC 2015 SA1 (SO1101)

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Determine Time to Saturation:

Calculate Time After Shutdown.

Standard: DETERMINED number of hours between 0000 on April 1st and 0600 on April 7th and CALCULATED Time After Shutdown = 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months .

Comment: SAT UNSAT Perform Step: 2 Determine Time to Saturation:

Find Time to Saturation from Attachment 5, Page 1.

Standard: REFERRED to Page 1 of Attachment 5 and PLOTTED the intersection of Time After Shutdown (150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months ) and Initial Temp (140ºF) and DETERMINED: TIME TO SATURATION = 9 +/- 1 minutes.

Comment: SAT UNSAT Perform Step: 3 Determine Time To Core Uncovery:

Find Time To Core Uncovery from Attachment 5, Page 2 Standard: REFERRED to Page 2 of Attachment 5 and PLOTTED the intersection of Time After Shutdown (10 days or 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months ) and Initial RCS Level (49 inches above the core plate) and DETERMINED: Time To Core Uncovery = 1.4 +/- 0.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Comment: SAT UNSAT Perform Step: 4 Determine Containment Closure time:

Find Containment Closure Time from Attachment 19:

Thermal Environment Limiting Curve.

Standard: REFERRED to Attachment 19 and PLOTTED the intersection of Time After Shutdown and Thermal Environment Limiting Curve and DETERMINED: Containment Closure Time = 43 +/- 2 minutes.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2015 SA1 (SO1101)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Determine Containment Closure time:

Find Containment Closure Time from Attachment 19:

Radiological Environment Limiting Curve.

Standard: REFERRED to Attachment 19 and PLOTTED the intersection of Time After Shutdown and Radiological Environment Limiting Curve and DETERMINED: Containment Closure Time = 45 +/- 2 minutes.

Comment: SAT UNSAT Examiner Note: Provide the examinee with copy of JPM Cue Sheet #2 and Technical Specifications.

This Step is not critical as Required Action B.2 encompasses this Required Action and may be omitted which would be an administrative error.

Perform Step: 6 Identify any Technical Specification REQUIRED ACTION associated with the loss of the standby Residual Heat Removal Pump.

Standard: DETERMINED Technical Specification LCO 3.4.8.A is applicable:

CONDITION - One RHR loop inoperable Immediately initiate action to restore RHR loop to OPERABLE status Comment: SAT UNSAT Perform Step: 6 Identify any Technical Specification REQUIRED ACTION associated with the loss of the standby Residual Heat Removal Pump.

Standard: DETERMINED Technical Specification LCO 3.4.8.B is applicable:

CONDITION - No RHR loop in operation.

Immediately suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1 (REQUIRED ACTION and COMPLETION TIME of LCO 3.4.8.B.1).

Immediately initiate action to restore one RHR loop to OPERABLE status and operation (REQUIRED ACTION and COMPLETION TIME of LCO 3.4.8.B.2).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 7 CPNPP NRC 2015 SA1 (SO1101)

Appendix C JPM CUE SHEET #1 Form ES-C-1 Initial Conditions: Given the following conditions:

JPM Cue Sheet Unit 2 is in MODE 5 with water level in the Reactor Vessel at 49

1 above the Core Plate.

All Pressurizer Safety Valves have been removed.

Reactor Coolant System temperature is 140ºF.

The Reactor was shutdown on April 1st at 0000 after operating at 100% power for the last 550 days.

Today is April 7th and the Unit experienced a Loss of Residual Heat Removal cooling at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months .

Initiating Cue: The Shift Manager directs you to PERFORM the following:

JPM Cue Sheet CALCULATE the following times per ABN-104, Residual Heat

1 Removal System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure:

DETERMINE Time to Saturation ________

DETERMINE Time to Core Uncovery ________

DETERMINE Both Containment Closure Times:

Thermal Environment Limiting ________

Radiological Environment Limiting ________

Page 6 of 7 CPNPP NRC 2015 SA1 (SO1101)

Appendix C JPM CUE SHEET #2 Form ES-C-1 Initial Conditions: Given the following conditions:

JPM Cue Sheet Unit 2 is in MODE 5 with water level in the Reactor Vessel at 49

2 above the Core Plate.

All Pressurizer Safety Valves have been removed.

Both Residual Heat Removal Pumps cannot be started.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

JPM Cue Sheet IDENTIFY any Technical Specification CONDITIONS and REQUIRED

2 ACTION associated with the loss of both Residual Heat Removal Pumps.

CONDITION REQUIRED ACTION LCO & CONDITION REQUIRED ACTION # & Action Page 7 of 7 CPNPP NRC 2015 SA1 (SO1101)

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA2 Task # SO1004 K/A # 2.1.4 3.3 / 3.8

Title:

Determine Licensed Operator License Status Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Today is April 6, 2015.

Three Staff Senior Reactor Operators are available to be assigned as the Unit 1, Unit Supervisor for the oncoming shift.

Given the first quarter shifts worked as recorded in the Unit and Station Logs.

Both Units maintained 100% RTP during the first quarter.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

DETERMINE which Senior Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status) o SRO A Active Inactive o SRO B Active Inactive o SRO C Active Inactive DETERMINE which Senior Reactor Operator(s) satisfy the requirements to fill the Unit 1, Unit Supervisor position for the oncoming shift.

o SRO __________________ can be assigned as the Unit Supervisor.

Task Standard: DETERMINED license status of each SRO and DETERMINED the only SRO qualified to stand the watch as the Unit 1, Unit Supervisor for the oncoming shift.

Required Materials: ODA-315, Licensed Operator Maintenance Tracking, Rev. 7-0.

ODA-315-1, Active License Status Form, Rev. 8.

Validation Time: 10 minutes Completion Time: ________ minutes Page 1 of 6 NRC SA2 (SO1004)

Appendix C JPM WORKSHEET Form ES-C-1 Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 6 NRC SA2 (SO1004)

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

ODA-315, Licensed Operator Maintenance Tracking.

ODA-315-1, Active License Status Form Work History Log Handout Page 3 of 6 NRC SA2 (SO1004)

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 DETERMINE which Senior Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status)

Standard: DETERMINED SRO A has only stood four 12-hour watches which qualify as the STA watches do not count and the 3/31/15 watch was not completed in the previous quarter and does not count. CIRCLED Inactive for SRO A.

Comment: SAT UNSAT Perform Step: 2 DETERMINE which Senior Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status)

Standard: DETERMINED SRO B has stood five 12-hour watches which qualify as the SM or US. CIRCLED Active for SRO B.

Comment: SAT UNSAT Perform Step: 3 DETERMINE which Senior Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status)

Standard: DETERMINED SRO C has only stood four 12-hour watches which qualify as the STA watches do not count and the 3/13/15 watch was only 8-hours and does not count. CIRCLED Inactive for SRO C.

Comment: SAT UNSAT Perform Step: 4 DETERMINE which Senior Reactor Operator(s) satisfy the requirements to fill the Unit 1, Unit Supervisor position for the oncoming shift.

Standard: DETERMINED SRO B can be assigned as the Unit Supervisor.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 6 NRC SA2 (SO1004)

Appendix C JPM STEPS Form ES-C-1 CPNPP 2015 NRC SA2 Handout SRO 1st Quarter Shifts Worked DATE SRO A SRO B SRO C 3/3/2015 U1 US: 0530-1830 3/4/2015 U2 US: 0530-1830 3/5/2015 STA: 0530-1830 U1 US: 0530-1830 U2 US: 1730-0630 3/6/2015 SM: 0530-1830 U2 US: 1730-0630 3/7/2015 U2 US: 0530-1830 3/12/2015 U1 US: 0530-1830 3/13/2015 STA: 0530-1830 U1 US: 0530-1530 3/14/2015 U1 US: 1730-0630 3/19/2015 U2 US: 1730-0630 STA: 1730-0630 3/24/2015 SM: 0530-1830 3/25/2015 STA: 0530-1830 U1 US: 0530-1830 3/30/2015 U2 US: 1730-0630 3/31/2015 U1 US: 1730-0630 Page 5 of 6 NRC SA2 (SO1004)

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Today is April 6, 2015.

Three Staff Senior Reactor Operators are available to be assigned as the Unit 1, Unit Supervisor for the oncoming shift.

Given the first quarter shifts worked as recorded in the Unit and Station Logs.

Both Units maintained 100% RTP during the first quarter.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

DETERMINE which Senior Reactor Operators are current on maintaining proficiency of an Active License. (Circle Correct Status) o SRO A Active Inactive o SRO B Active Inactive o SRO C Active Inactive DETERMINE which Senior Reactor Operator(s) satisfy the requirements to fill the Unit 1, Unit Supervisor position for the oncoming shift.

o SRO __________________ can be assigned as the Unit Supervisor.

Page 6 of 6 NRC SA2 (SO1004)

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA3 Task # SO1024 K/A # 2.2.23 3.1 / 4.6

Title:

Initiate a Manual LCOAR Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 and Unit 2 are at 100% power.

Motor Driven Auxiliary Feed Water Pump 1-02 (CP1-AFAPMD-02) was declared INOPERABLE for motor bearing replacement at 1200 on 3/2/15 per POD.

The electronic LCOAR program is out of service and there are no other Limiting Conditions for Operation in affect.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

COMPLETE the Manual Standard LCOAR Index per ODA-308, LCO Tracking Program.

COMPLETE the Manual Standard LCOAR up to the second SRO review. This is the first Manual LCOAR initiated this year.

Work Order and SmartForm Numbers may be marked as N/A.

PERFORM a Safety Function Determination (SFDP), DOCUMENT results of SFDP in Comments area of LCOAR.

Task Standard: COMPLETED Manual LCOAR per ODA-308 and IDENTIFIED the Limiting Condition of Operations requirements for this failure. DETERMINED that a Loss of Safety Function does not exist.

Required Materials: ODA-308, LCO Tracking Program, Rev. 15-3 ODA-308-3.7.5, Standard LCOAR for 3.7.5 Auxiliary Feedwater (AFW) System, Rev. 3 ODA-308-48, Manual Standard LCOAR Index, Rev. 0 Comanche Peak Unit 1 and 2 Technical Specifications, Amendment 164 Validation Time: 30 minutes Time Critical: N/A Completion Time: ________ minutes Page 1 of 9 NRC SA3 (SO1024)

Appendix C JPM WORKSHEET Form ES-C-1 Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 9 NRC SA3 (SO1024)

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

ODA-308, LCO Tracking Program.

ODA-308-3.7.5, Standard LCOAR for 3.7.5 Auxiliary Feedwater (AFW) System.

ODA-308-48, Manual Standard LCOAR Index.

Comanche Peak Unit 1 and 2 Technical Specifications.

Page 3 of 9 NRC SA3 (SO1024)

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Assign a Manual LCOAR Tracking Number in the Manual LCOAR Index.

Standard: ASSIGNEED tracking number A1-3/2/15-01 on ODA-308-48, Manual Standard LCOAR Tracking Index.

Comment: SAT UNSAT Perform Step: 2 Enter the LCOAR initiation Date/Time in the Manual LCOAR Index.

Standard: ENTERED 3-2-15/1200 on ODA-308-48, Manual Standard LCOAR Tracking Index.

Comment: SAT UNSAT Perform Step: 3 Enter the LCOs Affected in the Manual LCOAR Index.

Standard: ENTERED LCO 3.7.5 on ODA-308-48, Manual Standard LCOAR Tracking Index.

Comment: SAT UNSAT Perform Step: 4 Enter the Required Termination Date/Time in the Manual LCOAR Index.

Standard: ENTERED 3-5-15/1200 on ODA-308-48, Manual Standard LCOAR Tracking Index.

Comment: SAT UNSAT Perform Step: 5 Circle P on the Manual LCOAR Index for unplanned.

Standard: CIRCLED P on ODA-308-48, Manual Standard LCOAR Tracking Index.

Comment: SAT UNSAT Perform Step: 6 Enter Equipment Tag No.

Standard: ENTERED CP1-AFAPMD-02 on ODA-308-48, Manual Standard LCOAR Tracking Index.

Comment: SAT UNSAT Page 4 of 9 NRC SA3 (SO1024)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Train A B.

Standard: CIRCLED Train B.

Comment: SAT UNSAT Perform Step: 8 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Record tracking number.

Standard: RECORD LCOAR number on ODA-308-3.7.5.

Comment: SAT UNSAT Perform Step: 9 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Enter Condition B Entry Date/Time.

Standard: ENTERED 3-2-15/1200 on Condition B Entry Date/Time Comment: SAT UNSAT Perform Step: 10 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Enter Condition B.1 Required Date/Time.

Standard: ENTERED 3-5-15/1200 on Condition B.1 Required Date/Time Comment: SAT UNSAT Page 5 of 9 NRC SA3 (SO1024)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 11 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Enter Reason for Entry.

Enter Mode When Entered.

Check Unit 1.

Enter Affected Equipment/Equipment Number Enter Work Order Number Enter SmartForm Numbers Standard: ENTERED motor bearing replacement.

ENTERED 1 for Mode.

CHECKED Unit 1.

ENTERED CP1-AFAPMD-02.

ENTERED N/A for Work Order and SmartForm Numbers.

Comment: SAT UNSAT Perform Step: 12 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Refer to ODA-308, Figure 7.1 Flowchart and determine if a SFDP is required by answering:

Is the LCO condition being entered for Technical Specifications?

Standard: ANSWERED YES based on Technical Specification entry required.

Comment: SAT UNSAT Perform Step: 13 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Refer to ODA-308, Figure 7.1 Flowchart and determine if a SFDP is required by answering:

Is the LCO condition being entered for SSC other than an instrument channel?

Standard: ANSWERED YES as this not an instrument failure.

Comment: SAT UNSAT Page 6 of 9 NRC SA3 (SO1024)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 14 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Refer to ODA-308, Figure 7.1 Flowchart and determine if a SFDP is required by answering:

Is the LCO being entered for a TS support system or supported system?

Standard: ANSWERED YES as Tech Spec LCO 3.7.5, Auxiliary Feedwater System on page 2 of Figure 7.1.

Comment: SAT UNSAT Perform Step: 15 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Refer to ODA-308, Figure 7.1 Flowchart and determine if a SFDP is required by answering:

Are existing TS LCO(s) presently in effect on components powered from the opposite Safeguards electrical train?

Standard: ANSWERED NO as there are no other LCOs currently in affect.

Loss of Safety Function does NOT exist.

An SFDP Evaluation is NOT required.

Comment: SAT UNSAT Perform Step: 16 Complete the Manual Standard LCOAR Form, ODA-308-3.7.5:

Checked SFDP Complete and Documented Results in Comments Standard: CHECKED SFDP Complete and ENTERED a Loss of Safety Function does NOT exist in the comments.

Comment: SAT UNSAT Page 7 of 9 NRC SA3 (SO1024)

Appendix C JPM STEPS Form ES-C-1 EXAMINER NOTE Candidate may check notifications LCOAR Initiation. These details are not included as the classroom environment does not allow for proper performance and is therefore not part of the JPM.

Perform Step: 18 Enter the LCOAR initiation Date/Time on the Manual Standard LCOAR Form, ODA-308-3.7.5:

Standard: ENTERED 3-2-15/1200 on ODA-308-48, Manual Standard LCOAR Form, ODA-308-3.7.5.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 8 of 9 NRC SA3 (SO1024)

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Unit 1 and Unit 2 are at 100% power.

Motor Driven Auxiliary Feed Water Pump 1-02 (CP1-AFAPMD-

02) was declared INOPERABLE for motor bearing replacement at 1200 on 3/2/15 per POD.

The electronic LCOAR program is out of service and there are no other Limiting Conditions for Operation in affect.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

COMPLETE the Manual Standard LCOAR Index per ODA-308, LCO Tracking Program.

COMPLETE the Manual Standard LCOAR up to the second SRO review. This is the first Manual LCOAR initiated this year.

Work Order and SmartForm Numbers may be marked as N/A.

PERFORM a Safety Function Determination (SFDP),

DOCUMENT results of SFDP in Comments area of LCOAR.

Page 9 of 9 NRC SA3 (SO1024)

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA4 Task #SO1142 K/A #2.3.4 3.2 / 3.7

Title:

Choose a Volunteer for Emergency Radiation Exposure Examinee (Print):

Testing Method:

Simulated Performance: X Classroom: X Actual Performance: Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A Large Break Loss of Coolant Accident has occurred.

Cold Leg recirculation operations have been established.

An operator venting Residual Heat Removal Pump 1-02 was injured and needs assistance to exit the Radiological Controlled Area.

The Emergency Coordinator has authorized one volunteer to attempt a lifesaving activity.

Health Physics predicts a dose between 15 and 20 REM given the general radiation levels in the area of the injured person.

Initiating Cue: The Emergency Coordinator directs you to PERFORM the following:

EVALUATE and SELECT the preferred volunteer from the list of available candidates per EPP-305, Emergency Exposure Guidelines and Personnel Dosimetry, Steps 4.3.2 and 4.3.4.

Page 1 of 8 NRC SA4 (SO1142A)

Appendix C JPM WORKSHEET Form ES-C-1 Volunteer Selected (Circle one) Why or Why NOT selected A YES / NO B YES / NO C YES / NO D YES / NO E YES / NO F YES / NO G YES / NO Task Standard: EVALUATED and SELECTED the preferred volunteer to perform lifesaving activities during an emergency per EPP-305.

Required Materials: EPP-305, Emergency Exposure Guidelines and Personnel Dosimetry, Rev. 12.

List of Available Volunteers.

Validation Time: 15 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 8 NRC SA4 (SO1142A)

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

EPP-305, Emergency Exposure Guidelines and Personnel Dosimetry.

LIST of Available Volunteers.

Page 3 of 8 NRC SA4 (SO1142A)

Appendix C JPM CUE SHEET Form ES-C-1

Denotes a Critical Step* START TIME:

Perform Step: 1 Selection of individuals authorized to receive an emergency exposure for the purpose of conducting lifesaving activities or activities required to protect large numbers of people, shall be based on the following criteria:

The individual should be a volunteer or a professional rescue person.

The individual should be familiar with the consequences of exposure to radiation.

The individual shall not be a female capable of reproduction.

If more than one volunteer is being considered, preference should be given to individuals who have reached age 45 years or older.

Standard: REFERED to EPP-305, Emergency Exposure Guidelines and Personnel Dosimetry, Step 4.3.2.

Comment: SAT UNSAT Perform Step: 2 The individual should be a volunteer or a professional rescue person.

Standard: DETERMINED that all individuals have volunteered for Emergency Exposure.

Comment: SAT UNSAT Perform Step: 3 The individual should be familiar with the consequences of exposure to radiation.

Standard: DETERMINED that one individual is NOT familiar with the consequences of exposure to radiation and ELIMINATE Volunteer A.

Comment: SAT UNSAT Perform Step: 4 The individual shall not be a female capable of reproduction.

Standard: DETERMINED that one female volunteer has declared that she is pregnant and the other is capable of reproduction and ELIMINATE Volunteers B & E.

Comment: SAT UNSAT Page 4 of 8 NRC SA4 (SO1142A)

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 5 If more than one volunteer is being considered, preference should be given to individuals who have reached age 45 years or older.

Standard: DETERMINED that several individuals have NOT reached the age of 45 years or older and ELIMINATE Volunteers C & F. (Volunteer F may also be eliminated due to possible Iodine allergy.)

Comment: SAT UNSAT Perform Step: 6 Once selection of individuals has been completed, the following criteria shall be considered, prior to dispatching these individuals::

Dose to the individual should not be planned to exceed the guidelines given in Attachment 1.

In accordance with the policy of minimizing total dose equivalent, respiratory protection equipment may be used to minimize internal exposure and protective clothing may be used to minimize skin contamination.

Limit exposures received under these conditions to once in a lifetime.

Standard: REFERED to EPP-305, Emergency Exposure Guidelines and Personnel Dosimetry, Step 4.3.4.

Comment: SAT UNSAT Perform Step: 7 Dose to the individual should not be planned to exceed the guidelines given in Attachment 1.

Standard: DETERMINED dose to the individual between 15 and 20 REM meets the guidelines given in Attachment 1.

Comment: SAT UNSAT Perform Step: 8 Limit exposures received under these conditions to once in a lifetime.

Standard: DETERMINED that one individual has already received an exposure for Protecting Valuable Property and ELIMINATE Volunteer D.

Comment: SAT UNSAT Page 5 of 8 NRC SA4 (SO1142A)

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 9 Select the individual.

Standard: SELECTED Volunteer G as the most appropriate candidate for Emergency Exposure.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 8 NRC SA4 (SO1142A)

Appendix C JPM CUE SHEET Form ES-C-1 List of Available Volunteers Volunteer A is a 46-year-old male who is a newly hired Custodian who works outside the Security Access Point. He has no prior radiation protection training.

Volunteer B is a 27-year-old female that tells you she is pregnant.

Volunteer C is a 24-year-old male who was recently qualified as a Nuclear Equipment Operator.

Volunteer D is a 52-year-old male with a lifetime exposure of 150 REM, including a Protecting Valuable Property dose of 15 REM at another facility.

Volunteer E is a 35-year-old female from the Maintenance Department who is trying to start a family.

Volunteer F is a 42-year-old female who is not capable of becoming pregnant. She does not eat seafood due to allergic reactions.

Volunteer G is a 50-year-old male Unit Supervisor at Comanche Peak recently removed from License duties.

Page 7 of 8 NRC SA4 (SO1142A)

Appendix C JPM CUE SHEET Form ES-C-1 Initial Given the following conditions:

Conditions:

A Large Break Loss of Coolant Accident has occurred.

Cold Leg recirculation operations have been established.

An operator venting Residual Heat Removal Pump 1-02 was injured and needs assistance to exit the Radiological Controlled Area.

The Emergency Coordinator has authorized one volunteer to attempt a lifesaving activity.

Health Physics predicts a dose between 15 and 20 REM given the general radiation levels in the area of the injured person.

Initiating Cue: The Emergency Coordinator directs you to PERFORM the following:

EVALUATE and SELECT the preferred volunteer from the list of available candidates per EPP-305, Emergency Exposure Guidelines and Personnel Dosimetry, Steps 4.3.2 and 4.3.4.

Volunteer Selected (Circle one) Why or Why NOT selected A YES / NO B YES / NO C YES / NO D YES / NO E YES / NO F YES / NO G YES / NO Page 8 of 8 NRC SA4 (SO1142A)

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA5 Task # SO1140 K/A # 2.4.44 2.4 / 4.4

Title:

Determine Protective Action Recommendations Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Comanche Peak Unit 2 has experienced a Large Break Loss of Coolant Accident with multiple failures of Safeguards equipment and a breach of Containment.

The Site is in a GENERAL EMERGENCY, a radiological release is in progress, and the following information is provided:

Core Exit Thermocouple highest reading is 1300ºF.

Containment pressure is 2 psig.

Meteorological Tower Data:

Wind Speed 5 mph.

Wind Direction from 180º.

Pasquill Stability Class is D.

Field Dose results are:

Distance TEDE CDE Thyroid 1 mile 2000 mrem 9000 mrem 5 miles 1200 mrem 6250 mrem 10 miles 400 mrem 1500 mrem Weather conditions include freezing rain and a temperature of 30°F throughout Somervell and Hood counties.

The Initial Protective Action Recommendation was made at 0800.

The current time is 0900.

The duration of the release cannot be determined at this time.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

DETERMINE PAR per EPP-304, Protective Action Recommendations.

HIGHLIGHT the Decision Path on Attachment 1.

COMPLETE Attachment 2, Minimum Affected Area - Three (3) Sectors or Attachment 2A, Minimum Affected Area - Five (5) Sectors, as appropriate.

Page 1 of 7 NRC SA5 (SO1140B)

Appendix C JPM WORKSHEET Form ES-C-1 Task Standard: Utilizing EPP-304, DETERMINED Protective Action in accordance with approved key.

Required Materials: EPP-304, Protective Action Recommendations, Rev. 21.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 7 NRC SA5 (SO1140B)

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

EPP-304, Protective Action Recommendations.

Highlight pen.

Page 3 of 7 NRC SA5 (SO1140B)

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from EPP-304, Attachment 1.

Perform Step: 1 Enter Attachment 1 at GENERAL EMERGENCY declared:

Is this the Initial PAR?

Standard: ENTERED Attachment 1 at GENERAL EMERGENCY declared and DETERMINED that this is NOT the Initial PAR and CHOSE NO path.

Comment: SAT UNSAT Perform Step: 2 TEDE 1 Rem at 1 mile OR CDE Thyroid 5 Rem at 1 mile Standard: DETERMINED Both TEDE and CDE Thyroid exceed 1 mile limits and CHOSE "YES" path.

Comment: SAT UNSAT Perform Step: 3 TEDE 1 Rem at 5 miles OR CDE Thyroid 5 Rem at 5 miles Standard: DETERMINED Both TEDE and CDE Thyroid exceed 5 miles limits and CHOSE "YES" path.

Comment: SAT UNSAT Perform Step: 4 TEDE 1 Rem at 10 miles OR CDE Thyroid 5 Rem at 10 miles Standard: DETERMINED Both TEDE and CDE Thyroid do NOT exceed 10 miles limits and CHOSE "NO" path.

Comment: SAT UNSAT Examiner Note: Reference Inset Table1 on Attachment 1.

1 Perform Step: 5 SHELTER OR EVACUATE?

Standard: REFERRED to Inset Table1.

Comment: SAT UNSAT Page 4 of 7 NRC SA5 (SO1140B)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 Has there been severe core damage AND is a Rad release in progress?

Standard: DETERMINED severe core damage exists due to Core Exit Thermocouple temperature with a radiation release in progress and CHOSE "YES" path.

Comment: SAT UNSAT Perform Step: 7 Can release duration be accurately determined AND will the release be of short duration?

Standard: DETERMINED release duration can NOT be accurately determined and will NOT be of short duration based on breach of Containment and CHOSE "NO" path.

Comment: SAT UNSAT Perform Step: 8 Impediments? (ice, roads, hostile threat)

Standard: DETERMINED impediments exist from the Initial Conditions due to weather conditions and CHOSE YES path to SHELTER.

Comment: SAT UNSAT 1

Perform Step: 9 SHELTER OR EVACUATE?

Standard: CHOSE SHELTER path to Box D and SHELTERED 2 mile radius and Downwind Sectors to 10 miles AND ADVISED remainder of EPZ to go indoors and LISTEN to EAS.

Comment: SAT UNSAT Examiner Note: The following steps are from EPP-304, Attachment 2.

Examiner Note: The first sequence of steps on either Attachment is used to determine if Attachment 2 or 2A is appropriate.

Perform Step: 10 To identify Minimum Affected Area, use instruction below to determine Step 1 appropriate Attachment (Attachment 2 or Attachment 2A).

Standard: REFERRED to Attachment 2 or 2A.

Comment: SAT UNSAT Page 5 of 7 NRC SA5 (SO1140B)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 11 IF conditions are:

Step 1 ON-SITE Pasquill Stability Class C, D, E, F, or G and ON-SITE Wind Direction (From) is available THEN use Attachment 2 Standard: DETERMINED that Stability Class D allows Attachment 2 use.

Comment: SAT UNSAT Perform Step: 12 Circle ON-SITE Pasquill Stability Class C D E F G Step 2 Standard: CIRCLED Pasquill Stability Class D.

Comment: SAT UNSAT Perform Step: 13 Enter Wind Direction (From): ___________ degrees Step 3 Standard: ENTERED Wind Direction from 180 degrees.

Comment: SAT UNSAT Perform Step: 14 Circle applicable Centerline Sector in the Table below Step 4 Standard: CIRCLED Centerline Sector A.

Comment: SAT UNSAT Perform Step: 15 Knowing Centerline Sector, GO TO applicable subsequent page to Step 5 identify affected sectors and Emergency Response Zones (ERZ).

Standard: Knowing Centerline Sector is A, CIRCLED or HIGHLIGHTED the following:

AFFECTED SECTORS are RAB.

EMERGENCY RESPONSE ZONES from 0 to < 5 miles are 2A, 4B, 4C, 4A, 1B.

EMERGENCY RESPONSE ZONES from > 5 to < 10 miles are 1D, 4E, 4F, 1C.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 NRC SA5 (SO1140B)

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Comanche Peak Unit 2 has experienced a Large Break Loss of Coolant Accident with multiple failures of Safeguards equipment and a breach of Containment.

The Site is in a GENERAL EMERGENCY, a radiological release is in progress, and the following information is provided:

Core Exit Thermocouple highest reading is 1300ºF.

Containment pressure is 2 psig.

Meteorological Tower Data:

Wind Speed 5 mph.

Wind Direction from 180º.

Pasquill Stability Class is D.

Field Dose results are:

Distance TEDE CDE Thyroid 1 mile 2000 mrem 9000 mrem 5 miles 1200 mrem 6250 mrem 10 miles 400 mrem 1500 mrem Weather conditions include freezing rain and a temperature of 30°F throughout Somervell and Hood counties.

The Initial Protective Action Recommendation was made at 0800.

The current time is 0900.

The duration of the release cannot be determined at this time.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

DETERMINE PAR per EPP-304, Protective Action Recommendations.

HIGHLIGHT the Decision Path on Attachment 1.

COMPLETE Attachment 2, Minimum Affected Area - Three (3)

Sectors or Attachment 2A, Minimum Affected Area - Five (5) Sectors, as appropriate.

Page 7 of 7 NRC SA5 (SO1140B)

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 Facility: CPNPP Units 1 and 2 Date of Examination: June 2015 Exam Level: RO SRO(I) SRO (U) Operating Test Number: NRC Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function 001 -Control Rod Drive System (RO1030) D,S 1 S-1 Respond to Control Rods Below Insertion Limit 006 -Emergency Core Cooling System (RO1506D) A,EN,L,M,S 2 S-2 Transfer ECCS to Cold Leg Recirculation 006 -Emergency Core Cooling System (RO1511) A,EN,L,N,S 3 S-3 Isolate SI Accumulators Following a LOCA 005 -Residual Heat Removal System (RO1402) L,N,S 4P S-4 Alternate Residual Heat Removal Trains 045 -Main Turbine Generator System (RO3149) L,N,S 4S S-5 Roll Main Turbine to 1800 RPM (RO Only) 022 -Containment Cooling System (RO2101A) A,N,S 5 S-6 Alternate Containment Recirculation Units(CACRS) 064 -Emergency Diesel Generator System (RO4302D) A,D,S 6 S-7 Load Emergency Diesel Generator 008 -Component Cooling Water System (RO3603C) M,S 8 S-8 Rotate Component Cooling Water Pumps In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) 007 -Reactor Trip (AO6439B) D,E,R 1 P-1 Trip the Reactor and Stop MG Sets 068 -Control Room Evacuation (AO6413B) A,M,E,L,R 8 P-2 Respond to a Fire in the Control Room or Cable Spreading Room, NEO #2 Actions 062 -AC Electrical Distribution System (AO4204D) N,E 6 P-3 Transfer Inverter IVuPC1 from Bypass to Normal Page 1 of 4 ES-301-2 CPNPP 2015 RO & SRO System JPM Outline

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 RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / > 1(control room system)

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

(R)CA >1 / >1 / >1 (S)imulator NRC JPM Examination Summary Description S-1 Following a turbine runback, due to a trip of a Heater Drain Pump from 100%

power, the applicant will determine that control rods are below the required rod insertion limit by using ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, Section 4.0, Heater Drain Pump Trip. This JPM, requiries the applicant to manually determine the required boration using the Reactivity Briefing Sheet. The critical steps include determination of how much boration is needed, and the various control board manipulations needed to perform the boration. This is a direct from bank JPM under Control Rod Drive System - Reactivity Control Safety Function. (K/A 001.A4.05 - IR 3.7 / 3.7)

S-2 The applicant will be required to use EOS-1.3A, Transfer to Cold Leg Recirculation following a Large Break LOCA. This is an Alternate Path JPM because one of the RHR pump suction valves will NOT open, and the applicant will need to perform alternate steps for system realignment, including shutting off one pump and ensuring the other RHR pump is running. The critical steps include recognition of one RHR pump suction valve failing to open, and various control board manipulations needed for realignment in order to achieve cold leg recirculation.

This is a PRA significant action. This is a modified from bank JPM under the Emergency Core Cooling System - Reactor System Inventory Control Safety Function. (K/A 006.A4.05 - IR 3.7 / 3.6)

Page 2 of 4 ES-301-2 CPNPP 2015 RO & SRO System JPM Outline

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 S-3 Using EOS-1.2A, Post LOCA Cooldown and Depressurization, the applicant will be required to continue with Step 26 for determining if SI accumulators should be isolated and to isolate the accumulators. This is an Alternate Path JPM and requires the applicant to determine that one of the accumulator injection valves will NOT close. This will require the applicant to vent off this accumulator to minimize the consequences of undesired injection, since the accumulator cannot be isolated. The critical steps include restoring power to the injection valves, operation of the accumulator injection valves, and venting of the accumulator that cannot be isolated. This is a new JPM under the Emergency Core Cooling System

- Reactor Pressure Control Safety Function. (K/A 006.A4.02 - IR 4.0 / 3.8)

S-4 The applicant will use SOP-102A, Residual Heat Removal System, Section 5.6 Alternating RHR Trains in MODE 5, 6, or Defueled to perform the task. The critical steps will include various control board manipulations required for making the swap such as starting and stopping RHR pumps, operation of control valves, and requirements for temperature control. This is a new JPM under the Residual Heat Removal System - Primary System Heat Removal from Reactor Core Safety Function. (K/A 005.A4.01 - IR 3.6 / 3.4)

S-5 The applicant will use IPO-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator, beginning at Step 5.1.18 and completing Step 5.1.21. This involves setting up the turbine control for rolling the turbine to 1800 RPM. The Overspeed Trip test will NOT be required. The critical steps include setting up the turbine control panel to open the HP and LP stop valves, an interim step of holding at 500 RPM, placing of bearing lift oil pumps to AUTO, and then continuing to 1800 RPM where the JPM will terminate. This is a new JPM under the Main Turbine Generator System - Secondary System Heat Removal from Reactor Core Safety Function. RO Only.

(K/A 045.A4.02 - IR 2.7 / 2.6)

S-6 With a Containment Vent in progress, the applicant is directed to alternate Containment Recirculation Units using SOP-801A, Containment Ventilation System, Section 5.1.3. During the swap Containment Air Gaseous radiation monitor goes into Alert. This is an alternate path JPM requiring action to manually initiate isolation of the Containment Vent. The critical steps include starting the desired cooling unit and manual operation of several valves for isolation of the Containment Vent evolution. This is a new JPM under the Containment Cooling System - Containment Integrity Safety Function. (K/A 022.A4.01 - IR 3.6 / 3.6)

S-7 With OPT-214A, Diesel Generator Operability Test in progress and following a fast start of Diesel Generator 1-01, the applicant is to continue with the surveillance.

This involves beginning to load the diesel generator. This is an Alternate Path JPM. When loading is raised to approximately 2.2 MW, the Station Service Water Pump 1-01 will trip. This will result in the diesel generator running loaded with no cooling water. The applicant is required to shut down the diesel generator. The critical steps are proper loading of the diesel generator and shutting down the diesel generator to prevent equipment damage. This is a direct from bank JPM under the Emergency Diesel Generator System - Electrical Safety Function.

(K/A 064.A4.06 - IR 3.9 / 3.9)

Page 3 of 4 ES-301-2 CPNPP 2015 RO & SRO System JPM Outline

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 S-8 The applicant is directed to swap Component Cooling Water Pumps from Train A to Train B, using SOP-502A, Component Cooling Water System. The critical steps include establishing required system flow, control board manipulations required for the swap, starting the idle pump, and shutting down the pump to be idled. This is a modified from bank JPM under the Component Cooling Water System - Plant Service Systems Safety Function.

(K/A 008.A4.01 - IR 3.3 / 3.1)

P-1 With an Anticipated Transient Without Trip in progress on Unit 1, the applicant is required to locally trip the Unit 1 reactor, and to stop both Rod Drive Motor Generator Sets, in accordance with FRS-0.1A, Response to Nuclear Power Generator/ATWT, Step 6a RNO. Through a series of simulated operations and examiner cues, the applicant will open RTA and RTB trip breakers as critical steps.

The bypass breakers will not be considered critical steps. When that is complete, the applicant will de-energize both MG Sets by opening associated breakers, each of which is a critical step. This is a PRA significant action. This is a direct from bank JPM under the Reactor Trip System - Reactivity Control Safety Function.

(K/A 007.EA2.02 - IR 4.3 / 4.6)

P-2 During a Control Room evacuation due a fire, the applicant is required to take action to place the plant in control of the operators from outside the control room.

Actions will be performed using ABN-803A, Response to a Fire in the Control Room or Cable Spreading Room, Attachment 4, Nuclear Equipment Operator No.

2 Actions to Achieve Hot Shutdown. The critical steps include starting the Safety Chiller, Isolating RHR from the RWST and controlling AFW flow to the Steam Generators. This is a PRA significant action. This is a modified from bank JPM under the Control Room Evacuation System - Plant Service Systems Safety Function.

(K/A 068.AA1.26 - IR 3.6 / 3.8)

P-3 The applicant will be directed to perform SOP-607A/B, 118 VAC Distribution System and Inverters, Section 5.5.9 Transferring Inverter IVuPC1 from Bypass to Normal Operation. The critical steps will include operating the Static Transfer Switch to make the swap, and aligning the inverter to complete the operation. This is a new JPM under the AC Electrical Distribution System - Electrical Safety Function. (K/A 062.A4.04 - IR 2.6 / 2.7)

Page 4 of 4 ES-301-2 CPNPP 2015 RO & SRO System JPM Outline

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-1 Task # RO1030 K/A # 001.A4.05 3.7 / 3.7 SF-1

Title:

Respond to Control Rods Below Insertion Limit Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 has experienced a trip of Heater Drain Pump 1-01 from 100% MOL conditions.

All automatic control systems responded as expected.

ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, Section 4.0 Heater Drain Pump Trip is in progress.

The automatic turbine runback was completed, per ABN-302, Section 4.3, Step 1.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

Complete ABN-302, Section 4.0 beginning at Step 4.3.7.

Task Standard: Determined that control rods were not above the rod insertion limit and initiated a boration of a minimum of 175 gallons in accordance with the Reactivity Briefing Sheet.

Required Materials: MOL Reactivity Briefing Sheet.

ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, Rev. 14 PCN 18.

SOP-104A, Reactor Make-Up and Chemical Control System, Rev. 15 PCN 2.

Validation Time: 8 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 CPNPP NRC 2015 JPM S-1

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP SIMULATOR OPERATOR:

INITIALIZE to IC-46 and ENSURE the corrected boron concentration is displayed as the SAME VALUE (924 ppm) for all three parameters on the CB-06 Operator Aid.

OR INITIALIZE to IC-18 and INSERT the following:

FW14A, Heater Drain Pump 1 Trip Allow the plant to stabilize with the Control Rods below the RIL, and FREEZE.

EXAMINER:

PROVIDE the examinee with a copy of:

ABN-302, Section 4.0.

MOL Reactivity Briefing Sheet when requested.

SOP-104A, Section 5.1.2 when requested.

Page 2 of 7 CPNPP NRC 2015 JPM S-1

Appendix C JPM CUE SHEET Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-302, Section 4.3.

Perform Step: 1 Verify the following:

4.3.7.a Rods - ABOVE ROD INSERTION LIMIT Standard: DETERMINED that the Control Rods are below the Rod Insertion Limit.

Comment: SAT UNSAT Perform Step: 2 Verify SDM or initiate boration to restore SDM within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore Rods 4.3.7a RNO above insertion limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per TS 3.1.6.

Examiner Cue: If examinee informs examiner that they would contact Core Performance for a SDM calculation, state that Core Performance will not be available for minimum of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Standard: DETERMINED that boration is required.

Comment: SAT UNSAT Examiner Note: Provide examinee a copy of the Reactivity Briefing Sheet when requested.

Perform Step: 3 Using Reactivity Briefing Sheet for Runback to 800 MWe, determines that a Reactivity Briefing boration of 175 gallons should be initiated.

Sheet A Standard: Determined that a boration of 175 gallons should be initiated.

Examiner Cue: If examinee informs examiner that a boration is required per the Reactivity Briefing Sheet, state that the Unit Supervisor directs you to perform the required boration.

Comment: SAT UNSAT Page 3 of 7 CPNPP NRC 2015 JPM S-1

Appendix C JPM CUE SHEET Form ES-C-1 Examiner Note: The following steps are from SOP-104A, Section 5.1.2.

Perform Step: 4 Ensure the prerequisites of Section 2.1 and 2.2 are met.

5.1.2.A Standard: DETERMINED that the prerequisites of Section 2.1 are met and 2.2 are N/A for this evolution.

Comment: SAT UNSAT Perform Step: 5 If at BOL and desire to periodically Borate for long term THEN Use Attachment 5..1.2.B 2, BOL Boration for Long Term Use.

Standard: DETERMINED step is N/A.

Comment: SAT UNSAT N/A Perform Step: 6 ENSURE 1/1-MU, RCS MU MAN ACT is in STOP.

5.1.2.C Standard: PLACED 1/1-MU, RCS MU MAN ACT in STOP.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2015 JPM S-1

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 7 ENSURE the following handswitches are in AUTO, AND the valves are 5.1.2.D CLOSED:

1/1-FCV-111A, RMUW BLNDR FLO CTRL VLV 1/1-FCV-111B, RCS MU TO VCT ISOL VLV 1/1-FCV-110A, BA BLNDR FLO CTRL VLV 1/1-FCV-110B, RCS MU TO CHRG PUMP SUCT ISOL VLV Standard: VERIFIED all valves are in AUTO and CLOSED.

Comment: SAT UNSAT Perform Step: 8 PLACE 43/1-MU, RCS MU MODE SELECT in BORATE.

5.1.2.E Standard: PLACED 43/1-MU, RCS MU MODE SELECT in BORATE.

Comment: SAT UNSAT Perform Step: 9 SET 1-FK-110, BA BLNDR FLO CTRL to obtain the desire flowrate (Pot setting 5.1.2.F = flowrate/4).

Standard: LEFT 1-FK-110, BA BLNDR FLO CTRL at as found setting or ADJUSTED to desired flow setting..

Comment: SAT UNSAT Examiner Note: The counter has to be set to 1750 to obtain 175.0 gallons. The final digit is the tenths of gallons on the counter.

Perform Step: 10 SET 1-FY-110B, BA BATCH FLO counter to obtain the desired number of 5.1.2.G gallons.

Standard: SET 1-FY-110B, BA BATCH FLO counter at any setting > 175.0.

Comment: SAT UNSAT Perform Step: 11 START boration by placing 1/1-MU, RCS MU MAN ACT in START.

5.1.2.H Standard: PLACED 1/1-MU, RCS MU MAN ACT in START.

Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2015 JPM S-1

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 12 VERIFY a BA XFER PMP - STARTS.

5.1.2.I Standard: VERIFIED 1/1-APBA1, BA XFER PMP 1 RED light LIT, GREEN light DARK.

Comment: SAT UNSAT Perform Step: 13 VERIFY the following:

5.1.2.J 1/1-FCV-110A, BA BLNDR FLO CTRL VLV - THROTTLES to preset flow rate.

1/1-FCV-110B, RCS MU TO CHRG PMP SUCT ISOL VLV - OPENS.

Standard: VERIFIED 1/1-FCV-110A throttles to corresponding position and 1/1-FCV-110B OPENS.

Comment: SAT UNSAT Perform Step: 14 VERIFY the following are operating properly:

5.1.2.K 1-FY-110B, BA BATCH FLO counter 1-FR-110, R: BA FLO TO BLNDR/G: RCS MU FLO Flow Recorder Standard: VERIFIED 1-FY-110B and 1-FR-110 operating properly.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2015 JPM S-1

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 1 has experienced a trip of Heater Drain Pump 1-01 from 100% MOL conditions.

All automatic control systems responded as expected.

ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, Section 4.0 Heater Drain Pump Trip is in progress.

The automatic turbine runback was completed, per ABN-302, Section 4.3, Step 1.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

Complete ABN-302, Section 4.0 beginning at Step 4.3.7.

Page 7 of 7 CPNPP NRC 2015 JPM S-1

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-2 Task #RO1506 K/A 006.A4.05 3.7 / 3.6 SF-2

Title:

Transfer the ECCS System from the Injection Phase to the Cold Leg Recirculation Phase Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: X Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A Large Break Loss of Coolant Accident has occurred.

Refueling Water Storage Tank LO-LO level alarm has been reached.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

ALIGN the Emergency Core Cooling System for Cold Leg Recirculation per EOS-1.3A, Transfer to Cold Leg Recirculation.

Task Standard: Transferred both trains of ECCS to Cold Leg Recirculation.

Required Materials: EOS-1.3A, Transfer to Cold Leg Recirculation, Rev. 8 PCN 5.

Validation Time: 10 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 13 CPNPP NRC 2015 JPM S-2

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP SIMULATOR OPERATOR:

INITIALIZE to IC-41 OR INITIALIZE to any at power Initial Condition and PERFORM the following:

a. INSERT malfunction RC08D2, Large Break LOCA.

b. INSERT malfunction SS03F2, Defeats AUTO Swapover for Train B RHR.

c. PLACE Simulator in RUN.

d. REDUCE AFW flow to all Steam Generators.

e. RESET the following:

1. Safety Injection.

2. Safety Injection Sequencers.

3. Phase A & B Containment Isolation.

STOP both Emergency Diesel Generators.

STOP all Reactor Coolant Pumps.

ENSURE CCW Flow established to RHR and Containment Spray Heat Exchangers.

When the RWST reaches the LO-LO level setpoint of 33%:

Place Train B, Containment Spray Pumps and Heat Exchanger Outlet valve in Pull-out.

FREEZE the Simulator.

EXAMINER:

PROVIDE the examinee with a copy of EOS-1.3A, Transfer to Cold Leg Recirculation.

Page 2 of 13 CPNPP NRC 2015 JPM S-2

Appendix xC JPM STEP PS Foorm ES-C-1

- Chec ck Mark De enotes Crittical Step ST TART TIME E:

Examiner Note: The following ste eps are fro m EOS-1.3 3A.

Perform m Step: 1 Reset SI.

S 1

Standarrd: DEP PRESSED 1/1-SIRA 1 a nd 1/1-SIR RB OR DET TERMINED from PCIP P that SI wa as already R Reset.

Comme ent: AT UNS SA SAT Perform m Step: 2 Verify CCW C Flow As A Requireed:

2 Fromm RHR heatt exchangerrs Fromm Containme ent Spray h heat exchanngers Standarrd: VERIFIED FLOW on 1-FI-455 56, 1-FI-45 560, 1-FI-45 558 and 1-F FI-4562 Comme ent: AT UNS SA SAT Page 3 of o 13 CPNNPP NRC 2 015 JPM S--2

Appendix xC JPM STEP PS Fo orm ES-C-1 Perform m Step: 3 Align ECCCS For Cold C Leg Reecirculation::

3a a. Check open CN NTMT SMP P TO RHRP P 1 AND RH HRP 2 SUC CT ISOL VLV VS:

1/1-8811A 1

Standarrd: DETER RMINED 1/1 1-8811A OP PEN, red lig ght LIT, greeen light DA ARK Comme ent: SAAT UNS SAT Perform m Step: 4 Align ECCCS For Cold C Leg Reecirculation::

3a a. Check open CN NTMT SMP P TO RHRP P 1 AND RH HRP 2 SUC CT ISOL VS:

VLV 1/1-8811B 1

Standarrd: DETER RMINED 1/1 1-8811B CL LOSED, red d light DARRK, green Light LIT Comme ent: SAAT UNS SAT Examiner Note: The following ste ep represen nts the alteernate pathh of this JPPM.

Perform m Step: 5 IF ONEE RHR sump p suction va alve failed tto open, TH HEN stop R RHR pump 3a RNO with vallve closed AND A go to S Step 3b to align opera ating RHR p pump.

Stop p RHR pum mp 1(2).

Standarrd: PLACED 1/1-APR RH2 in STO P. (PULL O OUT is also o acceptablle).

Comme ent: SAAT UNS SAT Page 4 of o 13 CPNNPP NRC 2 015 JPM S--2

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 b. CLOSE RWST TO RHRP 1 AND RHRP 2 SUCT VLVS:

3b 1/1-8812A Standard: PERFORMED the following:

PLACED 1/1-8812A, in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (not-critical).

Comment: SAT UNSAT Examiner Note: 1/1-8812B will be closed in step 5 g. The step is only critical when the valve is closed, if verified in Step 5 g. the step is not critical.

The examinee may choose to not close 1/1-8812B at this time and that is also acceptable.

Perform Step: 7 b. CLOSE RWST TO RHRP 1 AND RHRP 2 SUCT VLVS:

3b 1/1-8812B Standard: PERFORMED the following:

PLACED 1/1-8812B in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (not-critical).

Comment: SAT UNSAT Examiner Note: The critical step is to either:

Close 1/1-8814A AND 1/1-8814B OR Close 1/1-8813 Perform Step: 8 c. Close SIP 1 AND SIP 2 MINIFLO VLVS:

3c 1/1-8814A Standard: PERFORMED the following:

PLACED 1/1-8814A in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (not-critical).

Comment: SAT UNSAT Page 5 of 13 CPNPP NRC 2015 JPM S-2

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Close SIP 1 AND SIP 2 MINIFLO VLVS:

3c 1/1-8814B Standard: PERFORMED the following:

PLACED 1/1-8814B in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (not-critical).

Comment: SAT UNSAT Perform Step: 10 Close SIP 1 AND SIP 2 MINIFLO VLVS:

3c 1/1-8813 Standard: INSERTED key and TURNED Key switch to ON. PLACED 1/1-8813 in CLOSE.

Comment: SAT UNSAT Examiner Note: It is critical that either 1/1-8716A OR 1/1-8716B is CLOSED.

Perform Step: 11 Close RHRP 1 AND RHRP 2 XTIE VLVS:

3d 1/1-8716A Standard: PERFORMED the following:

PLACED 1/1-8716A in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (not-critical).

Comment: SAT UNSAT Perform Step: 12 Close RHRP 1 AND RHRP 2 XTIE VLVS:

3d 1/1-8716B Standard: PERFORMED the following:

PLACED 1/1-8716B in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (not-critical).

Comment: SAT UNSAT Page 6 of 13 CPNPP NRC 2015 JPM S-2

Appendix C JPM STEPS Form ES-C-1 Examiner Note: It is critical that either 1/1-8511A OR 1/1-8512B is CLOSED.

Perform Step: 13 Close the CCP ALT MINIFLO ISOL VLVS:

3e 1/1-8511A Standard: PERFORMED the following:

PLACED 1/1-8511A in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (NOT critical).

Comment: SAT UNSAT Perform Step: 14 Close the CCP ALT MINIFLO ISOL VLVS:

3e 1/1-8512B Standard: PERFORMED the following:

PLACED 1/1-8512B in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (NOT critical).

Comment: SAT UNSAT Examiner Note: It is critical that either 1/1-8511B OR 1/1-8512A is CLOSED.

Perform Step: 15 Close the CCP ALT MINIFLO ISOL VLVS:

3e 1/1-8511B Standard: PERFORMED the following:

PLACED 1/1-8511B in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (NOT critical).

Comment: SAT UNSAT Perform Step: 16 Close the CCP ALT MINIFLO ISOL VLVS:

3e 1/1-8512A Standard: PERFORMED the following:

PLACED 1/1-8512A in CLOSE (critical).

OBSERVED green CLOSE light LIT, red OPEN light DARK (NOT critical).

Comment: SAT UNSAT Page 7 of 13 CPNPP NRC 2015 JPM S-2

Appendix C JPM STEPS Form ES-C-1 Examiner Note: It is critical that either 1/1-8807A OR 1/1-8807B is OPENED.

Perform Step: 17 Open SI CHRG SUCT HDR XTIE VLVS:

3f 1/1-8807A Standard: PERFORMED the following:

PLACED 1/1-8807A in OPEN (critical).

OBSERVED green CLOSE light DARK, red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 18 Open SI CHRG SUCT HDR XTIE VLVS:

3f 1/1-8807B Standard: PERFORMED the following:

PLACED 1/1-8807B in OPEN (critical).

OBSERVED green CLOSE light DARK, red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 19 Open RHRPs TO CCP/SIP SUCT VLVs:

3g 1/1-8804A Standard: PERFORMED the following:

PLACED 1/1-8804A in OPEN (critical).

OBSERVED green CLOSE light DARK, red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 20 Open RHRPs TO CCP/SIP SUCT VLVs:

3g 1/1-8804B Standard: PERFORMED the following:

PLACED 1/1-8804B in OPEN (critical).

OBSERVED green CLOSE light DARK, red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Page 8 of 13 CPNPP NRC 2015 JPM S-2

Appendix xC JPM STEP PS Fo orm ES-C-1 Perform m Step: 21 Align Containmentt Spray Sysstem for reccirculation.

4 Examiner Cue: Anothe er Operatorr will perfo orm Attach hment 1H o of EOS-1.3A A.

Comme ent: AT UNS SA SAT Perform m Step: 22 Performm the follow wing to comp plete Recircculation Alignment:

5 a. a. Check ECCS aligned a for ccold leg reccirculation.

Standarrd VERIFIED Train A RHR is su upplying EC CCS pump ssuctions via a 1/1-8804A.

Comme ent: AT UNS SA SAT Perform m Step: 23 b. Verify y closed CCCP MINIFLO O VLVS:

5 b. 1/11-8110 1/11-8111 Standarrd: VERIFIED CCP MINIFLO M VLLVS Closed:

1/1-88110 - greeen CLOSED D light LIT, rred OPEN light OFF.

1/1-88111 - greeen CLOSED D light LIT, rred OPEN light OFF.

Comme ent: AT UNS SA SAT Page 9 of o 13 CPNNPP NRC 2 015 JPM S--2

Appendix C JPM STEPS Form ES-C-1 Perform Step: 24 c. Close RWST TO CHRG PMP SUCT VLVS:

5 c. 1/1-LCV-112D 1/1-LCV-112E Standard: CLOSED RWST TO CHRG PMP SUCT VLVS:

1/1-LCV-112D, green CLOSED light LIT, red OPEN light OFF.

1/1-LCV-112E, green CLOSED light LIT, red OPEN light OFF.

Comment: SAT UNSAT Perform Step: 26 Verify CCP injection flow.

5 d.

Standard: VERIFIED flow on 1-FI-917, CCP SI FLO (CB04).

Comment: SAT UNSAT Perform Step: 27 Close RWST TO SIP SUCT VLV:

5 e. 1/1-8806 Standard: CLOSED 1/1-8806, green closed light LIT, red open light OFF (CB02).

Comment: SAT UNSAT Perform Step: 28 Verify SIP discharge flow(s).

5 f.

Standard: VERIFIED flow on 1-FI-918, SIP 1 DISCH FLO and/or 1-FI-922, SIP 2 DISCH FLO (CB02).

Comment: SAT UNSAT Perform Step: 29 Check RHR Status:

5 g. 1) Both RHR Trains running in cold leg recirculation.

Standard: DETERMINED train B RHR pump is not running (CB04).

Comment: SAT UNSAT Page 10 of 13 CPNPP NRC 2015 JPM S-2

Appendix C JPM STEPS Form ES-C-1 Examiner Note: If 1/1-8812B was closed in step 3 b. (Performance Step 7), then this is NOT a critical step.

Perform Step: 30 Perform the following:

5 g. 1) RNO A) IF RHR pump is stopped because CNTMT SMP TO RHRP 1 or RHRP 2 SUCT ISOL VLV (1/1-8811A or 1/1-8811B) failed to automatically open, THEN perform the following:

A) Close RWST to RHR Pump Suction Valve (1/1-8812A or 1/1-8812B) for the affected pump.

Standard: DETERMINED train B RHR pump is not running (non-critical)

CLOSED 1/1-8812B, green closed light LIT, red open light OFF (CB04). (critical)

Comment: SAT UNSAT Examiner Note: Applicants may use Plant Computer to verify valve position.

Perform Step: 31 Perform the following:

5 g. 1) RNO B) IF RHR pump is stopped because CNTMT SMP TO RHRP 1 or RHRP 2 SUCT ISOL VLV (1/1-8811A or 1/1-8811B) failed to automatically open, THEN perform the following:

B) Close RCS RHR Pump Suction Valve (1/1-8701A(B) OR 1/1-8702A(B) for the affected pump.

Standard: VERIFIED Closed 1/1-8701A and 1/1-8702B based on job aid on hand switches and green closed light OFF, red open light OFF (CB04).

Comment: SAT UNSAT Perform Step: 32 Perform the following:

5 g. 1) RNO C) IF RHR pump is stopped because CNTMT SMP TO RHRP 1 or RHRP 2 SUCT ISOL VLV (1/1-8811A or 1/1-8811B) failed to automatically open, THEN perform the following:

C) Open CNTMT Sump to RHR Pump Suction Valve (1/1-8811A OR 1/1-8811B) for the affected pump.

Standard: OPENED 1/1-8811B, green closed light OFF, red open light LIT (CB04).

Comment: SAT UNSAT Page 11 of 13 CPNPP NRC 2015 JPM S-2

Appendix C JPM STEPS Form ES-C-1 Perform Step: 33 Start affected RHR pump.

5 g. 1) RNO D)

Standard: PLACED 1/1-APRH2 in START. (CB04)

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 12 of 13 CPNPP NRC 2015 JPM S-2

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A Large Break Loss of Coolant Accident has occurred.

Refueling Water Storage Tank LO-LO level alarm has been reached.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

ALIGN the Emergency Core Cooling System for Cold Leg Recirculation per EOS-1.3A, Transfer to Cold Leg Recirculation.

Page 13 of 13 CPNPP NRC 2015 JPM S-2

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-3 Task # RO1511 K/A # 006.A4.02 4.0 / 3.8 SF-3

Title:

Isolate SI Accumulators Following a LOCA Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: X Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A LOCA has occurred.

The reactor has been tripped and safety injection initiated.

Appropriate actions of EOP-0.0A, Reactor Trip or Safety Injection and EOP-1.0A, Loss of Reactor or Secondary Coolant have been completed.

Actions of EOS-1.2A, Post LOCA Cooldown and Depressurization, have been completed through step 25.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

Continue actions of EOS-1.2A, Post LOCA Cooldown and Depressurization.

Start at EOS-1.2A, step 26.

Task Standard: Isolated SI accumulators 1-01, 1-02, and 1-03. Vented pressure from SI Accumulator 1-04 after determining the isolation valve would not close from the Control Room.

Required Materials: EOS-1.2A, Post LOCA Cooldown and Depressurization, Rev. 8-5.

Keys for 69/1-8808A - 8808D POWER switches.

Validation Time: 5 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 CPNPP NRC 2015 JPM S-3

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP SIMULATOR OPERATOR:

INITIALIZE to IC-36 OR PERFORM the following:

Load a 100% Power IC EXECUTE the following:

Insert override OPEN ACCUM 4 INJ VLV, 1/1-8808D.

Insert Malfunction RC17A, SBLOCA approximately 750 GPM then reduce to 300 gpm as required to stabilize the Unit with the following conditions:

Pressurizer Level approximately 60%.

RCS Temperature approximately 490 F.

RCS Pressure is above Accumulator injection pressure, approximately 1300 psig.

Perform appropriate actions of EOP-0.0A, Reactor Trip or Safety Injection, transition to and perform appropriate actions of EOP-1.0A, Loss of Reactor or Secondary Coolant, then perform appropriate actions of EOS-1.2A, Post LOCA Cooldown and Depressurization through step 25.

Prepare the following Scenario File to energize the SI accumulator Valves:

IRF SIR03 f:1 k:1 IRF SIR04 f:1 k:1 IRF SIR05 f:1 k:1 IRF SIR06 f:1 k:1 Place Simulator in Freeze.

When directed by the Examiner, place Simulator in run when examinee is ready to begin.

EXAMINER:

PROVIDE the examinee with a copy of EOS-1.2A, Post LOCA Cooldown and Depressurization.

Ensure all steps, as applicable are COMPLETE and PLACE KEPT through Step 25.

Page 2 of 7 CPNPP NRC 2015 JPM S-3

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from EOS-1.2A.

Perform Step: 1 Check If Accumulators Should Be Isolated:

26.a RCS subcooling - GREATER THAN 25F (55F FOR ADVERSE CONTAINMENT)

Standard: DETERMINED subcooling greater than 55F.

Comment: SAT UNSAT Perform Step: 2 PRZR level - GREATER THAN 13% (34% FOR ADVERSE CONTAINMENT) 26.b Standard: DETERMINED that Pressurizer Level is approximately 60%.

Comment: SAT UNSAT Perform Step: 3 Check power to injection valves - AVAILABLE 26.c Standard: DETERMINED Accumulator Power Switches are OFF and all Accumulator Injection Valve indications are DARK, indicating that the valves do NOT have power.

Comment: SAT UNSAT Page 3 of 7 CPNPP NRC 2015 JPM S-3

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Accumulator Injection Valves may be isolated in any order.

Examiner Note: Once examinee indicates that a key is required to energize the Accumulator Injection Valves, the examiner shall provide the required keys.

Examiner Note: When the Examinee requests the NEO energize the SI accumulator injection valves, have the SIMULATOR OPERATOR actuate key 1 to energize the valves. All four valves will energize at the same time.

SIMULATOR Actuate key 1 to energize all four accumulator valves when directed by OPERATOR NOTE: the Examiner to insert the following remote functions to energize the SI accumulator valves:

IRF SIR03 f:1 IRF SIR04 f:1 IRF SIR05 f:1 IRF SIR06 f:1 Perform Step: 4 Restore power to injection valve(s) 26.c RNO Standard: Contacted NEO to turn on the breakers for all four SI accumulator injection valves.

Examiner Cue: Report as the NEO that the SI accumulator injection valve breakers are ON.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2015 JPM S-3

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Critical portion of step is to CLOSE 1, 2 and 3 Accumulator Injection Valves. 69/1-8808A through C, POWER, switches must be placed in ON using the Key in order to close the valves.

Accumulator injection valve 4 will not close and is therefore not critical.

Examiner Note: The Alternate Path portion of this JPM begins below with the failure of 1/1-8808D, ACCUM 4 INJ VLV to close.

Perform Step: 5 Close all accumulator injection valves.

26.d Standard: OBTAINED keys and PLACED the selected accumulator lockout switches in ON and the associated accumulator valve Handswitch to CLOSE:

69/1-8808A, POWER- ON (CRITICAL) 1/1-8808A, ACCUM 1 INJ VLV - CLOSE (CRITICAL) 69/1-8808B, POWER- ON (CRITICAL) 1/1-8808B, ACCUM 2 INJ VLV (CRITICAL) 69/1-8808C, POWER- ON (CRITICAL) 1/1-8808C, ACCUM 3 INJ VLV (CRITICAL) 69/1-8808D, POWER- ON (NOT-CRITICAL) 1/1-8808D, ACCUM 4 INJ VLV - Accumulator 4 Accumulator Injection Valve NOT CLOSED. (NOT-CRITICAL)

Comment: SAT UNSAT Perform Step: 6 Vent any unisolated accumulator:

RNO step 26.d.1) 1) Close SI/PORV ACCUM N2 ISOL VLV. 1/1-8880.

Standard: Determined 1-04 Accumulator is NOT isolated. PLACED SI/PORV ACCUM N2 ISOL VLV. 1/1-8880, in CLOSE. (CB04)

Comment: SAT UNSAT Perform Step: 7 Open the unisolated accumulator(s) nitrogen vent valve.

RNO step 26.d.2) 2) 1/1-8875D, ACCUM 4 N2 SPLY/VENT VLV Standard: PLACED 1/1-8875D, ACCUM 4 N2 SPLY/VENT VLV, in OPEN. (CB04)

Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2015 JPM S-3

Appendix C JPM STEPS Form ES-C-1 Examiner Note: 1-HC-943 is required to open sufficiently so that Accumulator 4 pressure lowers. This does not require fully opening, rather opening enough to lower pressure will satisfy the standard.

Perform Step: 8 3) Open ACCUM 14 VENT CTRL 1-HC-943 RNO step 26.d.3)

Standard: At CB-04, ADJUSTS Control Knob for ACCUM 14 VENT CTRL 1-HC-943 CLOCKWISE until valve position indicates >0% and Accumulator 4 Pressure begins to lower.

Examiner Note: Terminate the JPM once SI Accumulator 1-04 indicated pressure begins to lower.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2015 JPM S-3

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A LOCA has occurred.

The reactor has been tripped and safety injection initiated.

Appropriate actions of EOP-0.0A, Reactor Trip or Safety Injection and EOP-1.0A, Loss of Reactor or Secondary Coolant have been completed.

Actions of EOS-1.2A, Post LOCA Cooldown and Depressurization, have been completed through step 25.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

Continue actions of EOS-1.2A, Post LOCA Cooldown and Depressurization.

Start at EOS-1.2A, step 26.

Page 7 of 7 CPNPP NRC 2015 JPM S-3

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-4 Task # RO1335 K/A # 005.A4.01 3.6 / 3.4 SF-4P

Title:

Swap RHR Trains Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 is in MODE 5.

Train A RHR is in service.

Train B RHR has been filled, vented, and properly aligned per the appropriate portion of section 5.12 of SOP-102A.

Flushing of Train B is NOT required.

The RCS is NOT in reduced inventory.

The RCS is NOT in solid plant operations.

Initiating Cue: The Unit Supervisor directs you to swap RHR trains to place Train B in service and secure Train A RHR pump in accordance with SOP-102A, Section 5.6, Alternating RHR Trains in MODE 5, 6, or Defueled.

Task Standard: Swapped RHR trains to place Train B in service and secured Train A, utilizing SOP-102A, Section 5.6,.

Required Materials: SOP-102A, Section 5.6, Rev. 19 PCN 7 Validation Time: 20 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP SIMULATOR OPERATOR:

LOAD IC35 OR INITIALIZE to a MODE 5 IC with RHR Train A in service.

Ensure the following:

RCS temperature is < 200°F.

Ensure the RCS Inventory / RHR screen selected on Plant Computer screens.

Ensure RCS not at reduced inventory or solid.

Enter the following remote functions and associated keys to ensure the RHR to CVCS valves can be operated from Keys 1 and 2.

IRF RHR01 f:0 k:2 IRF RHR02 f:100 k:1 Place the following Danger tags:

1/1-8702A, RHRP 1 HL RECIRC ISOL VLV 1/1-8701B, RHRP 2 HL RECIRC ISOL VLV Place GEM cover on 1/1-APRH1.

EXAMINER:

PROVIDE the examinee with a copy of SOP-102A, Section 5.6, Alternating RHR Trains in MODE 5, 6, or Defueled Page 2 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-102A, Section 5.6.

This section describes steps to alternate the in service RHR trains.

Perform Step: 1 VERIFY the following:

5.6 A Section 5.3, RHR Initial Startup Preparation for Shutdown Cooling Mode has been performed for the selected RHR train.

-OR-Selected RHR train has been filled AND vented per the appropriate portion of section 5.12.

Standard: DETERMINED that Train B RHR has been filled and vented from Initial Conditions.

Comment: SAT UNSAT Perform Step: 2 Verify the following:

5.6 A RCS temperature < 200°F.

Selected RHR Train pressure is approximately the same as RCS pressure.

Flushing of the on-coming RHR Train is NOT desired. (IF flushing is desired, THEN GO to section 5.4. SEE Caution above).

Standard: DETERMINED the following:

RCS temperature is < 200°F.

Train B RHR pressure is approximately the same as RCS pressure.

Flushing of Train B RHR is NOT desired (from Initial Conditions).

Comment: SAT UNSAT Page 3 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 EXAMINER NOTE: Examinee may choose to throttle less than 2500 gpm. If so, then, the Examinee should ensure RHR HX CCW return temperature has remained less than or equal to 165 °F.

Perform Step: 3 ENSURE CCW flow established to the RHR heat exchanger on the oncoming 5.6 B. 1) train by performing the following:

1) THROTTLE OPEN the CCW return valve:

1-HS-4572, RHR HX 1 CCW RET VLV 1-HS-4573, RHR HX 2 CCW RET VLV Standard: THROTTLED OPEN 1-HS-4573, RHR HX 2 CCW RET VLV.

Comment: SAT UNSAT Perform Step: 4 ENSURE the selected RHRP SEAL CLR CCW RET FLO LO alarm is clear:

5.6 B. 2) 1-ALB-3B, 3.7, RHRP1 SEAL CLR CCW RET FLO LO 1-ALB-3B, 4.7, RHRP2 SEAL CLR CCW RET FLO LO Standard: DETERMINED 1-ALB-3B, 4.7, RHRP2 SEAL CLR CCW RET FLO LO alarm is clear.

Comment: SAT UNSAT Perform Step: 5 ENSURE proper valve alignment AND VENT the RHR pump by performing the 5.6 C 1) following:

Standard: SELECTED 1/1-APRH2, RHRP2 in PULL OUT.

Comment: SAT UNSAT Page 4 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 6 ENSURE the following valves are CLOSED for the oncoming train:

5.6 C 2) TRAIN B 1/1-8811B, CNTMT SMP TO RHRP 2 SUCT ISOL VLV 1/1-8804B, RHRP 2 TO SIP SUCT VLV 1/1-8716B, RHRP 2 XTIE VLV 1/1-8840, RHR TO HL 2 & 3 INJ ISOL VLV 1/1-8812B, RWST TO RHRP 2 SUCT VLV Standard: ENSURED the following valves are CLOSED for Train B:

1/1-8811B, CNTMT SMP TO RHRP 2 SUCT ISOL VLV 1/1-8804B, RHRP 2 TO SIP SUCT VLV 1/1-8716B, RHRP 2 XTIE VLV 1/1-8840, RHR TO HL 2 & 3 INJ ISOL VLV 1/1-8812B, RWST TO RHRP 2 SUCT VLV Comment: SAT UNSAT Perform Step: 7 ENSURE that the hot leg recirculation isolation valves for the oncoming train 5.6 C. 3) are OPEN:

TRAIN B 1/1-8701B, RHRP 2 HL RECIRC ISOL VLV 1/1-8702B, RHRP 2 HL RECIRC ISOL VLV Standard: DETERMINED hot leg recirculation isolation valves for TRAIN B OPEN:

1/1-8701B, RHRP 2 HL RECIRC ISOL VLV - Open danger tagged OFF.

1/1-8702B, RHRP 2 HL RECIRC ISOL VLV - OPEN power ON.

Comment: SAT UNSAT Page 5 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 Examiner Note: This step requires Independent Verification for closure of 1RH-0022.

Since it is a local action, examinee should not ask for IV.

Perform Step: 8 VENT the selected RHR pump cooler AND VERIFY oil level by performing the 5.6 C. 4) following:

a. OPEN the selected RHRP seal cooler vent valve for a minimum of 60 seconds to ensure all air is expelled:

1RH-0022, RHR PMP 1-02 SEAL CLR VNT VLV

b. CLOSE the selected RHRP seal cooler vent valve:

1RH-0022, RHR PMP 1-02 SEAL CLR VNT VLV

c. VERIFY oil level for the motor bearings is at the proper level on the sight glass. (REFER to Attachment 4, RHR Pump Motor Oil Level Indication)

Standard: DISPATCHED an NEO to perform Steps 5.6 C.4) a, b, and c.

Examiner Cue: The NEO reports RHR Pump 1-02 seal cooler has been vented and motor oil levels are acceptable.

Comment: SAT UNSAT Examiner Note: The valve below is normally open in all modes of plant operation except for ECCS Hot Leg Injection Mode.

Perform Step: 9 IF selected valve is NOT OPEN with its breaker deenergized per IPO-010A, 5.6 C.5) THEN OPEN the cold leg injection valve for the oncoming train:

1/1-8809AB, RHR TO CL 1 & 2 INJ ISOL VLV 1/1-8809B, RHR TO CL 3 & 4 INJ ISOL VLV Standard: DETERMINED step is N/A, OR may verify the following valve is OPEN:

1/1-8809B, RHR TO CL 3 & 4 INJ ISOL VLV Comment: SAT UNSAT Page 6 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 10 ENSURE the selected train heat exchanger flow control valve is CLOSED:

5.6 C.6) 1-HC-606, RHR HX 1 FLO CTRL 1-HC-607, RHR HX 2 FLO CTRL Standard: ENSURED 1-HC-607, RHR HX 2 FLO CTRL controller set to 0% (CLOSE).

Comment: SAT UNSAT Perform Step: 11 ENSURE the selected train heat exchanger bypass flow control valve is 5.6 C.7) CLOSED:

1-FK-618, RHR HX 1 BYP FLO CTRL 1-FK-619, RHR HX 2 BYP FLO CTRL Standard: ENSURED the following on 1-FK-619, RHR HX 2 BYP FLO CTRL:

Amber MAN light ON.

Output indicating 0%.

Comment: SAT UNSAT Perform Step: 12 IF the RCS level is less than 56 inches above the core plate (8278), THEN 5.6 D ENSURE IPO-010A Attachment 12 has been performed on the oncoming train.

Standard: DETERMINED step is not applicable from Initial Conditions.

Comment: SAT UNSAT Perform Step: 13 IF the RCS is water solid, THEN PLACE 1-PK-131, LTDN HX OUT PRESS 5.6 E CTRL in MANUAL, AND CONTROL RCS pressure manually to maintain stable pressure while continuing with this procedure.

Standard: DETERMINED step is not applicable from Initial Conditions.

Comment: SAT UNSAT Page 7 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 14 START the oncoming RHR pump.

5.6 F 1/1-APRH1, RHRP 1 1/1-APRH2, RHRP 2 Standard: PERFORMED the following:

PLACED 1/1-APRH2, RHRP 2 to START (critical).

OBSERVED red PUMP light LIT, green PUMP light DARK (NOT critical).

OBSERVED RHRP 2 MOT CURRENT indication rising and then stabilizing. (NOT critical).

Comment: SAT UNSAT Perform Step: 15 VERIFY that the selected train miniflow OPENS.

5.6 G 1/1-FCV-610, RHRP 1 MINIFLO VLV 1/1-FCV-611, RHRP 2 MINIFLO VLV Standard: PERFORMED the following:

VERIFIED 1/1-FCV-611, RHRP 2 MINIFLO VLV green light DARK, red light LIT.

Comment: SAT UNSAT Perform Step: 16 Slowly (over a period of 5 - 10 min) ESTABLISH flow from the oncoming train 5.6 H while CLOSING the off-going train flow control valves as necessary to maintain desired temperature:

Train B Oncoming OPEN 1-FK-619, RHR HX 2 BYP FLO CTRL OR 1-HC-607, RHR HX 2 FLO CTRL OR both as desired while CLOSING the following:

1-HC-606, RHR HX 1 FLO CTRL AND 1-FK-618, RHR HX 1 BYP FLO CTRL Standard: ESTABLISHED flow from the Train B RHR pump through the RHR heat exchanger AND STOPPED flow through Train A RHR heat exchanger.

Comment: SAT UNSAT Page 8 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 17 ESTABLISH the desired flow rate, as indicated on the associate flow 5.6 I instruments.

1-FI-619, RHR TO CL 3 & 4 INJ FLO Standard: ESTABLISHED flow rate as indicated on 1-FI-619, RHR TO CL 3 & 4 INJ FLO such that flow is not less than 500 gpm and that RCS temperature is maintained at < 200°F.

Comment: SAT UNSAT EXAMINER NOTE: Examinee may choose to maintain the bypass flow controller in manual.

Perform Step: 18 IF desired, THEN PLACE the selected train controller in AUTO.

5.6 J 1-FK-619, RHR HX 2 BYP FLO CTRL Standard: PERFORMED the following:

DEPRESSED AUTO pushbutton on 1-FK-619.

OBSERVED amber MAN light DARK, white AUTO light LIT.

OBSERVED 1-FI-619, RHR TO CL 3 & 4 INJ FLO trending to approximately 3950 gpm.

Comment: SAT UNSAT Perform Step: 19 IF letdown flow to the CVCS is established, THEN PERFORM the following:

5.6 K 1) ENSURE 1-PK-131, LTDN HX OUT PRESS CTRL is in Manual AND ADJUST as necessary to maintain stable letdown flow rate while performing the following steps:

Standard: ENSURED 1-PK-131, LTDN HX OUT PRESS CTRL in Manual.

Comment: SAT UNSAT Perform Step: 20 OPEN the RHR to CVCS letdown isolation valve for the oncoming train:

5.6 K 2) 1RH-8734B-RO, RHR HX 1-02 TO CVCS LTDN ISOL VLV RMT OPER Standard: DISPATCHED an NEO to OPEN 1RH-8734B-RO, RHR HX 1-02 TO CVCS LTDN ISOL VLV RMT OPER.

Simulator Operator: When called as NEO, use Remote Function RHR02 to OPEN 1RH-8734B-RO. Report back to Control Room that 1RH-8734B-RO is OPEN when completed. (Key 1)

Comment: SAT UNSAT Page 9 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 21 CLOSE the RHR to CVCS letdown isolation valve for the off-going train:

5.6 K 3) 1RH-8734A-RO, RHR HX 1-01 TO CVCS LTDN ISOL VLV RMT OPER Standard: DISPATCHED an NEO to CLOSE 1RH-8734A-RO, RHR HX 1-01 TO CVCS LTDN ISOL VLV RMT OPER.

Booth Operator: When called as NEO, use Remote Function RHR01 to CLOSE 1RH-8734A-RO. Report back to Control Room that 1RH-8734A-RO is CLOSED when completed. (Key 2)

Comment: SAT UNSAT Perform Step: 22 OPERATE charging pumps AND charging flow as required for RCS level 5.6 K 4) control per SOP-103A.

Standard: MAINTAINED RCS level control by controlling charging flow.

Comment: SAT UNSAT Perform Step: 23 VERIFY on-coming RHR Train is in service maintaining RCS temperature 5.6 L < 200°F.

Standard: VERIFIED RHR Train B in service and RCS temperature < 200°F.

Comment: SAT UNSAT Page 10 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 24 ENSURE off-going RHR Train heat exchanger outlet valve AND RHR heat 5.6.3 M exchanger bypass valve are CLOSED:

RHRP 1-01 1-HC-606, RHR HX 1 FLO CTRL 1-FK-618, RHR HX 1 BYP FLO CTRL Standard: PERFORMED the following:

OBSERVED 1-HC-606, RHR HX 1 FLO CTRL indicates 0% on scale (CLOSE).

OBSERVED 1-FK-618, RHR HX 1 BYP FLO CTRL amber Manual light LIT, white AUTO light DARK, and output scale indicating 0%.

Comment: SAT UNSAT Examiner Note: IPO-010A is for Reduced Inventory Operations. Applicant will determine that this step does apply.

Perform Step: 25 IF the cold leg injection valves are NOT THROTTLED OPEN per IPO-010A, 5.6 N 1) THEN PERFORM the following:

1) CLOSE the cold leg injection valve for the train being shut down:

1/1-8809A, RHR TO CL 1 & 2 INJ ISOL VLV Standard: PERFORMED the following:

ENSURE key INSERTED in 69/1-8809A POWER, and turn to ON (critical).

OPERATE 1/1-8809A to CLOSE position (critical).

OBSERVE 1/1-8809A green CLOSE light LIT, red OPEN light DARK (NOT critical).

Comment: SAT UNSAT Perform Step: 26 VERIFY that the miniflow valve for the selected RHR pump OPENS:

5.6 N 2) 1/1-FCV-610, RHRP 1 MINIFLOW VLV Standard: OBSERVED 1/1-fcv-610, RHRP 1 MINIFLOW VLV green light DARK, red light LIT.

Comment: SAT UNSAT Page 11 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 27 STOP the selected RHR pump:

5.6 O 1/1-APRH1, RHRP 1 Standard: PERFORMED the following:

PLACED 1/1-APRH1, RHRP 1 to STOP (critical).

OBSERVED green PUMP light LIT, red PUMP light DARK (NOT critical).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 12 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 1 is in MODE 5.

Train A RHR is in service.

Train B RHR has been filled, vented, and properly aligned per the appropriate portion of section 5.12 of SOP-102A.

Flushing of Train B is NOT required.

The RCS is NOT in reduced inventory.

The RCS is NOT in solid plant operations.

INITIATING CUE: The Unit Supervisor directs you to swap RHR trains to place Train B in service and secure Train A RHR pump in accordance with SOP-102A, Section 5.6, Alternating RHR Trains in MODE 5, 6, or Defueled.

Page 13 of 13 CPNPP NRC 2015 JPM S-4

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-5 Task # RO3149 K/A # 045.A4.02 2.7 / 2.6 SF-4S

Title:

Roll the Main Turbine to 1800 RPM Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

The Unit is in MODE 1.

IPO-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator is in progress, and has been completed up to and including Step 5.1.17 C.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

Continue IPO-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator, beginning at Step 5.1.18 and to the completion of Step 5.1.21.

The Overspeed Trip test is NOT required.

Task Standard: Utilizing IPO-003A, the examinee rolled the Main Turbine to 1800 RPM, with auxiliary oil pumps placed in auto.

Required Materials: IPO-003A, Power Operations, Rev. 29 PCN 2 Validation Time: 30 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP SIMULATOR OPERATOR:

INITIALIZE to IC- 39 OR INITIALIZE to IC-17.

Perform Step 5.1.17 of IPO-003A.

Set Remote function MSR04 to CLOSED.

THEN Ensure TG Control screen is up on the left OT.

FREEZE the simulator.

WHEN examinee is ready, THEN place the simulator in RUN.

EXAMINER:

PROVIDE the examinee with a copy of:

IPO-003A, Power Operations, with Steps 5.1.1 through and including Step 5.1.17 appropriately marked/initialed as completed.

Page 2 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from IPO-003A, Section 5.1.

Perform Step: 1 CLOSE 1-HS-2417, HP CTRL VLV 1.4 BEF SEAT DRN VLV (1-CB-10).

5.1.18.A Standard: PLACED 1-HS-2417, HP CTRL VLV 1.4 BEF SEAT DRN VLV in CLOSE.

Comment: SAT UNSAT Perform Step: 2 EHC Detail Display 5.1.18.B VERIFY HP and LP Control Valves are CLOSED (0%)

HP CV 1 CV 2 CV 3 CV 4 LP1 CV 1 CV 2 LP2 CV 1 CV 2 Standard: On EHC Detail Display OBSERVED the following indications:

HP CV 1 - 0% (CLOSED)

CV 2 - 0% (CLOSED)

CV 3 - 0% (CLOSED)

CV 4 - 0% (CLOSED)

LP1 CV 1 - 0% (CLOSED)

CV 2 - 0% (CLOSED)

LP2 CV 1 - 0% (CLOSED)

CV 2 - 0% (CLOSED)

Comment: SAT UNSAT Page 3 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 3 On the "TG Control" Display in the "Start-Up" Section, turn on the "Open Stop 5.1.18.C Valves" Subloop Controller.

Standard: PERFORMED the following:

On "TG Control" Display 1ZA60H101, PLACED "Open Stop Valves" Subloop Controller in the ON condition. (critical).

OBSERVED "Open Stop Valves" status light change from green to red.

(NOT critical).

Comment: SAT UNSAT Perform Step: 4 On the TG Overview Display, verify HP and LP Stop Valves are OPEN:

5.1.18.D LPT 1 LP STOP VLV 1 LPT 2 LP STOP VLV 1 LPT 1 LP STOP VLV 2 LPT 2 LP STOP VLV 2 HPT STOP VLV 1 (SV1)

HPT STOP VLV 3 (SV3)

HPT STOP VLV 2 (SV2)

HPT STOP VLV 4 (SV4)

Standard: On TG Overview Display OBSERVED the following indications:

LPT 1 LP STOP VLV 1 - OPEN LPT 2 LP STOP VLV 1 - OPEN LPT 1 LP STOP VLV 2 - OPEN LPT 2 LP STOP VLV 2 - OPEN HPT STOP VLV 1 (SV1) - OPEN HPT STOP VLV 3 (SV3) - OPEN HPT STOP VLV 2 (SV2) - OPEN HPT STOP VLV 4 (SV4) - OPEN Comment: SAT UNSAT Perform Step: 5 OPEN 1-HS-2417, HP CTRL VLV 1.4 BEF SEAT DRN VLV (1-CB-10) 5.1.18.E Standard: PLACED 1-HS-2417, HP CTRL VLV 1.4 BEF SEAT DRN VLV in OPEN.

Comment: SAT UNSAT Page 4 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 6 IF temperature difference between MSR 1A (MSRL) and 1B (MSRR) 5.1.19.A tubesheets is >25°F, THEN perform the following:

Standard: DETERMINED step is N/A.

Comment: SAT UNSAT Perform Step: 7 Maintain Reactor power at approximately 6% - 8% and Tavg approximately 5.1.19.B 557°F, while rolling the Main Turbine to 1800 rpm.

Standard: Maintained Reactor power at approximately 6% - 8% and Tavg approximately 557°F during Main Turbine roll up to 1800 rpm.

Examiner Cue: Another operator will maintain reactor power.

Comment: SAT UNSAT Perform Step: 8 Dispatch a Plant Equipment Operator to locally inspect the Main Turbine 5.1.19.C during roll up for any unusual noises, rubbing, etc.

Standard: DISPATCHED a Plant Equipment Operator to monitor Main Turbine roll up.

Examiner Cue: A Nuclear Equipment Operator (NEO) is standing by at the Main Turbine to monitor for unusual noises, rubbing, etc.

Comment: SAT UNSAT Perform Step: 9 On the "TG Control" Display in the "Speed Control" Section, roll the Main 5.1.19.D Turbine to approximately 500 RPM by raising the "Speed Target" Controller to 500 RPM.

Standard: SET "Speed Target" Controller to 500 RPM.

Comment: SAT UNSAT Page 5 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 10 On the "Lube Oil" Display, verify "Turning Gear Valve #1" closes at a Main 5.1.19.E Turbine speed of approximately 260 RPM.

Standard: ACCESSED "TG Lube Oil" display and OBSERVED "Valve #1 1-HV-6554A" display indicating green and 0%.

Comment: SAT UNSAT Perform Step: 11 Verify no unexpected or sudden increase is indicated:

5.1.19.F Turbine Display or Turbine Vibration Display Generator Display or Generator Vibration Display Alarm Summary Display (Asd)

Standard: VERIFIED no unexpected or sudden increase indicated on Turbine Display or Turbine Vibration Display Generator Display or Generator Vibration Display Alarm Summary Display (Asd)

Comment: SAT UNSAT Page 6 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 12 On the "TSE Margin" Display, IF the Simulated Shaft Temperature is less than 5.1.19.G 120°F, THEN wait at least 20 minutes before increasing speed to 1800 rpm.

Standard: WAITED at least 20 minutes before increasing speed to 1800 rpm.

Examiner Cue: 20 minutes have passed.

Comment: SAT UNSAT Page 7 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 13 Determine the upper TSE margin temperature limitations by monitoring the 5.1.19.H 1st bullet "TSE Margin" Display:

IF the Admission Upper Margin is increasing or stable, THEN proceed to Next Step.

Standard: OBSERVED "TSE Margin" Display (1ZA60H213) and DETERMINED Admission Upper Margin is increasing or stable on "TSE Margin" Display" AND PROCEEDED to the next step.

Comment: SAT UNSAT Perform Step: 14 IF an Overspeed Trip test is required (Prerequisite 2.20), THEN perform the 5.1.20 test per Attachment 4.

Standard: DETERMINED that Overspeed Trip test is not required, per Initiating Cue instructions.

Comment: SAT UNSAT Perform Step: 15 Perform the following steps to increase Main Turbine speed to 1800 RPM:

5.1.21.A Verify no abnormal indications on the following Displays:

Turbine Display Generator Display Standard: VERIFIED no abnormal indications on:

Turbine Display Generator Display Comment: SAT UNSAT Page 8 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 16 Verify upper TSE Margin is above 60°F and Upper Admission Bar is green on 5.1.21.B the "TSE Margin" Display.

Standard: DETERMINED upper TSE Margin is above 60°F and Upper Admission Bar is green on the "TSE Margin" Display.

Comment: SAT UNSAT Perform Step: 17 In the "Speed Control" Section, roll the Main Turbine to 1800 RPM by raising 5.1.21.C the "Speed Target" Controller to 1800 RPM.

Standard: RAISED "Speed Target" Controller to 1800 RPM.

Comment: SAT UNSAT Perform Step: 18 Verify Lube Oil Temperature is maintained at approximately 113°F as indicated 5.1.21.D on the TURB BRG TEMP RCDR 1 recorder (1-SB10T010.G01 recorder point 12 on 1-CB-10) while Main Turbine speed is increased.

Standard: VERIFIED Lube Oil Temperature maintained at approximately 113°F while Main Turbine speed is increased.

Comment: SAT UNSAT Perform Step: 19 Perform the following:

5.1.21.E 1st bullet Verify 1-HS-6579, TURB SHAFT LIFT OIL PMP automatically stops at a Main Turbine speed of approximately 540 RPM.

Standard: When Main Turbine speed reached approximately 540 RPM, then OBSERVED green light LIT and red light DARK for 1-HS-6579, TURB SHAFT LIFT OIL PMP on 1-CB-10.

Comment: SAT UNSAT Page 9 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 20 Perform the following:

5.1.21.E 2nd bullet Place 1-HS-6579 in AUTO AFTER STOP Standard: PLACED 1-HS-6579 in AUTO AFTER STOP.

Comment: SAT UNSAT Perform Step: 21 WHEN turbine speed is approximately 1400 rpm, THEN ensure the EXCITER 5.1.21.F AIR DRIER and EXCITER HEATER in OFF at the Unit 1 GENERATOR AUXILIARIES CABINET JC91 (TB 778, U1 GAC).

Standard: DISPATCHED a Nuclear Equipment Operator to ensure EXCITER AIR DRIER and EXCITER HEATER in OFF for Unit 1.

Examiner Cue: An NEO was dispatched to the Unit 1 GENERATOR AUXILIARIES CABINET and reported that the EXCITER AIR DRIER and EXCITER HEATER are in OFF.

Comment: SAT UNSAT Perform Step: 22 Verify 1-PI-6558, TURB L/O PMP DISCH PRESS is between 155 and 175 5.1.21.G psig.

Standard: OBSERVED 1-PI-6558 (on 1-CB10-A) and DETERMINED indication was between 155 and 175 psig.

Comment: SAT UNSAT Perform Step: 23 WHEN Main Turbine speed increases above 1765 RPM, THEN stop ALL 5.1.21.H running Auxiliary Oil Pumps and place in AUTO.

Standard: When Main Turbine speed increased above 1765 rpm, ENSURED that the following Auxiliary Oil Pumps are OFF with control switches in AUTO:

1-HS-3287, TURB AUX L\O PMP A 1-HS-3288, TURB AUX L\O PMP B 1-HS-3292, TURB DC EMER L\O PMP Comment: SAT UNSAT Page 10 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 24 Verify no unexpected or sudden increase in vibration is indicated:

5.1.21.I Turbine Display or Turbine Vibration Display Generator Display or Generator Vibration Display Alarm Summary Display (Asd)

Standard: DETERMINED no unexpected or sudden increase in vibration indicated on:

Turbine Display or Turbine Vibration Display Generator Display or Generator Vibration Display Alarm Summary Display (Asd)

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 11 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

The Unit is in MODE 1.

IP-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator is in progress, and has been completed up to and including Step 5.1.17C.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

Continue IPO-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator, beginning at Step 5.1.18 and to the completion of Step 5.1.21.

The Overspeed Trip test is NOT required.

Page 12 of 12 CPNPP NRC 2015 JPM S-5

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-6 Task # RO2101 K/A # 022.A4.01 3.6 / 3.6 SF-5

Title:

Alternate Containment Recirculation Units (CACRS)

Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: X Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 is at 100% power.

A Containment Vent is in progress per SOP-801A, Containment Ventilation System, Section 5.6.5, Containment Pressure Relief System Operation.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

Alternate Containment Recirculation Units in accordance with SOP-801A, Containment Ventilation System, Section 5.1.3, by starting CACRS #1, and stopping CACRS #3.

The Containment Vent is to remain in progress during the swap.

Task Standard: Utilizing SOP-801A:

STARTED CACRS #1.

STOPPED CACRS #3.

When radiation alarm (Alert) comes in for Containment Air, manually SECURED Containment Vent.

Required Materials: SOP-801A, .Containment Ventilation System, Rev. 14 PCN 1 Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 CPNPP NRC 2015 JPM S-6

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP SIMULATOR OPERATOR:

LOAD IC37 OR INITIALIZE to a 100% power IC:

ENSURE CACR #1 is OFF, and CACR #3 is RUNNING.

Enter the following conditional command:

{DICHHS5413A.Value=1} IMF RM197 f:2E-5 Raise Containment pressure to approximately 1.2 psig as follows:

Set the following remote functions as indicated:

CHR12A - ON CHR12 - 1.2 When Containment pressure indicates 1.2 psig, then set CHR12A to OFF.

ENSURE the CONTAINMENT VENT IN PROGRESS job aid is on CB03 EXAMINER:

PROVIDE the examinee with a copy of:

SOP-801A, Containment Ventilation System, including markup of in-progress Section 5.6.6 with Steps A through E checked off as completed. There will be a CIRCLE around the box and the letter F next to Step F to indicate the procedure step is in progress.

Page 2 of 7 CPNPP NRC 2015 JPM S-6

Appendix C JPM CUE SHEET Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-801A, Section 5.1.3.

5.1.3 This section describes the steps to alternate running Containment Air Cooling AND recirculation units.

Perform Step: 1 VERIFY the Hydrogen Purge Supply AND Exhaust System is NOT in 5.1.3 A service.

Standard: VERIFIED Hydrogen Purge Supply and Exhaust not in service.

Comment: SAT UNSAT Perform Step: 2 IF a Containment Purge OR Vent is in progress, THEN PERFORM on of 5.1.3 B the following:

Standard: DETERMINED that Step 5.1.3 B. Second bullet is the only applicable step:

CLOSELY MONITOR the Containment Air Gaseous (1-RE-5503) AND Particulate Monitors (1-RE-5502) to verify they remain below their Alert Alarm Limit. IF radiation levels on one of these monitors increases to the Alert Alarm Limit, THEN Step 5.1.3H will direct the response. This step is applicable.

Comment: SAT UNSAT Page 3 of 7 CPNPP NRC 2015 JPM S-6

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 3 START the desired cooling unit(s) AND VERIFY the associated 5.1.3 C discharge damper opens.

1-HS-5405A, CNTMT FN CLR FN 1 (1-HV-5405D)

Standard: PERFORMED the following:

PLACED 1-HS-5405A, CNTMT FN CLR FN 1 (1-HV-5405D) to START (critical).

OBSERVED DMPR green CLOSE light DARK, red OPEN light LIT (NOT critical).

OBSERVED FAN green OFF light DARK, red ON light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 4 VERIFY the chill water return valve(s) from the selected cooling unit(s) 5.1.3 D automatically opens as indicated by the position lights on the valve handswitch located on CV-01.

1-HS-6074, CNTMT FN CLR 1 CH WTR RET VLV Standard: OBSERVED 1-HS-6074 green CLOSE light DARK, red OPEN light LIT.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2015 JPM S-6

Appendix C JPM CUE SHEET Form ES-C-1 Examiner Note: When applicant places 1-HS-5413A to STOP, the Alternate Path of this JPM begins. An Alert alarm (Yellow on PC-11) will initiate for 1-RE-5503 CAG-197, Containment Air Gaseous.

Perform Step: 5 SHUTDOWN the desire cooling unit(s) by performing the following 5.1.3 E 1) steps:

1) STOP the cooling unit(s) to be shutdown AND VERIFY the associated discharge damper(s) closes.

1-HS-5413A, CNTMT FN CLR FN 3 (1-HV-5413D)

Standard: PERFORMED the following:

PLACED 1-HS-5413A, CNTMT FN CLR FN 3 (1-HV-5413D) to STOP (critical).

OBSERVED DMPR red OPEN light DARK, green CLOSED light LIT (NOT critical).

OBSERVED FAN red ON light OFF, green OFF light LIT (NOT critical).

Comment: SAT UNSAT Examiner Note: Steps 5.1.3.E 2) through 5.1.3.G are omitted as the applicant will respond to the Rad alarm.

Examiner Note: The following steps are the Alternate Path for this JPM.

Examiner Note: The following steps are from SOP-801A, Section 5.6.5 Perform Step: 6 CLOSE 1-HS-5548, CNTMT PRESS RLF ISOL VLV.

5.6.5 G Standard: PERFORMED the following:

PLACED 1-HS-5548, CNTMT PRESS RLF ISOL VLV to CLOSE (critical).

OBSERVED 1-HS-5548 red OPEN light DARK, green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2015 JPM S-6

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 7 CLOSE 1-HS-5549, CNTMT PRESS RLF ISOL VLV.

5.6.5 H Standard: PERFORMED the following:

PLACED 1-HS-5549, CNTMT PRESS RLF ISOL VLV to CLOSE (critical).

OBSERVED 1-HS-5549 red OPEN light DARK, green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 8 CLOSE 1-HS-5574, AIR PRG EXH DMPR OR, IF this section was 5.6.5 I performed in preparation for purging the containment, THEN N/A this step.

Standard: PERFORMED the following:

PLACED 1-HS-5574, AIR PRG EXH DMPR to CLOSE (critical).

OBSERVED 1-HS-5574 red OPEN light DARK, green CLOSE light LIT (NOT critical).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2015 JPM S-6

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Unit 1 is at 100% power.

A Containment Vent is in progress per SOP-801A, Containment Ventilation System, Section 5.6.5, Containment Pressure Relief System Operation.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

Alternate Containment Recirculation Units in accordance with SOP-801A, Containment Ventilation System, Section 5.1.3, by starting CACRS

1, and stopping CACRS #3.

The Containment Vent is to remain in progress during the swap.

Page 7 of 7 CPNPP NRC 2015 JPM S-6

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-7 Task # RO4302 K/A # 064.A4.06 3.9 / 3.9 SF-6

Title:

Load Diesel Generator Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: X Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

OPT-214A, Diesel Generator Operability Test is in progress.

Diesel Generator 1-01 has been slow started in accordance with OPT-214A, Section 8.1.

All Diesel Generator parameters are normal and steady.

The NEO stationed locally at the Diesel Generator reports no abnormalities in the start or running state of the Diesel Generator.

Initiating Cue: The Unit Supervisor directs you to complete Section 8.1 of OPT-214A for Diesel Generator 1-01, beginning with Step 8.1.Q.

Task Standard: SYNCHRONIZED and LOADED Diesel Generator 1-01 to a minimum of 2.2 MW and then PLACED the Diesel Generator Emergency STOP/START switch in PULLOUT when Station Service Water Pump 1-01 tripped.

Required Materials: OPT-214A, Diesel Generator Operability Test, Rev. 22 PCN 14.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 CPNPP NRC 2015 JPM S-7

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP SIMULATOR OPERATOR:

INITIALIZE to IC-38 ENSURE that NO PCS screens on DAD.

ENSURE synch scope handle is NOT in SS1-EG1.

OR PERFORM the following:

Initialize to IC-18 ENTER the SSW Pump 1-01 Trip malfunction on key 1, IMF SW01A f:1 k:1 Start EDG 1-01 by performing a fast start in accordance with OPT-214A, Section 8.1.A ANR 20 DG-1 TRBL to NORM if required to clear the local EDG trouble alarm.

EXAMINER:

PROVIDE the examinee with copies of the following:

OPT-214A, Diesel Generator Operability Test, including, Attachment 10.7, TS 3.8.1 Administrative Controls and Test Termination Criteria - Section II completed.

OPT-214A-1, Train A Diesel Generator Operability Data Sheet appropriately marked through 8.1.P.

Page 2 of 6 CPNPP NRC 2015 JPM S-7

Appendix C JPM CUE SHEET Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from OPT-214A.

Perform Step: 1 Turn SS-1EG1, BKR 1EG1 SYNCHROSCOPE to ON.

8.1.Q Standard: INSERTED Synchroscope handle in SS-1EG1 AND PLACED in ON.

Comment: SAT UNSAT Perform Step: 2 Using 90-1EG1, DG 1 VOLT CTRL, gradually ADJUST V-IN on the 8.1.R synchroscope 1 to 2 volts higher than V-RUN on the synchroscope.

Standard: COMPARED V-IN to V-RUN and ADJUSTED as deemed necessary.

Comment: SAT UNSAT Perform Step: 3 Using 65-1EG1, DG 1 SPD CTRL, ADJUST speed so the synchroscope is 8.1.S moving 2 to 4 RPM in the fast direction.

Standard: ADJUSTED speed such that the synchroscope is moving 2 to 4 RPM in the fast direction.

Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2015 JPM S-7

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 4 IF the termination criteria of Attachment 10.7,Section II are met while the DG 8.1.T is synchronized with the offsite power source, THEN PERFORM the following:

OPEN CS-1EG1, DG1 BKR 1EG1.

Slowly ADJUST DG voltage to 6900 V (6831 V to 6969 V).

Slowly ADJUST DG frequency to 60.0 (59.7 to 60.3) Hz.

Standard: PLACE KEPT Continuous Action Step.

Comment: SAT UNSAT Perform Step: 5 To synchronize the Diesel Generator to the bus, PERFORM the following:

8.1.U 1) CLOSE CS-1EG1, DG 1 BKR 1EG1 when the synchroscope is slightly before the 12 o'clock position AND moving slowly in the fast direction.

Standard: CLOSED CS-1EG1.

Comment: SAT UNSAT Examiner Note: Ensure the Simulator Operator activates key 1 to insert Station Service Water Pump 1-01 trip once DG 1 load is increased to greater than or equal to 2.2 MW.

Responding to the SSW Pump trip will constitute the Alternate Path of this JPM.

SIMULATOR When directed by the Examiner, activate key 1 (IMF SW01A f:1 k:1)

OPERATOR NOTE:

Perform Step: 6 To synchronize the Diesel Generator to the bus, PERFORM the following:

8.1.U 2) Immediately LOAD the DG to 2.2 - 2.5 MW for stability by moving 65-1EG1, DG 1 SPD CTRL in the RAISE direction.

Standard: RAISED DG load to at least 2.2 MW.

Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2015 JPM S-7

Appendix C JPM CUE SHEET Form ES-C-1 Examiner: Note: The following step represents the Alternate Path of this JPM.

Examiner Note: The following step is an Initial Operator Action from ABN-501, Section 2.3, which is to be performed from memory.

Perform Step 7 Examinee determines Unit 1 Train A Station Service Water Pump has tripped.

Standard: DETERMINED SSW Pump 1-01 has tripped due to 1-ALB-1 Window 1.8 SSWP 1/2 OVERLOAD/TRIP alarm, SSW Flow on Train A is zero.

Perform Step: 8 Place affected train diesel generator handswitch, CS-uDGuE (emergency 2.3.1 stop/start) in PULLOUT.

Comment: SAT UNSAT Standard: PLACED CS-1DG1E handswitch in PULLOUT within 1 minute of Station Service Water Pump 1-01 trip.

Comment: SAT UNSAT Terminating Cue: This JPM is complete.

STOP TIME:

Page 5 of 6 CPNPP NRC 2015 JPM S-7

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

OPT-214A, Diesel Generator Operability Test is in progress.

Diesel Generator 1-01 has been slow started in accordance with OPT-214A, Section 8.1.

All Diesel Generator parameters are normal and steady.

The NEO stationed locally at the Diesel Generator reports no abnormalities in the start or running state of the Diesel Generator.

INITIATING CUE: The Unit Supervisor directs you to complete Section 8.1 of OPT-214A for Diesel Generator 1-01, beginning with Step 8.1.Q.

Page 6 of 6 CPNPP NRC 2015 JPM S-7

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-8 Task # RO3603 K/A # 008.A4.01 3.3 / 3.1 SF-8

Title:

Rotate Component Cooling Water Pumps Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

Actual Performance: X Simulator: X Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 is in MODE 1.

A CCW pump swap is required to support a maintenance activity in Train A CCW Pump Room.

A Nuclear Equipment Operator (NEO) is standing by for pump start.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

START Train B Component Cooling Water (CCW) Pump and STOP Train A CCW Pump per SOP-502A, Component Cooling Water System.

If needed to initiate flow through the Containment Spray or RHR Heat exchangers, do NOT exceed 1500 gpm flow per heat exchanger.

START at Step 5.2.1.1, Starting a Standby CCW Pump During Normal Operation, to place the Train B CCW Pump in service.

CONTINUE with Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation, to secure the Train A CCW Pump.

Task Standard: Utilized SOP-502A, Component Cooling Water System, STARTED Train B CCW Pump and Stopped Train A CCW Pump.

Required Materials: SOP-502A, Component Cooling Water System, Rev. 19 PCN 4.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 9 CPNPP NRC 2015 JPM S-8

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP SIMULATOR OPERATOR:

INITIALIZE to IC-39 (Can also use IC18)

SET UP Plant Computer screen to monitor CCW Pump 1-02 temperatures. GD_CCWP2 EXAMINER:

PROVIDE the examinee with a copy of:

SOP-502A, Component Cooling Water System.

Step 5.2.1.1, Starting a Standby CCW Pump During Normal Operation.

Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation.

Page 2 of 9 CPNPP NRC 2015 JPM S-8

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Ensure the Station Service Water Pump, associated with the CCW Pump to be 5.2.1.1.A started is operating.

SSWP 2 Standard: DETERMINED SSWP 2, Station Service Water Pump is running and OBSERVED red PUMP light LIT.

Comment: SAT UNSAT Perform Step: 2 Ensure the oil level in the bearing housings are normal.

5.2.1.1.B CCWP 2 Standard: DISPATCHED NEO to verify oil levels for CCWP 2.

Examiner Cue: The NEO reports that bearing housing oil levels are normal.

Comment: SAT UNSAT Page 3 of 9 CPNPP NRC 2015 JPM S-8

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Examinee may establish flow through either Train A or Train B heat exchangers at this time. Critical action is to establish sufficient flow to lower CCW Pump discharge pressure during two pump operation.

Perform Step: 3 IF CCW heat load is low, THEN additional CCW flow should be established 5.2.1.1.C through the CS HX or RHR HX prior to starting the second pump.

TRAIN A 1-HS-4574, CS HX 1 CCW RET VLV 1-HS-4572, RHR HX 1 CCW RET VLV TRAIN B 1-HS-4575, CS HX 2 CCW RET VLV 1-HS-4573, RHR HX 2 CCW RET VLV Standard: PERFORMED the following:

PLACED 1-HS-4574, CS HX 1 CCW RET VLV in OPEN (critical).

OBSERVED red OPEN light LIT (NOT critical).

and/or PLACED 1-HS-4572, RHR HX 1 CCW RET VLV in OPEN (critical).

OBSERVED red OPEN light LIT (NOT critical).

and/or PLACED 1-HS-4575, CS HX 2 CCW RET VLV in OPEN (critical).

OBSERVED red OPEN light LIT (NOT critical).

and/or PLACED 1-HS-4573, RHR HX 2 CCW RET VLV in OPEN (critical).

OBSERVED red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Page 4 of 9 CPNPP NRC 2015 JPM S-8

Appendix C JPM STEPS Form ES-C-1 Perform Step:4 Start the idle CCW Pump.

5.2.1.1.D 1-HS-4519A, CCWP 2 Standard: PERFORMED the following:

PLACED 1-HS-4519A, CCWP 2 to START (critical).

OBSERVED red FAN and PUMP lights LIT (NOT critical).

OBSERVED 1-PI-4521, CCWP2 DISCH PRESS rising (NOT critical).

OBSERVE 1-FI-4537A, CCW HX 2 OUT FLO rising (NOT critical).

Comment: SAT UNSAT Page 5 of 9 CPNPP NRC 2015 JPM S-8

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Examinee may establish flow through either Train A or Train B heat exchangers at this time. Expected action is to momentarily establish flow through all four heat exchangers during the transfer. Flow may have previously been established through any/all of these heat exchangers.

Examinee could bring in 1-ALB-3B, Window 3.11, ANY RCP THBR CLR CCW RET FLO LO while adjusting flows, starting the second pump and completing the SOP steps will clear the alarm.

If this alarm annunciates, then cue the examinee to continue with the task.

Perform Step: 5 IF the CCW PUMPS are being alternated for their bi-weekly rotation per OWI-5.2.1.1.E 409 EQUIPMENT ROTATION PROGRAM, THEN momentarily initiate flow through each RHR and CS heat exchanger while BOTH pumps are in service.

TRAIN A 1-HS-4574, CS HX 1 CCW RET VLV 1-HS-4572, RHR HX 1 CCW RET VLV TRAIN B 1-HS-4575, CS HX 2 CCW RET VLV 1-HS-4573, RHR HX 2 CCW RET VLV Standard: DETERMINED step is N/A per Initial Conditions.

Comment: SAT UNSAT Examiner Note: The following steps are from SOP-502A, Step 5.2.1.2.

Perform Step: 6 IF the safeguards loops are not cross-connected, THEN ensure the following 5.2.1.2.A & B equipment for the pump to be stopped has been removed from service:

Standard: DETERMINED the Safeguards Loops ARE cross-connected and N/A.

Comment: SAT UNSAT Page 6 of 9 CPNPP NRC 2015 JPM S-8

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 IF additional flow was established for two pump operation AND is not required, 5.2.1.2.C.1) THEN throttle the following valve(s) as necessary such that CCWP DISCHARGE PRESSURE is approximately 140 to 150 psig as indicated on 1 PI-4520 and 1-PI-4521. (MCB)

TRAIN A 1-HS-4574, CS HX 1 CCW RET VLV 1-HS-4572, RHR HX 1 CCW RET VLV TRAIN B 1-HS-4575, CS HX 2 CCW RET VLV 1-HS-4573, RHR HX 2 CCW RET VLV Standard: PERFORMED the following:

OBSERVED 1-PI-4520, CCWP1 DISCH PRESS approximately 140 to 150 PSIG.

OBSERVED 1-PI-4521, CCWP2 DISCH PRESS approximately 140 to 150 PSIG.

Comment: SAT UNSAT Perform Step: 8 Stop the desired CCW Pump AND hold the handswitch in STOP.

5.2.1.2.C.2) 1-HS-4518A, CCWP 1 Standard: PERFORMED the following:

PLACED and HELD 1-HS-4518A, CCWP 1 in STOP (critical).

OBSERVED green PUMP and red FAN lights LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 9 WHEN CCW flow and pressure stabilize, THEN release the CCW Pump 5.2.1.2.C.3) handswitch.

Standard: RELEASED 1-HS-4518A, CCWP 1 handswitch when CCW flow and pressure stabilized.

Comment: SAT UNSAT Page 7 of 9 CPNPP NRC 2015 JPM S-8

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Examinee may request an independent verification of the following step.

Perform Step: 10 Ensure BOTH CCW Pump handswitches are in AUTO:

5.2.1.2.D 1-HS-4518A, CCWP 1 1-HS-4519A, CCWP 2 Standard: VERIFIED 1-HS-4518A, CCWP 1 AND 1-HS-4519A, CCWP 2 handswitches are in AUTO.

Comment: SAT UNSAT Terminating Cue: This JPM is complete.

STOP TIME:

Page 8 of 9 CPNPP NRC 2015 JPM S-8

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 1 is in MODE 1.

A CCW pump swap is required to support a maintenance activity in Train A CCW Pump Room.

A Nuclear Equipment Operator (NEO) is standing by for pump start.

INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:

START Train B Component Cooling Water Pump and STOP Train A Component Cooling Water Pump per SOP-502A, Component Cooling Water System.

If needed to initiate flow through the Containment Spray or RHR Heat exchangers, do NOT exceed 1500 gpm flow per heat exchanger.

START at Step 5.2.1.1, Starting a Standby CCW Pump During Normal Operation, to place the Train B CCW Pump in service.

CONTINUE with Step 5.2.1.2, Placing a CCW Pump in Standby from Dual Pump Operation, to secure the Train A CCW Pump.

Page 9 of 9 CPNPP NRC 2015 JPM S-8

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-1 Unit 1 Task #AO6439 K/A #007.EA2.02 4.3 / 4.6 SF-1

Title:

Locally Trip the Reactor and Stop MG Sets Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: X Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions with Unit 1 at 100% power:

An Anticipated Transient Without Trip (ATWT) is in progress.

Solid State Protection System Testing is NOT in progress.

The Reactor Operator is currently inserting rods at 48 steps per minute.

Initiating Cue: The Unit Supervisor DIRECTS you to perform the following actions:

Locally OPEN the Unit 1 Reactor Trip Breakers.

Locally STOP both of the Unit 1 Control Rod Drive Motor Generator sets.

Task Standard: Locally OPENED the Unit 1 Reactor Trip Breakers and Locally STOPPED both of the Unit 1 Control Rod Drive Motor Generator sets.

Required Materials: None.

Validation Time: 6 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 CPNPP NRC 2015 JPM P-1

Appendix C JPM WORKSHEET Form ES-C-1 EXAMINER:

The Steps of the JPM may be performed in any order.

IF ROD CONTROL SYSTEM IS IN SERVICE, DO NOT OPEN REACTOR TRIP SWITCHGEAR BREAKER DOORS.

All operations for this JPM will be in Unit 1 Safeguards Building, 832' elevation on TBX-ESPDTS-01, Reactor Trip Switchgear 1-01.

Page 2 of 7 CPNPP NRC 2015 JPM P-1

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: Initial condition of Reactor Trip Breaker A is CLOSED.

Perform Step: 1 OPEN UNIT 1 TRAIN A REACTOR TRIP BREAKER RTA.

Standard: DEPRESSED red TRIP pushbutton on the breaker door OR DEPRESSED red TRIP pushbutton inside door on front of breaker.

Examiner Cue: The breaker makes clunking sound. Control Room reports RTA indicates OPEN.

Examiner Note: If applicant checks position on the breaker, report Breaker Open green flag is visible on the breaker (located inside cubicle door).

Comment: SAT UNSAT Examiner Note: Based on the cue, the applicant may determine this step is unnecessary as there is no SSPS testing in progress, and mark the step N/A.

Initial condition of Reactor Trip Bypass Breaker A is OPEN and racked out to DISCONNECT.

Perform Step: 2 Open Reactor Trip Bypass Breaker A.

Standard: VERIFIED red close and green open lights on front of cubicle are OFF.

OR OBSERVED Breaker Open green flag visible with breaker racked to DISCONNECT position.

Examiner Cue: Red close and green open lights are off.

OR Open green flag is visible with breaker racked to DISCONNECT position.

Comment: SAT UNSAT N/A Page 3 of 7 CPNPP NRC 2015 JPM P-1

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Initial condition of Reactor Trip Breaker B is CLOSED.

Perform Step: 3 OPEN UNIT 1 TRAIN B REACTOR TRIP BREAKER RTB.

Standard: DEPRESSED red TRIP pushbutton on the breaker door.

OR DEPRESSED red TRIP pushbutton inside door on front of breaker.

Examiner Cue: The breaker makes clunking sound. Control Room reports RTB indicates OPEN.

Examiner Note: If applicant checks position on the breaker, report Breaker Open green flag is visible on the breaker (located inside cubicle door).

Comment: SAT UNSAT Examiner Note: Based on the cue, the applicant may determine this step is unnecessary as there is no SSPS testing in progress, and mark the step N/A.

Initial condition of Reactor Trip Bypass Breaker B is OPEN and racked out to DISCONNECT.

Perform Step: 4 Open Reactor Trip Bypass Breaker B.

Standard: VERIFIED red close and green open lights on front of cubicle are OFF.

OR OBSERVED Breaker Open green flag visible with breaker racked to DISCONNECT position.

Examiner Cue: Red close and green open lights are off.

OR Open green flag is visible with breaker racked to DISCONNECT position.

Comment: SAT UNSAT N/A Perform Step: 5 Stop Control Rod Drive Motor Generator Set 1-01.

Standard: PLACED 1/1-ELPS1, MOTOR 1-01 STARTING BREAKER to TRIP OR PULL LAMP CUT OUT.

Examiner Cue: Breaker makes clunking sound. Motor Generator begins to slow (if placed in TRIP, green light LIT, red light OFF.)

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2015 JPM P-1

Appendix C JPM STEPS Form ES-C-1 Examiner Note: If the applicant opened the Motor Breaker first, the Generator Breaker will trip OPEN.

Perform Step: 6 Stop Rod Drive Motor Generator Set 1-01.

Standard: PLACED 1/1-MGPS1, MG SET 1-01 GENERATOR CKT BKR CONTROL SWITCH to TRIP.

OR PULL OUT.

Examiner Cue: INDICATE the Generator Breaker is OPEN (lights are OFF in PULL OUT).

Comment: SAT UNSAT N/A Perform Step: 7 Stop Rod Drive Motor Generator Set 1-02.

Standard: PLACED 1/1-ELPS2, MOTOR 1-02 STARTING BREAKER to TRIP OR PULL LAMP CUT OUT.

Examiner Cue: Breaker makes clunking sound. Motor Generator begins to slow (if placed in TRIP, green light LIT, red light OFF).

Comment: SAT UNSAT Examiner Note: If the applicant opened the Motor Breaker first, the Generator Breaker will trip OPEN.

Perform Step: 8 Stop Rod Drive Motor Generator Set 1-02.

Standard: PLACED 1/1-MGPS2, MG SET 1-02 GENERATOR CKT BKR CONTROL SWITCH to TRIP OR PULL OUT.

Examiner Cue: INDICATE the Generator Breaker is OPEN (lights are OFF in PULL OUT).

Comment: SAT UNSAT N/A Page 5 of 7 CPNPP NRC 2015 JPM P-1

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Notify the Unit 1 Control Room that Reactor Trip and Bypass Breakers are OPEN and both Control Rod Drive Motor Generator Sets are STOPPED.

Standard: NOTIFIED the Unit 1 Control Room that Reactor Trip and Bypass Breakers are OPEN and both Control Rod Drive Motor Generator Sets are STOPPED.

Terminating Cue: The Control Room reports DRPI indication shows all Rod Bottom lights ON. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2015 JPM P-1

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions with Unit 1 at 100% power:

An Anticipated Transient Without Trip (ATWT) is in progress.

Solid State Protection System Testing is NOT in progress.

The Reactor Operator is currently inserting rods at 48 steps per minute.

INITIATING CUE: The Unit Supervisor DIRECTS you to perform the following actions:

Locally OPEN the Unit 1 Reactor Trip Breakers.

Locally STOP both of the Unit 1 Control Rod Drive Motor Generator sets.

Page 7 of 7 CPNPP NRC 2015 JPM P-1

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-1 Unit 2 Task #AO6439 K/A #007.EA2.02 4.3 / 4.6 SF-1

Title:

Locally Trip the Reactor and Stop MG Sets Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: X Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions with Unit 2 at 100% power:

An Anticipated Transient Without Trip (ATWT) is in progress.

Solid State Protection System Testing is NOT in progress.

The Reactor Operator is currently inserting rods at 48 steps per minute.

Initiating Cue: The Unit Supervisor DIRECTS you to perform the following actions:

Locally OPEN the Unit 2 Reactor Trip Breakers.

Locally STOP both of the Unit 2 Control Rod Drive Motor Generator sets.

Task Standard: Locally OPENED the Unit 2 Reactor Trip Breakers and Locally STOPPED both of the Unit 2 Control Rod Drive Motor Generator sets.

Required Materials: None.

Validation Time: 6 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 CPNPP NRC 2015 JPM P-1 (A06439B) (U2)

Appendix C JPM WORKSHEET Form ES-C-1 EXAMINER:

The Steps of the JPM may be performed in any order.

IF ROD CONTROL SYSTEM IS IN SERVICE, DO NOT OPEN REACTOR TRIP SWITCHGEAR BREAKER DOORS.

All operations for this JPM will be in Unit 2 Safeguards Building, 832' elevation on TCX-ESPDTS-01, Reactor Trip Switchgear 2-01.

Page 2 of 7 CPNPP NRC 2015 JPM P-1 (A06439B) (U2)

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: Initial condition of Reactor Trip Breaker A is CLOSED.

Perform Step: 1 OPEN UNIT 2 TRAIN A REACTOR TRIP BREAKER RTA.

Standard: DEPRESSED red TRIP pushbutton on the breaker door OR DEPRESSED red TRIP pushbutton inside door on front of breaker.

Examiner Cue: The breaker makes clunking sound. Control Room reports RTA indicates OPEN.

Examiner Note: If applicant checks position on the breaker, report Breaker Open green flag is visible on the breaker (located inside cubicle door).

Comment: SAT UNSAT Examiner Note: Based on the cue, the applicant may determine this step is unnecessary as there is no SSPS testing in progress, and mark the step N/A.

Initial condition of Reactor Trip Bypass Breaker A is OPEN and racked out to DISCONNECT.

Perform Step: 2 Open Reactor Trip Bypass Breaker A.

Standard: VERIFIED red close and green open lights on front of cubicle are OFF.

OR OBSERVED Breaker Open green flag visible with breaker racked to DISCONNECT position.

Examiner Cue: Red close and green open lights are off.

OR Open green flag is visible with breaker racked to DISCONNECT position.

Comment: SAT UNSAT N/A Page 3 of 7 CPNPP NRC 2015 JPM P-1 (A06439B) (U2)

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Initial condition of Reactor Trip Breaker B is CLOSED.

Perform Step: 3 OPEN UNIT 2 TRAIN B REACTOR TRIP BREAKER RTB.

Standard: DEPRESSED red TRIP pushbutton on the breaker door.

OR DEPRESSED red TRIP pushbutton inside door on front of breaker.

Examiner Cue: The breaker makes clunking sound. Control Room reports RTB indicates OPEN.

Examiner Note: If applicant checks position on the breaker, report Breaker Open green flag is visible on the breaker (located inside cubicle door).

Comment: SAT UNSAT Examiner Note: Based on the cue, the applicant may determine this step is unnecessary as there is no SSPS testing in progress, and mark the step N/A.

Initial condition of Reactor Trip Bypass Breaker B is OPEN and racked out to DISCONNECT.

Perform Step: 4 Open Reactor Trip Bypass Breaker B.

Standard: VERIFIED red close and green open lights on front of cubicle are OFF.

OR OBSERVED Breaker Open green flag visible with breaker racked to DISCONNECT position.

Examiner Cue: Red close and green open lights are off.

OR Open green flag is visible with breaker racked to DISCONNECT position.

Comment: SAT UNSAT N/A Perform Step: 5 Stop Control Rod Drive Motor Generator Set 2-01.

Standard: PLACED 1/2-ELPS1, MOTOR 2-01 STARTING BREAKER to TRIP OR PULL LAMP CUT OUT.

Examiner Cue: Breaker makes clunking sound. Motor Generator begins to slow (if placed in TRIP, green light LIT, red light OFF.)

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2015 JPM P-1 (A06439B) (U2)

Appendix C JPM STEPS Form ES-C-1 Examiner Note: If the applicant opened the Motor Breaker first, the Generator Breaker will trip OPEN.

Perform Step: 6 Stop Rod Drive Motor Generator Set 2-01.

Standard: PLACED 1/2-MGPS1, MG SET 2-01 GENERATOR CKT BKR CONTROL SWITCH to TRIP.

OR PULL OUT.

Examiner Cue: INDICATE the Generator Breaker is OPEN (lights are OFF in PULL OUT).

Comment: SAT UNSAT N/A Perform Step: 7 Stop Rod Drive Motor Generator Set 2-02.

Standard: PLACED 1/2-ELPS2, MOTOR 2-02 STARTING BREAKER to TRIP OR PULL LAMP CUT OUT.

Examiner Cue: Breaker makes clunking sound. Motor Generator begins to slow (if placed in TRIP, green light LIT, red light OFF).

Comment: SAT UNSAT Examiner Note: If the applicant opened the Motor Breaker first, the Generator Breaker will trip OPEN.

Perform Step: 8 Stop Rod Drive Motor Generator Set 2-02.

Standard: PLACED 1/2-MGPS2, MG SET 2-02 GENERATOR CKT BKR CONTROL SWITCH to TRIP OR PULL OUT.

Examiner Cue: INDICATE the Generator Breaker is OPEN (lights are OFF in PULL OUT).

Comment: SAT UNSAT N/A Page 5 of 7 CPNPP NRC 2015 JPM P-1 (A06439B) (U2)

Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Notify the Unit 2 Control Room that Reactor Trip and Bypass Breakers are OPEN and both Control Rod Drive Motor Generator Sets are STOPPED.

Standard: NOTIFIED the Unit 2 Control Room that Reactor Trip and Bypass Breakers are OPEN and both Control Rod Drive Motor Generator Sets are STOPPED.

Terminating Cue: The Control Room reports DRPI indication shows all Rod Bottom lights ON. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2015 JPM P-1 (A06439B) (U2)

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions with Unit 2 at 100% power:

An Anticipated Transient Without Trip (ATWT) is in progress.

Solid State Protection System Testing is NOT in progress.

The Reactor Operator is currently inserting rods at 48 steps per minute.

INITIATING CUE: The Unit Supervisor DIRECTS you to perform the following actions:

Locally OPEN the Unit 2 Reactor Trip Breakers.

Locally STOP both of the Unit 2 Control Rod Drive Motor Generator sets.

Page 7 of 7 CPNPP NRC 2015 JPM P-1 (A06439B) (U2)

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-2 Task # AO6413 K/A # 068.AA1.22 4.0 / 4.3

Title:

Response to Fire in the Control Room or Cable Spreading Room, NEO #2 Actions Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Alternate Path: X Plant: X Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 has entered ABN-803A, Response to Fire in the Control Room or Cable Spreading Room.

Attachment 4, Nuclear Equipment Operator No. 2 Actions to Achieve Hot Shutdown are in progress.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

Continue with ABN-803A, Response to Fire in the Control Room or Cable Spreading Room Attachment 4, (Nuclear Equipment Operator No. 2 Actions to Achieve Hot Shutdown) at Step l.

The RO at the RSP has just informed you that CCW pump 1-01 is running.

Task Standard: PERFORMED Steps l through n ABN-803A, Response to Fire in the Control Room or Cable Spreading Room, of Attachment 4 including starting Safety Chiller 1-05.

Required Materials: ABN-803A, Response to Fire in the Control Room or Cable Spreading Room, Attachment 4 (Nuclear Equipment Operator No. 2 Actions to Achieve Hot Shutdown).

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 7 CPNPP NRC 2015 JPM P-2

Appendix C JPM WORKSHEET Form ES-C-1 EXAMINER:

PROVIDE the examinee with the following:

ABN-803A, Attachment 4 marked through performance of Step k.

If the examinee requests to look inside the Safety Chiller Panel during performance step 2 or 3, then provide Attachment 1 of this JPM.

Page 2 of 7 CPNPP NRC 2015 JPM P-2

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-803A, Attachment 4 Examiner Note: The following represents the Alternate Path of this JPM.

Examiner Note: ECB 778 Unit 1 Safety Chiller Equipment Room (Rm 1-115A)

Examiner Cue: The RO at the RSP informs you that CCW pump 1-01 is running.

When the examinee arrives at the Unit 1 Train A Safety Chiller:

Examiner Cue:

Power ON and System Run lights are DARK WHEN CCW pump is running, THEN ensure Safety Chiller 1 RUNNING Perform Step: 1 step l & l 1) IF Safety Chiller NOT running, THEN perform the following:

Verify Recirculation Pump running.

Standard: CHECKED Recirculation Pump 1-05 running.

Examiner Cue: The Recirculation Pump is running.

Comment: SAT UNSAT If the examinee requests to look inside the Safety Chiller Panel during Examiner Note:

performance step 2 or 3, then provide Attachment 1 of this JPM.

Perform Step: 2 WHEN CCW pump is running, THEN ensure Safety Chiller 1 RUNNING step l 2)

IF Safety Chiller NOT running, THEN perform the following:

Place STOP/RESET-START switch (1-HS-6710A) in STOP/RESET.

Standard: PLACED 1-HS-6710A in STOP/RESET.

Comment: SAT UNSAT Perform Step: 3 WHEN CCW pump is running, THEN ensure Safety Chiller 1 RUNNING step l 3)

IF Safety Chiller NOT running, THEN perform the following:

Place STOP/RESET-START switch in START.

Standard: PLACED 1-HS-6710A in START.

Examiner Cue: Power ON and System Run lights are LIT. The Safety Chiller is running.

Comment: SAT UNSAT Page 3 of 7 CPNPP NRC 2015 JPM P-2

Appendix C JPM STEPS Form ES-C-1 Examiner Note: SFGD 790, Corridor Outside CS Chem Add Tk Room, (RM 1-070)

Examiner Cue: The Position Indicator is at the Top in line with the OPEN indication.

Perform Step: 4 Ensure the following valves - CLOSED.

step m 1st Bullet 1-8812A, RWST 1-01 TO RHR PMP 1-01 SUCT VLV Standard: DEPRESSED Declutch lever.

ROTATED Handwheel in the Clockwise direction.

Examiner Cue: The Handwheel has stopped turning and Position Indicator is at the Bottom in line with the CLOSED indication.

Comment: SAT UNSAT Examiner Cue: The Position Indicator is at the Top in line with the OPEN indication.

Perform Step: 5 Ensure the following valves - CLOSED.

step m 2nd Bullet 1-8812B, RWST 1-01 TO RHR PMP 1-02 SUCT VLV Standard: DEPRESSED Declutch lever.

ROTATED Handwheel in the Clockwise direction.

Examiner Cue: The Handwheel has stopped turning and Position Indicator is at the Bottom in line with the CLOSED indication.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2015 JPM P-2

Appendix C JPM STEPS Form ES-C-1 Examiner Note: For each Steam Generator either an upstream or downstream isolation valve may be used for throttling.

The valves are normally Locked Open, the examinee will need to indicate that he has cut the seal before the valve can be moved.

Examiner Cue: Once examinee arrives at throttle valves provide the following cue:

The RO reports the Initial Flow Rates are as follows:

Steam Generator # 1 is 300 gpm.

Steam Generator # 2 is 300 gpm.

Total Flow from MDAFW Pump 1-01 is 650 gpm.

The RO desires 150 gpm to each Steam Generator and total flow from MDAFW Pump 1-01 of 400 gpm.

Perform Step: 6 Train A MD AFW PMP Room (SG 790' 1-072) step n As directed by the RO, locally control auxiliary feedwater flow to Steam Generators 1 and 2:

SG 1-01 1AF-0074, MD AFW PMP 1-01 DISCH TO SG 1-01 UPSTRM ISOL VLV OR 1AF-0121, MD AFW PMP 1-01 DISCH TO SG 1-01 DNSTRM ISOL VLV Standard: UNLOCKED and THROTTLED CLOSED 1AF-0074 or 1AF-0121 by ROTATING handwheel in CLOCKWISE direction.

Examiner Cue: Once examinee has demonstrated throttling the valve closed, provide examinee with the modified flow rates:

Steam Generator # 1 is 100 gpm.

Steam Generator # 2 is 350 gpm.

Total Flow from MDAFW Pump 1-01 is 525 gpm.

Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2015 JPM P-2

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Train A MD AFW PMP Room (SG 790' 1-072) step n As directed by the RO, locally control auxiliary feedwater flow to Steam Generators 1 and 2:

SG 1-02 1AF-0082, MD AFW PMP 1-01 DISCH TO SG 1-02 UPSTRM ISOL VLV OR 1AF-0123, MD AFW PMP 1-01 DISCH TO SG 1-02 DNSTRM ISOL VLV Standard: UNLOCKED and THROTTLED CLOSED 1AF-0082 or 1AF-0123 by ROTATING handwheel in CLOCKWISE direction.

Examiner Cue: Once examinee has demonstrated throttling the valve closed, provide examinee with the modified flow rates:

Steam Generator # 1 is 150 gpm.

Steam Generator # 2 is 150 gpm.

Total Flow from MDAFW Pump 1-01 is 400 gpm.

Examiner Cue: This JPM is Complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2015 JPM P-2

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Unit 1 has entered ABN-803A, Response to Fire in the Control Room or Cable Spreading Room.

Attachment 4, Nuclear Equipment Operator No. 2 Actions to Achieve Hot Shutdown are in progress.

Initiating Cue: The Unit Supervisor directs you to PERFORM the following:

Continue with ABN-803A, Response to Fire in the Control Room or Cable Spreading Room Attachment 4, (Nuclear Equipment Operator No. 2 Actions to Achieve Hot Shutdown) at Step l.

The RO at the RSP has just informed you that CCW pump 1-01 is running.

This JPM is NOT Time Critical Page 7 of 7 CPNPP NRC 2015 JPM P-2

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-3 Task # AO4204D K/A # 062.A4.04 2.6 / 2.7 SF-6

Title:

Transfer Inverter IV2PC1 from Bypass to Normal Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: X Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 2 is at 100% power.

Inverter IV2PC1 is currently energized and on Bypass Power.

Appropriate repairs have been completed.

Initiating Cue: The Unit Supervisor directs you to Transfer Inverter IV2PC1 from Bypass to Normal Operation, in accordance with SOP-607B, 118 VAC Distribution System and Inverters, Section 5.5.9.

Task Standard: Utilizing SOP-607B, 118 VAC Distribution System and Inverters, Section 5.5.9, Transferring Inverter IV2PC1 from Bypass to Normal Operation.

Required Materials: SOP-607B, 118 VAC Distribution System and Inverters, Rev. 16, PCN 2.

Validation Time: 10 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 6 CPNPP NRC 2015 JPM P-3

Appendix C JPM WORKSHEET Form ES-C-1 EXAMINER:

PROVIDE the examinee with a copy of SOP-607B, 118 VAC Distribution System and Inverters, Section 5.5.9, Transferring Inverter IV2PC1 from Bypass to Normal Operation Page 2 of 6 CPNPP NRC 2015 JPM P-3

Appendix C JPM CUE SHEET Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-607B, Section 5.5.9.

Perform Step: 1 IF Inverter IV2PC1 is deenergized, THEN ENERGIZE IV2PC1 per section step A. 5.5.1.

Standard: DETERMINED that step is N/A, per Initial Conditions.

Comment: SAT UNSAT Perform Step: 2 IF Inverter IV2PC1 is energized, THEN PERFORM the following to PLACE step B 1) IV2PC1 in INVERTER SUPPLYING LOAD:

1) VERIFY IN SYNC light is LIT.

Standard: VERIFIED IN SYNC light LIT.

Examiner Cue: Simulate IN SYNC light LIT.

Comment: SAT UNSAT Examiner Note: The as found condition of the static switch is BYPASS SOURCE SUPPLYING LOAD red light lit.

Perform Step: 3 2) DEPRESS BYPASS SOURCE TO LOAD pushbutton (Static Transfer step B 2) Switch) AND VERIFY BYPASS SOURCE SUPPLYING LOAD red light is LIT.

Standard: DEPRESSED BYPASS SOURCE TO LOAD pushbutton (Static Transfer Switch)

AND VERIFIED BYPASS SOURCE SUPPLYING LOAD red light LIT.

Examiner Cue: BYPASS SOURCE SUPPLYING LOAD red light LIT.

Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2015 JPM P-3

Appendix C JPM CUE SHEET Form ES-C-1 Examiner Note: The as found condition of TRS10IV2PC1 is in BYPASS SOURCE.

Perform Step: 4

3) PLACE TRS1-IV2PC1, BYP SW S1 in NORMAL SOURCE.

step B 3)

Standard: PLACED TRS1-IV2PC1, BYP SW S1 in NORMAL SOURCE.

Examiner Cue: Simulate Switch TRS1-IV2PC1, BYP SW S1 in NORMAL SOURCE.

Comment: SAT UNSAT Examiner Note: The red alarm lights, Inverter Failure, DC Volts Low, and Fan Failure are all OFF.

Perform Step: 5

4) VERIFY IV2PC1 alarm lamps are OFF.

step B 4)

Standard: VERIFIED IV2PC1 Red alarm lamps OFF.

Examiner Cue: Red alarm lamps are OFF.

Comment: SAT UNSAT Perform Step: 6 step B 5) 5) VERIFY Inverter AC OUTPUT voltage is 118 to 128 VAC.

Standard: VERIFIED Inverter AC OUTPUT voltage between 118 to 128 VAC.

Examiner Cue: INDICATE on meter Inverter AC OUTPUT voltage is 125 VAC.

Comment: SAT UNSAT Examiner Note: When the INVERTER TO LOAD button is depressed the Yellow INVERTER SUPPLYING LOAD light will light and the Red BYPASS SOURCE SUPPLYING LOAD light will go OFF.

Perform Step: 7 6) DEPRESS INVERTER TO LOAD pushbutton (Static Transfer Switch) step B 6) AND VERIFY INVERTER SUPPLYING LOAD yellow light is LIT.

Standard: DEPRESSED INVERTER TO LOAD pushbutton (Static Transfer Switch)

(critical).

VERIFIED INVERTER SUPPLYING LOAD yellow light is LIT (NOT critical).

Examiner Cue: Once pushbutton is depressed, INVERTER SUPPLYING LOAD yellow light is LIT. Red BYPASS SOURCE SUPLLYING LOAD light is OFF.

Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2015 JPM P-3

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 8 VERIFY Inverter AC OUTPUT voltage is 118 to 128 VAC.

step B 7)

Standard: VERIFIED Inverter AC OUTPUT voltage is 118 to 128 VAC.

Examiner Cue: INDICATE on meter Inverter AC OUTPUT voltage is 125 VAC.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP NRC 2015 JPM P-3

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 2 is at 100% power.

Inverter IV2PC1 is currently energized and on Bypass Power.

Appropriate repairs have been completed.

INITIATING CUE: The Unit Supervisor directs you to Transfer Inverter IV2PC1 from Bypass to Normal Operation, in accordance with SOP-607B, 118 VAC Distribution System and Inverters, Section 5.5.9.

Page 6 of 6 CPNPP NRC 2015 JPM P-3

Scenario Event Description NRC Scenario 1 Facility: CPNPP 1 & 2 Scenario No.: 1 Op Test No.: June 2015 NRC Examiners: Operators:

Initial Conditions: 100% power MOL - RCS Boron is 924 ppm (by sample).

Turnover: Begin a 30 minute ramp to 600 MW for removing Main Feedwater Pump 1-01 from service to repair an oil leak.

Critical Tasks: Initiate Train A and/or Train B Safety Injection due to Failure to Automatically Actuate prior to Exiting EOP-0.0A, Reactor Trip or Safety Injection.

Trip Reactor Coolant Pumps within 5 minutes upon a Loss of Subcooling per EOP-0.0A, Reactor Trip or Safety Injection or EOP-1.0A, Loss of Reactor or Secondary Coolant, Foldout Pages.

Initiate Cooldown of Reactor Coolant System Prior to Exiting EOS-1.2A, Post LOCA Cooldown and Depressurization.

Event No. Malf. No. Event Type* Event Description 1 ---- R - RO Begin power reduction for removing MFP 1-01 from service.

N - BOP N - SRO 2 CC02A C - BOP CCW Pump 1-01 trips. Standby fails to auto start.

CC03A TS - SRO 3 CH10 C - BOP CRDM Vent Fan trips. Requires manual start of alternate.

C - SRO 4 RP05A I - RO NR Cold Leg TI (TE-411B) fails high.

TS - SRO 5 RC03C C - RO RCP 1-03 vibration (Ramps to 20 mils over 5 min).

C - BOP C - SRO 6 RC19C M - ALL SBLOCA.

7 RP07A I - RO Both trains SI fail to auto actuate.

RP07B 8 ED05E C - RO Loss of 1EA1 Safeguards Bus (86-2 actuation).

CV01F CCP 1-01 fails to sequence on. Requires manual start.

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

Page 1 of 37 CPNPP NRC 2015 Scenario 1

Scenario Event Description NRC Scenario 1 SCENARIO 1

SUMMARY

Event 1 Due to an oil leak on Main Feedwater Pump 1-01, the crew begins a 30 minute ramp to 600 MW for removing MFP 1-01 from service.

Event 2 The next event is a trip of Component Cooling Water (CCW) Pump 1-01, with a failure of the standby pump (CCW Pump 1-02) to automatically start The crew will enter ABN-502, Section 2.0, CCW Pump Trip, and manually start CCW Pump 1-02, per Step 1 RNO. The SRO will refer to Technical Specifications for this malfunction.

Event 3 The operating CRDM vent fan trips. The crew will refer to 1-ALB-3A, Window 1.6, CRDM SHROUD EXH TEMP HI, and ensure that at least one CRDM vent fan is in service, and manually start an alternate vent fan, per SOP-801A. They will use either Section 5.3.1, Control Rod Drive Mechanism Ventilation System Startup, or Section 5.3.3, Alternating Control Rod Drive Mechanism Ventilation Fans, for this evolution.

Event 4 The next event is a failure of Cold Leg Loop 1 NR Temperature Transmitter (TE-411B). It will fail high (630°F).

The Reactor Operator will take action per ABN-704, Tc/N-16 Instrumentation Malfunction. This event requires taking manual control of rods, since the Tc failure results in a higher Tave and rods will be inserting in automatic.

The SRO will refer to Technical Specifications for this malfunction.

Event 5 The next event is the precursor to the major event and involves high shaft vibration of Reactor Coolant Pump 1-03. This malfunction ramps in over a period of 5 minutes, allowing the crew time to evaluate and enter ABN-101, Section 6.0, Excessive Reactor Coolant Pump Vibration. Alarm 1-ALB-5B, Window 3.5, RCP 3 VIBR HI will come in (setpoint is 15 mils shaft vibration). Bearing temperatures and amps will continue to rise as the condition worsens. As the event progresses, the crew will recognize that RCP trip criteria have been exceeded.

The crew then trips the reactor and enters to EOP-0.0A.

Event 6 When the reactor is tripped, a SBLOCA occurs inside containment on RCS Loop 3 at 1500 gpm. The crew will progress through EOP-0.0A, and then transition to EOP-1.0A, Loss of Reactor or Secondary Coolant. Adverse Containment Conditions will apply at some point as containment pressure rises due to the LOCA.

Event 7 This scenario is complicated by the automatic failure of both trains of Safety Injection to actuate. Manual actuation of both trains will be successful.

Event 8 Once SI has been reset, a Safeguard Bus 1EA1 lockout (86-2) occurs. The bus will reenergize from the Emergency Diesel Generator and all loads will properly sequence on with the exception of Centrifugal Charging Pump (CCP) 1-01. Manual start of CCP 1-01 will be successful. The crew will transition to EOS-1.2A, Post LOCA Cooldown and Depressurization, and begin the required cooldown. The scenario will be terminated approximately 5 minutes after the cooldown is commenced.

Risk Significance:

Failure of risk important system prior to trip: Loss of CCW (Pump trip)

RCP high vibration Risk significant core damage sequence: RCP high vibration, then Small Break LOCA Risk significant operator actions: Manually Initiate Safety Injection Page 2 of 37 CPNPP NRC 2015 Scenario 1

Scenario Event Description NRC Scenario 1 Critical Task Determination Measurable Safety Performance Critical Task Cueing Performance Significance Feedback Indicators Initiate Train A Recognize a failure Procedural direction at The operator will PCIP Window 1.8 and/or Train B or an incorrect EOP-0.0A Step 4 to manually actuate annunciates Safety Injection due automatic determine if a Safety Safety Injection indicating both to Failure to actuation of an Injection is required and using either the trains of SI have Automatically ESF system or annunciators indicating handswitch on actuated.

Actuate prior to component. that an SI should have CB-07 or CB-02. Numerous Exiting EOP-0.0A, occurred yet did not equipment changes Reactor Trip or occur. of state.

Safety Injection.

Trip Reactor Take one or more Procedurally driven from The operator will Indication of pump Coolant Pumps actions that would EOP-0.0A and EOP-1.0A secure ALL RCPs stop including light within 5 minutes prevent a Foldout pages. using the indication, flow and upon a Loss of challenge to plant Availability of Subcooling handswitches on motor current.

Subcooling per safety. indication both on meters CB-05.

EOP-0.0A, Reactor FSAR II.K.3.5; and computer.

Trip or Safety WCAP-9584; WOG Injection or EOP- ERG Generic Issue 1.0A, Loss of for RCP Trip /

Reactor or Restart Secondary Coolant, Foldout Pages.

Initiate Cooldown of Take one or more Procedurally driven from The operator will Lowering SG Reactor Coolant actions that would EOS-1.2A to commence increase dumping pressures and System Prior to prevent a cooldown to reduce the steam from the lowering RCS Exiting EOS-1.2A, challenge to plant overall temperature of SGs via the ARVs temperatures Post LOCA safety. the RCS. or Steam Dumps beginning with the Cooldown and to reduce RCS cold leg Depressurization. temperature. temperatures.

Page 3 of 37 CPNPP NRC 2015 Scenario 1

Scenario Event Description NRC Scenario 1 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC18 and LOAD NRC Scenario 1.

DEMAND INITIATING EVENT TYPE MALF # DESCRIPTION VALUE PARAMETER RP07A Train A SI fails to auto actuate. f:1 K0 7

RP07B Train B SI fails to auto actuate. f:1 K0 2 CC03A CCW Pump 1-02 fails to auto start. f:1 K0 8 CV01F CCP 1-01 fails to sequence on Blackout. f:1 K0 CC02A CCW Pump 1-01 trips. f:1 K2 2

CC03A CCW Pump 1-02 fails to auto start. f:1 K0 3 CH10 CRDM Vent Fan #1 trips. f:1 K3 4 RP05A NR Cold Leg TI (TE-411B) fails high. f:630 K4 RCP1-03 vibration, ramps to 20 mils over 300 5 RC03C f:20 K5 seconds.

6 RC19C Small Break LOCA Loop 3. f:1500 (1)

RP07A Train A SI fails to auto actuate. f:1 K0 7

RP07B Train B SI fails to auto actuate. f:1 K0 ED05E Loss of 1EA1 Safeguard Bus (86-2) f:1 (2) 8 CV01F CCP 1-01 fails to sequence on Blackout. f:1 K0 (1) {DIRPRTC.Value=1} IMF RC19C f:1500 - Insert Small Break LOCA at 1500 gpm upon taking the RX trip switch to the TRIP position.

(2) {DICSHSRWSTB.Value=1} IMF ED05E f:1 - Insert 86-2 Lockout on Safeguard Bus 1EA1 when the Train B RHR Auto Swap Over Reset pushbutton is DEPRESSED.

Page 4 of 37 CPNPP NRC 2015 Scenario 1

Scenario Event Description NRC Scenario 1 Simulator Operator: INITIALIZE to IC18 and LOAD NRC Scenario 1.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE all Control Board Tags are removed.

ENSURE Operator Aid Tags reflect current boron conditions.

ENSURE Rod Bank Update (RBU) is performed.

ENSURE Turbine Load Rate set at 10 MWe/minute.

ENSURE 60/90 buttons DEPRESSED on ASD.

ENSURE ASD speakers are ON at half volume.

ENSURE Reactivity Briefing Sheet printout provided with Turnover.

ENSURE procedures in progress are on SRO desk:

- COPY of IPO-003A, Power Operations, Section 5.6, Reducing Turbine Power from 100% to Mode 3.

ENSURE Control Rods are in AUTO with Bank D at 215 steps.

ENSURE RCP Vibration Panel is running and connected; set on RCP1-03 shaft.

Control Room Annunciators in Alarm:

PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.2 - IR TRN A RX TRIP BLK PCIP-1.4 - CNDSR AVAIL STM DMP ARMED C-9 PCIP-1.6 - RX 10% PWR P-10 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.2 - IR TRN B RX TRIP BLK PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.2 - PR TRN A LO SETPT RX TRIP BLK PCIP-4.2 - PR TRN B LO SETPT RX TRIP BLK Page 5 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 6 of 37 Event

Description:

30 minute down power to remove Main Feed Pump from service Time Position Applicants Actions or Behavior Examiner Note: The following steps are from IPO-003A, Power Operations, Section 5.6, Reducing Turbine Power from 100% to Mode 3.

Direct power reduction to 600 MW to remove MFP 1-01 from service using US IPO-003A Power Operations, Section 5.6, Reducing Turbine Power from 100% to MODE 3.

CONTACT Chemistry AND PLACE the specified demineralizers in service US per SOP-103A or SOP-106A prior to starting the power reduction. [5.6.1]

US Notify QSE Generation Controller prior to reducing load. [5.6.2]

Page 6 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 7 of 37 Event

Description:

30 minute down power to remove Main Feed Pump from service Time Position Applicants Actions or Behavior IF Reactor power will be decreased by >15% within a one hour period, US THEN notify Chemistry and Radiation Protection. (TS SR 3.4.16.2, ODCM 4.11.2.1.1.2, 4.11.2.1.1.3) [5.6.3]

PERFORM the following steps to reduce Turbine load to approximately 200 US MW (16%) or the desired intermediate load: [5.6.4]

Page 7 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 8 of 37 Event

Description:

30 minute down power to remove Main Feed Pump from service Time Position Applicants Actions or Behavior IF desired, THEN DETERMINE the amount of boration required to reduce RO Reactor power to approximately 200 MW or the desired intermediate load using the appropriate currently approved Reactivity Projection. [5.6.4.A]

IF desired, THEN DETERMINE the rate of boration required to allow slow RO control rod inward motion as the turbine load decreases, using the appropriate currently approved Reactivity Projection. [5.6.4.B]

REFER to Attachment 2 for guidance in controlling AFD during power ramps.

RO

[5.6.4.C]

RO INITIATE RCS boration/dilution using SOP-104A. [5.6.4.D]

WHEN the following are met:

1) No TSE alarms are active BOP 2) ENSURE turbine load/speed is matched with target load/speed THEN TURN ON TSE Influence. [5.6.4.E]

In the Load Control Section, SET in the desired unloading rate using the BOP Load Rate Setpoint Controller. [5.6.4.F]

In the Load Control Section, LOWER the Load Target Setpoint Controller BOP as necessary to obtain 200 MW or the desired intermediate load to control turbine load. [5.6.4.G]

Page 8 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 9 of 37 Event

Description:

30 minute down power to remove Main Feed Pump from service Time Position Applicants Actions or Behavior Examiner Note: The following steps are from SOP-104A, Reactor Make-up and Chemical Control System, Section 5.1.2, Borate Mode.

Examiner Note: Additional Backup Heaters may be turned on for the boration.

RO PERFORM the following to COMMENCE RCS boration:

ENSURE Prerequisites of Section 2.1 and 2.2 are met. [Step 5.1.2.A]

ENSURE 1/1-MU, RCS MU MAN ACT is in STOP. [Step 5.1.2.B]

PLACE 43/1-MU, RCS MU MODE SELECT in BORATE. [Step 5.1.2.C]

SET 1-FK-110, BA BLNDR FLO CTRL to ~4.68 pot setting for ~18.7 GPM. [Step 5.1.2.D]

SET 1-FY-110B, BA BATCH FLO counter for 561 gallons. [Step 5.1.2.E]

ENSURE 1/1-FCV-110A, BA BLNDR FLO CTRL VLV in AUTO.

[Step 5.1.2.F]

PLACE 1/1-MU, RCS MU MAN ACT in START. [Step 5.1.2.G]

VERIFY 1/1-APBA1, BA XFR PMP 1 STARTS. [Step 5.1.2.H]

VERIFY 1/1-FCV-110A, BA BLNDR FLO CTRL VLV throttles to ~18.7 GPM. [Step 5.1.2.I]

VERIFY 1/1-FCV-110B, RCS MU TO CHG PMP SUCT ISOL VLV OPEN.

[Step 5.1.2.I]

VERIFY 1-FY-110B, BA BATCH FLO counter operating properly.

[Step 5.1.2.J]

VERIFY 1-FR-110, BA BATCH FLO TO BLNDR red pen operating properly. [Step 5.1.2.J]

Page 9 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 10 of 37 Event

Description:

30 minute down power to remove Main Feed Pump from service Time Position Applicants Actions or Behavior OPERATE 1/1-LCV-112A, VCT LVL CTRL VLV as necessary to maintain proper VCT level. [Step 5.1.2.K]

When desired amount of boric acid is added, PLACE 1/1-MU, RCS MU MAN ACT in STOP. [Step 5.1.2.L]

Examiner Note: The following steps continue from IPO-003A, Power Operations, Section 5.6, Reducing Turbine Power from 100% to Mode 3.

BOP SET Turbine Load Rate Setpoint Controller to ~22 MWe/min. [Step 5.6.4.E]

OPEN Load Rate Setpoint OSD.

SELECT blue bar and ENTER 22 MWe/min.

CLOSE Load Rate Setpoint OSD.

BOP SET Turbine Load Target to ~600 MWe. [Step 5.6.4.F]

OPEN Load Target OSD.

SELECT blue bar and ENTER 600 MWe.

DEPRESS Accept then VERIFY value in blue bar is desired Load Target (magnitude and direction).

DEPRESS Execute then VERIFY Load Target changes to desired load.

CLOSE Load Target OSD.

CREW MONITOR load change.

When crew has demonstrated ability to reduce power in a controlled manner, or at Lead Examiner discretion, PROCEED to Event 2.

Page 10 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 11 of 37 Event

Description:

Train A Component Cooling Water (CCW) Pump Trip / Train B CCW Pump Start Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 2 (Key 2).

- CC02A, Train A CCW Pump (1-01) trip.

- CC03A, Train B CCW Pump (1-02) start failure.

Indications Available:

3C-2.3 - CCWP 1 / 2 OVLD TRIP 3C-3.3 - CCW TRAIN B SFGD LOOP PRESS LO Multiple CCW low flow alarms BOP RESPOND to Annunciator Alarm Procedures.

Examiner Note: The operator may recognize that an automatic start has not occurred and immediately start CCW Pump 1-02 which is permissible.

RECOGNIZE Train A CCW Pump trip with failure of Train B CCW Pump to BOP start.

DIRECT implementation of ABN-502, Component Cooling Water System US Malfunctions, Section 2.0.

Examiner Note: The following steps are from ABN-502, Component Cooling Water System Malfunctions, Section 2.0, CCW Pump Trip.

BOP VERIFY Train B CCW Pump - Not RUNNING. [Step 1]

Manually START Train B CCW Pump 1-02.

BOP VERIFY Train B Station Service Water Pump - RUNNING. [Step 2]

RO/BOP VERIFY Train B Safety Chiller Recirc Pump 1 RUNNING. [Step 3]

Simulator Operator Note: When dispatched to locally inspect Train A CCW Pump and Breaker, report a 50/51 relay is tripped at the breaker on Phases A and B and there is an acrid odor, no fire.

Page 11 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 12 of 37 Event

Description:

Train A Component Cooling Water (CCW) Pump Trip / Train B CCW Pump Start Failure Time Position Applicants Actions or Behavior VERIFY CCW Heat Exchanger outlet flow - LESS THAN 17,500 GPM PER BOP HEAT EXCHANGER. [Step 4]

1-FI-4536A, CCW HX 1 OUT FLO 1-FI-4537A, CCW HX 2 OUT FLO VERIFY required Train B equipment for existing plant conditions - IN BOP OPERATION. [Step 5]

Control Room Air Conditioning Units Containment Spray System UPS HVAC Unit Excess Letdown RHR System Examiner Note: Common equipment may be turned over to Unit 2.

BOP STOP Train A equipment - AS NECESSARY. [Step 6]

Control Room Air Conditioning Units Containment Spray System UPS HVAC Unit RHR System Safety Chiller Recirculation Pump VERIFY CCW Heat Exchanger outlet temperature did NOT exceed 122ºF BOP with pump running. [7]

US INITIATE a Work Request per STA-606. [8]

Page 12 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 13 of 37 Event

Description:

Train A Component Cooling Water (CCW) Pump Trip / Train B CCW Pump Start Failure Time Position Applicants Actions or Behavior US EVALUATE Technical Specifications. [9]

LCO 3.7.7.A, Component Cooling Water System.

CONDITION A - One CCW train inoperable.

ACTION A.1 - Restore CCW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

US REFER to EPP-201. [10]

When the crew has completed the actions of ABN-502, or at Lead Examiner discretion, PROCEED to Event 3.

Page 13 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 14 of 37 Event

Description:

CRDM Vent Fan trips. Requires manual start of alternate fan.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 3 (Key 3).

- CH10, Control Rod Drive Mechanism Fan (1-01) trips.

Indications Available:

3A-2.1 - CNTMT FN MASTER TRIP 3A-1.3 - CRDM VENT FN 1 P LO 3A-1.6 - CRDM SHROUD EXH TEMP HI 3B-4.2 - CRDM ANY VENT FAN DISCH TEMP HI (30 seconds later) 1-HS-5421, CRDM VENT FN amber MISMATCH, white TRIP, and green STOP lights LIT BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE CRDM Vent Fan 1-01 tripped.

DIRECT performance of ALM-0031A, 1-ALB-3A, Window 1.6 - CRDM US SHROUD EXH TEMP HI.

Examiner Note: The following steps are from ALM-0031A, 1-ALB-3A, Window 1.6 - CRDM SHROUD EXH TEMP HI.

Simulator Operator Note: When dispatched to locally inspect CRDM Vent Fan breaker, report the breaker tripped on overload.

BOP VERIFY at least one CRDM Vent Fan in service. [Step 1]

If NO fans are in service, START one CRDM Vent Fan per SOP-801A, BOP Containment Ventilation System. [Step 1.a]

Page 14 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 15 of 37 Event

Description:

CRDM Vent Fan trips. Requires manual start of alternate fan.

Time Position Applicants Actions or Behavior Examiner Note: The following two steps are from SOP-801A, Containment Ventilation System.

PLACE 1-HS-5423, CRDM VENT FN 2 handswitch in START.

BOP

[Step G]

BOP MONITOR Containment Radiation levels until they stabilize. [Step I]

Examiner Note: The next steps continue with ALM-0031A, 1-ALB-3A, Window 1.6 - CRDM SHROUD EXH TEMP HI.

BOP MONITOR 1-TI-5400A, CNTMT AVE TEMP. [Step 2]

VERIFY X-TI-6071, CH WTR SPLY HDR TEMP is 45ºF to 55ºF at X-CV-01.

BOP

[Step 3]

ENSURE 1-FI-6081, CNTMT FN CLR CH WTR RET FLO is between 912 BOP and 1008 GPM with any combination of 3 of 4 units in service. [Step 4]

BOP MONITOR CRDM Shroud exhaust temperature. [Step 5]

1-TI-5455, CRDM VENT FN 2 DISCH TEMP.

REFER to Technical Specifications LCO 3.6.5, Containment Air US Temperature. [Step 6]

CORRECT the condition or INITIATE a work request per STA-606.

US

[Step 7]

When CRDM cooling is restored, or at Lead Examiner discretion, PROCEED to Event 4.

Page 15 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 16 of 37 Event

Description:

NR Cold Leg TI (TE-411B) Fails High.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 4 (Key 4).

- NR Cold Leg TI (TE-411B) fails high.

Indications Available:

6D-1.10 - AVE TAVE TREF DEV 6D-2.10 - AVE TAVE HI 6D-3.14 - 1 OF 4 OT N16 ROD STOP & TURB RUNBACK 1-TI-411A, CL 1 TEMP (NR) CHAN I indication failed high 1-TI-412, RC LOOP 1 TAVE CHAN I indication failed high RO RESPOND to Annunciator Alarm Procedures.

RO RECOGNIZE Control Rods inserting due to TCOLD failed high.

DIRECT performance of ABN-704, Tc / N-16 Instrumentation Malfunction, US Section 2.0.

Examiner Note: The RO may place 1-FK-121, Charging Flow Controller, in MANUAL to maintain PZR level on setpoint.

PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in MANUAL.

RO

[Step 2.3.1]

Page 16 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 17 of 37 Event

Description:

NR Cold Leg TI (TE-411B) Fails High.

Time Position Applicants Actions or Behavior RO SELECT LOOP 1 on 1-TS-412T, TAVE Channel Defeat. [Step 2.3.2]

VERIFY Steam Dump System is NOT actuated and NOT armed.

RO/BOP

[Step 2.3.3]

Examiner Note: Crew should Hold Setpoint on Turbine Ramp and stop boration on this failure (may have been previously performed).

SELECT LOOP 1 on 1/1-JS-411E, N16 Power Channel Defeat.

RO/BOP

[Step 2.3.5]

RO ENSURE a valid N16 channel supplying recorder on 1/1-TS-411E, 1 TR 411 CHAN SELECT. [Step 2.3.6]

RO/BOP VERIFY PCIP, Window 3.4 - TURB LOAD REJ STM DMP ARMED C-7, not ARMED (DARK). [Step 2.3.7]

US/BOP VERIFY Steam Dumps were NOT blocked. [Step 2.3.8]

US EVALUATE Technical Specifications. [Step 2.3.11]

LCO 3.3.1.E, Reactor Trip System Instrumentation (Functions 6 & 7).

CONDITION E - One channel inoperable.

ACTION E.1 - Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , OR ACTION E.2 - Be in MODE 3 within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months .

US INITIATE a work request per STA-606. [Step 2.3.12]

US INITIATE a Condition Report per STA-421. [Step 2.3.13]

When Technical Specifications are addressed, or at Lead Examiner discretion, proceed to Events 5.

Page 17 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5 Page 18 of 37 Event

Description:

RCP 1-03 High Vibration.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Events 5 (Key 5).

- RCP 1-03 High Vibration (Ramps to 20 mils over 300 seconds)

Indications Available:

1-ALB-5B, Window 3.5, RCP 3 VIBR HI Rising vibration observed on RCP Vibration Monitors RO RESPOND to Annunciator Alarm Procedures.

BOP REPORT RCP 1-03 shaft vibration greater than 15 mils.

DIRECT implementation of ABN-101, Reactor Coolant Pump US Trip/Malfunction, Section 6.0, Excessive Reactor Coolant Pump Vibration.

Examiner Note: The following steps are from ABN-101, Reactor Coolant Pump Trip/Malfunction, Section 6.0, Excessive Reactor Coolant Pump Vibration.

RO/BOP CHECK RCP Vibration - WITHIN LIMITS: [Step 6.3.1]

RCP shaft vibration: [Step 6.3.1.a]

BETWEEN 15 mils and 20 mils and amplitude INCREASING less than 1 mil per hour. [Step 6.3.1.a]

TRIP Reactor and GO to EOP-0.0A while other operators continue RO/BOP this procedure. [Step 6.3.1.1) RNO]

STOP affected RCP 1-03 after Reactor trip.

RO

[Step 6.3.1.2) RNO]

When the REACTOR is tripped, a SBLOCA will occur on RCS Loop 3 at 1500 gpm (automatically triggered on the Reactor Trip Switch), PROCEED to Events 6, 7, and 8.

Page 18 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 19 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior Simulator Operator: Event 6 (Automatically inserts on the REACTOR Trip Switch)

-RC19C, SBLOCA RCS Loop 3 (1500 gpm)

-Both Trains of SI fail to actuate

-Loss of 1EA1 Safeguards Bus (86-2 Lockout)

-CCP1-01 fails to sequence on Indications Available:

2A-2.8 - ANY CNTMT SMP PMP RUN 2B-4.12 - CNTMT FN CLR 1 & 2 CNDS FILL RATE HI 2B-3.12 - CNTMT FN CLR 3 & 4 CNDS FILL RATE HI 5B-3.4 - PRZR 1 OF 4 PRESS LO 5B-4.4 - PRZR 1 OF 4 SI PRESS LO 5B-3.6 - PRZR LVL LO 5C-1.2 - PRZR LVL DEV LO 5C-3.3 - PRZR PRESS LO BACKUP HTRS ON 6A-3.4 - CHRG FLO HI / LO US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

Examiner Note: The following steps are from EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip: [1]

VERIFY Reactor Trip Breakers - OPEN. [1.a]

VERIFY Neutron flux - DECREASING. [1.a]

VERIFY all Control Rod Position Rod Bottom Lights - ON. [1.b]

BOP VERIFY Turbine Trip: [2]

VERIFY all HP Turbine Stop Valves - CLOSED. [2]

BOP VERIFY Power to AC Safeguards Buses: [3]

VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED. [3.a]

VERIFY both AC Safeguards Buses - ENERGIZED. [3.b]

Page 19 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 20 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior RO CHECK SI status: [4]

VERIFY SI Actuated - FIRST OUT ANNUNCIATOR LIT [4.a]

Examiner Note: SI fails to actuate automatically. Requires MANUAL actuation (Event 7).

CRITICAL TASK Initiate Train A and/or Train B Safety Injection due to Failure to Automatically STATEMENT Actuate prior to Exiting EOP-0.0A, Reactor Trip or Safety Injection.

RO Check if SI is required. [4.a.RNO]

Steam Line Pressure less than 610 psig.

Pressurizer Pressure less than 1820 psig.

Containment Pressure greater than 3.0 psig.

IF SI is required, THEN manually actuate SI from either handswitch.

RO

[4.a.RNO]

VERIFY Both Trains SI Actuated: [4.b]

SI Actuated blue status light - ON NOT FLASHING [4.b]

CRITICAL RO Manually Actuate SI. [4.b.RNO]

TASK Examiner Note: RO will trip RCP 1-03 after completion of EOP-0.0A, Immediate Actions due to High Vibrations.

RO Secure RCP 1-03 Upon completion of EOP-0.0A Immediate Actions.

Examiner Note: The RO may adjust seal injection and the BOP may adjust AFW Flow in accordance with guidance on the EOP-0.0A Foldout Page.

Page 20 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 21 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior Examiner Note: EOP-0.0A, Attachment 2 steps performed by BOP begin on Page 32 of the scenario guide.

US/BOP INITIATE Proper Safeguards Equipment Operation Per Attachment 2. [5]

RO VERIFY AFW Alignment: [6]

VERIFY both MDAFW Pumps - RUNNING. [6.a]

PLACE TDAFW Pump in PULLOUT per Foldout Page. [6.b]

VERIFY AFW total flow - GREATER THAN 460 GPM. [6.c]

VERIFY AFW valve alignment - PROPER ALIGNMENT. [6.d]

RO VERIFY Containment Spray NOT Required: [7]

VERIFY 1-ALB-2B, Window 1-8, CS ACT - NOT ILLUMINATED. [7.a]

VERIFY 1-ALB-2B, Window 4-11, CNTMT ISOL PHASE B ACT - NOT ILLUMINATED. [7.a]

VERIFY Containment pressure - LESS THAN 18.0 psig. [7.a]

VERIFY Containment Spray Heat Exchanger Outlet Valves - CLOSED.

[7.b]

VERIFY Containment Spray Pumps - RUNNING. [7.c]

Examiner Note: The crew may MANUALLY isolate Main Steam Lines prior to Automatic Isolation.

Page 21 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 22 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior RO CHECK if Main Steam lines should be ISOLATED: [8]

VERIFY Containment pressure - LESS THAN 6.0 psig. [8.a]

VERIFY Steam Line pressure - GREATER THAN 610 psig. [8.a]

Examiner Note: TCOLD is used to determine RCS temperature trend as this indication will be accurate independent of the condition of the RCPs.

RO CHECK RCS Temperature: [9]

VERIFY RCS Average Temperature - STABLE AT OR TRENDING TO 557°F. [9]

If temperature less than 557°F, PERFORM the following:

STOP dumping steam. [9.a RNO]

If cooldown continues, MINIMIZE AFW flow as required. [9.b RNO]

If cooldown continues, CLOSE MSIVs. [9.c RNO]

RO CHECK PRZR Valve Status: [10]

VERIFY PRZR Safeties - CLOSED. [10.a]

VERIFY Normal PRZR Spray Valves - CLOSED. [10.b]

VERIFY PORVs - CLOSED. [10.c]

VERIFY Power to at least 1 Block Valve - AVAILABLE. [10.d]

VERIFY Block Valves - AT LEAST ONE OPEN. [10.e]

Trip Reactor Coolant Pumps within 5 minutes upon a Loss of Subcooling per CRITICAL TASK EOP-0.0A, Reactor Trip or Safety Injection, or EOP-1.0A, Loss of Reactor or STATEMENT Secondary Coolant.

RO VERIFY RCS subcooling less than 25ºF (55ºF FOR ADVERSE CONTAINMENT) and STOP all RCPs. [11]

VERIFY RCS subcooling - LESS THAN 25°F. [11.a]

VERIFY ECCS Pumps (CCP or SI) - AT LEAST ONE RUNNING. [11.b]

CRITICAL STOP all RCPs. [11.c]

TASK Page 22 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 23 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior RO/BOP CHECK if Any Steam Generator Is Faulted: [12]

VERIFY NO Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [12.a]

VERIFY NO Steam Generator pressure - COMPLETELY DEPRESSURIZED. [12.a]

RO/BOP CHECK if Steam Generator Tubes Are NOT Ruptured: [13]

VERIFY Condenser Off Gas radiation - NORMAL. [13]

VERIFY Main Steam Line radiation - NORMAL. [13]

VERIFY SG Blowdown Sample Radiation Monitor - NORMAL. [13]

VERIFY levels in all Steam Generators - NORMAL. [13]

RO/BOP CHECK if RCS is Intact: [14]

VERIFY Containment pressure - GREATER THAN 1.3 psig. [14]

VERIFY Containment recirculation sump levels - NOT NORMAL. [14]

VERIFY Containment radiation levels - NOT NORMAL. [14]

GO to EOP-1.0A, Loss of Reactor or Secondary, Step 1. [14 RNO]

US TRANSITION to EOP-1.0A, Loss of Reactor or Secondary Coolant, Step 1.

Examiner Note: EOP-1.0A, Loss of Reactor or Secondary Coolant steps begin here.

Page 23 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 24 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior US CHECK If RCPs Should Be Stopped: [1]

VERIFY RCS subcooling less than 25ºF (55ºF FOR ADVERSE CONTAINMENT). [1.a]

VERIFY ECCS Pumps (CCP or SI) - AT LEAST ONE RUNNING. [1.b]

Trip Reactor Coolant Pumps within 5 minutes upon a Loss of Subcooling per CRITICAL TASK EOP-0.0A, Reactor Trip or Safety Injection, or EOP-1.0A, Loss of Reactor or STATEMENT Secondary Coolant.

RO VERIFY RCS subcooling less than 25ºF (55ºF FOR ADVERSE CONTAINMENT) and STOP all RCPs. [1.a]

CRITICAL STOP all RCPs. [1.c]

TASK RO/BOP CHECK if Any Steam Generator Is Faulted: [2]

VERIFY NO Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [2.a]

VERIFY NO Steam Generator pressure - COMPLETELY DEPRESSURIZED. [2.a]

US CHECK Intact Steam Generator Levels: [3]

VERIFY Narrow range level - GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT). [3.a]

MAINTAIN total AFW flow greater than 460 GPM until narrow range level GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT).

[3.b]

US CHECK Secondary Radiation NORMAL: [4]

VERIFY Condenser off gas radiation - NORMAL. [4]

VERIFY Main Steam Line radiation - NORMAL. [4]

VERIFY SG Blowdown Sample Radiation Monitor - NORMAL. [4]

VERIFY levels in all Steam Generators - NORMAL. [4]

Page 24 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 25 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior US CHECK PRZR PORVs and Block Valves: [5]

VERIFY power to Block Valves - AVAILABLE. [5.a]

VERIFY PORVs - CLOSED. [5.b]

VERIFY Block Valves - AT LEAST ONE OPEN. [5.c]

US/RO CHECK if ECCS Flow Should Be Reduced: [6]

VERIFY Secondary heat sink conditions - SATISFIED. [6.a]

VERIFY total AFW flow to Intact SGs - GREATER THAN 460 GPM.

[6.a]

VERIFY intact SG NR level - GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT). [6.a]

VERIFY RCS subcooling - NOT GREATER THAN 25°F (55°F FOR ADVERSE CONTAINMENT). [6.b]

RO/BOP RESET ESF Actuation Signals. [7]

RO/BOP PLACE both EDG EMERG STOP/START handswitches in START. [7.a]

Page 25 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 26 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior RO/BOP RESET SI. [7.b]

DEPRESS 1/1-SIRA, TRAIN A SI RESET pushbutton.

DEPRESS 1/1-SIRB, TRAIN A SI RESET pushbutton.

RO/BOP RESET SI Sequencers. [7.c]

At SI Sequencer Train A Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

After ~ 2 seconds, PLACE ON/RESET toggle switch in ON.

At SI Sequencer Train B Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

After ~ 2 seconds, PLACE ON/RESET toggle switch in ON.

RO/BOP RESET Containment Isolation Phase A and Phase B. [7.d]

DEPRESS 1/1-C1PARA, CNTMT ISOL - PHASE A RESET pushbutton.

DEPRESS 1/1-C1PARB, CNTMT ISOL - PHASE A RESET pushbutton.

DEPRESS 1/1-C1PBRA, CNTMT ISOL - PHASE B RESET pushbutton.

DEPRESS 1/1-C1PBRB, CNTMT ISOL - PHASE B RESET pushbutton.

RO/BOP RESET Containment Spray Signal. [7.e]

DEPRESS 1/1-CSRA, TRAIN A CS RESET pushbutton.

DEPRESS 1/1-CSRB, TRAIN B CS RESET pushbutton.

Page 26 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 27 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior US CHECK If RHR Pumps Should Be Stopped: [8]

VERIFY RCS pressure - GREATER THAN 325 psig (425 psig FOR RO/BOP ADVERSE CONTAINMENT). [8.a.1)]

RO/BOP VERIFY RCS pressure - STABLE OR INCREASING. [8.a.2)]

VERIFY RHR Pumps - RUNNING WITH SUCTION ALIGNED TO RO/BOP RWST. [8.b]

RO/BOP STOP RHR Pumps and PLACE in standby. [8.c]

RO/BOP RESET RHR Auto Switchover. [8.d]

Examiner Note: A Loss of Safeguards Bus 1EA1 (86-2) will occur upon RESET of RHR Auto Swapover. The Train A EDG will start and energize the bus. Centrifugal Charging Pump (CCP) 1-01 will then fail to sequence on to the bus. This will result in the need to Restart CCP and SIP 1-01 (Event 8).

US CHECK RCS and SG Pressures: [9]

RO/BOP VERIFY RCS pressure - STABLE OR DECREASING. [9]

RO/BOP VERIFY all SG pressures - STABLE OR INCREASING. [9]

US CHECK If Diesel Generators Should Be Stopped: [10]

VERIFY AC Safeguards Buses ENERGIZED by Diesel Generators.

RO/BOP

[10.a]

RO/BOP Restart Centrifugal Charging Pump (CCP) 1-01.

RO/BOP Restart Safety Injection Pump (SIP) 1-01.

Page 27 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 28 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior US INITIATE Evaluation of Plant Status. [11]

RO/BOP VERIFY Cold Leg Recirculation capability: [11.a]

VERIFY Train A RHR Pump - AVAILABLE. [11.a.1)]

VERIFY CCW to Train A RHR Pump - AVAILABLE.

VERIFY 1/1-8811A, CNTMT SMP TO RHRP 1 SUCT ISOL VLV -

AVAILABLE.

VERIFY Train B RHR Pump - AVAILABLE. [11.a.1)]

VERIFY CCW to Train B RHR Pump - AVAILABLE.

VERIFY 1/1-8811B, CNTMT SMP TO RHRP 2 SUCT ISOL VLV -

AVAILABLE.

VERIFY 1/1-8804A, RHRP 1 TO CCP SUCT VLV - AVAILABLE.

[11.a.2)]

VERIFY 1/1-8804B, RHRP 2 TO SIP SUCT VLV - AVAILABLE.

[11.a.2)]

CHECK Auxiliary Building and Safeguards Building radiation -

RO/BOP NORMAL: [11.b]

CHECK PC-11 monitors - NORMAL OR Notify Radiation Protection to take local Radiation Surveys.

NOTIFY Chemistry to obtain RCS samples to assist in determining US extent of the accident. [11.c]

US CONTACT Plant Staff to EVALUATE plant equipment. [11.d]

US CHECK if RCS Cooldown and Depressurization Is Required: [12]

VERIFY RCS pressure - GREATER THAN 325 psig (425 psig FOR RO/BOP ADVERSE CONTAINMENT). [12.a]

GO to EOS-1.2A, Post LOCA Cooldown and Depressurization, Step 1.

US

[12.b]

Page 28 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 29 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior Examiner Note: EOS-1.2A, Post LOCA Cooldown and Depressurization, steps begin here.

Steps in [brackets] are from the associated EOS-1.2A Attachments.

RO/BOP [1.D] VERIFY Diesel Generators - RUNNING. [1]

RO/BOP [1.D] VERIFY SI - RESET. [2]

RO/BOP [1.D] VERIFY SI Sequencers - RESET. [3]

RO/BOP [1.D] VERIFY Containment Isolation Phase A and Phase B - RESET. [4]

RO/BOP [1.D] VERIFY Containment Spray Signal - RESET. [5]

Simulator Operator Note: If requested, EXECUTE remote functions EDR73, 1EB3/11D BKR to CLOSE and EDR74, 1EB4/11D BKR to CLOSE to RESET Instrument Air Compressors 1-01 & 1-02.

Page 29 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 30 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior RO/BOP [1.D] ESTABLISH Instrument Air and Nitrogen to Containment. [6]

ESTABLISH Instrument Air: [6.a]

VERIFY Air Compressor - RUNNING.

ESTABLISH Instrument Air to Containment:

ESTABLISH Nitrogen: [6.b]

VERIFY ACCUM 14 VENT CTRL, 1-HC-943 - CLOSED. [6.b.1)]

OPEN SI/PORV ACCCUM N2 ISOL VLV 1/1-8880. [6.b.2)]

BOP VERIFY all AC Buses - ENERGIZED BY OFFSITE POWER. [7]

RO DEENERGIZE PRZR Heaters: [8]

PLACE all PRZR heater switches in OFF position. [8.a]

CONSULT Plant Staff for a recommended minimum indicated PRZR water level that will ensure heaters are covered. [8.b]

US CHECK If RHR Pumps Should Be Stopped. [9]

VERIFY RHR Pumps - NOT RUNNING. [9.a]

Page 30 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 31 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior US CHECK Intact SG Levels: [10]

VERIFY narrow range level - GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT): [10.a]

CONTROL AFW flow to maintain narrow range level between 43% (50%

FOR ADVERSE CONTAINMENT) and 60%. [10.b]

CRITICAL TASK Initiate Cooldown of Reactor Coolant System Prior to Exiting EOS-1.2A, Post STATEMENT LOCA Cooldown and Depressurization.

US INITIATE RCS Cooldown to Cold Shutdown: [11]

MAINTAIN cooldown rate in RCS Cold Legs - LESS THAN 100°F/HR.

[11.a]

BLOCK Low Main Steam Pressure SI signal when Pressurizer pressure

- LESS THAN 1960 psig. [11.b]

CRITICAL DUMP steam from intact Steam Generators via ARVs. [11.c. RNO]

TASK When an RCS Cooldown is initiated, TERMINATE the scenario.

Page 31 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 32 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior Examiner Note: These steps are performed by the BOP per EOP-0.0A, Attachment 2.

BOP VERIFY SSW Alignment: [1]

VERIFY SSW Pumps - RUNNING. [1.a]

VERIFY EDG Cooler SSW Return Flow. [1.b]

BOP VERIFY Safety Injection Pumps - RUNNING. [2]

BOP VERIFY Containment Isolation Phase A - APPROPRIATE MLB LIGHT INDICATION (RED WINDOWS). [3]

BOP VERIFY Containment Ventilation Isolation - APPROPRIATE MLB LIGHT INDICATION (GREEN WINDOWS). [4]

BOP VERIFY CCW Pump 1 RUNNING. [5]

BOP VERIFY RHR Pumps - RUNNING. [6]

BOP VERIFY Proper CVCS Alignment: [7]

VERIFY CCPs - RUNNING. [7.a]

VERIFY Letdown Relief Valve Isolation: [7.b]

Letdown Orifice Isolation Valves - CLOSED. [7.b.1)]

Letdown Isolation Valves 1/1-LCV-459 & 1/1-LCV-460 - CLOSED.

[7.b.2)]

Page 32 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 33 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior BOP VERIFY ECCS flow: [8]

CCP SI flow indicator - CHECK FOR FLOW. [8.a]

RCS pressure - LESS THAN 1700 PSIG (1800 PSIG FOR ADVERSE CONTAINMENT). [8.b]

SIP discharge flow indicator - CHECK FOR FLOW. [8.c]

RCS pressure - LESS THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT). [8.d]

GO to Step 9. [8.d.RNO]

BOP VERIFY Feedwater Isolation Complete: [9]

Feedwater Isolation Valves - CLOSED.

Feedwater Isolation Bypass Valves - CLOSED.

Feedwater Bypass Control Valves - CLOSED.

Feedwater Control Valves - CLOSED.

BOP VERIFY Diesel Generators - RUNNING. [10]

BOP VERIFY Monitor Lights for SI Load Shedding on 1-MLB-9 and 1-MLB10 -

LIT. [11]

BOP VERIFY Proper SI alignment - PROPER MLB LIGHT INDICATION. [12]

BOP INITIATE periodic monitoring of Spent Fuel Cooling. [13]

Spent Fuel Pool temperature (T2900A, T2901A).

Spent Fuel Pool level (L4800A, L4801A, L4802A, L4803A).

Page 33 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 34 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior BOP VERIFY Components on Table 1 are Properly Aligned. [14]

Location Equipment Description Condition CB-03 X-HS-5534 H2 PRG SPLY FN 4 STOPPED CB-03 X-HS-5532 H2 PRG SPLY FN 3 STOPPED CB-04 1/1-8716A RHRP 1 XTIE VLV OPEN CB-04 1/1-8716B RHRP 2 XTIE VLV OPEN CB-06 1/1-8153 XS LTDN ISOL VLV CLOSED CB-06 1/1-8154 XS LTDN ISOL VLV CLOSED CB-07 1/1-RTBAL RX TRIP BKR OPEN CB-07 1/1-RTBBL RX TRIP BKR OPEN CB-07 1/1-BBAL RX TRIP BYP BKR OPEN/DEENERGIZED CB-07 1/1-BBBL RX TRIP BYP BKR OPEN/DEENERGIZED CB-08 1-HS-2397A SG 1 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2111C FWPT A TRIP TRIPPED CB-08 1-HS-2112C FWPT B TRIP TRIPPED CB-09 1-HS-2490 CNDS XFER PUMP STOPPED (MCC deenergized on SI)

CV-01 X-HS-6181 PRI PLT SPLY FN 17 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK STOPPED/DEENERGIZED DMPR Page 34 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 35 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior CV-01 X-HS-6202 PRI PLT SPLY FN 20 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6209 PRI PLT SPLY FN 21 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6216 PRI PLT SPLY FN 22 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6223 PRI PLT SPLY FN 23 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6230 PRI PLT SPLY FN 24 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-3631 UPS & DISTR RM A/C FN 1 & STARTED BSTR FN 42 CV-01 X-HS-3632 UPS & DISTR RM A/C FN 2 & STARTED BSTR FN 43 CV-01 1-HS-5600 ELEC AREA EXH FN 1 STOPPED/DEENERGIZED CV-01 1-HS-5601 ELEC AREA EXH FN 2 STOPPED/DEENERGIZED CV-01 1-HS-5602 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 3 & EXH DMPR CV-01 1-HS-5603 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 4 & EXH DMPR CV-01 1-HS-5618 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 17 CV-01 1-HS-5620 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 18 CV-03 X-HS-5855 CR EXH FN 1 STOPPED/DEENERGIZED CV-03 X-HS-5856 CR EXH FN 2 STOPPED/DEENERGIZED CV-03 X-HS-5731 SFP EXH FN 33 STOPPED/DEENERGIZED CV-03 X-HS-5733 SFP EXH FN 34 STOPPED/DEENERGIZED CV-03 X-HS-5727 SFP EXH FN 35 STOPPED/DEENERGIZED CV-03 X-HS-5729 SFP EXH FN 36 STOPPED/DEENERGIZED Page 35 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8 Page 36 of 37 Event

Description:

Rx Trip, SBLOCA, SI Fails to Actuate, 1EA1 (86-2 Lockout), CCP 1-01 Start Failure Time Position Applicants Actions or Behavior Examiner Note: The next four (4) steps would be performed on Unit 2.

CB-03 2-HS-5538 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5539 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5537 AIR PRG SPLY ISOL DMPR CLOSED CB-03 2-HS-5536 AIR PRG SPLY ISOL DMPR CLOSED BOP NOTIFY Unit Supervisor attachment instructions complete AND to IMPLEMENT FRGs as required.

EOP-0.0A, Attachment 2 steps are now complete.

Page 36 of 37 CPNPP NRC 2015 Scenario 1

Scenario Event Description NRC Scenario 1

CPNPP 2015 NRC Initial Scenario 1

Load IC18

INITIAL SETUP

Both Trains SI Fail to Actuate (Event 7)

IMF RP07A f:1 IMF RP07B f:1

Train A pressure switch fails to start B CCWP (Event 2)

IMF CC03A f:1

CCP 1-01 Fails to sequence on BO (Event 8)

IMF CV01F f:1

MALFUNCTIONS

CCW Pump 1-01 Trip (Event 2)

IMF CC02A f:1 k:2

CRDM Vent fan 1 Phase Overcurrent (Event 3)

IMF CH10 f:1 k:3

Cold Leg Loop 1 NR Fail High (TE-411B) (Event 4)

IMF RP05A f:630 k:4

RCP 3 Vibration 20 mils (Event 5)

IMF RC03C f:20 r:300 k:5

SBLOCA Loop 3 1500 gpm (Event 6)

{DIRPRTC.Value=1} IMF RC19C f:1500

86-2 on bus 1EA1 insert on Train B SI (Event 8)

{DICSHSRWSTB.Value=1} IMF ED05E f:1 Page 37 of 37 CPNPP NRC 2015 Scenario 1

Appendix D Scenario Outline Form ES-D-1 June 2015 NRC Exam Facility: CPNPP 1 & 2 Scenario No.: 2 Op Test No.: June 2015 Examiners: Operators:

Initial Conditions: 1 x 10-8 amps following a refueling outage. MDAFWPs are maintaining Steam Generator Water Levels 60-75%. Steam dumps are in Steam Pressure mode. Boron is 1669 ppm (by sample).

Turnover: Raise power to 100%.

Critical Tasks: Isolate Reactor Coolant System Leakage Paths in accordance with ECA-0.0A, Loss of All AC Power, prior to initiation of Steam Generator depressurization.

Restore Power to Bus 1EA2 in accordance with ECA-0.0A, Loss of All AC Power, prior to initiation of Steam Generator depressurization.

Identify and isolate the Faulted Steam Generator Prior to Exiting EOP-2.0A, Faulted Steam Generator Isolation.

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

R - RO 1

--- N - BOP Begin raising power to 2% to 3%.

N - SRO 2 C - RO CV01B Centrifugal Charging Pump (CCP) 1-01 trip.

TS - SRO 3 I - RO RX08A PT-455 PZR pressure fails high.

TS - SRO 4 C - BOP FW24B AFW Pump 1-02 trips. Manual start of TDAFW Pump required.

TS - SRO RD03B12 5 RD03D2 C - RO Shutdown Bank A (4 rods) drops.

RD03M14 C - SRO RD03P4 ED01 Loss of Offsite Power.

6 EG06A M - ALL DG 1-01 will not start in auto or manual.

EG15B DG 1-02 requires manual start.

7 MS01B M - ALL Main Steam Line Break on SG 1-02 inside containment.

8 RP09B C - BOP Auto Containment Isolation Phase A Actuation Failure on Train B

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

Page 1 of 34 CPNPP June 2015 NRC Exam Scenario 2

Scenario Event Description June 2015 NRC Exam Scenario 2 SCENARIO 2

SUMMARY

Event 1 In accordance with turnover instructions, the crew begins raising power to 2% to 3%, per IPO-002A, Plant Startup From Hot Standby, Section 5.4, Increasing Reactor Power to Approximately 2% Following Reactor Startup and Establishing Main Feedwater Flow to the SGs.

Event 2 The next event is a Centrifugal Charging Pump (CCP) 1-01 trip. The crew will enter ABN-105, Section 3.0, Charging Pump Trip; and as an Initial Operator Action, the operator will manually start CCP 1-02. The SRO will refer to Technical Specifications.

Event 3 The next event is a failure of Pressurizer Pressure Channel PT-455 high. The crew will enter ABN-705, Pressurizer Pressure Malfunction, Section 2.0, Pressurizer Pressure Instrument Malfunction. The associated PORV will open and the operator will close the PORV, its associated Block Valve, and place 1-PK-455A, Master Pressurizer Pressure Controller in manual and control PZR pressure. The SRO will refer to Technical Specifications.

Event 4 Upon Pressurizer pressure control restoration to automatic, Motor Driven Auxiliary Feedwater Pump (MDAFWP) 1-02 will trip. The crew will enter ABN-305, Auxiliary Feedwater System Malfunction, Section 3.0, Motor Driven Auxiliary Feedwater Pump Malfunction. The crew will manually start the Turbine Driven Auxiliary Feedwater Pump (TDAFWP) and feed Steam Generators 1-03 and 1-04 with the TDAFWP. The SRO will refer to Technical Specifications.

Event 5 When the Unit is stable, Shutdown Bank A Control Rods will drop fully into the core. The reactor will be manually tripped. The crew will enter EOP-0.0A, Reactor Trip or Safety Injection, and transition to EOS-0.1A, Reactor Trip Response.

Event 6 After the crew has transitioned to EOS-0.1A, Reactor Trip Response, a Loss of Offsite Power occurs. In conjunction with the Loss of Offsite Power, Emergency Diesel Generator (EDG) 1-01 will fail to start and EDG 1-02 will fail to automatically start. The crew will transition to ECA-0.0A, Loss of All AC Power. Letdown will be isolated as a Critical Task for isolating leakage paths. Power is restored in ECA-0.0A, via manual start of EDG 1-02.

Event 7 After transitioning back to EOS-0.1A, Reactor Trip Response, a Main Steamline Break occurs on SG 1-02 inside containment. The crew will transition back to EOP-0.0A, Reactor Trip or Safety Injection and then transition to EOP-2.0A, Faulted Steam Generator isolation. Upon completion of EOP-0.0A, Attachment 2, and when the crew has transitioned to EOP-2.0A the scenario will be terminated.

Event 8 When the crew transitions to EOP-0.0A, Reactor Trip or Safety Injection, the Unit Supervisor will direct the Balance-of-Plant (BOP) Operator to perform Attachment 2, Safety Injection Actuation Alignment, and during performance, the BOP Operator will discover that Auto Containment Isolation Phase A has failed on the B Train.

This will require the operator to manually initiate Phase A on Train B and verify that a proper containment isolation has occurred.

Risk Significance:

Failure of risk important system prior to trip: Charging Pump trips 4 dropped rods AFW pump trips Risk significant core damage sequence: Loss of Offsite Power DG failures to start Main Steam Line Break Risk significant operator actions: Manually start TDAFW pump Manually start DG 1-02 Identify and isolate faulted SG Manually initiate Phase A, Train B Critical Task Determination Page 2 of 34 CPNPP June 2015 NRC Exam Scenario 2

Scenario Event Description June 2015 NRC Exam Scenario 2 Measurable Safety Performance Critical Task Cueing Performance Significance Feedback Indicators Isolate Reactor Take one or more Procedural direction at The operator will Valve position will Coolant System actions that would ECA-0.0A Step 3 to manually close the change and Leakage Paths in prevent a minimize RCS inventory Letdown Isolation letdown flow will accordance with challenge to plant loss. Valve position Valves. lower to zero.

ECA-0.0A, Loss of safety. indication and letdown All AC Power, prior flow.

to initiation of Steam Generator depressurization.

Restore Power to Recognize a failure Procedural direction at The operator will Indication of DG Bus 1EA2 in or an incorrect ECA-0.0A Step 5 to manually start running and loading accordance with automatic restore power via EDG EDG 1-02 using via bus voltage and ECA-0.0A, Loss of actuation of an 1-02 to 1EA2. Bus the handswitch on frequency.

All AC Power, prior ESF system or voltage indication and CB-11.

to initiation of component EDG parameters.

Steam Generator resulting in depressurization. degraded ECCS capacity.

Identify and isolate Take one or more Procedurally driven from The operator will Valve position will the Faulted Steam actions that would EOP-2.0A to isolate the close the AFW change and AFW Generator Prior to prevent a faulted SG to prevent flow control valve flow to SG 1-02 will Exiting EOP-2.0A, challenge to plant further RCS cooldown to SG 1-02. reduce to zero.

Faulted Steam safety. and mass addition to Generator Isolation. containment.

Page 3 of 34 CPNPP June 2015 NRC Exam Scenario 2

Scenario Event Description June 2015 NRC Exam Scenario 2 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC08 and LOAD NRC Scenario 2.

REM. DEMAND INITIATING EVENT MALF. DESCRIPTION FUNC. VALUE PARAMETER EG06A Diesel Generator (1-01) Air Start Failure 6 f:1 K0 EG15B Diesel Generator (1-02) Fail to Auto Start Auto Containment Isolation Phase A Failure 8 RP09B f:1 K0 (Train B) 2 CV01B CCP 1-01 trips. f:1 K2 3 RX08A PT-455 PZR Pressure Fails High. f:2500 K3 4 FW24B AFW Pump 1-02 trips. f:1 K4 RD03B12 RD03D2 5 Shutdown Bank A, Group 1 rods drop (4 rods). f:1 K5 RD03M14 RD03P4 ED01 Loss of Offsite Power K6 6 EG06A DG 1-01 Air Start Failure. f:1 K0 EG15B DG 1-02 Fail to Auto Start. K0 Main Steam Line Break on SG 1-02 Inside 7 MS01B f:2 K7 Containment Auto Containment Isolation Phase A Failure 8 RP09B f:1 K0 (Train B)

Page 4 of 34 CPNPP June 2015 NRC Exam Scenario 2

Scenario Event Description June 2015 NRC Exam Scenario 2 Simulator Operator: INITIALIZE to IC08 and LOAD NRC Scenario 2.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE all Control Board Tags are removed.

ENSURE Operator Aid reflects current boron conditions (1669 ppm BOL).

ENSURE Rod Bank Update (RBU) is performed (C at 214 / D at 99).

ENSURE Turbine Load Rate set at 10 MWe/minute.

ENSURE 60/90 buttons DEPRESSED on ASD.

ENSURE ASD speakers are ON to half volume.

ENSURE Reactivity Briefing Sheet printout provided with Turnover (BOL).

ENSURE procedures in progress are on SRO desk:

- COPY of IPO-002A, Plant Startup From Hot Standby, Section 5.4, Increasing Reactor Power to Approximately 2% Following Reactor Startup and Establishing Main Feedwater Flow to the SGs AND Bubble Chart Page 5 provided.

ENSURE Control Rods are in MANUAL with Bank C at 214 steps and Bank D at 99 steps.

ENSURE PCS TT06 is set to GTGC MODE2 and on proper scale.

ENSURE Steam Dump Pot set at 6.70 Control Room Annunciators in Alarm:

1-ALB-6D-1.1 - SR HI VOLT FAIL 1-ALB-6D-3.1 - SR SHTDN FLUX ALM BLK PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.3 - AMSAC BLK TURB < 40% PWR C-20 PCIP-1.4 - CNDSR AVAIL STM DMP ARMED C-9 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.4 - LO TURB PWR ROD WITHDRWL BLK C-5 PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.5 - RX & TURB 10% PWR P-7 PCIP-4.5 - RX 48% PWR 3-LOOP FLO PERM P-8 PCIP-4.6 - TURB 10% PWR P-13 1-ALB-7B-1.6 - FW FLUSH VLV NOT CLOSE HV-2166 1-ALB-8A-1.10 - 1 OF 4 TURB STOP VLV CLOSE 1-ALB-10A-3.12 - GEN PRI WTR SYS TRBL 1-ALB-9A - Various Heater Drain and Extraction Steam Alarms Page 5 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 1 Page 6 of 34 Event

Description:

Raise Reactor Power to 2% to 3%

Time Position Applicants Actions or Behavior Examiner Note: The following steps are from IPO-002A, Plant Startup From Hot Standby, Section 5.4, Increasing Reactor Power to Approximately 2% Following Reactor Startup and Establishing Main Feedwater Flow to the SGs.

RO Withdraw control rods to establish a 0.5 dpm startup rate.

RO Reduce startup rate to 0.2 dpm at approximately 3 x 10-6 amps.

RO Verify Power Range channels begin to respond.

RO VERIFY Steam Dumps are maintaining temperature.

RO VERIFY 1-PCIP, 3.6 TAVE LO LO P-12 is OFF.

RO Maintain Reactor Power between 2% and 3%.

When the crew has demonstrated that they can maintain power stable between 2% and 3%, or at Lead Examiner discretion, PROCEED to Event 2.

Page 6 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 7 of 34 Event

Description:

Centrifugal Charging Pump (CCP) 1-01 trips.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 2 (Key 2).

- CV01B, Centrifugal Charging Pump (CCP) 1-01 trip.

Indications Available:

5A-1.6 - ANY RCP SEAL WTR INJ FLO LO 6A-1.7 - ANY CHG PMP OVRLOAD / TRIP 6A-3.4 - CHG FLO HI / LO 1-FI-121A, CHRG FLO lowers to zero (0) GPM 1/1-APCH1, CCP 1, amber MISMATCH and white TRIP lights LIT RO RESPOND to Annunciator Alarm Procedures.

RO RECOGNIZE Charging Pump 1-01 trip.

DIRECT performance of ABN-105, Chemical and Volume Control System US Malfunction, Section 3.0.

Examiner Note: The following steps are from ABN-105, Chemical and Volume Control System Malfunction, Section 3.0, Charging Pump Trip. The Diamond steps () are Initial Operator Actions.

Page 7 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 8 of 34 Event

Description:

Centrifugal Charging Pump (CCP) 1-01 trips.

Time Position Applicants Actions or Behavior RO START Centrifugal Charging Pump 1-02. [Step 3.3.1]

RO VERIFY at least one Charging Pump - RUNNING. [Step 3.3.2]

VERIFY Seal Injection Flow to each RCP - BETWEEN 6 GPM AND 13 RO GPM. [Step 3.3.3]

VERIFY RCP parameters in - NORMAL OPERATING RANGE.

RO

[Step 3.3.4]

Examiner Note: The crew will use the Plant Computer on screen GD RCP1(2,3,4) to monitor RCP parameters.

VERIFY PRZR level - GREATER THAN 17% AND INCREASING.

RO

[Step 3.3.5]

Simulator Operator: When contacted about status of Centrifugal Charging Pump 1-01, REPORT Phase B 50/51 overcurrent relays are tripped at the breaker and an acrid odor is present at the CCP.

Simulator Operator: When contacted, EXECUTE remote functions CVR05 and CVR06 for the Centrifugal Charging Pump (1-01 & 1-02) Auxiliary Lube Oil Pumps.

Page 8 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 9 of 34 Event

Description:

Centrifugal Charging Pump (CCP) 1-01 trips.

Time Position Applicants Actions or Behavior Examiner Note: In the event that Letdown was isolated in ABN-105, Step 1, the following steps will re-establish Letdown.

RO IF isolated in Step1, THEN establish normal Letdown: [Step 3.3.6]

OPEN Letdown Isolation Valves: [Step 3.3.6.a ]

1/1-LCV-460, LTDN ISOL VLV 1/1-LCV-459, LTDN ISOL VLV 1/1-8152, LTDN CNTM ISOL VLV ORC 1/1-8160, LTDN CNTMT ISOL VLV IRC Manually OPEN 1-PK-131, LTDN HX OUT PRESS CTRL to 30%

demand (50% if restoring two orifice valves). [Step 3.3.6.b]

Manually OPEN 1-TK-130, LTDN HX OUT TEMP CTRL to 50%demand.

[Step 3.3.6.c]

ADJUST charging to desired flow and MAINTAIN seal injection flow between 6 and 14 gpm. [Step 3.3.6.d] ~100 gpm OPEN selected Letdown Orifice Isolation Valves(s). [Step 3.3.6.e]

1/1-8149A, LTDWN ORIFICE ISOL VLV (45 gpm) 1/1-8149B, LTDWN ORIFICE ISOL VLV (75 gpm) 1/1-8149C, LTDWN ORIFICE ISOL VLV (75 gpm)

ADJUST 1-PK-131, LTDN HX OUT PRESS CTRL to ~310 psig on 1-PI-131, LTDN HX OUT PRESS then PLACE in AUTO. [Step 3.3.6.f]

ADJUST 1-TK-130, LTDN HX OUT TEMP CTRL to obtain ~95ºF on 1-TI-130, LTDN HX OUT TEMP, then PLACE in AUTO. [Step 3.3.6.g]

RO VERIFY RCS leakage - NORMAL: [Step 3.3.7]

VERIFY PRZR level stable at or trending to program. [Step 3.3.7.a]

VERIFY Charging flow less than 15 gpm above Letdown flow.

[Step 3.3.7.b]

US EVALUATE Technical Specifications. [Step 3.3.8]

LCO 3.5.2, ECCS - Operating.

CONDITION A - One train inoperable because of the inoperability of a centrifugal charging pump.

ACTION A.1 - Restore pump to OPERABLE status within 7 days.

Page 9 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 10 of 34 Event

Description:

Centrifugal Charging Pump (CCP) 1-01 trips.

Time Position Applicants Actions or Behavior US EVALUATE Technical Requirements Manual. [Step 3.3.8]

LCO 13.1.31, Two boration injection subsystems shall be OPERABLE.

CONDITION B - One charging pump inoperable.

ACTION B.1 - Restore charging pump to OPERABLE status within 7 days.

US INITIATE a work request per STA-606. [Step 3.3.9]

US INITIATE a SMART Form per STA-421. [Step 3.3.10]

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 3.

Page 10 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 11 of 34 Event

Description:

PT-455 PRZR Pressure fails high.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 3 (Key 3).

- RX08A, Pressurizer Pressure Channel (PT-455) fails high.

Indications Available:

5C-1.4 - PORV 455A/456 NOT CLOSE 5C-3.1 - PRZR 1 OF 4 PRESS HI 5C-4.3 - PRZR PRESS DEV HI PRZR variable heaters turn OFF.

Both PRZR spray valves OPEN.

PORV OPENs and then closes once pressure reduces to 2185 psig.

RO RESPOND to Annunciator Alarm Procedures.

RO RECOGNIZE PRZR pressure channel PT-455A has failed high.

DIRECT performance of ABN-705, Pressurizer Pressure Malfunction, US Section 2.0.

Examiner Note: The following steps are from ABN-705, Pressurizer Pressure Malfunction, Section 2.0, Pressurizer Pressure Instrument Malfunction. The Diamond steps

() are Initial Operator Actions.

VERIFY PORV - CLOSED. [Step 2.3.1]

RO Place PRZR PORV, 1/1-PCV-455A to CLOSE Place PRZR PORV BLK VLV, 1/1-8000A to CLOSE RO PLACE 1-PK-455A, PRZR MASTER PRESS CTRL in MANUAL. [Step 2.3.2]

RO ADJUST 1-PK-455A for current RCS pressure. [Step 2.3.3]

Examiner Note: DNB Tech Spec (TS 3.4.1) may be entered based on plant response due to failed channel; however, it is not applicable in Mode 2.

Page 11 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 12 of 34 Event

Description:

PT-455 PRZR Pressure fails high.

Time Position Applicants Actions or Behavior TRANSFER 1/1-PS-455F, PRZR PRESS CTRL CHAN SELECT to an RO Alternate Controlling Channel. [Step 2.3.4]

RO PLACE 1-PK-455A, PRZR MASTER PRESS CTRL in AUTO. [Step 2.3.5]

VERIFY automatic control restoring Pressurizer pressure to 2235 psig.

RO

[Step 2.3.6]

ENSURE valid channel selected on recorder 1/1-PS-455G, 1-PR-455 PRZR RO PRESS SELECT. [Step 2.3.7]

IF necessary, return PORV closed in Step 1 RNO to AUTO and ENSURE it US/RO remains closed. [Step 2.3.8]

US/RO IF necessary, OPEN block valve closed in Step 1 RNO. [Step 2.3.9]

Within one hour, VERIFY PCIP Window 2.6 - PRZR PRESS SI BLK PERM US/RO P DARK. [Step 2.3.10]

VERIFY other instruments on common instrument line - NORMAL.

US/RO

[Step 2.3.11]

Page 12 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 13 of 34 Event

Description:

PT-455 PRZR Pressure fails high.

Time Position Applicants Actions or Behavior US EVALUATE Technical Specifications. [Step 2.3.14]

LCO 3.3.1, Reactor Trip System Instrumentation (Function 6, Overtemperature N-16 & 8.b, Pressurizer Pressure High).

CONDITION E - One channel inoperable.

ACTION E.1 - Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , OR ACTION E.2 - Be in MODE 3 within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months .

Examiner Note: Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Function 8.a, Pressurizer Pressure LOW does not apply in current plant conditions. Must be in MODE 1 and above the P-7 (At Power Permissive) interlock for this Function to apply.

LCO 3.3.2, ESFAS Instrumentation (Function 1.d, Safety Injection, Pressurizer Pressure - Low).

CONDITION D - One channel inoperable.

ACTION D.1 - Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , OR ACTION D.2.1 - Be in MODE 3 within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months , AND ACTION D.2.2 - Be in MODE 4 within 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months .

LCO 3.3.2, ESFAS Instrumentation (Function 8.b, ESFAS Interlocks, Pressurizer Pressure - P-11).

CONDITION L - One or more required channel(s) inoperable.

ACTION L.1 - Verify interlock is in required state for existing unit condition within one hour, OR ACTION L.2.1 - Be in MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , AND ACTION L.2.2 - Be in MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

LCO 3.3.3, PAM Instrumentation (Function 2, Subcooling Monitors).

CONDITION A - One or more Functions with one required channel inoperable.

ACTION A.1 - Restore required channel to OPERABLE status.

US INITIATE a Condition Report per STA-421, as applicable.

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 4.

Page 13 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 14 of 34 Event

Description:

AFW Pump 1-02 trips. Turbine Driven AFW Pump manual start.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 4 (Key 4).

- FW24BA, Motor Driven Auxiliary Feedwater Pump (MDAFWP) 1-02 trip.

Indications Available:

8B-4.3 - MD AFWP 1/2 OVRLOAD/TRIP 1-HS-2451A, MD AFWP 2, amber MISMATCH and green PUMP lights LIT SGs 1-03 & 1-04 AFW FLO Indicators indicating (0) GPM (1-FI-2465A/C and 1-FI-2466A/C)

MD AFWP 2 CURRENT indicating (0) AMPS (1-II-2451)

MD AFWP 2 DISCH PRESS indicating (0) PSIG (1-PI-2454A)

MD AFWP 2 DISCH FLO indicating (0) GPM (1-FI-2457A)

SGs 1-03 & 1-04 LVL (NR) decreasing (1-LI-553/554 SGs 1-03/4 Controlling NR Channels)

RO/BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE trip of Motor Driven Auxiliary Feedwater Pump 1-02.

DIRECT performance of ABN-305, Auxiliary Feedwater System Malfunction, US Section 3.0, Motor Driven Auxiliary Feedwater Pump Malfunction.

Examiner Note: The following steps are from ABN-305, Auxiliary Feedwater System Malfunction, Section 3.0, Motor Driven Auxiliary Feedwater Pump Malfunction.

US/BOP Verify MD AFW Pump 1-02 has tripped. [Step 3.3.1]

BOP VERIFY MD AFW Pump 1-01 is running. [Step 3.3.2]

Page 14 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 15 of 34 Event

Description:

AFW Pump 1-02 trips. Turbine Driven AFW Pump manual start.

Time Position Applicants Actions or Behavior BOP Verify Steam Generator levels - NORMAL. [Step 3.3.3 RNO]

Start the Turbine Driven AFW Pump and feed Steam Generator 1-03 and 1-04.

Simulator Operator: When contacted, REPORT the breaker for MD AFW Pump 1-02 tripped on overcurrent.

Dispatch an NEO to check breaker status of MD AFW Pump 1-02.

US (Step 3.3.4]

1EA2/13/BKR, 1APMD2, AUXILIARY FEEDWATER PUMP 1-02 BKR (SFGD 852 Rm 1-103)

Verify MD AFW Pump 1-01 suction pressure greater than or equal to 10 psig.

BOP

[Step 3.3.5]

Simulator Operator: When contacted, REPORT that the motor casing for MD AFW Pump 1-02 is hot to the touch.

Dispatch an NEO to MD AFW Pump 1-02 Room to inspect pump condition.

US

[Step 3.3.6]

Pump casing and discharge piping at ambient temperature Pump and pump motor - NO APPARENT DAMAGE No excessive leakage Page 15 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 16 of 34 Event

Description:

AFW Pump 1-02 trips. Turbine Driven AFW Pump manual start.

Time Position Applicants Actions or Behavior If damage to motor or pump is apparent, or excessive leakage is found, then US refer to Technical Specification 3.7.5 for LCO. [Step 3.3.6 RNO step b for pump casing temperature]

LCO 3.7.5, Auxiliary Feedwater (AFW) System CONDITION B - One AFW train inoperable for reasons other than Condition A.

ACTION B.1 - Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

When Steam Generator Levels are being maintained between 60% and 75%, Technical Specifications have been addressed, or at Lead Examiner discretion, PROCEED to Event 5.

Page 16 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 17 of 34 Event

Description:

Shutdown Bank A (4 rods) drop.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 5 (Key 5).

- RD03B12

- RD03D2

- RD03M14

- RD03P4 Shutdown Bank A (4 rods) drops.

Indications Available:

6D-3.5, - DRPI ROD DEV 6D-3.7 - ANY ROD AT BOT 6D-4.7 - > 2 ROD AT BOT RO RECOGNIZE two or more rods dropped.

Examiner Note: Crew may recognize two or more rods dropped, manually trip the reactor and immediately enter EOP-0.0A, Reactor Trip or Safety Injection.

DIRECT performance of ABN-712, Rod Control System Malfunction, Section US 3.3, Dropped or Misaligned Rod in MODE 1 or 2.

Examiner Note: The following step is from ABN-712, Rod Control System Malfunction, Section 3.3, Dropped or Misaligned Rod in MODE 1 or 2.

Verify number of rods misaligned from step counter by > 12 steps is < ONE.

RO

[Step 3.3.1 RNO]

Trip Reactor and GO TO EOP-0.0A.

Page 17 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 18 of 34 Event

Description:

Shutdown Bank A (4 rods) drop.

Time Position Applicants Actions or Behavior Examiner Note: EOP-0.0A, Reactor Trip or Safety Injection steps begin here.

US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip: [Step 1]

VERIFY Reactor Trip Breakers - OPEN. [Step 1.a]

VERIFY Neutron flux - DECREASING. [Step 1.a]

VERIFY all Control Rod Position Rod Bottom Lights - ON.

[Step 1.b]

BOP VERIFY Turbine Trip: [Step 2]

VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2]

BOP VERIFY Power to AC Safeguards Busses: [Step 3]

VERIFY AC safeguards busses - AT LEAST ONE ENERGIZED

[Step 3.a]

AC safeguards bus voltage - 6900 Volts (6500 - 7100 Volts)

VERIFY AC safeguards busses - BOTH ENERGIZED RO CHECK SI status: [Step 4]

CHECK is SI is actuated. [Step 4.a RNO]

CHECK if SI is required:

Steam Line Pressure less 610 psig.

Pressurizer Pressure less than 1820 psig.

Containment Pressure greater than 3.0 psig.

IF SI is NOT required, THEN go to EOS-0.1A, REACTOR TRIP US RESPONSE, Step 1.

Page 18 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 19 of 34 Event

Description:

Shutdown Bank A (4 rods) drop.

Time Position Applicants Actions or Behavior Examiner Note: The crew will transition to EOS-0.1A, Reactor Trip Response.

RO CHECK RCS Temperature - [Step 1]

Check RCPs - ANY RUNNING [Step 1.a]

RCS temperature stable at or trending to 557°F [Step 1.b]

BOP Check FW Status: [Step 2]

VERIFY reactor trip breakers - OPEN [Step 2.a]

Check RCS average temperatures - LESS than 564°F. (Step 2.b]

VERIFY Feedwater Isolation - ISOLATION COMPLETE. [Step 2.c]

VERIFY total AFW flow to SGs - GREATER THAN 460 GPM.

[Step 2.d]

Upon completion of EOS-0.1A, Step 2.d, or at Lead Examiner's discretion, PROCEED to Event 6.

Page 19 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6 Page 20 of 34 Event

Description:

Loss of Offsite Power; DG 1-01 start failure; DG 1-02 requires manual start.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 6 (Key 6).

- ED01, Loss of Offsite Power.

- EG06A, DG 1-01 Air Start Failure.

- EG15B, DG 1-02 Fails to Auto or Emergency Start.

Indications Available:

10B-2.4 - 6.9KV ANY NON-1E BUS VOLTLOSS 10B-2.6 - 6.9KV BUS 1EA1/1EA2 VOLTLOSS Numerous Loss of Offsite Power Alarms.

RO/BOP RECOGNIZE Loss of Offsite Power conditions.

Examiner Note: The crew will enter ECA-0.0A, Loss of All AC Power.

US DIRECT performance of ECA-0.0A, Loss of All AC Power.

Examiner Note: The following steps are from ECA-0.0A, Loss of All AC Power.

RO VERIFY Reactor Trip: [Step 1]

VERIFY Reactor Trip Breakers - AT LEAST ONE OPEN. [Step 1]

VERIFY Neutron flux - DECREASING. [Step 1]

BOP VERIFY Turbine Trip: [Step 2]

VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2]

Page 20 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6 Page 21 of 34 Event

Description:

Loss of Offsite Power; DG 1-01 start failure; DG 1-02 requires manual start.

Time Position Applicants Actions or Behavior CRITICAL TASK Isolate Reactor Coolant System Leakage Paths in accordance with STATEMENT ECA-0.0A, Loss of All AC Power prior to initiation of Steam Generator depressurization.

RO CHECK If RCS Is Isolated: [Step 3]

CHECK Letdown Isolation Valves - CLOSED. [Step 3.a]

1/1-LCV-459 and 1/1-LCV-460 Examiner Note: The Letdown Isolation Valves are interlocked with the Letdown Orifice Isolation Valves. The Letdown Isolation Valves cannot be closed until the Letdown Orifice Isolation Valves are closed.

CRITICAL TASK RO CLOSE Letdown Isolation Valves. [Step 3.a RNO]

PLACE 1/1-LCV-459 AND 1/1-LCV-460, Letdown Isolation Valves in CLOSE. [Step 3.a RNO]

CHECK Pressurizer Power Operated Relief Valves - CLOSED.

RO

[Step 3.b]

RO CHECK Excess Letdown Isolation Valves - CLOSED. [Step 3.c]

1/1-8153 and 1/1-8154 RO CHECK Primary Sample System Isolation Valves - CLOSED. [Step 3.d]

1/1-4165A and 1/1-4167A CLOSE Primary Sample System Isolation Valves. [Step 3.d RNO]

PLACE 1-HS-4165A, Primary Sample System Isolation Valves in CLOSE. [Step 3.d RNO]

RO/BOP VERIFY AFW Flow - GREATER THAN 460 GPM: [Step 4]

Page 21 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6 Page 22 of 34 Event

Description:

Loss of Offsite Power; DG 1-01 start failure; DG 1-02 requires manual start.

Time Position Applicants Actions or Behavior CRITICAL TASK Restore Power to Bus 1EA2 in accordance with ECA-0.0A, Loss of All STATEMENT AC Power, prior to initiation of Steam Generator depressurization.

BOP RESTORE Power to Any AC Safeguards Bus: [Step 5]

ENERGIZE selected AC Safeguards Bus with Diesel Generator

[Step 5.a]

VERIFY selected Diesel Generator - RUNNING [Step 5.a.1]

Start selected diesel generator as follows: [Step 5.a.1 RNO]

Perform an Emergency Start. [Step 5.a.1 RNO Step A]

Examiner Note: The crew may select Diesel Generator 1-01 to start first; it will not start either normally or with an emergency start. The crew will then proceed to Diesel Generator 1-02; it will not start with an emergency start, however, it will start normally. The crew may also select Diesel Generator 1-02 to be started first.

CRITICAL If the diesel generator is NOT running, THEN perform a Normal TASK BOP Start. [Step 5.a.1 RNO Step B]

Examiner Note: When Diesel Generator 1-02 is started, the supply breaker will automatically CLOSE when the Diesel Generator is ready to accept load (~10 seconds).

Check selected diesel generator AC safeguards bus 1EA2 supply BOP breaker closed. [Step 5.a.2]

Check AC safeguards busses - AT LEAST ONE ENERGIZED

[Step 5.c]

Examiner Note: With Safeguards Bus 1EA2 now energized, crew will transition back to procedure and step in effect; EOS-0.1A, Reactor Trip Response, Step 3.

RO Check PRZR Level Control: [Step 3]

Level - GREATER THAN 17% [Step 3.a]

VERIFY charging - IN SERVICE [Step 3.b]

VERIFY letdown - IN SERVICE [Step 3.c RNO]

Examiner Note: Crew may discuss whether restoration of letdown is needed. Proceed to next event prior to any substantive action taken in Step 3.c of EOS-0.1A.

Page 22 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 23 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 7 (Key 7).

Main Steam Line Break on SG 1-02 inside containment.

Indications Available:

7A-1.12 - MSIV 1 NOT OPEN 7A-2.12 - MSIV 2 NOT OPEN 7A-3.12 - MSIV 3 NOT OPEN 7A-4.12 - MSIV 4 NOT OPEN 2B-1.10 - CNTMT 1 OF 3 PRESS HI-1 2B-2.10 - CNTMT 1 0F 3 PRESS HI-2 Numerous alarms associated with Main Steam Line Break inside containment RECOGNIZE lowering RCS temperature and pressure and rising RO/BOP containment pressure.

Examiner Note: Crew will transition from EOS-0.1A to EOP-0.0A, Reactor Trip or Safety Injection.

US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

Examiner Note: The following steps are from EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip: [Step 1]

VERIFY Reactor Trip Breakers - OPEN. [Step 1.a]

VERIFY Neutron flux - DECREASING. [Step 1.a]

VERIFY all Control Rod Position Rod Bottom Lights - ON. [Step 1.b]

BOP VERIFY Turbine Trip: [Step 2]

VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2]

BOP VERIFY Power to AC Safeguards Buses: [Step 3]

VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.

[Step 3.a]

VERIFY both AC Safeguards Buses - ENERGIZED. [Step 3.b]

Restore power to 1EA1 as time permits. [Step 3.b RNO]

Page 23 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 24 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior RO CHECK SI status: [Step 4]

CHECK if SI is actuated. [Step 4.a]

SI actuation indicated on First Out Annunciator 1-ALB-6C SI Actuated blue status light - ON RO VERIFY Both Trains SI Actuated: [Step 4.b]

SI Actuated - Alternate Indication (RHR Auto Switchover Lights Lit)

Examiner Note: EOP-0.0A, Attachment 2 steps performed by the BOP are identified on Page 29 of the scenario guide.

INITIATE Proper Safeguards Equipment Operation Per Attachment 2 US/BOP

[Step 5]

RO VERIFY AFW Alignment: [Step 6]

VERIFY MDAFW Pump 1 RUNNING [Step 6.a]

VERIFY Turbine Driven AFW Pump running. [Step 6.b]

VERIFY AFW total flow - GREATER THAN 460 gpm. [Step 6.c]

VERIFY AFW proper valve alignment [Step 6.d]

Page 24 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 25 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior RO VERIFY Containment Spray NOT Required: [Step 7]

VERIFY 1-ALB-2B, Window 1-8, CS ACT - NOT ILLUMINATED.

[Step 7.a]

VERIFY 1-ALB-2B, Window 4-11, CNTMT ISOL PHASE B ACT - NOT ILLUMINATED. [Step 7.a]

VERIFY Containment pressure - LESS THAN 18.0 psig. [Step 7.a]

VERIFY Containment Spray Heat Exchanger Outlet Valves - CLOSED.

[Step 7.b]

VERIFY Containment Spray Pumps 1-02 and 1 RUNNING.

[Step 7.c]

RO CHECK If Main Steamlines Should Be Isolated: [Step 8]

VERIFY Containment pressure - GREATER THAN 6.0 PSIG [Step 8.a]

VERIFY main steam isolation complete: [Step 8.b ]

VERIFY Main Steam isolation valves CLOSED. [Step 8.b]

VERIFY Before MSIV drippot isolation valves CLOSED. [Step 8.b]

RO CHECK RCS Temperature: [Step 9]

RCS AVERAGE TEMPERATURE STABLE AT OR TRENDING TO 557°F [Step 9 RNO]

RO STOP dumping steam. [Step 9 RNO Step a]

RO REDUCE total AFW flow to minimize the cooldown: [Step 9 RNO Step b]

MAINTAIN a minimum of 460 gpm UNTIL narrow range level greater than 50%

Page 25 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 26 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior RO CHECK PRZR Valve Status: [Step 10]

VERIFY PRZR Safeties - CLOSED. [Step 10.a]

VERIFY normal PRZR spray valves - CLOSED. [Step 10.b]

VERIFY PORVs - CLOSED. [Step 10.c]

VERIFY power to at least one block valve - AVAILABLE. [Step 10.d]

VERIFY block valves - AT LEAST ONE OPEN. [Step 10.e]

RO CHECK If RCPs Should Be Stopped: [Step 11]

RCS subcooling - LESS THAN 55°F FOR ADVERSE CONTAINMENT

[Step 11.a RNO]

RO/BOP CHECK If Any SG Is Faulted: [Step 12]

DETERMINE SG 1-02 is completely DEPRESSURIZED. [Step 12.a]

US TRANSITION to EOP-2.0A, Faulted Steam Generator Isolation, Step 1.

Examiner Note: The following steps are from EOP-2.0A, Faulted Steam Generator isolation.

RO CHECK Main Steamline Isolation Valves - CLOSED. [Step 1]

RO CHECK At Least One SG Pressure - STABLE OR INCREASING. [Step 2]

Page 26 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 27 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior CRITICAL TASK Identify and isolate the Faulted Steam Generator Prior to Exiting EOP-STATEMENT 2.0A, Faulted Steam Generator isolation.

CRITICAL RO/BOP IDENTIFY SG 1-02 as the Faulted Steam Generator. [Step 3]

TASK Simulator Operator Note: Crew may contact to locally close 1-HV-2492A, AFWIV 2. If contacted acknowledge report, wait 5 minutes and EXECUTE remote function - IRF FWR125 f:0 - then report the valve is closed.

RO/BOP ISOLATE Faulted Steam Generator 1-02. [Step 4]

ISOLATE main feedline to SG 1-02.

CRITICAL ISOLATE AFW flow to SG 1-02.

TASK IF SG 1 or 4 faulted, THEN place TDAFW Pump steam supply valve(s) in pull-out.

ISOLATE blowdown and sample lines to SG 1-02.

ENSURE SG 1-02 atmospheric - CLOSED.

ENSURE main steamline drippot isolation valve - CLOSED.

RO CHECK CST Level - GREATER THAN 10%. [Step 5]

US/BOP VERIFY Faulted SG 1-02 Break Inside Containment. [Step 6]

US/RO CHECK Secondary Radiation: [Step 7]

REQUEST periodic activity samples of all Steam Generators. [Step 7.a]

CHECK available secondary radiation monitors - NORMAL. [Step 7.b]

Page 27 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 28 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior US/RO CHECK If ECCS Flow Should Be Reduced: [Step 8]

VERIFY secondary heat sink: [Step 8.a]

Total AFW flow to intact SGs - GREATER THAN 460 GPM OR Narrow range level in at least one intact SG - GREATER THAN 50%.

VERIFY RCS subcooling - GREATER THAN 55°F. [Step 8.b]

VERIFY RCS pressure - STABLE OR INCREASING. [Step 8.c]

VERIFY PRZR level - GREATER THAN 34%. [Step 8.d]

US Go to EOS-1.1A, SAFETY INJECTION TERMINATION, Step 1

[Step 8.e]

Go to Step 9. [Step 8 RNO]

Examiner Note: It is possible that Step 8.b, c, and d will be AER and that the crew will transition to EOS-1.1A, Safety Injection Termination, depending on the timing, sequence of operator actions, and plant response. If the conditions to transition to EOS-1.1A are not met, the crew will transition to EOP-1.0A, Loss of Reactor or Secondary Coolant and eventually transition to EOS-1.1A when the conditions are met.

Go To EOP-1.0A, LOSS OF REACTOR OR SECONDARY COOLANT, US Step 1 [Step 9]

When EOP-0.0A Attachment 2 is complete AND the crew has transitioned out of EOP-2.0A, TERMINATE the scenario.

Page 28 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 29 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior Examiner Note: These steps are performed by the BOP per EOP-0.0, Reactor Trip or Safety Injection, Attachment 2 Examiner Note: Train A Safeguards Bus, 1EA1, is de-energized. Train A equipment will not be running.

BOP VERIFY SSW Alignment: [Step 1]

VERIFY SSW Pump 1 RUNNING. [Step 1.a]

VERIFY EDG Cooler SSW return flow. [Step 1.b]

BOP VERIFY Safety Injection Pump 1 RUNNING. [Step 2]

Examiner Note: Event 8, Auto Containment Isolation Phase A Actuation Failure on Train B, should be diagnosed at the next step of Attachment 2. Manual initiation of Phase A on the B Train will be required.

VERIFY Containment Isolation Phase A - APPROPRIATE MLB LIGHT BOP INDICATION (RED WINDOWS). [Step 3]

Manually Initiate Phase A, Train B VERIFY Containment Ventilation Isolation - APPROPRIATE MLB LIGHT BOP INDICATION (GREEN WINDOWS). [Step 4]

BOP VERIFY CCW Pump 1 RUNNING. [Step 5]

BOP VERIFY RHR Pump 1 RUNNING. [Step 6]

Page 29 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 30 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior BOP VERIFY Proper CVCS Alignment: [Step 7]

VERIFY CCP 1 RUNNING. [Step 7.a]

VERIFY Letdown Relief Valve Isolation: [Step 7.b]

Letdown Orifice Isolation Valves - CLOSED. [Step 7.b.1)]

Letdown Isolation Valves 1/1-LCV-459 & 1/1-LCV-460 - CLOSED.

[Step 7.b.2)]

BOP VERIFY ECCS flow: [Step 8]

CCP SI flow indicator - CHECK FOR FLOW. [Step 8.a]

RCS pressure - LESS THAN 1700 PSIG (1800 PSIG FOR ADVERSE CONTAINMENT). [Step 8.b]

SIP discharge flow indicator - CHECK FOR FLOW. [Step 8.c]

RCS pressure - LESS THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT). [Step 8.d]

GO to Step 9. [Step 8.d RNO]

BOP VERIFY Feedwater Isolation Complete: [Step 9]

Feedwater Isolation Valves - CLOSED.

Feedwater Isolation Bypass Valves - CLOSED.

Feedwater Bypass Control Valves - CLOSED.

Feedwater Control Valves - CLOSED.

BOP VERIFY Diesel Generator 1 RUNNING. [Step 10]

BOP VERIFY Monitor Lights for SI Load Shedding on 1-MLB-9 and 1-MLB LIT. [Step 11]

Page 30 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 31 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior VERIFY Proper SI alignment - PROPER MLB LIGHT INDICATION.

BOP

[Step 12]

BOP INITIATE periodic monitoring of Spent Fuel Cooling. [Step 13]

Spent Fuel Pool temperature (T2900A, T2901A).

Spent Fuel Pool level (L4800A, L4801A, L4802A, L4803A).

BOP VERIFY Components on Table 1 are Properly Aligned. [Step 14]

Location Equipment Description Condition CB-03 X-HS-5534 H2 PRG SPLY FN 4 STOPPED CB-03 X-HS-5532 H2 PRG SPLY FN 3 STOPPED CB-04 1/1-8716A RHRP 1 XTIE VLV OPEN CB-04 1/1-8716B RHRP 2 XTIE VLV OPEN CB-06 1/1-8153 XS LTDN ISOL VLV CLOSED/H.S. IN CLOSED CB-06 1/1-8154 XS LTDN ISOL VLV CLOSED/H.S. IN CLOSED CB-07 1/1-RTBAL RX TRIP BKR OPEN CB-07 1/1-RTBBL RX TRIP BKR OPEN CB-07 1/1-BBAL RX TRIP BYP BKR OPEN/DEENERGIZED CB-07 1/1-BBBL RX TRIP BYP BKR OPEN/DEENERGIZED CB-08 1-HS-2397A SG 1 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2111C FWPT A TRIP TRIPPED CB-08 1-HS-2112C FWPT B TRIP TRIPPED Page 31 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 32 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior CB-09 1-HS-2490 CNDS XFER PUMP STOPPED (MCC deenergized on SI)

CV-01 X-HS-6181 PRI PLT SPLY FN 17 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6202 PRI PLT SPLY FN 20 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6209 PRI PLT SPLY FN 21 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6216 PRI PLT SPLY FN 22 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6223 PRI PLT SPLY FN 23 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6230 PRI PLT SPLY FN 24 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-3631 UPS & DISTR RM A/C FN 1 & STARTED BSTR FN 42 CV-01 X-HS-3632 UPS & DISTR RM A/C FN 2 & STARTED BSTR FN 43 CV-01 1-HS-5600 ELEC AREA EXH FN 1 STOPPED/DEENERGIZED CV-01 1-HS-5601 ELEC AREA EXH FN 2 STOPPED/DEENERGIZED CV-01 1-HS-5602 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 3 & EXH DMPR CV-01 1-HS-5603 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 4 & EXH DMPR CV-01 1-HS-5618 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 17 CV-01 1-HS-5620 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 18 CV-03 X-HS-5855 CR EXH FN 1 STOPPED/DEENERGIZED CV-03 X-HS-5856 CR EXH FN 2 STOPPED/DEENERGIZED CV-03 X-HS-5731 SFP EXH FN 33 STOPPED/DEENERGIZED CV-03 X-HS-5733 SFP EXH FN 34 STOPPED/DEENERGIZED CV-03 X-HS-5727 SFP EXH FN 35 STOPPED/DEENERGIZED CV-03 X-HS-5729 SFP EXH FN 36 STOPPED/DEENERGIZED Page 32 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7 Page 33 of 34 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior Examiner Note: The next four (4) steps would be performed on Unit 2.

CB-03 2-HS-5538 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5539 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5537 AIR PRG SPLY ISOL DMPR CLOSED CB-03 2-HS-5536 AIR PRG SPLY ISOL DMPR CLOSED NOTIFY Unit Supervisor attachment instructions complete AND to BOP IMPLEMENT FRGs as required. [Step 14]

EOP-0.0A, Attachment 2 steps are now complete.

Page 33 of 34 CPNPP June 2015 NRC Exam Scenario 2

Scenario Event Description June 2015 NRC Exam Scenario 2

CPNPP 2015 NRC Initial Scenario 2

Load IC08

INITIAL SETUP

DG A fail to start auto or manual (Event 6)

IMF EG06A f:1

DG B fail to auto start (Event 6)

IMF EG15B f:1

Phase A Auto Isol Fail, Train B (Event 8)

IMF RP09B f:1

MALFUNCTIONS

CCP 1-01 Trip (Event 2)

IMF CV01B f:1 k:2

PZR press PT-455 fails high (Event 3)

IMF RX08A f:2500 k:3

AFW pump 1-02 trip (Event 4)

IMF FW24B f:1 k:4

SD Bank A Group 1 Rods drop (Event 5)

IMF RD03B12 f:1 k:5 IMF RD03D2 f:1 k:5 IMF RD03M14 f:1 k:5 IMF RD03P4 f:1 k:5

Loss Offsite Power (Event 6)

IMF ED01 f:1 k:6

Main Steam Line break IRC SG 1-02 (Event 7)

IMF MS01B f:2 k:7 Page 34 of 34 CPNPP June 2015 NRC Exam Scenario 2

Appendix D Scenario Outline Form ES-D-1 June 2015 NRC Exam Facility: CPNPP 1 & 2 Scenario No.: 3 Op Test No.: June 2015 Examiners: Operators:

Initial Conditions: 100% power, EOL. SI Pump 1-02 tagged out for inspection.

Turnover: SI Pump 1-02 returned to service in approx. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Critical Tasks: Place EHC Pumps in PULL OUT or Manually Close MSIVs Upon Failure of Main Turbine Trip Prior to Exiting EOP-0.0A, Reactor Trip or Safety Injection.

Manually Start Safety Injection Pump 1-01 Prior to completing Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection.

Identify and isolate the Ruptured Steam Generator Prior to Commencing an Operator Induced Cooldown per EOP-3.0A.

Event No. Malf. No. Event Type* Event Description 1 I - RO NI42 Power Range Channel fails high.

NI04E TS - SRO 2 C - BOP TP01 TPCW leak. Auto makeup fails.

C - SRO 3 I - RO RX05B PZR LT-460 fails low. Letdown isolates.

TS - SRO 4 FW16 C - BOP CEV pump trips. Manually start alternate.

FW17A C - SRO R - RO 5 SG 1-02 tube leak. Down power per ABN-106.

SG01B N - BOP, TS - SRO 6 M - ALL SG02B SG 1-02 tube rupture.

7 C - BOP Turbine fails to auto trip. Manual trip not successful. EHC pumps TC07C to Pull Out.

8 C - BOP SI04C SI Pump 1-01 fails to Auto start.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 7 Total malfunctions (5-8) 2 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) 3 Critical tasks (2-3)

Page 1 of 42 CPNPP NRC 2015 Simulator Scenario 3

Scenario Event Description NRC Scenario 3 SCENARIO 3

SUMMARY

Event 1 The first event is failure high of NI42 Power Range Channel. The crew will enter ABN-703, Power Range Instrumentation Malfunction. Since the failure is in the high direction, rods will be rapidly inserting. This will require the operator to place rod control to Manual, per Step 1.b of ABN-703. The SRO will refer to Technical Specifications.

Event 2 The next event is initiation of a leak in the Turbine Plant Cooling Water system at 15 gpm. The normal makeup valve (1-HS-3050 Makeup Valve) fails to auto open. Requires manual makeup, as directed by 1-ALB-9A, Window 2.10, TPCW HEAD TK LVL LO. This manual makeup operation will be successful, and alarm will clear as level restores.

Event 3 Once the TPCW Head Tank level is restored, the next event is a low failure of PZR LT-460. This failure causes letdown to isolate and a loss of the pressurizer heaters. The crew will enter ABN-706, Section 2.0, Pressurizer Level Instrument Malfunction, and per Step 1 and 2, manually control PZR level and reenergize PZR heaters.

The SRO will refer to Technical Specifications.

Event 4 The operating Condenser Exhaust Vacuum (CEV) pump trips. The crew will observe megawatts lowering and condenser vacuum lowering. They will also receive an alarm (1-ALB-9A, Window 1.12, CNDSR ANY VAC PMP TRIP, for the actual trip of the vacuum pump. They will also enter ABN-304, Section 3.0, Main or Auxiliary Condenser vacuum Decreasing, and manually start the alternate CEV pump. The crew may slightly reduce turbine load.

Event 5 A tube leak (10 gpm) will develop on SG 1-02. The crew will enter ABN-106, Section 3.0, Steam Generator Tube Leakage Greater than or equal to 75 gpd (0.52 gpm). They will recognize per the procedure, that a reduction in power is required. This evolution is intended to satisfy the reactivity manipulation requirement and normal evolution for this scenario. The SRO will refer to Technical Specifications.

Event 6 As the power reduction progresses, the tube leak on SG 1-02 worsens to a tube rupture event. The crew will recognize the change in leakage and conclude that a manual reactor trip is warranted. The reactor will be manually tripped, but the turbine will fail to auto trip. The crew enters EOP-0.0A, Reactor Trip or Safety Injection.

Event 7 The Main Turbine fails to auto trip. The Manual trip is NOT successful. This will require the operator to place the EHC pumps to PULL OUT or manually close the MSIVs, per Immediate Action Step 2, RNO.

Event 8 When safety injection is actuated in response to the SG Tube Rupture SI Pump 1-01 will fail to auto start. The operator performing EOP-0.0A, Attachment 2 should start the pump. The crew will continue through EOP-0.0A, and transition EOP-3.0A, Steam Generator Tube Rupture. When the ruptured Steam Generator 1-02 is isolated, including stopping Auxiliary Feedwater flow, the scenario can be terminated.

Risk Significance:

Failure or risk important system prior to trip: Steam Generator Tube Leak Main Turbine Fails to Trip Risk significant core damage sequence: SG tube leak leads to tube rupture event Two stuck rods on reactor trip Risk significant operator actions: Place Turbine EHC Pumps to PULL OUT Initiate Emergency Boration for stuck rods Identify and isolate ruptured Steam Generator Page 2 of 42 CPNPP NRC 2015 Simulator Scenario 3

Scenario Event Description NRC Scenario 3 Critical Task Determination Critical Task Safety Cueing Measurable Performance Significance Performance Feedback Indicators Place EHC Pumps Recognize a failure Procedural direction at The operator will EHC fluid pressure in PULL OUT or or an incorrect EOP-0.0A Step 2 to manually place all lowering and Manually Close automatic determine if a turbine trip EHC pumps position indication MSIVs Upon actuation of an has occurred. Position handswitch on for HP Turbine Stop Failure of Main ESF system or indication of the HP CB-10 to pull out. Valves indicating Turbine Trip Prior to component. Turbine Stop Valves as Or Isolate Main closed.

Exiting EOP-0.0A, still open. Steam lines on Reactor Trip or CB07.

Safety Injection.

Manually Start Recognize a failure Procedural direction per The operator will Indication of pump Safety Injection or an incorrect EOP-0.0A Attachment 2 manually start SI start including light Pump 1-01 Prior to automatic to start SI Pump 1-01. Pump 1-01. indication, pressure completing actuation of an Pump indication lights, and flow. of ESF system or flow and discharge EOP-0.0A, Reactor component. pressure.

Trip or Safety Injection.

Identify and isolate Take one or more Procedurally driven from The operator will SG pressure the Ruptured actions that would EOP-3.0A, to identify close the MSIV increasing, AFW Steam Generator prevent a and isolate a ruptured and stop feeding flow reduced to Prior to challenge to plant SG. Indications include the SG once zero and valve Commencing an safety. MSL Radiation alarms sufficient level to position indications.

Operator Induced and SG level. cover the tubes is Cooldown per EOP- available.

3.0A.

Page 3 of 42 CPNPP NRC 2015 Simulator Scenario 3

Scenario Event Description NRC Scenario 3 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC #20 and LOAD NRC Scenario 3.

REM. DESCRIPTION DEMAND INITIATING EVENT MALF.

FUNC. VALUE PARAMETER Main Turbine fails to auto trip. Also defeats SETUP TC07C f:1 K0 manual turbine trip pushbutton.

SI04C SI Pump 1-01 fails to auto start f:1 K0 DITPHS TPCW Fill Handswitch auto override prevents 2 IOR auto make up to surge tank. f:0 K0 3050 SSPS TR A MASTER RELAY K504 FAILURE 7 SS02A1 f:1 K0

[OPEN, MSL ISO]

SSPS TR B MASTER RELAY K504 FAILURE 7 SS02A2 f:1 K0

[OPEN, MSL ISO]

1 NI04E NI42 Power Range Channel fails high f:200 K1 2 TP01 TPCW Leak (1) f:15 K2 CMR5 Demin Wtr Trans Pmp 2, start when if 2 f:3 K10 1 required.

3 RX05B PZR LT-460 fails low. f:0 K3 4 FW16 Main Condenser Air Inleakage f:2 K4 4 FW17A Main Condenser Vacuum Pump Trip f:1 K4 5 SG01B SG 1-02 tube leak f:10 K5 6 SG02B SG 1-02 tube rupture f:1 K6 Main Turbine fails to auto trip. Also defeats 7 TC07C f:1 K0 manual turbine trip pushbutton.

SSPS TR A MASTER RELAY K504 FAILURE 7 SS02A1 f:1 K0

[OPEN, MSL ISO]

SSPS TR B MASTER RELAY K504 FAILURE 7 SS02A2 f:1 K0

[OPEN, MSL ISO]

8 SI04C SI Pump 1-01 fails to auto start f:1 K0 (1) Delete override and leak when RO fills using 1-HS-3050:

{DITPHS3050.Value=2} DOR DITPHS3050

{DITPHS3050.Value=2} DMF TP01 Page 4 of 42 CPNPP NRC 2015 Simulator Scenario 3

Scenario Event Description NRC Scenario 3 Simulator Operator: INITIALIZE to IC #20 and LOAD NRC Scenario 3.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE all Control Board Tags are removed.

ENSURE Operator Aid Tags reflect current boron conditions.

ENSURE Rod Bank Update (RBU) is performed.

ENSURE Turbine Load Rate set at 10 MWe/minute.

ENSURE 60/90 buttons DEPRESSED on ASD.

ENSURE ASD speakers are ON to half volume.

ENSURE Reactivity Briefing Sheet printout provided with Turnover.

ENSURE procedures in progress are on SRO desk:

COPY of IPO-003A, Power Operations, Section 5.5, Operating at Constant Turbine Load.

ENSURE Control Rods are in AUTO with Bank D at 215 steps.

ENSURE GEM Sign Posting Log for SIP 1-02 is provided with Turnover.

PLACE SIP 1-02 handswitch in PULL OUT, affix a danger tag to the handswitch.

ENSURE SIP 1-02 Breaker is racked out IRF SIR01 f:0.

PLACE GEM Cover on train A SIP handswitch.

CHANGE Delta I target to -4.9 using Delta Flux Option #5, change the target to -4.9, then depress ENTER, then save. Ensure the computer updated.

When the scenario has been run for the last time, ENSURE the plant computer is updated for the MOL Delta I target of -3.10%.

ENSURE the EOL AFD Job Aid on CB-07 is displayed.

Control Room Annunciators in Alarm:

PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.2 - IR TRN A RX TRIP BLK PCIP-1.4 - CNDSR AVAIL STM DMP ARMED C-9 PCIP-1.6 - RX 10% PWR P-10 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.2 - IR TRN B RX TRIP BLK PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.2 - PR TRN A LO SETPT RX TRIP BLK PCIP-4.2 - PR TRN B LO SETPT RX TRIP BLK SSII-TRN B-1.2 - ECCS Page 5 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 1 Page 6 of 42 Event

Description:

N42 Power Range Channel Fails High Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 1 (Key 1).

NI42 Power Range Channel fails high. IMF NI04E f:200 k:1 Indications Available:

1 OF 4 OT N-16 HI (5C-2.5) 1 OF 4 HI SETPT PR FLUX HI (6D-1.3) 1 OF 4 LO SETPT PR FLUX HI (6D-2.3) 1 OF 4 PR FLUX RATE HI (6D-3.3)

RX _50% PWR UP PR DET FLUX DEV HI (6D-1.4)

PR CHAN DEV (6D-3.4)

QUADRANT PWR TILT (6D-4.10)

OP HI FLUX ROD STOP C-2 (6D-2.14)

RO REFER to Annunciator Alarm Procedures.

RO RECOGNIZE Power Range Nuclear Instrument N-42 detector failure.

Examiner Note: If a Power Range Channel fails HIGH while the Rod Control System is in AUTO, Control Rods will be rapidly inserted.

DIRECT implementation of ABN-703, Power Range Instrumentation US Malfunction, Section 2.0.

RO VERIFY rapid Control Rod insertion - NOT REQUIRED. [Step 2.3.1]

VERIFY Reactor and Turbine Power - MATCHED.

[Step 2.3.1.a]

VERIFY TAVE less than 3°F above TREF. [Step 2.3.1.a]

PLACE Rod Control in MANUAL. [Step 2.3.1.b]

RO VERIFY Reactor Power < 75% rated thermal power. [Step 2.3.2]

INITIATE actions to comply with Technical Specification SR 3.2.4.2.

US

[Step 2.3.2 RNO ]

PERFORM at Channel N-42 Drawers: [Step 2.3.3 ]

At Detector Current Comparator Drawer, SELECT Rod Stop Bypass RO/BOP Switch to N-42. [Step 2.3.3.a ]

Page 6 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 1 Page 7 of 42 Event

Description:

N42 Power Range Channel Fails High Time Position Applicants Actions or Behavior At Comparator and Rate Drawer, SELECT Comparator Channel Defeat RO/BOP Switch to N-42. [Step 2.3.3.b ]

At Detector Current Comparator Drawer, SELECT Upper Section Switch RO/BOP to N-42. [Step 2.3.3.c ]

At Detector Current Comparator Drawer, SELECT Lower Section Switch RO/BOP to N-42. [Step 2.3.3.d ]

At Detector Current Comparator Drawer, SELECT Power Mismatch RO/BOP Bypass Switch to N-42. [Step 2.3.3.e]

At the Power Range A Drawer, SELECT Rate Mode Switch momentarily RO/BOP to RESET for N-42. [Step 2.3.3.f]

PLACE 1/1-JS-411E, N16 PWR CHAN DEFEAT Switch to LOOP 2.

RO/BOP

[Step 2.3.3.g]

PLACE 1/1-TS-412T, TAVE CHAN DEFEAT Switch to LOOP 2.

RO/BOP

[Step 2.3.3.g]

PLACE 1/1-TS-411E, 1-TR-411 Channel Select to an OPERABLE channel.

RO/BOP

[Step 2.3.4]

RO RESTORE TAVE to within 1ºF of TREF. [Step 2.3.5]

Page 7 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 1 Page 8 of 42 Event

Description:

N42 Power Range Channel Fails High Time Position Applicants Actions or Behavior Verify WITHIN 1 Hour, of Instrument Malfunction, Interlocks in - REQUIRED US/RO STATE: [Step 2.3.6]

RX & TURB 10% PWR P-7 (PCIP - 3.5) - DARK. [Step 2.3.6.a]

RX 48% PWR 3-LOOP FLO PERM P-8 (PCIP - 4.5) - DARK.

[Step 2.3.6.a]

RX 50% PWR TURB TRIP PERM P-9 (PCIP - 1.7) - DARK.

[Step 2.3.6.a]

RX 10% PWR P-10 (PCIP - 1.6) - LIT. [Step 2.3.6.a]

US/RO RECORD verification in Unit Log. [Step 2.3.6.b]

US/RO CHECK Quadrant Power Tilt Ratio within limits: [Step 2.3.7]

CHECK Power Range Channels- ONE OR MORE INOPERABLE

[Step 2.3.7.a]

CHECK Reactor Power - GREATER THAN 50%. [Step 2.3.7.b]

REFER to TS 3.2.4, Table 3.3.1-1, Items 2, 3 (ACTIONS D and E) and TR 13.2.33. [Step 2.3.7.c]

Page 8 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 1 Page 9 of 42 Event

Description:

N42 Power Range Channel Fails High Time Position Applicants Actions or Behavior US EVALUATE Technical Specifications. [Step 2.3.10]

LCO 3.3.1.D, Reactor Trip System Instrumentation (Function 2.a, Power Range Neutron Flux High)

CONDITION D - One Power Range Neutron Flux-High channel inoperable.

ACTION D.1.1 - Perform SR 3.2.4.2 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery of THERMAL POWER> 75% RTP, AND ACTION D.1.2 - Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , OR ACTION D.2 - Be in MODE 3 within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months .

LCO 3.3.1.E, Reactor Trip System Instrumentation (Function 3.a, Power Range Neutron Flux Rate High Positive Rate)

CONDITION E - One channel inoperable.

E.1 - Place Channel in Trip in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

OR E.2 - Be in MODE 3 in 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months .

LCO 3.3.1.S, Reactor Trip System Instrumentation (Function 18.e, Power Range Neutron Flux, P-10)

CONDITION S - One or more required channel(s) inoperable.

ACTION S.1 - Verify interlock is in the required state for existing unit conditions within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , OR ACTION S.2 - Be in MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

LCO 3.3.1.T, Reactor Trip System Instrumentation.

(Function 18.b, c, & d, Power Range Neutron Flux, P-7, P-8, & P-9)

CONDITION T - One or more required channel(s) inoperable.

ACTION T.1 - Verify interlock is in the required state for existing unit conditions within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION T.2 - Be in MODE 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

US INITIATE a Condition Report per STA-421. [Step 2.3.11]

US INITIATE repairs per STA-606. [Step 2.3.12]

When the Technical Specification actions are addressed, or at Lead Evaluators discretion, PROCEED to Event 2.

Page 9 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2 Page 10 of 42 Event

Description:

TPCW Leak, Auto Fill Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 2 (Key 2).

- TP01, TPCW leak. Auto makeup fails.

Indications Available:

1-ALB-9A, Window 2.10, TPCW HEAD TK LVL LO 1-LI-3051. TPCW HEAD TK LVL lowering.

1-HS-3050, TPCW HEAD TK MAKEUP VLV - NOT open.

BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE failure to auto makeup (1-HS-3050).

US DIRECT performance of 1ALB-9A.

ENSURE 1-HS-3050, TPCW HEAD TK MAKEUP VLV is open. [Step 1]

A. IF all handswitch light indications are off, THEN DISPATCH an operator BOP to 1-TC-21 FB1 Fuses 21 and 23 to check for a blown control power fuse.

VERIFY at least one demineralized water transfer pump is in service.[Step 2.]

BOP X-ZL-5327, DEMIN WTR XFER PMP 1 X-ZL-5328, DEMIN WTR XFER PMP 2 Page 10 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2 Page 11 of 42 Event

Description:

TPCW Leak, Auto Fill Failure Time Position Applicants Actions or Behavior MONITOR 1-LI-3051, TPCW HEAD TK LVL.[Step 3.]

A. IF TPCW head tank level is < 63%, THEN DISPATCH an operator to TB 830 to fill the head tank by opening 1TW-0203, TPCW HEAD TK 1-01 BOP DWS IN LVL CTRL VLV 3050 BYP VLV.

B. IF level continues to decrease, THEN GO to ABN-306 for Excessive TPCW System Leakage.

Simulator Operator Note: When dispatched to find leakage, wait 2 minutes and then report, 1TW-0222, TPCW Pump 1-02 DISCH DRN VLV was partially open as it was bumped by personnel moving equipment around the 1-02 TPCW Pump. The valve has been closed ENSURE 1-HS-3050 has been opened prior to report.

DELETE malfunction TP01.

Examiner Note: The ALM provides all steps necessary to respond to the TPCW malfunction.

The US could determine entry into ABN-306, Turbine Plant Cooling Water System Malfunction, Section 2.0, Excessive TPCW System Leakage, is necessary, the steps begin below. The steps of ABN-306 may not all be performed, for example, the US may determine that starting the second Demineralized Water Transfer pump is not required. Additionally there is no TPCW chemical addition in progress, nor is Main Generator leakage indicated. Therefore the steps of the ABN are listed as a contingency.

BOP Verify TPCW Head Tank Level is Trending Higher. [Step 2.3.1 2nd Bullet]

BOP Verify TPCW Head Tank Level-Greater than or equal to 50%. [Step 2.3.2]

Check Main Generator - NO IN-LEAKAGE, locally check Main Generator BOP Liquid Level detectors at seal oil rack (TB 803 Rm 1-008) - NO LIQUID

[Step 3 a.]

BOP Verify GEN GAS MOISTURE HI alarm (10A-1.10) - DARK. [Step 2.3.3 b.]

Page 11 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2 Page 12 of 42 Event

Description:

TPCW Leak, Auto Fill Failure Time Position Applicants Actions or Behavior Ensure makeup aligned to the TPCW Head Tank, 1-HS-3050, TPCW HEAD BOP TK MAKEUP VLV, - OPEN. [Step 2.3.4 a.]

Simulator Operator Note: When dispatched to start the second demineralized water transfer pump, wait 3 minutes and then activate key 10 to insert the remote function to start demineralized water transfer pump X-02.

IRF CMR51 f:3 k:10 BOP BOTH Demineralized Water Transfer Pumps - Running [Step 2.3.4 b.]

Dispatch Nuclear Equipment Operators to inspect TPCW System for leaks.

BOP

[Step 2.3.5]

BOP Verify Chemical Addition to TPCW - SECURED. [Step 2.3.6]

Verify TPCW Head Tank level - STABLE AT OR TRENDING TO NORMAL.

BOP

[Step 7]

Verify TPCW System aligned for normal operation per SOP-313A/B.

BOP

[Step 2.3.8]

US Initiate repair per STA-606. [Step 2.3.9]

US Initiate a Condition Report per STA-421 as applicable. [Step2.3.10]

When the TPCW Head Tank level alarm is clear, or at Lead Examiner discretion, PROCEED to Event 3.

Page 12 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 3 Page 13 of 42 Event

Description:

PZR LT-460 fails low. Letdown isolates.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 3 (Key 3).

- RX05B, Pressurizer Level Transmitter (LT-460) fails low.

Indications Available:

1-ALB-5B, Window 1.4, PRZR HTR GRP C CTRL TRBL 1-ALB-5B, Window, 3.6, PRZR LVL LO 1-ALB-5C, Window 1.2, PRZR LVL DEV LO 1-ALB-6A, Window 3.8, CVCS HELB PT-5358A 1-ALB-6A, Window 4.8, CVCS HELB PT-5358 1-LI-460A, PRZR LVL CHAN II indication failed low RO RESPOND to Annunciator Alarm Procedures.

RECOGNIZE PZR level lowering and REPORT Pressurizer Level Channel II (LT-460) failed low.

DIRECT performance of ABN-706, Pressurizer Level Instrumentation US Malfunction, Section 2.0.

Manually control 1-LK-459, PRZR LVL CTRL OR 1-FK-121, CCP CHRG RO FLO CTRL to maintain level at program. [Step 2.3.1]

Transfer 1/1-LS-459D, PRZR LVL CTRL CHAN SELECT to an operable RO alternate controlling channel. [Step 2.3.2]

TRANSFER 1/1-LS-459E, 1/1-LR-459 PZR Level Recorder Select to an RO/BOP OPERABLE channel. [Step 2.3.3]

Page 13 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 3 Page 14 of 42 Event

Description:

PZR LT-460 fails low. Letdown isolates.

Time Position Applicants Actions or Behavior Examiner Note: Letdown flow is re-established using ABN-706, Attachment 6, or the Letdown Restoration Job Aid.

RO VERIFY Normal Letdown aligned. [Step 2.3.4]

WHEN pressurizer level is greater than 17%, THEN restore letdown per Attachment 6.

OPEN or VERIFY OPEN Letdown Isolation Valves 1/1-LCV-460 &

1/1-LCV 459. [Step 1]

Manually OPEN 1-PK-131, LTDN HX OUT PRESS CTRL to 30% (75 GPM) or 50% (120 GPM) DEMAND. [Step 2]

Manually OPEN 1-TK-130, LTDN HX OUT TEMP CTRL to 50%

DEMAND. [Step 3]

ADJUST Charging to desired flow and MAINTAIN Seal Injection flow between 6 and 13 GPM. [Step 4]

OPEN selected Orifice Isolation Valves. [Step 5]

o 1/1-8149A, LTDN ORIFICE ISOL VLV (45 GPM) o 1/1-8149B, LTDN ORIFICE ISOL VLV (75 GPM) o 1/1-8149C, LTDN ORIFICE ISOL VLV (75 GPM)

ADJUST 1-PK-131, LTDN HX OUT PRESS CTRL to ~310 psig on 1-PI-131, LTDN HX OUT PRESS then PLACE in AUTO. [Step 6]

ADJUST 1-TK-130, LTDN HX OUT TEMP CTRL to obtain ~95ºF on 1-TI-130, LTDN HX OUT TEMP, then PLACE in AUTO. [Step 7]

If necessary, Reclose 1/u-PCPR, PRZR CTRL HTR GROUP C by placing the RO control switch in the "ON" position. [Step 2.3.5]

RESTORE PZR Level Control or Charging Flow Control to AUTO as desired.

RO

[Step 2.3.6]

VERIFY other instruments on common instrument line - NORMAL.

US/RO

[Step 2.3.7]

VERIFY Loop 2 Instrument PT-0456 and PT-0458 responding normally per Attachment 1.

Page 14 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 3 Page 15 of 42 Event

Description:

PZR LT-460 fails low. Letdown isolates.

Time Position Applicants Actions or Behavior US EVALUATE Technical Specifications. [Step 2.3.10]

LCO 3.3.1.M, Reactor Trip System Instrumentation (Function 9 -

Pressurizer Water Level - High).

CONDITION M - One channel inoperable.

US INITIATE repairs per STA-606. [Step 2.3.11]

US INITIATE a SMART Form per STA-421. [Step 2.3.12]

When Letdown flow has been restored and Technical Specifications have been addressed, or at Lead Examiner discretion, PROCEED to Event 4.

Page 15 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 4 Page 16 of 42 Event

Description:

CEV 1-01 Trip.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 4 (Key 4).

- FW16, FW17A CEV pump trips. Manually start alternate Indications Available:

1-ALB-9A, Window 1.12, CNDSR ANY VAC PMP TRIP Plant Computer Alarms:

P6600A - CNDSR A PRESS (VA)

P6601A - CNDSR B PRESS (VA) 1-PI-2042-1, CNDNSR A PRESS lowering 1-PI-2042-2, CNDNSR B PRESS lowering BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE Main Condenser vacuum lowering slowly.

DIRECT performance of ABN-304, Main Condenser and Circulating Water US System Malfunction, Section 3.0.

BOP START all available Condenser Vacuum Pumps. [Step 3.3.1]

Simulator Operator: When dispatched to verify CEV seal water tank levels, after 3 minutes, report, The seal tank on 1-01 CEV was empty and it has been filled.

Delete the Air in-leakage malfunction, FW16.

DISPATCH an operator to VERIFY CEV seal water tank level indicated.

BOP

[Step 3.3.2]

BOP VERIFY Main Condenser vacuum > 21 Hg. [Step 2.3.3]

Page 16 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 4 Page 17 of 42 Event

Description:

CEV 1-01 Trip.

Time Position Applicants Actions or Behavior BOP DETERMINE Main Condenser vacuum > 26.5 Hg. [Step 2.3.4]

On the Back Pressure Limit Display ensure turbine NOT operating for more than 5 minutes in the NOT PERMISSIBLE region [Step 2.3.4 RNO]

Examiner Note: The crew may perform at least one 50 MWe load reduction if Rated Thermal power exceeds 100%.

Verify Main Condenser Vacuum Being Maintained - GREATER THAN 24.5" BOP HG AND STABLE [Step 2.3.5]

AND Reactor Power - LESS THAN 100%

BOP Locally verify In-leakage paths - NORMAL [Step 2.3.6]

US DIRECT performance of ALM-0091A, CNDSR ANY VAC PMP TRIP BOP PLACE affected vacuum pump handswitch in OFF. [Step 1]

1-HS-2956, CNDSR VAC PMP 1 1-HS-2957, CNDSR VAC PMP 2 1-HS-2958, CNDSR VAC PMP 3 A. IF NO vacuum pumps are in service, THEN START an available pump per SOP-309A for Startup.

VERIFY condenser vacuum is maintained above 24.5 inches Hg vacuum.

BOP

[Step 2]

A. IF vacuum can NOT be maintained, THEN GO to ABN-304 for Main or Auxiliary Condenser Vacuum Decreasing.

Page 17 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 4 Page 18 of 42 Event

Description:

CEV 1-01 Trip.

Time Position Applicants Actions or Behavior Simulator Operator: When dispatched to check CEV pump 1-01, after 3 minutes, report, The 1-01 CEV motor is hot and there is an acrid odor, the breaker has tripped on overload.

DISPATCH an operator to TB 778' CEV AREA to check pump for signs of BOP damage (i.e., smoke, acrid odor, overheating). [Step 3]

BOP CORRECT the condition or INITIATE a work request per STA-606.[Step 4]

At Lead Examiner discretion, PROCEED to Event 5.

Page 18 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 19 of 42 Event

Description:

SG 1-02 10 GPM Tube Leak.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 5 (Key 5).

- SG01B, Steam Generator 1-02 Tube Leak at 10 GPM.

Indications Available:

PC MSL-179 (1-RE-2326) is RED PC N16-175 MSL #2 (1-RE-2326A) is RED PC COG-182 (1-RE-2959) is RED (Condenser Off Gas is delayed)

RO/BOP RESPOND to PC-11, Digital Radiation Monitoring System alarms.

RO/BOP RECOGNIZE radiation monitor alarms associated with Steam Generator 1-02.

US DIRECT performance of ABN-106, High Secondary Activity, Section 3.0.

DETERMINE Main Steam Line 1-02 radiation alarm 1-RE-2326 is RED on RO/BOP PC-11.

REDUCE power to 50% in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND be in MODE 3 in the next 2 US hours.

US GO to Step 5.b.

Examiner Note: Crew should implement Reactivity Briefing Sheet for a Rapid Plant Shutdown within one hour.

RO VERIFY PRZR level - STABLE OR TRENDING TO NORMAL LEVEL.

VERIFY Condenser off Gas Radiation Monitor OR Main Steam Line Leak US Rate Radiation Monitor on Affected Steam Generator - OPERABLE.

Page 19 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 20 of 42 Event

Description:

SG 1-02 10 GPM Tube Leak.

Time Position Applicants Actions or Behavior US DIRECT Chemistry to implement CHM-113.

ADJUST Steam Generator 1-02 Atmospheric Relief Controller setpoint to BOP 1160 PSIG per TDM-501A.

BOP VERIFY Affected Steam Generator - SG 1-02.

US EVALUATE Technical Specifications.

LCO 3.4.13, RCS Operational Leakage CONDITION B - Primary to secondary LEAKAGE not within limits.

Examiner Note: The following steps are from IPO-003A, Power Operations, Section 5.6, Reducing Turbine Power from 100% to MODE 3.

DIRECT load reduction to 200 MWe per IPO-003A, Power Operations, US Section 5.6, Reducing Turbine Power from 100% to MODE 3.

RO CONTACT Chemistry and place specified demineralizers in-service.

RO NOTIFY QSC Generation Controller prior to reducing load.

Page 20 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 21 of 42 Event

Description:

SG 1-02 10 GPM Tube Leak.

Time Position Applicants Actions or Behavior NOTIFY Chemistry and Radiation Protection that power will be lowered RO 15% within a one hour period.

Page 21 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 22 of 42 Event

Description:

SG 1-02 10 GPM Tube Leak.

Time Position Applicants Actions or Behavior RO PERFORM the following to reduce Turbine Load to ~200MWe:

DETERMINE the amount of Boration required to reduce Reactor Power to 200 MWe (~15% power).

If desired, DETERMINE the rate of Boration required to allow slow Control RO Rod inward motion as Turbine load lowers.

RO REFER to Attachment 2 for guidance in controlling AFD during power ramp.

Page 22 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 23 of 42 Event

Description:

SG 1-02 10 GPM Tube Leak.

Time Position Applicants Actions or Behavior INITIATE RCS boration per SOP-104A, Reactor Make-up and Chemical RO Control System.

Examiner Note: The following steps are from SOP-104A, Reactor Make-up and Chemical Control System, Section 5.1.2, Borate Mode.

RO PERFORM the following to COMMENCE RCS boration:

ENSURE Prerequisites of Section 2.1 and 2.2 are met. [Step 5.1.2.A]

ENSURE 1/1-MU, RCS MU MAN ACT is in STOP. [Step 5.1.2.B]

PLACE 43/1-MU, RCS MU MODE SELECT in BORATE. [Step 5.1.2.C]

Examiner Note: The Boration amounts and pot setting are approximations based on the briefing sheets, the crew may vary from the listed values based on plant conditions and desired rate of power reduction.

SET 1-FK-110, BA BLNDR FLO CTRL to ~5.0 pot setting for ~20 GPM.

[Step 5.1.2.D]

SET 1-FY-110B, BA BATCH FLO counter for 589 gallons. [Step 5.1.2.E]

ENSURE 1/1-FCV-110A, BA BLNDR FLO CTRL VLV in AUTO.

[Step 5.1.2.F]

PLACE 1/1-MU, RCS MU MAN ACT in START. [Step 5.1.2.G]

VERIFY 1/1-APBA1, BA XFR PMP 1 STARTS. [Step 5.1.2.H]

VERIFY 1/1-FCV-110A, BA BLNDR FLO CTRL VLV throttles to

~20 GPM. [Step 5.1.2.I]

VERIFY 1/1-FCV-110B, RCS MU TO CHG PMP SUCT ISOL VLV OPEN.

[Step 5.1.2.I]

Page 23 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 24 of 42 Event

Description:

SG 1-02 10 GPM Tube Leak.

Time Position Applicants Actions or Behavior VERIFY 1-FY-110B, BA BATCH FLO counter operating properly.

[Step 5.1.2.J]

VERIFY 1-FR-110, BA BATCH FLO TO BLNDR red pen operating properly. [Step 5.1.2.J]

OPERATE 1/1-LCV-112A, VCT LVL CTRL VLV as necessary to maintain proper VCT level. [Step 5.1.2.K]

When desired amount of boric acid is added, PLACE 1/1-MU, RCS MU MAN ACT in STOP. [Step 5.1.2.L]

Examiner Note: The following steps continue from IPO-003A, Power Operations, Section 5.6, Reducing Turbine Power from 100% to Mode 3.

The listed rate of load reduction is based on the Reactivity briefing sheet and is based on ~50 minutes to 200 MWe. The crew may reduce load at a faster or slower rate.

BOP SET Turbine Load Rate Setpoint Controller to ~20 MWe/min.

OPEN Load Rate Setpoint OSD.

SELECT blue bar and ENTER 20 MWe/min.

CLOSE Load Rate Setpoint OSD.

Page 24 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 25 of 42 Event

Description:

SG 1-02 10 GPM Tube Leak.

Time Position Applicants Actions or Behavior BOP SET Turbine Load Target to 200 MWe.

OPEN Load Target OSD.

SELECT blue bar and ENTER 200 MWe.

DEPRESS Accept then VERIFY value in blue bar is desired Load Target (magnitude and direction).

DEPRESS Execute then VERIFY Load Target changes to desired load.

CLOSE Load Target OSD.

CREW MONITOR load change.

When the crew has demonstrated controlled load reduction, or as determined by the lead examiner, proceed to Event 6.

Page 25 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 26 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior Examiner Note: Events 7 and 8 will occur as they were inserted on setup, and therefore this is the last active key for the scenario.

Simulator Operator: When directed, EXECUTE Event 6 (Key 6).

SG02B, SG 1-02 Tube Rupture, One Tube.

Indications Available:

6A-3.4 - CHRG FLO HI / LO 5C-1.2 - PRZR LVL DEV LO 5C-3.3 - PRZR PRESS LO BACKUP HTRS ON PC MSL-179 (1-RE-2326) is RED Main Steam Line Radiation level rising Pressurizer pressure lowering RO/BOP RECOGNIZE Pressurizer level and pressure LOWERING at a rising rate.

RECOGNIZE PRZR pressure decreasing with Steam Line Radiation RO/BOP Monitors in alarm and steam / feed mismatch.

RO Manually INITIATE a Reactor Trip.

PLACE 1/1-RTC, RX TRIP BKR Switch in TRIP.

US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip: [Step 1]

VERIFY Reactor Trip Breakers - OPEN. [Step 1.a]

VERIFY Neutron flux - DECREASING. [Step 1.a]

VERIFY all Control Rod Position Rod Bottom Lights - ON. [Step 1.b]

Page 26 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 27 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior Examiner Note: Turbine will not trip which will require the operator to stop EHC pumps or close the Main steam isolation valves, either action satisfies the Critical Task.

CRITICAL TASK Place EHC Pumps in PULL OUT or Manually Close MSIVs Upon Failure of Main Turbine Trip Prior to Exiting EOP 0.0A, Reactor Trip or Safety Injection.

BOP VERIFY Turbine Trip: [Step 2]

All HP Turbine Stop Valves - CLOSED. [Step 2]

Manually trip turbine. [Step 2 RNO]

IF the turbine will NOT trip, THEN pull-out all EHC fluid pumps. [Step 2 RNO]

CRITICAL TASK BOP IF the turbine still NOT tripped, THEN close or verify closed main steamline isolation valves.

BOP VERIFY Power to AC Safeguards Buses: [Step 3]

VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.

[Step 3.a]

VERIFY both AC Safeguards Buses - ENERGIZED. [Step 3.b]

RO CHECK SI status: [Step 4]

CHECK if SI is actuated. [Step 4.a]

PLACE 1/1-SIA2, SI MAN ACT Switch to ACT position at CB-07 and DETERMINE SI has actuated.

VERIFY Both Trains SI Actuated: [Step 4.b]

SI Actuated blue status light - ON NOT FLASHING.

Examiner Note: Attachment 2 Steps begin on page 37 of the scenario.

INITIATE Proper Safeguards Equipment Operation Per Attachment 2.

US/BOP

[Step 5]

Page 27 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 28 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior RO VERIFY AFW Alignment: [Step 6]

MDAFW Pumps - RUNNING. [Step 6.a]

Turbine Driven AFW Pump - RUNNING IF NECESSARY. [Step 6.b]

AFW total flow - GREATER THAN 460 GPM. [Step 6.c]

AFW valve alignment - PROPER ALIGNMENT. [Step 6.d]

RO DETERMINE Containment Spray NOT Required: [Step 7]

VERIFY 1-ALB-2B, Window 1-8, CS ACT - NOT ILLUMINATED.

[Step 7.a]

-AND-VERIFY 1-ALB-2B, Window 4-11, CNTMT ISOL PHASE B ACT - NOT ILLUMINATED. [Step 7.a]

-AND-VERIFY Containment pressure - LESS THAN 18.0 PSIG. [Step 7.a]

VERIFY Containment Spray Heat Exchanger Outlet Valves - CLOSED.

RO

[Step 7.b]

RO VERIFY Containment Spray Pumps - RUNNING. [Step 7.c]

CHECK if Main Steam lines should be ISOLATED: [Step 8]

RO/BOP

a. Verify the following:

VERIFY Containment pressure - GREATER THAN 6.0 PSIG.

[Step 8.a]

-OR-VERIFY Steam Line pressure - LESS THAN 610 PSIG. [Step 8.a]

RO/BOP Determine Main Steam lines should not be isolated and go to Step 9.

[Step 8 a. RNO]

Check RCS Temperature - RCS AVERAGE TEMPERATURE STABLE AT RO/BOP OR TRENDING TO 557OF [Step 9]

Page 28 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 29 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior RO/BOP Check PRZR Valve Status:[Step 10]

a. PRZR Safeties - CLOSED

b. Normal PRZR spray valves -CLOSED

c. PORVs - CLOSED

d. Power to at least one block valve - AVAILABLE

e. Block valves - AT LEAST ONE OPEN RO/BOP Check If RCPs Should Be Stopped:[Step 11]

a. RCS subcooling - LESS THAN 25OF (55OF FOR ADVERSE CONTAINMENT)

b. ECCS pumps - AT LEAST ONE RUNNING CCP

-OR-SI pump

c. Stop all RCPs.

RO/BOP Check If Any SG Is Faulted:[Step 12]

a. Check pressures in all SGs: a. Go to Step 13.

ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER

-OR-ANY SG COMPLETELY DEPRESSURIZED

b. Go to EOP-2.0A, FAULTED STEAM GENERATOR ISOLATION, Step 1.

RO/BOP Check If SG Tubes Are Ruptured: [Step 13]

Condenser off gas radiation - NORMAL (COG-182, 1RE-2959)

Main steamline radiation - NORMAL (MSL-178 through 181, 1RE-2325 through 2328)

SG blowdown sample radiation monitor - NORMAL (SGS-164, 1RE-4200)

No Steam Generator level increasing in an uncontrolled manner RNO: Go to EOP-3.0A, STEAM GENERATOR TUBE RUPTURE. Step 1 US Transition to EOP-3.0A, STEAM GENERTOR TUBE RUPTURE.

Page 29 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 30 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior Examiner Note: EOP-3.0, Steam Generator Tube Rupture steps begin here.

RO/BOP Check If RCPs Should Be Stopped: [Step 1]

a. RCS subcooling LESS THAN 25°F (55°F FOR ADVERSE CONTAINMENT)

b. ECCS pumps AT LEAST ONE RUNNING CCP

-OR-SI pump

c. Stop all RCPs.

Identify and isolate the Ruptured Steam Generator Prior to CRITICAL TASK Commencing an Operator Induced Cooldown per EOP-3.0A.

Identify Ruptured SG(s): SG 1-02 is the only one. [Step 2]

Unexpected increase in any SG narrow range level

-OR-CRITICAL RO/BOP High radiation from any SG blowdown sample line. (SGS164, TASK 1RE4200)

-OR-High radiation from any Main steamline. (MSL178 through 181, 1RE2325 through 2328)

CRITICAL Identified 1-02 Steam Generator Tubes are ruptured.

TASK Page 30 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 31 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior CRITICAL TASK RO/BOP Isolate Flow From Ruptured SG(s): [Step 3]

a. Adjust ruptured SG(s) atmospheric controller setpoint to 1160 psig.

b. Check ruptured SG(s) atmospheric CLOSED

c. Close ruptured SG(s) main steamline isolation, and SG drippot isolation valves

d. PullOut steam supply valve handswitch from ruptured SG(s) to Turbine Driven AFW pump - Not Applicable to SG 1-02.

e. Verify blowdown isolation valve(s) from ruptured SG(s) CLOSED RO/BOP Check Ruptured SG(s) Level: [Step 4]

a. Narrow range level GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT)

CRITICAL TASK

b. Stop AFW flow to ruptured SG(s).

Page 31 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 32 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior RO/BOP Check Ruptured SG(s) Pressure GREATER THAN 420 PSIG. [Step 5]

RO/BOP Initiate RCS Cooldown: [Step 6]

a. Check PRZR pressure LESS THAN 1960 PSIG

b. Block low steamline pressure SI signal

c. Determine required core exit temperature from Table 1.

Page 32 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 33 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior Page 33 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 34 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior RO/BOP d. Dump steam to condenser from intact SG(s) at maximum rate and avoid main steam isolation.

1) Transfer Steam Dump to steam pressure mode.

2) Place the steam pressure controller in manual and increase demand.

3) When P12 (553°F TAVG) is reached, select bypass interlock on Steam Dumps and continue cooldown.

e. Place all PRZR heater switches to OFF position.

f. Core exit TCs LESS THAN REQUIRED TEMPERATURE RNO: Continue with Step 7. WHEN core exit TCs less than required temperature, THEN do Step 6g and 6h.

g. Stop RCS cooldown.

h. Maintain core exit TCs LESS THAN REQUIRED TEMPERATURE RO/BOP Check Intact SG Levels: [Step 7]

a. Narrow range level GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT)

b. Control AFW flow to maintain narrow range level between 43% and 60%.

RO/BOP Check PRZR PORVs and Block Valves: [Step 8]

a. Power to block valves AVAILABLE

b. PORVs CLOSED

c. Block valves AT LEAST ONE OPEN Page 34 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 35 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior RO/BOP IF The Diesels are Running, THEN Place Both DG EMER STOP/START Handswitches In START. [Step 9]

RO/BOP Reset SI. [Step 10]

RO/BOP Reset SI Sequencers. [Step 11]

RO/BOP Reset Containment Isolation Phase A and Phase B. [Step 12]

RO/BOP Reset Containment Spray Signal. [Step 13]

RO/BOP Establish Instrument Air and Nitrogen To Containment: [Step 14]

a. Establish instrument air:

Verify air compressor running.

-AND-Establish instrument air to containment.

b. Establish nitrogen:

1) Verify ACCUM 1-4 VENT CTRL, 1HC943 CLOSED

2) Open SI/PORV ACCUM N2 ISOL VLV, 1/18880 Page 35 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 36 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior RO/BOP Check If RHR Pumps Should Be Stopped: [Step 15]

a. RHR pumps ANY RUNNING WITH SUCTION ALIGNED TO RWST

b. RCS pressure GREATER THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT)

c. Stop RHR pumps and place in standby.

d. Reset RHR auto switchover.

RO/BOP Check If RCS Cooldown Should Be Stopped: [Step 16]

a. Core exit TCs LESS THAN REQUIRED TEMPERATURE DO NOT proceed until core exit TCs less than required temperature. [Step 16 RNO]

b. Verify Steps 6g and 6h complete.

RO/BOP Check Ruptured SG(s) Pressure STABLE OR INCREASING [Step 17]

RO/BOP Check RCS Subcooling GREATER THAN 45°F (75°F FOR ADVERSE CONTAINMENT) [Step 18]

Page 36 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 37 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior RO/BOP Depressurize RCS To Minimize Break Flow and Refill PRZR: [Step 19]

a. Normal PRZR spray AVAILABLE

b. Spray PRZR with maximum available spray until ANY of the following conditions satisfied:

BOTH of the following:

1) RCS pressure LESS THAN RUPTURED SG(s) PRESSURE

2) PRZR level GREATER THAN 13% (34% FOR ADVERSE CONTAINMENT)

-OR-PRZR level GREATER THAN 75% (65% FOR ADVERSE CONTAINMENT)

-OR-RCS subcooling AT 25°F (55°F FOR ADVERSE CONTAINMENT)

c. Close spray valve(s):

1) Normal spray valves

2) Auxiliary spray valve When the crew has begun RCS depressurization or at the discretion of the lead examiner, the scenario can be terminated.

Page 37 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 38 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior Examiner Note: These steps are performed by the BOP per EOP-0.0A, Attachment 2.

BOP VERIFY SSW Alignment: [Step 1]

VERIFY SSW Pumps - RUNNING. [Step 1.a]

VERIFY Diesel Generator Cooler SSW return flow. [Step 1.b]

CRITICAL TASK Manually Start Safety Injection Pump 1-01 Prior to completing Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection.

BOP VERIFY Safety Injection Pumps - RUNNING. [Step 2]

CRITICAL DETERMINE SI Pump 1-01 failed to start and MANUALLY START SI TASK BOP Pump 1-01. [Step 2 RNO]

BOP VERIFY Containment Isolation Phase A. [Step 3]

BOP VERIFY Containment Ventilation Isolation. [Step 4]

BOP VERIFY CCW Pumps - RUNNING. [Step 5]

BOP VERIFY RHR Pumps - RUNNING. [Step 6]

BOP VERIFY Proper CVCS Alignment: [Step 7]

VERIFY both CCPs - RUNNING. [Step 7.a]

VERIFY Letdown Relief Valve isolation: [Step 7.b]

DETERMINE Letdown Orifice Isolation Valves - CLOSED.

[Step 7.b.1)]

DETERMINE Letdown Isolation Valves1/1-LCV-459 & 1/1-LCV-460

- CLOSED. [Step 7.b.2)]

BOP VERIFY ECCS flow: [Step 8]

VERIFY CCP SI flow indicator. [Step 8.a]

VERIFY RCS pressure < 1800 PSIG. [Step 8.b]

VERIFY SI Pumps discharge flow indicator. [Step 8.c]

Page 38 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 39 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior VERIFY RCS pressure > 325 PSIG. [Step 8.d]

BOP VERIFY Feedwater Isolation Complete: [Step 9]

VERIFY Feedwater Isolation Valves CLOSED. [Step 9]

VERIFY Feedwater Isolation Bypass Valves CLOSED. [Step 9]

VERIFY Feedwater Bypass Control Valves CLOSED. [Step 9]

VERIFY Feedwater Control Valves CLOSED. [Step 9]

BOP VERIFY both Diesel Generators - RUNNING. [Step 10]

BOP VERIFY Monitor Lights For SI Load Shedding - LIT. [Step 11]

BOP VERIFY Proper SI alignment per MLB light indication. [Step 12]

BOP VERIFY Components Properly Aligned per Table 1. [Step 13]

Location Equipment Description Condition CB-03 X-HS-5534 H2 PRG SPLY FN 4 STOPPED CB-03 X-HS-5532 H2 PRG SPLY FN 3 STOPPED CB-04 1/1-8716A RHRP 1 XTIE VLV OPEN CB-04 1/1-8716B RHRP 2 XTIE VLV OPEN CB-06 1/1-8153 XS LTDN ISOL VLV CLOSED CB-06 1/1-8154 XS LTDN ISOL VLV CLOSED CB-07 1/1-RTBAL RX TRIP BKR OPEN CB-07 1/1-RTBBL RX TRIP BKR OPEN CB-07 1/1-BBAL RX TRIP BYP BKR OPEN/DEENERGIZED CB-07 1/1-BBBL RX TRIP BYP BKR OPEN/DEENERGIZED CB-08 1-HS-2397A SG 1 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2111C FWPT A TRIP TRIPPED CB-08 1-HS-2112C FWPT B TRIP TRIPPED Page 39 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 40 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior CB-09 1-HS-2490 CNDS XFER PUMP STOPPED (MCC deenergized on SI)

CV-01 X-HS-6181 PRI PLT SPLY FN 17 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6202 PRI PLT SPLY FN 20 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6209 PRI PLT SPLY FN 21 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6216 PRI PLT SPLY FN 22 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6223 PRI PLT SPLY FN 23 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6230 PRI PLT SPLY FN 24 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-3631 UPS & DISTR RM A/C FN 1 & STARTED BSTR FN 42 CV-01 X-HS-3632 UPS & DISTR RM A/C FN 2 & STARTED BSTR FN 43 CV-01 1-HS-5600 ELEC AREA EXH FN 1 STOPPED/DEENERGIZED CV-01 1-HS-5601 ELEC AREA EXH FN 2 STOPPED/DEENERGIZED CV-01 1-HS-5602 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 3 & EXH DMPR CV-01 1-HS-5603 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 4 & EXH DMPR CV-01 1-HS-5618 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 17 CV-01 1-HS-5620 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 18 CV-03 X-HS-5855 CR EXH FN 1 STOPPED/DEENERGIZED CV-03 X-HS-5856 CR EXH FN 2 STOPPED/DEENERGIZED CV-03 X-HS-5731 SFP EXH FN 33 STOPPED/DEENERGIZED CV-03 X-HS-5733 SFP EXH FN 34 STOPPED/DEENERGIZED CV-03 X-HS-5727 SFP EXH FN 35 STOPPED/DEENERGIZED CV-03 X-HS-5729 SFP EXH FN 36 STOPPED/DEENERGIZED Page 40 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, 8 Page 41 of 42 Event

Description:

SGTR 1-02 ONE Tube, Turbine Fails to Trip, SIP 1-01 Fails to Start Time Position Applicants Actions or Behavior Examiner Note: The next four (4) steps would be performed on Unit 2.

CB-03 2-HS-5538 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5539 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5537 AIR PRG SPLY ISOL DMPR CLOSED CB-03 2-HS-5536 AIR PRG SPLY ISOL DMPR CLOSED BOP NOTIFY Unit Supervisor attachment instructions complete and to IMPLEMENT FRGs as required. [Step 13]

EOP-0.0A, Attachment 2 steps are now complete.

Page 41 of 42 CPNPP NRC 2015 Simulator Scenario 3

Scenario Event Description NRC Scenario 3

CPNPP 2015 NRC Initial Scenario 3

Load IC20

INITIAL CONDITIONS

SIP 1-02 placed in pull out

Danger Tag on Handswitch

Breaker racked out

GEM Cover on Train A SIP HS IRF SIR02 f: 0

SIP 1-01 Fail to start on SI (Event 8)

IMF SI04C f:1

Turbine Fails to Auto/Man trip (Event 7)

IMF TC07C f:1

Auto MSLI Failure Trn A/B (Event 7)

IMF SS02A1 f:1 IMF SS02A2 f:1

TPCW Auto fill block ((Event 2)

IOR DITPHS3050 f:0

EVENTS

N-42 Power Range Fails hi (Event 1)

IMF NI04E f:200 k:1

TPCW Leak 15 gpm (Event 2)

IMF TP01 f:15 k:2

Delete override and leak when RO fills (Event 2)

{DITPHS3050.Value=2} DOR DITPHS3050

{DITPHS3050.Value=2} DMF TP01

Start a second Demin Pump if needed (Event 2)

IRF CMR51 f:3 k:10

PRZR Lvl trans 460 fails low (Event 3)

IMF RX05B f:0 k:3

CEV 1-01 Trip with air in leakage IMF FW16 f: 2 k:4 IMF FW17A f:1 k:4

SG2 10 gpm tube leak (Event 5)

IMF SG01B f:10 k:5

SG 2 Tube rupture 1 tube (Event 6)

IMF SG02B f:1 k:6 Page 42 of 42 CPNPP NRC 2015 Simulator Scenario 3

Appendix D Scenario Outline Form ES-D-1 June 2015 NRC Exam Facility: CPNPP 1 & 2 Scenario No.: 4 Op Test No.:

Examiners: Operators:

Initial Conditions: 73 % RTP, 875 MWe MOL - RCS boron is 993 ppm. Xe is at equilibrium. EHC pump motor is tagged out. Boric Acid Pump 1-01 is tagged out.

Turnover: Maintain 73% Reactor Power.

Critical Tasks: Manually Trip Reactor due to RCP trip prior to exiting EOP-0.0A, Reactor Trip or Safety Injection.

Manually start at least one low-head (RHR pump) ECCS pump before completion of Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection.

Transfer a single train of ECCS to Cold Leg Recirculation per EOS-1.3A, Transfer to Cold Leg Recirculation prior to RWST Empty alarm.

Event No. Malf. No. Event Type* Event Description 1 MS13C I - RO Atmospheric Relief Valve (1-03) fails open due to PT-2327 failure.

C - SRO 2 RD12C I - RO Loss of Digital Rod Position Indication (TS)

TS - SRO 3 RX04B I - BOP SG 1-02 LT-552 fails high. (TS)

TS - SRO 4 FW03B R - RO MFP 1-02 trips. Turbine runs back, but rods require manual RX03 C - BOP insertion.

C - SRO 5 RC04B M - ALL RCP 1-02 shaft breaks.

RP01 Reactor fails to auto trip.

6 RC09B2 M - ALL LBLOCA 7 RH01A C - BOP RHR Pump 1-01 starts and trips.

RH01D RHR Pump 1-02 fails to auto start.

8 CS05B C - BOP 1-HS-4783 (Cont. Spray suction valve) fails to open (stuck closed).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 4 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 2 Major transients (1-2) 3 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 3 Critical tasks (2-3)

Page 1 of 40 CPNPP NRC 2015 Simulator Scenario 4

Scenario Event Description June 2015 NRC Exam Scenario 4 SCENARIO 4

SUMMARY

Event 1 The first event is Steam Generator Atmospheric Relief Valve 1-03 failing open due to PT-2327 failure. The crew will enter ABN-709, Section 2.0, Steam Line Pressure Instrument Malfunction, and per Step 2 RNO, manually closes 1-ZL-2327, SG 3 ATMOS RLF VLV.

Event 2 The scenario continues with a loss of the Digital Rod Position Indication (DRPI) system. The crew will stop any dilution in progress, and enter ABN-712, Section 4.0. Digital Rod Position Indication Malfunction. The SRO will refer to Technical Specifications. Per Tech. Spec. 3.1.7, Condition B, the crew will place rods in Manual immediately. This also complicates the Reactor Trip later in the scenario requiring an Emergency Boration due to loss of DRPI.

Event 3 SG 1-02 LT-552 fails HIGH. This failure mode causes the FRVs to close, with a resulting lowering SG level. The crew will enter ABN-710, Steam Generator Level Instrumentation Malfunction Operator, and per Step 2 will manually control SG level at programmed level. The SRO will refer to Technical Specifications.

Event 4 Once the operators have control of SG levels and the Unit has stabilized from the previous malfunction, the Main Feed Pump 1-02 trips. The crew will enter ABN-302, Section 2.0, Feedwater Pump Trip. The Main Turbine will automatically runback at 35% per minute to 60% power. The event will be complicated by the fact that the control rods must be inserted in manual during the turbine runback. This will be due to the fact that: 1.) the operators previously placed the rods in manual for loss of DRPI, and/or 2.) If the operators had restored the rods to auto, a malfunction is inserted that will still require manual insertion of rods during the turbine runback.

Event 5 After the crew stabilizes the Unit from the MFP 1-02 trip, RCP 1-02 shaft will fail (breaks). RCS flow in the associated loop reduces until the automatic reactor trip setpoint (due to low RCS loop flow) is reached. The reactor FAILS to auto trip, requiring a manual trip. Loss of DRPI requires an Emergency Boration in accordance with the Foldout Page of EOP-0.0A, Reactor Trip or Safety Injection.

Event 6 Following the manual reactor trip, and after the emergency boration has been initiated, a large break LOCA on Loop 2 occurs due to the dislodged RCP components. Pressurizer pressure lowers to the auto SI setpoint and actuates. RHR Pump 1-01 auto starts on the SI, but immediately trips. RHR Pump 1-02 fails to auto start. The crew must manually start RHR Pump 1-02 to establish low head ECCS flow. This is a Critical Task.

Event 7 1-HS-4783 Containment Spray Suction Valve fails to open. Requires manual action to open valve to ensure suction is available to both trains of the Containment Spray System.

Risk Significance:

Failure of risk important system prior to trip: Loss of Digital Rod Position and rods in manual RCP shaft break Risk significant core damage sequence: RCP shaft break resulting in LBLOCA Failure of automatic reactor trip Failure of low-head ECCS injection Risk significant operator actions: Manually insert control rods on turbine runback Manually initiate reactor trip Start RHR Pump 1-02 for low-head injection Page 2 of 40 CPNPP NRC 2015 Simulator Scenario 4

Scenario Event Description June 2015 NRC Exam Scenario 4 Critical Task Safety Cueing Measurable Performance Significance Performance Feedback Indicators Manually Trip Recognize a failure Procedural direction at The operator will Reactor Trip Reactor due to or an incorrect EOP-0.0A Step 1 to manually trip the Breakers open, flux RCP trip prior to automatic determine if a reactor trip Reactor with the lowering, rod exiting EOP-0.0A, actuation of an has occurred. Position handswitch on bottom lights lit.

Reactor Trip or ESF system or indication of the Reactor CB-07 or CB-10 Safety Injection. component. Trip breakers and placed to trip.

Reactor Power, Annunciator First out alarms.

Manually Start RHR Recognize a failure Procedural direction per The operator will Indication of pump Pump 1-01 Prior to or an incorrect EOP-0.0A Attachment 2 manually start start including light completing automatic to start RHR Pump 1-01. RHR Pump 1-01. indication, pressure of actuation of an Pump indication lights, and flow.

EOP-0.0A, Reactor ESF system or flow and discharge Trip or Safety component. pressure.

Injection.

Transfer a single Recognize entry Procedurally driven from The operator(s) ECCS flow is train of ECCS to criteria for EOP-1.0A, to transition will align ECCS for maintained, RWST Cold Leg EOS-1.3A, upon receipt of RWST cold leg Recirc by suction valves are Recirculation per Transfer to Cold LO-LO level alarm to positioning valves closed, all mini-flow EOS-1.3A, Transfer Leg Recirculation EOS-1.3A. Note that using or recirculation to Cold Leg and ensure suction only one full ECCS train handswitches and paths to the RWST Recirculation prior source for core can be shifted. Both a key on the MCB. are also isolated.

to RWST Empty cooling is trains SI and CCP can alarm. maintained. be supplied from 1 running RHR pump.

Page 3 of 40 CPNPP NRC 2015 Simulator Scenario 4

Scenario Event Description June 2015 NRC Exam Scenario 4 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC #17 and LOAD NRC Scenario 4.

EVENT REM. MALF. DESCRIPTION DEMAND INITIATING FUNC. VALUE PARAMETER DITCHS65 SETUP IOR 52 EHC Pump C Tagged out of service f:0 K0 DICVAPB Boric Acid Transfer Pump 1-01 Tagged out of IOR A1 f:0 K0 service.

5 RP01 Reactor fails to auto trip. f:1 K0 7 RH01D RHR Pump 1-02 fails to auto start. f:1 K0 8 CS05B CT SMP SUCT VLV 2 stuck closed 4783 f:1 K0 1 MS13C ARV 1-03 fails open due to PT-2327 failure. f:1300 K1 2 RD12C Loss of DRPI f:1 K2 3 RX04B SG 1-02 LT-552 fails high. f:100 K3 4 FW03B Main Feed Pump 1-02 trips. f:1 K4 4 RD15A Auto Rods Failure, Work in Manual f:1 K4 5 RC04B RCP 1-02 shaft breaks. f:1 K5 5 RP01 Reactor fails to auto trip. f:1 K0 6 RC09B2 Large Break LOCA f:1 d:10 K6 7 RH01A RHR Pump 1-01 starts and trips. f:1 d:50 K6 7 RH01D RHR Pump 1-02 fails to auto start. f:1 K0 8 CS05B CT SMP SUCT VLV 2 stuck closed 4783 f:1 K0 Page 4 of 40 CPNPP NRC 2015 Simulator Scenario 4

Scenario Event Description June 2015 NRC Exam Scenario 4 Simulator Operator: INITIALIZE to IC #18 and LOAD NRC Scenario 4.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE all Control Board Tags are removed.

ENSURE Operator Aid Tags reflect current boron conditions.

ENSURE Rod Bank Update (RBU) is performed.

ENSURE Turbine Load Rate set at 10 MWe/minute.

ENSURE 60/90 buttons DEPRESSED on ASD.

ENSURE ASD speakers are ON to half volume.

ENSURE Reactivity Briefing Sheet printout provided with Turnover.

ENSURE procedures in progress are on SRO desk:

COPY of IPO-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator.

ENSURE Control Rods are in AUTO with Bank D at 215 steps.

ENSURE EHC pump C is in Pull Out with a Danger Tag on the Handswitch.

ENSURE Boric Acid Transfer Pump 1-01 is in Pull out with a Danger Tag on the handswitch.

ENSURE Boric Acid Transfer Pump 1-02 is in AUTO.

Control Room Annunciators in Alarm:

PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.2 - IR TRN A RX TRIP BLK PCIP-1.4 - CNDSR AVAIL STM DMP ARMED C-9 PCIP-1.6 - RX 10% PWR P-10 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.2 - IR TRN B RX TRIP BLK PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.2 - PR TRN A LO SETPT RX TRIP BLK PCIP-4.2 - PR TRN B LO SETPT RX TRIP BLK 1-ALB-9B-14.5 - ANY EHC PMP CTRL SWITCH IN PULL OUT Page 5 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 1 Page 6 of 40 Event

Description:

Atmospheric Relief Valve 1-03 fails open due to PT-2327 failure.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 1 (Key 1).

- MS13C, Steam Generator Pressure Transmitter 1-PT-2327 failure high.

Indications Available:

1-PI-2327, MSL 3 PRESS pegged high 1-ZL-2327 SG 3 ATMOS RLF VLV read OPEN light LIT Plant Computer alarm Y6704D, SG 3 ATM RLF VLV OPEN BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE Steam Generator 1-03 Steam Pressure Transmitter (PT-2327)

BOP failed high.

DIRECT performance of ABN-709, Steam Line Pressure, Steam Header US Pressure, Turbine 1st-Stage Pressure, and Feed Header Pressure Instrument Malfunction, Section 2.0.

DETERMINE 1-PI-2327 MSL 3 PRESS indicating - GREATER THAN 60 psig BOP difference between remaining channels. [Step 2.3.1]

DETERMINE 1-ZL-2327, SG 3 ATMOS RLF VLV is OPEN BOP AND 1-PI-2327, MSL 3 PRESS NOT indicating NORMAL.

Manually CLOSE 1-ZL-2327, SG 3 ATMOS RLF VLV. [Step 2 RNO]

US Evaluate Technical Specifications. [Step 2.3.11]

DETERMINE no LCO entry required.

US INITIATE a Condition Report per STA-421, as applicable. [Step 2.3.12]

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 2.

Page 6 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 2 Page 7 of 40 Event

Description:

Loss of Digital Rod Position Indication Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 2 (Key 2).

- RD12C, Digital Rod Position Power Failure.

Indications Available:

6D-3.6 - DRPI URGENT FAIL 6D-3.7 - ANY ROD AT BOT 6D-4.6 - DRPI NON-URGENT FAIL 6D-4.7 - 2 ROD AT BOT Control Rod Position Indication bezel is dark RO RESPOND to Annunciator Alarm Procedures.

RECOGNIZE Control Rod Position bezel is dark and DETERMINE Digital RO Rod Position Indication failure.

DIRECT performance of ABN-712, Rod Control System Malfunction, Section US 4.0.

DETERMINE CONTROL ROD POSN bezel - NOT INDICATING.

RO

[Step 4.3.1]

Page 7 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 2 Page 8 of 40 Event

Description:

Loss of Digital Rod Position Indication Time Position Applicants Actions or Behavior Simulator Operator Note: When dispatched to check the breakers on 1C14. Wait 3 minutes, then report, All the breakers are closed, I will contact Prompt Team Electricians to troubleshoot.

Check power supply breakers on uC14 (SFGD 832' wall behind the rod control cabinets) - ON [Step 4.3.1 RNO b.]

1C14/1/BKR, DATA CAB A 1C14/2/BKR, DATA CAB B 1C14/3/BKR, Control Board Display If necessary, shift uC14 power supply per SOP-608A/B.

[Step 4.3.1 RNO c.]

US DETERMINE Unit is in MODE 1. [Step 4.3.2]

RO/US Check Inoperable DRPIs - < ONE PER GROUP PLACE 1/1-RBSS, Control Rod Bank Select Switch in MANUAL.

RO

[Step 4.3.3 RNO a.]

Monitor and record RCS Tavg once per hour. [Step 4.3.3 RNO b]

Determine position of non-indicating rod(s) by core power distribution measurement information: [Step 4.3.3 RNO c]

1) Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

2) Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after any motion of non-indicating rod which exceeds 24 steps in one direction since last determination of rod's position.

-OR-

3) Reduce THERMAL POWER to less than 50% of RTP per IPO-003A/B within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months restore inoperable DRPI(s) to operable status such that a maximum of one per group is inoperable. [Step 4.3.3 RNO d]

Refer to TS 3.1.7B,C,E [Step 4.3.3 RNO d]

Page 8 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 2 Page 9 of 40 Event

Description:

Loss of Digital Rod Position Indication Time Position Applicants Actions or Behavior US EVALUATE Technical Specifications.

LCO 3.1.7, Rod Position Indication.

CONDITION A - One DRPI per group inoperable for one or more groups.

ACTION A.1 - Verify the position of the rods with inoperable position indicators indirectly by using core power distribution measurement information.

OR Reduce THERMAL POWER TO < 50% RTP.

CONDITION B - More than one DRPI per group inoperable.

ACTION B.1 - Immediately place the control rods under manual control.

ACTION B.2 - Monitor and record RCS TAVG once per hour.

ACTION B.3 - Verify the position of the rods with inoperable position indicators indirectly by using core power distribution measurement information once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

ACTION B.4 - Restore inoperable position indicators to OPERABLE status such that a maximum of one DRPI per group is inoperable within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 3.

Page 9 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 3 Page 10 of 40 Event

Description:

Steam Generator Level Transmitter LT-552 Failure High.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 3 (Key 3).

- RX04B, Steam Generator 1-02 Level Transmitter (LT-552) fails high.

Indications Available:

8A-2.8 - SG 2 STM & FW FLO MISMATCH 8A-2.12 - SG 2 LVL DEV 1-LI-552, SG 2 LVL (NR) CHAN II indication failed high Plant Computer Alarm L6423A SG2 LVL (NR) CHAN II HI-HI RO/BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE Steam Generator 1-02 Level Transmitter (LT-552) failed high.

DIRECT performance of ABN-710, Steam Generator Level Instrumentation US Malfunction, Section 2.0.

BOP DETERMINE controlling level channel has failed. [Step 2.3.1]

Manually CONTROL 1-FK-520, SG 2 FW FLO CTRL as necessary to BOP maintain Steam Generator 1-02 at programmed level. [Step 2.3.2]

VERIFY instruments on common instrument line indicate NORMAL.

BOP

[Step 2.3.3]

VERIFY Loop 2 Instruments FT-522, LT-529, FT-523, and LT-528 responding normally per Attachment 1.

Page 10 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 3 Page 11 of 40 Event

Description:

Steam Generator Level Transmitter LT-552 Failure High.

Time Position Applicants Actions or Behavior DETERMINE all HI-HI level bistable windows on TSLB-3 for Steam BOP Generator 1-02 are DARK. [Step 2.3.4]

BOP VERIFY automatic SG level control available: [Step 2.3.5]

OBSERVE alternate level control channel 1-LI-529A indication NORMAL. [Step 2.3.5.a]

DETERMINE automatic level control desired by Unit Supervisor.

[Step 2.3.5.b]

PLACE 1-LS-529C, Steam Generator 2 Level Channel Select to the LY-529 BOP position. [Step 2.3.6]

VERIFY affected Steam Generator level is stable at program level.

BOP

[Step 2.3.7]

Page 11 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 3 Page 12 of 40 Event

Description:

Steam Generator Level Transmitter LT-552 Failure High.

Time Position Applicants Actions or Behavior PLACE 1-FK-520, SG 2 FW FLO CTRL in AUTO and MONITOR operation.

BOP

[Step 2.3.8]

US EVALUATE Technical Specifications.

LCO 3.3.1.E, Reactor Trip System Instrumentation.

CONDITION E - One channel inoperable.

ACTION E.1 - Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

LCO 3.3.2.D, ESFAS Instrumentation.

CONDITION D - One channel inoperable.

ACTION D.1 - Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

LCO 3.3.2.I, ESFAS Instrumentation.

CONDITION I - One channel inoperable.

ACTION I.1 - Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 4.

Page 12 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 4 Page 13 of 40 Event

Description:

Main Feedwater Pump 1-02 trips. Control rods require manual insertion.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 4 (Key 4).

- FW03B, Main Feedwater Pump 1-02 trip.

- RD15A, Automatic Rod Control Failure, Manual Rod Control Works.

Indications Available:

1-ALB-8A-1.3 - FWPT B TRIP 1-ALB-8A-1.8 - SG 1 STM & FW FLO MISMATCH 1-ALB-8A-2.8 - SG 2 STM & FW FLO MISMATCH 1-ALB-8A-3.8 - SG 3 STM & FW FLO MISMATCH 1-ALB-8A-4.8 - SG 4 STM & FW FLO MISMATCH 1-ALB-6D-1.9 - ANY TURB RUNBACK EFFECTIVE 1-ALB-6D-1.10 - AVE TAVE-TREF DEV RO/BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE trip of Main Feedwater Pump B, turbine runback in progress RO/BOP with no automatic control rod insertion.

DIRECT performance of ABN-302, Feedwater, Condensate, Heater Drain US System Malfunction, Section 2.0.

RO VERIFY automatic plant response. Determine that a Turbine Runback is IN BOP PROGRESS and control rods are NOT moving in automatic. [Step 2.3.1]

SELECT 1/1-RBSS, CONTROL BANK SELECT in MANUAL and insert RO control rods. [Step 2.3.1 RNO a]

Page 13 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 4 Page 14 of 40 Event

Description:

Main Feedwater Pump 1-02 trips. Control rods require manual insertion.

Time Position Applicants Actions or Behavior RO STABILIZE Reactor power. [Step 2.3.2]

BOP VERIFY Main Feedwater Flow to Steam Generators. [Step 2.3.3]

Main Feed Pump 1-01 RUNNING AND Main Feedwater ALIGNED [Step 2.3.3.a]

VERIFY feedwater header pressure greater than main steam header BOP pressure. [Step 2.3.3.b]

BOP VERIFY 1-FK-2290, FWP B RECIRC FLO CTRL - CLOSED [Step 2.3.3.c]

VERIFY Tave - TRENDING TO TREF. [Step 2.3.4]

RO/BOP 1-TI-412A, AVE TAVE - TREF DEV Page 14 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 4 Page 15 of 40 Event

Description:

Main Feedwater Pump 1-02 trips. Control rods require manual insertion.

Time Position Applicants Actions or Behavior CONTROL Main Feed flow to maintain narrow range level between 60% and BOP 75%. [Step 2.3.5]

BOP Monitor Main Feedwater response. [Step 2.3.6]

VERIFY differential pressure between feedwater and main steam pressure 80 psid to 181 psid (P5446A) [Step 2.3.6.a]

SG FW FLO CTRL Valves - AUTO [Step 2.3.6.b]

1-FK-510, SG 1 FW FLO CTRL 1-FK-520, SG 2 FW FLO CTRL 1-FK-530, SG 3 FW FLO CTRL 1-FK-540, SG 4 FW FLO CTRL VERIFY MFP flow 1-FI-2289, FWP A SUCT FLO is < 22,000 gpm

[Step 2.3.6.c]

RO VERIFY the following: [Step 2.3.7]

RODS - ABOVE ROD INSERTION LIMIT [Step 2.3.7.a]

FLUX - (AFD) WITHIN LIMITS [Step 2.3.7.b]

WHEN steam dumps close, THEN reset steam dump arming signal (C-7 BOP interlock). [Step 2.3.8]

43/1-SD, STM DMP MODE SELECT NOTIFY QSE Generation Controller and update GAPS to Create Current US Condition for the down power. [Step 2.3.9]

Page 15 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 4 Page 16 of 40 Event

Description:

Main Feedwater Pump 1-02 trips. Control rods require manual insertion.

Time Position Applicants Actions or Behavior US INITIATE equipment repairs per STA-606. [Step 2.3.10]

US CHECK Chemistry Sampling Requirement: [Step 2.3.11]

SG ARVS - REMAINED CLOSED AND TDAFW Pump - REMAINED STOPPED [Step 2.3.11.a]

NOTIFY Chemistry to perform RCS Isotopic analysis for iodine between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after power change. [Step 2.3.11.b RNO]

RO RESET Turbine Runback per ABN-401. [Step 2.3.12]

Return to procedure and step in effect AND adjust power as desired.

US

[Step 2.3.13]

Examiner Note: The following steps are from ABN-401, Main Turbine Malfunction, Section 8.0, Turbine Reloading After Runback. These steps are used for RESET of the turbine runback.

Verify ANY TURB RUNBACK EFFECTIVE (6D-1.9) - DARK BOP

[Step 8.3.1]

In the Load Control Section, ENSURE Load Rate Setpoint Controller is set BOP to support reload or current plant conditions. [Step 8.3.2]

Page 16 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 4 Page 17 of 40 Event

Description:

Main Feedwater Pump 1-02 trips. Control rods require manual insertion.

Time Position Applicants Actions or Behavior In the Load Control Section, ensure the Load Target Setpoint Controller is BOP set for actual MW. [Step 8.3.3]

BOP DETERMINE Manual Runback was not used. [Step 8.3.4]

BOP Verify the turbine runback is reset.

Verify Runback -LESS THAN 15% WITHIN ONE HOUR.

US Notify Chemistry to perform RCS Isotopic analysis for iodine between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after power change. [Step 8.3.6 RNO]

US Control turbine load as required per IPO-003A/B. [Step 8.3.7]

US Notify Nuclear Engineering of runback. [Step 8.3.8]

US Initiate a CR, if required per STA-421. [Step 8.3.9]

US Initiate repair per STA-606. [Step 8.3.10]

When turbine runback has been reset, or at the discretion of the Lead Examiner, PROCEED to EVENT 5.

Page 17 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5 Page 18 of 40 Event

Description:

RCP 1-02 shaft breaks. Reactor fails to auto trip.

Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 5 (Key 5).

- RC04B, RCP 1-02 shaft shear.

Indications Available:

Multiple alarms RECOGNIZE loss of Reactor Coolant System flow, and failure of the reactor RO/BOP to automatically trip.

Manually Trip Reactor due to RCP trip prior to exiting EOP-0.0A, CRITICAL TASK Reactor Trip or Safety Injection.

CRITICAL TASK RO PLACE 1/1-RTC, RX TRIP BKR in TRIP to manually TRIP the Reactor.

US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip: [Step 1]

VERIFY Reactor Trip Breakers - AT LEAST ONE OPEN.

Neutron flux - DECREASING [Step 1.a]

Examiner Note: Digital Rod Position Indication is deenergized, the reactor operator will emergency borate from the foldout page (Attachment 1A) after step 4 of EOP-0.0A, Reactor Trip or Safety Injection.

RO All control rod position rod bottom lights - ON [Step 1.b]

BOP VERIFY Turbine Trip: [Step 2]

VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2]

BOP VERIFY Power to AC Safeguards Buses: [Step 3]

VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.

[Step 3.a]

VERIFY both AC Safeguards Buses - ENERGIZED. [Step 3.b]

RO/BOP DETERMINE SI is NOT actuated and is NOT required. [Step 4]

Page 18 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5 Page 19 of 40 Event

Description:

RCP 1-02 shaft breaks. Reactor fails to auto trip.

Time Position Applicants Actions or Behavior Examiner Note: The RO will initiate Emergency Boration in accordance with the Foldout page step of EOP-0.0A, Attachment 1A, Step 2., 2nd bullet, Control rod position indication is NOT available (3600 gallons of 7000 ppm boric acid).

The crew should trip RCP 1-02 after immediate actions are completed and verbalized.

Initiate Emergency Boration per ABN-107, due to Control rod position indication RO is NOT available (3600 gallons of 7000 ppm boric acid). [Step Att. 1A 2. 2nd bullet]

Examiner Note: EOS-0.1A, Reactor Trip Response steps begin here.

US Transition to EOS-0.1A, Reactor Trip Response.

RO CHECK RCS Temperature -

Check RCPs - ANY RUNNING [Step 1 a.]

RCS AVERAGE TEMPERATURE STABLE AT OR TRENDING TO 557°F

[Step 1 b.]

RO/BOP CHECK FW Status:

VERIFY Reactor Trip Breakers - OPEN. [Step 2 a.]

CHECK RCS average temperatures < 564ºF. [Step 2 b.]

VERIFY Feedwater Isolation - ISOLATION Complete. [Step 2 c.]

BOP DETERMINE total AFW flow to SGs > 460 GPM. [Step 2 d.]

RO Check PRZR Level Control:

Level - GREATER THAN 17% [Step 3 a.]

Verify charging - INSERVICE [Step 3 b.]

Verify letdown - IN SERVICE [Step 3 c.]

Level - TRENDING TO 25% [Step 3 d.]

Page 19 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5 Page 20 of 40 Event

Description:

RCP 1-02 shaft breaks. Reactor fails to auto trip.

Time Position Applicants Actions or Behavior RO CHECK PRZR Pressure Control:

DETERMINE PRZR Pressure > 1820 PSIG. [Step 4 a.]

DETERMINE PRZR Pressure - TRENDING TO 2235 PSIG. [Step 4 b.]

BOP CHECK Steam Generator Levels:

Narrow ranger level - 43% [Step 5 a.]

Maintain total feed flow greater than 460 gpm until narrow range level greater than 43% in at least one SG. [Step 5 a. RNO a.]

Control feed flow to maintain narrow range level between 43% and 60%.

[Step 5 b.]

After checking SG Narrow range levels, or at the discretion of the Lead Examiner, PROCEED to EVENT 6.

Page 20 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 21 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 6 (Key 6).

- RC09B2, Large Break LOCA Indications:

RCS Pressure lowering.

PRZR Level lowering.

CAG-197, Containment Air PIG alarming.

Containment Sump level and fill rate Alarms.

Containment air cooler fill rate alarms.

RECOGNIZE loss of Reactor Coolant System inventory and Initiate Safety RO/BOP injection, if not actuated automatically.

Transition to AND DIRECT performance of EOP-0.0A, Reactor Trip or Safety US Injection.

RO VERIFY Reactor Trip: [Step 1]

Examiner Note: Digital Rod Position Indication is deenergized, the reactor operator should have begun emergency boration from the foldout page (Attachment 1A) after step 4 of EOP-0.0A, Reactor Trip or Safety Injection.

All control rod position rod bottom lights - OFF [Step 1.b], emergency RO boration in progress.

BOP VERIFY Turbine Trip: [Step 2]

VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2]

BOP VERIFY Power to AC Safeguards Buses: [Step 3]

VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.

[Step 3.a]

VERIFY both AC Safeguards Buses - ENERGIZED. [Step 3.b]

RO/BOP Check SI Status: [Step 4]

Page 21 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 22 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior Check if SI Is Actuated:

RO SI actuation as indicated on the First Out Annunciator 1-ALB-6C.

SI Actuated blue status light - ON [Step 4 a.]

Verify Both Trains SI Actuated:

RO SI Actuated blue status light - ON NOT FLASHING [Step 4 b.]

Examiner Note: EOP-0.0A, Attachment 2 steps performed by the BOP are identified at the end of the scenario.

INITIATE Proper Safeguards Equipment Operation Per Attachment 2.

US/BOP

[Step 5]

RO VERIFY AFW Alignment: [Step 6]

MDAFW Pumps - RUNNING. [Step 6.a]

TDAFW Pump in PULLOUT per Foldout Page. [Step 6.b]

AFW total flow - GREATER THAN 460 GPM. [Step 6.c]

AFW valve alignment - PROPER ALIGNMENT. [Step 6.d]

RO VERIFY Containment Spray Not Required: [Step 7]

Containment pressure - HAS REMAINED LESS THAN 18.0 PSIG [Step 7.a]

Page 22 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 23 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior VERIFY Containment Spray AND Phase B Actuation initiated.

[Step 7.a RNO a.1)]

VERIFY appropriate MLB indication for CNTM SPRAY (BLUE WINDOWS)

AND PHASE B (ORANGE WINDOWS). [Step 7.a RNO a.2)]

VERIFY containment spray flow at approximately 3500 gpm per pump.

[Step 7.a RNO a.3)]

Ensure CHEM ADD TK DISCH VLVs - OPEN [Step 7.a RNO a.4)]

1-HS-4752 1-HS-4753 STOP all RCPs. [Step 7.a RNO a.5)]

RO CHECK If Main Steamlines Should Be Isolated: [Step 8]

DETERMINED Containment pressure - GREATER THAN 6.0 PSIG

[Step 8.a]

VERIFY main steam isolation complete: [Step 8.b]

Main Steam isolation valves Before MSIV drippot isolation valves RO CHECK RCS Temperature: [Step 9]

a. VERIFY RCS Average Temperature - STABLE AT OR TRENDING TO 557°F. [Step 9]

STOP dumping steam. [Step 9 RNO a.]

REDUCE total AFW flow to minimize the cooldown.

MAINTAIN a minimum of 460 gpm until level in at least one SG is greater than 50%.

STOP Turbine Driven AFW pump.

Page 23 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 24 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior RO CHECK PRZR Valve Status: [Step 10]

VERIFY PRZR Safeties - CLOSED. [Step 10.a]

VERIFY Normal PRZR Spray Valves - CLOSED. [Step 10.b]

VERIFY PORVs - CLOSED. [Step 10.c]

VERIFY Power to at least 1 Block Valve - AVAILABLE. [Step 10.d]

VERIFY Block Valves - AT LEAST ONE OPEN. [Step 10.e]

RO CHECK if RCPs Should Be Stopped: [Step 11]

RECOGNIZE that RCPs have previously been stopped.

RO/BOP CHECK if Any Steam Generator Is Faulted: [Step 12]

VERIFY any Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [Step 12.a]

-OR-VERIFY any Steam Generator pressure - COMPLETELY DEPRESSURIZED. [Step 12.a]

GO to Step 13. [Step 12.a RNO]

RO/BOP CHECK if Steam Generator Tubes Are NOT Ruptured: [Step 13]

VERIFY Condenser Off Gas radiation - NORMAL.

VERIFY Main Steam Line radiation - NORMAL.

VERIFY SG Blowdown Sample Radiation Monitor - NORMAL.

VERIFY levels in all Steam Generators - NORMAL.

RO/BOP CHECK if RCS is Intact: [Step 14]

VERIFY Containment pressure - LESS THAN 1.3 PSIG.

VERIFY Containment recirculation sump levels - NORMAL.

VERIFY Containment radiation levels - NORMAL.

GO to EOP-1.0A, Loss of Reactor or Secondary, Step 1.

[Step 14 RNO]

US TRANSITION to EOP-1.0A, Loss of Reactor or Secondary Coolant, Step 1.

Page 24 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 25 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior Examiner Note:

Shortly after entry into EOP-1.0A, ORANGE paths on Integrity and Containment will require a transition to FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition.

The Unit Supervisor should immediately exit EOP-1.0A and enter FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition.

Upon exit of FRP-0.1A, the US should immediately exit the FRP and enter FRZ-0.1A, Response to High Containment Pressure Examiner Note: FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition, steps begin here.

TRANSITION to FRP-0.1A, Response to Imminent Pressurized Thermal US Shock Condition US/RO CHECK RCS pressure - GREATER THAN 425 PSIG [Step 1]

DETERMINE total RHR pump injection flow is greater than 750 gpm.

[Step 1 RNO]

US RETURN to procedure and step in effect.

Examiner Note: FRZ-0.1A, Response to High Containment Pressure, steps begin here.

US TRANSITION to FRZ-0.1A, Response to High Containment Pressure.

US/RO CHECK Containment pressure - GREATER THAN 50 PSIG. [Step 1]

DETERMINE proper Containment Spray alignment was verified in RO/BOP EOP-0.0A. [Step 1 RNO]

US RETURN to procedure and step in effect.

Page 25 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 26 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior Examiner Note: The following steps are from EOP-1.0A, Loss of Reactor or Secondary Coolant.

US/RO CHECK If RCPs Should Be Stopped: [Step 1]

RECOGNIZE RCPs have been previously stopped.

RO/BOP CHECK if Any Steam Generator Is Faulted: [Step 2]

VERIFY any Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [Step 2.a]

VERIFY any Steam Generator pressure - COMPLETELY DEPRESSURIZED. [Step 2.a]

GO to Step 3. [Step 2.a RNO]

BOP CHECK Intact Steam Generator Levels: [Step 3]

VERIFY Narrow range level - GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT). [Step 3.a]

MAINTAIN total AFW flow greater than 460 GPM until narrow range level GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT). [Step 3.a RNO]

US CHECK Secondary Radiation NORMAL: [Step 4]

VERIFY Condenser off gas radiation - NORMAL. [Step 4]

Page 26 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 27 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior VERIFY Main Steam Line radiation - NORMAL. [Step 4]

VERIFY SG Blowdown Sample Radiation Monitor - NORMAL. [Step 4]

US CHECK PRZR PORVs and Block Valves: [Step 5]

VERIFY power Block Valves - AVAILABLE. [Step 5.a]

VERIFY PORVs - CLOSED. [Step 5.b]

VERIFY Block Valves - AT LEAST ONE OPEN. [Step 5.c]

US/RO CHECK if ECCS Flow Should Be Reduced: [Step 6]

VERIFY Secondary heat sink conditions - SATISFIED. [Step 6.a]

VERIFY RCS subcooling - GREATER THAN 25°F (55°F FOR ADVERSE CONTAINMENT). [Step 6.b]

GO to Step 7 and OBSERVE CAUTIONS Prior to Step 7.

[Step 6.b RNO]

RO/BOP RESET ESF Actuation Signals. [Step 7]

Page 27 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 28 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior PLACE both EDG EMERG STOP/START handswitches in START.

BOP

[Step 7.a]

RO/BOP RESET SI. [Step 7.b]

DEPRESS 1/1-SIRA, TRAIN A SI RESET pushbutton.

DEPRESS 1/1-SIRB, TRAIN A SI RESET pushbutton.

RO/BOP RESET SI Sequencers. [Step 7.c]

At SI Sequencer Train A Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

PLACE ON/RESET toggle switch in ON.

At SI Sequencer Train B Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

PLACE ON/RESET toggle switch in ON.

RO/BOP Reset Containment Isolation Phase A and Phase B. [Step 7.d]

DEPRESS 1/1-C1PARA, CNTMT ISOL - PHASE A RESET pushbutton.

DEPRESS 1/1-C1PARB, CNTMT ISOL - PHASE A RESET pushbutton.

DEPRESS 1/1-C1PBRA, CNTMT ISOL - PHASE B RESET pushbutton.

DEPRESS 1/1-C1PBRB, CNTMT ISOL - PHASE B RESET pushbutton.

RO/BOP RESET Containment Spray Signal. [Step 7.e]

DEPRESS 1/1-CSRA, TRAIN A CS RESET pushbutton.

DEPRESS 1/1-CSRB, TRAIN B CS RESET pushbutton.

US CHECK If RHR Pumps Should Be Stopped: [Step 8]

Page 28 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 29 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior VERIFY RCS pressure - GREATER THAN 325 PSIG (425 PSIG FOR RO/BOP ADVERSE CONTAINMENT). [Step 8.a.1)]

GO to Step 10. [Step 8.a.1) RNO]

US CHECK If Diesel Generators Should Be Stopped: [Step 10]

VERIFY both AC Safeguards Buses ENERGIZED by Offsite Power.

RO/BOP

[Step 10.a]

RO/BOP PLACE both EDG EMERG STOP/START handswitches in STOP.

[Step 10.b]

VERIFY Train A RHR Pump - AVAILABLE. [Step 11.a.1)]

DETERMINE Train A RHR Pump NOT available.

VERIFY Train B RHR Pump - AVAILABLE. [Step 11.a.1)]

VERIFY CCW to Train B RHR Pump - AVAILABLE.

[Step 11.a.1)]

VERIFY 1/1-8811B, CNTMT SMP TO RHRP 2 SUCT ISOL VLV -

AVAILABLE. [Step 11.a.1)]

VERIFY 1/1-8804A, RHRP 1 TO CCP SUCT VLV - AVAILABLE.

[Step 11.a.2)]

VERIFY 1/1-8804B, RHRP 2 TO SIP SUCT VLV - AVAILABLE.

[Step 11.a.2)]

CHECK Auxiliary Building and Safeguards Building radiation - NORMAL:

RO/BOP

[Step 11.b]

CHECK PC-11 monitors - NORMAL OR Notify Radiation Protection to take local Radiation Surveys. [Step 11.b]

NOTIFY Chemistry to obtain RCS samples to assist in determining US extent of the accident. [Step 11.c]

Page 29 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 30 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior US CONTACT Plant Staff to EVALUATE plant equipment. [Step 11.d]

US CHECK if RCS Cooldown and Depressurization Is Required: [Step 12]

VERIFY RCS pressure - GREATER THAN 325 PSIG (425 PSIG FOR RO/BOP ADVERSE CONTAINMENT). [Step 12.a]

VERIFY RHR Pump flow greater than 750 GPM and GO to Step 13.

RO/BOP

[Step 12.a RNO]

US CHECK If Transfer to Cold Leg Recirculation Is Required. [Step 13]

VERIFY RWST Level - LESS THAN LO-LO LEVEL.

RO/BOP

[Step 13.a]

US TRANSITION to EOS-1.3A, Transfer to Cold Leg Recirculation, Step 1.

[Step 13.b]

Examiner Note: The following steps are from EOS-1.3A, Transfer to Cold Leg Recirculation.

US/RO RESET SI. [Step 1]

RECOGNIZE SI previously reset.

RO VERIFY CCW Flow As Required: [Step 2]

From RHR heat exchangers From Containment Spray heat exchangers Page 30 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 31 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior CRITICAL TASK Transfer a single train of ECCS to Cold Leg Recirculation per EOS-1.3A, STATEMENT Transfer to Cold Leg Recirculation prior to RWST Empty alarm.

CRITICAL RO/BOP Align ECCS For Cold Leg Recirculation: [Step 3]

TASK Check open CNTMT SMP TO RHRP 1 AND RHRP 2 SUCT ISOL VLVS:

[Step 3.a]

1/1-8811A 1/1-8811B RO Close RWST TO RHRP 1 AND RHRP 2 SUCT VLVS: [Step 3.b]

1/1-8812A 1/1-8812B BOP Close SIP 1 AND SIP 2 MINIFLO VLVS: [Step 3.c]

1/1-8814A 1/1-8814B 1/1-8813 RO Close RHRP 1 AND RHRP 2 XTIE VLVS: [Step 3.d]

Page 31 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 32 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior 1/1-8716A 1/1-8716B RO Close the CCP ALT MINIFLO ISOL VLVS: [Step 3.e]

1/1-8511A 1/1-8512B 1/1-8511B 1/1-8512A BOP Open SI < - -> CHRG SUCT HDR XTIE VLVS: [Step 3.f]

1/1-8807A 1/1-8807B Open RHRPs TO CCP / SIP SUCT VLVs: [Step 3.g]

1/1-8804A 1/1-8804B US/RO Align Containment Spray System for Recirculation: [Step 4]

Check RWST level - LESS THAN 6% [Step 4.a]

Continue with Step 5. [Step 4.a RNO]

Page 32 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 33 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior RO/BOP Perform The Following To Complete Recirculation Alignment: [Step 5]

DETERMINE ECCS aligned for cold leg recirculation. [Step 5.a]

Verify closed CCP MINIFLO VLVS: [Step 5.b]

1/1-8110 1/1-8111 RO Close RWST TO CHRG PMP SUCT VLVS: [Step 5.c]

1/1-LCV-112D 1/1-LCV-112E Verify CCP injection flow. [Step 5.d]

BOP Close RWST TO SIP SUCT VLV: [Step 5.e]

1/1-8806 Verify SIP discharge flow (s). [Step 5.f]

Check RHR status: [Step 5.g]

Train B RHR running in cold leg recirculation.

Reset RHR Auto switchover.

Check Containment Spray aligned for recirculation. [Step 5.h]

Complete Step 4.b PRIOR TO continuing. [Step 5.h RNO]

Page 33 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6, 7, 8 Page 34 of 40 Event

Description:

LBLOCA, RHR 1-02 Fail To Auto Start, 1-01 RHR Trips, CT Smp Suct Vlv 4783 Stuck Time Position Applicants Actions or Behavior BOP Realign Containment Spray System as follows: [Step 4.b]

Open CNTMT SMP TO CSP 1 & 3 AND 2 & 4 SUCT ISOL VLVs:

1-HS-4782 1-HS-4783 BOP DETERMINE that 1-HS-4783 will NOT open. [Step 4.b RNO]

Place CSPs 1-02 and 1-04 in PULL-OUT. [Step 4.b RNO Step 1)]

Place affected CS HX OUT VLV in PULL-OUT.

US Consult Plant Staff to determine contingency actions.

Close RWST TO CSP 1 & 3 AND 2 & 4 SUCT VLVs:

1-HS-4758 1-HS-4759 BOP IF containment spray pumps have been stopped due to RWST level, THEN perform the following:

DETERMINE containment spray pumps have not been stopped.

Verify Monitor Lights for CNTMT SMP RECIRC on 1-MLB-4A3 and 1-MLB-RO/BOP 4B3 are LIT. [Step 5.i]

BOP Record containment recirculation sump level:

__________________ feet [Step 5.j]

BOP Make plant announcement that recirculation flow has been established for ECCS or Containment Spray as applicable. [Step 5.k]

When recirculation flow has been established and plant announcement has been made, or at Lead Examiner's discretion, TERMINATE the scenario.

Page 34 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7 Page 35 of 40 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior Examiner Note: These steps are performed by the BOP per EOP-0.0, Reactor Trip or Safety Injection, Attachment 2 BOP VERIFY SSW Alignment: [Step 1]

VERIFY SSW Pumps - RUNNING. [Step 1.a]

VERIFY EDG Cooler SSW return flow. [Step 1.b]

BOP VERIFY Safety Injection Pumps - RUNNING. [Step 2]

VERIFY Containment Isolation Phase A - APPROPRIATE MLB LIGHT BOP INDICATION (RED WINDOWS). [Step 3]

VERIFY Containment Ventilation Isolation - APPROPRIATE MLB LIGHT BOP INDICATION (GREEN WINDOWS). [Step 4]

BOP VERIFY CCW Pumps - RUNNING. [Step 5]

Page 35 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7 Page 36 of 40 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior CRITICAL TASK Manually start at least one low-head (RHR pump) ECCS pump before STATEMENT transition out of EOP-0.0A, Reactor Trip or Safety Injection.

BOP VERIFY RHR Pumps - RUNNING. [Step 6]

RECOGNIZE RHR Pump 1-01 has tripped.

CRITICAL Determine 1-02 RHR pump did NOT auto start, AND START 1-02 BOP TASK RHR pump.

BOP VERIFY Proper CVCS Alignment: [Step 7]

VERIFY both CCPs - RUNNING. [Step 7.a]

VERIFY Letdown Relief Valve Isolation: [Step 7.b]

Letdown Orifice Isolation Valves - CLOSED. [Step 7.b.1)]

Letdown Isolation Valves 1/1-LCV-459 & 1/1-LCV-460 - CLOSED.

[Step 7.b.2)]

BOP VERIFY ECCS flow: [Step 8]

CCP SI flow indicator - CHECK FOR FLOW. [Step 8.a]

RCS pressure - LESS THAN 1700 PSIG (1800 PSIG FOR ADVERSE CONTAINMENT). [Step 8.b]

SIP discharge flow indicator - CHECK FOR FLOW. [Step 8.c]

RCS pressure - LESS THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT). [Step 8.d]

GO to Step 9. [Step 8.d RNO]

BOP VERIFY Feedwater Isolation Complete: [Step 9]

Feedwater Isolation Valves - CLOSED.

Feedwater Isolation Bypass Valves - CLOSED.

Feedwater Bypass Control Valves - CLOSED.

Feedwater Control Valves - CLOSED.

BOP VERIFY Diesel Generators - RUNNING. [Step 10]

Page 36 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7 Page 37 of 40 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior BOP VERIFY Monitor Lights for SI Load Shedding on 1-MLB-9 and 1-MLB LIT. [Step 11]

VERIFY Proper SI alignment - PROPER MLB LIGHT INDICATION.

BOP

[Step 12]

BOP INITIATE periodic monitoring of Spent Fuel Cooling. [Step 13]

Spent Fuel Pool temperature (T2900A, T2901A).

Spent Fuel Pool level (L4800A, L4801A, L4802A, L4803A).

BOP VERIFY Components on Table 1 are Properly Aligned. [Step 14]

Location Equipment Description Condition CB-03 X-HS-5534 H2 PRG SPLY FN 4 STOPPED CB-03 X-HS-5532 H2 PRG SPLY FN 3 STOPPED CB-04 1/1-8716A RHRP 1 XTIE VLV OPEN CB-04 1/1-8716B RHRP 2 XTIE VLV OPEN CB-06 1/1-8153 XS LTDN ISOL VLV CLOSED/H.S. IN CLOSED Page 37 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7 Page 38 of 40 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior CB-06 1/1-8154 XS LTDN ISOL VLV CLOSED/H.S. IN CLOSED CB-07 1/1-RTBAL RX TRIP BKR OPEN CB-07 1/1-RTBBL RX TRIP BKR OPEN CB-07 1/1-BBAL RX TRIP BYP BKR OPEN/DEENERGIZED CB-07 1/1-BBBL RX TRIP BYP BKR OPEN/DEENERGIZED CB-08 1-HS-2397A SG 1 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2111C FWPT A TRIP TRIPPED CB-08 1-HS-2112C FWPT B TRIP TRIPPED CB-09 1-HS-2490 CNDS XFER PUMP STOPPED (MCC deenergized on SI)

CV-01 X-HS-6181 PRI PLT SPLY FN 17 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6202 PRI PLT SPLY FN 20 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6209 PRI PLT SPLY FN 21 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6216 PRI PLT SPLY FN 22 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6223 PRI PLT SPLY FN 23 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6230 PRI PLT SPLY FN 24 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-3631 UPS & DISTR RM A/C FN 1 & STARTED BSTR FN 42 CV-01 X-HS-3632 UPS & DISTR RM A/C FN 2 & STARTED BSTR FN 43 CV-01 1-HS-5600 ELEC AREA EXH FN 1 STOPPED/DEENERGIZED CV-01 1-HS-5601 ELEC AREA EXH FN 2 STOPPED/DEENERGIZED CV-01 1-HS-5602 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 3 & EXH DMPR Page 38 of 40 CPNPP NRC 2015 Simulator Scenario 4

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7 Page 39 of 40 Event

Description:

Main Steam Line Break on SG 1-02 inside containment.

Time Position Applicants Actions or Behavior CV-01 1-HS-5603 MS & FW PIPE AREA EXH STOPPED/DEENERGIZED FN 4 & EXH DMPR CV-01 1-HS-5618 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 17 CV-01 1-HS-5620 MS & FW PIPE AREA SPLY STOPPED/DEENERGIZED FN 18 CV-03 X-HS-5855 CR EXH FN 1 STOPPED/DEENERGIZED CV-03 X-HS-5856 CR EXH FN 2 STOPPED/DEENERGIZED CV-03 X-HS-5731 SFP EXH FN 33 STOPPED/DEENERGIZED CV-03 X-HS-5733 SFP EXH FN 34 STOPPED/DEENERGIZED CV-03 X-HS-5727 SFP EXH FN 35 STOPPED/DEENERGIZED CV-03 X-HS-5729 SFP EXH FN 36 STOPPED/DEENERGIZED Examiner Note: The next four (4) steps would be performed on Unit 2.

CB-03 2-HS-5538 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5539 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5537 AIR PRG SPLY ISOL DMPR CLOSED CB-03 2-HS-5536 AIR PRG SPLY ISOL DMPR CLOSED NOTIFY Unit Supervisor attachment instructions complete AND to BOP IMPLEMENT FRGs as required. [Step 14]

EOP-0.0A, Attachment 2 steps are now complete.

Page 39 of 40 CPNPP NRC 2015 Simulator Scenario 4

Scenario Event Description June 2015 NRC Exam Scenario 4

CPNPP 2015 NRC Initial Scenario 4

Load IC17

INITIAL CONDITIONS

EHC Pump C Tagged out.

IOR DITCHS6552 f:0

Complicates Emergency Boration on DRPI loss

1-01 Boric Acid pmp oos IOR DICVAPBA1 f: 0

RHR 1-02 Fails to auto start (Event 7)

IMF RH01D f:1

CT SMP Suct 2 stuck closed 4783 (Event 8)

IMF CS05B f:1

Reactor Auto Trip Fail (Event 5)

IMF RP01 f:1

EVENTS

2327 Fail Hi, ARV 1-03 Opens (Event 1)

IMF MS13C f:1300 k:1

Loss of DRPI (Event 2)

IMF RD12C f:1 k:2

SG 1-02 LT 552 fails hi (Event 3)

IMF RX04B f:100 k:3

MFP 1-02 Trips (Event 4)

IMF FW03B f:1 k:4

Auto Rods Failure (Event 4)

IMF RD15A f:1 k:4

RCP 1-02 Shaft Breaks (Event 5)

IMF RC04B f:1 k:5

RC Loop 2 CL LBLOCA (Event 6)

IMF RC09B2 f:1 d:10 k:6

RHR 1-01 Trips after SI (Event 7)

IMF RH01A f:1 d:50 k:6 Page 40 of 40 CPNPP NRC 2015 Simulator Scenario 4

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