Text

11 Draft Operating Test
	ML17355A641
Person / Time
Site:	Wolf Creek
Issue date:	11/15/2017
From:	Vincent Gaddy; Operations Branch IV
To:	; Wolf Creek
References
	50-482/17-11 50-482/OL-17
	Download: ML17355A641 (287)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: WCNOC Date of Examination: 11/6/17 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

A1 - PERFORM A MANUAL Perform a manual shutdown margin calculation SHUTDOWN MARGIN CALCULATION using STS RE-004, SHUTDOWN MARGIN R, M DETERMINATION, Attachment A, Shutdown Conduct of Operations Margin Calculation Short Form.

K/A: 2.1.37 (4.3/4.6) - Knowledge of procedures, guidelines, or limitations associated with reactivity management.

A2 - ESTIMATE TIME TO BOIL, TIME R, D Estimate time to boil, time to onset of core TO ONSET OF CORE UNCOVERING, uncovering, and time to complete core AND TIME TO COMPLETE CORE uncovering using Figures 5 and 6 per OFN EJ-UNCOVERING 015, LOSS OF RHR COOLING, Step 31.

Conduct of Operations K/A: 2.1.25 (3.9/4.2) - Ability to interpret reference materials, such as graphs, curves, tables, etc.

A3 - DETERMINE ISOLATION POINTS Given a Clearance Order Worksheet, work FOR A MDAFW PUMP CLEARANCE order instructions, and drawings, determine ORDER R, N isolation points to provide a safe work boundary for a MDAFW pump bearing oil change using Equipment Control AP 21E-001, CLEARANCE ORDERS.

K/A: 2.2.13 (4.1 / 4.3) - Knowledge of tagging and clearance procedures.

A4 - DETERMINE DAC HOURS R, D Calculate the dose an Operator would receive working a job with and without wearing a full-face respirator and determine which provides Radiation Control the Operator with less dose.

K/A: 2.3.12 (3.2/3.7) - Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

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

ES-301 Administrative Topics Outline Form ES-301-1

Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes) (2)

(N)ew or (M)odified from bank ( 1) (2)

(P)revious 2 exams ( 1, randomly selected) (0)

Facility: WCNOC Date of Examination: 11/6/17 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

A5 - REVIEW A SHUTDOWN MARGIN Review a completed manual shutdown margin CALCULATION calculation for approval, identify errors, and R, M disapprove using STS RE-004, SHUTDOWN Conduct of Operations MARGIN DETERMINATION, Attachment A, Shutdown Margin Calculation Short Form.

K/A: 2.1.37 (4.3/4.6) - Knowledge of procedures, guidelines, or limitations associated with reactivity management.

A6 - DETERMINE LICENSED R, N Review watch standing history and Determine OPERATOR LICENSE STATUS ROs 1 & 4 license status are inactive, ROs 2 &3 license status are active, and ROs 2 & 3 can be assigned to stand watch as the RO per AI 26C-Conduct of Operations 002, CONDITIONS FOR MAINTAININGIN INDIVIDUAL LICENSES AT WOLF CREEK.

K/A: 2.1.4 (3.3/3.8) - Knowledge of individual licensed Operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

A7 - REVIEW A CLEARANCE ORDER R, D Review a completed clearance order for approval, identify the critical errors, and Equipment Control disapprove the clearance order using AP 21E-001, CLEARANCE ORDERS.

K/A: 2.2.13 (4.1/4.3) - Knowledge of tagging and clearance procedures.

A8 - REVIEW A LIQUID RELEASE R, N Given a prepared liquid release permit, identify PERMIT critical errors and determine if it is NOT ready to be authorized for release to the environment.

Radiation Control K/A: 2.3.6 (2.0/3.0) - Ability to approve release permits.

ES-301 Administrative Topics Outline Form ES-301-1 A9 - MAKE A PROTECTIVE ACTION R, M Given a set of conditions, determine a RECOMMENDATION GENERAL EMERGENCY exists per APF 06-002-01, EMERGENCY ACTION LEVELS and Make a Protective Action Recommendation Emergency Plan using EPP 06-006, PROTECTIVE ACTION RECOMMENDATIONS, Attachment A, K/A: 2.4.44 (2.4/4.4) - Knowledge of Protective Action Recommendation Chart.

emergency plan protective action recommendations.

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

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

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

(P)revious 2 exams ( 1, randomly selected) (0)

WC-2017-11 JPM A1 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

DETERMINE SHUTDOWN Job Performance Measure No: A1 MARGIN USING STS RE-004, SHUTDOWN MARGIN CALCULATION K/A

Reference:

2.1.37 (4.3 RO): Knowledge of procedures, guidelines, or limitations associated with reactivity management.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Initial Given:

Conditions:

The date is November 1, 2017. Current time is 1100.

The unit tripped 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago after 180 days of full power operation.

All systems functioned as designed.

Core Burnup is 7000 MWD/MTU.

Current boron concentration is 1220 ppm.

RCS Temperature is stable at 557°F using steam dumps Initiating CRS directs you to determine if shutdown margin is met using STS RE-004, Cue: SHUTDOWN MARGIN DETERMINATION, ATTACHMENT A, SHUTDOWN MARGIN CALCULATION SHORT FORM.

Use references provided.

Notify the CRS of results when Shutdown Margin Determination is complete.

Task Applicant performed Shutdown Margin Attachment A, calculated a minimum Standard:

boron concentration of 1327 - 1355 ppm, and determined Shutdown Margin is NOT met.

Attachment A, SHUTDOWN MARGIN CALCULATION SHORT FORM of STS Required RE-004, SHUTDOWN MARGIN DETERMINATION Materials:

WCRX-27 Rev.18, CONTROL ROOM OPERATING CURVES AND TABLES REFERENCE MANUAL (Dated 9/26/17)

WC-2017-11 JPM A1 Form ES-C-1 WCRX-27 CONTROL ROOM OPERATING CURVES AND TABLES

References:

REFERENCE MANUAL, Rev 18 STS RE-004, SHUTDOWN MARGIN DETERMINATION, Rev 30A Time No Alternate No Validation 20 minutes Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP

- CRITICAL STEP CUE STANDARD

1. Applicant entered date and time Step A.1.1: from initial conditions.

PRESENT CONDITIONS: Date / Time:

Current Date/Time 11/1/2017 / 1100 S/U

2. Applicant entered Shutdown Step A.1.2: date and time from initial conditions.

Shutdown Date/Time Date / Time:

11/1/2017 / 0600 S/U

3. Applicant entered Burnup Step A.1.3: MWD/MTU from initial conditions.

Core Average Burnup Burnup: 7,000 S/U

WC-2017-11 JPM A1 Form ES-C-1 JPM STEP / PROCEDURE STEP

- CRITICAL STEP CUE STANDARD

4. Applicant entered RCS Step A.1.4: Average temperature from initial conditions.

Current Core Average Temperature Temperature: 557°F IF in Mode 1 or 2, THEN enter 557. S/U IF in Modes 3, 4, 5, THEN enter actual value.

5. Applicant entered concentration Step A.1.5: from initial conditions.

Current boron concentration Boron: 1220 ppm S/U 6.

Step A.1.6: Applicant entered Correction Factor 0.941 from page 5.8 Boron-10 Correction Factor WCRX-27 for 7000 MWD/MTU From Curve Book Page 5.8 S/U 7.

Step A.2.1: Applicant entered concentration from WCRX-27 page 7.1 for MINIMUM BORON 7000 MWD/MTU at 557°F of CONCENTRATION: 1569 ppm Minimum Boron Concentration, S/U per Curve Book page 7.1 at burnup (A.1.3) and temperature (A.1.4)

WC-2017-11 JPM A1 Form ES-C-1 JPM STEP / PROCEDURE STEP

- CRITICAL STEP CUE STANDARD

8. Applicant entered Xenon credit Step A.2.2: because both conditions:

Reactor operated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Apply Xenon Credit if the continuously prior to trip and following conditions are satisfied: present time is within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months from time of trip, are met.

o Reactor operated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months continuously at 95% to 100% power prior to trip.

o Present time is within 20 Applicant uses 300 ppm credit hours from the time of trip from page 3.7 of WCRX-23.

IF Xenon credit is S/U allowed, THEN enter the Xenon credit from Curve Book page 3.7, ELSE enter 0.

9. Applicant determined 1341

- Step A.2.3: ppm (+/- 1%) boron concentration by calculating:

Minimum Boron Concentration (A.2.1) - (A.2.2) + [(A.1.5) x (1 -

A.1.6)]

(1569 ppm) - (300 ppm)

+[(1220 ppm) x (1 - 0.941)].

(1569 ppm) - (300 ppm)

+[(1220 ppm) x (0.059)].

(1569 ppm) - (300 ppm) +

(71.98).

1269 + 71.98 = 1341 ppm,

(+/- 1%)

1327 - 1355 ppm S/U 10.

Step A.2.4: Applicant entered 0200 for 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months from time of Shutdown IF (A.2.2) is not and 11/2/17 as the date.

zero, THEN determine the Time and Date that this Shutdown S/U Margin calculation is accurate until (A.1.2. + 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months ), ELSE enter N/A

WC-2017-11 JPM A1 Form ES-C-1 JPM STEP / PROCEDURE STEP

- CRITICAL STEP CUE STANDARD

11. Applicant answered No to

- Step A.3.1: Cue: (If Asked) question.

Performance of the long SHUTDOWN MARGIN Is A.1.5 greater than A.2.3?

form calculation to verify DETERMINATION: Shutdown Margin is NOT Is 1220 ppm greater than 1341 required. ppm? No Is the Current Boron Concentration (A.1.5) greater than or equal to the Minimum Boron Concentration (A.2.3)? S/U Terminating cue: The JPM Is complete when the applicant has determined if current boron concentration is greater than or equal to minimum, or not.

STOP TIME:

WC-2017-11 JPM A1 Form ES-C-1 Initial Conditions:

Given:

The date is November 1, 2017. Current time is 1100.

The unit tripped 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago after 180 days of full power operation.

All systems functioned as designed.

Core Burnup is 7000 MWD/MTU.

Current boron concentration is 1220 ppm.

RCS Temperature is stable at 557°F using steam dumps.

Initiating Cue:

CRS directs you to determine if shutdown margin is met using STS RE-004, SHUTDOWN MARGIN DETERMINATION, ATTACHMENT A, SHUTDOWN MARGIN CALCULATION SHORT FORM.

Use references provided.

Circle answer choice below and notify the CRS of results when Shutdown Margin Determination is complete by providing the completed ATTACHMENT A work sheet.

Minimum Boron Concentration = ___________________________

Minimum Shutdown Margin IS / IS NOT met.

WC-2017-11 JPM A2 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

ESTIMATE TIME TO BOIL, Job Performance Measure No: A2 TIME TO ONSET OF CORE UNCOVERY AND TIME TO COMPLETE CORE UNCOVERY K/A

Reference:

2.1.25 (3.9) Ability to interpret reference materials, such as graphs, curves, tables, etc.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Initial Given:

Conditions:

The unit was shut down 6 days ago from full power at EOL for a refueling outage.

The unit is in MODE 5.

Reduced Inventory conditions are established per GEN 00-008, RCS LEVEL LESS THAN REACTOR VESSEL FLANGE OPERATIONS.

All RHR cooling was lost 10 minutes ago at 0700.

Initiating The CRS directs you to determine the estimate time to boil, onset of core Cue: uncovery and complete core uncovery per OFN EJ-015, LOSS OF RHR COOLING, Step 31.

Task Upon completion, the Applicant will estimate time to boil, onset to boiling and Standard: core uncovery using Figures 5 AND 6 of OFN EJ-015, LOSS OF RHR COOLING, Step 31 based on six days from shutdown with the RCS Pressurized.

o Time to Boil is 27 +/- 1 minute from 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months OR Applicant may report 17

+/-1 minutes remaining to time to boil.

o Time to Onset of Core Uncovery 105 minutes +/- 5 minute OR Applicant may report 95 +/- 5 minutes remaining to onset of core uncovery.

o Time to Complete Core Uncovery 225 minutes +/- 5 minutes OR Applicant may report 215 +/- 5 minutes remaining until complete core uncovery.

WC-2017-11 JPM A2 Form ES-C-1 Required OFN EJ-015, LOSS OF RHR COOLING, REV 29A, Step 31 and Figures 5 and Materials: 6.

References:

OFN EJ-015, LOSS OF RHR COOLING, REV 29A Time No Alternate No Validation 10 Minutes Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

1. Applicant recognized from initial Step 31.a: conditions that the plant is in reduced inventory.

Check Plant - IN REDUCED INVENTORY CONDITION S/U

2. Examiner NOTE: To correctly

- Step 31.b: perform Applicant must use the Vessel Capable Of Being Estimate time to boiling, using Pressurized line on Figure 5 FIGURE 5. TIME TO BOILING IN REDUCED INVENTORY.

Using the graph estimated time to boil is approx. 27 minutes +/- 1 minute. (Acceptable range 26 to 28 minutes)

OR Applicant may report that 17 +/- 1 minutes remain.

(Acceptable range 16 to 18 minutes remain)

S/U

WC-2017-11 JPM A2 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

3. To correctly perform Applicant

-Step 31.c: must use the Onset Of Core Uncovery line on Figure 6 Estimate time to onset of core uncovery, using FIGURE 6, Using the graph estimated time TIME TO CORE UNCOVERY to uncovery is approx. 105 REDUCED INVENTORY. minutes. +/- 5 minutes (Acceptable range is 100 minutes to 110 minutes.)

OR Applicant may report that ~95 +/-

5 minutes remain. (Acceptable range is 90 to 100 minutes remaining.)

S/U 4.

-Step 31.d: To correctly perform Applicant must use the Complete Core Estimate time to complete core Uncovery line on Figure 6:

uncovery, using Figure 6, TIME Using the graph estimated time TO CORE UNCOVERY IN to uncovery is approx. 225 REDUCED INVENTORY.

minutes. +/- 5 minutes (Acceptable range is 220 to 230 minutes.)

OR Applicant may report that ~215

+/- 5 minutes remain.

(Acceptable range is 210 to 220 minutes remaining).

S/U Terminating cue: The JPM Is complete when the Applicant has analyzed information from graphs and determined the three (3) estimated times per OFN EJ-015, Step 31.

STOP TIME:

WC-2017-11 JPM A2 Form ES-C-1 Initial Conditions: Given:

The unit was shut down 6 days ago from full power at EOL for a refueling outage.

The unit is in MODE 5.

Reduced Inventory conditions are established per GEN 00-008, RCS LEVEL LESS THAN REACTOR VESSEL FLANGE OPERATIONS.

All RHR cooling was lost 10 minutes ago at 0700.

Initiating Cue:

The CRS directs you to determine the estimate time to boil, Onset of Core Uncovery and Complete Core Uncovery per OFN EJ-015, LOSS OF RHR COOLING, Step 31.

Fill out the times below and notify the CRS of results when complete.

Estimated Time To Boil:

Estimated Time to Onset of Core Uncovery:

Estimated Time to Complete Core Uncovery:

WC-2017-11 JPM A3 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

DETERMINE ISOLATION POINTS Job Performance Measure No: A3 FOR A MDAFWP CLEARANCE ORDER K/A

Reference:

2.2.13 (4.1) Knowledge of tagging and clearance procedures.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Initial The unit is in MODE 3. You are the relief RO. The B Motor Driven Auxiliary Conditions: Feedwater Pump needs to be tagged out for a bearing oil change.

Initiating Because of computer problems, ESOMS IS NOT AVAILABLE. The CRS Cue: directs you to determine the Clearance Order boundary while ESOMS is unavailable.

DETERMINE the required clearance order item(s), the instructions from the planner are to Remove Main Power and Prevent Pump Rotation On the attached worksheet, RECORD the REQUIRED ITEM(S), and the required HANG POSITION.

Identify mechanical/electrical isolation:

Task

1. AL HIS-22A, B MD AFP Control Switch Standard:

2. NB0205, B MD AFP Feeder Breaker

3. ALV0028, B MD AFP Mini-flow Recirc to CST Isolation

4. ALV0031, B MD AFP Discharge Isolation M-12AL01, P&ID for AFW Required E-13AL01B, Schematic Diagram, Motor Driven Auxiliary Feedwater Pump B Materials:

APF 21E-001-01, Rev 03 APF 21E-001-02, Rev 1A

References:

AP 21E-001, CLEARANCE ORDERS, Rev 40C Time No Alternate No Validation 30 minutes Critical: Path: Time:

WC-2017-11 JPM A3 Form ES-C-1 START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

1. The following drawings are Refer to the provided prints CUE: (If applicant asks for provided:

a work order or clearance

M-12AL01, P&ID for AFW order work sheet (COW) All information listed on

E-13AL01B, Schematic these documents are Diagram, Motor Driven included in the Initiating Auxiliary Feedwater Pump B cue.

2.

- Determine Mechanical isolation NOTE: Applicant may Applicant determines the following points for Motor Driven Auxiliary identify additional isolation valves must be placed in the Feedwater Pump B. points, including vents and CLOSED position at a minimum:

drain valves which exceed minimum requirements. ALV0028 - MD AFW Pump B Miniflow Recirc to CST Isolation NOTE: Component Description column is NOT ALV0031 - MD AFW Pump B required to be filled out. Discharge Isolation S /U 3.

- Determine Electrical isolation NOTE: Applicant may also Applicant determines the following points for Motor Driven Auxiliary include sequence, but this breaker must be OPENED and Feedwater Pump B. exceeds minimum RACKED DOWN requirements of this JPM.

NB0205 - MD AFW Pump B Feeder Breaker Applicant determines the following control switch must be placed in PULL-TO-LOCK position at a minimum AL HIS-22A - MD AFW Pump Control Switch S /U Terminating cue: The JPM Is complete when the Applicant makes notification that the clearance isolation is complete.

STOP TIME:

WC-2017-11 JPM A3 Form ES-C-1 Initial Conditions: The unit is in MODE 3. You are the relief RO. The B Motor Driven Auxiliary Feedwater Pump needs to be tagged out for a bearing oil change.

Initiating Cue: Because of computer problems, ESOMS IS NOT AVAILABLE. The CRS directs you to determine the Clearance Order boundary while ESOMS is unavailable.

DETERMINE the required clearance order item(s), the instructions from the planner are to Remove Main Power and prevent pump rotation.

On the attached worksheet, RECORD the REQUIRED ITEM(S), and the required HANG POSITION and present to the CRS upon completion.

WC-2017-11 JPM A4 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

DETERMINE DAC HOURS Job Performance Measure No: A4 K/A

Reference:

2.3.12 (3.2) - Knowledge of radiological safety principles pertaining to licensed Operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Initial You are an Off Watch Reactor Operator and Job Lead.

Conditions:

Initiating A Non Licensed Station Operator (NSO) is assigned a job in Containment to tag and Cue: drain some Emergency Core Cooling System piping.

The Radiation Protection Technician states there is a 35 mRem/hour radiation field in the area where the work will be accomplished.

The air sample taken in the area indicates a 1.5 DAC-hour field.

Historical data shows that the job takes two hours. It takes ~20% longer to do the job when wearing a full-face respirator.

Protection factor of a Full Face Air Purifying (FFAP) Respirator = 50.

1 DAC-hour = 2.5 mRem Calculate the dose the NSO would receive working the job with and without wearing a full-face respirator and determine which provides the Operator with less dose.

Task Upon completion of this JPM, the Examinee will have calculated the dose an NSO Standard: would receive working a job with (84.18 mRem) and without (77.5 mRem) wearing a full-face respirator and determined the NSO should NOT wear a respirator.

Required None Materials:

RPP 03-205, DAC-Hour Tracking, Rev. 17

References:

RPF 03-205, DAC-Hour Calculation Sheet, Rev. 7

WC-2017-11 JPM A4 Form ES-C-1 Time No Alternate No Validation 15 Minutes Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

1. (2 hr x 35 mRem/hr) + (2 hr x 1.5 Determine dose without wearing DAC-hr x 2.5 mRem/DAC-hr) a full-face respirator.

70 mRem + 7.5 mRem =

77.5 mRem without wearing a full-face respirator S/U

2. It takes ~20% longer to perform Determine dose while wearing a the task while wearing a full-face full-face respirator. respirator. So instead of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , it is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 24 minutes or 2.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

(2.4 hr x 35 mRem/hr) + (2.4 hr x 1.5 DAC-hr x 2.5 mRem/DAC-hr)/50 protection factor 84 mRem + 0.18 mRem 84.18 mRem received while wearing a full-face respirator S/U

3. Should NSO wear the full-face Do NOT wear the full-face respirator based on calculations respirator. Less dose will be performed? received by the NSO.

77.5 mRem in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months < 84.18 mRem in 2.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

S/U Terminating cue: The JPM Is complete when the applicant has completed the radiation exposure analysis and determined dose with a respirator, without respirator, and whether the job should be performed with/without a respirator.

STOP TIME:

WC-2017-11 JPM A4 Form ES-C-1 Initial Conditions: You are an Off Watch Reactor Operator and Job Lead.

Initiating Cue: A Non Licensed Station Operator (NSO) is assigned a job in Containment to tag and drain some Emergency Core Cooling System piping.

The Radiation Protection Technician states there is a 35 mRem/hour radiation field in the area where the work will be accomplished.

The air sample taken in the area indicates a 1.5 DAC-hour field.

Historical data shows that the job takes two hours. It takes ~20% longer to do the job when wearing a full-face respirator.

Protection factor of a Full Face Air Purifying (FFAP) Respirator = 50.

1 DAC-hour = 2.5 mRem Calculate the dose the NSO would receive working the job with and without wearing a full-face respirator and determine which provides the Operator with less dose.

Record results in table below and circle the correct answer.

Dose NOT Wearing Respirator:

Dose Wearing Respirator:

The NSO Should / Should NOT Wear a Respirator to perform this task.

WC-2017-11 JPM A5 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

APPROVE/DISAPPROVE A Job Performance Measure No: A5 COMPLETED MANUAL CALCULATION OF SHUTDOWN MARGIN PER STS RE-004, SHUTDOWN MARGIN DETERMINATION.

K/A

Reference:

2.1.37 (4.6) Knowledge of procedures, guidelines, or limitations associated with reactivity management.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Initial Given:

Conditions:

The current date and time is 11/7/2017, 0900.

The unit tripped 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago after 180 days of full power operation.

All systems functioned as designed.

Core Burnup is 11,000 MWD/MTU.

Current boron concentration is 1070 ppm.

RCS Temperature is stable at 557°F using steam dumps.

Due to the unavailability of the Shutdown Margin Computer Program, the Reactor Operator performed STS RE-004, SHUTDOWN MARGIN DETERMINATION ATTACHMENT A, SHUTDOWN MARGIN CALCULATION SHORT FORM.

Initiating Review the completed STS RE-004, ATTACHMENT A, identify any errors and Cue: either approve or disapprove the completed work. Complete the JPM by listing ALL errors (If any) and circling approval status.

Approve / Disapprove Applicant evaluates STS RE-004, ATTACHMENT A and disapproves after determining Task these five errors exist:

Standard: 1. Step A.1.5, used 1075 ppm instead of given 1070 ppm.

2. Step A.2.1. used 10,000 MWD/MTU as 1352 ppm. The correct boron for given 11,000 MWD/MU is 1270 ppm.

3. Step A.2.3 was calculated minimum boron as 1120 ppm. The correct minimum boron concentration is 1038 ppm.

WC-2017-11 JPM A5 Form ES-C-1

4. Step A.2.4 used the wrong time (A.1.1 vs. A.1.2) to calculate the time that the shutdown margin was accurate to. The correct time for SDM is 11/7/2017 at 2100 hrs.

5. Step A.3.1 should indicate YES. The current boron is greater than the required minimum boron to maintain shutdown margin.

Required Completed STS RE-004, SHUTDOWN MARGIN DETERMINATION, Attachment A, Materials: SHUTDOWN MARGIN CALCULATION SHORT FORM.

WCRX-27 Rev.18, CONTROL ROOM OPERATING CURVES AND TABLES REFERENCE MANUAL

References:

STS RE-004, SHUTDOWN MARGIN DETERMINATION WCRX-27 Rev.18, CONTROL ROOM OPERATING CURVES AND TABLES REFERENCE MANUAL Time No Alternate No Validation 15 Minutes Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

1. Applicant evaluates date and time Step A.1.1: from initial conditions.

The date and time entered is PRESENT CONDITIONS: correct: 11/7/2017 0900 Current Date/Time S/U

2. Applicant evaluates Shutdown Step A.1.2: date and time from initial conditions.

Shutdown Date/Time The date and time entered is correct: 11/7/2017 / 0100.

S/U 3.

Step A.1.3: Applicant evaluates Burnup MWD/MTU from initial conditions.

Core Average Burnup The burnup is correct: 11,000 NWD/MTU S/U

WC-2017-11 JPM A5 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

4. Applicant evaluates RCS Average Step A.1.4: temperature from initial conditions.

The value is correct: 557°F.

Current Core Average Temperature S/U IF in Mode 1 or 2, THEN enter 557.

IF in MODE 3, 4, or 5 THEN enter actual value.

5. Applicant evaluates concentration Step A.1.5: from initial conditions.

Note: Error #1 1075 ppm is incorrect. 1070 ppm Current boron concentration is given value.

S/U 6.

Step A.1.6: Applicant evaluates Correction Factor 0.937 from page 5.8 Boron-10 Correction Factor From WCRX-30 for 11,000 MWD/MTU.

Curve Book Page 5.8. 0.937 is the correct factor.

S/U

7. Applicant evaluates concentration Step A.2.1: Note: Error #2 from WCRX-30 page 7.1 for 11,000 MWD/MTU is incorrect.

MINIMUM BORON The value recorded (1352 ppm)

CONCENTRATION: corresponds to 10,000 MWD/MTU at 557 °F.

Minimum Boron Concentration, per Curve Book page 7.1 at burnup The correct value for 11,000 (A.1.3) and temperature (A.1.4).

MWD/MTU at 557 °F should be 1270 ppm.

S/U

WC-2017-11 JPM A5 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

8. Applicant evaluates Xenon credit Step A.2.2: because both conditions: Reactor operated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months continuously Apply Xenon Credit if the following prior to trip and present time is conditions are satisfied: within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months from time of trip, are met.

Reactor operated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months continuously at 95% to 100% power Applicant uses 300 ppm credit prior to trip. from page 3.7 of WCRX-23. This is the correct Xenon credit. This is Present Time is within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months step is correct.

from the time of trip.

S/U IF Xenon credit is allowed, THEN enter the Xenon credit from Curve Book page 3.7, ELSE enter 0.

9. Applicant evaluates 1120 ppm Step A.2.3: Note: Error #3 boron concentration as incorrect.

The Applicant may demonstrate Minimum Boron Concentration calculating: minimum correct concentration of 1270 ppm minus the xenon credit (300 ppm) plus the current boron concentration (1070 ppm) times one minus the boron correction factor (0.937).

Correct minimum boron concentration is 1038 ppm.

(Acceptable range 1035 ppm to 1041 ppm)

S/U 10.

Step A.2.4: Note: Error #4 Applicant evaluates 11/8/2017 0500 for 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months from time of IF (A.2.2) is not Shutdown as incorrect. A.1.1 was zero, THEN determine the Time and incorrectly used and should have Date that this Shutdown Margin used A.1.2. Correct answer should calculation is accurate until (A.1.2 + be 11/7/2017 2100.

20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months ), ELSE enter N/A.

S/U

WC-2017-11 JPM A5 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 11.

Step A.3.1: Error #5 Answer should be Yes since the given 1170 ppm boron SHUTDOWN MARGIN concentration exceeds the DETERMINATION: correctly calculated minimum 1038 ppm requirement.

Is the Current Boron Concentration (A.1.5) greater than or equal to the S/U Minimum Boron Concentration (A.2.3)?

IF YES, THEN the Shutdown Margin is met.

12.

Records errors and circles Cue: The JPM is Applicant lists the errors and disapproved on the cue sheet complete. disapproved the submitted informs evaluator that JPM is Attachment A classification.

complete.

S/U Terminating cue: The JPM Is complete when the Applicant has completed verification of SDM.

STOP TIME:

WC-2017-11 JPM A5 Form ES-C-1 Initial Conditions: Given:

The current date and time is 11/7/2017, 0900.

The unit tripped 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago after 180 days of full power operation.

All systems functioned as designed.

Core Burnup is 11,000 MWD/MTU.

Current boron concentration is 1070 ppm.

RCS Temperature is stable at 557°F using steam dumps.

Due to the unavailability of the Shutdown Margin Computer Program, the Reactor Operator performed STS RE-004, SHUTDOWN MARGIN DETERMINATION ATTACHMENT A, SHUTDOWN MARGIN CALCULATION SHORT FORM.

Initiating Cue: Review the completed STS RE-004, ATTACHMENT A, identify ALL errors, if any, and either approve or disapprove the completed work.

Complete the JPM by listing ALL errors, If any, below and circling approval status.

Approve / Disapprove

WC-2017-11 JPM A6 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

DETERMINE LICENSED Job Performance Measure No: A6 OPERATOR LICENSE STATUS K/A

Reference:

2.1.4 (3.8) - Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Initial Given:

Conditions:

Today is April 6, 2017.

The unit is on line at 100% power when the RO had a medical emergency. He will not be able to work his next scheduled shift. The Operations Office Specialist has contacted four off-shift individuals to replace the RO on the following day.

The Individual Operators watch standing history for the first quarter is provided on the enclosed Handout.

The Unit tripped on 3/12 and returned to power on 3/14.

The Shift Manager directs you to PERFORM the following:

Initiating Cue:

DETERMINE which operator(s), if any, are current on maintaining proficiency of an Active License (Circle Correct Status)

RO #1 Active / Inactive RO #2 Active / Inactive RO #3 Active / Inactive RO #4 Active / Inactive

DETERMINE which operator(s), if any, satisfy the requirements to fill the RO position for the oncoming shift

Operator(s) ________________ can be assigned as the RO Task Determine ROs 1 & 4 license status is inactive (for the correct reasons), ROs 2 & 3 Standard: license status is active (for the correct reasons), and ROs 2 & 3 can be assigned to stand watch as the RO per AI 26C-002, CONDITIONS FOR MAINTAINING INDIVIDUAL LICENSES AT WOLF CREEK

WC-2017-11 JPM A6 Form ES-C-1 Required Watch standing History Handout Materials:

References:

AP 21-001, CONDUCT OF OPERATIONS, Rev 80 AP 30B-001, LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM, Rev 28 AI26C-002, CONDITIONS FOR MAINTAINING INDIVIDUAL LICENSES AT WOLF CREEK, Rev 6A.

Time No Alternate No Validation 15 Minutes Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

DETERMINE which Reactor Applicant DETERMINED RO #1 Operators are current on has only stood four 12-hour maintaining proficiency of an watches which qualify as RO Active License. (Circle Correct watches. Watches as 3rd RO do Status) not count as a licensed proficiency watch.

RO #1 CIRCLED Inactive for RO #1.

S/U 2.

DETERMINE which Reactor Applicant DETERMINED RO #2 Operators are current on has reactivated during the previous maintaining proficiency of an quarter and although he has only Active License. (Circle Correct stood four watches, he is still Status).

considered active.

RO #2 CIRCLED Active for RO #2.

S/U

WC-2017-11 JPM A6 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

3. DETERMINE which Reactor Operators are current on Applicant DETERMINED RO #3 maintaining proficiency of an has just received his license and Active License. (Circle Correct has also stood a watch as the Status) BOP. RO #3 is active as soon as the licensed is received, and is therefore still active.

RO #3 CIRCLED Active for RO #3.

S/U

4. DETERMINE which Reactor Operators are current on Applicant DETERMINED RO #4 maintaining proficiency of an has worked a total of (4) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Active License. (Circle Correct shifts that would count towards Status) maintaining an active status. The watch on 2/18/17 does not count because he did not stand watch for RO #4 the full 12-hour shift.

CIRCLED Inactive for RO #4.

S/U

5. DETERMINE which Reactor Operator(s) satisfy the Applicant DETERMINED ROs 2 requirements to fill RO position for and 3 can be assigned as the RO.

the April 7th day shift.

S/U Terminating cue: The JPM Is complete when the applicant has determined Licensed Operator status for all four (four) operators.

STOP TIME:

WC-2017-11 JPM A6 Form ES-C-1 Initial Conditions: Given:

Today is April 6, 2017.

The unit is on line at 100% power when the RO had a medical emergency. He will not be able to work his next scheduled shift. The Operations Office Specialist has contacted four off-shift individuals to replace the RO on the following day.

The Individual Operators watch standing history for the first quarter is provided on the enclosed Handout.

The Unit tripped on 3/12 and returned to power on 3/14.

Initiating Cue:

The Shift Manager directs you to PERFORM the following:

DETERMINE which operator(s), if any, are current on maintaining proficiency of an Active License (Circle Correct Status)

RO #1 Active / Inactive RO #2 Active / Inactive RO #3 Active / Inactive RO #4 Active / Inactive

DETERMINE which operator(s), if any, satisfy the requirements to fill the RO position for the oncoming shift.

Operator(s) ________________ can be assigned to stand RO on April 7, 2017.

WC-2017-11 JPM A7 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

REVIEW A CLEARANCE Job Performance Measure No: A7 ORDER K/A

Reference:

2.2.13 (4.3): Knowledge of tagging and clearance procedures.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Initial The unit is in MODE 1. The PEM01A, Safety Injection Pump A has developed Conditions: an oil leak and the pump must be tagged out for emergent maintenance.

Initiating You are an extra SRO.

Cue:

Review the completed Clearance Order (CO) proposal for approval as the Tagging Authority per AP 21E-001, CLEARANCE ORDERS.

1. Identify ALL errors on the CO Tag List, if any, and record on Cue Sheet.

2. Circle Approve or Disapprove on the Cue Sheet.

The Clearance Order Checklist and the Clearance Order Cover Sheet are provided for REFERENCE ONLY.

Task Review a completed clearance order for approval, identify the three critical Standard: errors, and disapprove the clearance order per AP 21E-001, CLEARANCE ORDERS.

1. Identify Sequencing Error, EM HIS-004, SI Pump A Control Switch must be taken to PTL position prior to racking out NB0103 breaker.

2. Identify Mechanical Isolation Error, Valve EM HV-8814A should be CLOSED instead of OPEN.

3. Identify Electrical Isolation Error, EM HV-8814A breaker is NG01AER3 instead of NG01AER2.

WC-2017-11 JPM A7 Form ES-C-1 Drawings: M-12EM01, E-13EM01, E-13EM03 Required Materials: Handout 1: CO Coversheet Handout 2: Clearance Order Tag List Handout 3: APF 21E-001-15, CLEARANCE ORDER CHECKLIST M-12EM01, P&I DIAGRAM, HIGH PRESSURE COOLANT INJECTION

References:

SYSTEM, Rev 44 E-13EM01, SCHEMATIC DIAGRAM SAFETY INJECTION PUMPS, Rev 5 E-13EM03, SIS MINIFLOW ISOLATION VALVE. Rev 5 AP 21E-001, CLEARANCE ORDER, Rev 40C Time No Alternate No Validation 20 Minutes Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Reviews clearance order for Applicant reviews clearance correct component sequencing. order for correct component sequencing.

Identify correct clearance order:

1. EMHIS004, SI Pump A Control Switch - needs to be taken to PTL prior to racking NB0103 breaker.

Other clearance order priority may exist and be identified.

S/U

WC-2017-11 JPM A7 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 2.

Review clearance order for Placement Configuration of EM proper Placement Configuration. HV-8814 A is identified in the incorrect position.

The CO Tag List identifies EM HV-8814A in the open position, it should be closed.

S/U 3.

Review clearance order for NG01AER2 is identified as proper electrical isolation wrong breaker, should be integrity. NG01AER3 for EM HV-8814A.

S/U 4.

Approve or Disapprove Circle Disapprove Clearance Order S/U Terminating cue: The JPM Is complete when the Applicant has completed identifying and recording errors and determining approval or disapproval status.

STOP TIME:

WC-2017-11 JPM A7 Form ES-C-1 Initial The unit is in MODE 1. The PEM01A, Safety Injection Pump A has Conditions: developed an oil leak and the pump must be tagged out for emergent maintenance.

Initiating Cue:

You are an extra SRO.

Review the completed Clearance Order (CO) proposal for approval as the Tagging Authority per AP 21E-001, CLEARANCE ORDERS.

1. Identify ALL errors on the CO Tag List, if any, and record below.

2. Circle Approve or Disapprove on the Cue Sheet.

The Clearance Order Checklist and the Clearance Order Cover Sheet are provided for your REFERENCE ONLY.

APPROVE / DISAPPROVE

WC-2017-11 JPM A8 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

Job Performance Measure No: A8 REVIEW A LIQUID RELEASE PERMIT K/A

Reference:

2.3.6 (3.0) - Ability to approve release permits.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Initial Given:

Conditions:

The unit is in MODE 1.

Waste Monitor Tank, THB07A is being released.

Preparations are being made to release Secondary Liquid Waste Monitor Tank, THF04B.

As the Shift Manager, review the provided Secondary Liquid Waste Monitor, Initiating THF04B Release Permit. Identify ALL errors, if any, and specify whether or Cue:

not you would authorize this release.

Record ALL errors, if any, in the space provided below.

Release Permit is (Circle one) Authorized / NOT Authorized Task Reviewed a prepared release permit and identified errors:

Standard:

1. In RELEASE CONDITIONS Section, the High Setpoint and Low Setpoint Values are swapped.

2. In SPECIAL INSTRUCTIONS Section, concurrent batch releases are NOT allowed. This release may NOT be performed until Waste Monitor Tank release is complete.

3. In AUTHORIZATION/RELEASE DATA SECTION, Supervisor RM-80 Setpoints have NOT been Verified by a second Operator.

Given the errors listed, the SM should NOT Authorize the Secondary Liquid Waste Monitor Tank release.

Required Filled out APF 07B-001-02-13 (Rev 10) Handout, Page 1 only.

Materials:

References:

AI 07B-019, INSTRUCTIONS FOR LIQUID RELEASE PERMITS, Rev 21

WC-2017-11 JPM A8 Form ES-C-1 Time No Alternate No Validation 10 Minutes Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Reviews the presented APF 07B- Applicant identifies that the 001-02-13 THF04 Release Permit expected monitor Low Setpoint for authorization. was higher than the High Setpoint.

RELEASE CONDITIONS Section.

S/U 2.

Reviews the presented APF 07B- Applicant identifies Concurrent 001-02-13 THF04 Release Permit batch releases allowed. Is marked for authorization. NO and recognizes from the given conditions that the Waste SPECIAL INSTRUCTIONS Section. Monitor Tank may NOT be released concurrently.

S/U 3.

Reviews the presented AFP 07B- Applicant identifies there is NOT a 001-02-13 THF04 Release Permit second set of Operator initials for for authorization. Verifying Supervisor RM-80 Database Setpoints.

AUTHORIZATION / RELEASE DATA Section S/U 4.

Release Authorization Based on Any of the errors presented above, Determines the Release is NOT authorized.

S/U Terminating cue: The JPM Is complete when the applicant authorizes/does not authorize the Release and any/all errors have been identified.

STOP TIME:

WC-2017-11 JPM A8 Form ES-C-1 Initial Conditions: Given:

The unit is in MODE 1.

Waste Monitor Tank, THB07A is being released.

Preparations are being made to release Secondary Liquid Waste Monitor Tank, THF04B.

Initiating Cue:

As the Shift Manager, review the provided Secondary Liquid Waste Monitor Tank, THF04B Release Permit. Identify ALL errors, if any, and specify whether or not you would authorize this release.

Record ALL errors, if any, in the space provided below.

Release Permit is (Circle one) Authorized / NOT Authorized

WC-2017-11 JPM A9 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

MAKE A PROTECTIVE ACTION Job Performance Measure No: A9 RECOMMENDATION K/A

Reference:

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

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant Initial Given:

Conditions:

A large break LOCA has occurred,

All systems operated as designed with the exception of the Containment Spray Pumps, which both failed to start automatically and manually.

Containment pressure is 35 PSIG and falling rapidly.

Critical Safety Function Status Trees indicate a valid Containment ORANGE Path and Core Cooling RED Path.

Meteorological Conditions: Stability Class = D, Wind at 10 mph, Wind from 150o to 330°.

Initiating THIS IS A TIME CRITICAL JPM Cue:

As the Shift Manager,

1. Determine Emergency Classification. Once classification is determined, present to examiner for time critical action assessment.

2. Once handed EFP 06-007-01 Notification Form, Correctly (without errors) complete the form to include identifying the correct Protective Action Recommendations, if any.

Task Given a set of conditions, determines a GENERAL EMERGENCY exists per Standard: APF 06-002-01, EMERGENCY ACTION LEVELS, EAL 3- LCRB, blocks 1,2,3,4 and makes Protective Action Recommendation to Evacuate JRR, CCL, CTR and Sub zones 2-10 miles down wind, which are N-1, NW-1, N-2, and NW-2 for the given wind direction, speed, and stability class. Must classify within 15 minutes and fill out form EPF 007-01 (Correctly, without errors) within 15 minutes from the time the Emergency Classification is made to successfully meet Time Critical Action requirements.

WC-2017-11 JPM A9 Form ES-C-1 Required APF 06-002-01, Emergency Action Levels, Rev 17A Materials:

EPF 06-007-01, Wolf Creek Generating Station Emergency Notification, Rev 13 EPP 06-006, Protective Action Recommendations, Rev 9

References:

EPP 06-001, Control Room Operations, Rev 25 EPP 06-005, Emergency Classification, Rev 8 EPP 06-007, Emergency Notifications, Rev 24 Time Yes Alternate No Validation 30 minutes Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Record Time T-0 when cue Cue: (Hand Applicant Examiner Note:

sheet is provided. the cue sheet) Time Critical Action starts Time Zero (T-0) for the 15 Now. minute requirement to complete the declaration begins when the Examiner: Record Time cue sheet is provided T-0 (Start Time) when cue sheet provided to Applicant.

Time T-0____________

2.

Per EPP 06-001, EPP 06-005, Examiner: When the Determines classification is a and APF 06-002-01, determine Applicant determines GENERAL EMERGENCY correct Emergency Emergency Classification. Classification, Record 3-LCRB Time T-1 (Classification Time) EAL Flow Path 1,2,3,4 Time T-1 ___________ S/U

WC-2017-11 JPM A9 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 3.

Applicant Classified within the Examiner: Record Examiner Note:

required time frame. Classification time.

The Applicant must classify T1-T0 = _________min correctly within 15 minutes from Start Time to meet Time Critical Action for Classification.

S/U 4.

Record Time T-2 when second Cue: (Hand Applicant Examiner Note:

cue and notification worksheet is the second cue sheet provided. and notification form) Time T-2 for the 15 minute Time Critical Action requirement to complete the starts Now. Notification Form begins when the cue sheet and blank form is Examiner: Record Time provided.

T-2 (Start Time) when cue sheet and blank form provided to Applicant.

Time T-2____________

WC-2017-11 JPM A9 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 5.

Using EPP 06-006, determine Examiner: When the Applicant Determines Protective correct Protective Action Applicant turns in Action Recommendation Recommendation and fill out completed EPF 06-007-EPF 06-007-01. 01, Record Time T-3 Evacuate JRR, CCL, CTR, and Subzones 2-10 miles downwind Time T-3 ___________ per Attachment B.

For wind from 150° and Stability Class D.

Checked - Evacuate CCL & JRR Checked Evacuate Checked 0-2 Miles - CTR Checked 2-5 Miles - N-1, NW-1 Checked 5-10 Miles - N-2 & NW-2 Examiner Note: See A9 KEY for expected standard.

S/U 6.

Applicant completed Examiner: Record Examiner Note:

Emergency Notification Form Notification time.

within the required time frame. The Applicant must fill out T3-T2 = _________min Emergency Notification Form, with PARs, correctly within 15 minutes from Classification Time to meet Time Critical Cue: The JPM is Action for Notification.

complete.

RECORD STOP TIME BELOW.

S/U Terminating cue: The JPM Is complete when the declaration has been made & the Emergency Notification Form with PARs has been completed and turned in to examiner.

STOP TIME:

WC-2017-11 JPM A9 Form ES-C-1 Initial Given:

Conditions:

A large break LOCA has occurred,

All systems operated as designed with the exception of the Containment Spray Pumps, which failed to start automatically or manually.

Containment pressure is 35 PSIG and falling rapidly.

Critical Safety Function Status Trees indicate a valid Heat Sink ORANGE Path and Core Cooling RED Path.

Meteorological Conditions: Stability Class = D, Wind at 10 mph, Wind From 150o.

Initiating Cue: THIS IS A TIME CRITICAL JPM As the Shift Manager, Determine Emergency Classification. Once classification is determined, present to examiner for evaluation.

Following classification, you will be handed a blank EFP 06-007-01 Notification Form which you will be required to complete, to include identification of the correct Protective Action Recommendations (PAR), if any.

Record the Emergency Classification (Including Emergency Action Level (EAL) Tree for Classification and the EAL flow path) in the space provided below:

WC-2017-11 JPM A9 Form ES-C-1 2nd Initiating Cue: THIS IS A TIME CRITICAL JPM Once handed a blank EFP 06-007-01 Notification Form, Correctly (without errors) complete the form with the previously identified information to include identification of the correct Protective Action Recommendations (PAR), if any.

Facility: WCNOC Date of Examination: 11/6/2017 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U (Bold indicates alternate path)

System/JPM Title Type Code* Safety Function S1 - Control Rod Drive System / PERFORM ACTIONS TO S, D 1 - Reactivity RETRIEVE A DROPPED CONTROL ROD Control K/A: APE 003 AA1.02 (3.6 / 3.4): Ability to operate and/or monitor the following as they apply to the Dropped Control Rod: Controls and components necessary to recover rod RO, SRO - I S2 - SI Termination / ESTABLISH LETDOWN DURING SI S, N, A, EN, L 2 - Inventory TERMINATION IAW EMG ES-03 (ESTABLISH EXCESS Control LETDOWN)

K/A: EA1.1 (4.0 / 3.9): Ability to operate and / or monitor the following as they apply to SI termination: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

RO, SRO - I, SRO - U S3 - Emergency Core Cooling System / OPERATE SI PUMP TO S, D, A, EN 3 - Pressure RAISE ACCUMULATOR LEVEL (RECOGNIZE SI PUMP GAS Control BINDING AND SECURE THE PUMP)

K/A: 006 A4.07 (4.4 / 4.4): Ability to manually operate and/or monitor in the control room: ECCS pumps and valves.

RO, SRO - I, SRO - U S4 - Waste Gas Disposal System / SET RM-11R SETPOINTS FOR S, D 9 - Radioactivity A Radioactive Release Release K/A: 071 A4.25 (3.2 / 3.2): Ability to manually operate and/or monitor in the control room: Setting of process radiation monitor alarms, automatic functions, and adjustment of setpoints.

RO

S5 - Reactor Coolant Pump System / START RCP D IAW EMG ES- S, D, L 4P - Heat 11 Removal (Primary System)

K/A: E03 EA1.1 (4.0 / 4.0) Ability to operate and / or monitor the following as they apply to LOCA cooldown and depressurization:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

RO, SRO - I S6 - Containment Spray System / MANUALLY ALIGN S, N, L, A, EN 5 - Containment CONTAINMENT SPRAY COMPONENTS THAT FAILED TO Integrity ACTUATE FOLLOWING A LOSS OF COOLANT ACCIDENT.

K/A: 026 A4.01 (4.5 / 4.3) Ability to manually operate and/or monitor in the control room: CSS controls.

RO, SRO - I S7 - Emergency Diesel Generators / TRANSFER NB02 FROM S, N , A 6 - Electrical THE EDG TO THE NORMAL POWER SUPPLY (UNLOAD AND STOP THE EDG FOLLOWING LOSS OF ESW)

K/A: 064 A1.03 (3.2 / 3.3): Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the EDG system controls including: Operating voltages, currents, and temperatures.

RO, SRO - I S8 - Reactor Protection System / BYPASS A FAILED PRNI S, D 7-CHANNEL Instrumentation K/A: 012 A4.03 (3.6 / 3.6): Ability to manually operate and/or monitor in the control room: Channel blocks and bypasses.

RO, SRO - I In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U P1 - DC Electrical Distribution System / TRANSFER BUS NN02 D, L 6 - Electrical POWER Supply TO NN12 FROM BYPASS CVT FOLLOWING A LOSS OF AND RESTORATION OF BUS NK02.

K/A: 058 AA1.03 (3.1 /3.3): Ability to operate and/or monitor the following as they apply to the Loss of DC Power: Vital and battery bus components.

RO, SRO - I, SRO - U

P2 - Spent Fuel Pool Cooling System / MAKEUP TO THE SFP N, R 8 - Plant Service FROM ESW Systems K/A: 033 A2.03 (3.1 / 3.5) Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level.

RO, SRO - I, SRO - U P3 - Chemical and Volume Control System / PERFORM LOCAL D, A, E, R 1 - Reactivity ACTIONS TO BORATE THE REACTOR COOLANT SYSTEM (USE Control THE ALTERNATE METHOD FOR LOCAL OPERATION)

K/A: APE 024 / AA1.04 (3.6 / 3.7): Ability to operate and / or monitor the following as they apply to emergency boration: Manual boration valve RO, SRO - I, SRO - U

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

Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path 4-6 (5) /4-6 (5) /2-3 (3)

(C)ontrol room (0/0/0)

(D)irect from bank 9 (7) / 8 (6) / 4 (3)

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

(EN)gineered safety feature 1 (3) / 1 (3) / 1 (2) (control room system)

(L)ow-Power/Shutdown 1 (4) / 1 (4) / 1 (2)

(N)ew or (M)odified from bank including 1(A) 2 (4) / 2 (4) / 1 (2)

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

(R)CA 1 (2) / 1 (2) / 1 (2)

(S)imulator (8/7/2)

WC-2017-11 JPM S1 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

PERFORM ACTIONS TO Job Performance Measure No: S1 RETRIEVE A DROPPED CONTROL ROD K/A

Reference:

APE 003 AA1.02 (3.6 / 3.4): Ability to operate and/or monitor the following as they apply to the Dropped Control Rod: Controls and components necessary to recover rod.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Initial Given:

Conditions:

You are the Reactor Operator.

30 minutes ago, Control Rod H8 dropped into the core.

The plant has been stabilized per OFN SF-011, REALIGNMENT OF DROPPED, MISALIGNED ROD (S) AND ROD CONTROL MALFUNCTIONS.

I&C personnel have determined that the rod dropped due to a blown fuse in the stationary gripper coil circuit. The circuit has been verified good and the fuse has been replaced.

Actions to commence recovery of the dropped rod are ready to be performed. I&C personnel are standing by in the Rod Drive MG Set Room.

MCB Alarms 079C-RPI DEV OR PR TILT, 080C-RPI ROD DEV, and 081B-ROD AT BOTTOM have actuated.

Initiating

The CRS directs you to recover the dropped rod using OFN SF-011, Cue: REALIGNMENT OF DROPPED, MISALIGNED ROD (S) AND ROD CONTROL MALFUNCTIONS beginning at Step 11.

Updating the rod position computer points and controlling Tavg with Tref are NOT necessary for this JPM.

The Call Superintendent, I&C and Reactor Engineering have all been notified.

Reactor Engineering said the control rod could be moved at a normal rate.

Per the Sim Difference list, step counters are not the same as in the main control room. Reset the counter by pushing the reset button with a stylus.

WC-2017-11 JPM S1 Form ES-C-1 Task The applicant identified the correct group step position to withdraw the dropped rod to, Standard: and withdrew only dropped rod H8 at least 30 steps (stopping point for the JPM) in accordance with OFN SF-011 while ensuring accurate Pulse-to-Analog converter count is maintained.

Required OFN SF-011, REALIGNMENT OF DROPPED, MISALIGNED ROD (S) AND ROD Materials: CONTROL MALFUNCTIONS Rev 12.

Simulator Setup: IC 305: IC-30, IMF mSF04H8, DMF mSF04H8, OFN SF-011, through Step 10 (Rods in Manual and adjust Turbine load to match Tref and Tavg within band). JPM to run concurrently with SIM JPM S4 (RM11 setpoint change).

Booth Operator Note: Ensure stylus to reset Group Step Counter is staged.

References:

OFN SF-011, REALIGNMENT OF DROPPED, MISALIGNED ROD (S) AND ROD CONTROL MALFUNCTIONS Rev 12.

Time Critical: No Alternate No Validation Time: 10 min Path:

START TIME:

WC-2017-11 JPM S1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

1. Step 11: Recognized on DRPI that H8 indicates at the bottom.

Check If Rod Can Be Moved At Normal Rate: Realized from the cue that the rod has been misaligned for less than Rod misaligned by less than 12 one hour and that Reactor steps.

Engineering had said move rod at OR normal rate.

Rod misaligned for less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months S / U

2. Step 12: Continued with Step.

Prepare To Retrieve Dropped Rod:

S / U

3. Step 12.a: Rotated SE HS-9 to the Control Bank D position (CBD).

a. Place ROD BANK AUTO/MAN SEL switch to the bank with the dropped rod.

o SE HS-9 S / U

4. Step 12.b: Contacted I&C at the Rod Control WHEN I&C Cabinets.

contacted, THEN:

b. Direct I&C to locally verify rod Cue: Control Bank D is bank selected by SE HS-9 is selected by light indication.

aligned properly, by light indications on associated cabinets.

S / U

5. Note: The label inside of the Recognize and read note, place control rod disconnect switch box keeps, and acknowledges that the can be used to determine which note was read and understood.

group has the dropped rod. This information will be needed in later steps S / U

WC-2017-11 JPM S1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

6. Step 12.c: At the Control Rod Disconnect Switch Box in the back of the

c. At lift coil disconnect panel, Control Room, toggled switches place all lift coil disconnect switches out and upward to the ROD for other rods in affected bank to DISCONNECT position for ONLY ROD DISCONNECTED position. (without H-8):

D-4, M-12, D-12, and M-4 S / U

7. Step 12.d: Recorded the step counter reading on Bank D, SC CB-D2 229 Steps.

d. At RL003, record position of group step counter for group containing dropped rod.

S / U o Group step counter________

8. Step 12.e: Opened window on the affected group (SC CB-D2) and reset

e. At step counter for affected affected group step counter by group, open window and reset hand to zero.

affected group step counter by hand to zero.

S / U

9. Note: Steps 13 and 14 shall be Recognize and read note, place performed at the same time. keeps, and acknowledges that the note was read and understood.

S / U

10. Step 13: WHEN turbine load Contacted CRS/Extra RO.

adjustment is

13. ()Adjust Turbine Load, As required, THEN:

Necessary, To Maintain Tavg Within 3°F of Tref Cue: The extra RO will attend to Turbine load adjustment. S / U

WC-2017-11 JPM S1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD

11. Note: Recognize and read note, place o When motion is attempted, keeps, and acknowledges that the annunciator 00-079A, ROD note was read and understood.

CTRL URG FAIL, will be received and the URGENT FAILURE red light will be lit on the local power cabinet containing the other group of the affected bank.

o If dropped rod in in a control group, the Pulse-to-Analog Converter switch must be held in MANUAL, to maintain proper rod position information.

S / U

12. Step 14: Continued with Step

14. () Withdraw Affected Rod:

S / U

13. Step 14.a and RNO a: Cue: The AUTO-MANUAL Recognize Rod H8 is NOT in the switch is in MANUAL. shutdown group and contacted

a. Check Dropped Rod in I&C at the control cabinet and SHUGDOWN GROUP: - NO directed them to hold AUTO-MANUAL switch in MANUAL.

RNO a. At Pulse-to-Analog Converter cabinet, hold AUTO-MANUAL switch in MANUAL.

S / U

14. Step 14.b: Monitored DRPI.

Ensure only affected rod moves during withdrawal. S / U

15. Step 14.c: Actuated MAN ROD CTRL switch, SF HS-2 (OUT), and withdrew rod Withdraw dropped rod until Cue: The JPM is H-8 50 steps.

operating step counter reaches complete.

group step position recorded in step RECORD STOP TIME Note: JPM is completed when 12.d. BELOW. H-8 has been withdrawn 30 steps.

S / U Terminating cue: The JPM Is complete when the applicant has withdrawn Control Rod H8 30 steps.

STOP TIME:

WC-2017-11 JPM S1 Form ES-C-1 Initial Conditions:

You are the Reactor Operator.

30 minutes ago, Control Rod H8 dropped into the core.

The plant has been stabilized per OFN SF-011, REALIGNMENT OF DROPPED, MISALIGNED ROD (S) AND ROD CONTROL MALFUNCTIONS.

I&C personnel have determined that the rod dropped due to a blown fuse in the stationary gripper coil circuit. The circuit has been verified good and the fuse has been replaced.

Actions to commence recovery of the dropped rod are ready to be performed.

I&C personnel are standing by in the Rod Drive MG Set Room.

MCB Alarms 079C-RPI DEV OR PR TILT, 080C-RPI ROD DEV, and 081B-ROD AT BOTTOM have actuated.

Initiating Cues:

The CRS directs you to recover the dropped rod using OFN SF-011, REALIGNMENT OF DROPPED, MISALIGNED ROD (S) AND ROD CONTROL MALFUNCTIONS beginning at Step 11.

Updating the rod position computer points and controlling Tavg with Tref are NOT necessary for this JPM.

The Call Superintendent, I&C and Reactor Engineering have all been notified.

Reactor Engineering said the control rod could be moved at a normal rate.

Per the Sim Difference list, step counters are not the same as in the main control room. Reset the counter by pushing the reset button with a stylus.

WC-2017-11 JPM S2 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

ESTABLISH LETDOWN DURING Job Performance Measure No: S2 SI TERMINATION IAW EMG ES-03 (ESTABLISH EXCESS LETDOWN)

K/A

Reference:

E02 EA1.1 (4.0/3.9): Ability to operate and / or monitor the following as they apply to SI termination: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Initial Given:

Conditions:

A LOCA occurred while the unit was operating at power.

Safety injection actuated, and a reactor trip occurred.

The crew transitioned from EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT, to EMG ES-03, SI TERMINATION.

The crew has just completed EMG ES-03, Step 18, and verified that ECCS flow is NOT required.

Initiating You are the Reactor Operator, and the Control Room Supervisor directs you to Cue: establish Letdown starting at Step 19 of EMG ES-03.

Task The operator established excess letdown per EMG ES-03, Step 20, at the maximum Standard: flow rate.

Required EMG ES-03, SI TERMINATION, Revision 24.

Materials:

Simulator Setup: IC 306: IC 30, IMF mBB06B (RCS Loop 2 Cold leg break, 1),

EMG E-0, EMG E-1, EMG ES-03 actions through step 18.

References:

EMG ES-03, SI TERMINATION, Revision 24 Time Critical: No Alternate Yes Validation Time: 10 min Path:

START TIME:

WC-2017-11 JPM S2 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Step 19: Recognized step to be completed from the initiating Check if Letdown can be cue.

established:

S / U 2.

Step 19.a: Cue: (IF asked) Recognized that PZR level is Containment Conditions are greater than 20%.

PZR Level - Greater than 20% NOT adverse due to

[47%] radiation levels.

S / U 3.

Step 19.b.1: Opened Letdown System Containment Isolation Valves Establish Normal Letdown: Open HV-8152 and HV-8160.

Letdown System Containment Isolation Valves o BG HIS-8152 o BG HIS-8160 S / U 4.

Step19.b.2. first bullet: Opened LCV-459 (Note:

bulleted steps may be Open RCS Letdown To performed in any order, and Regenerative Heat Exchanger thus the candidate may not Valves open LCV-459 before attempting to open LCV-460 o BG HIS-459 and proceeding to the RNO actions).

S / U

5. Attempted to open LCV-460, Step 19.b.2 second bullet: recognized that LCV-460 Cue: Acknowledge that failed to open, reports that LCV-460 failed to open.

Open RCS Letdown To LCV-460 failed to open to the Regenerative Heat Exchanger CRS, and proceeds to the Valves RNO column.

o BG HIS-460

COMMENCE ALTERNATE PATH* S / U

WC-2017-11 JPM S2 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 6.

Step 19.b RNO: Continued to Step 20.

Go to Step 20 S / U 7.

Step 20.a: Throttled Excess Letdown Heat Exchanger Outlet Flow Establish Excess Letdown: Ctrl Valve HCV-123 open 45% to 55%.

Throttle Excess Letdown Heat Exchanger Outlet Flow Control Valve open 45% to 55%

S / U o BG HC-123 8.

Step 20.b.1: Recognized that BG HV-8100 and BG HV-8112 are closed Check VCT - Available: Check and proceeded to the RNO seal water return containment column.

isolation valves open (Note: Safety Injection Signal o BG HIS-8100 actuates Containment Isolation Signal phase A, o BG HIS-8112 which closes BG HV-8100 and BG HV-8112)

S / U 9.

Step 20.b RNO a): Cue: The RCDT is aligned Discusses directing for pump down. performance of SYS HB-120.

Ensure RCDT is aligned for pump down per SYS HB-120, REACTOR COOLANT DRAIN TANK OPERATIONS S / U 10.

Step 20.b RNO b): Positioned HV-8143 to RCDT.

Select RCDT on EXCESS LTDN HX TO RCDT/SEAL WTR HX o BG HIS-8143 S / U

WC-2017-11 JPM S2 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 11.

Steps 20.c.1) a and b: Opened BG HV-8153A and BG HV-8154A.

Check Train A Excess Letdown -

Available:

1. Open A Train RCS TO EXCESS LTDN HX valves:

a) BG HIS-8153A S / U b) BG HIS-8154A 12.

Step 20.d: Cue: Establish maximum Establishes maximum flow flow rate. rate Set Excess Letdown Heat Exchanger Outlet Flow Control Set Excess Letdown Heat valve to maintain desired flow. Exchanger Outlet Flow Control Valve HCV-123 to full o BG HC-123 open.

Examiner note: there is no Cue: The JPM is flow indication for Excess complete. Letdown to RCDT, only temp and press.

RECORD STOP TIME BELOW. S / U Terminating cue: The JPM Is complete when the candidate has completed Step 20.d to establish letdown flow.

STOP TIME:

WC-2017-11 JPM S2 Form ES-C-1 Initial Conditions: Given:

A LOCA occurred while the unit was operating at power.

Safety injection actuated, and a reactor trip occurred.

The crew transitioned from EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT, to EMG ES-03, SI TERMINATION.

The crew has just completed EMG ES-03, Step 18, and verified that ECCS flow is NOT required.

Initiating Cue: You are the Reactor Operator, and the Control Room Supervisor directs you to establish Letdown starting at Step 19 of EMG ES-03.

WC-2017-11 JPM S3 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

OPERATE SI PUMP TO RAISE Job Performance Measure No: S3 ACCUMULATOR LEVEL (RECOGNIZE SI PUMP GAS BINDING AND SECURE THE PUMP)

K/A

Reference:

006/A4.07 (4.4 / 4.4): Ability to manually operate and/or monitor in the control room:

ECCS pumps and valves.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Initial Given:

Conditions:

Main Control Board alarms 044B (ACC TK B PRESS HILO) & 044C (ACC TK B LEV HILO) were received and reported to the CRS.

ALR actions have been taken and the CRS has directed filling operations per SYS EP-200.

Boron concentration has been verified and Chemistry samples are NOT required.

Initiating You are the Reactor Operator, the CRS has directed you to fill Accumulator Tank B, Cue: with the B SI Pump, using SYS EP-200, step 6.1, All prerequisites have been completed.

Task Commenced filling Accumulator Tank B using B SI Pump, recognized the indications Standard: of gas bound pump and secured B SI Pump within 5 minutes of opening EP HIS-8878B (start of gas binding).

Required SYS EP-200, SAFETY INJECTION ACCUMULATOR OPERATIONS, Rev 41 Materials:

Simulator Setup: IC 307: IC 30, SYS EP-200, Section 6.5 to reduce level in Accumulator Tank B to 40% (with pressure at 600 psig). IRF rEM05 f:100 to locally open EM-V250, Conditional fault for SI PUMP B air binding 30 seconds after initiating fill. {vlEPHV8878B.position>0.9} ICM vIEMHV8923B t:2 f:0.01 d:30 r:0.

JPM Initial conditions set to run concurrently with S8 JPM (IMF mSE03C f:0, PRNI Channel 43 fail low).

References:

SYS EP-200, SAFETY INJECTION ACCUMULATOR OPERATIONS, Rev 41 OFN BG-045, GAS BINDING OF CCPS OR SI, Rev 5

WC-2017-11 JPM S3 Form ES-C-1 Time Critical: No Alternate Yes Validation Time: 10 minutes Path:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

NOTE: Step 6.1.1 is intended to Recognize and read note, minimize high pressure alarms place keeps, and caused by the pressure increase acknowledges that the note associated with raising Accumulator was read and understood.

level. If an alarm is received due to high pressure while filling an Accumulator, the alarm should clear after the Accumulator cools to ambient temperature.

S/U 2.

Step 6.1.1: On panel RL018, Locates level and pressure indication IF Accumulator level is less than for Accumulator Tank B (EP 45% AND Accumulator pressure is PI-962 & 963, EP LI-952 &

greater than 619 953).

psig, THEN ADJUST Accumulator pressure to less than 619 psig, Verifies level in Accumulator using section 6.8, Decreasing Tank B is less than 45% AND Accum Pressure. pressure is less than 619 psig Determines that transition to step 6.8 is not required and proceeds to next step.

S/U

WC-2017-11 JPM S3 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 3.

Step 6.1.2: On panel RL002, Locates pressure indicators (either on RECORD RCS pressure read on the Main Control Board or on any of the following indicators: NPIS) and records ANY/ALL of the values, Panel RL002.

BB PI-455A Records data in procedure:

BB PI-456 BB PI-455A= 2235 psig +/- 10

BB PI-457 psig

BB PI-458 BB PI-456= 2235 psig +/- 5 psig BB PI-457 = 2235 psig +/- 5 psig BB PI-458= 2235 psig +/- 10 psig S/U 4.

NOTE: Depressurizing the RHR Recognize and read note, CUE: CRS does NOT header should reduce back place keeps, and desire to depressurize the pressure on check valves EP-8818 acknowledges that the note RHR header.

A, B, C, and D, allowing the check was read and understood.

valves to seat while the SI Pump is running. This step should be Requests direction from the performed at SM/CRS discretion CRS for performance of the and system engineering should be step.

contacted.

S/U 5.

Step 6.1.3: Step is N/A based on previous guidance from the IF desired, THEN DEPRESSURIZE CRS.

RHR header, as follows:

Proceed to the next step in the procedure.

S/U 6.

Step 6.1.4: Step is N/A based on initial direction from the CRS.

IF using SI Pump A to fill Accumulators, THEN perform the Proceed to the next step in following: the procedure.

S/U

WC-2017-11 JPM S3 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 7.

Step 6.1.5.: Proceed to the next step in the procedure.

IF Using SI Pump B to fill Accumulators, THEN PERFORM S/U the following:

8.

Step 6.1.5.1: On panel RL017, Located push button, verifies EM HIS-ENSURE EM HIS-8814B, SI PUMP 8814B indicates OPEN (Red B RECIRC TO RWST is OPEN. light on, Green light off) o EM HIS-8814B - OPEN S/U 9.

Step 6.1.5.2: On panel RL017, Located push button, verifies BN HIS-ENSURE BN HIS-8813, SI PUMPS 8813 indicates OPEN (Red RECIRC TO RWST is open. light on, Green light off) o BN HIS-8813 - OPEN S/U 10.

NOTE: The trend is monitored prior Recognize and read note, to and during pump starts, to ensure place keeps, and any indication of voiding, such as acknowledges that the note unexpected fluctuating parameters was read and understood.

is observed and compensatory measures can be accomplished prior to damage occurring.

S/U

WC-2017-11 JPM S3 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 11.

Step 6.1.5.3: Reactor Operator will:

Prior to starting SI Pump B, a NPIS 1: Use NPIS screen EM1 and computer trend shall be STARTED select the SI pumps for and MONITORED to ensure proper monitoring (bottom two points pump operation and system represent SI Pump B) response. The following are points that need to be monitored. Any OR other available points that monitor pump operation may be monitored. 2: Create their own trend plot using Custom Trends, and o EMI0018 SI PUMP B AMP selecting the points o EMF0922 SI PUMP B DISCH individually for the monitored FLOW parameters S/U 12.

Step 6.1.5.4: Cue: (IF applicant starts to On panel RL017, Located SI announce pump start) Pump hand switch, places START SI PUMP B, using EM Pump Start EM HIS-5 in the NORMAL-HIS-5, SI PUMP B. Announcement has been AFTER-RUN position.

made. Verifies pump is running (Red o EM HIS NORMAL-AFTER- light on, Green light off) and RUN changes in flow and amp readings.

S/U 13.

Step 6.1.6: On panel RL018, Located push button, verified EM HIS-OPEN EM HV-8888, Using 8888 indicates CLOSED (Red EM HIS-8888, ACC TANKS FILL light off, Green light on)

LINE VALVE.

Depresses and holds OPEN o EM HIS-8888 - OPEN push button until valve indicates open (Red light on, Green light off)

S/U

WC-2017-11 JPM S3 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 14.

NOTE: If the RWST boron Recognize and read note, concentration is within Technical place keeps, and Specification and TRM limits, acknowledges that the note Chemistry sample of the was read and understood.

Accumulators is NOT required Given initial conditions state boron concentration has been verified and Chemistry sampling is NOT required.

S/U 15.

Step 6.1.7: Step is N/A based on previous guidance from the IF filling Accumulator Tank A, THEN CRS.

PERFORM the following:

Proceed to the next step in the procedure.

S/U 16.

Step 6.1.8.1: On panel RL018, Located level indications for IF filling Accumulator Tank B, THEN Accumulator Tank B (EP LI-PERFORM the following: 952 & 953)

RECORD initial Accumulator Tank Records level indications in B level form the highest reading the procedure indicator.

Level = 40% +/- 2%

EP LI-952

EP LI-953 S/U

WC-2017-11 JPM S3 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 17.

Step 6.1.8.2: On panel RL018, Located push button, verified EP HIS-OPEN EP HV-8878B using EP 8878B indicates CLOSED HIS-8878B, ACC TANK B FILL (Red light off, Green light on)

LINE VLV.

Depresses and OPEN push o EP HIS-8878B - OPEN Time Opened: _________ button verifies valve indicates open (Red light on, Green light off)

NOTE: When EP HV-8878B is opened, SI PUMP B will begin to show signs of gas binding.

S/U 18.

Step 6.1.8.3: Cue: (IF requested) The On Panels RL017 & 18, BOP will perform the Monitors highest reading level WHEN Accumulator Tank B level is Individual Verification (IV) and prepares to close EP between 55% and 58% on the following completion of HIS-8878B upon reaching highest reading indicator, THEN your procedure steps. desired level (between 55%-

close EP HV-8878B, using 58%)

EP HIS-8878B, ACC TANK B FILL LINE VLV. Monitors pump conditions on trend plots. (Should note gas binding before completing this

EP LI-952 - Between 55% AND step) 58%

EP LI-953 - Between 55% AND 58%

AND o EP HIS-8878B - CLOSED S/U

WC-2017-11 JPM S3 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 19.

Conditional on EP HV-8878B Recognizes indication that SI opening (ACC TANK B FILL Pump B is gas bound LINE VLV), SI PUMP B will begin to show signs of gas On panel RL017, Located binding. hand switch, places EM HIS-5 in the NORMAL-AFTER-Reactor Operator will recognize STOP position, within 5 drop in amps & discharge flow minutes of opening EP HIS-with small oscillations and take 8878B (start of gas action to secure SI PUMP B. binding). Verifies pump is stopped (Red light off, Green o EMI0018 SI PUMP B AMP - light on) and changes in flow LOWERING and amp readings. NOTE, o EMF0922 SI PUMP B DISCH they may also close EP HIS-FLOW - LOWERING 8878B to isolate the flowpath, per step 6.1.8.3 AND Time Stopped: _________

NOTE: It is also acceptable if o EM HIS NORMAL- the applicant takes EM HIS-5 AFTER-STOP to PTL per OFN BG-045, GAS BINDING OF CCPS OR SI PUMPS (Step 12 as a reference)

S/U 20.

Inform CRS of indications for SI Cue: CRS acknowledges Informs CRS of the abnormal PUMP B and that SI Pump B is report. plant conditions and any/all stopped actions taken to resolve.

Cue: The JPM is complete. May make recommendation to enter OFN BG-045, GAS RECORD STOP TIME BINDING OF CCP AND SI BELOW. PUMPS.

S/U Terminating cue: The JPM Is complete when the applicant has stopped SI PUMP B and reported the abnormal conditions to the CRS.

STOP TIME:

WC-2017-11 JPM S3 Form ES-C-1 Initial Given:

Conditions:

Main Control Board alarms 044B (ACC TK B PRESS HILO) & 044C (ACC TK B LEV HILO) were received and reported to the CRS.

ALR actions have been taken and the CRS has directed filling operations per SYS EP-200.

Boron concentration has been verified and Chemistry samples are NOT required.

Initiating Cue: You are the Reactor Operator, the CRS has directed you to fill Accumulator Tank B, with the B SI Pump, using SYS EP-200, step 6.1. All prerequisites have been completed.

WC-2017-11 JPM S4 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

SET RM-11R SETPOINTS FOR Job Performance Measure No: S4 A RADIOACTIVE RELEASE K/A

Reference:

071/A4.25 (3.2): Ability to manually operate and/or monitor in the control room: Settings of process radiation monitor alarms, automatic functions, and adjustment of setpoints Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Initial Given:

Conditions:

The Unit is at 100% power in MODE 1.

Chemistry has completed sampling and has brought APF 07B-001-02-13, THF04 B RELEASE PERMIT for a liquid release.

Initiating You are the Reactor Operator, the CRS hands you the release permit and Cue: directs you to enter the Supervisor RM-80 Setpoints listed using SYS SP-121, step 6.3.

Task On RM-11R, The applicant successfully changed either HF RE-45 (SP056A Standard: Number 456) High Setpoint (Channel Item 009) to 2.5E-5 µCi/ml, or Low Setpoint (Channel Item 010) to 2.00E-5 µCi/ml.

Required AFP 07B-001-02-13 handout and SYS SP-121, OPERATION OF THE G.A.

Materials: MONITOR SYSTEM Simulator Setup: IC305 (Any initial condition will suffice)

JPM Initial Conditions established to run concurrently with JPM S1 (Recover dropped rod)

NOTE: RM11 alarm history does NOT reset with the simulator. Booth Operator must Restart the three RM11 computers per DTI-600, ATTTACHMENT R, EXAM SECURITY CLEANUP between successive performances of this JPM.

References:

SYS SP-121, OPERATION OF THE G.A. MONITOR SYSTEM, Rev 28

WC-2017-11 JPM S4 Form ES-C-1 Time No Alternate No Validation 10 minutes Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Step 6.3: Located correct step in procedure and continues Channel Item & Release with this section.

Setpoint Operations using RM-11 (SP056A) S/U 2.

Step 6.3.1: On panel SP056A, Verified that grid 1 was selected.

IF grid 1 is NOT selected, THEN SELECT grid 1 from the S/U MASTER MENU.

3.

Steps 6.3.2. and 6.3.2.1: NOTE: Applicant may On panel SP056A, Selects click on the channel LOGIN from the MASTER To change the value of a (456) from Grid 1 to MENU Current RM-80 Database check Current setpoint Channel Item, PERFORM the prior to logging on to following: make the change.

SELECT LOGIN, located in the MASTER MENU section. S/U 4.

Step 6.3.2.2: On panel SP056A, Verifies that the User login pop-up User login pop up window will appears.

appear, requesting user name (super) and the password.

S/U 5.

NOTE: The password is located Recognize and read note, Cue: (as Shift Manager) in the Shift Managers note book. place keeps, and The password is password acknowledges report from the Shift Manager with the password.

S/U

WC-2017-11 JPM S4 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 6.

Step 6.3.2.3: On panel SP056A, Enters user name (super) and ENTER the user name password (password) in (super) and the password the User login pop-up box.

(password) in the User login pop-up box. S/U 7.

NOTE: When RM-11 is in the Recognize and read note, SUPERVISOR mode the word place keeps, and SUPERVISOR is displayed acknowledges that the above the MASTER MENU and note was read and a green border appears around understood.

the page.

S/U 8.

Step 6.3.2.4: On panel SP056A, Selects ok.

SELECT ok.

S/U 9.

Step 6.3.2.5: On panel SP056A, Verifies SUPERVISOR is selected ENUSRE SUPERVISOR is by noting SUPERVISOR in selected by verifying that: the upper right corner of the MASTER MENU o The word SUPERVISOR is screen and the green displayed in upper right hand border appeared corner of the MASTER MENU screen o The green border appears around the page. S/U 10.

Step 6.3.2.6: On panel SP056A, Right clicks instrument HF RE-45 On grid 1, RIGHT CLICK the (456), verifies pop up box selected channel, pop up box appears.

will appear.

S/U 11.

Step 6.3.2.7: On panel SP056A, Selects the channel item edit.

SELECT CHANNEL ITEM EDIT. S/U

WC-2017-11 JPM S4 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 12.

NOTE: The value will be Recognize and read note, bordered in red when selected. place keeps, and acknowledges that the note was read and understood.

S/U 13.

Step 6.3.2.8: On panel SP056A, Selects either channel item 009 or SELECT the VALUE of the 010, verifies that it is Channel Item (CI) to be bordered in red.

changed.

S/U 14.

Step 6.3.2.9: On panel SP056A, Opens the channel item editor by To open the Channel Item either of the following:

Editor pop up box, PERFORM either of the following: 1: Selects EDIT SELCTED ITEM

EDIT SELECTED ITEM -

SELECTED 2: Double clicks SELECTED CHANNEL

SELECTED CHANNEL ITEM ITEM VALUE VALUE - DOUBLE CLICK S/U 15.

Step 6.3.2.10: On panel SP056A, Keys in desired value:

Key in the desired Channel Item value in the correct format. HF RE 45 (456)

For channel item 009 =

2.50e-05 OR For channel item 010 =

2.00e-05 S/U

WC-2017-11 JPM S4 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 16.

Step 6.3.2.11: On panel SP056A, To the right of the NEW VAULE SELECT the SEND TO RM- selects SEND to RM-80.

80 immediately to the right of the NEW VALUE change field. S/U 17.

Step 6.3.2.12: On panel SP056A, Verifies change monitor A Change Monitor Item configuration pop up box Configuration pop up box will appears.

appear on screen:

Verifies data entered in o IF the data in the message step 6.3.2.10 is correct, area is correct, THEN then presses the YES PRESS the YES button. button.

o IF the data in the message area is incorrect, THEN IF the data displayed is PRESS the NO incorrect, presses the NO button AND RETURN to button and returns to step Step 6.3.2.10 6.3.2.10.

S/U 18.

Step 6.3.2.13: On panel SP056A, Verifies on the alarm screen that a IF the entry is accepted, THEN message is displayed ENSURE the message on the showing the correct value.

Alarm screen indicates the correct value. S/U 19.

Step 6.3.2.14: On panel SP056A, Verifies that entry was accepted IF the entry is NOT and this step is N/A.

accepted, THEN VERIFY an error message is displayed. S/U

WC-2017-11 JPM S4 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 20.

Step 6.3.3.1: On panel SP056A, Keys in desired value:

To change the value of a Master RM-80 Database Channel Item, Keys same value as on PERFORM the following: step 6.3.2.10 Key in the desired Channel Item value in the correct format.

S/U 21.

Step 6.3.3.2: On panel SP056A, To the right of the SEND to RM-80 SELECT the SEND TO box, selects SEND TO MASTER box immediately to the MASTER.

right of the SEND to RM-80 box.

S/U 22.

Step 6.3.3.3: On panel SP056A, Verifies change monitor A Channel Change Item configuration pop up box Confirmation pop up box will appears.

appear on screen:

Verifies data entered in o IF the data in the message step 6.3.3.1 is correct, then area is correct, THEN PRESS presses the YES button.

the YES button.

o IF the data in the message IF the data displayed is area is incorrect, THEN incorrect, presses the NO PRESS the NO button and returns to step button AND RETURN to Step 6.3.3.1.

6.3.3.1 S/U 23.

Step 6.3.3.4 On panel SP056A, Verifies on the alarm screen that a IF the entry is accepted, THEN message is displayed ENSURE the message on the showing the correct value.

Alarm screen indicates the correct value. S/U

WC-2017-11 JPM S4 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 24.

Step 6.3.3.5 On panel SP056A, Verifies that entry was accepted IF the entry is NOT and this step is N/A.

accepted, THEN VERIFY an error message is displayed. S/U

25. Recognize and read note, NOTE: When successfully place keeps, and logged out, the LOG OUT will acknowledges that the disappear from the screen. note was read and understood.

S/U 26.

Step 6.3.3.6: On panel SP056A, closes the CHANNEL ITEM WHEN no further changes are EDITOR box and selects desired, THEN PERFORM the LOG OUT following:

a. CLOSE the CHANNEL ITEM EDITOR pop up box.

b. SELECT the LOG OUT NOTE: The Applicant will Cue: The JPM is continue in the procedure to complete.

repeat entering the other channel setpoint change. The RECORD STOP TIME S/U JPM may be ended at this point. BELOW.

Terminating cue: The JPM Is complete when the Applicant has completed entering the first setpoint change in the RM-11R.

STOP TIME:

WC-2017-11 JPM S4 Form ES-C-1 Initial Given:

Conditions:

The Unit is at 100% power in MODE 1.

Chemistry has completed sampling and has brought APF 07B-001 13, THF04 B RELEASE PERMIT for a liquid release.

Initiating Cue: You are the Reactor Operator, the CRS hands you the release permit and directs you to enter the Supervisor RM-80 Setpoints listed using SYS SP-121, step 6.3.

WC-2017-11 JPM S5 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

START RCP D IAW EMG ES-11 Job Performance Measure No: S5 K/A

Reference:

E03/EA1.1 (4.0 / 4.0): Ability to manually operate and / or monitor the following as they apply to LOCA cooldown and depressurization: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Initial Given:

Conditions:

A Loss of Coolant Accident has occurred (LOCA).

EMG E-0, REACTOR TRIP OR SAFETY INJECTION, and EMG E-1 LOSS OF REACTOR OR SECONDARY COOLANT actions have been completed and the crew has completed EMG ES-11, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 17 to Depressurize RCS to Refill PZR.

Initiating You are the Reactor Operator, the CRS has directed you to restart Reactor Cue: Coolant Pump (RCP) D, using EMG ES-11, POST LOCA COOLDOWN AND DEPRESSURIZATION, steps 18 through 20.

Task D RCP Oil Lift Pump was started, D RCP was started and left running, and Standard: D RCP Oil Lift Pump was stopped.

Required EMG ES-11, POST LOCA COOLDOWN AND DEPRESSURIZATION Materials:

Simulator setup: IC 308; IC 30, IMF mBB06B f:1.5 (RCS Loop 2 Cold leg break, 1.5, Modify break size as necessary while cooling down and depressurizing per EMG ES-11 to establish subcooling >30F and PZR Level >20%), Perform procedure actions of EMG E-0, EMG E-1, and EMG ES-11 up through Step 17.

References:

EMG ES-11, POST LOCA COOLDOWN AND DEPRESSURIZATION, Rev 24 Time No Alternate No Validation 10 minutes Critical: Path: Time:

WC-2017-11 JPM S5 Form ES-C-1 START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

CAUTION: If RCP seal cooling Cue: CRS informs the Recognize and read had previously been lost, the Operator that seal caution, place keeps, and affected RCP(s) shall not be cooling has not been lost acknowledges that the started prior to a status note was read and evaluation understood.

S/U 2.

NOTE: RCP D running alone Recognize and read note, will provide adequate PZR spray place keeps, and flow. If RCP D is available, all acknowledges that the remaining RCPs should be run note was read and to provide adequate spray flow. understood.

S/U

WC-2017-11 JPM S5 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 3.

Step 18.a: Initial cue includes RCPs stopped. On panel RL021, Check if RCP(s) Should be Several Diverse indications started: could also be checked to verify RCPS stopped

a. RCPs - ALL STOPPED including.

Located RCP hand switches, verifies BB HIS-37/38/39/40 indicates STOPPED (Red light off, Green light on).

Located RCP amp indications, verifies BB II-1/2/3/4 indicate(s) 0 amps.

On panel RL022, Located RCP flow indications, verifies all indicate 0%

flow.

Loop 1, BB FI-414, 415, 416 Loop 2, BB FI-424, 425, 426 Loop 3, BB FI-434, 435, 436 Loop 4, BB FI-444, 445, 446 S/U

WC-2017-11 JPM S5 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 4.

Step 18.b: Reactor Operator:

Cue: (IF asked)

Containment

b. RCS Subcooling - 1: Located RCS conditions are NOT GREATER THAN 30oF subcooling indications on Adverse due to high

[45oF] Panel RL022, verifies BB radiation levels.

TI-1390A/B indicate(s) greater than 30oF OR 2: Located RCS Subcooling indication on NPIS, verifies SPDS screen indicates greater than 30oF S/U 5.

Step 18.c: Reactor Operator will:

c. PZR Level - GREATER 1: Located PZR level THAN 20% [47%] indication on Panel RL002, verifies BB LI-460A/459A/461 indicates greater than 20%

OR 2: Located PZR Level indication on NPIS, verifies screen indicates greater than 20%

S/U

WC-2017-11 JPM S5 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 6.

Step 19.a: On panel RL016, Located PA02 indications, verifies Establish conditions for starting PA ZL-2 (White light lit) desired RCP(s): and/or PA EI-2 indicates bus voltage ~13.8 KV.

a. Ensure power to RCP(s) -

AVAILABLE

PA01 for RCPs A and B

PA02 for RCPs C and D S/U 7.

Step 19.b: On panel RL021, located Oil Lift pump hand switch,

b. Start oil lift pump(s) places BB HIS-44 in the RUN position. Verifies pump is running (Red run light on, Green stop light off).

Denotes time started.

S/U 8.

Step 19.c: Located Annunciator window 00-052A on the

c. Ensure Annunciator 00- MCB, verifies window is 052A, CCW to RCP FLOW CLEAR (not lit).

LO - CLEAR S/U 9.

Step 19.d: Located Annunciator window 00-073C for RCP

d. Ensure RCP thermal barrier D, verifies window is CCW flow annunciator - CLEAR (not lit).

CLEAR

00-070C for RCP A

00-071C for RCP B

00-072C for RCP C

00-073C for RCP D S/U

WC-2017-11 JPM S5 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 10.

Step 19.e: On panel RL021, Located number 1 seal P, verifies

e. Ensure number 1 seal P - BB PI-150A indicates >200 GREATER THAN 200 PSID PSID.

BB PI-153A for RCP A

BB PI-152A for RCP B

BB PI-151A for RCP C

BB PI-150A for RCP D S/U 11.

Step 19.f: On panel RL022, Located number 1 seal leakoff flow

f. Ensure number 1 seal on the MCB, verifies BG leakoff flow - GREATER FR-154 indicates number 1 THAN 0.2 GPM seal leakoff flow > 0.2

BG FR-157 for RCP A GPM.

BG FR-156 for RCP B

BG FR-155 for RCP C

BG FR-154 for RCP D S/U 12.

Step 19.g: On panel RL022, Located seal injection flow on the

g. Ensure seal injection flow - MCB, verifies BG FR-154 BETWEEN 8 GPM AND 13 indicates seal flow GPM. between 8-13 gpm.

BG FR-157 for RCP A

BG FR-156 for RCP B

BG FR-155 for RCP C

BG FR-154 for RCP D S/U 13.

Step 19.h: On panel RL002, Located VCT pressure on the MCB,

h. Ensure VCT pressure - verifies BG PI-115 is GREATER THAN 15 PSIG. greater than 15 psig.

o BG PI-115 S/U

WC-2017-11 JPM S5 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 14.

Step 20.a: Cue: (If the applicant Determines time started in completes the checks step 19.b and compares to Start desired RCP: within 2 minutes) 2 current time, verifies minutes have elapsed. greater than 2 minutes has

a. Check oil lift pump(s) - elapsed before continuing RUNNING FOR to the next step.

GREATER THAN 2 MINUTES S/U 15.

Step 20.b: Cue: (IF applicant starts May announce starting D to announce pump start) RCP

b. Start desired RCP(s). Pump Start

BB HIS-37 for RCP A Announcement has On panel RL021, Located

BB HIS-38 for RCP B been made. RCP hand switch, places

BB HIS-39 for RCP C BB HIS-40 in the

BB HIS-40 for RCP D NORMAL-AFTER-RUN position. Verifies pump is running (Red light on, Green light off) and changes in flow and amp readings.

Reports to CRS that D RCP started Denotes start time.

S/U 16.

Step 20.c: Determines time started in step 20.b and compares to

c. Check RCP(s) - RUNNING current time, verifies FOR GREATER THAN 1 greater than 1 minute has MINUTE elapsed before continuing to the next step.

S/U

WC-2017-11 JPM S5 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 17.

Step 20.d: On panel RL021, Located Oil Lift Pump hand switch,

d. Stop oil lift pump(s) Cue: The JPM is places BB HIS-44 in the o BB HIS-41 complete. STOP position. Verifies o BB HIS-42 pump is stopped (Red run o BB HIS-43 RECORD STOP TIME light off, Green stop light o BB HIS-44 BELOW. on).

S/U Terminating cue: The JPM Is complete when D RCP is running and Oil Lift Pump has been stopped.

STOP TIME:

WC-2017-11 JPM S5 Form ES-C-1 Initial Given:

Conditions:

A Loss of Coolant Accident has occurred (LOCA).

EMG E-0, REACTOR TRIP OR SAFETY INJECTION, and EMG E-1 LOSS OF REACTOR OR SECONDARY COOLANT actions have been completed and the crew has completed EMG ES-11, POST LOCA COOLDOWN AND DEPRESSURIZATION , Step 17 to Depressurize RCS to Refill PZR.

Initiating Cue: You are the Reactor Operator, the CRS has directed you to restart Reactor Coolant Pump (RCP) D, using EMG ES-11, POST LOCA COOLDOWN AND DEPRESSURIZATION, Steps 18 through 20.

WC-2017-11 JPM S6 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

Verify Containment Spray Job Performance Measure No: S6 requirements using EMG E-0 ATTACHMENT F K/A

Reference:

026/A4.01 (4.5 / 4.3): Ability to manually operate and/or monitor in the control room: CSS controls.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Initial A large break LOCA has occurred, control room personnel have entered and Conditions: are performing the steps of EMG E-0, REACTOR TRIP OR SAFETY INJECTION.

Initiating You are the Reactor Operator and were directed to complete EMG E-0 Cue: attachment F, AUTOMATIC SIGNAL VERIFICATION. You are on step F12.

Task Applicant manually aligns Containment Spray System by starting A Standard: Containment Spray Pump (EN HIS-3), opening discharge valve (EN HIS-6) and opening containment spray additive supply isolation valve (EN HIS-15).

Required EMG E-0 ATTACHMENT F, AUTOMATIC SINGAL VERIFICATION, Step F12 Materials:

Simulator Setup: IC 311: IC30, INSERT mBB05A f:29, mSA15A f:

AUTO/MAN, Trip RCPs

References:

EMG E-0, REACTOR TRIP OR SAFETY INJECTION, Rev 39 Time No Alternate Yes Validation 5 min Critical: Path: Time:

START TIME:

WC-2017-11 JPM S6 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Step F12.a: Recognizes that both Annunciator 00-59A & 0059B Verify Containment Spray Not are both LIT, transitions to RNO Required steps.

a. Containment pressure -

HAS REMAINED LESS THAN 27 PSIG:

o Annunciator 00-59A, CSAS - NOT LIT o Annunciator 00-59B, CSIB - NOT LIT o GN PR-934 S/U 2.

Step F.12.1 RNO: On panel RL021, Recognizes that all RCPs have already Perform the following: been tripped.

1. Stop all RCPs S/U 3.

Step F.12.2 RNO: On panel RL018, Attempts to manually initiate containment

2. IF containment spray spray by placing the following has NOT switches to ACTUATE actuated, THEN manuall o SB HS-43 AND SB HS-y actuate containment 45 spray.

o SB HS-44 AND SB HS-o SB HS-43 AND 46 SB HS-45 o SB HS-44 AND SB HS-46 NOTE: Actuation of CSAS is a two-handed operation, switches

Commence Alternate Path*

must be turned simultaneously.

S/U

WC-2017-11 JPM S6 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 4.

Step F.12.3 RNO: ESF SYS STATUS INDICATION SA 066-Y

3. Check ESFAS status panel CSAS section - Verifies the YELLOW Train ALL WHITE LIGHTS LIT LIGHTS LIT o Red Train ESF SYS STATUS o Yellow Train INDICATION SA 066-X Recognizes that the RED Train lights are NOT LIT and continues to the next step S/U 5.

Step F.12.4 RNO: Note: On panel RL017, Recognizes Candidate MAY place that the A train of Containment

4. IF any CSAS ESF PANEL SA-066X Spray did not align and component NOT properly MODE SEL SA HS-23 in manually aligns it:

aligned, THEN manually Pull-To-Lock in order to STARTS CTMT SPRAY PUMP align associated see White Light A

component indication of repositioned ESF equipment during o EN HIS PLACED IN the alignment. RUN (Red light ON, Green light OFF)

OPENS CTMT SPRAY PUMP A DISCH VLV o EN HIS OPEN (Red light ON, Green light OFF)

OPENS CTMT SPRAY A ADDITIVE SPLY o EN HIS OPEN (Red light ON, Green light OFF)

Cue: The JPM is complete.

RECORD STOP TIME S/U BELOW.

.Terminating The JPM Is complete when the candidate has manually aligned A cue: Containment Spray system for operation.

STOP TIME:

WC-2017-11 JPM S6 Form ES-C-1 WC-2017-11 JPM S6 Form ES-C-1 Initial A large break LOCA has occurred, control room personnel have entered Conditions: and are performing the steps of EMG E-0, REACTOR TRIP OR SAFETY INJECTION.

Initiating Cue: You are the Reactor Operator and were directed to complete EMG E-0 attachment F, AUTOMATIC SIGNAL VERIFICATION. You are on step F12.

WC-2017-11 JPM S7 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

TRANSFER NB02 FROM THE Job Performance Measure No: S7 EDG TO THE NORMAL POWER SUPPLY (UNLOAD AND STOP THE EDG FOLLOWING LOSS OF ESW)

K/A

Reference:

064/A1.03 (3.2 / 3.3): Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the EDG system controls including: Operating voltages, currents, and temperatures.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Initial Given:

Conditions:

The unit has experienced a loss of off-site power (LOOP) event.

All systems responded as designed.

EMG E-0, REACTOR TRIP OR SAFETY INJECTION and EMG ES-02, REACTOR TRIP RESPONSE have been completed.

The cause of the power loss has been corrected, off-site power is now available.

Bus NB01 has been transferred to the normal off-site power source and Diesel Generator NE01 has been secured.

The Turbine Building Operator is standing by at local EDG control panel for NE02 with communications established with the Control Room.

The SM has conducted a crew briefing discussing the evolution.

NB0214, SBO DG BUS feeder breaker is open/racked up.

The required RTFQ Report has been run and reviewed.

Initiating You are the Reactor Operator, the CRS directs you to transfer NB02 to the Cue: normal off-site supply and secure Diesel Generator NE02 using SYS NB-202, TRANSFERRING NB02 POWER SOURCES, step 6.4.

Task Bus NB02 is successfully transferred from NE02 to Normal off-site power Standard: supply per SYS-NB-202, and Diesel Generator NE02 is unloaded and tripped within 3 minutes of a loss of ESW.

WC-2017-11 JPM S7 Form ES-C-1 Required SYS NB-202, TRANFERRING NB02 POWER SOURCES.

Materials:

Simulator Setup: IC 310: IC 30, Loss and restoration of Offsite Power (IMF rSY01 i:-1 f:-1, DMF mSY01, IRF rSY01 f:1, IRF rSY02 f:2, IRF rSY03 f:1, IRF rSY05 f:1, IRF rSY06), Actions of EMG E-0 and EMG ES-02, Restoration of normal power to NB01 using SYS NB-201. Conditional loss of B ESW as pump breaker will trip once normal supply breaker to NB01 is closed. {bkNB00209.state=1} ICM bkrDPEF01B t:1 d:0

References:

SYS NB-202, TRANSFERRING NB02 POWER SOURCES, Rev 55 OFN EF-033, LOSS OF ESSENTIAL SERVICE WATER, Rev 18 Time No Alternate Yes Validation 15 min Critical: Path: Time:

START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Step 6.4: Located correct step in procedure and continues Transfer from DG NE02 to with this section.

normal FDR BKR S/U 2.

Step 6.4.1: Recognizes Emergency Diesel start was by an IF started by auto signal, automatic signal (LOOP).

THEN DEPRESS KJ HS-108A, DG NE02 START-RESET/STOP On panel RL015, pushbutton for Diesel Generator depresses KJ HS-108A NE02. START-RESET push button o KJ HS-108A, START RESET - DEPRESSED S/U

WC-2017-11 JPM S7 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 3.

Step 6.4.2: On panel RL015, Located normal supply sync PLACE NB HS-8, NB02 NRM transfer hand switch, SPLY SYNC TRANSFER switch places NB HS-8 to the ON to on. position.

o NB HS ON S/U 4.

Step 6.4.3: On panel RL015, Located sync scope selector hand PLACE NB HS-11, 4.16 KV switch, places NB HS-11 BUS NB02 SYNC-SCOPE SEL to the MAIN FDR BRKR to MAIN FDR BRKR position. position NB HS MAIN FDR BRKR S/U 5.

Step 6.4.4: Contacts Turbine Building Cue: (As Turbine Operator to verify Building Operator)

IF PARALLEL OPERATION PARALLEL OPERATION PARALLEL white light is NOT lit, THEN white light lit at panel OPERATION white light PLACE NE HS-6, DG NE02 NE106 is NOT LIT at panel UNIT PARALLEL switch to the NE106.

RESET then PARALLEL position On panel RL015, Located AND HOLD in PARALLEL, until unit parallel hand switch for the PARALLEL OPERATION NE02, places NE HS-6 in white is lit at panel NE106. the RESEST position and then to the PARALLEL

1. NE HS RESET- position.

THEN-PARALLEL

2. NE106 Parallel Operation Cue: (After Reactor After receiving report from

- WHITE LIGHT LIT Operator places NE HS-6 Turbine Building Operator,

3. NE HS OFF-AFTER- in PARALLEL position, releases hand switch NE PARALLEL as Turbine Building HS-6, verifies it returns to Operator) PARALLEL the OFF position OPERATION white light IS LIT at panel NE106 S/U

WC-2017-11 JPM S7 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 6.

Step 6.4.5: On panel RL015, Located NE02 governor switch and ADJUST KJ HS-107A, DG Synchroscope for NB02, NE02 GOV switch, to adjust the adjusted KJ HS-107A until frequency so Synchroscope NB indication on NB EI-4 was EI-4 rotates in the FAST in the FAST direction with direction, with one rotation every one rotation every 10-20 10-20 seconds seconds.

o KJ HS-107A - ADJUSTED Verifies NE-31 light LIT.

o NB EI FAST DIRECTION ROTATION 10 TO 20 SECONDS o NE ZL-31 LIT S/U 7.

NOTE: Proper operation of NB Recognize and read note, ZL-10 is ensured by observing place keeps, and that the lights are dimmest when acknowledges that the the pointer on the Synchroscope note was read and NB EI-4 is at 12 oclock and understood.

brightest when the pointer is at 6 oclock. S/U 8.

Step 6.4.6: On panel RL015, Located synchroscope for NB02, VERIFY proper operation of NB verifies NB ZL-10 indicates ZL-10, 4.16 KV BUS NB02 dim at the 12 oclock SYNCH LIGHT. position and bright at the 6 oclock position.

o NB ZL DIM AT 12 OCLOCK POISTION o NB ZL BRIGHT AT 6 OCLOCK POSITION S/U

WC-2017-11 JPM S7 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 9.

NOTE: On RL015, NB ZL-3 will Recognize and read note, only be lit when the synchro- place keeps, and scope is in the 12 oclock acknowledges that the position. note was read and understood.

S/U 10.

Step 6.4.7: On panel RL015, Located NE02 auto voltage reg ADJUST NE HS-14A, DG NE02 switch, bus voltage AUTO VOLT REG switch, so NB incoming source, NB02 EI-29, BUS NB02 VOLTAGE bus voltage, and NB02 INCOMING SOURCE is norm supply synch light.

matched with NB EI-2, 4.16 KV BUS NB02 VOLT. Adjusted KJ HS-14A until indication on NB EI-29 and o NE HS-14A - ADJUSTED NB EI-2 matched and NB o NB EI-29 & NB EI ZL-3 light LIT.

MATCHED o NB ZL LIT S/U 11.

Step 6.4.8: On panel RL015, Located Synchroscope for NB02 WHEN Synchroscope NB EI-4 and normal supply breaker pointer reaches the 11 oclock for NB02 hand switch, at position, THEN CLOSE NB HIS- 11 oclock indication on NB 4, NB02 NORM SPLY BKR EI-4 placed NB HIS-4 in NB0209 the NORMAL-AFTER-CLOSE position. Verifies o NB HIS NORMAL- breaker closed (Red light AFTER-CLOSE on, Green light off) and releases switch.

S/U

WC-2017-11 JPM S7 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 12.

Upon closure of breaker NB0209 Cue: This is the Site Recognizes that cooling (NB02 Normal Supply Breaker) Watch, there is an acrid flow has been lost to DG ESW Pump B will trip resulting in odor and smoke in the NE02 and that it must be a loss of cooling to DG NE02. vicinity of the B ESW unloaded and shutdown pump. within 3 minutes.

Commence Alternate Path*

Cue: (If the applicant NOTE: The applicant will Reactor Operator might reports the loss of ESW be performing actions on recognize ESW Pump Trouble to the CRS without taking Panel RL015. The ESW (55C) alarm is active, and that action, Report as CRS) pump running indications ESW Pump B has tripped. What action do you and alarms are on Panel recommend? RL019.

Per OFN EF-033, LOSS OF ESSENTIAL SERVICE WATER, Foldout Page item #1, Without cooling flow, the loaded Diesel Generator NE02 should be secured within 3 minutes. S/U

13. Per OFN EF-033, LOSS OF ESSENTIAL SERVICE WATER, Note: Time start is when On panel RL015, Located Foldout Page item #1, IF any ESW is lost, time stop is emergency supply breaker emergency diesel is running when the EDG is for NB02, places NE HIS-LOADED AND cooling flow can unloaded (output breaker 26 in PTL NOT be established, THEN open) and stopped.

unload affected emergency Directs the Local Operator diesel within 3 minutes by Start:________ to stop B EDG by locally performing the following: placing the Master Transfer Stop:_________ Switch to LOC/MAN

a. Place affected EDG Supply position and depressing Breaker in PTL KJ-HS 108B.

NE HIS-26 for NE02 NOTE: The critical step is

b. Stop affected emergency also met if the applicant diesel. stops B EDG from the

1) Locally place Master control room by depressing Transfer Switches to KJ HS-108A switch on LOC/MAN. Panel RL015 per AP 15C-003, PROCEDURE

KJ HS-109 for NE02 USERs GUIDE FOR

2) Locally stop the diesel. ABNORMAL PLANT CONDITIONS, Paragraph

KJ HS-108B for NE02 4.15, Manual Preemption.

S/U

WC-2017-11 JPM S7 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 14.

Inform CRS that NB02 has been Cue: CRS Informs CRS procedure transferred to the Normal Supply acknowledges report. step(s) completed and B and that B Diesel Output Diesel output Breaker is Breaker is Open and B EDG is Cue: The JPM is Open and B EDG is stopped due to a loss of cooling complete. secured.

water.

RECORD STOP TIME BELOW.

S/U Terminating cue: The JPM Is complete when the applicant has transferred NB02 bus power supply, Placed the B EDG Output breaker in PTL, and either stopped or directed local stopping of B EDG and reported the abnormal condition to the CRS.

STOP TIME:

WC-2017-11 JPM S7 Form ES-C-1 Initial Given:

Conditions:

The unit has experienced a loss of off-site power (LOOP) event.

All systems responded as designed.

EMG E-0, REACTOR TRIP OR SAFETY INJECTION and EMG ES-02, REACTOR TRIP RESPONSE have been completed.

The cause of the power loss has been corrected, off-site power is now available.

Bus NB01 has been transferred to the normal off-site power source and Diesel Generator NE01 has been secured.

The Turbine Building Operator is standing by at local EDG control panel for NE02 with communications established with the Control Room.

The SM has conducted a crew briefing discussing the evolution.

NB0214, SBO DG BUS feeder breaker is open/racked up.

The required RTFQ Report has been run and reviewed.

Initiating Cue: You are the Reactor Operator, the CRS directs you to transfer NB02 to the normal off-site supply and secure Diesel Generator NE02 using SYS NB-202, TRANSFERRING NB02 POWER SOURCES, step 6.4.

WC-2017-11 JPM S8 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

BYPASS A FAILED PRNI Job Performance Measure No: S8 CHANNEL K/A

Reference:

012/A4.03 (3.6 / 3.6): Ability to manually operate and/or monitor in the control room: Channel blocks and bypasses.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant Initial Power Range Nuclear Instrument N-43 has failed low. The crew is responding Conditions: per OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment R.

Initiating You are the Reactor Operator. The CRS directs you to bypass the failed Cue: power range flux channel per OFN SB-008, Attachment R, Step R4.

Task Power Range Nuclear Instrument N-43 is bypassed per OFN SB-008 Step R4.

Standard:

Required OFN SB-008, INSTRUMENT MALFUNCTIONS, Rev 45, Page 83 of 122.

Materials:

Simulator Set up: IC 307: IC 30, IMF mSE03C f:0 (PR NI-43 fails low),

Actions per OFS SB-008, Attachment R, Steps 1-3, Rods in Manual.

JPM initial conditions set to run concurrently with S3 JPM (Fill B Accumulator).

References:

OFN SB-008, INSTRUMENT MALFUNCTIONS, ATTACHMENT R, Rev 45 Time No Alternate No Validation 5 minutes Critical: Path: Time:

START TIME:

WC-2017-11 JPM S8 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Step R4: Located correct step in procedure and continues Bypass Failed Power Range with this section.

Flux Channel S/U 2.

Step R4.a.1): Nuclear Instrumentation Protection Channel IV,

a. At the Detector Current Drawer N50.

Comparator Drawer (N50),

perform the following: Located Upper Section switch and places it in the

1) Turn the Upper Section PRN43 position.

switch to the failed power range flux channel. Verifies CHANNELS DEFEAT light is LIT (above switch).

S/U 3.

Step R4.a.2): Nuclear Instrumentation Protection Channel IV,

2) Turn the Lower Section Drawer N50.

switch to the failed power range flux channel. Located Lower Section switch and places it in the PRN43 position.

Verifies CHANNELS DEFEAT light is LIT (above switch).

S/U

WC-2017-11 JPM S8 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 4.

Step R4.a.3): Nuclear Instrumentation Protection Channel IV,

3) Turn the Power Drawer N50 Mismatch Bypass switch to the failed power range Located Power Mismatch flux channel. Bypass switch(s) and places the left switch in BYPASS PRN43 position.

S/U 5.

Step R4.a.4): Nuclear Instrumentation Protection Channel IV,

4) Turn the Rod Stop Drawer N50 Bypass switch to the failed power range flux Located the Rod Stop channel. Bypass switch(s) and places the left switch in BYPASS PRN43 position.

S/U 6.

Step R4.b.1): Nuclear Instrumentation Protection Channel IV,

b. At the Comparator and Rate Drawer N37/46 Drawer (N37/46), perform the following: Located the Comparator Channel Defeat switch and

1) Turn the Comparator places it in the PRN43 Channel Defeat switch to position.

the failed power range channel. Verifies COMPARATOR DEFEAT light is LIT and CHANNEL DEVIATION light is NOT LIT Cue: The JPM is May return to the control complete. room to verify annunciator 078A PR CHANNEL DEV RECORD STOP TIME window is CLEAR.

BELOW.

S/U

WC-2017-11 JPM S8 Form ES-C-1 Terminating cue: The JPM Is complete when the applicant has completed step R4 of OFN SB-008.

STOP TIME:

WC-2017-11 JPM S8 Form ES-C-1 Initial Power Range Nuclear Instrument N-43 has failed low. The crew is Conditions: responding per OFN SB-008, INSTRUMENT MALFUNCTIONS, Attachment R.

Initiating Cue: You are the Reactor Operator. The CRS directs you to bypass the failed power range flux channel per OFN SB-008, Attachment R, Step R4.

WC-2017-11 JPM P1 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

TRANSFER BUS NN02 Job Performance Measure No: P1 POWER SUPPLY TO NN12 FROM BYPASS CVT FOLLOWING A LOSS OF AND RESTORATION OF BUS NK02.

K/A

Reference:

058/AA1.03 (3.1 / 3.3): Ability to operate and/or monitor the following as they apply to the Loss of DC Power: Vital and battery bus components.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance X Actual Performance Classroom Simulator Plant X Initial Given:

Conditions:

The unit is in MODE 1 following a loss of NK02 at power.

Bus NN02 is energized from the Bypass CVT.

Electrical Maintenance has restored power to bus NK02.

The CRS directs you to realign power supply to bus NN02 from Inverter Initiating NN12, powered from NK02 using SYS NN-200B, TRANSFERRING NN02 Cue:

AND NN04 BUSES BETWEEN POWER SOURCES, starting with step 6.12.1.4. A brief has been conducted and the Shift Manager has provided you all the keys needed to perform this evolution.

Task Vital 120 VAC Instrument Bus NN02 transferred from bypass CVT to Inverter Standard: NN12 without interruption of power.

Required SYS NN-200B, TRANSFERRING NN02 AND NN04 BUSES BETWEEN Materials: POWER SOURCES, Rev 1A, Section 6.12 marked up handout and FIGURE 1, 120VAC BUS (NN) - B TRAIN.

References:

SYS NN-200B, TRANSERRING NN02 AND NN04 BUSES BETWEEN POWER SOURCES, Rev 1A Time No Alternate No Validation 15 Min Critical: Path: Time:

WC-2017-11 JPM P1 Form ES-C-1 START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Step 6.12.1.4: Located correct step in the procedure and proceeds to the WHEN NK02 is available and next step.

NN12 is ready to be restored, S/U THEN PERFORM the following:

2.

Step 6.12.1.4.a.1): Cue: Switch is DOWN On NN12, Located DC INPUT and Green Lamp LIT. Breaker, verifies B1 is in the At NN12 INVERTER, VERIFY OFF position.

NN12 is aligned for transfer, as follows: S/U

1) NN12 B1, DC INPUT breaker is off.

o B1 - OFF 3.

Step 6.12.1.4.a.2): Cue: Switch is DOWN On NN12, Located INVERTER and Green Lamp is LIT. OUTPUT, verifies B2 is in the

2) NN12 B2, INVERTER OFF position.

OUTPUT breaker is off.

o B2 - OFF S/U 4.

Step 6.12.1.4.a.3): On NN12, Located BYPASS Cue: Switch is UP and Red Lamp is LIT. INPUT TO STATIC SWITCH,

3) NN12 B4, BYPASS verifies B4 is in the ON INPUT TO STATIC position.

SWITCH breaker is on.

o B4 - ON S/U

WC-2017-11 JPM P1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 5.

CAUTION: Breaker B701 is 480 Recognize and read caution, Cue: Proper PPE is VAC. Follow requirements of AI place keeps, and acknowledges obtained.16-007, WCNOC ELECTRICAL that the note was read SAFETY MANUAL understood.

Discusses correct electrical safety requirements and precautions that would be taken.

S/U 6.

Step 6.12.1.4.a.4): Cue: Switch is UP and On NN12, Located AC INPUT Red Light is LIT. to BYPASS CVT, verifies B701

4) NN12 B701, AC INPUT is in the ON position.

to BYPASS CVT breaker is on.

o B701 - ON S/U 7.

Step 6.12.1.4.a.5): Cue: Indicate that the On NN12, Located switch is to the left and MAINTENANCE BYPASS

5) NN12 MAINTENANCE Normal Operation Lamp SWITCH, verifies it is in the BYPASS SWITCH in is LIT. NORMAL OPERATION normal operation. position.

o MAINTENANCE BYPASS SWITCH -

NORMAL OPERATION S/U 8.

Step 6.12.1.4.a.6): Cue: Indicate that the On NN12, Located MANUAL switch is to the left and TRANSFER SWITCH, verifies it

6) NN12 MANUAL Normal Operation Lamp is in the NORMAL OPERATION TRANSFER SWITCH in is LIT. position.

normal operation.

o MANUAL TRANSFER SWITCH - NORMAL OPERATION S/U

WC-2017-11 JPM P1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 9.

Step 6.12.1.4.a.7): Cue: Indicate that the On NN12, Located ALARM Switch is aligned to the DEFEAT switch, verifies it is in

7) NN12 ALARM DEFEAT right. the NORMAL position.

switch in normal.

o ALARM DEFEAT -

NORMAL S/U 10.

Step 6.12.1.4.a.8): Cue: Indicate that switch On NN12, Located SYNCH is aligned to the left and REFERENCE switch, verified it

8) NN12 SYNCH Green Lamp is LIT. is in the SYNC INPUT FROM REFERENCE switch in INTERNAL BYPASS SOURCE sync input from internal position.

bypass source.

o SYNC REFERENCE -

SYNC INPUT FROM INTERNAL BYPASS SOURCE S/U 11.

Step 6.12.1.4.b.1): Cue: Disconnect switch On NK02, verify NK0211 is UP. breaker is closed.

ENERGIZE NN12 INVERTER, as follows:

1) ENSURE NK0211, NN012 7.5 KVA INVERTER is closed o NK0211 - ON S/U 12.

Step 6.12.1.4.b.2): Cue: All lamps LIT On NN12, Located PRESS TO TEST LIGHTS button, pressed

2) TEST NN12 lamps, by the button, and verified all lights depressing the PRESS LIT.

TO TEST LIGHTS button while inspecting lamps.

a) PRESS TO TEST LIGHTS -

DEPRESSED b) LAMPS - ALL LIT S/U

WC-2017-11 JPM P1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 13.

NOTES: Recognize and read notes, place keeps, and acknowledges o Substeps of step that the note was read 6.12.1.4.b.3 may be understood.

checked as completed following performance of all substep actions. The substeps should be carefully reviewed prior to performing to ensure the proper sequence of actions is understood.

o The precharge lamp will light shortly after the precharge pushbutton is S/U depressed.

WC-2017-11 JPM P1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 14.

Step 6.12.1.4.b.3): On NN12, Located PRECHARGE pushbutton, Cue: (before simulating depresses PRECHARGE

3) CLOSE NN12 B1, DC depressing the button) pushbutton and holds.

INPUT BREAKER, as Light is NOT LIT.

follows:

a) DEPRESS and HOLD the PRECHARGE pushbutton.

PRECHARGE BUTTON -

DEPRESSED AND HELD Cue: (after simulating b) WHEN PRECHARGE depressing the button) Located breaker B1, when light is lit, THEN Light is LIT. PRECHARGE light is LIT and CLOSE B1 breaker. while still holding the a).1 PRECHARGE PRECHARGE pushbutton, LIGHT - LIT closes breaker B1 b).2 B1 - On c) WHEN DC INPUT Cue: Switch is UP and BREAKER CLOSED Red Lamp is LIT. When breaker B1 indicates light is lit, THEN closed, releases PRECHARGE RELEASE pushbutton.

PRECHARGE pushbutton. Marks time that Inverter was c).1 DC INPUT energized.

BREAKER CLOSED - LIT c).2 PRECHARGE PUSHBUTTON S/U

- RELEASED 15.

Step 6.12.1.4.b.4): Cue: (when correct On NN12, Located DC INPUT meter is identified) VOLTS, reads and documents

4) RECORD DC INPUT Indicates 133 VDC on indication.

VOLTS from NNEI0121 meter o NNEI0121 Volts

________VDC S/U

WC-2017-11 JPM P1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 16.

Step 6.12.1.4.b.5): On NN12, Located INVERTER OUTPUT breaker, closes breaker B2 and verifies closed

5) CLOSE NN12 B2, light lit (Red light on, Green INVERTER OUTPUT light off) breaker and VERIFY INVERTER OUTPUT BREAKER CLOSED light is lit. Cue: Switch is up a) B2 - ON b) INVERTER Cue: Red light is LIT OUTPUT BREAKER CLOSED - LIT S/U 17.

Step 6.12.1.4.b.6): Cue: Button is depressed On NN12, Located ALARM RESET, presses pushbutton.

6) RESET NN12 Inverter alarms, by pressing the S/U ALARM RESET pushbutton.

o ALARM RESET -

PRESSED 18.

NOTE: Voltage is expected to be Recognize and read note, place high immediately after starting a keeps, and acknowledges that cold inverter and should trend the note was read understood.

down as the inverter warms up.

S/U

WC-2017-11 JPM P1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 19.

Step 6.12.1.4.b.7): Cue: (after each lamp is On NN12, Located alarm panel checked) Lamp is OUT for NN12, verified each of the

7) VERIFY the following listed alarms was CLEAR.

alarms clear o OVER TEMPERATURE -

CLEAR o DC LOW VOLTAGE -

CLEAR o DC HIGH VOLTAGE -

CLEAR o OUT OF SYNCH -

CLEAR o INVERTER OUTPUT LOW VOLTAGE -

CLEAR o INVERTER OUPUT HIGH VOLTAGE -

CLEAR o FUSE BLOWN -

CLEAR S/U 20.

Step 6.12.1.4.b.8): Cue: 16 minutes have Reads step and starts 15 elapsed minute wait based on start time

8) ENSURE NN12 B1, DC from step 6.12.1.4.B.3 for INPUT BREAKER, has inverter warm up.

been closed for at least 15 minutes to allow the internal inverter to warm up.

o INVERTER -

WARMED UP S/U 21.

Step 6.12.1.4.b.9): Cue: Lamp is LIT On NN12, Located NN12 IN SYNC light, verifies that light is

9) VERIFY NN12 IN SYNC LIT.

light lit o IN SYNCH - LIT S/U

WC-2017-11 JPM P1 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 22.

Step 6.12.1.4.b.10): Cue: Lamp is LIT On NN12, Located INVERTER TO LOAD pushbutton, depresses INVERTER TO

10) On NN12, DEPRESS LOAD pushbutton.

pushbutton INVERTER TO LOAD and VERIFY Located INVERTER INVERTER SUPPLYING SUPPLYING LOAD LIGHT, LOAD light lit. verified light is LIT.

a) INVERTER TO LOAD -

DEPRESSED b) INVERTER S/U SUPPLYING LOAD -

LIT 23.

NOTE: Inverter output voltage Recognize and read note, place and frequency shall be 112.1 - keeps, and acknowledges that 123.9 VAC and 59.7 - 60.3 Hz the note was read understood.

for inverter to be operable.

S/U 24.

Step 6.12.1.4.b.11): Cue: (When correct On NN12, Located SYSTEM meter is identified) OUTPUT VOLTS and

11) RECORD SYSTEM INVERTER OUTPUT OUTPUT VOLTS and FREQUENCY reads and INVERTER OUTPUT documents indication.

FREQUENCY Indicate 120 Volts on the o NNEI0122_____VAC meter o NNSI0121_____Hz Indicates 60 Hz on the meter Cue: The JPM is complete.

RECORD STOP TIME S/U BELOW.

Terminating cue: The JPM Is complete when NN12 Inverter has been aligned to bus NK02.

STOP TIME:

WC-2017-11 JPM P1 Form ES-C-1 Initial Conditions: Given:

The unit is in MODE 1 following a loss of NK02 at power.

Bus NN02 is energized from the Bypass CVT.

Electrical Maintenance has restored power to bus NK02.

Initiating Cue: The CRS directs you to realign power supply to bus NN02 from Inverter NN12, powered from NK02 using SYS NN-200B, TRANSFERRING NN02 AND NN04 BUSES BETWEEN POWER SOURCES, starting with step 6.12.1.4. A brief has been conducted and the Shift Manager has provided you all the keys needed to perform this evolution.

WC-2017-11 JPM P2 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

MAKEUP TO THE SFP FROM Job Performance Measure No: P2 ESW K/A

Reference:

033 A2.03 (3.1/3.5): Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance X Actual Performance Classroom Simulator Plant X Initial Given:

Conditions:

A leak occurred in the Spent Fuel Pool (SFP).

The crew entered OFN EC-046, FUEL POOL COOLING AND CLEANUP MALFUNCTIONS.

SFP level is at -30 inches and the crew is attempting to restore level.

No borated sources are available.

Initiating The Control Room Supervisor directs you to perform OFN EC-046, Step 16 Cue: RNO, to makeup to the Spent Fuel Pool from the Train A of the ESW System.

Task The Operator established makeup from ESW System, Train A ONLY to the Standard: SFP per OFN EC-046, Step 16 RNO.

Required 1. PPE appropriate for entering the RCA.

Materials:

2. OFN EC-046, Revision 6, Step 16

References:

OFN EC-046, Revision 5 Time No Alternate No Validation 10 Minutes Critical: Path: Time:

WC-2017-11 JPM P2 Form ES-C-1 START TIME:

JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

Step 16 RNO a: Cue: The valve is open. Located EC-V127 at 2026' Fuel Building, HVAC Room and closed

Makeup from ESW System: EC-V127.

a. Close ESW To Spent Fuel Cue: The handwheel Turns valve hand wheel clockwise Pool Line Drain Valve: rotates in the clockwise to close.

direction and the stem is

EC-V127 (2026' FUEL moving inward until it stops S / U BLDG, HVAC ROOM) - Train A moving.

EC-V126 (2026 FUEL BLDG, HVAC ROOM) - Train B NOTE: EC-V126 is for Train B and should NOT be closed.

WC-2017-11 JPM P2 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 2.

Step 16 RNO b: When the applicant Described removal of padlock from describes using the EC-V020 and EC-V125 hand Unlock and open ESW Supply Standard Operations Key wheels.

Valves to Fuel Pool Cooling and (2924) to remove the Cleanup System: padlock and free the Turned handwheel for EC-V020 handwheel, The key is in counter-clockwise to the open

EC-V020 And EC-V125 the Aux Building Watch key position.

ring. Cue: the valve is (both valves are located 2026' unlocked. Turned handwheel for EC-V125 Fuel Building, HVAC Room) - counter-clockwise to the open Train A If the applicant does NOT position.

describe removing the

EC-V020 And EC-V124 lock: Cue: the valve does May inform Control Room of the NOT move. actions taken to monitor for rise in (both valves are located 2026 SFP Level.

FUEL BLDG, HVAC ROOM) - Cue: The handwheel (EC-Train B V020) rotates in the counter clockwise direction and the NOTE: EC-V019 and EC-V124 are hand wheel moves out Exam Note:

for Train B and Should NOT be towards you until it stops Unlocked or Opened. moving. SFP Level EC LI-39A indication is in the Control room on panel Cue: The handwheel (EC- RL021.

V125) rotates in the counter clockwise direction and the Local FLEX SFP Level indication hand wheel moves out EC LI-059 and EC LI-060 are towards you until it stops located in the 2047 Aux Building moving. Control Room A/C Unit rooms and may be used without entering the Cue: Sound of flowing Fuel Building to verify locally.

water are heard.

S / U THE JPM IS COMPLETE RECORD STOP TIME BELOW.

Terminating cue: The JPM is completed when the ESW Train A Supply to SFP Cooling System valves EC-V020 and EC-V125 are open.

STOP TIME:

WC-2017-11 JPM P2 Form ES-C-1 Initial Conditions: Given:

A leak occurred in the Spent Fuel Pool (SFP).

The crew entered OFN EC-046, FUEL POOL COOLING AND CLEANUP MALFUNCTIONS.

SFP level is at -30 inches and the crew is attempting to restore level.

No borated sources are available.

Initiating Cue: The Control Room Supervisor directs you to perform OFN EC-046, Step 16 RNO, to makeup to the Spent Fuel Pool from the Train A of the ESW System.

WC-2017-11 JPM P3 Form ES-C-1 Facility: WCNOC Task No:

Task

Title:

PERFORM LOCAL ACTIONS TO Job Performance Measure No: P3 BORATE THE REACTOR COOLANT SYSTEM (USE THE ALTERNATE METHOD FOR LOCAL OPERATION).

K/A

Reference:

APE 024/AA1.04 (3.6 / 3.7): Ability to operate and / or monitor the following as they apply to emergency boration: Manual Boration Valve.

Examinee: NRC Examiner:

Start: ___________ Stop: ____________ Date: _________________________

Result: Satisfactory / Unsatisfactory Examiner Signature: ______________________

Method of testing: Simulated Performance X Actual Performance Classroom Simulator Plant X Initial A reactor trip has recently occurred from 100% power and multiple rods did NOT Conditions: insert. The control room is performing OFN BG-009, EMERGENCY BORATION, Attachment A, Emergency Boration, Establishing Alternate Boration Flowpath.

Initiating The Control Room Supervisor (CRS) informs you that that during step A2, BG FCV-Cue: 110A, Boric Acid Blending Tee Inlet Isolation Valve, failed to open from the Control Room. The CRS directs you to continue OFN BG-009, Attachment A at step A2 RNO.

Task Emergency boration established greater than 30 GPM through Emergency Boration Standard: Valve, BG HV-8104.

Required OFN BG-009, Emergency Boration, Rev 26, Attachment A Materials:

References:

OFN BG-009, Emergency Boration, Rev 26.

Time Critical: No Alternate Yes Validation Time: 10 Minutes Path:

START TIME:

WC-2017-11 JPM P3 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 1.

RNO Step A2: Reads and recognizes the correct procedure step, proceeds to sub-Fail open BORIC ACID BLENDING steps.

INLET ISOLATION S/U 2.

RNO Step A.2.a: 1974 level of Aux Bldg, A Safety Injection Pump Room.

a. Locally isolate instrument air to Cue: V1 and V2 Handles BG FCV-110A. (1974 AUX are perpendicular to the air Located valve BG FCV-110A and BLDG, SI PUMP RM A) lines the air isolations, V1 and V2.

Closed the two instrument air isolation valves to the positioner and the valve by turning the handles so they are perpendicular to the airlines S/U 3.

RNO Step A.2.b: Cue: Sound of air venting Vented air off the operator by is heard opening the petcock on the bottom

b. Locally vent air pressure form of the regulator filter drain or by valve Cue: BG FCV-110A does any other method that will bleed air not move off the top of the operator.

Verifies through valve stem response that the valve is NOT re-positioning S/U 4.

RNO Step A.2.c: Recognizes from cue that the Cue: (if contacted, as the valve cannot be opened, goes to control room) acknowledge

c. IF valve can NOT be opened, Step A8.

report that valve would not THEN go to step A8.

move. May contact control room to report condition of valve and that they are proceeding to Step 8.

COMMENCE ALTERNATE PATH*

S/U 5.

Step A8: Reads and recognizes the correct procedure step, proceeds to Establish Manual Emergency substep Boration S/U

WC-2017-11 JPM P3 Form ES-C-1 JPM STEP / PROCEDURE STEP CRITICAL STEP CUE STANDARD 6.

Step A8.a: Cue: Clutch lever engaged 1974 level of Aux Bldg, A Safety Injection Pump Room.

() Locally open Emergency Valve handwheel is turning.

Boration Valve. Located valve, engaged the Valve stem indicates manual operator by pulling down o BG HV-8104 (1974 AUX moving upward. on the clutch lever and turning the BLDG, SI PUMP RM A NEAR handwheel several turns DOORWAY) Valve handwheel stops. counterclockwise until the clutch is engaged.

Valve stem indicates full open. Releases clutch lever, turns handwheel in the counterclockwise direction until the handwheel stops and the valve indicates open S/U 7.

Step A8.b: Cue: (as the control room Applicant will:

when contacted) report flow Check Emergency Boration Flow - is 90 gpm 1: Contacts the control room to GREATER THAN 30 GPM verify flow indications.

Cue: The applicant may o BG FI-183A leave the room to look at 2. Acknowledges report from the BG FI-183B local indication control room and proceed to next in the corridor for diverse step.

indication. You may cue 90 gpm, but they should still S/U call the control room.

8.

Step A8.c: Cue: The JPM is complete.

Return to procedure, Step 2.

RECORD STOP TIME BELOW.

Terminating cue: The JPM Is complete when the Applicant has established boration flow using Emergency Boration Valve, BG HV-8104.

STOP TIME:

WC-2017-11 JPM P3 Form ES-C-1 Initial A reactor trip has recently occurred from 100% power and multiple rods did NOT Conditions: insert. The control room is performing OFN BG-009, EMERGENCY BORATION, Attachment A, Emergency Boration, Establishing Alternate Boration Flowpath.

Initiating Cue: The Control Room Supervisor (CRS) informs you that that during step A2, BG FCV-110A, Boric Acid Blending Tee Inlet Isolation Valve, failed to open from the Control Room. The CRS directs you to continue OFN BG-009, Attachment A at step A2 RNO.

Facility: _Wolf Creek_________ Scenario No.: ____1________ Op-Test No.: _________

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 95% Power, B CCP in service, 75 gpm letdown _____________________

Turnover: No equipment out of service. The crew has been directed to raise letdown flow to 120 gpm after taking the watch. Power level reduced in preparation for Heater Drain Pump A maintenance later in the shift. _____________________ _____________ _________________

Critical Tasks: CT-1 Isolate faulted S/G C before CTMT CSF Orange Path met on CTMT normal sump level >= 2003 11. CT-2 Isolate High Head ECCS flow through the BIT before overfill of the RCS results in a rupturing of the pressurizer relief tank (PRT) ____________________

Event Malf. Event Type* Event No. No. Description 1 N (SRO, RO) Raise Letdown to 120 GPM I (SRO, RO) 2 PZR Level Instrument BB LI-459A Fails Low TS (SRO) 3 I (SRO, BOP) Steam Header Pressure Instrument PI-507 fails low I (SRO, BOP) 4 Spurious opening of S/G B ARV TS (SRO)

C (SRO, RO, 5 RCP A Hi Vibration, requires RX trip BOP) 6 M (All) Unisolable Loop C main feed line break in Containment 7 C (SRO, BOP) FWIS fails to actuate automatically (both trains)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 2

5. Entry into a contingency EOP with substantive actions (> 1 per scenario set) 0

6. Preidentified critical tasks (> 2) 2

Measurable Performance Critical Task Safety Significance Cueing Performance Feedback Indicators CT 1: Isolate faulted Failure to isolate feed S/G pressure and With the failure Indication of S/G C before flow into containment level indications will of FWIS to FWIV closure on Containment CSF leads to an make it possible to actuate, the MCB (green Orange Path met on unnecessary and identify S/G C as Applicant will lamp lit).

CTMT normal sump avoidable challenge the faulted S/G. manually close Pressure drop in level >= 2003 ft 11 to the containment Lowering Level S/G the following (6) intact S/Gs stop, in. integrity critical safety C. Containment valves to isolate and S/G levels function as a result of pressure and temp C S/G. stabilize.

flooding. rise resulting in

AB HV-20 SIS. Containment

AE HV-41 radiation levels do

AE FK-530 not rise as

AL HV-11 expected if a LOCA

AL HV-12 was present.

AB V-V087 FWIS will show as not actuated on the ESFAS Status Panel. Valve position indication on MCB and plant computer show C FRV and FWIV open.

CT 2: Isolate high Continued maximum RCS pressure and The Operator Green lights LIT head ECCS flow injection causes RCS pressurizer level will isolate the for the following through the BIT to go solid and rise. PORVs open, BIT per EMG valves:

before overfill of the PORV to open, flow indicated. ES-03, Step 13. *EM HIS-8803A RCS results in a passing excess PRT level, *EM HIS-8803B rupturing of the inventory through pressure, and *EM HIS-8801A pressurizer relief PORVs to the PRT. temperature rise. *EM HIS-8801B tank (PRT) Failure to terminate When PRT ruptures ECCS flow when it is at ~91 psig, PRT CCP To BIT possible to do so pressure drops and Flow indicators results in a rupture of equalizes with drop to 0 GPM.

the PRT, spread of Containment *EM FI-917A radioactive coolant Pressure. *EM FI-917B into Containment, and constitutes an avoidable degradation of a fission product barrier, as well as increased risk of stuck open PORV (SBLOCA).

Note: Causing an unnecessary plant trip or ESF actuation may constitute a Critical Task failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Appendix D Scenario Outline Form ES-D-1 SCENARIO # 1 NARRATIVE Turnover: The Unit is operating at 95% power MOL. B CCP is in service. No equipment is out of service. The crew has been directed to raise letdown flow to 120 gpm after taking the watch.

Event 1: Raise Letdown to 120 GPM. The crew will raise letdown flow from 75 GPM to 120 GPM in accordance with SYS BG-201, SHIFTING CHARGING PUMPS, Step 6.6 per beginning of shift guidance.

Once the PZR Level Master Controller BB LK-459 is in auto and letdown flow has been raised to 120 GPM, and/or at the discretion of the Lead Examiner, the next event will start.

Event 2: PZR Level Instrument BB LI-459 Fails LOW. The upper selected controlling PZR Level channel will fail to 20%. The crew will select an alternate PZR level channel and enter OFN SB-008, INSTRUMENT MALFUNCTIONS, to perform ATTACHMENT J. The SRO will evaluate Tech Spec LCO 3.3.1 Reactor Trip System (RTS) Instrumentation (Table 3.3.1-1 Function 8.a) and determine Conditions A (Immediate) and M - (72 Hours) are applicable. When the crew has returned PZR Level control to Auto and evaluated Technical Specifications, the next event will start.

Event 3: Steam header pressure instrument PI-507 fails LOW. The crew takes manual control of the MFP Master Speed Control and then enters OFN SB-008, INSTRUMENT MALFUNCTIONS, and performs Attachment B. After the crew has placed the Master MFP Speed Controller in manual to restore S/G levels to program, the next event will start.

Event 4: S/G B ARV AB PV-2 opens spuriously. The crew will attempt to place the ARV in manual and close, but this attempt will NOT be successful. The crew will be required to dispatch an operator for local closure of S/G B ARV isolation valve AB-V040 to stop steam flow. The SRO should evaluate and determine Tech Spec LCO 3.7.4 Atmospheric Relief Valves (ARVs) Condition A (7 days) is applicable.

When the crew has isolated B ARV and determined applicable tech specs, the next event will start.

Event 5: RCP A Hi Vibration, Requires Rx Trip, MCB Annunciators 070B-RCP VIB SYS ALERT and 070A-RCP VIB DANGER illuminate. The crew will validate Immediate Trip Criteria per OFN BB-005, RCP MALFUNCTIONS conditions exist and manually trip the reactor and the A RCP.

Events 6 and 7: Unisolable Loop C Main Feed Line Break in Containment and Failure of FWIS to automatically actuate. When the crew has tripped the reactor, stopped RCP A and completed the immediate action steps of EMG E-0, REACTOR TRIP OR SAFETY INJECTION, an unisolable feedwater line break occurs on C S/G inside containment. Both trains of FWIS fail to actuate, so the crew is required to isolated Feed Water Isolation Valves (FWIV) and Feed Water Regulation valves (FRV).

The crew will re-perform the immediate actions of EMG E-0, and then perform Foldout Page Item 3 to isolate C S/G by closing the MSIV, FWIV AE HV-41, and stopping auxiliary feedwater and main feedwater flow to C S/G. The crew will transition to EMG E-2, FAULTED STEAM GENERATOR ISOLATION, and complete isolation of C S/G. CT 1: Isolate faulted S/G C before Containment CSF Orange Path met on CTMT normal sump level >= 2003 ft 11 in.

The crew then transitions to EMG ES-03, SI TERMINATION, and reduces ECCS flow by isolating flow through the BIT. CT 2: Isolate high head ECCS flow through the BIT before overfill of the RCS results in a rupturing of the pressurizer relief tank (PRT).

The scenario is complete when the crew has completed isolation of C S/G and isolated ECCS flow through the BIT, and/or at the discretion of the Lead Examiner.

Note: Causing an unnecessary plant trip or ESF actuation may constitute a Critical Task failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Appendix D Scenario Outline Form ES-D-1

2017 ILO NRC Exam, Scenario 1

Event 1 - No Keys - Raise Letdown to 120 GPM.

Event 2 - [Key 2] PZR Level Instrument BB LI-459A Fails LOW IMF mBB22A f: 20 r:30 k:2

Event 3 - [Key 3] Steam Header Pressure Chanel PI-507 Fails LOW ICM trABPT0507 t: 1 d:0 k:3

Event 4 - [Key 4] Spurious Opening of 'B' ARV IMF mAB07F f: 100 r:30 k:4

REMOTE Action to Locally Close B ARV isolation AB-V040

{KEY[7} IRF rAB02B f:0 r:300

Event 5 - [Key 5]'A' RCP High Vibration IMF mBB31A f: 6 r:30 k:5 IMF mBB32A f:22 r:30 k:5

Event 6 - Unisolable Feedline Break in CTMT (both Auto and Manual initiation options available)

{bkPA00107.state=0} IMF mAE14C f:1e+07

{KEY[6]} IMF mAE14C f:1e+07

Event 7 - FWIS fails to auto actuate on both trains IMF mSA21A f: 1 IMF mSA21B f:1

REMOTE Action to Locally Close AB V-087

{KEY[8]} IRF rAB04B f:0 r:30

Appendix D 1 Form ES-D-2 Op Test No.: 11/2017 Scenario No.: 1 Event No.: 1 Total No Pages 36 Event

Description:

Raise letdown from 75 gpm to 120 gpm Time Position Applicants Actions or Behavior Event 1 starts when the crew takes the watch and performs normal evolution as pre-shift briefed.

CRS Direct the RO to raise letdown from 75 GPM to 120 GPM in accordance with SYS BG-201, SHIFTING CHARGING PUMPS, Step 6.6.

SYS BG-201, SHIFTING CHARGING PUMPS (Rev 71)

RO 6.6.1. ENSURE at least one set of Pressurizer Backup Heaters have been energized, using SYS BB-203, PRESSURIZER BACKUP HEATER OPERATIONS.

SYS BB-203, PRESSURIZER BACKUP HEATER OPERATIONS (Rev 4A)

RO Performs the following steps in SYS BB-203 to energize one set of backup heaters:

6.1.1.1. Depress BB PK-455A, PZR PRESS MASTER CTRL MAN pushbutton (BB PK-455A - MAN PUSHBUTTON LIT).

6.1.1.2. Depress BB PK-455A, PZR PRESS MASTER CTRL OUTPUT lower pushbutton to change the output to 60% (BB PK-455A - OUTPUT AT 60%). [PZR spray valve starts to open and maintains pressure at 2235 psig.]

6.1.1.3. Energize desired Pressurizer Backup Heater Group by placing associated heater group handswitch to close (BB HIS-51A, PZR HTR B/U GROUP A or BB HIS-52A, PZR HTR B/U GROUP B).

6.1.1.4. Depress BB PK-455A, PZR PRESS MASTER CTRL AUTO pushbutton (BB PK-455A - AUTO PUSHBUTTON LIT).

6.1.1.5. Monitors Pressurizer Pressure for correct response (pressure stable) and then returns to Step 6.6.2 in SYS BG-201.

SYS BG-201, SHIFTING CHARGING PUMPS (Rev 71)

RO 6.6.2. (N/A) The BTRS is not inservice CAUTION regarding shifting to the CCP does not apply.

6.6.3. IF the BTRS is NOT inservice, then PLACE BG HIS-129, CVCS DEMIN INLET DIVERT VLV to VCT (switch is initially in DEMIN position).

Appendix D 2 Form ES-D-2 Op Test No.: 11/2017 Scenario No.: 1 Event No.: 1 Total No Pages 36 Event

Description:

Raise letdown from 75 gpm to 120 gpm Time Position Applicants Actions or Behavior RO 6.6.4 and 6.6.5 are N/A.

RO 6.6.6. IF Letdown is 75 gpm AND it is desired to raise it to 120 gpm, THEN perform the following:

RO 6.6.6.1. Places charging flow controller BG FK-121 to MANUAL and raises charging flow by adjusting BG FI-121A to 130-135 GPM.

RO 6.6.6.2 and 6.6.6.3. Places Letdown Heat Exchanger Outlet Pressure Controller BG PK-131 to MANUAL and adjusts BG PK-131 until Letdown Heat Exchanger Outlet Pressure Control Valve PCV-131 is 90-100% open.

RO 6.6.6.4. Opens Letdown Orifice Isolation Valve A HV-8149A by placing BG HIS-8149AA to OPEN.

RO 6.6.6.5 and 6.6.6.6. Adjusts Letdown Heat Exchanger Outlet Pressure Controller BG PK-131 to establish 350 psig on BG PI-131, LTDN HX OUTLET PRESS, and then places BG PK-131 to AUTO.

RO 6.6.6.7. Verifies Letdown Heat Exchanger Outlet Flow is 110-130 GPM (nominal 120 GPM) on flow indicator BG FI-132.

RO 6.6.6.8. Restores PZR level to program level (55.5%) using Charging Flow Controller BG FK-121 (Examiners Note: Charging will have been greater than letdown for a small period of time, and PZR level may have increased above program level. Thus it may be necessary to reduce charging flow below 130 GPM in order to bring PZR level back to 55.5%).

RO 6.6.6.9. Adjusts charging flow to 130-135 GPM by performing the following steps:

Place the PZR Master Controller BB LK-459 in MANUAL and adjusts BB LK-459 to 65-68%

When PZR level is 57% and stable, places Charging Flow Controller BG FK-121 to AUTO

Adjusts PZR Master Controller BB LK-459 to establish 130-135 GPM charging flow and then places BB LK-459 to AUTO RO 6.6.7 - 6.6.9 are N/A.

6.6.10. Places BG HIS-129, CVCS DEMIN INLET DIVERT VLV in DEMIN.

Appendix D 3 Form ES-D-2 Op Test No.: 11/2017 Scenario No.: 1 Event No.: 1 Total No Pages 36 Event

Description:

Raise letdown from 75 gpm to 120 gpm Time Position Applicants Actions or Behavior RO 6.6.11. Performs the following steps in SYS BB-203 to place PZR backup heaters in AUTO:

SYS BB-203, PRESSURIZER BACKUP HEATER OPERATIONS (Rev 4A)

RO 6.1.2.1. Presses BB PK-455A, PZR PRESS MASTER CTRL MAN pushbutton.

6.1.2.2. Presses BB PK-455A, PZR PRESS MASTER CTRL OUTPUT raise pushbutton to change the output to 50%.

6.1.2.3. Places associated heater group handswitch for backup heaters that are in manual to auto using BB HIS-51A, PZR HTR B/U GROUP A or BB HIS-52A, PZR HTR B/U GROUP B.

6.1.2.4. Presses BB PK-455A AUTO pushbutton.

6.1.2.5. Monitors Pressurizer Pressure for correct response (ensure pressure stabilizes at NOP of 2235 psig).

6.1.3. Signs for Section 6.1 of SYS BB-203, complete, and informs CRS that all backup PZR heaters are in AUTO.

SYS BG-201, SHIFTING CHARGING PUMPS (Rev 71)

RO 6.6.12. Signs that Section 6.6 of SYS BG-201 is complete and informs CRS that letdown flow has been raised to 120 GPM.

Event 1 termination: When the crew has restored all PZR backup heaters to AUTO and raised letdown flow to 120 GPM, and/or at the Lead Examiners discretion.`

Simulator Operator: Insert Key 2 at direction of Lead Examiner.

Appendix D 4 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 2 Total No Pages 36 Event

Description:

PZR Level Instrument BB LI-459A Fails Low.

Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 2 at direction of Lead Examiner.

Diagnostics: BB LI-459A indication lowers to 20%, charging flow rises, Actual PZR level rises gradually.

Annunciators: 00-032C, PZR LO LEV DEV NOTE: Crew may refer to ALR or enter OFN SB-008 directly.

RO Diagnoses instrument channel and informs CRS.

ALR 032C, PZR LO LEV DEV (Rev 12)

RO 1. Check Controlling PZR Level Channel - 5% <Program Level -

Yes

2. Check for Instrument Failure:

a. Check Controlling PZR Level Channel - Within 6% of remaining channels - NO RNO Perform the following:

1. IF failed pressurizer level channel is selected on PZR LEV CTRL SEL switch, THEN select alternate level channel o BB LS-459D

2. Go to OFN SB-008, INSTRUMENT MALFUNCTIONS, OFN SB-008, INSTRUMENT MALFUNCTIONS (Rev 45)

Simulator Operator: IF contacted as WWM, acknowledge requests for maintenance support, IF contacted as Call Supt., acknowledge report of plant status.

RO, CRS 1. Check for Malfunction.

Check if Reactor Coolant System or Instrument Channel or Controller is Malfunctioning:

a. Perform appropriate attachment for malfunctioning channel or controller from table below:

VARIABLE CHANNELS ATTACHMENT PZR Level L-459, L-460, L-461 ATTACHMENT J (BB)

ATTACHMENT J, PZR LEVEL CHANNEL MALFUNCTION RO J1. Identifies Failed Instrument Channel is BB LI-459A J2. Ensures Alternate Pressurizer Level Channel On PZR LEV CTRL SEL Switch BB LS-459D selected (461/460).

J3. Checks Failed Pressurizer Level Channel Failed LOW - YES RO J4. Checks Letdown Flow - ESTABLISHED -YES.

Appendix D 5 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 2 Total No Pages 36 Event

Description:

PZR Level Instrument BB LI-459A Fails Low.

Time Position Applicants Actions or Behavior RO J5. Manually Control Charging And Letdown To Stabilize Pressurizer Level At Level Appropriate For Plant Power (57%)

J6. Ensures Pressurizer Control Heaters - ON J7. Places Charging/Letdown Flow Control In Automatic J8. Monitors Pressurizer Level Response To Ensure Proper Control J9. Ensures Failed PZR Level Channel - NOT USED FOR RECORDER CRS J10. Monitors the Following Technical Specification LCO::

LCO 3.3.1, Function 9

LCO 3.3.4, Function 12

LCO 3.3.3, Function 11 Determines the following apply:

LCO 3.3.1, Cond A - IMMEDIATELY enter the Condition referenced in Table 3.3.1-1 for the channel (Condition M)

LCO 3.3.1, Cond. M - Place inoperable channel in trip within 72 hr.

Event termination: After the crew has returned PZR Level control to Auto and identified applicable Tech Spec. entries, and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 3 at direction of Lead Examiner.

Appendix D 6 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 3 Total No Pages 36 Event

Description:

Steam header pressure instrument PI-507 fails low.

Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 3 at direction of Lead Examiner.

Diagnostics: MFP speed will lower, all S/G levels will begin to lower, possible S/G level deviation alarms.

Annunciators 108B-SG A LEV DEV, 109B-SG B LEV DEV, 110B-SG C LEV DEV, 111B -SG D LEV DEV NOTE: It is allowed per AP 21-001, Conduct Of Operations step 6.3.12.8, that the operator takes manual control during equipment malfunctions which result in a transient and then inform the Control Room SRO.

BOP Diagnoses channel failure and inform crew.

BOP Takes manual control of the master MFP speed controller by placing controller FC SK-509A to manual and restores speed to pre-event values (approximately 5025 rpm).

CRS Enters and directs OFN SB-008, INSTRUMENT MALFUNCTIONS, OFN SB-008, INSTRUMENT MALFUNCTIONS (Rev 45)

BOP, CRS Check for Malfunction.

Check if Secondary System Instrument Channel or Controller is Malfunctioning:

a. Perform appropriate attachment for malfunctioning channel or controller from table below:

VARIABLE CHANNELS ATTACHMENT Steam or Feedwater Header P-507 ATTACHMENT B Pressure P-508 (AB,AE)

OFN SB-008, INSTRUMENT MALFUNCTIONS (Rev 45)

NOTES o Failure of PT-507 can result in improper operation of the Steam Dump System (when in the steam pressure mode of operation) and the Feed Pump Speed Control System.

o At full power, head loss in steam lines will cause steam header pressure indication to read approximately 20 psi lower than S/G pressure indications.

o Step B1 is a Memory Action Step.

Appendix D 7 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 3 Total No Pages 36 Event

Description:

Steam header pressure instrument PI-507 fails low.

Time Position Applicants Actions or Behavior BOP B1. Verify proper main feedwater pump speed control.

o MFW pump speed is stable for plant conditions - NO o FC SK-88 o FC SK-188 RNO Perform the following:

a. Place MFP TURBS MASTER SPEED CTRL in manual o FC SK-509A

b. Control pump speed to PROGRAMMED FEEDWATER dP IAW programmed value (Refer to Figure 1) (See Attachment 1) o FC SK-509A

c. N/A (Master Speed Controller controls in Manual)

BOP B2. Verify Steam Header Pressure Channel Malfunction:

o Observes Steam Header Pressure - ABNORMALLY LOWER THAN S/G PRESSURE - YES BOP B3. Checks STEAM DUMP SEL Switch - IN STEAM PRESSURE MODE -

NO:

RNO. Go to step B6.

BOP B6. Place STEAM HDR PRESS CTRL AB PK-507 In - MANUAL.

o AB PK-507 Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

BOP B7. Request I&C to request repair failed channel.

BOP B8. WHEN Failed Channel Is Repaired, THEN Restore MFP TURBS MASTER SPEED CTRL Or STEAM HDR PRESS CTRL To Auto, As Directed By SM/CRS.

o FC SK-509A o AB PK-507 Crew B9. Return To Procedure And Step In Effect Event 4 termination: After the crew has placed the master MFP speed controller in manual and controlled S/G level and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 4 at direction of Lead Examiner.

Appendix D 8 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 4 Total No Pages 36 Event

Description:

Spurious opening of B S/G ARV.

Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 4 at direction of Lead Examiner.

Diagnostics: Reactor Power slowly rising, RCS Temperature slowly lowering, Steam Generator levels rise, Full Open indication on B ARV, Audible steam flow noise in simulator.

Annunciators: None NOTE: IF the failed open ARV is diagnosed by the crew, direction may attempt to close the isolation valve prior to entry into OFN AB-041. Once the crew diagnoses ARV will not close in manual, they should dispatch local operator to close isolation valve AB HV-040.

CRS Enters and directs OFN AB-041, STEAMLINE OR FEEDLINE LEAK NOTE: If crew isolates ARV locally and correctly identifies Tech Specs, they may NOT choose to enter OFN AB-041.

OFN AB-041, STEAMLINE OR FEEDLINE LEAK (Rev 5)

ATC 1. Check Reactor Power - LESS THAN 100% - YES

SE NI-41B, SE NI-42B, SE NI-43B, SE NI-44B BOP 2. Checks containment parameters (temperature, pressure, humidity, radiation process monitors, area radiation monitors, containment sump and instrument sump levels and determines all are normal).

BOP 3. Check Steam Generator Levels - STABLE OR TRENDING TO PROGRAM ATC 4. Check Tref/Tavg Deviation - LESS THAN 3°F

00-065D - NOT LIT BOP 5. Check Condenser Hot Well Level - STABLE OR INCREASING

AD LI-114 Simulator Operator:

o WHEN contacted as the Auxiliary Building Operator, acknowledge order to close AB-V040.

o Insert Key 7, Wait 5 minutes and report that the valve is closed.

BOP 6. Ensure SG ARVs - CLOSED

AB PIC-2A For S/G B - NO. Operator attempts to manually close S/G B ARV, it will be unsuccessful.

6. RNO a. IF any valve cannot be closed, THEN dispatch operator to locally isolate affected S/G ARV (Main Steam Enclosure above grating) o AB-V040 for S/G B CRS 6. RNO b. Refer to Tech Spec 3.7.4

CRS determines LCO 3.7.4 CONDITION A is applicable.

Event termination: After the crew has manually isolated the B ARV and reviewed Tech Specs and/or at the discretion of the Lead Examiner.

Simulator operator: Insert Key 5 at the lead examiners direction.

Appendix D 9 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 5 Total No Pages 36 Event

Description:

RCP A high vibration, requires RX trip.

Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 5 at direction of Lead Examiner.

Annunciators: 070B RCP VIB/SYS ALERT, 070A RCP VIB DANGER NOTE: Crew may enter OFN BB-005 directly instead of addressing ALRs.

RO Acknowledges annunciators 070B RCP VIB/SYS ALERT, 070A RCP VIB DANGER ALR 00-070B RCP VIB/SYS ALERT (Rev 10B) -OR- ALR 00-070A RCP VIB DANGER (Rev 9B)

RO/BOP 1. Checks RCP VIB Monitor OK lights and observes they are ALL LIT.

2. Checks RCP frame and shaft vibration readings and observes they are elevated.

Any VERT or HORIZ FRAME Vibration Readings >= 5 Mils

Any VERT or HORIZ SHAFT Vibration Reading >= 20 Mils

3. Go To OFN BB-005, RCP MALFUNCTION.

OFN BB-005, RCP MALFUNCTION (Rev 27)

RO Monitors foldout page:

Determines frame vibration exceeds 5 mils and shaft vibration exceeds 20 mils 2.RNO: Go to ATTACHMENT B, Step B.1 CRS Performs crew update/brief to inform crew of the following:

The reactor will be tripped and the CRS and BOP will perform EMG E-0 while the RO continues with OFN BB-05

RO will trip RCP A after the tripping the reactor Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

Appendix D 10 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 5 Total No Pages 36 Event

Description:

RCP A high vibration, requires RX trip.

Time Position Applicants Actions or Behavior RO Performs the following actions in Attachment B:

B1. Check if Reactor Should Be Tripped:

B1.a. Check Reactor - CRITICAL - YES B1.b. Check RCPs - Only One Being Shutdown - YES B1.c. Check Reactor Power - Greater than 48% - YES B2. Manually TRIP REACTOR and Stabilize Plant Using EMGs While Continuing With This Procedure B3. Shutdown Affected RCP:

B3.a. Check RCP A being stopped B3.b. Place associated pressurizer spray valve controller BB PK-455B in manual at zero output B3.e. Stop RCP A.

B3.f. Defeat Tavg and delta T for RCS Loop A:

BB TS-412T

BB TS-411F B4. Check if No. 1 Seal Leakoff can remain unisolated:

No. 1 Seal Leakoff was LESS THAN 6 GPM prior to securing RCP

- YES

No. 1 Seal Leakoff was within the limits of FIGURE 1 and RCP No.

1 Seal Inlet temperature was stable and within limits prior to securing RCP - YES

SDS has not activated - YES B5. Check Reactor - CRITICAL - No.

B5.RNO.a. Return to procedure and step in effect (EMG E-0).

CRS Enters and directs EMG E-0, REACTOR TRIP OR SAFETY INJECTION.

EMG E-0, REACTOR TRIP OR SAFETY INJECTION (Rev 39A)

BOP 1. Verify Reactor Trip:

a. Check all rod bottom lights - LIT

b. Check reactor trip breakers and bypass breakers - OPEN o SB ZL-1/-2/-3/-4

c. Check intermediate range neutron flux - DECREASING o SE NI-35B [GAMMA METRICS]

o SE NI-36B [GAMMA METRICS]

BOP 2. Verify Turbine trip:

a. Observes all Main Stop valves are closed BOP 3. Check AC Emergency Busses - AT LEAST ONE ENERGIZED NB01 NB02

Appendix D 11 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 5 Total No Pages 36 Event

Description:

RCP A high vibration, requires RX trip.

Time Position Applicants Actions or Behavior BOP 4. Check if Safety Injection is actuated:

a. Check any indication SI is actuated - LIT (NO) o Annunciator 00-030A, NF039A LOCA SEQ ACTUATED o Annunciator 00-031A, NF039B LOCA SEQ ACTUATED o ESFAS status panel SIS section - ANY WHITE LIGHT o Partial Trip Status Permissive/Block status panel - SI RED LIGHT 4.RNO.a. Perform the following:

1) Check SI required (containment pressure >3.5psig, RCS pressure < 1830 psig, RCS subcooling < 30F, any S/G pressure <

615 psig, PZR level < 6%) - NO, SI is not required.

3) If SI is NOT required, THEN:

a) Monitor Critical Safety Functions using EMG F-0 b) Go to EMG ES-02, Reactor Trip Response, Step 1.

Event termination: After the crew has tripped the reactor and stopped RCP A, Events 6 and 7 Automatically start (Conditional to Breaker BB HIS-37 being taken to Normal-After-Stop). IF the crew does NOT trip the RCP, and with direction from the Lead evaluator, Insert Key 6 to manually initiate Events 6 and 7.

Appendix D 12 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior Simulator Operator: Conditional failure is inserted once the A RCP is tripped. If necessary, Events may be Manual Initiated by inserting Key 6.

Diagnostics: All S/G pressures and levels lower, containment pressure rises, RCS pressure rises, and containment sump level rises.

Annunciators: Multiple, EMG entry will preclude alarm response procedure guidance All Identify all S/G pressures and levels lowering, containment pressure rising, containment sump level rising, and SI actuation due to high containment pressure.

CRS/BOP Identify both trains of FWIS failed to actuate and directs closing of the FWIVs CRS Directs re-performing EMG E-0 at Step 1 due to SI actuation.

EMG E-0, REACTOR TRIP OR SAFETY INJECTION (Rev 39A)

RO 1. Performs immediate action Step 1 and verifies reactor trip:

a. Check all rod bottom lights - LIT

b. Check reactor trip breakers and bypass breakers - OPEN o SB ZL-1/-2/-3/-4

c. Check intermediate range neutron flux - DECREASING o SE NI-35B [GAMMA METRICS]

o SE NI-36B [GAMMA METRICS]

BOP 2. Verify Turbine trip:

a. Observes all Main Stop valves are closed BOP 3. Check AC Emergency Busses - AT LEAST ONE ENERGIZED NB01 NB02 BOP 4. Check if Safety Injection is actuated: (YES)

a. Check any indication SI is actuated - LIT o Annunciator 00-030A, NF039A LOCA SEQ ACTUATED (YES) o Annunciator 00-031A, NF039B LOCA SEQ ACTUATED (YES) o ESFAS status panel SIS section - ANY WHITE LIGHT (YES) o Partial Trip Status Permissive/Block status panel - SI RED LIGHT (YES)

b. Check both trains of SI actuated (YES) o Annunciator 00-030A, NF039A LOCA SEQ ACTUATED (YES) o Annunciator 00-031A, NF039B LOCA SEQ ACTUATED (YES)

Appendix D 13 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior BOP FOLDOUT PAGE Step 3. FAULTED S/G ISOLATION CRITERIA IF any S/G pressure decreasing in an uncontrolled manner OR any S/G is completely depressurized, THEN perform the following:

a. Close main steam isolation valves (AB HIS-11, 14, 17, and 20)

b. Isolate feed flow to faulted S/G C:

Manually close FWIV AE HV-41

Close MDAFW pump discharge to S/G C valve AL HV-11 and TDAFW pump discharge to S/G C valve AL HV-12.

c. Maintain total feed flow greater than 270,000 lbm/hr until NR level in at least one S/G is greater than 6% [29%]

CT 1: Isolate faulted S/G C before Containment CSF Orange Path met on CTMT normal sump level >= 2003 ft 11 in. (4 of the 6 valves)

All Observe pressures and levels stabilizing in all S/Gs except for C S/G Observe pressure and level continuing to lower on C S/G and diagnose that a main feedline break on C S/G occurred in containment.

5. Check if SI is required:

SI was manually actuated AND was required - MAYBE Containment pressure is currently or has been - GREATER THAN RO OR EQUAL TO 3.5 PSIG - YES RCS pressure is currently or has been - LESS THAN OR EQUAL TO 1830 PSIG - NO Any S/G pressure is currently or has been LESS THAN OR EQUAL TO 615 PSIG - YES

6. Verify Automatic Actions Using Attachment F, AUTOMATIC SIGNAL VERIFICATION (Examiner NOTE: See Attachment 2)

F2: Verify Feedwater Isolation.

a. MFP Tripped -YES

b. Close Feedwater Red Valves -

o AE ZL-510 for S/G A o AE ZL-520 for S/G B o AE ZL-530 for S/G C o AE ZL-540 for S/G D

c. Main Feedwater Reg Bypass valves - CLOSED - YES

d. Close Main Feedwater isolation valves -

o AE HS-39 for S/G A RO o AE HS-40 for S/G B o AE HS-41 for S/G C o AE HS-42 for S/G D

e. Close Feedwater Chemical Injection valves - NO o AE HS-43 for S/G A o AE HS-44 for S/G B o AE HS-45 for S/G C o AE HS-46 for S/G D

f. Check ESFAS status panel SGBSIS section - ALL WHITE LIGHTS LIT - YES CT 1: Isolate faulted S/G C before Containment CSF Orange Path met on CTMT normal sump level >= 2003 ft 11 in. (Valve 5 of 6, AE ZL-530)

F16 : Stop NCP, BG HIS-3

Appendix D 14 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior

7. Check Main Generator Breakers And Exciter Breaker - OPEN - YES BOP o MA ZL-3A o MA ZL-4A o MB ZL-2 BOP 8. Check Total AFW Flow - GREATER THAN 270,000 LBM/HR - YES

9. Check RCS Cold Leg Temperatures:

Stable at or trending to 557°F for condenser steam dumps or S/G BOP ARVs Stable at or trending to a range of 553°F to 557°F for S/G ARVs if recovering from an inadvertent SI

10. Establish S/G Pressure Control:

a. Check condenser - AVAILABLE - YES o C-9 LIT o MSIV - OPEN o Circulating water pumps - RUNNING

b. Place Steam Header Pressure Control in Manual o AB PK-507 BOP

c. Manually set Steam Header Pressure Control output to zero o AB PK-507

d. Place Steam Dump Select Switch in STEAM PRESS position o AB US-500Z

e. Place Steam Header Pressure Control in Automatic o AB PK-507

11. Check PZR PORVs

a. Check PZR PORVs - CLOSED - YES o BB HIS-455A o BB HIS-456A RO b. Power to block valves - AVAILABLE - YES o BB HIS-8000A o BB HIS-8000B

c. RCS pressure - LESS THAN 2185 PSIG RO 12. Check Normal PZR Spray Valves - CLOSED - YES o BB ZL-455B o BB ZL-455C

Appendix D 15 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior ATC 13. Check PZR Safety Valves - CLOSED - YES o BB ZL-8010A o BB ZL-8010B o BB ZL-8010C ATC, BOP 14. Check If RCPs Should Be Stopped:

a. Check RCPS - ANY RUNNING - YES

b. Check RCS pressure - LESS THAN 1400 psig - NO RNO. Go to Step 15.

CRS 15. Direct operator to Monitor Critical Safety Functions Using EMG F-0, CRITICAL SAFETY FUNCTION STATUS TREES (CSFST).

BOP 16. Check If S/Gs Are Not Faulted: Identifies C S/G IS faulted

a. Check pressures in all S/Gs -

o NO S/G PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR COMPLETELY DEPRESSURIZED - Goes to RNO based on pressure decreasing or completely depressurized S/G C RNO: Perform the following:

1) Ensure BIT Inlet and Outlet Valves are open o EM HIS-8803A o EM HIS-8803B o EM HIS-8801A o EM HIS-8801B

2) Go to EMG E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.

CRS Enters and directs EMG E-2, FAULTED STEAM GENERATOR ISOLATION.

EMG E-2, FAULTED STEAM GENERATOR ISOLATION (Rev 21)

BOP 1. Check Steamlines On All S/Gs - ISOLATED

a. Ensure Main Steamline Isolation Valve(s) - CLOSED (These valves should have been isolated by the crew per Foldout Page in EMG E-0, or on MSLIS).

o AB HIS-14 For S/G A o AB HIS-17 For S/G B o AB HIS-20 For S/G C o AB HIS-11 For S/G D

b. Ensure Main Steamline Isolation Bypass Valves - CLOSED o AB ZL-15A For S/G A o AB ZL-18A For S/G B o AB ZL-21A For S/G C o AB ZL-12A For S/G D Step 1 continued on next page.

c. Ensure Main Steamline Low Point Drain Valve(s) - CLOSED

Appendix D 16 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior BOP o AB HIS-9 For S/G A o AB HIS-8 For S/G B o AB HIS-7 For S/G C o AB HIS-10 For S/G D CRS 2.Check If Limitations For Fault In Area 5 Are Required: NO RNO: Go to step 3.

BOP 3. Check If Any S/G Is Not Faulted: (Observes S/G A, B, and D are NOT faulted)

a. Check pressure in all S/Gs:

ANY S/G PRESSURE STABLE OR ANY S/G PRESSURE INCREASING - Notes pressures are stable or increasing in S/G A, B, and D.

BOP 4. Identify Faulted S/Gs: Identifies S/G C is faulted:

a. Check pressure in all S/Gs:

ANY S/G PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR ANY S/G COMPLETELY DEPRESSURIZED BOP 5. Isolate Faulted S/G(s) (Note: If S/G C was not isolated in EMG E-0 per Foldout Page Item 3, then it will be isolated at this step).

a. Close affected S/G(s) MD AFP Flow Control Valve(s).

AL HK-11A For S/G C - Manually closed

b. Close affected S/G(s) TD AFWP Flow Control Valve(s).

AL HK-12A For S/G C - Manually closed

c. Locally close steam supply to Turbine Driven AFW Pump AB-V087 CT 1: Isolate faulted S/G C before Containment CSF Orange Path met on CTMT normal sump level >= 2003 ft 11 in. (Valve 6 of 6, AB-V087)

d. Ensure S/G ARV On Faulted S/G(s) - CLOSED - YES AB PIC-3A For S/G C Simulator operator:

o WHEN request to locally close steam supply to Turbine Driven AFW Pump AB-V087, acknowledge request.

o INSERT Key 8 o WAIT 2 minutes, and then call back to report AB-V087 has been closed.

Appendix D 17 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior BOP 6. Verify Feedline Isolated On Faulted S/G(s): YES

a. Main Feedwater Reg Valve - CLOSED AE ZL-530 For S/G C

b. Main Feedwater Reg Bypass Valve - CLOSED AE ZL-570 For S/G C

c. Main Feedwater Isolation Valve - CLOSED AE HIS-41 For S/G C

d. Main Feedwater Chemical Injection Valves - CLOSED AE HIS-45 for S/G C CT 1: Isolate faulted S/G C before Containment CSF Orange Path met on CTMT normal sump level >= 2003 ft 11 in. (2nd check for valves)

BOP 7. Verify Blowdown, Lower And Upper Sampling Isolated On Faulted S/G(s): YES

a. S/G Blowdown Containment Isolation Valves - CLOSED BM HIS-3A For S/G C

b. S/G Upper Sample Isolation Valves - CLOSED BM HIS-21 For S/G C

c. S/G Lower Sample Isolation Valves - CLOSED BM HIS-37 For S/G C RO 8. Check PZR PORVs And Block Valves:

a. Power To Block Valves - AVAILABLE - YES o BB HIS-8000A o BB HIS-8000B

b. PZR PORVs - CLOSED - YES o BB HIS-455A o BB HIS-456A

c. RCS Pressure - LESS THAN 2185 PSIG BOP 9. Check If Uncontrolled Cooldown Has Stopped:

a. Check RCS Hot Leg Temperatures - STABLE OR INCREASING -

YES

b. Perform the following to maintain stable RCS hot leg temperatures:

o Decrease ARV setpoints of intact S/Gs to stabilize intact S/G pressures.

AB PIC-1A For S/G A AB PIC-2A For S/G B AB PIC-4A For S/G D o Adjust AFW flow to intact S/Gs, as necessary.

AL HK-7A For S/G A AL HK-8A For S/G A AL HK-9A For S/G B AL HK-10A For S/G B AL HK-5A For S/G D AL HK-6A For S/G D

Appendix D 18 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior RO, BOP 10. Determine Secondary Radiation Levels:

a. Direct Health Physics to survey steamlines in area 5 of Aux Bldg.

b. Check S/G Sampling - ISOLATED - YES

c. Ensure SI - RESET and resets SI o SB HS-42A o SB HS-43A

d. Check Instrument Air Pressure - GREATER THAN 105 PSIG o KA PI YES

e. Open CCW To Radwaste System Isolation Valves o EG HS-69 o EG HS-70

f. Open all S/G sample isolation valves.

o BM HIS-65 For S/G A o BM HIS-35 For S/G A o BM HIS-66 For S/G B o BM HIS-36 For S/G B o BM HIS-67 For S/G C o BM HIS-37 For S/G C o BM HIS-68 For S/G D o BM HIS-38 For S/G D

g. Direct Chemistry to sample all S/Gs for activity.

Simulator operator:

o WHEN contacted as HP, acknowledge request.

o WHEN contacted as Chemistry, acknowledge request.

Appendix D 19 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior RO, BOP 11. Verify Instrument Air Compressor Is Running:

a. Ensure At Least One ESW TRN TO AIR COMPRESSOR Valve - OPEN EF HIS YES EF HIS YES

b. Check AIR COMPRESSOR BRKR RESET Switch Associated With Open ESW Valve(s) - CLOSED - NO KA HIS-3C KA HIS-2C RNO: Reset and close AIR COMPRESSOR BRKR RESET Switch.

KA HIS-3C KA HIS-2C

c. Check INST AIR PRESS - GREATER THAN 105 PSIG o KA PI YES

d. Check Neither ESW TO AIR COMPRESSOR Valve - Locally Opened -

YES

e. Check Both ESW TRN TO AIR COMPRESSOR Valves - OPEN - YES o EF HIS-43 o EF HIS-44

f. Check Both AIR COMPRESSOR BRKR RESET Switches - CLOSED o KA HIS-3C o KA HIS-2C RNO: Reset and close the open AIR COMPRESSOR BRKR RESET Switch.

KA HIS-3C KA HIS-2C RO, BOP 12. Check If S/G Tubes Are Intact: - YES

a. Condenser Air Discharge Radiation - NORMAL BEFORE ISOLATION o GEG 925

b. S/G Blowdown And Sample Radiation - NORMAL o BML 256 o SJL 026 o Sample Results

c. Turbine Driven Auxiliary Feedwater Pump Exhaust Radiation -

NORMAL o FCT 381

d. S/G Steamline Radiation - NORMAL o ABS 114 For S/G A o ABS 113 For S/G B o ABS 112 For S/G C o ABS 111 For S/G D o Local Surveys

e. S/G Levels - NO LEVEL INCREASING IN AN UNCONTROLLED MANNER - No levels are increasing uncontrolled.

RO, BOP 13. Check If Containment Spray Should Be Stopped:

a. Check Spray Pumps - ANY RUNNING - NO RNO: Go to step 14.

Appendix D 20 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior RO, BOP 14. Check If ECCS Flow Should Be Reduced: YES

a. RCS Subcooling - GREATER THAN 30°F [45°F]

b. Secondary heat sink:

Total Feed Flow To Intact S/Gs - GREATER THAN 270,000 LBM/HR OR Narrow Range Level In At Least One Intact S/G - GREATER THAN 6% [29%]

c. RCS Pressure - STABLE OR INCREASING

d. PZR Level - GREATER THAN 6% [32%]

e. Go to EMG ES-03, SI TERMINATION, Step 1.

CRS Enters and directs EMG ES-03, SI TERMINATION EMG ES-03, SI TERMINATION (Rev 24)

RO 1. Reset SI:

o SB HS-42A o SB HS-43A RO 2. Reset Containment Isolation Phase A and Phase B:

o SB HS-56 For Phase A o SB HS-53 For Phase A o SB HS-55 For Phase B o SB HS-52 For Phase B RO, BOP 3. Verify Instrument Air Compressor Is Running: (Already completed)

RO 4. Verify Instrument Air To Containment:

a. Check PZR PRESS MASTER CTRL Output - LESS THAN 55%

o BB PK-455A RNO: Perform the following:

1) Place PZR PRESS MASTER CTRL in manual.

2) Set PZR PRESS MASTER CTRL to less than 55% output signal.

3) WHEN instrument air has been established to containment AND pressurizer pressure control is established, THEN place PZR PRESS MASTER CTRL in automatic.

b. Open INST AIR SPLY CTMT ISO VLV.

o KA HIS-29 RO 5. Reduce Charging Flow:

a. Check Shutdown Sequencers - NOT ACTUATED o Annunciator 00-018C, NF039A S/D SEQ ACTUATED - CLEAR o Annunciator 00-021C, NF039B S/D SEQ ACTUATED - CLEAR

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

BG HIS-1A OR BG HIS-2A

Appendix D 21 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior

6. Check If NCP Should Be Stopped:

a. CCPs - ANY RUNNING - YES

b. Stop NCP o BG HIS-3

7. Check RCS Pressure - Stable or Rising - YES

8. Verify CCW To Service Loop:

a. Ensure CCW Pumps - AT LEAST ONE RUNNING - YES

b. Ensure One Pair of CCW Service Loop Supply and Return Valves for an Operating CCW Pump - OPEN o EG ZL-15 AND EG ZL-53 OR o EG ZL-16 AND EG ZL-54.

c. Open CCW To Radwaste System Isolation Valves.

o EG HS-69 o EG HS-70

9. Verify CCW To Containment:

a. Ensure CCW To And From RCS Isolation Valves - OPEN - YES o EG HIS-58 o EG HIS-59 o EG HIS-60 o EG HIS-71

10. Verify RCP Thermal Barrier Cooling:

a. Ensure CCW From RCP Thermal Barrier Valves OPEN - YES o BB HIS-13 For RCP A o BB HIS-14 For RCP B o BB HIS-15 For RCP C o BB HIS-16 For RCP D

b. Ensure CCW Return From RCS Isolation Valves - OPEN- YES o EG HIS-61 o EG HIS-62

Appendix D 22 Form ES-D-2 Op-Test No.: 11/2017 Scenario No.: 1 Event No.: 6/7 Total No Pages 36 Event

Description:

Unisolable Loop C Main Feed Line Break in Containment, both trains of FWIS fails to actuate automatically.

Time Position Applicants Actions or Behavior

11. Align CCPs For Normal Charging

a. Check CCPs - AT LEAST ONE RUNNING - YES BG HIS-1A BG HIS-2A

b. Check CCP Discharge To Charging Header Isolation Valve For Running CCP - OPEN BG-8483A For CCP A (1974 AUX BLDG, CCP A ROOM) -

Yes BG-8483C For CCP B (1974 AUX BLDG, CCP B ROOM) - NO

c. Reset CCP Recirc Valves.

o BG HS-8110 o BG HS-8111

d. Open CCP Recirc Valves.

o BG HIS-8110 o BG HIS-8111

12. Align Charging System:

a. Throttle CCP Discharge Flow Control valve to 7% open o BG FK-121

b. Close Charging Header Back Pressure Control Valve.

o BG HC-182

c. Open Charging Pumps To Regenerative Heat Exchanger Containment Isolation valves.

o BG HIS-8105 o BG HIS-8106

d. Align Regenerative Heat Exchanger To Loop Cold Leg valves, to establish only one open.

o BG HIS-8146 For Loop 1 o BG HIS-8147 For Loop 4.

13. Isolate BIT:

a. Close BIT Inlet Valves o EM HIS-8803A o EM HIS-8803B

b. Close BIT Outlet Valves o EM HIS-8801A o EM HIS-8801B CT 2: Reduce high head ECCS flow through the BIT before overfill of the RCS results in a rupturing of the pressurizer relief tank (PRT).

Event termination: After the crew has isolated S/G C and isolated ECCS flow through the BIT and/or at the direction of the Lead Examiner.

Simulator Operator: Freeze the simulator at direction of Lead Examiner.

Appendix D 23 Form ES-D-2 Attachment 1 (Page 1 of 1)

Appendix D 24 Form ES-D-2 Attachment 2 (Page 1 of 13)

Appendix D 25 Form ES-D-2 Attachment 2 (Page 2 of 13)

Appendix D 26 Form ES-D-2 Attachment 2 (Page 3 of 13)

Appendix D 27 Form ES-D-2 Attachment 2 (Page 4 of 13)

Appendix D 28 Form ES-D-2 Attachment 2 (Page 5 of 13)

Appendix D 29 Form ES-D-2 Attachment 2 (Page 6 of 13)

Appendix D 30 Form ES-D-2 Attachment 2 (Page 7 of 13)

Appendix D 31 Form ES-D-2 Attachment 2 (Page 8 of 13)

Appendix D 32 Form ES-D-2 Attachment 2 (Page 9 of 13)

Appendix D 33 Form ES-D-2 Attachment 2 (Page 10 of 13)

Appendix D 34 Form ES-D-2 Attachment 2 (Page 11 of 13)

Appendix D 35 Form ES-D-2 Attachment 2 (Page 12 of 13)

Appendix D 36 Form ES-D-2 Attachment 2 (Page 13 of 13)

Appendix D Scenario Outline Form ES-D-1 Facility: _Wolf Creek_________ Scenario No.: ____2________ Op-Test No.: ____1_____

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 100% Power, EDG B and B ESW out of service. B CCP in service, 120 gpm letdown. A and B CCW Pump in service with Service Loop aligned to A train. _____________

Turnover: Crew will place C CCW Pump in service per SYS EG-120, COMPONENT COOLING WATER SYSTEM, Section 6.3, Shifting Train A CCW Pumps____________________________

Critical Tasks: CT-1, Establish AFW Flow during SBO before 3 S/G WR level < =12%. CT-2, Energize at least one AC Emergency Bus prior to performing depressurization and cooldown Step 32 of EMG C-0.__________________________________________________________________________

Event Malf. No. Event Type* Event No. Description 1 N (SRO, BOP) Swap CCW Pumps C (SRO/RO) 2 B CCP trips (TS)

TS (SRO)

I (SRO/ BOP) 3 C S/G Level Channel, AE LI-553 Fails HIGH (TS)

TS (SRO) 4 C (ALL) Condensate Pump B Trip, Downpower to 90%

5 C (ALL) MFP A Trip, Rx Trip Required 6 M (ALL) LOOP and A EDG trips, (Loss of All AC) 7 C (SRO, BOP) TDAFW pump fails to Auto Start 8 SWYD East Bus Restored, Energize NB01

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (> 1 per 1 scenario set)

6. Pre-identified critical tasks (> 2) 2

Appendix D Scenario Outline Form ES-D-1 Measurable Performance Critical Task Safety Significance Cueing Performance Feedback Indicators CT-1 Establish at The failure of the

Indication Manipulation of Indication that at least 270,000 lbm/hr controls in the least the minimum TDAFW pump to and/or AFW flow rate to the control room as required AFW flow start requires the annunciation of required to is being delivered S/Gs before 3 S/G operator to take station establish the to the S/Gs wide range levels manual action to blackout minimum reach 12% [28%]. ensure the required S/G Levels rising AND necessary decay AFW flow rate heat removal

Indication to the S/Gs system is and/or maintained for the annunciation required station that insufficient blackout coping AFW flow to duration. S/Gs is present CT-2 Energize at Reenergizing an

Indication Manipulation of Normal voltage emergency bus controls in the indicated on the least one AC and/or allows transition to a control room as Emergency Bus Emergency bus annunciation of required to prior to conducting recovery procedure station establish power the depressurization for normal recovery. blackout to one AC and cooldown Step Conducting the Emergency cooldown would AND 32 of EMG C-0. Bus.

cause a Safety

Indication that Injection signal and an Offsite complicate the Power source recovery. is available Note: Causing an unnecessary plant trip or ESF actuation may constitute a Critical Task failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Appendix D Scenario Outline Form ES-D-1 SCENARIO 2 NARRATIVE Turnover: 100% Power, EDG B and B ESW are out of service. B CCP is in service with 120 gpm letdown. Both trains of CCW are in service with the service loop aligned to A train. The crew will swap running CCW Pumps in A train per SYS EG-120, COMPONENT COOLING WATER SYSTEM, Section 6.3, Shifting Train A CCW Pumps after taking the watch.

Event 1: BOP Swaps CCW Loop per SYS EG-120, Section 6.3. A copy of SYS EG-120 will be presented to the BOP at shift turnover. The BOP will perform the selected procedure section to start C CCW Pump and secure A CCW Pump. Upon completion of step 6.3.11, Event 2 will start.

Event 2: B CCP Trips. MCB Annunciators 42A, CHG LINE FLOW HILO and 42E, CHARGING PMP TROUBLE will actuate. The crew is expected to respond by performing ALR 00-042E. There is a memory Action step for the RO to isolate letdown if NO Charging pump is running. The CRS will determine that LCO 3.5.2, ECCS-OPERATING, Condition A - 72 Hours and TRM 3.1.9, BORATION INJECTION SYSTEM - OPERATING, CONDITION A - 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months are applicable. Once charging and letdown are re-established and returned to automatic control, and the CRS has determined technical specifications, Event 3 will start.

Event 3: C S/G Level Channel, AE LI-553 Fails HIGH. MCB Annunciators 110B, SG C LEV DEV will actuate. The BOP has a memory action to take manual control of C S/G Feed Reg Valve (AE FK-530) and match steam and feed flows to restore S/G Level to program 50%. The crew will determine which instrument failed and remove it from control before restoring to automatic. The CRS will determine LCO 3.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION, Conditions A-Immediately, and E-72 hours are applicable per Table 3.3.1-1, Function 14. LCO 3.3.2, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION, CONDITIONS A-Immediately, D-72 hours and I-72 hours are applicable per Table 3.3.2-1, Functions 5.c and 6.d. Once the CRS has determined applicable technical specifications Event 4 will start.

Event 4: Condensate Pump B Trip, Downpower to 90%. MCB Annunciators 120B, MFP A SUCT PRESS LO, 123B, MFP B SUCT PRESS LO, and 126D, CONDS PUMP TRIP will actuate. ALR 00-126D, directs the crew to reduce Turbine load using OFN MA-038, RAPID PLANT SHUTDOWN to restore MFP suction pressure to >340 psig. The crew is expected to commence down power using reactivity numbers that were pre-briefed before the scenario. Once the reactor turbine load reduction has stopped at 90%, or at the direction of the lead examiner, Event 5 will start.

Event 5: Main Feed Pump A Trip, Rx Trip Required. MCB Annunciator 120A, MFP A TRIP will actuate and S/G levels will lower rapidly, causing S/G Level alarms to also actuate. Step 2 of ALR 00-120A directs tripping the reactor and going to EMG E-0, REACTOR TRIP OR SAFETY INJECTION if power level is >62%. Depending on crew response, they may manually trip the reactor or the reactor will automatically trip on S/G LoLo level. The next two events automatically start with the Reactor Trip.

Event 6: Loss of Offsite Power and A EDG Trips, (Loss of All AC). The crew will perform immediate actions of EMG E-0, where at Step 3 the RO will realize neither NB01 nor NB02 are able to be powered and the crew is expected to transition to EMG C-0, LOSS OF ALL AC POWER. The crew will perform actions of EMG C-0 until, with the concurrence of the lead examiner, power from the Lacygne/Waverly line will be made available to reenergize the switchyard East Bus and start Event 8.

Event 7: TDAFW pump fails to auto start. With the Loss of all AC and failure of the TDAFW Pump to auto start, the crew must manually start the TDAFW Pump to provide heat sink. EMG C-0, Step 5 provides direction to start TDAFW Pump.

CT-1 Establish at least 270,000 lbm/hr AFW flow rate to the S/Gs before 3 S/G wide range levels reach 12% [28%].

Appendix D Scenario Outline Form ES-D-1 Event 8, SWYD East Bus Restored, Energize NB01, The crew will restore power to bus NB01 using OFN NB-030, LOSS OF AC EMERGENCY BUS NB01 (NB02). Upon re-energization of bus NB01 and with concurrence of the lead examiner, the exam scenario is complete [Freeze Simulator].

CT-2 Energize at least one AC Emergency bus prior to conducting the depressurization and cooldown Step 32 of EMG C-0.

Note: Causing an unnecessary plant trip or ESF actuation may constitute a Critical Task failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Appendix D Scenario Outline Form ES-D-1

ILO 2017 Scenario #2

Tag out 'B' EDG scn SimGroup\TAGDGB

Tag out 'B' ESW ICR bkrDPEF01B t: 2 d:0

Event 1, No Keys

Event 2, [Key 2] 'B' CCP trips ICM bkrNB00201 t: 1 d:0 k:2

Event 3, [Key 3] S/G 'C' level channel AE LT-553 fails high IMF mAE15C4 f: 101 r:10 k:3

Event 4, [Key 4] Condensate Pump 'B' trips ICM bkrDPAD01B t: 1 d:0 k:4

Event 5, [Key 5] 'A' MFP Trips IMF mFC01A f: 1 k:5

Event 6, Loss of Offsite power on Rx trip, 'A' EDG Trips

{jpplp4} IMF mSY01 i:-1 f:-1 d:10 IMF mNE04A i:-1 f:-1

Event 7, TDAFWP fails to auto start IMF mAL01 i: -1 f:-1

[Key 6] Restore Waverly/LaCygne Line, Swyd energizes

{Key[6]} DMF mSY01 IMF mSY03E i:-1 f:-1 k:6 IRF rSY05 f:1 k:6 IRF rSY06 f:1 k:6

[Key 7] Isolate RCP seals

LOCALLY CLOSE SEAL WTR RETURN ISO VLV BGHV8100 ICR movBGHV8100 t: 2 f:0 d:120 r:30 k:7

LOCALLY CLOSE SEAL WTR INJ FILTER INLET ISO'S BGV101/105 IRF rBG09A f: 0 d:30 r:30 k:7 IRF rBG09B f:0 d:60 r:30 k:7

LOCALLY CLOSE EG HV61 ICM movEGHV0061 t: 2 d:0 k:7

Appendix D 1 Form ES-D-2 bOp Test No: 11/2017 Scenario No: 2 Event No: 1 Total No Pages 23 Event

Description:

Place C CCW pump in service per SYS EG-120, COMPONENT COOLING WATER SYSTEM, Section 6.3, Shifting Train A CCW Pumps. The Aux Building Watch is on station to support local operations.

Time Position Applicants Actions or Behavior SYS EG-120 COMPONENT COOLING WATER SYSTEM (Rev 40)

BOP Obtains copy of SYS EG-120. (Provided at pre-shift brief)

SRO Direct the BOP to swap A train CCW pumps in accordance with SYS EG-120, Section 6.3.

BOP Step 6.3.1: Verifies CCW Train A is in operation.

Step 6.3.2: Directs Aux Building Watch to turn off CCW Pump motor space BOP heater for C CCW Pump Simulator Operator: WHEN contacted Aux Building Watch, acknowledge requests. Call back and Report breaker PG19NJF119 is in OFF Position.

BOP Notes the note prior to Step 6.3.3.

NOTE The trend is monitored prior to and during pump starts, to ensure any indication of voiding, such as unexpected fluctuating parameters is observed and compensatory measures can be accomplished prior to damage occurring.

Step 6.3.3: START and MONITOR CCW Pump C NPIS Computer Trend:

o EGI0010 CCW PUMP C AMP BOP o EGF0097 CCW PMP C DISCH FLOW o EGP0077 A CCW DISCH PRESS o EGE0021 CCW PUP A STATUS BOP Step 6.3.4: Records CCW Surge Tank A Lev from EG LI-1.

Notes the (3) Notes prior to step 6.3.5 including the reactivity step symbol.

May inform the team of anticipated alarms and possible reactivity change.

BOP May also make announcement for personnel to stand clear of C CCW Pumps while starting.

NOTES o When starting a CCW Pump, expect the following momentary alarms: Annunciator 00-051C, CCW PMP A FLOW LO, for pump A and Annunciator 00-052C, CCW PMP C FLOW LO, for pump C.

o Any alarm which is more than momentary, or NOT directly coincident with the pump start, shall be investigated using the appropriate alarm response.

o Starting a second pump in a CCW train which is supplying the non-safety loads may cause a high flow condition in that loop Annunciators 00-052F, CCW TO AUX COMP FLOW HI, 00-054F, CCW SEAL HX FLOW HILO, 00-074A, RCP MTR CCW FLOW HILO, 00-070C, RCP A THRM BAR CCW FLOW, 00-071C, RCP B THRM BAR CCW FLOW,00-072C, RCP C THRM BAR CCW FLOW, 00-073C, RCP D THRM BAR CCW FLOW and 00-074C, RCP THRM BAR CCW FLOW may alarm when the second pump is started.

BOP Step 6.3.5, Starts CCW PUMP C using EG HIS-23 Normal after run.

BOP Step 6.3.6: Records CCW Surge Tank A Lev from EG LI-1.

Notes the note and reactivity symbol prior to step 6.3.7. Should investigate any alarms that are present. May inform the team of anticipated possible BOP reactivity change. May also make announcement of stopping A CCW Pump.

Appendix D 2 Form ES-D-2 NOTE Any flow alarms caused by hi flow in non-safety components, which do NOT clear following shutdown of the standby pump, shall be investigated using the applicable alarm response.

BOP Step 6.3.7 Stops A CCW Pump EG HIS-21 Normal after stop.

BOP Step 6.3.8 is N/A Steps 6.3.9 and 6.3.10: Directs Aux Building Watch to verify proper room BOP cooler damper alignment and to energize motor space heaters for A CCW Pump.

Simulator Operator: WHEN contacted as Aux Building Watch, acknowledge requests. Call back and Report GL-D157 is OPEN, GL-D156 is CLOSED, and breaker PG19NJF118 is ON.

BOP Step 6.3.11: Initials and Dates that Section 6.3 is complete.

Event termination: After the crew has completed SYS EG-120, Section 6.3 and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 2 at direction of Lead Examiner.

Appendix D 3 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 2 Total No Pages 23 Event

Description:

Trip of B CCP Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 2 at direction of Lead Examiner.

Diagnostics: BG HIS-2A indicates trip (amber light). Charging flow trends to zero. Pressurizer level trends down. Pressurizer pressure trends down.

Annunciators: 041A-SEAL INJ TO RCP FLOW LO, 042A-CHG LINE FLOW HILO, 042E-CHARGING PMP TROUBLE.

Diagnoses B CCP has tripped and refers to ALR 00-042A or 00-042E.

NOTE: ALR 00-042A memory action step 1 directs the crew to perform ALR 00-042E after isolating letdown.

RO NOTE: The crew may energize a set of PZR backup heaters to address the pressure transient caused by B CCP Tripping.

NOTE: If pressure drops below 2220 psig, they may announce Entering and Departing DNB Tech Spec LCO 3.4.1, Condition A, 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action to restore pressure to >2220 psig.

CRS Enters and directs ALR 00-042E.

ALR 00-042E, CHARGING PMP TROUBLE (Rev 14)

NOTE Steps 1 through 3 are Memory Action Steps.

RO 1. Check Previously Running Charging Pump - TRIPPED o BG HIS-1A For CCP A o BG HIS-2A For CCP B o BG HIS-3 For NCP RO 2. Check Charging Pumps - NONE RUNNING RO 3. Close Letdown Orifice Isolation Valves.

o BG HIS-8149AA o BG HIS-8149BA o BG HIS-8149CA CRS 4. Contact Electrical Maintenance To Determine Cause Of Pump Trip Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

CAUTION If gas binding of pumps is suspected, performance of OFN BG-045, GAS BINDING OF CCPS OR SI PUMPS, should be considered.

NOTE Total pump flow should be maintained above 175 gpm to minimize the effects of low flow cavitation.

RO 5. Establish Charging Flow:

a. Check RCS Temperature - GREATER THAN 350°F

b. Start CCP aligned for normal charging.

BG HIS-1A For CCP A, No RNO Go to Step 5.d

BG HIS-2A For CCP B,

d. Start NCP, BG HIS-3

Appendix D 4 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 2 Total No Pages 23 Event

Description:

Trip of B CCP Time Position Applicants Actions or Behavior Simulator Operator:

o IF contacted as Aux Building Watch to check A CCP, acknowledge request. Call back and Report the pump casing is hot.

o IF contacted as Turbine Building, REPORT an overcurrent flag is dropped ion the breaker.

6. Ensure RCP Seal Injection - BETWEEN 8 GPM AND 13 GPM TO EACH RCP RO o BG FR-157 For RCP A, BG FR-156 For RCP B, BG FR-155 For RCP C, BG FR-154 For RCP D

7. Reestablish Letdown:

a. Adjust Charging flow to maintain flow greater than Letdown flow, while maintaining RCP Seal Injection flow between 8 gpm and 13 gpm.

BG FK-121

BG FK-462

BG HC-182

b. Check RCS Letdown To Regen HX valves open.

o BG HIS-459 o BG HIS-460

c. Place Letdown HX Outlet Pressure Control in manual.

RO o BG PK-131

d. Open Letdown HX Outlet Pressure Control between 90% and 100%.

o BG PK-131

e. Open desired Letdown Orifice Isolation Valve(s).

BG HIS-8149AA

BG HIS-8149BA

BG HIS-8149CA

f. Adjust Letdown HX Outlet Pressure Control to establish Letdown HX Outlet Pressure between 340 psig and 360 psig.

o BG PI-131

g. Place Letdown HX Outlet Pressure Control in auto.

8. Check Charging Header Flow And Letdown Flow - BALANCED RO RNO: Adjust charging and letdown, as necessary, to maintain PZR level at program value.

9. Verify CCP Adequate Flow:

RO

a. Check CCPs - ANY RUNNING - NO, RNO Go to step 10.

10. Perform OFN AF-025, UNIT LIMITATIONS For Possible Open Phase CRS Condition, While Continuing With This Procedure Will determine this is Not Applicable

11. Ensure Compliance With Technical Specifications And TRM:

a. Check Plant - IN MODES 1, 2 OR 3

b. Refer to TR 3.1.9 and Technical Specification 3.5.2.

CRS Enters LCO 3.5.2, ECCS - OPERATING, Condition A - 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Enters TRM 3.1.9 BORATION INJECTION SYSTEM - OPERATING, Condition A - 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Event termination: After the crew has started the NCP, balanced letdown and charging flows and after the CRS has determined applicable Tech Specs and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 3 at direction of Lead Examiner.

Appendix D 5 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 3 Total No Pages 23 Event

Description:

C S/G Level Channel, AE LI-553 Fails HIGH Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 3 at the direction of the Lead Examiner.

Diagnostics: Indicated level on AE FR-530 and AE LI-553 trending up. Actual level on AE LI-539, AE LI-538 and AE LI-537 trending down. S/G C MFW Reg valve, AE LK-530 output trending towards 0%

open. Actual Feed flow trending down.

Annunciators 110A-SG C LEV HI/LO and 110B-SG C LEV DEV.

BOP Recognizes and reports failure and takes manual control of Main Feedwater Reg Valve (FWRV).

Crew Enters and performs ALR 00-110A NOTE: The Crew may enter ALR 00-110B instead. The mitigation action to place FWRV, AE FK-530 in Manual and restore level to program is the same as in ALR 00-110A.

The Crew may also enter OFN SB-008 directly instead of performing either ALR procedure.

ALR 00-110A, S/G C LEV HI/LO (Rev 8)

NOTE Steps 1 through 3 are Memory Action steps.

BOP 1. Check Steam Generator C Controlling Level Channel:

Less Than 30%

OR

Greater Than 70%

BOP 2. Check Instruments - OPERATING PROPERLY

a. Steam Generator C Controlling Level Channel - WITHIN 7% OF REMAINING S/G C LEVEL CHANNELS

AE LI-539

AE LI-553 Not within 7%

RNO: Perform the following:

1. Place Feedwater Reg Control Valve in manual.

AE FK-530

2. Adjust Feedwater Reg Control Valve, as necessary, to establish Steam Generator level at program value.

AE FK-530

3. Go to OFN SB-008, INSTRUMENT MALFUNCTIONS, step 1.

CRS Enters and directs OFN SB-008, INSTRUMENT MALFUNCTIONS.

Appendix D 6 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 3 Total No Pages 23 Event

Description:

C S/G Level Channel, AE LI-553 Fails HIGH Time Position Applicants Actions or Behavior OFN SB-008, INSTRUMENT MALFUNCTIONS (Rev 45)

CRS 1. Check For Malfunction:

Check If Secondary System Instrument Channel Is Malfunctioning: - YES

a. Perform appropriate attachment for malfunctioning channel or controller from table below:

VARIABLE CHANNELS ATTACHMENT CONTROL CHANNELS S/G Level L-519, L-529, L-539, ATTACHMENT F (AE)

L-549, L-551, L-552, L-553, L-554 CRS Enters and directs ATTACHMENT F, S/G LEVEL CHANNEL MALFUNCTION ATTACHMENT F, S/G LEVEL CHANNEL MALFUNCTION (Rev 45)

NOTE Steps F1 through F3 are Memory Action steps.

ATC, BOP F1. Identify Failed Narrow Range S/G Level Instrument Channel:

a. Compare narrow range S/G level indications to confirm a narrow range S/G level channel failure:

S/G INDICATION FUNCTION AE LI-537 Indication AE LI-538 Indication C

AE LI-539 Control AE LI-553 Control BOP F2. Check Failed S/G Level Channel Selected On SG LEV CHANNEL SEL Switch:

AE LS-539C BOP F3. Check Main Feed Reg Valves In Control:

a. Place Affected SG MFW REG CTRL - IN MANUAL

AE FK-530

b. Adjust affected SG MFW REG CTRL, as necessary, to establish Steam Generator level at program.

AE FK-530 CRS Provides bounding order, including control band and target S/G level.

BOP F4. Select Alternate S/G Level Channel On SG LEV CHANNEL SEL Switch:

AE LS-539C BOP F5. Check Main Feed Reg Valves In Control:

a. Restore affected S/G SG MFW REG CTRL To - AUTO

AE FK-530

Appendix D 7 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 3 Total No Pages 23 Event

Description:

C S/G Level Channel, AE LI-553 Fails HIGH Time Position Applicants Actions or Behavior CRS F6. Monitor The Following Technical Specifications For LCOs And Comply With Action Statements, As Appropriate:

o 3.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION, Table 3.3.1-1, Function 14 - Yes o 3.3.2, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION, Table 3.3.2-1, Functions 5.c And 6.d - Yes o 3.3.4, REMOTE SHUTDOWN INSTRUMENTATION, Table 3.3.4-1, Function 8 - Minimum met o 3.3.3, ACCIDENT MONITORING INSTRUMENTATION, Table 3.3.3-1, Function 13 - Minimum met Enters LCO 3.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION, Table 3.3.1-1, Function 14, Condition A - Immediately, Condition E -

72 hrs.

Enters LCO 3.3.2, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION, Table 3.3.2-1, Functions 5.c And 6.d, Condition A - Immediately, Condition D - 72 hrs, and Condition I - 72 hrs.

Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

CRS F7. Place Appropriate S/G Level Bistables For Failed Channel In TRIPPED Mode:

NOTE: Bistables will not be tripped CRS/BOP F8. Check Any AMSAC S/G Level Channels Failed:

AE LT-517

AE LT-528

AE LT-537

AE LT-548 NO, RNO: Go to step F10.

CRS F10. Request I&C To Repair Failed Channel CRS F11. Review Attachment S For Post-Accident And Remote Shutdown Instrumentation Requirements CRS F12. Return To Procedure And Step In Effect Event termination: After MFW Reg valve is placed in AUTO and Technical Specifications have been identified and/or at the direction of the Lead Examiner.

Simulator Operator: Insert Key 4 at the direction of the Lead Examiner.

Appendix D 8 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 4 Total No Pages: 23 Event

Description:

Condensate Pump B Trip, Downpower to 90%

Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 4 at the lead evaluators direction.

Diagnostics: AD HIS-2 indicates trip (amber light), MFP Suction pressure lowering Annunciators: 126D-CNDS PUMP TRIP, 120B-MFP A SUCT PRESS LO, and 123B-MFP B SUCT PRESS LO Recognize the loss of operating condensate pump and reference either ALR Crew 00-126D, or OFN AF-025 to recognize a downpower per OFN MA-038, is required.

ALR 00-126D, COND PUMP TRIP (Rev 10)

1. Verify Condensate Pump A, B, or C - TRIPPED o Condensate Pump Trip Amber Light - LIT BOP AD HIS-1 AD HIS-2 AD HIS-3 NOTES o Head loss through the LP heaters causes a pressure drop from the Condensate Pumps to the Main Feed Pumps that varies with flow rate (power level).

o Condensate pressure may be used if MFP suction pressure is unavailable.

2. Check MFP Suction Pressures Using Graphic 6101 - GREATER THAN 340 psig. (Condensate Pressure GREATER THAN 456 psig)

BOP NO, RNO Reduce Turbine load, as necessary, using OFN MA-038, RAPID PLANT SHUTDOWN to restore MFP suction pressure to 340 psig, AD PI-25, CNDS PUMPS DISCH PRESS 456 psig. Approximately 90% power.

CRS 3. Go To OFN AF-025, UNIT LIMITATIONS OFN AF-025, UNIT LIMITATIONS (Rev 52)

NOTE Steps 1 through 12 may be done in any order.

Steps 1 through 11 N/A for this malfunction

12. Check For Conditions Requiring Unit Load Reduction:

CRS a. Determine maximum unit load, using ATTACHMENT A, UNIT LOAD LIMITS.

One condensate pump out of service, 1102 MWE - 90% (1) (2)

(1) If one condensate pump is lost, reduce power as necessary to maintain MFP suction pressure > 340 psig as indicated on Graphic 6101.

(2) Maintain Motor Current for the operating Condensate Pumps to less 440 amps as indicated on NPIS Computer points, ADI0010, ADI0011 or ADI0012 as applicable. Per E-012.3-0005, the rating of the Condensate Motors is 442 amps.

CRS should announce to the crew to perform a 10% power reduction per the CREW beginning of shift brief using guidance OFN MA-038.

Appendix D 9 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 4 Total No Pages: 23 Event

Description:

Condensate Pump B Trip, Downpower to 90%

Time Position Applicants Actions or Behavior Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

OFN MA-038, RAPID PLANT SHUTDOWN (Rev 28A)

CAUTION Fast unloading rates may result in elevated turbine vibration.

NOTES o Foldout page shall be monitored throughout this procedure.

o Load reduction at greater than 65 MW (5%)/minute will arm condenser steam dumps.

o Steps 1, 2 and 3 are memory action steps.

1. Determine Turbine Unloading Method To Be Used:

a. Check Desired Unloading Rate - LESS THAN OR EQUAL TO 65 BOP MW/MINUTE (5%)

b. Check Automatic Turbine Unloading - DESIRED NOTES o If the High Limiter Active on Graphic 5551 is in alarm, load can only be decreased with the Load Control selected to Open Loop. When High Limiter Active is cleared as indicated by the alarm changing to Limiter Activated, the Load Control Mode may be changed.

o The following is the preferred Mode of Load Control, unless otherwise directed by another procedure:

Open Loop - When Turbine Load is not being changed or the first 10% load reduction from 100%.

MW - If making Turbine Load changes where there is no ongoing secondary side transient.

FSP - If a secondary side transient requires changing Turbine Load or there is a need to keep primary side more stable.

2. () Reduce Turbine Load In Automatic:

a. From Graphic 5551, TURBINE CONTROL SYSTEM -

OPERATION PANEL, LOAD CONTROL section - Select method of Load Control, as directed by CRS/SM.

First Stage Pressure

Megawatts

Open Loop (Only for first 10% load reduction from 100%)

b. Perform the following steps to reduce turbine load:

1) From Graphic 5551, SETPOINTS section, select CHANGE.

RO/BOP 2) At popup 7055, enter the desired MW (greater than or equal to 90% if in Open Loop) and select ENTER.

3) At popup 7055, in the RATE - DEC field enter the desired rate of decrease and select ENTER.

4) From Graphic 5551, SETPOINTS section, select GO to commence load reduction.

-Step 2 Continued on next page-

Appendix D 10 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 4 Total No Pages: 23 Event

Description:

Condensate Pump B Trip, Downpower to 90%

Time Position Applicants Actions or Behavior

c. () Borate RCS And Adjust Control Rods, As Necessary, To Maintain The Following:

o Target Tavg/Tref Temperature Error Between 0°F And +5°F o Control Rods Above The Rod Insertion Limits NOTE: See Attachment 1, SYS BG-200, REACTOR MAKEUP CONTROL SYSTEM NORMAL OPERATION, ATTACHMENT B, Boration For Temperature Adjustment in MODE 1 and 2. This is the laminated hard card that the RO will utilize

d. () Energize PZR Backup Heaters.

o BB HIS-51A o BB HIS-52A

e. Maintain desired turbine unloading rate.

f. Go to step 4.

4. Check PZR PORVs:

a. RCS Pressure - LESS THAN 2335 PSIG

b. PZR PORVs - CLOSED o BB HIS-455A RO o BB HIS-456A

c. RCS Pressure - GREATER THAN 2185 PSIG

d. PORV Block Valves - OPEN o BB HIS-8000A o BB HIS-8000B RO 5. Check PZR Pressure - Stable at or trending to 2235 psig.

RO 6. Check PZR Level - Stable at or trending to program level.

BOP 7. Check S/G Levels Controlling between 45% and 55%.

Simulator Operator: IF contacted as Radiation Protection, acknowledge requests.

CRS 8. Notify Health Physics to perform the following:

9. Check if Sampling is Required:

CRS a. Thermal Power is Changed >15% change in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

NO. RNO Go to step 10.

CRS 10. Check Reactor Power - <65%. NO, RNO, Go to Step 42.

42. At final power level? NO, RNO do not continue in procedure until CRS plant is at final desired power level.

Event termination: After the crew has commenced down power and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 5 at direction of Lead Examiner.

Appendix D 11 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Events No: 5 Total No Pages 23 Event

Description:

Main Feed Pump A Trip, Reactor Trip Required.

Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 5 at the lead evaluators direction.

Diagnostics: A MFP Turbine Speed lowering while B MFP Turbine speed rises, Rapidly lowering S/G Water Levels in all four S/Gs. Lowering Feed Flow to All four S/Gs. Individual MFW Reg Valves trending to full open. Reactor Trips on S/G LOLO when 2/4 S/G Water Levels channels <23% on 1/4 S/Gs.

Annunciators: 120A-MFP A TRIP, 108C through 110C-SG A/B/C/D FLOW MISMATCH, 108B through 111B-SG A/B/C/D LEV DEV Diagnosis the loss of MFP and determines a manual reactor trip is required.

Crew Crew may reference ALR 00-120A before tripping the reactor.

CRS Will Direct Tripping the Reactor.

RO will Trip the Reactor using SB HS-1.

NOTE: When the reactor Trips, Events 6 and 7 are automatically Initiated.

ALR 00-120A, MFP A TRIP (Rev 12)

BOP 1. Verify MFP A Tripped:

2. Check Rector Power <62%

CRS NO, RNO Manually trip the Reactor and Go to EMG E-0, REACTOR TRIP OR SAFETY INJECTION.

Upon reactor trip, recognition of loss of off site power, and loss of the only CRS available EDG, the CRS might proceed directly to EMG C-0 (See Event 6) instead of directing EMG E-0 Immediate Actions.

EMG E-0, REACTOR TRIP OR SAFETY INJECTION (Rev 39A)

NOTE o Steps 1 through 4 are immediate action steps.

o Foldout page shall be monitored throughout this procedure.

1. Verify Reactor Trip:

a. Check all rod bottom lights - LIT

b. Check Reactor trip breakers and bypass breakers - OPEN o SB ZL-1 RO o SB ZL-2 o SB ZL-3 o SB ZL-4

c. Check intermediate range neutron flux - LOWERING o SE NI-35B [GAMMA METRICS]

o SE NI-36B [GAMMA METRICS]

2. Verify Turbine Trip:

BOP

a. Check Main Stop Valves - ALL CLOSED

Appendix D 12 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Events No: 5 Total No Pages 23 Event

Description:

Main Feed Pump A Trip, Reactor Trip Required.

3. Check AC Emergency Busses - AT LEAST ONE ENERGIZED

NB01 - ENERGIZED

NB02 - ENERGIZED No, RNO Perform the following:

a. Depress START/RESET push button for any stopped Diesel RO Generator o KJ HS-8A for EDG A o KJ HS-108A for EDG B

b. IF at least one AC emergency bus is now energized, THEN go to Step 4. (NO)

c. Go to EMG C-0, LOSS OF ALL AC POWER, Step 1.

Event termination: After the Reactor has tripped, a loss of off site power and trip of A EDG automatically occur. The crew will respond by entering or transitioning to EMG C-0.

Appendix D 13 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Events No: 6/7 Total No Pages 23 Event

Description:

Loss of Offsite Power and A EDG Trips, (Loss of All AC), TDAFW Pump Fails to Auto Start Time Position Applicants Actions or Behavior Events 6 and 7 are automatically initiated upon reactor trip signal.

Diagnostics: Lighting reduced in the Control Room Simulator, Amber Tripped light on NE HIS-25 NB01 EMERG SPLY BKR NB0111, both NB ZL-5, 4.16 KV BUS NB01 and NB ZL-6, 4.16 KV BUS NB02 indicating lights out, no voltage on either NB bus. Both 345 KV WEST (and EAST) BUS 1EL-SY004 (and (1EL-SY-008) indicating lights out. TDAFW Pump steam supply valves closed, no speed indicated on FC HIS-303A, No indicated AFW flow to any of the S/Gs.

Annunciators: Multiple alarms including 018B/021B-NB01/NB02 BUS UV, 021D-DG NE01 TROUBLE and 128B-TD AFP START CRS Enters and directs EMG C-0, LOSS OF ALL AC POWER.

EMG C-0, LOSS OF ALL AC POWER (Rev 41)

NOTES o Steps 1 and 2 are immediate action steps.

o Foldout page shall be monitored throughout this procedure.

o CSF status trees shall be monitored for information only. Function Restoration (FR) Procedures shall not be implemented during this procedure.

RO 1. Verify Reactor Trip: YES BOP 2. Verify Turbine Trip: YES BOP Foldout page Step 5 for RCS Temperature Control:

IF a Loss-Of-Offsite Power has occurred, THEN perform the following:

a. Close the MSIVs using either AB HS-79 or AB HS-80.

b. Reduce ARV setpoints to control RCS C/L temperature 557°F (1090 psig).

BOP 3. Check Main Generator Breakers And Exciter Breaker - OPEN - YES Simulator Operator: WHEN contacted to close SJ-V054, SJ-V057, and SJ-V103 acknowledge request.

Wait 5 minutes and report back that the valves are closed.

RO 4. Check If RCS Is Isolated:

a. Check RCS Letdown To Regenerative Heat Exchanger valves -

CLOSED o BG HIS-459 o BG HIS-460

b. Check PZR PORVs - CLOSED

c. Check Reactor Coolant To Excess Letdown Heat Exchanger valves - CLOSED

d. Check Reactor Vessel Head Vents - AT LEAST ONE VALVE CLOSED IN EACH TRAIN

e. Dispatch operator to locally close RCS and PZR sample line isolation valves:

o SJ-V054 (2000' AUX BLDG, NORTH PIPE PEN ROOM ON MEZZANINE) o SJ-V057 (2000' AUX BLDG, NORTH PIPE PEN ROOM IN CORNER FURTHEST FROM DOOR) o SJ-V103 (2000' AUX BLDG, SOUTH PIPE PEN ROOM ON MEZZANINE)

Appendix D 14 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Events No: 6/7 Total No Pages 23 Event

Description:

Loss of Offsite Power and A EDG Trips, (Loss of All AC), TDAFW Pump Fails to Auto Start Time Position Applicants Actions or Behavior

5. Check Total AFW Flow >270,000 lbm/hr NO, RNO Perform the following:

a. Ensure Turbine Driven AFW Pump running. IF Turbine Driven AFW Pump NOT running, THEN perform the following:

1) Open steam supply valves o AB HIS-5A o AB HIS-6A BOP 2) Open trip throttle valve o FC HIS-312A CT 1: Establish at least 270,000 lbm/hr AFW flow rate to the S/Gs before 3 S/G wide range levels reach 12% [28%]

NOTE: ALR 00-128B, TD AFP START provides the same direction to start the TDAFP. Performing this action prior to EMG E-0, Step 5 also satisfies the Critical Task.

Foldout Page Step 5 for RCS Temperature Control:

BOP IF RCS C/L temperature Is 557°F AND Lowering, THEN control total feed flow to limit RCS cooldown. Maintain total feedwater flow >270,000 lbm/hr until NR level >6% in at least 1 S/G.

BOP 6. Check Emergency Oil Pumps:

a. Emergency Seal Oil Pump - RUNNING - YES o CD ZL-9

b. Main Feedwater Pump Turbine Emergency Lube Oil Pumps -

BOTH RUNNING - YES o PFC03A For MFWP A (Graphic 6104) o PFC03B For MFWP B (Graphic 6105)

c. Main Turbine Emergency Bearing Oil Pump - RUNNING - YES o CB ZL-13 NOTES o Annunciators 00-018A, NB01 BUS LOCKOUT and/or 00-021A, NB02 BUS LOCKOUT being lit is indicative of a NB Bus Lockout. This will prevent the energization of the affected NB bus from any source until the bus fault is cleared.

o Annunciators 00-018A, NB01 BUS LOCKOUT and/or 00-021A, NB02 BUS LOCKOUT are only functional if either the normal or alternate supply breaker is closed.

CRS/RO 7. Evaluate Availability Of AC Emergency Busses:

a. Check NB01 for faults.

o Annunciator 00-018A, NB01 BUS LOCKOUT - NOT LIT

- Yes

b. Check NB02 for faults.

o Annunciator 00-021A, NB02 BUS LOCKOUT - NOT LIT

- Yes

c. Check NB Bus Status - AT LEAST ONE AVAILABLE - Yes NOTE Annunciator 501-07D, GENERATOR PROTECTIVE RELAY and/or 502-07D, GENERATOR PROTECTIVE RELAY being lit indicates a potential EDG generator electrical fault and associated Emergency Diesel Supply Feeder Breaker lockout or a bus fault while the EDG was tied to the bus with the normal and alternate feeder breakers open.

Appendix D 15 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Events No: 6/7 Total No Pages 23 Event

Description:

Loss of Offsite Power and A EDG Trips, (Loss of All AC), TDAFW Pump Fails to Auto Start Time Position Applicants Actions or Behavior Simulator Operator: WHEN contacted to check EDGs, acknowledge request. Wait 3 minutes and report annunciator 501-07D, GENERATOR PROTECTIVE RELAY, is clear. Report EDG A has a Start Failure alarm locked in (501-06A) and there is fuel oil all over the floor.

ALSO Report that as you walked past the SBO DG Control Panel, you heard a Pop sound and there are no light or screen indications present KU101 HMI Panel.

CRS/RO 8. Evaluate Availability Of EDGs:

a. Check EDG A electrical status.

o Annunciator 501-07D GENERATOR PROTECTIVE RELAY - NOT LIT - YES, but Annunciator 501-06A, DIESEL START FAILURE is lit.

b. Check EDG B electrical status.

o Unavailable due to maintenance.

c. Check EDG Electrical Status - AT LEAST ONE AVAILABLE ASSOCIATED WITH AN AVAILABLE NB BUS - NO RNO: Go to step 10.

Simulator Operator: IF contacted as Turbine Building watch to locally secure the EDG, ON Panel NE107, Take KJ HS-9 to LOC/MAN Position

10. Check AC Emergency Busses - BOTH ENERGIZED o NB01 Voltage - NORMAL o NB02 Voltage - NORMAL NO, RNO: Perform the following:

a. Manually energize AC emergency bus.

b. IF either emergency bus can NOT be energized, THEN CRS/RO perform the following:

1) Locally shutdown associated Diesel Generator:

2) Try to energize affected AC emergency bus(es) from any available power supply, while continuing with this procedure.

o Refer To OFN NB-030, LOSS OF AC EMERGENCY BUS NB01 (NB02)

CRS Assigns RO to perform OFN NB-030 while continuing in EMG C-0.

NOTE: RO Actions in OFN NB-030 in Event 8 Simulator Operator: WHEN contacted to perform Attachments A and B (x2), acknowledge requests.

11. Check If AC Power Has Been Restored:

a. Check AC Emergency Busses - AT LEAST ONE ENERGIZED -

NO, RNO Perform the following:

1. Set ARVs to 1000 psig CRS/BOP 2. Record starting time for Cooldown

3. Open equipment cabinet doors using Attach B

4. Dispatch Opening TDAFW pump room doors using Attach A

5. OBSERVE CAUTION PRIOR TO STEP 15 and continue with Step 15.

CAUTION An Essential Service Water Pump shall be allowed to automatically load on its energized AC emergency bus, to provide Diesel Generator cooling.

Appendix D 16 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Events No: 6/7 Total No Pages 23 Event

Description:

Loss of Offsite Power and A EDG Trips, (Loss of All AC), TDAFW Pump Fails to Auto Start Time Position Applicants Actions or Behavior RO 15. Place The Following Switches In Pull-To-Lock Position:

o MD AFP A (AL HIS-23A) o MD AFP B (AL HIS-22A) o CCP A (BG HIS-1A) o CCP B (BG HIS-2A) o CTMT SPRAY PUMP B (EN HIS-9) o RHR PUMP B (EJ HIS-2) o SI PUMP B (EM HIS-5) o SI PUMP A (EM HIS-4) o RHR PUMP A (EJ HIS-1) o CTMT SPRAY PUMP A (EN HIS-3) o CCW PUMP B (EG HIS-22) o CCW PUMP D (EG HIS-24) o CCW PUMP A (EG HIS-21) o CCW PUMP C (EG HIS-23) o CTMT COOLER FAN B (GN HIS-9) o CTMT COOLER FAN D (GN HIS-17) o CTMT COOLER FAN A (GN HIS-5) o CTMT COOLER FAN C (GN HIS-13) o CTRL RM A/C UNIT 4A FAN & DAMPER (GK HIS-29) o CLASS I/E ELEC EQUIP A/C UNIT 5A (GK HIS-100) o CTRL RM A/C UNIT 4B FAN & DAMPER (GK HIS-40) o CLASS I/E ELEC EQUIP A/C UNIT 5B (GK HIS-103)

Simulator Operator: WHEN contacted to isolate BG HV-8100, BG-V101, BG-V105, EG HV-61, and EG HV-133, acknowledge request. Insert Key 7. The file takes 5 minutes to run. Report valves are isolated when file is finished running.

RO/BOP 16. Dispatch Personnel To Locally Close Valves To Isolate RCP Seals:

a. Seal Water Return Containment Isolation Valve.

o BG HV-8100 (2000' AUX BLDG, SOUTH PIPE PEN ROOM LOWER LEVEL)

b. Seal Water Injection Filters Inlet Isolations.

o BG-V101 (2000' AUX BLDG., DEMIN ALLEY BA/SEAL INJ FILTER A VALVE ROOM) o BG-V105 (2000' AUX BLDG, DEMIN ALLEY CTMT COOLANT FILTER/SEAL INJ FILTER B VALVE ROOM)

c. CCW Return From RCS Isolation Valve.

o EG HV-61 (2000' AUX BLDG NORTH PIPE PEN ROOM)

d. CCW From RCS CTMT Isolation Valve Bypass.

o EG HV-133 (2000' AUX BLDG NORTH PIPE PEN ROOM)

Simulator Operator: IF contacted as System Transmission REPORT, Most of the grid went down but were restoring Wichita right now and expect to power your switchyard within a few minutes.

CRS 17. Check If AC Power Can Be Restored Within 4 Hours Simulator Operator: WHEN contacted as Security (x2), acknowledge requests. WHEN contacted to start TSC Diesel, acknowledge request to use STN KAT-001 to start TSC EDG.

Appendix D 17 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Events No: 6/7 Total No Pages 23 Event

Description:

Loss of Offsite Power and A EDG Trips, (Loss of All AC), TDAFW Pump Fails to Auto Start Time Position Applicants Actions or Behavior RO/BOP 18. Check SL31 and SL2 Status:

a. Check Bus SL31 - DEENERGIZED - YES

b. Ensure Permanent Diesel Driven Fire Pump - RUNNING - YES

c. Check Bus SL2 - DEENERGIZED - YES

d. Check Security Electrical Loads Transferred To Security Diesel Generator.

e. Direct Site Watch to start TSC Diesel, using STN KAT-001, TECHNICAL SUPPORT DIESEL GENERATOR OPERATION.

CAUTION Control room operators may be adversely affected by prolonged exposure to elevated temperatures that may occur during an ELAP or SBO. Rotation of Operators out of the control room, based on stay times, and the use of ice vests stored in the freezer on the 2016 elevation of the Comm Corridor will help minimize the impact until ventilation is restored.

19. Establish Emergency Ventilation:

a. Open Control Building doors, using ATTACHMENT B, DOOR ALIGNMENT IN CONTROL ROOM FOR LOSS OF ALL AC, while continuing with this procedure.

RO/BOP c. Direct Security to perform the following:

o Deenergize redundant security computer in Room 3609 (CAS).

o Take appropriate compensatory measures for open doors.

RO 20. Check SI Accumulator Tank Outlet Isolation Valves - OPEN - YES o EP HV-8808A o EP HV-8808B o EP HV-8808C o EP HV-8808D RO 21. Check If CST Is Isolated From Hotwell:

a. Place condenser Hotwell isolation valve controllers in manual and zero output.

1) AD LIC-79A, CNDS REJECT TO CST

2) AD LIC-79B, COND HOTWELL M/U LEV CTRL Simulator Operator: Insert Key 6 at direction of Lead Examiner to restore an off site power source upon completion of Step 21. Call the CRS as the Transmission System Operator and report power is restored via the Wavery/LaCygne Line.

Appendix D 18 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Events No: 6/7 Total No Pages 23 Event

Description:

Loss of Offsite Power and A EDG Trips, (Loss of All AC), TDAFW Pump Fails to Auto Start Time Position Applicants Actions or Behavior RO 22. Isolate Main Steamlines:

a. Close Main Steamline Isolation Valves.

AB HS-79

AB HS-80

b. Ensure Main Steamline Isolation Valves - CLOSED o AB HIS-14 For S/G A o AB HIS-17 For S/G B o AB HIS-20 For S/G C o AB HIS-11 For S/G D

c. Ensure Main Steamline Isolation Bypass Valves - CLOSED o AB ZL-15A For S/G A o AB ZL-18A For S/G B o AB ZL-21A For S/G C o AB ZL-12A For S/G D

d. Ensure Main Steamline Low Point Drain Valves - CLOSED o AB HIS-9 For S/G A o AB HIS-8 For S/G B o AB HIS-7 For S/G C o AB HIS-10 For S/G D RO 23. Verify Feedwater Isolation: YES

a. Main Feedwater Pumps - TRIPPED o Annunciator 00-120A, MFP A TRIP - LIT o Annunciator 00-123A, MFP B TRIP - LIT

b. Main Feedwater Reg Valves - CLOSED o AE ZL-510 For S/G A o AE ZL-520 For S/G B o AE ZL-530 For S/G C o AE ZL-540 For S/G D

c. Main Feedwater Reg Bypass Valves - CLOSED o AE ZL-550 For S/G A o AE ZL-560 For S/G B o AE ZL-570 For S/G C o AE ZL-580 For S/G D

d. Main Feedwater Isolation Valves - CLOSED o AE HIS-39 For S/G A o AE HIS-40 For S/G B o AE HIS-41 For S/G C o AE HIS-42 For S/G D

e. Main Feedwater Chemical Injection Valves - CLOSED o AE HIS-43 For S/G A o AE HIS-44 For S/G B o AE HIS-45 For S/G C o AE HIS-46 For S/G D Event termination: After the completion of step 21 and/or at the direction of the Lead Examiner, off site power will be restored. The crew may proceed in EMG C-0, and discuss applying foldout page criteria (Step 2) to go to Step 44 upon restoration of the power, but the intent is to end the scenario once power is restored to an NB Bus per OFN NB-030 at the direction of the Lead Examiner. (See Event 8).

Appendix D 19 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 8 Total No Pages 23 Event

Description:

SWYD East Bus Restored, Energize NB01.

Tim e Position Applicants Actions or Behavior RO Enters and performs OFN NB-030 OFN NB-030, LOSS OF AC EMERGENCY BUS NB01 (NB02) (Rev 34)

1. Check AC Emergency Buses - AT LEAST ONE ENERGIZED NO, RNO Perform the following:

a. IF entering this procedure from EMG C-0, LOSS OF ALL AC POWER OR OFN NB-034, LOSS OF ALL AC POWER - SHUTDOWN RO CONDTIONS, THEN go to the desired attachment:

Attachment A, Step A14 for NB01

Attachment B, Step B14 for NB02 NOTE: The steps in Attachment B mirror the steps in Attachment A. ONLY Attachment A steps are provided in this guideline.

CAUTION Prior to using any normal operating procedure to restore equipment and/or resetting any lockout relays, all faults should be verified to be clear.

NOTES o Annunciator 00-018A, NB01 BUS LOCKOUT being lit is indicative of a bus lockout. This will prevent energization of the NB bus from any source until the bus fault is cleared.

o Annunciator 00-018A, NB01 BUS LOCKOUT will not alarm if a bus fault occurs with breakers NB0112 and NB0109 open and EDG A carrying the bus.

A14. Check NB01 Bus Status:

RO o Annunciator 00-018A, NB01 BUS LOCKOUT - CLEAR - YES NOTE Annunciator 501-07D, GENERATOR PROTECTIVE RELAY being lit may be indicative of either a EDG generator fault or a NB bus fault that occurred while the EDG was tied to the bus.

Simulator Operator: IF contacted to check EDGs, acknowledge request. Wait 3-5 minutes (unless reported earlier) and report annunciator 501-07D, GENERATOR PROTECTIVE RELAY, is clear.

Report EDG A has a Start Failure alarm locked in (501-06A) and there is fuel oil all over the floor.

A15. Check NB01 EDG Status RO o Annunciator 501-07D, GENERATOR PROTECTIVE RELAY - CLEAR -

YES NOTE Steps A16 through A24 will attempt to energize NB01 from one of the following: EDG, XNB01 via normal off-site power, XNB01 via SL7, XNB01 via Sharp Station, or NB02 via the cross-tie, or directly from the Station Blackout (SBO) Diesel Generators. The Sharpe Station option requires that the 69KV Phillips line be energized and is fairly time consuming. The SBO EDG option is very quick but requires a dead bus transfer back.

Appendix D 20 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 8 Total No Pages 23 Event

Description:

SWYD East Bus Restored, Energize NB01.

A16. Check Emergency Diesel NE01 Running.

NO, RNO Perform the following:

a. IF SM/CRS directs that NB01 be energized from a source other than the diesel, THEN go to:

Step A19 for normal offsite power via XNB01, offsite power via SL7 or via RO Sharpe Diesels.

Step A21 for alternate offsite power via XNB02

Step A24 for SBO Diesel Generators.

NOTE: EDG NE01 cannot be started per the previously given reports and if off-site power is not restored by this point, the crew might pursue using the SBO Diesel Generators to energize NB01 or NB02.

Simulator Operator: IF contacted to ROTATE power switch NF39A 8N28-1 on bottom panel, to off, THEN Report Crew Discuss OFN NB-030, Step A19 will be used to reenergize bus NB01.

A19. Check Normal Offsite Power Supply - Available

a. Check Annunciator 00-019A, XNB01 SFMR LOCKOUT - CLEAR - YES RO

b. Check ESF Transformer XNB01 - ENERGIZED BY OFFSITE POWER. -

YES A20. Reenergize NB01 From Normal Offsite Power Supply:

a. Place NB01Normal Supply Sync Transfer switch to ON position.

o NB HS-6

b. Place 4.16 KV BUS NB01 SYCN-SCOPE SEL to Main FDR BRKR position.

o NB HS-10

c. Check BUS NB01 VOLTAGE INCOMING SOURCE - NORMAL o NB EI-28

d. Close NB01 Normal Supply Breaker NB0112.

o NB HIS-2 RO

e. Place NB01 Normal Supply Sync Transfer switch to OFF.

o NB HS-6

f. Place 4.16 KV Bus NB01 SYNC-SCOP SEL To OFF.

o NB HS-10

g. Check NB01 - ENERGIZED CT 2: Energize at least one AC Emergency bus prior to conducting the depressurization and cooldown step 32 of EMG C-0.

h. Go to Step A25.

RO A25. Check NB01 - ENERGIZED

Appendix D 21 Form ES-D-2 Op Test No: 11/2017 Scenario No: 2 Event No: 8 Total No Pages 23 Event

Description:

SWYD East Bus Restored, Energize NB01.

A26. Check OFN NB-034, LOSS OF ALL AC POWER - SHUTDOWN CONDITIONS or EMG C-0, LOSS OF ALL AC POWER - NOT IN EFFECT RO - NO, RNO Perform the following:

a. IF NB02 is deenergized THEN go to ATTACHMENT B, LOSS OF NB02, Step B14.

Scenario termination: After the crew has reenergized bus NB01and/or at the direction of the lead examiner, Freeze the Simulator.

Appendix D 22 Form ES-D-2 Attachment 1 (Page 1 of 2)

Appendix D 23 Form ES-D-2 Attachment 1 (Page 2 of 2)

Appendix D Scenario Outline Form ES-D-1 Facility: _Wolf Creek_________ Scenario No.: ____3________ Op-Test No.: ___1__ __

Examiners: ___________________________ Operators: ____________________ ________

Initial Conditions: 100% Power, No equipment out of service, No maintenance in Progress.______

Turnover:__ Continue 100% Power operations.____________________________ ____________

Critical Tasks: CT Manually Trip The Turbine CT Isolate an intact S/G from the ruptured S/G.

CT Depressurize RCS to meet SI termination criteria prior to overfilling ruptured S/G.

Event Malf. No. Event Type* Event No. Description BG PK-131, LTDN HX OUTLET PRESS CTRL fails 1 C (SRO / RO) closed in Auto 2 C (SRO / BOP) PORV 455A fails Open (TS) 3 I (SRO / BOP) D S/G Press Channel PI-545 fails HIGH (TS) 4 C (ALL) Heater Drain Pump trip (Downpower) 5 M (ALL) SGTR on A S/G, A MSIV fails Open 6 C (SRO / BOP) Turbine will not Auto Trip, Manual available 7 C (SRO / BOP) B ESW pump fails to Auto Start

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 2

5. Entry into a contingency EOP with substantive actions (> 1 per 1 scenario set)

6. Pre-identified critical tasks (> 2) 3

Appendix D Scenario Outline Form ES-D-1 Measurable Performance Critical Task Safety Significance Cueing Performance Feedback Indicators CT-1 Manually trip Failure to stop an Turbine Stop Manipulation Indication of the main turbine uncontrolled valves do not of controls as Turbine Stop before a severe cooldown constitutes close on SI signal required to Valves closed.

orange-path a potential challenge trip the RCS uncontrolled RCS challenge develops to both Integrity and turbine. cooldown Temperature to either the Subcriticality Critical stopped.

drops due to subcriticality or the Safety Functions, excessive integrity Critical resulting in a steaming after Safety Function or reduction of margin to reactor trip.

before transition to safety.

EMG E-2, whichever happens first.

CT-2, Isolate an Failure to decouple Radiation monitor Manipulation B, C, and/or D intact S/G from the the ruptured S/G from alarms. of controls to MSIVs close ruptured S/G prior to the RCS by failing to close at least providing at least All MSIVs indicate exiting EMG E-3, or close any non- 1 MSIV: one intact S/G open on MCB.

attempting to ruptured S/G MSIV that is thermo-extends the loss of Ruptured S/G B: AB HIS-17 dynamically perform a controlled RCS inventory and pressure dropping C: AB HIS-20 isolated from the RCS cooldown.

raises the amount of while attempting D: AB HIS-11 ruptured S/G.

contamination that to use a non-bypasses ruptured S/G for B/C/D:

containment into the cooldown. AB HIS-79/80 secondary system.

CT-3, Commence Depressurizing the S/G Level rising Manipulation RCS Pressure controlled RCS RCS to equalize with in an uncontrolled of controls as reducing in a depressurization to Ruptured S/G manner with feed required to controlled allow for SI pressure prior to flow isolated. depressurize manner, termination prior to overfilling the the RCS.

Radiation monitor subcooling overfilling the ruptured S/G alarms maintained, ruptured S/G (90% minimizes radioactive release to the leak rate to WR).

environment from the ruptured S/G ruptured S/G, drops, minimizes stress to PZR Level >6%,

the Main Steam Lines, and allows for Ruptured S/G a subcooled recovery Level <93% NR.

vice a potential saturated recovery.

Note: Causing an unnecessary plant trip or ESF actuation may constitute a Critical Task failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Appendix D Scenario Outline Form ES-D-1 Scenario 3 Narrative Turnover, 100% Power, MOL, Boron Concentration 976 ppm, No equipment out of service, No maintenance in Progress.

Event 1, BG PK-131 fails closed in Auto. MCB Annunciators 039C, LP LTDN RELIEF TEMP HI and 039D, LTDN HX DISCH PRESS HI will both actuate. Crew may perform either ALR procedure as the procedural guidance is the same. The RO will take manual control of BG PK-131 and adjust controller output to establish and maintain a letdown pressure of 350 psig. Upon completion of the ALR, and with the concurrence of the lead examiner, Event 2 will start.

Event 2, PORV 455A Fails Open, MCB Annunciator 035B, PORV OPEN will actuate. Step 1 of ALR 00-035B is a memory action step for the Operator to close the affected PZR PORV if PZR Pressure is <2315 psig and then close the associated block valve when the PORV fails to indicate fully shut. The CRS will determine that Technical Specification 3.4.11, Condition B is applicable with a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months completion time to close and remove power to the associated block valve. Upon completion of the ALR, and after the CRS has determined technical specification, and with the concurrence of the Lead examiner, Event 3 will start.

Event 3, D S/G Pressure Channel AB PI-545 fails HIGH, MCB Annunciator 111C SG D FLOW MISMATCH will actuate. The crew is expected to respond by performing OFN SB-008, INSTRUMENT MALFUNCTIONS, ATTACHMENT C. The BOP has a memory action to take manual control of D S/G Feed Reg Valve (AE FK-540) and match steam and feed flows to restore S/G Level to program 50%.

The crew will determine which instrument failed (AE PI-545) and remove it from control before returning AD FK-540 Feed Reg Valve to automatic. The CRS will determine LCO 3.3.2, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION, CONDITIONS A-Immediately, and D-72 hours are applicable per Table 3.3.2-1, Functions 1.e and 4.e. Once the SRO has determined applicable technical specifications and with the concurrence of the lead examiner, Event 4 will start.

Event 4, A Heater Drain Pump Trip, (Downpower) MCB Annunciators 103E, HEATER DRN TK DUMP will actuate 60-70 seconds after the pump trips. The crew may notice a change in Main Generator load trending down, or a NPIS alarm prior to Annunciator 103E alarming. Expect the crew to perform ALR 103E and/or reference OFN AF-025, UNIT LIMITATIONS. OFN AF-025 directs a Maximum unit load of 95% and performance of SYS AF-121 to address continued operations with one Heater Drain Pump Out Of Service. The crew may choose to rapidly reduce power using OFN MA-038, RAPID PLANT SHUTDOWN or conduct a reactivity brief and lower power at a slower rate to 95% using GEN 00-004 hard card. Once the reactor turbine load reduction has stopped at 95%, or at the direction of the lead examiner, Event 5 will start.

Event 5, SGTR on A S/G, with A MSIV failed open. The crew will diagnose a SGTR with RCS pressure and PZR Level dropping and MCB Annunciator 061A, PROCESS RAD HIHI alarm with corresponding RED radiation levels on RM-11 Panel for GE RE-92, CONDENSER AIR REMOVAL DISCHARGE Process Radiation Monitor. The crew will Trip the reactor and actuate SI and perform EMG E-0, REACTOR TRIP OR SAFETY INJECTION until directed to transition to EMG E-3, STEAM GENERATOR TUBE RUPTURE at step 17. Prior to exiting EMG E-0, The BOP Operator will have to address a failure of the turbine to trip (Event 6) and perform foldout page direction to isolate A S/G while the RO addresses failure of B ESW Pump to auto start. Events 5-7 all occur simultaneously. While performing EMG E-3, the Crew will identify the inability to close A S/G MSIV and may transition to EMG C-31, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Once the crew starts depressurizing the RCS and /or with the direction of the lead evaluator the scenario will be complete.

CT-2: Isolate an intact S/G from the ruptured S/G prior to exiting EMG E-3, or attempting to perform a controlled RCS cooldown.

CT-3: Commence controlled RCS depressurization to allow for SI termination prior to overfilling the ruptured S/G (90% WR).

Appendix D Scenario Outline Form ES-D-1 Event 6, Turbine will not trip in Auto. The BOP will note the turbine stop valves are not closed when looking at the Ovation Graphic Screen. The turbine should have tripped on Safety Injection. The RNO action is to depress BOTH turbine trip buttons which successfully trips the turbine.

CT-1: Manually trip the main turbine before a severe orange-path challenge develops to either the subcriticality or the integrity CSF or before transition to EMG E-2, whichever happens first.

Event 7, B ESW Pump fails to Auto Start, The B EDG will be running unloaded without cooling water.

One of the Operators may notice the pump failed to start and will manually start the pump per AP15C-003, PROCEDURE USERs GUIDE FOR ABNORMAL PLANT CONDITIONS Manual Backup. The RO is also directed to check this pump running during performance of EMG E-0, ATTACHMENT F. Per OFN EF-033, LOSS OF ESW, the diesel generator may run for up to 30 minutes unloaded before over temperature condition develop. NOT a critical task since both NB busses are powered from off-site power, but failure to take appropriate action within the required timelines would eliminate an emergency source of power and unnecessarily complicate the scenario and reduce the safety margin.

Note: Causing an unnecessary plant trip or ESF actuation may constitute a Critical Task failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Appendix D Scenario Outline Form ES-D-1

2017 ILO Scenario #3, (IC 303)

Event 1 - [Key 1] BG PK-131 fails closed IMF mBG17A f: 0 r:5 k:1

Event 2 - [Key 2]PORV 455A fails Open, Manual Available

{Key[2]}IMF mSA27BB07

{Key[2]}set cnS829A_NO.input=1

{Key[2]}set cnK811A_NO.input=1 IOR P21053A f:1 k:2

{Key[11]} IRF rBB31A f:1

Event 3 - [Key 3]SG Press channel AB PT-545 fails HIGH IMF mAB01D2 f: 1313 k:3

Event 4 - [Key 4]Heater Drain Pump 'A' trips ICM bkrDPAF01A t: 1 d:0 k:4

Event 5 - [Key 5]SGTR on 'A' SG IMF mBB02A f: 350 r:30 k:5

'A' MSIV fails Open ICM vmodABHV0014 t: 1 d:0

Event 6 - Turbine fails to Auto trip IMF mAC02B i: -1 f:-1

Event 7 - ESW 'B' does not Auto Start IMF mEF05B i: -1 f:-1

Remote Local Action [Key 6]Locally close AB V-062 IRF rAB03A f: 0 r:30 k:6

Remote Local Action [Key 7] Place 'A' EDG in Standby

{Key[7]}scn SimGroup\EDGA_STBY

Remote Local Action [Key 8] Place 'B' EDG in Standby

{Key[8]}scn SimGroup\EDGB_STBY

Remote Local Action [Key 9] Close NG01AFF4 and NG02AAF4 (Bat Pumps)

IRF rBG40A f:1 k:9 IRF rBG40B f:1 k:9

Remote Local Action [Key 10] Close NG04CPF2 (BG HV-8104)

IRF rBG41 f:1 k:10

Appendix D 1 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 1 Total No Pages 53 Event

Description:

BG PK-131, LTDN HX OUTLET PRESS CTRL fails closed in Auto Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 1 at the lead examiners direction.

Diagnostics: Letdown flow lowers, Letdown pressure rises.

Annunciators: 039C-LP LTDN RELIEF TEMP HI, 039D-LTDN HX DISCH PRESS HI Direct either ALR 00-039C or ALR 00-039D; both procedures contain the same mitigative action.

NOTE: While not a Memory Action per either ALR, the crew may take CRS manual control of BG PK-131 per AP15C-003, PROCEDURE USERS GUIDE FOR ABNORMAL PLANT CONDITIONS, paragraph 4.14 Manual Backup prior to entering the ALR.

ALR 00-039C, LP LTDN RELIEF TEMP HI (Rev 10)

NOTE The letdown high pressure relief valve is set to relieve at 600 psig.

1. Check Letdown High Pressure Relief Valve Outlet Temperature -

RO GREATER THAN 140°F - YES

2. Check Letdown Containment Isolation Valves - OPEN - YES RO o BG HIS-8152 o BG HIS-8160

3. Check Letdown Heat Exchanger Outlet Pressure - Greater Than 600 PSIG - YES RO o BG PI-131

4. Check Letdown Heat Exchanger Inlet Temperature Control Valve (BG TCV-381B) Open: - YES

a. Check CVCS Letdown to Letdown HX Valve - OPEN RO

Computer Point BG0381B

TCV381B on NPIS BG2

5. Check Letdown Heat Exchanger Outlet Pressure Control -

OPERATING PROPERLY - NO RNO: Perform the following:

RO

a. Place controller in manual.

b. Adjust pressure controller, as necessary, to establish 350 psig.

CRS Provide controlling band and target pressure for controller in manual.

6. Check Letdown Heat Exchanger Outlet Pressure - BETWEEN 300 PSIG AND 350 PSIG - YES RO o BG PI-131

Appendix D 2 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 1 Total No Pages 53 Event

Description:

BG PK-131, LTDN HX OUTLET PRESS CTRL fails closed in Auto Time Position Applicants Actions or Behavior

7. Check PRT Parameters:

o PRT Pressure - NOT RISING - YES BOP AND o PRT Level - NOT RISING - YES Crew 8. Return To Procedure And Step In Effect ALR 00-039D, LTDN HX DISCH PRESS HI (Rev 7)

1. Check Letdown Heat Exchanger Outlet Pressure - >500 psig RO o BG PI-131 - YES

2. Check Letdown Heat Exchanger Outlet Pressure Control -

OPERATING PROPERLY o BG PK - 131- NO RO RNO: Perform the following:

a. Place controller in manual.

b. Adjust pressure controller, as necessary, to establish 350 psig.

3. Check CVCS Demineralizers:

RO a. Check CVCS demineralizers by - BEING SHIFTED - NO RNO: Go to Step 4.

4. Check BTRS - IN SERVICE - NO RO RNO Go to Step 5.

5. Check Letdown Heat Exchanger Outlet Pressure - BETWEEN 300 RO PSIG AND 350 PSIG - YES Crew 6. Return To Procedure And Step In Effect Simulator Operator:

o IF contacted as WWM, acknowledge requests.

o IF contacted as Call Supt., acknowledge status.

Event termination: After the crew has restored letdown pressure to normal and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 2 at direction of Lead Examiner.

Appendix D 3 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 2 Total No Pages 53 Event

Description:

PORV 455A fails Open in Auto, Manual Control NOT available Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 2 at the lead examiners direction.

Diagnostics: RCS Pressure Drop, PZR Level drop, PRT Temperature rises, PORV Block Valve closes Annunciators: 035B-PORV OPEN, 034C-PZR PORV BLOCK, 034D-PRT TEMP HI, 035D- PZR PORV DISCH TEMP HI ALR 00-035B, PORV OPEN (Rev 9)

NOTE Step 1 is a Memory Action Step.

1. Check if PZR PORVs Should be closed when Not in Cold Over pressure Protection:

a. Check Cold Overpressure Protection System - NOT IN SERVICE o BLOCK/ARM switches in BLOCK - YES o BB HS-8000A o BB HS-8000B

b. Check PZR Pressure - LESS THAN AFFECTED PORV CLOSURE SETPOINT

BB PCV-455A - 2315 PSIG - YES

c. Close affected PZR PORVs.

BB HIS-455A - NO RNO - IF affected PORV(s) will NOT close, THEN close associated PORV block valve.

BB HIS-8000A For BB PCV-455A.

NOTE: The crew may discuss LCO 3.4.1, Departure from Nucleate Boiling (DNB) if RCS Pressure drops below 2220 psig during the transient. Cond BOP A Required action is to restore RCS Pressure to >2220 psig within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

2. Check if PZR PORVs Should be closed when in Cold Over pressure Protection:

a. Check Cold Overpressure Protection System - IN SERVICE o BLOCK/ARM switches in ARM - NO o BB HS-8000A o BB HS-8000B BOP RNO Go to Step 3

3. Verify PZR PORVs - AT LEAST ONE OPENED

a. Check PZR PORV Discharge Temperature - GREATER THAN NORMAL BOP o BB TI-463

Appendix D 4 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 2 Total No Pages 53 Event

Description:

PORV 455A fails Open in Auto, Manual Control NOT available Time Position Applicants Actions or Behavior NOTE This step is checking to see if a CISA has actuated at any time during the event. NPIS historical trend using SAQ0601 can be used. A CISA will cause BG HV-8100 and BG HV-8112 to close, this will then lift BG-8121, RCP SEAL LEAKOFF RELIEF TO PRT ISO and fill the relief valve discharge header with water.

Simulator Operator: IF contacted as local operator to drain RHR suction relief header, Acknowledge the request.

4. CISA Was Actuated RNO: Perform the following:

a. Perform SYS BB-202, PRESSURIZER RELIEF TANK OPERATION to drain RHR suction relief header.

NOTE: SYS BB-202, Paragraph 6.9.7 performs the directed task.

All actions are LOCAL, so the BOP should dispatch a local operator to perform.

BOP b. Go to Step 6.

Simulator Operator: WHEN contacted as the Aux Building Watch to open breaker NB01BBR3 for BB HV-800A, THEN Insert Key 11. Wait 2 minutes and report the breaker is Open.

6. Refer to Technical Specifications 3.4.11 And 3.4.12.

LCO 3.4.11, COND B is applicable, to close the block valve and remove power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and Restore PORV to OPERABLE status CRS within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

CRS 7. Return to Procedure and Step in Effect.

Event termination: After the crew completed the ALR, the CRS has determined applicable tech specs and power is removed from the PORV Block Valve and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 3 at direction of Lead Examiner.

Appendix D 5 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 3 Total No Pages 53 Event

Description:

D S/G Pressure Channel AB PI-545 fails HIGH Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 3 at the lead examiners direction.

Diagnostics: Indicated steam pressure trends up slow, Indicated steam flow trends up slow, S/G level trends up slow.

Annunciators: 111C-SG D FLOW MISMATCH, 111B, SG D LEV DEV Recognizes and reports failure and takes manual control of Main BOP Feedwater Reg Valve (FWRV).

Enters and Performs ALR 00-111C.

NOTE: Crew may enter ALR 00-111B instead. The mitigation action to place FWRV in manual and restore level to program is the same as in ALR 00-111C.

The Crew may also enter OFN SB-008 directly instead of performing CRS either ALR procedure.

Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

ALR 00-111C, SG D FLOW MISMATCH (Rev 10)

NOTE Steps 1 through 3 are Memory Action steps.

1. Check Difference Between Steam Generator D Steam Flow and Feed Flow - >0.7 MPPH - YES o AB FI-542A For Steam Flow o AB FI-543A For Steam Flow o AE FI-540A For Feed Flow o AE FI-541A For Feed Flow BOP

2. Check for Instrument Operating Properly: - NO o Steam Generator A Controlling Steam Pressure Channel -

WITHIN 100 PSIG of remaining channels - NO

AB PI-545A - Failed High RNO: Perform the following:

a. Place Feedwater Reg Valve or Feedwater Reg Bypass Control Valve in manual.

AE FK-540

b. Adjust Feedwater Reg Valve or Feedwater Reg Bypass Control Valve, as necessary, to establish Steam Generator level at program value.

BOP c. Go to OFN SB-008, INSTRUMENT MALFUNCTIONS, step 1.

Appendix D 6 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 3 Total No Pages 53 Event

Description:

D S/G Pressure Channel AB PI-545 fails HIGH Time Position Applicants Actions or Behavior OFN SB-008, INSTRUMENT MALFUNCTIONS (Rev 45)

1. Check For Malfunction:

Check If Secondary System Instrument Channel Is Malfunctioning: - YES

a. Perform appropriate attachment for malfunctioning channel or controller from table below:

VARIABLE CHANNELS ATTACHMENT P-514, P-515, P-516 S/G P-524, P-525, P-526 Pressure ATTACHMENT C P-534, P-535, P-536 (AB)

P-544, P-545, P-546 CRS Enters and directs ATTACHMENT C.

NOTE: If the crew mis-diagnoses steam flow channel as the cause of the steam flow mismatch and enters Attachment A, Step A5 checks for S/G Pressure Channel malfunction and directs transition to Attachment C.

There is no consequence for entering Attachment A since the mitigative actions to take manual control of the Feed Rev valve and selecting out the CRS impacted steam flow channel are the same in either attachment.

OFN SB-008, S/G PRESSURE CHANNEL MALFUNCTION (Rev 45)

CAUTION S/G steam pressure is an input to the thermal power program. A failed steam pressure channel could cause the thermal power program to be inaccurate.

NOTE o Steps C1 through C3 are Memory Action steps.

o A steam flow channel compensated by failed pressure channel will affect Main Feed pump speed until the failed channel is selected out.

BOP C1. Identify Failed Instrument Channel: AB PI-545A for S/G D C2. Check If Failed S/G Pressure Channel Used For Feedwater Control:

BOP YES, F-543 C3. Check Main Feed Reg Valves In Control: -YES

a. Place Affected SG MFW REG VLV CTRL - IN MANUAL BOP

AE FK-540

b. Adjust AE FK-540 as necessary to establish S/G Level at program.

C4. Select Alternate Steam Flow Channel On SG STEAM FLOW BOP CHANNEL SEL Switch:

AB FS-542C BOP C5. Restore Affected SG MFW REG VLV CTRL To - AUTO

Appendix D 7 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 3 Total No Pages 53 Event

Description:

D S/G Pressure Channel AB PI-545 fails HIGH Time Position Applicants Actions or Behavior NOTE When a TS 3.3 functions refers to another TS 3.3 function for all initiation functions and requirements, only the actions associated with TS 3.3.2, Function 1 (Safety Injection) is required to be taken.

Declaring LCOs 3.3.6 and 3.3.7 not met due to an inoperable Safety Injection instrument is not required. However, for completeness a control room log entry stating that TS 3.3.6 and TS 3.3.7 have been reviewed is desired.

C6. Monitor The Following Technical Specifications LCOs And Comply With Action Statements, As Appropriate:

o 3.3.2, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION, Table 3.3.2-1, Functions 1.e And 4.e - YES COND A- IMMEDIATE, COND D - 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months o 3.3.4, REMOTE SHUTDOWN INSTRUMENTATION, Table 3.3.4-1, Function 7 - Minimum Met CRS o 3.3.3, POST ACCIDENT MONITORING INSTRUMENTATION, Table 3.3.3-1 Function 8 - Minimum Met o 3.3.6, CONTAINMENT PURGE ISOLATION INSTRUMENTATION -Minimum Met (See Note) o 3.3.7, CONTROL ROOM EMERGENCY VENTILATION SYSTEM ACTUATION NSTRUMENTATION -Minimum Met (See Note)

Event termination: After the crew has MFRV in auto, S/G Level at or trending to program, Tech. Specs.

identified and /or at the direction of the lead examiner.

Simulator Operator: Insert Key 4 at direction of Lead Examiner.

Appendix D 8 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 4 Total No Pages 53 Event

Description:

Heater Drain Pump A Trips.

Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 4 at the lead examiners direction.

Diagnostics: Generator load trending down, HDP A trip indication (Amber Light Lit), NPIS Alarm Annunciators: 103E-HEATER DRN TK DUMP Recognize HDP A Trip Crew NOTE: If the crew does not see the NPIS alarm, it will take 60-70 seconds for MCB Annunciator 103E to alarm and prompt crew response.

ALR 00-103E, HEADER DRN TK DUMP (Rev 14)

1. Check Heater Drain Dump Valves, Using NPIS Computer - OPEN - YES BOP o AFD0074A for AF LV-74A o AFD0074B for AF LV-74B Simulator Operator: WHEN contacted To determine level in Heater Drain Tank acknowledge request, WAIT 3 minutes and REPORT: Level is above 25 and slowly rising

2. Check If Dump Valves Should Be - OPEN o Locally Check Heater Drain Tank Level - HIGHER THAN 20 BOP INCHES ABOVE CENTERLINE Dispatch Building Watch to investigate.

3. Check Turbine Power - Less than or equal to 25% - NO BOP RNO: Go to step 5.

Simulator Operator:

O IF contacted as WWM, acknowledge requests.

O IF contacted as Call Supt., acknowledge status.

5. Check Heater Drain Pumps - RUNNING - NO RNO: Perform the following:

a. IF a Heater Drain Pump has tripped, THEN perform the following:

o Notify Electrical Maintenance to determine and correct cause.

o Complete shutdown of affected Heater Drain Pump per SYS BOP AF-121, HEATER DRAIN PUMP OPERATION.

b. N/A (One HDP is running)

NOTE: Section 6.2 of SYS AF-121 is applicable. (See Page 10 for procedure steps)

Appendix D 9 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 4 Total No Pages 53 Event

Description:

Heater Drain Pump A Trips.

Time Position Applicants Actions or Behavior Simulator Operator:

o WHEN directed to check AF LV-71A and 71B, acknowledge request. WAIT 3 minutes and REPORT valve 71A is closed.

6. Locally Check Heater Drain Tank Level Control Valves - OPEN BOP o AF LV-71A o AF LV-71B NOTE Heater Drain Pump discharge flow must be maintained less than 3.11 x 106 lbs/hr at AF FI-89, HTR DRN PMP A & B DISCH FLOW.

7. Try To Raise Heater Drain Pump Flow, By Reducing Condensate Pump Discharge Pressure:

a. From Graphic 6102, using Condensate Pumps Recirc Valve controllers, adjust running Condensate Pumps Recirc Valves to BOP increase Heater Drain Pump discharge flow and establish normal Heater Drain Tank level.

o ADFV-0007B For Pump A o ADFV-0015B For Pump B o ADFV-0022B For Pump C

8. Verify Heater Drain Pump - RECIRCULATION FLOW

a. ENSURE Heater Drain Pump Recirculation Controllers - SET AT BOP 0.55 x106 LMB/HR o AF FIC-72B For Pump A o AF FIC-73B For Pump B CRS 9. Return To Procedure And Step In Effect.

OFN AF-025, UNIT LIMITATIONS (Rev 52)

Crew Recognize there is a 95% power limit for operation with only one HDP.

NOTE o Steps 1 through 12 may be done in any order. [N/A for this malfunction]

o Reactor power reductions using this OFN are limited to 6 MWe (0.5%) per minute. Reactor power reductions at greater than 12 MWe(1.0%) per minute must be done using OFN MA-038, RAPID PLANT SHUTDOWN.

12. Check for Conditions Requiring Unit Load Reduction.

Crew

a. Determine maximum unit load, using ATTACHMENT A, UNIT LOAD LIMITS.

[3385 MWT 95% (3) (4) (5)]

(3) Refer to SYS AF-121 (4) If Reactor Power >60%, ensure all three main condensate pumps are running (5) If Reactor Power >65%, ensure no LP Heater Strings are isolated.

Appendix D 10 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 4 Total No Pages 53 Event

Description:

Heater Drain Pump A Trips.

Time Position Applicants Actions or Behavior

b. Reduce unit load, as necessary, to satisfy load limits using appropriate procedure:

Crew *GEN 00-004, POWER OPERATION NOTE: If crew chooses this method, they will use GEN 00-004, POWER OPERATIONS, ATTACHMENT F laminated hard card.

(See Attachment 1). Boron will be added as briefed per SYS BG-200, REACTOR MAKEUP CONTROL SYSTEM NORMAL OPERATION, ATTACHMENT B, boration For Temperature Adjustment in MODE 1 and 2. (See attachment 2)

NOTE: The crew may choose to lower turbine load 30 MW using FAST LOAD DECREASE IAW Pre-shift reactivity brief actions per GEN 00-004, ATTACHMENT F laminated hard card (See Attachment 1).

OR

GEN 00-005, MINIMUM LOAD TO HOT STANDBY OR

OFN MA-038, RAPID PLANT SHUTDOWN NOTE: If crew chooses this method, see OFN MA-038 expected actions below. The crew pre-briefs 10% down power, so they may choose to perform this method of load reduction.

SYS AF-121, HEATER DRAIN PUMP OPERATION (Rev 24)

BOP 6.2.1 ENSURE Reactor Power <95%

6.2.2 IF Reactor Power >60%, THEN Perform the following:

BOP 1. ENSURE all three Condensate Pumps are running.

2. ENSURE Main Turbine Load Control is in Open Loop mode.

NOTES (Pump already stopped) o When one HDP is stopped with Reactor Power between 90% and 100%, Generator output may lower between 20 and 30 Mw, due to loss of plant efficiency o When HDP A is stopped, Condensate and Feedwater System parameters should be monitored, to ensure proper operation.

Simulator Operator: WHEN contacted TSO/TBW, acknowledge report.

6.2.3 Notify Treatment System Operator and Turbine Building watch that BOP HDP A was secured.

6.2.4 IF directed by SM/CRS, THEN ENSURE AD HIS-28, CNDS DEMIN BOP BYPASS VLV is full open.

Appendix D 11 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 4 Total No Pages 53 Event

Description:

Heater Drain Pump A Trips.

Time Position Applicants Actions or Behavior Simulator Operator: WHEN contacted as TBW, acknowledge request to isolate discharge valve, use REMOTE rAF02A, wait 3 minutes and report valve AF-231 is closed.

6.2.5 IF Reactor Power is >50%, THEN PERFORM the following:

BOP 1. CLOSE AF-V231, HDP A DISCH LV-71A OUTLET ISO.

2. ENSURE AF FV-72B, HDP RECIRC VLV is throttled open.

NOTE

5 Heaters Hi-Hi setpoints could be challenged if the valves are NOT operating properly.

BOP 6.2.6 ENSURE AF LV-74A and -74B are FUNCTIONING PROPERLY.

BOP 6.2.7 Stop HDP A (AF HIS Normal After Stop)

BOP 6.2.8 ENSURE HDP Discharge Flow <3.11E6 lb/hr at AF FI-89.

BOP 6.2.9 IF HDP B is operating AND pump flow is <3.0E6 lbm/hr Take Actions.

BOP 6.2.10, N/A 6.2.11 N/A, 6.2.12 Section Complete.

OFN MA-038, RAPID PLANT SHUTDOWN (Rev 28A) (Contingent Steps for Down power)

CAUTION Fast unloading rates may result in elevated turbine vibration.

NOTES o Foldout page shall be monitored throughout this procedure.

o Load reduction at greater than 65 MW (5%)/minute will arm condenser steam dumps.

o Steps 1, 2 and 3 are memory action steps.

1. Determine Turbine Unloading Method To Be Used:

a. Check Desired Unloading Rate - LESS THAN OR EQUAL TO 65 BOP MW/MINUTE (5%)

b. Check Automatic Turbine Unloading - DESIRED NOTES o If the High Limiter Active on Graphic 5551 is in alarm, load can only be decreased with the Load Control selected to Open Loop. When High Limiter Active is cleared as indicated by the alarm changing to Limiter Activated, the Load Control Mode may be changed.

o The following is the preferred Mode of Load Control, unless otherwise directed by another procedure:

Open Loop - When Turbine Load is not being changed or the first 10% load reduction from 100%.

MW - If making Turbine Load changes where there is no ongoing secondary side transient.

FSP - If a secondary side transient requires changing Turbine Load or there is a need to keep primary side more stable.

Appendix D 12 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Event No: 4 Total No Pages 53 Event

Description:

Heater Drain Pump A Trips.

Time Position Applicants Actions or Behavior

2. () Reduce Turbine Load In Automatic:

a. From Graphic 5551, TURBINE CONTROL SYSTEM -

OPERATION PANEL, LOAD CONTROL section - Select method of Load Control, as directed by CRS/SM.

First Stage Pressure

Megawatts

Open Loop (Only for first 10% load reduction from 100%)

b. Perform the following steps to reduce turbine load:

1) From Graphic 5551, SETPOINTS section, select CHANGE.

2) At popup 7055, enter the desired MW (greater than or equal to 90% if in Open Loop) and select ENTER.

3) At popup 7055, in the RATE - DEC field enter the desired rate of decrease and select ENTER.

4) From Graphic 5551, SETPOINTS section, select GO to RO/BOP commence load reduction.

c. () Borate RCS And Adjust Control Rods, As Necessary, To Maintain The Following:

o Target Tavg/Tref Temperature Error Between 0°F And +5°F o Control Rods Above The Rod Insertion Limits NOTE: See Attachment 2, SYS BG-200, REACTOR MAKEUP CONTROL SYSTEM NORMAL OPERATION, ATTACHMENT B, Boration For Temperature Adjustment in MODE 1 and 2. This is the laminated hard card that the RO is utilizing.

d. () Energize PZR Backup Heaters.

o BB HIS-51A o BB HIS-52A

e. Maintain desired turbine unloading rate.

f. Go to step 4.

Event termination: After the crew has completed ALR 00-103E, reduced power to 95%, the RO has performed a reactivity manipulation, and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 5 at direction of Lead Examiner.

Appendix D 13 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 5 at the lead examiners direction.

Diagnostics: Process Rad Monitor Alarms, RCS Pressure dropping, PZR Level lowering, Charging flow rising, Feed flow to A S/G lowering Annunciators: 061A-PROCESS RAD HIHI, 062B-PROCESS RAD HI Diagnose RCS Pressure dropping. May discuss entry to either OFN BB-007 RCS LEAKAGE HIGH or OFN BB-07A STEAM GENERATOR TUBE LEAKAGE and /or need to maximize charging, isolate letdown and Crew determine PZR Level trend to determine the need to trip and actuate SI.

NOTE: With the given SGTR Leak rate at 350 gpm, either OFN BB-007 or OFN BB-07A Foldout page criteria will be met.

EITHER OFN BB-007, RCS LEAKAGE HIGH (Rev 18A) OR OFN BB-07A, STEAM GENERATOR TUBE RUPTURE (Rev 20)

Step 1 Foldout page SI Actuation Criteria:

IF any condition listed occurs, THEN trip the reactor, actuate SI and go to EMG E-0, REACTOR TRIP OR SAFETY INJECTION Step 1.

All of the following conditions exist:

RO o Normal charging is maximized from one pump.

AND o Letdown is isolated.

AND o Pressurizer level is still dropping.

Diagnose SGTR and Trip the Reactor and Actuate SI.

Crew NOTE: Events 6 and 7 are also active once the Reactor Trips.

Direct performance of Reactor Trip, SI Actuation, and Immediate Actions of CRS EMG E-0.

EMG E-0, REACTOR TRIP OR SAFETY INJECTION (Rev 39A)

NOTES o Steps 1 through 4 are immediate action steps.

o Foldout page shall be monitored throughout this procedure.

RO 1. Verify Reactor Trip - Yes

Appendix D 14 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior

2. Verify Turbine Trip:

a. Check Main Stop Valves ALL CLOSED - NO RNO Perform the following:

1) Manually trip turbine - YES BOP CT 1: Manually trip the main turbine before a severe orange-path challenge develops to either the subcriticality or the integrity Critical Safety Functions or before transition to EMG E-2, whichever happens first.

NOTE: See Attachments 3 and 4 from EMG F-0, CRITICAL SAFETY FUNCTION STATUS TREES (CSFST), FIGURES 1 and 4.

3. Check AC Emergency Busses - AT LEAST ONE ENERGIZED - YES RO *NB01 - ENERGIZED

NB02 - ENERGIZED

4. Check if Safety Injection is Actuated.

RO a. Check any indication SI is actuated - LIT - YES

b. Check both trains actuated (030A, 031A) - YES FOLDOUT PAGE 4. IF any S/G level rises in an uncontrolled manner OR any S/G has abnormal radiation, AND NR level in affected S/G(s) is >6%

[29%], THEN perform the following.

BOP a. Close ruptured S/G AFW flow control valves.

o AL HK-8A, SG A TD AFP AFW REG VLV CTRL o AL HK-7A, SG A MD AFP AFW REG VLV CTRL FOLDOUT PAGE 7. IF RCS C/L Temperature is <557°F and BOP lowering, THEN Throttle aux feed flow to >270,000 lbm/hr until NR level is

>6%[29%] in at least one S/G CAUTION If offsite power is lost after SI reset, manual action may be required to restore safeguards equipment to the required configuration.

5. Check if SI is required - YES, RO

SI was Manually actuated AND was required.

6. Verify Automatic Actions Using ATTACHMENT F, AUTOMATIC SIGNAL VERIFICATION.

NOTE: See Attachment 5 for full EMG E-0, Appendix F. The RO will be required to perform 2 actions.

F7. Manually start B ESW Pump using EF HIS-56A, which failed to RO auto start, and F16. Stop the NCP using BG HIS-3.

NOTE: B EDG will be running unloaded since bus NB02 is still powered from off-site. Per OFN EF-033, LOSS OF ESSENTIAL SERVICE WATER, Foldout Page step 2, the B EDG should be stopped if cooling water cannot be established within 30 min.

Appendix D 15 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior BOP 7. Check Main Generator Breakers And Exciter Breakers - OPEN - YES BOP 8. Check Total AFW Flow - GREATER THAN 270,000 LBM/HR - YES BOP 9. Check RCS Cold Leg Temperatures:

Stable at or trending to 557°F for condenser steam dumps or S/G ARVs RNO Perform the following:

a. IF temperature is <557F and dripping, THEN perform the following:

1) Stop dumping steam.

2) IF any MSIV is open, THEN close Main Turbine Stop And Control Valves Startup Drains.

o AC HIS-134

3) IF cooldown continues, THEN control total feed flow to limit RCS cooldown.

BOP 10. Establish S/G Pressure Control:

a. Check Condenser AVAILABLE - YES

b. Place Steam Header Pressure Control in Manual o AB PK-507

c. Manually set steam header pressure control output to zero o AB PK-507

d. Place Steam Dump Select Switch in STEAM PRESS position o AB US-500Z

e. Place Steam Header Pressure Control in Automatic o AB PK-507 BOP 11. Check PZR PORVs:

a. Check PZR PORVs - Closed - NO RNO a. Actions Already complete.

b. Power to block Valves - AVAILABLE - NO RNO b. Restore power to block valves NG01BBR3 for BB HV-8000A NOTE: Power was purposely removed earlier in Event 2, it is expected that the crew will leave power removed

c. RCS Pressure <2185 psig.

BOP 12. Check Normal PZR Spray Valves - CLOSED - YES BOP 13. Check PZR Safety Valves - CLOSED - YES BOP 14. Check If RCPs Should Be Stopped: - NO

a. Check RCPs - ANY RUNNING

b. Check RCS Pressure <1400 PSIG

c. Check ECCS pumps - AT LEAST ONE RUNNING

d. Check Operator Controlled cooldown - NOT IN PROGRESS

e. Stop all RCPs RNO: Go to Step 15.

BOP 15. Direct Operator To Monitor Critical Safety Functions Using EMG F-0, CRITICAL SAFETY FUNCTION STATUS TREES (CSFST).

Appendix D 16 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior BOP 16. Check If S/Gs Are Not Faulted:

a. Check pressures in all S/Gs o NO S/G PRESSURE DECREASING IN AN UNCONTROLLED MANNER - YES o NO S/G COMPLETELY DEPRESSURIZED - YES Simulator Operator: IF contacted as Health Physics acknowledge requests.

BOP 17. () Check If S/G Tubes Are Intact:

o Check S/G Levels - NOT RISING IN AN UNCONTROLLED MANNER - NO RNO: Perform the following:

a. Direct Health Physics to survey steamlines in Area 5 of the Auxiliary Building.

b. Ensure BIT Inlet and Outlet Valves are open o EM HIS-8803A o EM HIS-8803B o EM HIS-8801A o EM HIS-8801B

c. N/A for A S/G

d. Go to EMG E-3, STEAM GENERATOR TUBE RUPTURE, Step 1 CRS Enters and directs EMG E-3 without transition brief.

EMG E-3, STEAM GENERATOR TUBE RUPTURE (Rev 34B)

NOTE o Foldout page shall be monitored throughout this procedure.

o Seal Injection flow shall be maintained to all RCPs.

1. Check if RCPs should be Stopped: - NO

a. Check RCPs - ANY RUNNING

b. Check RCS Pressure <1400 PSIG BOP c. Check ECCS pumps - AT LEAST ONE RUNNING

d. Check Operator Controlled cooldown - NOT IN PROGRESS

e. Stop all RCPs RNO: Go to Step 2.

CAUTION If steamlines are NOT intact, extreme caution will be necessary when performing local surveys.

BOP 2. Identify A S/G as Ruptured.

Appendix D 17 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior Simulator Operator: WHEN contacted to close AB-V062, THEN INSERT Key 6. Report back valve is closed.

BOP 3. Isolate Flow from A Ruptured S/G.

a. Adjust A S/G ARV setpoint to 1160 psig.

b. Check Ruptured S/Gs ARV - CLOSED

c. N/A for A S/G

d. Locally isolate main steamline low point drain valve(s) from ruptured S/G(s).

Close AB-V062 For S/G A BOP 4. Verify Blowdown, Lower, and Upper Sampling Isolated on Ruptured S/G(s): - YES

BM HIS-1A

BM HIS-19

BM HIS-35 CAUTION At least one S/G shall be maintained available for RCS cooldown.

Simulator Operator:

o IF Applicant goes to SA-057A/B cabinets, booth operator reports fuses have been pulled.

o IF contacted to perform EMG E-3, ATTACHMENT B, acknowledge requests.

5. Isolate Steamline On Ruptured S/G(s):

a. Close main steamline isolation valve.

AB HIS-14 For S/G A - NO RNO: Perform the following:

1. Ensure main steamline isolation valves closed.

AB HS-79 OR AB HS-80 BOP CT 2: Isolate an intact S/G from the ruptured S/G prior to exiting EMG E-3, or attempting to perform a controlled RCS cooldown.

2. IF ruptured S/G MSIV is NOT closed OR a MSIV associated with at least one intact S/G is NOT closed, THEN in SA057A or SA075B, disconnect A and B solenoid fuses (4 fuses total) for the affected valve(s):

Fuses for AB HV-14 (NOTE: While not procedurally required to pull fuses, they may choose to do so.)

3. Ensure MS ISO BYPASS VLVS CTRL is in MAN with 0% output.

o AB HIK MAN / 0%

4. IF ruptured S/G MSIV is NOT closed, THEN:

a) Isolate steam header using Attachment A, MAIN STEAM HEADER ISOLATION - CONTROL ROOM, while continuing with this procedure.

(NOTE: See page 23 for Attachment A Actions)

Appendix D 18 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior BOP b) Direct operator to locally isolate steam header, using Attachment B, MAIN STEAM HEADER ISOLATION - LOCAL

5. Use intact S/G ARVs for steam dump.

6. IF at least one S/G MSIV and its associated Bypass Valve are NOT closed, THEN go to EMG C-31, SGTR WITH LOSS OF REACTOR COOLANT -

SUBCOOLED RECOVERY DESIRED, Step 1.

NOTE: Crew may transition to EMG C-31 at this step. (See page 24 for this procedure flowpath)

CAUTION If any ruptured S/G is also faulted and the affected S/G is not needed for RCS cooldown, feed flow to that S/g shall remain isolated during subsequent recovery actions.

BOP 6. Check if Feed Flow should be isolated to Ruptured S/G(s)

a. Check Ruptured S/G(S) NR >6% [29%] - YES BOP 7. Stop Feed Flow to Ruptured S/G(s)

a. Close affected S/G(s) MD AFP Flow Control Valve(s).

o AL HK-7A for S/G A

b. Close affected S/G(s) TD AFP Flow Control Valve(s).

o AL HK-8A for S/G A BOP 8. Verify Ruptured S/G(s) Isolation

a. Check Ruptured S/G(s) - NOT NEEDED FOR RCS COOLDOWN-Yes

b. Verify Ruptured S/G(s) steamline has been isolated from at least one intact S/G:

MSIV And Bypass Valve On At least one intact S/G CLOSED -

Yes

c. Check MSIV and Bypass Valve on Ruptured S/G(s) - CLOSED -

NO RNO DO NOT CONTINUE until Attachment A, MAIN STEAM HEADER ISOLATION - CONTROL ROOM is complete.

d. N/A (TDAFW Steam Supply NOT from A S/G)

CAUTION N/A, (Not at EOL)

BOP 9. Check Ruptures S/G(s) Pressure >380 PSIG - YES

Appendix D 19 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior NOTE If high steam pressure rate setpoint (100 psi/50 sec) is exceeded after low steamline pressure SI signal is blocked, main steamline isolation will occur.

BOP 10. Check if Low Steamline Pressure SI should Be Blocked:

a. Check RCS Pressure <1970 psig o P-11 Light - LIT RNO: WHEN RCS Pressure is <1970 psig, THEN block low steamline pressure SI. Continue with step 11.

b. Block low steamline pressure SI.

o SB HS-9 o SB HS-10 BOP 11. Determine Target Plant Conditions From Table Below:

CAUTION N/A (RCPs are running)

NOTE o After Operator initiated RCS cooldown has started, RCP trip criteria no longer applies.

o Once the maximum rate cooldown is started, it must be maintained until the target temperature is reached.

BOP 12. Determine Method Used to Cooldown RCS At Maximum Rate:

a. Check Steam Dumps - AVAILABLE. - NO, RNO Go to step 14.

Appendix D 20 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior BOP 14. Perform RCS Cooldown Using ARVs.

a. Check Intact S/G(s) AVAILABLE:

1) Dump steam at maximum rate:

Use Intact S/G ARVs In Manual at 100%.

b. Adjust controller setpoint of each ARV used for cooldown to a value < setpoint target value from step 11.

AB PIC-2A for S/G B

AB PIC-3A for S/G C

AB PIC-4A for S/G D

c. Check RCS Temperature <Target Temperatures

Core Exit TCs (or RCS Hot Leg RTDs) - NO RNO Perform the following:

1) WHEN RCS temperature is < target temperature, THEN perform Step 14.d.

2) Go to Step 15.

d. Check Automatic Temperature Control Desired

1) Place ARV controller IN AUTO.

2) Adjust ARV controllers, as needed, to maintain RCS temperature < target temperature.

BOP 15. Check Intact S/G Levels:

a. Check NR Level in at least 1 S/G >6% [29%]

RNO Maintain total feed flow >270,000 lbm/hr, until NR level

>6%[29%] in at least one S/G.

b. Control feed flow to maintain NR level in all S/Gs between 29%

[29%] and 50%.

CAUTION If any PZR PORV opens becomes of high PZR pressure, the PORV shall be monitored to ensure it recloses after pressure lowers to <2335 psig.

RO 16. Check PZR PORVs And Block Valves:

a. Power To Block Valves - AVAILABLE o BB HIS-8000A o BB HIS-8000B

b. PZR PORVs - CLOSED o BB HIS-455A o BB HIS-456A

c. RCS Pressure <2185 psig.

RO 17. Check PZR Safety Valves - CLOSED o BB ZL-8010A o BB ZL-8010B o BB ZL-8010C

Appendix D 21 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior CAUTION If offsite power is lost after SI reset, manual action may be required to restore safeguards equipment to the required configuration.

RO 18. Reset SI:

o SB HS-42A o SB HS-43A RO 19. Reset Containment Isolation Phase A an Phase B:

o SB HS-56 For Phase A o SB HS-53 For Phase A o SB HS-55 For Phase B o SB HS-52 For Phase B NOTE Locally opening EF HV-43, ESW A TO AIR COMPRESSOR or EF HV-44, ESW B TO AIR COMPORSSOR requires the associated ESW Train to be declared INOPERABLE. Local opening of the valve, on 200 NORTH END AUX BLDG, will preclude it from automatically isolating on a high flow conditions.

20. Verify Instrument Air Compressor is Running: - NO

a. Ensure At Least One ESW TRN TO AIR COMPRESSOR Valve -

OPEN o EF HIS-43 o EF HIS-44

b. Check AIR COMPRESSOR BRKR RESET Switch Associated With Open ESW Valves(s) CLOSED o KA HIS-3C o KA HIS-2C RNO Reset and Close AIR COMPORESSOR BRKR RESET BOP Switch o KA HIS 3C o KA HIS-2C

c. Check INST AIR PRESS >105 psig KA PI-40

d. N/A NOT locally opened

e. Check Both ESW TRN TO AIR COMPORESSOR Valves - OPEN o EF HIS-43 o EF HIS-44

f. Check Both AIR COMPRESSOR BRKR RESET Switches -

CLOSED o KA HIS-3C o KA HIS-2C

21. Verify Instrument Air to Containment:

a. Check PZR PRESS MASTER CTRL Output <55%

BOP o BB PK-455A

b. Open INST AIR SPLY CTMT ISO VLV.

o KA HIS-29

Appendix D 22 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior CAUTION After RHR Pumps have been stopped, RCS pressure shall be monitored for RHR Pump restart criteria.

22. Check if RHR Pumps should be stopped.

a. Check RHR Pumps - ANY RUNNING - YES

b. Check RHR System - ALIGNED FOR INJECTION - YES

c. Check RCS Pressure >325 psig - YES RO d. Stop RHR Pumps and place in standby.

o EJ HIS-1 o EJ HIS-2

e. Check RCS pressure >325 psig during subsequent recovery actions.

23. Check If RCS Cooldown Should Be Stopped:

BOP a. Check RCS Temperatures <Target Temperature

Core Exit TCs (Or RCS Hot Leg RTDs)

24. Check Ruptured S/G Pressure Stable or rising RNO: IF ruptured S/G pressure is <250 psig above the pressure of the intact S/Gs used for cooldown, THEN go to EMG C-31, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

NOTE: Depending on crew progress through the procedure, Ruptured S/G pressure might meet criteria to transition to EMG C-31 at this step.

See page 24 for EMG C-31steps.

25. Check RCS Subcooling >50F [65F].

RNO: Go to EMG C-31, SGTR WITH LOSS OF REACTOR COOLANT -

SUBCOOLED RECOVERY DESIRED, Step 1.

26. Depressurize RCS Using Normal Spray To Minimize Break Flow and Refill PZR:

a. Verify Normal PZR Spray - AVAILABLE - YES

RCP D Running

b. Spray PZR with maximum available spray, until any of the following conditions satisfied:

PZR Level - >76% [62%] OR CT 3: Commence controlled RCS depressurization to allow for SI termination prior to overfilling the ruptured S/G (90% WR).

RCS Subcooling <30F [ 45F] OR

Both of the following:

1) RCS Pressure <Ruptured S/G Pressure

2) PZR Level >6% [32%]

Appendix D 23 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior OR

Both of the following:

1) RCS Pressure - WITHIN 300 PSIG OF RUPTURES S/Gs PRESSURE

2) PZR Level >36% [50%]

Scenario termination: After the crew has commenced depressurizing the RCS, and/or at the direction of the Lead Examiner.

Simulator Operator: FREEZE Simulator.

EMG E-3, ATTACHMENT A - MAIN STEAM HEADER ISOLATION - CONTROL ROOM BOP A1. Ensure Main Turbine Stop Valves - CLOSED - YES BOP A2. Ensure MFW Pumps - Tripped - YES BOP A3. Close Condenser Steam Dump Valves

a. Set intact S/G ARV controller setpoints to 1125 psig.

b. Place Steam Dump Bypass Interlock Switches in off position.

o AB HS-63 o AB HS-64

c. Ensure Condenser Steam Dump Valves - CLOSED - YES BOP A4. Close Main Steam Supply to MSR 2nd Stage Valves.

o AB HIS-32 BOP A5. Transfer Steam Seal Supply to Aux Steam

a. Check Aux Steam AVAILABLE. - NO RNO: Break Vacuum:

1. Open condenser vacuum breaker valves o AD HIS-113

2. Place all Condenser Vacuum Pumps in pull-to-lock position.

o CG HIS-1 o CG HIS-2 o CG HIS-3

3. Close Main Steam To Steam Seal System o AB HIS-46

4. Close Steam Seal System Auxiliary Steam Supply Valve o CA HIS-4

5. Go to Step A6.

RO A6. Return to Procedure and Step in Effect.

Appendix D 24 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior EMG C-31, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED (Rev 25A)

CAUTION If offsite power is lost after SI reset, manual action may be required to restore safeguards equipment to the required configuration.

NOTE Foldout page shall be monitored throughout this procedure.

1. Reset SI RO o SB HS-42A o SB HS-43A

2. Reset CIS Phase A and Phase B o SB HS-56 for Phase A RO o SB HS-53 for Phase A o SB HS-55 for Phase B o SB HS-52 for Phase B BOP 3. Verify Instrument Air Compressor is Running: - YES

4. Verify Instrument Air to Containment:

a. Check PZR PRESS MASTER CTRL Output <55%

BOP o BB PK-455A

b. Open INST AIR SPLY CTMT ISO VLV.

o KA HIS-29

Appendix D 25 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior Simulator Operator: IF contacted as TB Watch to place A and B EDGs in Standby using SYS KJ-121, THEN acknowledge the report. Insert Key 7 and Key 8, When Scenario File complete, report both EDG A and B are in standby.

5. Check if Diesel Generators Should Be Stopped.

RO

a. Check NB01 - ENERGIZED BY OFFSITE POWER - YES

b. Depress START/RESET pushbutton for Diesel Generator NE01.

o KJ HS-8A

c. Depress STOP pushbutton for Diesel Generator NE01 o KJ HS-8A

d. Place EDG NE01 in standby using SYS KJ-121, DIESEL GENERATOR NE01 AND NE02 LINEUP FOR AUTOMATIC OPERATION, while continuing with this procedure.

e. Check NB02 - ENERGIZED BY OFFSITE POWER - YES

f. Depress START/RESET pushbutton for Diesel Generator NE02.

o KJ HS-108A

g. Depress STOP pushbutton for Diesel Generator NE02 o KJ HS-108A

h. Place EDG NE02 in standby using SYS KJ-121, DIESEL GENERATOR NE01 AND NE02 LINEUP FOR AUTOMATIC OPERATION, while continuing with this procedure.

CAUTION PZR heaters shall not be energized until PZR water level indicates greater than minimum recommended by the TSC to ensure heaters are covered.

Simulator Operator: IF contacted as TSC, acknowledge request to determine minimum PZR Water level that will ensure heaters are covered.

6. Deenergize PZR Heaters:

RO

a. Place PZR B/U heater switches in trip and PZR CTRL Heaters in PTL position.

o BB HIS-51A, o BB HIS-52A o BB HIS-50

b. Direct TSC to determine minimum PZR water level that will ensure PZR heaters are covered.

Appendix D 26 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior Simulator Operator:

o WHEN contacted as Turbine building watch to close BAT Pump Breakers, acknowledge request.

Insert Key 9. WAIT 1 Minute and report breakers closed.

o WHEN contacted as Aux building watch to close emergency borate valve, acknowledge request.

Insert Key 10. WAIT 1 Minute and report breaker closed.

7. Load Equipment on Energized AC Emergency Busses:

RO

a. Locally reset and close Boric Acid Transfer Pump breakers.

o NG01AHF4 for Pump A o NB02AAF4 for Pump B

b. Locally reset and close Emergency Borate Valve breaker.

o NG04CPF2 for BG HV-8104

8. Restore Power to PZR Backup Heaters:

RO

a. Check NB01 ENERGIZED BY OFFSITE POWER - YES

b. Close Supply Breaker for PG 21.

o PG HIS-19

c. Check NB02 ENERGIZED BY OFFSITE POWER - YES

d. Close Supply Breaker for PG 22.

o PG HIS-21

9. Close Non-Class 1E Battery Charger Breakers:

RO o PK HIS-2 For PK-21 o PK HIS-3 For PK-22 o PK HIS-4 For PK-23 o PK HIS-5 For PK-24

10. Check All Non-Class 1E AC Busses And Load Centers - ENERGIZED RO BY OFFSITE POWER - YES

11. Check if Containment Spray should be Stopped.

RO

a. Check Spray Pumps - ANY RUNNING - NO RNO Go to Step 12.

12. Check Ruptured S/G(s) Level:

BOP

a. Check Ruptured S/Gs Pressure: NOT DECREASING IN AN UNCONTROLLED MANNER, or NOT COMPLETELY DEPRESSURIZED - YES

b. Check Ruptured S/G NR Level > 6% -

RNO Perform the following:

1) Maintain feed flow to ruptured S/G, until level >6%

2) WHEN ruptured S/G level > 6%, THEN stop feed flow to ruptured S/Gs.

3) Continue with Step 13.

Appendix D 27 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior CAUTION After RHR Pumps have been stopped, RCS pressure shall be monitored for RHR Pump restart criteria.

13. Check of RHR Pumps Should Be Stopped:

RO

a. Check RHR Pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST - YES.

b. Check RCS Pressure:

1) Pressure >325 psig - YES

2) Pressure Stable or Rising - YES

c. Stop RHR Pumps and place in standby.

o EJ HIS-1 o EJ HIS-2

d. Check RCS Pressure >325 psig during subsequent recovery actions.

14. Align CCW To Sampling Systems:

RO

a. Open CCW To Radwaste System Isolation Valves.

o EG HS-69 o EG HS-70

15. Place Hydrogen Analyzers Inservice:

RO

a. On RL011, place power lockout switches for containment sample valves in NON-ISO position.

o GS HIS-40 o GS HIS-41 o GS HIS-42 o GS HIS-43

b. On RL011, open one Hydrogen Anal7yzer Supply Inner Containment Isolation Valve per Train o GS HIS-13 or GS HIS-14 for Red Train.

o GS HIS-4 Or GS HIS-5 for Yellow Train.

c. On RL011, open remaining hydrogen analyzer containment isolation valves.

o GS HIS-12 o GS HIS-17 o GS HIS-18 o GS HIS-3 RO o GS HIS-8 o GS HIS-9

d. On RL020, place containment hydrogen analyzer controls witches in ANALYZE position.

o GS HIS-16A o GS HIS-11A

e. On RL020, monitor containment hydrogen concentration.

o GS AI-19 o GS AI-10

Appendix D 28 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior Simulator Operator: IF contacted as Health Physics, acknowledge requests.

16. Check Fuel / Auxiliary Building Radiation - NORMAL: - YES BOP

a. Shift Fuel/Auxiliary Building Exhaust sample to EMERGENCY o GG HIS-27 o GG HIS-28

b. Direct Health Physics to survey Fuel and Auxiliary Buildings with priority being pipe penetration areas and piping tunnels.

c. Check Fuel/Auxiliary Building radiation monitors - NONE ALARMING Simulator Operator: IF contacted as Chemistry, acknowledge requests.

17. Obtain Samples:

BOP

a. Request Chemistry obtain boron and activity samples.

18. Initiate Evaluation of Plant Status:

CRS

a. Evaluate plant equipment to ensure availability:

b. Start additional plant equipment, as necessary to assist in recovery:

NOTE: Lead Examiner prompt CRS that the Shift Manager is performing this evaluation, if asked or if CRS attempts to perform.

BOP 19. Check if S/Gs are NOT Faulted. - YES

20. Check Intact S/G Levels:

BOP

a. Check NR Level in at least one S/G >6%

RNO Maintain total feed flow >270,000 lbm/hr, until NR Level >6%

in at least one S/G.

b. Control feed flow to maintain NR level in all S/Gs between 29%

and 50%.

21. Check if Condenser Air Removal Should Be Returned to Normal:

BOP

a. Check the following:

o MSIVs - AT LEAST ONE OPEN - NO, ONLY THE RUPTURED S/G MSIV IS OPEN o Condensate Pumps - AT LEAST ONE RUNNING o Circulating Water Pumps - AT LEAST ONE RUNNING o Condenser Vacuum - ESTABHLISHED RNO Go to Step 22 NOTE If high steam pressure rate setpoint (100 psi/50 sec) is exceeded after low steamline pressure SI signal is blocked, main steamline isolation will occur.

Appendix D 29 Form ES-D-2 Op Test No: 11/2017 Scenario No: 3 Events No: 5 / 6 / 7 Total No Pages 53 Event

Description:

SGTR on A S/G with A MSIV Failed Open / Turbine Fails to Trip in Auto

/ B ESW Pump Fails to Auto Start.

Time Position Applicants Actions or Behavior

22. Check if Low Steamline Pressure SI Should Be Blocked:

RO

a. Check RCS Pressure <1970 spig o P-11 Light - LIT RNO WHEN RCS pressure is <1970 psig, THEN block low steamline pressure SI. Continue with Step 23.

b. Block Low steamline Pressure SI.

o SB HS-9 o SB HS-10

23. Initiate RCS Cooldown to Cold Shutdown:

BOP

a. Maintain Cooldown Rate In RCS Cold Legs <100°F/hr.

b. Check RHR System in SHUTDOWN COOLING MODE - NO RNO Go to Step 23.d.

d. Check Steam Dumps - AVAILABLE - NO RNO Perform the following:

1) Manually dump steam from intact S/Gs:

Use S/G ARV

2) N/A (Intact S/Gs are available)

3) Go to Step 24.

24. Check if subcooled recovery is appropriate: - YES CRS

a. Check RWST Level >69%

b. Check Ruptured S/G NR Level <93%

25. Check RCS Subcooling - >30°F RO

26. Check the Following Conditions - ANY SATISFIED RO

SI Pumps - ANY RUNNING - YES OR

BIT - NOT ISOLATED - YES

27. Depressurize RCS to Refill PZR:

RO

a. Check PZR Level <20%

b. Check Normal PZR Spray AVAILABLE - YES

c. Depressurize using normal PZR Spray CT 3: Commence controlled RCS depressurization to allow for SI termination prior to overfilling the ruptured S/G (90% WR).

d. Check PZR Level >20%

RNO WHEN level >20%, then perform Step 27.e. Continue with Step 28

e. Stop RCS depressurization by closing normal spray valves.

Scenario termination: After the crew has commenced depressurizing the RCS, and/or at the direction of the Lead Examiner.

Simulator Operator: FREEZE Simulator.

Appendix D 30 Form ES-D-2 Attachment 1 (Page 1 of 7)

Appendix D 31 Form ES-D-2 Attachment 1 (Page 2 of 7)

Appendix D 32 Form ES-D-2 Attachment 1 (Page3 of 7)

Appendix D 33 Form ES-D-2 Attachment 1 (Page4 of 7)

Appendix D 34 Form ES-D-2 Attachment 1 (Page5 of 7)

Appendix D 35 Form ES-D-2 Attachment 1 (Page 6 of 7)

Appendix D 36 Form ES-D-2 Attachment 1 (Page 7 of 7)

Appendix D 37 Form ES-D-2 Attachment 2 (Page 1 of 2)

Appendix D 38 Form ES-D-2 Attachment 2 (Page 2 of 2)

GO TO FR-S1 Appendix D GO TO FR-S1 IS POWER RANGE NO LESS THAN 5%

[GAMMA METRICS LESS THAN 5%]? YES GO TO FR-S2 IS INTERMEDIATE RANGE NO STARTUP RATE ZERO OR NEGATIVE [GAMMA METRICS IS INTERMEDIATE RANGE NO STABLE OR DECREASING]? YES STARTUP RATE MORE NEGATIVE THAN-0.2 DPM[GAMMA METRICS STABLE OR DECREASING]? YES 39 CSF SAT NO IS SOURCE RANGE ENERGIZED?

YES GO TO FR-S2 (Page 1 of 1)

IS SOURCE RANGE NO STARTUP RATE ZERO OR NEGATIVE [GAMMA METRICS STABLE OR DECREASING]? YES CSF SAT F-01 SUBCRITICALITY Form ES-D-2

GO TO FR-P1 ARE ALL RCS PRESSURE/COLD NO LEG TEMPERATURE POINTS Appendix D TO THE RIGHT OF LIMIT A? GO TO (REFER TO FIGURE 5) YES FR-P1 ARE ALL RCS COLD LEG NO TEMPERATURES GO TO GREATER THAN 240OF (T1)? YES FR-P2 ARE ALL RCS COLD LEG NO TEMPERATURES GREATER THAN 270OF (T2)? YES CSF WAS TEMPERATURE DECREASE SAT IN ALL RCS COLD LEGS NO LESS THAN 100OF IN LAST 60 MINUTE PERIOD? YES GO TO 40 FR-P1 ARE ALL RCS COLD LEG NO TEMPERATURES GREATER THAN 240OF (T1)? YES (Page 1 of 1)

IS RCS PRESSURE NO LESS THAN COLD GO TO OVERPRESSURE LIMIT? FR-P2 (REFER TO FIGURE 5) YES ARE ALL RCS COLD LEG NO TEMPERATURES CSF GREATER THAN SAT 375OF? YES CSF SAT F-04 INTEGRITY Form ES-D-2

Appendix D 41 Form ES-D-2 Attachment 5 (Page 1 of 13)

Appendix D 42 Form ES-D-2 Attachment 5 (Page 2 of 13)

Appendix D 43 Form ES-D-2 Attachment 5 (Page 3 of 13)

Appendix D 44 Form ES-D-2 Attachment 5 (Page 4 of 13)

Appendix D 45 Form ES-D-2 Attachment 5 (Page 5 of 13)

Appendix D 46 Form ES-D-2 Attachment 5 (Page 6 of 13)

Appendix D 47 Form ES-D-2 Attachment 5 (Page 7 of 13)

Appendix D 48 Form ES-D-2 Attachment 5 (Page 8 of 13)

Appendix D 49 Form ES-D-2 Attachment 5 (Page 9 of 13)

Appendix D 50 Form ES-D-2 Attachment 5 (Page 10 of 13)

Appendix D 51 Form ES-D-2 Attachment 5 (Page 11 of 13)

Appendix D 52 Form ES-D-2 Attachment 5 (Page 12 of 13)

Appendix D 53 Form ES-D-2 Attachment 5 (Page 13 of 13)

Appendix D Scenario Outline Form ES-D-1 Facility: _Wolf Creek_________ Scenario No.: ___4________ Op-Test No.: ___1______

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 2% power. A MFP in service. Power ascension on hold due to emergent work on A CCP. A CCP tagged out. LCO. 3.5.2 Condition A entered. Estimate return in 30 minutes. Both CCW trains are in service with CCW Pumps A and B running, with Service Loop aligned to B train.

Turnover: Maintain current power level while the crew briefs for the upcoming MODE Change. Swap Operating Spent Fuel Pool (SFP) Cooling Pumps to support Mechanical Maintenance on B SFP Cooling Pump.________________________________________________________________

Critical Tasks: CT-1, Manually Actuate Safety Injection. CT-2, Manually Start CCW Pump D.

CT-3, Isolate LOCA outside Containment by closing EJ HIS-8701A.

Event Malf. Event Type* Event No. No. Description 1 N (SRO/BOP) Swap Running SFP pumps per SYS EC-120 2 TS (SRO) Dual Data Failure on one Shutdown Bank Rod (TS) 3 C (SRO/BOP) A Main Feed Reg Bypass valve fails open 4 C (SRO/RO) Letdown HX BG TCV-130 controller fails closed in Auto I (SRO/ RO) 5 PZR Press instr BB PI-456 fails high, PORV Opens (TS)

TS (SRO) 6 M (ALL) SSE Earthquake, RCS leak to RHR system outside CTMT 7 C (SRO/RO) SI fails to Auto actuate 8 C (SRO/BOP) CCW Pump B trips on SI, CCW Pump D fails to Auto start

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. Entry into a contingency EOP with substantive actions (> 1 1 per scenario set)

6. Pre-identified critical tasks (> 2) 3

Appendix D Scenario Outline Form ES-D-1 Measurable Performance Critical Task Safety Significance Cueing Performance Feedback Indicators CT-1 Manually Failure to manually PRZR pressure Manipulation Indication and/or actuate at least one actuate SI under the less than SI of Either: annunciation that train of SI before postulated conditions actuation setpoint.

SB HS- at least one train any of the following: constitutes 27 or of SI is actuated:

PRZR water level

Transition to misoperation or

SB HS-28 Annunciator less than the any EMG E-1 incorrect crew to manually 030A or 031A, foldout page series, EMG E- performance in which actuate at Red SI Actuate criterion for SI 2 series, or the crew does not least one train Light on Panel actuation.

EMG E-3 series prevent degraded of SI. SB 069 procedure or No indication or emergency core transition to any annunciation that cooling system FRG. SI is actuated (ECCS)capacity.

Completion of Step 16 of EMG ES-02.

CT-2 Manually start Failure to maintain Indication and/or Manipulation CCW low D CCW pump prior CCW flow to ECCS annunciation that of EG HIS-24 pressure to transition out of components results SI is actuated to start D condition clear; EMG E-0, or in a reduction of CCW Pump. indication of AND completion of safety margin. Red pressure Train ECCS Indication and/or CCW low flow Attachment F, equipment is annunciation that condition clear; whichever occurs degraded due to less than the indication of flow; later.

LOCA outside minimum number Red running light Containment through of CCW pumps on EG HIS-24.

Loop Hot Leg to required to provide RHR Pump A adequate Suction Isolation component cooling Valve, requiring for the operating Yellow Train CCW safeguards train(s) for Safe Shutdown. are running CT-3 Isolate the Failure to isolate a Indication and/or Manipulation Indication of LOCA outside LOCA outside annunciation that of EJ HIS- rising RCS containment before containment SI is actuated and 8701A to pressure transition out of degrades is required isolate the EMG C-12. containment integrity LOCA AND beyond the level of degradation Indication and/or irreparably annunciation of introduced by the abnormally high postulated radiation in the conditions. auxiliary building Note: Causing an unnecessary plant trip or ESF actuation may constitute a Critical Task failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Appendix D Scenario Outline Form ES-D-1 SCENARIO NARRATIVE Initial Conditions: 2% power. A MFP in service. Power ascension on hold due to emergent work on A CCP. A CCP tagged out. LCO. 3.5.2 Condition A entered. Estimate return in 30 minutes. Maintain current power level while the crew briefs for the upcoming MODE Change.

Event 1: Swap Running SFP pumps from B to A per SYS EC-120. Crew turnover includes direction to swap operating Spent Fuel Pool (SFP) Cooling Pumps to support mechanical maintenance on B SFP Cooling Pump. A copy of SYS EC-120, FUEL POOL COOLING AND CLEANUP SYSTEM STARTUP will be provided with instructions to perform section 6.1, starting with step 6.1.3. Maintenance has NOT just been performed on the A SFP Cooling Pump and SFP Cleanup System is NOT in service.

Event 2: Dual Data Failure on one Shutdown Bank Rod. Numerous alarms associated with rod control.

080A, RPI URG ALARM is the higher tier alarm and should be entered by the SRO. DRPI indication will show General Warning (GW) and Rod Bottom (RB) lights for shutdown rod N11. There are no verifiable actions for the board operators. The SRO will review and enter T.S. 3.1.4, Condition B, T.S. 3.1.7, Condition A, and review T.R. 3.1.7, which is N/A for this Mode.

Event 3: A MFRV Bypass valve fails open. Level in A S/G rises. Annunciator 108B, SG A LEV DEV will alarm if level gets to 55%. SRO should perform ALR 108B. There is no OFN guidance for this failure.

At this low power and low flows this will be a slow moving event.

Event 4: Letdown HX BG TCV-130 controller fails closed in Auto. Temperature will rise on BG TI-130 on MCB RL002. Annunciator 039B, LTDN HX TEMP HI, will alarm. 039A, LTDN HX TEMP HI DIVERT, may also alarm later. THE SRO should enter one of the ALRs. Direction form the ALRS is to place BG TCV-130 in manual and control temperature between 110 and 120°F.

Event 5: PZR Press instrument BB PI-456 fails high, PORV Opens. This is the lower controlling channel and will only affect PORV BB HIS-456A. Block valves will close at 2185 psig but will reopen when pressure rises above 2192 psig. Annunciator 039B, PORV OPEN will alarm. ALR has memory action to close PORV however SRO may enter OFN SB-008, INSTRUMENT MALFUNCTIONS, directly if the RO recognizes the channel failure. The RO should select P455/P458 on BB PS-455F to select out the failed channel. SRO will determine LCO 3.3.1, Conditions A, E, and M are applicable (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action) and LCO 3.3.2, Conditions A, D (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action) and L (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action to verify P-11 interlock is in correct state).

Event 6: SSE Earthquake, RCS leak to RHR system outside CTMT. The LOCA is delayed 10 seconds after the earthquake. The crew should observe PZR pressure and level lowering quickly and the SRO should order a reactor trip and safety injection. The crew should progress through EMG C-12 and close Loop Hot Leg to RHR Pump A Suction Isolation Valve EJ-HV-8701A to isolate the LOCA. When RCS pressure is noted to be rising, the scenario can be terminated at the Lead Examiners direction.

CT-3: Isolate the LOCA outside containment before transition out of EMG C-12 Event 7: SI fails to Auto actuate. Manual is available. Crew will manually actuate SI, either with pre-emptive action or as a manual backup to failed auto actuation during performance of immediate actions.

CT-1: Manually actuate at least one train of SI before any of the following:

Transition to any EMG E-1, EMG E-2, or EMG E-3 series procedure or transition to any FRG.

Completion of Step 16 of EMG ES-02.

Event 8: CCW Pump B trips on SI, CCW Pump D does not auto start. The BOP may identify and correct the deficiency following performance of immediate actions, or the RO will have procedure guidance to verify correct CCW System alignment when performing EMG E-0, ATTACHMENT F.

CT-2: Manually start at least one CCW pump in the train with required ECCS equipment prior to transition out of EMG E-0, or completion of Attachment F, whichever occurs later.

Note: Causing an unnecessary plant trip or ESF actuation may constitute a CT failure. Actions taken by the applicant(s) will be validated using the methodology for critical tasks in Appendix D to NUREG-1021.

Appendix D Scenario Outline Form ES-D-1

2017 ILO Scenario #4

Initial Conditions - Tag Out 'A' CCP scn SimGroup\Tag A CCP

Initial Conditions - Position EJ HV-8701A, Ack alarm when done

+1 ICM movEJHV8701A t:4 f:0.2 d:0 r:0

+03 ICR movEJHV8701A t:1 d:0

+4 ICR movEJHV8701A t:0 d:0

+2 IMF ANN-B049 f:1

Event 1 - No Keys

Event 2 - [Key 2] DRPI Failure Shutdown Rod N11 IMF mSF10N11 f: 2 k:2

Event 3 - [Key 3] 'A' MFRV Bypass fails open IMF mAE20A f: 99.1 r:10 k:3

Event 4 - [KEY 4] BG TCV-130 fails closed IMF mBG18A f: 0 r:10 k:4

Event 5 - [Key 5] BB PI-456 fails high IMF mBB21B f: 2508 r:10 k:5

Event 6 - [Key 6] SSE Earthquake, RCS Leak to RHR and pipe rupture IMF mSG01 f: 60 k:6 ICM vlBBPV8702A t:1 f:0.02 d:10 r:0 k:6 IMF mEJ04A f:3500 d:10 k:6

Local Remote Action - [Key 7] Restore Power to Loop Isolation Valves

{Key[7]}DCM movEJHV8701A ICR movBBPV8702A t:1 d:0 k:7 ICR movBBPV8702B t:1 d:3 k:7 ICR movEJHV8701A t:1 d:30 k:7 ICR movEJHV8701B t:1 d:33 k:7 IOR P17091A f:1 k:7

Event 7 - automatic SI fails - No Key IMF mSA14B f: 1 IMF mSA14A f:1

Event 8 - 'B' CCW trips on SI, 'D' does not auto start - No Key

{jpplsi}ICM bkrDPEG01B t:1 d:0 IMF mEG14D f:-1

Appendix D 1 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 1 Total No Pages 31 Event

Description:

Swap Running SFP pumps from B to A per SYS EC-120 Time Position Applicants Actions or Behavior Simulator Operator: Crew should perform SYS EC-120 upon assumption of watch per pre-shift brief.

BOP Uses SYS EC-120 to perform pump swap starting with Step 6.1.3 SYS EC-120, FUEL POOL COOLING AND CLEANUP SYSTEM STARTUP (Rev 56) 6.1.3 IF Starting Fuel Pool Cooling Pump A, THEN PERFORM the following:

1. ENSURE A CCW Train is inservice.

2. ENSURE EC HV-11 is open, using EC HIS-11, SFP HX A CCW OUTLET VLV.

o EC HIS OPEN

3. N/A (Not starting pump after maintenance)

BOP

4. START SFP COOL PUMP A, using EC HIS-27, SFP COOL PUMP A.

o EC HIS NORMAL-AFTER-RUN

5. VERIFY EC FI-17A, SFP COOL PUMP A DISCH FLOW >722,000 lbm/hr.

o EC FI-17a - >722,000 lbm/hr.

6. N/A (Proper flow obtained.)

Simulator Operator: WHEN contacted as Aux Building Watch to verify fuel pool cooling HX outlet temperature, Report temperature is 73°F

7. Locally Verify EC TI-13, FUEL POOL CLG HX A OUT Temperature BOP is <125°F.

8. N/A (SFP Temp <125°F)

Simulator Operator: WHEN contacted as Aux Building Watch to VERIFY Fuel Pool Cooling Pump Room Cooler status, THEN Report A Pump Room Cooler is Running.

9. VERIFY Fuel Pool Cooling Pump Room Cooler is running.

BOP o SGG04A - RUNNING Simulator Operator: WHEN contacted as Aux Building Watch to Stop the B Fuel Pool Cooling Pump Room Cooler, THEN Wait 2 minutes and report B Pump Room Cooler is Stopped.

10. IF Spent Fuel Pool Cooling Pump B is running AND is NOT required, THEN PERFORM the following:

a. STOP SFP COOL PUMP B, using EC HIS-28, SFP COOL PUMP B.

o EC HIS NORMAL-AFTER-STOP

b. Locally at MCC, STOP B Fuel Pool Cooling Pump Room Cooler.

o NG04CEF1-STOPPED.

11. N/A (SFP Cleanup system NOT in service)

Event termination: After the crew has stopped SFP Cooling Pump B and room cooler and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 2 at direction of Lead Examiner.

Appendix D 2 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 2 Total No Pages 31 Event

Description:

Dual Data Failure on one Shutdown Bank Rod Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 2 at the lead evaluators direction.

Diagnostics: Multiple Rod control related alarms. DRPI will show General Warning (GW) and (Rod Bottom) lights for shutdown rod N11.

Annunciators: 080A-RPI URG ALARM, 080B-RPI NON URG ALARM, 080C-RPI ROD DEV Recognize using diverse indications that there is a failure of the rod Crew position indication system and NOT an actual dropped rod.

Enter and Direct ALR 00-080A, RPI URG ALARM and/or ALR 00-080C, RPI ROD DEV NOTE: ALR 00-080B, if referenced, directs performance of ALR 00-080A if CRS that alarm is in.

ALR 00-080A, RPI URG ALARM (Rev 7A)

1. Determine Affected Rod (s)Using DRPI LEDS:

o Rod at Bottom (N11)

RO o General Warning

2. Refer to Technical Specifications 3.1.4, 3.1.7 and TR 3.1.7.

CRS Determines:

o LCO 3.1.4, COND B is applicable - 1 Hour to verify SDM to be within the limits provided by the COLR (among other actions that would also satisfy requirements).

o LCO 3.1.7, COND A is applicable - Action to reduce THERMAL POWER TO <50% RTP in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is satisfied.

o TRM 3.1.7, is reviewed and found to be N/A (Shutdown CRS conditions).

Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

RO 3. Direct I&C To Determine and Correct Cause of DRPI Failure.

Crew 4. Return to Procedure and Step In Effect.

ALR 00-080C, RPI ROD DEV (Rev 8A)

1. Check for Turbine Runback: NO BOP RNO Go to Step 3.

3. Place SE HS-9 Bank Selector Switch in Manual Position - No action RO required.

4. Stabilize plant:

a. Stop any plant operations requiring rod motion.

RO b. N/A (Turbine not synced to grid.)

Appendix D 3 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 2 Total No Pages 31 Event

Description:

Dual Data Failure on one Shutdown Bank Rod Time Position Applicants Actions or Behavior

5. Check DRPI Has Not Failed:

Annunciator 00-080A, RPI URG ALARM - CLEAR - NO RNO: Perform the following:

a. IF plant is in MODEs 1 or 2, THEN refer to Technical Specification 3.1.7.

CRS Determines:

LCO 3.1.7, COND A is applicable - Action to reduce THERMAL POWER TO <50% RTP in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is satisfied.

b. N/A (Plant NOT in MODE 3,4,or 5)

CRS c. Go to ALR 00-080A, RPI URG ALRM, STEP 1.

Event termination: After the crew has requested troubleshooting help, the CRS has determined applicable Tech Specs and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 3 at direction of Lead Examiner.

Appendix D 4 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 3 Total No Pages 31 Event

Description:

A Main Feed Reg Bypass valve fails OPEN Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 3 at the lead examiners direction.

Diagnostics: Indicated flow and level on AE FR-510 trending UP. Actual feed flows on AE FI-510A, and -511A, and actual level on AE LI 517-519 trending UP. Feed Reg Bypass Valve Controller AE FK-550 Opens.

Annunciators: 108B-SG A LEV DEV, 108C-SG A FLOW MISMATCH Recognizes AE FK-550 is opening and takes Manual Control.

NOTE: It is expected per AP 21-001, CONDUCT OF OPERATIONS (Rev BOP 80) step 6.3.12.8, that the Operator takes manual control during equipment malfunctions which result in a transient and then inform the CRS.

Enters and directs ALR 00-108C, SG A FLOW MISMATCH NOTE: ALR 00-108B, SG A LEV DEV might also actuate based on CRS timeliness of BOP recognizing the flow deviation and taking manual control. The mitigation action to manually control the Main Feed Rev Bypass valve is the same in both ALRs.

ALR 00-108C, SG A FLOW MISMATCH (Rev 10)

NOTE Steps 1 through 3 are Memory Action steps.

1. Check Difference Between Steam Generator A Steam Flow And Feed Flow - GREATER THAN 0.7 MPPH - YES o AB FI-512A For Steam Flow BOP o AB FI-513A For Steam Flow o AE FI-510A For Feed Flow o AE FI-511A For Feed Flow

2. Check For Instruments Operating Properly: YES o Steam Generator A Controlling Steam Pressure Channel -

WITHIN 100 PSIG OF REMAINING CHANNELS

AB PI-514A BOP

AB PI-515A o Steam Generator A Controlling Feedwater Flow Channel -

WITHIN 0.2 MPPH OF OTHER CHANNEL o Steam Generator C Controlling Steam Flow Channel - WITHIN 0.2 MPPH OF OTHER CHANNEL

3. Restore Steam Generator A Level To Program Value:

a. Check Feedwater Control Valve - INSERVICE TO FEED S/G C o AE FK-510 - NO RNO Perform the following:

BOP

1) Place Feedwater Reg Bypass Control Valve in manual.

o AE LK-550

2) Adjust Feedwater Control Valve, as necessary, to maintain program value.

CRS Provides bounding order, including control band and target S/G level.

Appendix D 5 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 3 Total No Pages 31 Event

Description:

A Main Feed Reg Bypass valve fails OPEN Time Position Applicants Actions or Behavior Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

BOP 4. Check Secondary Plant Conditions - STABLE - YES

5. Check For S/G A Tube Leakage: None BOP RNO: Return to procedure and step in effect.

Event termination: After the crew has AE FK-550 in manual and controlling S/G level at or trending to program 50% level and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 4 at direction of Lead Examiner.

Appendix D 6 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 4 Total No Pages 31 Event

Description:

Letdown HX BG TCV-130 Controller Fails CLOSED in Auto.

Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 4 at the lead evaluators direction.

Diagnostics: Output on BG TK-130 trends to 100%. LTDN HX Outlet Temp BG TI-130 temperature rises out of green band (>120F), CVCS DEMIN INLET DIVERT VLV, BG HIS-129 shifts from DEMIN to VCT Position.

Annunciators: 039B-LTDN HX DISCH TEMP HI, 039A-LTDN HX TEMP HI DIVERT (maybe)

CRS Enters and directs either ALR 00-039B or ALR 00-039A ALR 00-039B, LTDN HX DISCH TEMP HI (Rev 8)

1. Check Letdown Heat Exchanger Outlet Temperature - >120F ATC o BG TI-130 - YES

2. Check Annunciator ALR 00-039A, LTDN HX TEMP HI DIVERT Clear ATC IF YES - Continue to Step 3 IF NO - RNO: Go to ALR 00-039A.

3. Check Letdown Heat Exchanger Outlet Temperature Control Valve -

FULLY OPEN (BG TK-130) - NO ATC RNO Perform the following:

a. Place valve in manual and establish temperature between 110°F and 120°F. - YES

4. Check Letdown Heat Exchanger Outlet Flow <120 GPM ATC o BG FI-132 - YES

5. Check Letdown Heat Exchanger Outlet Temperature LOWERING ATC o BG TI-130 -YES CRS 6. Return to procedure and step in effect.

ALR 00-039A, LTDN HX TEMP HI DIVERT (Rev 11)

1. Check Letdown Heat Exchanger Outlet Temperature >137°F ATC o BG TI-130 - YES (if they entered this ALR)

2. Check CVCS Demineralizer Inlet Divert Valve in VCT Position ATC o BG HIS-129 - YES

3. Check Annunciator 00-038A, LTDN REGEN HX TEMP HI - CLEAR -

ATC YES

4. Check Letdown Heat Exchanger Outlet Temperature Control Valve -

Responding Properly o BG TK-130 - NO ATC RNO: Perform the following:

a. Place valve in manual and establish temperature between 110°F and 120°F. - YES

5. Check Letdown Heat Exchanger Outlet Flow <120 GPM ATC o BG FI-132 - YES

Appendix D 7 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 4 Total No Pages 31 Event

Description:

Letdown HX BG TCV-130 Controller Fails CLOSED in Auto.

Time Position Applicants Actions or Behavior

6. Check Letdown Heat Exchanger Outlet Temperature LOWERING OR ATC STABLE BETWEEN 110°F to 120°F o BG TI-130 - YES

7. Check Letdown Heat Exchanger Outlet Temperature <120°F ATC o BG TI-130 - NO RNO: WHEN Letdown Heat Exchanger is <120°F, THEN Go to Step 8.

8. Place CVCS Demineralizer Inlet Divert Valve in DEMIN Position ATC o BG HIS-129 CRS 9. Return to Procedure and Step in Effect.

Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

Event termination: After the crew has manual control with Letdown Heat Exchanger Outlet Temperature LOWERING and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 5 at direction of Lead Examiner.

Appendix D 8 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 5 Total No Pages 31 Event

Description:

PZR Press Instrument BB PI-456 fails HIGH Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 5 at the lead evaluators direction.

Diagnostics: Indication on BB PI-456 trends to full scale, While indications on BB PI-455, -457, and -

458 trend lower as PORV 456A Opens.

Annunciators: 033C-PZR PRESS LO HTRS ON, 035B-PORV OPEN, 034D-PRT TEMP HI, 034E-PRT PRESS HI RO Identifies Failed Instrument channel and informs crew.

CRS Enters and directs OFN SB-008.

OFN SB-008, INSTRUMENT MALFUNCTIONS (Rev 45)

1. Check For Malfunction:

Check If Reactor Coolant System Instrument Channel Or Controller Is Malfunctioning: - YES

a. Perform appropriate attachment for malfunctioning channel CRS, RO or controller from table below:

VARIABLE CHANNELS ATTACHMENT P-455, P-456, PZR Pressure (BB) ATTACHMENT K P-457, P-458 CRS Enters and directs ATTACHMENT K, PZR PRESSURE MALFUNCTION.

ATTACHMENT K, PZR PRESSURE MALFUNCTION NOTE Steps K1 through K4 are Memory Action steps.

K1. Identify Failed Instrument Channel:

a. Compare pressurizer pressure indications to confirm a pressurizer pressure channel failure:

RO o BB PI-455A o BB PI-456 - Failed high o BB PI-457 o BB PI-458 K2. Check Failed Pressurizer Pressure Channel Selected On PZR RO PRESS CTRL SEL Switch. YES o BB PS-455F K3. Place PZR PRESS MASTER CTRL In Manual And Control Pressure.

RO o BB PK-455A Provides bounding order, including control band and target Pressurizer CRS pressure.

K4. Select Alternate Pressurizer Pressure Channel On PZR PRESS CTRL RO SEL Switch.

o BB PS-455F

Appendix D 9 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 5 Total No Pages 31 Event

Description:

PZR Press Instrument BB PI-456 fails HIGH Time Position Applicants Actions or Behavior K5. Take Following Actions, As Appropriate To Stop Pressure Control Transient:

a. Check Pressurizer Spray Valves - RESPONDING CORRECTLY RO - YES

b. Check PZR Control Heaters - OPERABLE - YES

c. Ensure PZR PORV - CLOSED - YES K6. Return Pressurizer Pressure Control To Automatic:

o Spray Valves o Control Heaters o Backup Heaters (using SYS BB-203) as desired RO o Open PORV Block Valves o Pressurizer Pressure Control NOTE: Manual control will be maintained until target pressure is reached, then the master controller will be placed in automatic.

Manual adjustments may be made to fine tune the controller.

RO K7. Monitor Pressurizer Pressure Response To Ensure Proper Control K8. Check Failed Pressure Channel Not Selected On PZR PRESS RO RECORD SEL. Not selected o BB PS-455G K9. Check Failed Pressure Channel Not Selected On OP DT/OT DT RO LOOP RECORD SEL Switch. Not selected o SC TS-411E CRS K10. Monitor The Following Technical Specification LCOs And Comply With Action Statements, As Appropriate:

3.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION, Table 3.3.1-1, Functions 6 and 8 - NOT MET

3.3.2, ENGINEERED SAFETY FEATURES ACTUATION INSTRUMENTATION, Table 3.3.2-1, Functions 1.d, 3.a.3, 5.d, 6.e And 8.b - NOT MET

3.3.4, REMOTE SHUTDOWN INSTRUMENTATION, Table 3.3.4-1, Function 3 - Minimum Met

3.3.6, CONTAINMENT PURGE ISOLATION INSTRUMENTATION- Minimum Met

3.3.7, CONTROL ROOM EMERGENCY VENTILATION SYSTEM ACTUATION INSTRUMENTATION- Minimum Met CRS Determines:

TS 3.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION, Condition A (Immediately entered due to failure) and from Table 3.3.1-1, Function 6 and 8, Conditions E and M are entered (both are 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to trip bistables).

TS 3.3.2, ENGINEERED SAFETY FEATURES ACTUATION INSTRUMENTATION, Condition A (Immediately due to failure) and from Table 3.3.2-1, 1.d, 3.a.3, 5.d, 6.e and 8.b, Conditions D (1.d, 3.a.3:

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to place channel in bypass) and L (one hour to verify P-11 interlock in correct state).

Appendix D 10 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event No: 5 Total No Pages 31 Event

Description:

PZR Press Instrument BB PI-456 fails HIGH Time Position Applicants Actions or Behavior CAUTIONS o Avoid introduction of 2/4 low pressurizer pressure signals, which can initiate a reactor trip and SI.

o Avoid introduction of 2/4 OTT reactor trip by ensuring other channels are NOT tripped TB-411C, TB-421C, TB-431C or TB-441C.

NOTE o When the last bistable for the effected instrument is tripped, the output to that control board indication will drop to zero.

o If time permits prior to tripping bistables, I&C should trouble shoot and obtain as-found information, including a determination of which SSPS train is affected. M-767-00310, Tables 603 and 604 may be used to aid I&C in SSPS train determination.

K11. Place Appropriate Reactor Trip/Safeguards Bistables for Failed Pressure Channel in TRIPPED MODE:

NOTE: Channels will NOT be placed in trip before the end of the scenario, even if requested.

K12. Request I&C To Repair Failed Channel.

Simulator Operator: IF contacted as WWM, acknowledge requests. IF contacted as Call Supt.,

acknowledge status.

K13. Review Attachment S for Post-Accident And Remote Shutdown CRS Instrumentation Requirements CRS K14. Return To Procedure And Step In Effect Event termination: After the crew has selected an alternate controlling pressure channel and the CRS has determined the applicable Tech Specs and/or at the direction of the lead examiner.

Simulator Operator: Insert Key 6 at direction of Lead Examiner.

Appendix D 11 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event Nos: 6/7/8 Total No Pages 31 Event

Description:

SSE Earthquake, RCS leak to RHR system outside CTMT, SI Fails to Auto Actuate, CCW Pump B Trips on SI, CCW Pump D Fails to Auto Start Time Position Applicants Actions or Behavior Simulator Operator: Insert Key 6 at the lead evaluators direction.

Diagnostics: Earthquake felt. After a 10 second delay, RCS Pressure trends down. PZR Level trends down while charging flow rises. Rising Aux Building Area Rad Monitor readings, Rising Aux Building sump levels. Constant Containment conditions Annunciators: Multiple, including 098E-SEISMIC RECORDER ON, 062B-AREA RAD HI, 062A-AREA RAD HIHI Diagnose RCS Pressure dropping. May discuss entry to OFN BB-007 RCS LEAKAGE HIGH and /or need to maximize charging, isolate letdown and determine PZR Level trend to determine the need to trip and actuate Crew SI.

NOTE: With the given LOCA Leak Rate, OFN BB-007 foldout page criteria will be met.

OFN BB-007, RCS LEAKAGE HIGH (Rev 18A)

Step 1 Foldout page SI Actuation Criteria:

IF any condition listed occurs, THEN trip the reactor, actuate SI and go to EMG E-0, REACTOR TRIP OR SAFETY INJECTION Step 1.

All of the following conditions exist:

RO o Normal charging is maximized from one pump.

AND o Letdown is isolated.

AND o Pressurizer level is still dropping.

CRS Enter and direct EMG E-0, REACTOR TRIP OR SAFETY INJECTION.

EMG E-0, REACTOR TRIP OR SAFETY INJECTION (Rev 39A)

NOTE o Steps 1 through 4 are immediate action steps.

o Foldout page shall be monitored throughout this procedure.

1. Verify Reactor Trip: YES

a. Check all rod bottom lights - LIT

b. Check reactor trip breakers and bypass breakers - OPEN o SB ZL-1 o SB ZL-2 RO o SB ZL-3 o SB ZL-4

c. Check intermediate range neutron flux - DECREASING o SE NI-35B [GAMMA METRICS]

o SE NI-36B [GAMMA METRICS]

Appendix D 12 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event Nos: 6/7/8 Total No Pages 31 Event

Description:

SSE Earthquake, RCS leak to RHR system outside CTMT, SI Fails to Auto Actuate, CCW Pump B Trips on SI, CCW Pump D Fails to Auto Start Time Position Applicants Actions or Behavior

2. Verify Turbine Trip: YES BOP

a. Check Main Stop Valves - ALL CLOSED

3. Check AC Emergency Busses - AT LEAST ONE ENERGIZED - YES RO

NB01 - ENERGIZED

NB02 - ENERGIZED

4. Check If Safety Injection Is Actuated:

NOTE: IF the crew manually actuated SI then Step 4 will be satisfied with both trains actuated and Critical Task will be met.

a. Check any indication SI is actuated - LIT - NO RNO: Perform the following:

1) Check SI required: - YES

RCS Pressure <1830 psig

2) IF SI is required, THEN manually actuate SI and go to Step 6.

RO o SB HS-27 o SB HS-28 CT 1: Manually actuate SI (SB HS-27 & 28) after auto SI actuation criteria are met before any of the following:

Transition to any EMG E-1 series, EMG E-2 series, or EMG E-3 series procedure or transition to any FRG.

Completion of Step 15 of EMG ES-02

b. Check both trains of SI actuated - YES May notice D CCW Pump failed to auto start and manually start it.

NOTE: Per AP 15C-003, PROCEDURE USERs GUIDE FOR ABNORMAL PLANT CONDITIONS (Rev 35), step 6.4.4, foldout page BOP items may be performed after immediate actions have been completed and prior to the procedure being read without the Control Room SROs permission. This guidance specifically applies to manual backup starting of a CCW Pump that failed to auto start.

Monitor for RCP Trip Criteria per Foldout Page Item #1.

IF all conditions listed below occur, THEN trip all RCPs:

BOP o RCS pressure - LESS THAN 1400 PSIG o CCPs or SI pumps - AT LEAST ONE RUNNING o Operator controlled cooldown - NOT IN PROGRESS Monitor RCS Temperature per Foldout Page Item #7.

o IF RCS C/L temperature is less than 557°F AND lowering, THEN BOP control total feed flow to limit RCS cooldown.

o Maintain total feed flow greater than 270,000 lbm/hr until narrow range is greater than 6% [29%] in at least one S/G.

Appendix D 13 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event Nos: 6/7/8 Total No Pages 31 Event

Description:

SSE Earthquake, RCS leak to RHR system outside CTMT, SI Fails to Auto Actuate, CCW Pump B Trips on SI, CCW Pump D Fails to Auto Start Time Position Applicants Actions or Behavior

5. () Check if SI is required:

SI was manually actuated AND was required - YES RO

RCS pressure is currently or has been - LESS THAN OR EQUAL TO 1830 PSIG NOTE: This step will be skipped by the crew if they manually actuate SI while performing Step 4.

6. Verify Automatic Actions Using Attachment F, AUTOMATIC SIGNAL VERIFICATION [See Attachment 1 for full Attachment F]

NOTE: All Attachment F Automatic Actions are satisfied with one possible exception. There are two potential required actions by the RO while performing this

Attachment:

F6. Verify CCW Alignment:

a. Check CCW pumps - ONE RUNNING IN EACH TRAIN - NO RO RNO. Manually start D CCW pump to establish one running pump in Yellow train (EG HIS-24.)

CT 2: Manually start at least one CCW pump in the train with required ECCS equipment prior to transition out of EMG E-0, or completion of Attachment F, whichever occurs later.

F16. Secure the NCP using BG HIS-3.

7. Check Main Generator Breakers And Exciter Breaker - OPEN - YES o MA ZL-3A BOP o MA ZL-4A o MB ZL-2 BOP 8. Check Total AFW Flow - GREATER THAN 270,000 LBM/HR - YES

9. Check RCS Cold Leg Temperatures:

Stable at or trending to 557°F for condenser steam dumps or S/G BOP ARVs

Stable at or trending to a range of 553°F to 557°F for S/G ARVs if recovering from an inadvertent SI

10. Establish S/G Pressure Control:

a. Check condenser - AVAILABLE -YES

b. Place Steam Header Pressure Control in Manual o AB PK-507

c. Manually set Steam Header Pressure Control output to zero BOP o AB PK-507

d. Place Steam Dump Select Switch in STEAM PRESS Position o AB US-500Z

e. Place Steam Header Pressure Control in Automatic o AB PK-507

Appendix D 14 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event Nos: 6/7/8 Total No Pages 31 Event

Description:

SSE Earthquake, RCS leak to RHR system outside CTMT, SI Fails to Auto Actuate, CCW Pump B Trips on SI, CCW Pump D Fails to Auto Start Time Position Applicants Actions or Behavior

11. Check PZR PORVs

a. Check PZR PORVs - CLOSED - YES o BB HIS-455A o BB HIS-456A RO

b. Power to block valves - AVAILABLE - YES o BB HIS-8000A o BB HIS-8000B

c. RCS pressure - LESS THAN 2185 PSIG

12. Check Normal PZR Spray Valves - CLOSED - YES RO o BB ZL-455B o BB ZL-455C

13. Check PZR Safety Valves - CLOSED - YES o BB ZL-8010A RO o BB ZL-8010B o BB ZL-8010C NOTE Seal Injection flow shall be maintained to all RCPs.

14. Check If RCPs Should Be Stopped: - YES

a. Check RCPs - ANY RUNNING

b. Check RCS pressure - LESS THAN 1400 PSIG

c. Check ECCS pumps - AT LEAST ONE RUNNING RO, BOP

CCP OR SI pump

d. Check operator controlled cooldown - NOT IN PROGRESS

e. Stop all RCPs NOTE: RCPs may have previously been stopped per foldout page item # 1, RCP TRIP CRITERIA.

15. Direct Operator to Monitor Critical Safety Functions Using EMG F-0, CRS CRITICAL SAFETY FUNCTION STATUS TREES (CSFST).

LEAD EVALUATOR NOTE: Computer is accurate BOP 16. Check If S/Gs are NOT Faulted - YES BOP 17. Check if S/Gs are Intact - YES RO 18. Check if RCS Is Intact in Containment: - YES

19. Check if ECCS Flow Should Be Reduced: - NO

a. RCS Subcooling >30F

c. RCS Pressure - Stable or Rising Crew

d. PZR Level >6%

RNO: Go to Step 20

Appendix D 15 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event Nos: 6/7/8 Total No Pages 31 Event

Description:

SSE Earthquake, RCS leak to RHR system outside CTMT, SI Fails to Auto Actuate, CCW Pump B Trips on SI, CCW Pump D Fails to Auto Start Time Position Applicants Actions or Behavior

20. Reset SI.

RO o SB HS-42A o SB HS-43A

21. Reset Containment Isolation Phase A and Phase B.

o SB HS-56 for phase A RO o SB HS-53 for phase A o SB HS-55 for phase B o SB HS-52 for phase B BOP 22. Verify Instrument Air Compressor is Running: - YES

23. Verify Instrument Air to Containment:

a. Check INST AIR SPLY CTMT ISO VLV - CLOSED o KA HIS-29 BOP b. Check PZR PRESS MASTER CTRL Output - <55%

o BB PK-455A

c. Open INST AIR SPLY CTMT ISO VLV.

o KA HIS-29

24. Check S/G Levels:

a. Check NR Level in at least one S/G >6% - YES BOP

b. Control feed flow to maintain NR Level in all S/Gs between 6% and 50%.

Simulator Operator: WHEN contacted as Health Physics, acknowledge requests. WHEN contacted as Chemistry, acknowledge request.

25. Check if S/G Tubes are Intact:

a. Direct Health Physics to survey steamlines in Area 5 of the Auxiliary Building.

b. Check S/G sampling isolated.

1) Open CCW to Radwaste System Isolation Valves o EG HS-69 BOP o EG HS-70

2) Open all S/G Sample Isolation Valves.

3) Direct Chemistry to sample all S/Gs for Activity

c. Check Health Physics surveys / Chemistry samples complete. - NO RNO WHEN HP surveys AND/OR Chemistry samples are complete, THEN perform step 25.d. Continue with Step 26.

Appendix D 16 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event Nos: 6/7/8 Total No Pages 31 Event

Description:

SSE Earthquake, RCS leak to RHR system outside CTMT, SI Fails to Auto Actuate, CCW Pump B Trips on SI, CCW Pump D Fails to Auto Start Time Position Applicants Actions or Behavior Simulator Operator: WHEN contacted as Health Physics, acknowledge requests.

26. Check Fuel / Auxiliary Building Radiation - NORMAL:

a. Shift Fuel/Auxiliary Building Exhaust sample to EMERGENCY o GG HIS-27 o GG HIS-28

b. Direct Health Physics to survey Fuel and Auxiliary Buildings with priority being pipe penetration areas and piping tunnels.

c. Check Fuel/Auxiliary Building radiation monitors - NONE ALARMING - NO RNO: Perform the following:

1. Try to identify and isolate leakage:

a) Review plant indications and operating history for source of RO leakage.

o Containment sump levels o RHR sump levels o Instrument Tunnel Sump Level o Auxiliary Building Sump Levels b) Review trend recorders and computer data for radiation changes and tank level changes.

c) IF environmental considerations AND radiation conditions permit, THEN isolate leakage paths.

2. IF source of leakage is a loss of RCS inventory outside CTMT, THEN perform the following:

a) Ensure BIT Inlet and Outlet Valves are open - YES b) Go to EMG C-12, LOCA OUTSIDE CONTAINMENT, Step 1.

EMG C-12, LOCA OUTSIDE CONTAINMENT (Rev 15)

NOTE Foldout page shall be monitored throughout this procedure.

Simulator Operator: WHEN contacted as Building Watch, acknowledge requests. INSERT KEY 6, Wait 2 minutes and report Breakers for RHR suction valves from RCS Hot leg valves are closed.

1. Reenergize RHR Loop Suction Valves:

a. Dispatch Operator to close breakers for Loop Hot Leg To RHR Pump Suction valves:

RO o NG02BCF2 for BB HIS-8702A o NG02BBF3 for BB HIS-8702B o NG01BEF2 for EJ HIS-8701A o NG01BDF3 for EJ HIS-8701B

Appendix D 17 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event Nos: 6/7/8 Total No Pages 31 Event

Description:

SSE Earthquake, RCS leak to RHR system outside CTMT, SI Fails to Auto Actuate, CCW Pump B Trips on SI, CCW Pump D Fails to Auto Start Time Position Applicants Actions or Behavior

2. Verify Proper SI System Valve Alignment: - YES

a. Check RHR Hot Leg Recirc Valve - CLOSED o EJ HIS-8840

b. Check SI Pump Discharge to Hot Leg Injection valves - CLOSED RO o EM HIS-8802A o EM HIS-8802B

c. Check SI Test Line Containment Isolation Valves - CLOSED o EM HIS-8871 o EM HIS-8964

3. Verify Proper CVCS Valve Alignment:

a. Check Letdown System Containment Isolation Valves - CLOSED o BG HIS-8160 o BG HIS-8152

b. Check RCS To Excess Letdown Heat Exchanger Valves - Closed o BG HIS-8153A o BG HIS-8154A o BG HIS-8153B RO o BG HIS-8154B

c. Check Charging Pumps To Regenerative Heat Exchanger Containment Isolation Valves - CLOSED o BG HIS-8105 o BG HIS-8106

d. Check Seal Water Return Containment Isolation Valves - CLOSED o BG HIS-8100 o BG HIS-8112

4. Verify Proper RHR Loop Suction Valve Alignment:

a. Ensure power restored to Loop Hot Leg To RHR Pump Suction Valves:

o EJ HIS-8701A o EJ HIS-8701B o BB HIS-8702A o BB HIS-8702B

b. Check Loop Hot Leg to RHR Pump Suction valves - AT LEAST ONE CLOSED IN EACH TRAIN o EJ HIS-8701A OR BB HIS-8702A - CLOSED - NO o EJ HIS 8701B OR BB HIS-8702B - CLOSED RNO: Perform the following:

1) Manually close valves. - YES CT 3: Isolate the LOCA outside containment before transition out of EMG C-12.

c. Check RCS Pressure STABLE or LOWERING - NO RNO: Go to Step 8

Appendix D 18 Form ES-D-2 Op Test No: 11/2017 Scenario No: 4 Event Nos: 6/7/8 Total No Pages 31 Event

Description:

SSE Earthquake, RCS leak to RHR system outside CTMT, SI Fails to Auto Actuate, CCW Pump B Trips on SI, CCW Pump D Fails to Auto Start Time Position Applicants Actions or Behavior

8. Check if Break is Isolated:

a. Check RCS Pressure Rising - YES

b. Go to EMG E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

Scenario Termination: After the crew has isolated the LOCA and determined they should proceed to EMG E-1and/or at the direction of the lead examiner, FREEZE Simulator

Appendix D 19 Form ES-D-2 Attachment 1 (Page 1 of 13)

Appendix D 20 Form ES-D-2 Attachment 1 (Page 2 of 13)

Appendix D 21 Form ES-D-2 Attachment 1 (Page 3 of 13)

Appendix D 22 Form ES-D-2 Attachment 1 (Page 4 of 13)

Appendix D 23 Form ES-D-2 Attachment 1 (Page 5 of 13)

Appendix D 24 Form ES-D-2 Attachment 1 (Page 6 of 13)

Appendix D 25 Form ES-D-2 Attachment 1 (Page 7 of 13)

Appendix D 26 Form ES-D-2 Attachment 1 (Page 8 of 13)

Appendix D 27 Form ES-D-2 Attachment 1 (Page 9 of 13)

Appendix D 28 Form ES-D-2 Attachment 1 (Page 10 of 13)

Appendix D 29 Form ES-D-2 Attachment 1 (Page 11 of 13)

Appendix D 30 Form ES-D-2 Attachment 1 (Page 12 of 13)

Appendix D 31 Form ES-D-2 Attachment 1 (Page 13 of 13)

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Wolf Creek 1 Date of Exam: 11/6-10/2017 Operating Test No.: 2017301 A E Scenarios P V 1 4 3 2 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U RX 0 1 1 0 NOR 1 1 2 1 1 1 I/C 2,3,4 3,4,5 10 4 4 2 U1 5,7 ,7,8 MAJ 6 6 2 2 2 1 TS 2,4 2,5 4 0 2 2 RX 0 1 1 0 NOR 0 1 1 1 R1 I/C 3,4, 4,5, 7 4 4 2 5,7 7 MAJ 6 6 2 2 2 1 TS 0 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 RO RX 1 1 0 NOR 1 1 1 SRO-I I/C 4 4 2 SRO-U MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional I/C malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Wolf Creek 1 Date of Exam: 11/6-10/2017 Operating Test No.:

A E Scenarios P V 1 4 3 2 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U RX 0 1 1 0 NOR 1 1 2 1 1 1 I/C 2,3,4 4,5, 2,3,4 13 4 4 2 I1 5,7 7 5,7 MAJ 6 6 6 3 2 2 1 TS 2,4 2,3 4 0 2 2 RX 0 1 1 0 NOR 1 1 1 3 1 1 1 I2 I/C 2,5 3,4,5 2,3,4 12 4 4 2

,7,8 5,7 MAJ 6 6 6 3 2 2 1 TS 2,5 2,3 4 0 2 2 R3 RX 0 1 1 0 NOR 1 1 1 1 1 I/C 3,4, 3,8 2,4,5 9 4 4 2 5,7 MAJ 6 6 6 3 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional I/C malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Wolf Creek 1 Date of Exam: 11/6-10/2017 Operating Test No.:

A E Scenarios P V 1 4 3 2 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U RX 0 1 1 0 NOR 1 1 2 1 1 1 I/C 2,3,4 4,5, 2,3,4 13 4 4 2 I3 5,7 7 5,7 MAJ 6 6 6 3 2 2 1 TS 2,4 2,3 4 0 2 2 RX 0 1 1 0 NOR 1 1 1 3 1 1 1 I4 I/C 2,5 3,4,5 3,4,5 11 4 4 2

,7,8 ,7 MAJ 6 6 6 3 2 2 1 TS 2,5 2 0 2 2 R4 RX 0 1 1 0 NOR 1 1 1 1 1 I/C 3,4, 3,8 2,4,5 9 4 4 2 5,7 MAJ 6 6 6 3 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional I/C malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Wolf Creek 1 Date of Exam: 11/6-10/2017 Operating Test No.:

A E Scenarios P V 1 4 3 2 T M P E O I L N CREW CREW POSITION CREW POSITION CREW POSITION T N I T POSITION I

C A S A B S A B S A B S A B M A T L R T O R T O R T O R T O U N Y O C P O C P O C P O C P M(*)

T P E R I U I5 RX 0 1 1 0 NOR 1 1 2 1 1 1 I/C 2,3,4 3,4,5 2,4,5 13 4 4 2 5,7 ,7,8 MAJ 6 6 6 3 2 2 1 TS 2,4 2,5 4 0 2 2 RX 0 1 1 0 NOR 1 1 1 3 1 1 1 R5 I/C 2,5 3,8 3,4,5 8 4 4 2

,7 MAJ 6 6 6 3 2 2 1 TS 0 0 2 2 R6 RX 0 1 1 0 NOR 1 1 1 1 1 I/C 3,4, 4,5, 3,4,5 11 4 4 2 5,7 7 ,7 MAJ 6 6 6 3 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions. Instant SROs (SRO-I) must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an SRO-I additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional I/C malfunctions on a one-for-one basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4. For new reactor facility licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

ES-301 Competencies Checklist Form ES-301-6 Facility: Wolf Creek 1 Date of Examination: 11/6-10/17 Operating Test No.: 2017301 APPLICANTS U1 R1 Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 2,3 2,3 3,4 4,5 and Conditions 4,5 ,4, ,5, ,6, 6,7 5,6 6,7 7

,7, 8

Comply with and All All 3,4 4,5 Use Procedures (1) ,5, ,6, 6,7 7 Operate Control NA NA 3,4 4,5 Boards (2) ,5, ,6, 6,7 7 Communicate All All 3,4 4,5 and Interact ,5, ,6, 6,7 7 Demonstrate Supervisory All All NA NA Ability (3)

Comply with and 2,4 2,5 NA NA Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES 303 1 and ES 303 3 describe the competency rating factors.)

ES-301 Competencies Checklist Form ES-301-6 Facility: Wolf Creek 1 Date of Examination: 11/6-10/17 Operating Test No.: 2017301 APPLICANTS I1 I2 R3 Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events 2,3 2,3, 4,5 2,5 2,3, 2,3 3,4 2,4 3,6 and Conditions ,4, 4,5, ,6, ,6 4,5, ,4, ,5, ,5, ,8 5,6 6,7 7 6,7 5,6 6,7 6

,7 ,7, 8

4,5 1,3 Comply with and All All ,6, 1,2 All All 3,4 2,4 ,6, Use Procedures (1) 7 ,5, ,5, ,5, 8 6 6,7 6 2,4 1,3 Operate Control 4,5 1,2 3,4 ,5, ,6, Boards (2) ,6, ,5, ,5, 6 8 7 6 6,7 2,4 1,3 Communicate All All 4,5 1,2 All All 3,4 ,5, ,6, and Interact ,6, ,5, ,5, 6 8 7 6 6,7 Demonstrate Supervisory All All All All NA NA NA Ability (3)

Comply with and 2,4 2,3 2,3 2,5 NA NA NA Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES 303 1 and ES 303 3 describe the competency rating factors.)

ES-301 Competencies Checklist Form ES-301-6 Facility: Wolf Creek 1 Date of Examination: 11/6-10/17 Operating Test No.: 2017301 APPLICANTS I3 I4 R4 Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 3,6 Interpret/Diagnose Events 2,3 2,3 4,5 2,5 3,4 3,4 3,4 2,4 ,8 and Conditions ,4, ,4, ,6, ,6 ,5, ,5, 5,6 ,5, 5,6 5,6 7 6,7 6,7 ,7 6

,7 ,7 ,8 1,3 Comply with and All All 4,5 1,2 1,3 All 3,4 2,4 ,6, Use Procedures (1) ,6, ,5, ,4, 5,6 ,5, 8 7 6 5,6 ,7 6

,7 1,2 1,3 Operate Control 4,5 ,5, 1,3 3,4 2,4 ,6, Boards (2) ,6, 6 ,4, 5,6 ,5, 8 7 5,6 ,7 6

,7 All 1,2 1,3 Communicate All 4,5 ,5, 1,3 All 3,4 2,4 ,6, and Interact ,6, 6 ,4, 5,6 ,5, 8 7 5,6 ,7 6

,7 Demonstrate Supervisory All All All NA NA NA Ability (3)

Comply with and 2,4 2,3 2,5 NA NA NA Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES 303 1 and ES 303 3 describe the competency rating factors.)

ES-301 Competencies Checklist Form ES-301-6 Facility: Wolf Creek 1 Date of Examination: 11/6-10/17 Operating Test No.: 2017301 APPLICANTS I5 R5 R6 Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 4,5 Interpret/Diagnose Events 2,3 2,4 3,4, 2,5 3,4, 3,6 3,4 3,4 ,6, and Conditions ,4, ,5, 5,6, ,6 5,6, ,8 ,5, ,5, 7 5,6 6 7,8 7 6,7 6,7

,7 2,4 All 1,3 4,5 Comply with and All ,5, 1,2 1, 1,3 3,4 ,4, ,6, Use Procedures (1) 6 ,5, 3,4, ,6, ,5, 5,6 7 6 5,6, 8 6,7 ,7 7

2,4 1,2 1, 1,3 1,3 4,5 Operate Control ,5, ,5, 3,4, ,6, 3,4 ,4, ,6, Boards (2) 6 6 5,6, 8 ,5, 5,6 7 7 6,7 ,7 2,4 All 1,2 1, 1,3 1,3 4,5 Communicate All ,5, ,5, 3,4, ,6, 3,4 ,4, ,6, and Interact 6 6 5,6, 8 ,5, 5,6 7 7 6,7 ,7 Demonstrate Supervisory All All NA NA NA NA NA NA Ability (3)

Comply with and 2,4 2,5 NA NA NA NA NA NA Use TS (3)

Notes:

(1) Includes TS compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Forms ES 303 1 and ES 303 3 describe the competency rating factors.)

ML17355A641

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