Text

Draft Operating Test (Section a, Section B, Section C) (Folder 2)
	ML20274A066
Person / Time
Site:	Calvert Cliffs
Issue date:	02/07/2020
From:	; NRC Region 1
To:	Thomas Setzer; Operations Branch I
Shared Package
ML19105A101	List: ML19157A096; ML20057E559; ML20057E560; ML20274A066; ML20274A083; ML20274A092; ML20274A094; ML20274A105; ML20274A136; ML20279A331; ML21025A073; ML21025A143; ML21025A414;
References
	50-317/20-01, 50-318/20-01, CAC 000500 50-317/OL-20, 50-318/OL-20
	Download: ML20274A066 (260)
	v • d • e

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-RO Admin1

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: RO Admin1 Alternate Path: No Task Number: 202.023 Task

Title:

Respond to a complete loss of SDC (Estimate Time to Boiling & Core Uncovery)

Task Standard: Candidate determines Time to Boil and Time to Core Uncovery.

K/A

Reference:

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

Method of Testing: Actual Performance-Classroom Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. AOP-3B, Revision 03001 Abnormal Shutdown Cooling Conditions JPM Setup Instructions:

1. Consumable copy of AOP-3B, Abnormal Shutdown Cooling Conditions RO Admin1 Page 2 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 RCS is drained to 38.6 feet in preparation for Vacuum Fill of the RCS.

2. RCS temperature is 100 F.

3. The reactor was shut down 25 days ago after an extended period of full power operation.

4. Refueling operations have been completed. 88 fresh fuel assemblies were loaded in the core.

5. A loss of shutdown cooling has occurred.

6. You are performing the duties of an extra CRO.

Initiating Cue:

1. The Shift Manager directs you to calculate the time to boiling AND core uncovery per AOP-3B Attachment (14) steps 2 and 3 (attached).

2. The Unit Supervisor will independently verify both calculation after both have been calculated.

3. Are there any questions? You may begin.

RO Admin1 Page 3 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

EVALUATOR NOTE Completion of this JPM requires interpreting graphs that have the potential to induce minor variations in calculated results. For that reason, calculated results are given an acceptable band.

AOP-3B Attachment 14, Calculation of Time to 200°F, Boil or Core Uncovery Section 2. Calculate Time to Boil Determine the Time to Boil at 24 Using Attachment (10),

hours after shutdown from the 2a determines TTB @ 24 hrs is __ __

appropriate figure, based on approximately 13.25 minutes.

RCS level and RCS temperature Evaluator Comment CRITICAL STEP*

Obtain the multiplier from

Attachment (13), Multiplier on Using attachment (13) 2b Time to 200°F, Start Boiling or records multiplier of 3.39 and __ __

Core Uncovery, based on time post refueling multiplier of after shutdown. 1.36 on attachment (14) step 2.c.

Evaluator Comment CRITICAL STEP*

Performs TTB calculation Multiply the Time to Boil at 24 and records on attachment

(14) step 2.c hours after shutdown by the __ __

2c multiplier. 13.25 X 3.39 X 1.36 = 61.1 (Answers in the range of 58 to 64 minutes are acceptable)

Evaluator Comment RO Admin1 Page 4 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD AOP-3B Attachment 14, Calculation of Time to 200°F, Boil or Core Uncovery Section 3. Calculate Time to Core Uncovery Determine the Time to Core Using Attachment (15),

Uncovery at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after determines Time to Core 3a shutdown from the appropriate __ __

Uncovery @ 24 hrs is figure, based on RCS level and approximately 128 minutes.

RCS temperature Evaluator Comment CRITICAL STEP*

Obtain the multiplier from

Attachment (13), Multiplier on Using attachment (13) 3b Time to 200°F, Start Boiling or records multiplier of 3.39 and __ __

Core Uncovery, based on time post refueling multiplier of after shutdown. 1.36 on attachment (14) step 3.c.

Evaluator Comment CRITICAL STEP*

Performs TTB calculation and records on attachment Multiply the Time to Boil at 24 (14) step 3.c hours after shutdown by the __ __

3c 128 X 3.39 X 1.36 = 590.1 multiplier.

(Answers in the range of 580 to 600 minutes are acceptable)

Evaluator Comment TERMINATING CUE:

This JPM is complete when the candidate completes Attachment 14, steps 2 and 3.

The Examinee is expected to end the JPM.

TIME STOP: _______

RO Admin1 Page 5 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: RO Admin1 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

RO Admin1 Page 6 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 RCS is drained to 38.6 feet in preparation for Vacuum Fill of the RCS.

2. RCS temperature is 100 F.

3. The reactor was shut down 25 days ago after an extended period of full power operation.

4. Refueling operations have been completed. 88 fresh fuel assemblies were loaded in the core.

5. A loss of shutdown cooling has occurred.

6. You are performing the duties of an extra CRO.

Initiating Cue:

1. The Shift Manager directs you to calculate the time to boiling AND core uncovery per AOP-3B Attachment (14) steps 2 and 3 (attached).

2. The Unit Supervisor will independently verify both calculation after both have been calculated.

3. Are there any questions? You may begin.

RO Admin1 Page 7 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 RO Admin1 Page 8 of 8

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-RO Admin2

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: RO Admin2 Alternate Path: No Task Number: 201.072 Task

Title:

Ensure adequate shutdown margin exists with all CEAs operable, in Mode 3 Task Standard: Adequate shutdown margin is verified, using the figure method, for the stated core conditions, with all CEAs operable, in Mode 3 K/A

Reference:

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

Method of Testing: Actual Performance-Classroom Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. NEOP-301, Revision 01600

2. NEOP-23, Revision 035 JPM Setup Instructions:

1. Consumable copy of NEOP-301, Revision 01600

2. Consumable copy of NEOP-23, Revision 035 RO Admin2 Page 2 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-2 had been operating at 100% power for 100 days when power was reduced, three days ago, for work requiring 21 SGFP to be secured (work still in progress)

2. At 0800 this morning Unit-2 experienced an uncomplicated reactor trip

3. TAVG is stable at 532°F

4. RCS boron concentration is 1400 PPM per a grab sample obtained at 1100

5. Current time, for purposes of this JPM, is 1130

6. Core Burnup is 11,500 MWD/MTU

7. Start-up is anticipated to occur in approximately 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

8. A Xenon report has yet to be provided by Reactor Engineering

9. POWERTRAX is currently unavailable

10. You are performing the duties of an extra RO Initiating Cue:

EOP-Attachment 13 requires a shutdown margin calculation be performed. The CRS directs you to verify and document (on the attached attachment 2) that shutdown margin is adequate, using the figure method, for the present plant conditions, per NEOP-301 Are there any questions? You may begin.

RO Admin2 Page 3 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

Locates NEOP-301, Operator Locates NEOP-301, Operator Surveillance Procedure and Surveillance Procedure and __ __

proceeds to step 4.1 proceeds to step 4.1 Evaluator Comment NEOP-301, Operator Surveillance Procedure, Section 4.1 CAUTION Step 4.1.1 allowable times to verify SDM are applicable for TAVG greater than or equal to 515°F with a steady or increasing soluble Boron concentration, when the SDM will be acceptable for a minimum of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months under all non-accident conditions. SDM shall be verified before decreasing TAVG below 515°F or reducing boron concentration, both of which will invalidate the times to verify SDM in step 4.1.1 and may lead to a loss of adequate shutdown margin.

Determine the allowable time to Selects 4.1.1.1 based on 1.1 verify SDM by performing Step information provided in the __ __

4.1.1.1 or Step 4.1.1.2: Cue Evaluator Comment References the table and 1.1.1 Reference the following table: determines SDM must be __ __

verified within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Evaluator Comment Model the trip using the XENON 1.2 Determines the step is N/A __ __

code (or Powertrax)

Evaluator Comment RO Admin2 Page 4 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Determine the shutdown boron Selects 2.1.A based on the 2.1 concentration using one of the information provided in the __ __

following methods: Cue Evaluator Comment CUE If requested, the B10 Correction Factor is 0.93 CRITICAL STEP*

Refers to NEOP-23, Figure 2-II.A.3.

Refer to NEOP-23, Figure 2-Determines required __ __

2.1.A II.A.3 shutdown boron concentration is 1375 PPM and records on Attachment 2.

Evaluator Comment 2.1.B Determine using Powertrax. Determines the step is N/A __ __

Evaluator Comment If needed, then Borate the RCS 2.2 to at least the shutdown boron Determines the step is N/A __ __

concentration Evaluator Comment Perform the following within the Verifies the current time is time determines in Step 4.1.1 2.3 within the time determined in __ __

and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Step 4.1.1 thereafter:

Evaluator Comment RO Admin2 Page 5 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

-Logs Sequence #: 1

-Logs Unit#: 2

-Logs Cycle #: 23

-Logs Method: Figure Document the following -Logs

Reference:

2-II.A.3 conditions on Attachment 2, -Logs Mode: 3 Shutdown Margin Verification. -Logs TAVG: 532F

-Logs Actual Burnup: 11,500

RCS TAVG is acceptable for MWD/MTU

the current operating Mode

-Determines and Logs CEA __ __

2.3.A

A boron concentration position: IN sample from the RCS has

-Logs date/time of sample:

been obtained Today at 1100

RCS boron concentration is -Logs boron Sample: 1400 at least the shutdown boron PPM concentration -Logs shutdown boron conc:

1375 PPM

-Determines from NEOP and Logs SDM valid until: a time less than or equal to tomorrow at 1130 Evaluator Comment Compares RCS boron CRITICAL STEP*

concentration is equal to or

-Enters initials/date/time: as __ __

Att 2 greater than the required shutdown boron concentration. preparer (todays date/1130)

Evaluator Comment TERMINATING CUE: This JPM is complete when the status of core shutdown margin has been determined and recorded. The Examinee is expected to end the JPM.

TIME STOP: _______

RO Admin2 Page 6 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: RO Admin2 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

RO Admin2 Page 7 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-2 had been operating at 100% power for 100 days when power was reduced, three days ago, for work requiring 21 SGFP to be secured (work still in progress)

2. At 0800 this morning Unit-2 experienced an uncomplicated reactor trip

3. TAVG is stable at 532°F

4. RCS boron concentration is 1400 PPM per a grab sample obtained at 1100

5. Current time, for purposes of this JPM, is 1130

6. Core Burnup is 11,500 MWD/MTU

7. Start-up is anticipated to occur in approximately 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

8. A Xenon report has yet to be provided by Reactor Engineering

9. POWERTRAX is currently unavailable

10. You are performing the duties of an extra RO Initiating Cue:

EOP-Attachment 13 requires a shutdown margin calculation be performed. The CRS directs you to verify and document (on the attached attachment 2) that shutdown margin is adequate, using the figure method, for the present plant conditions, per NEOP-301 Are there any questions? You may begin.

RO Admin2 Page 8 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 3

RO Admin2 Page 9 of 9

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-RO Admin3

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: RO Admin3 Alternate Path: No Task Number: 052/061.028 Task

Title:

Verify SIS valve operability (operating)

Task Standard: Candidate documents the required isolations and technical specification LCO on the Examinees Cue Sheet.

K/A

Reference:

2.2.41 (3.5) Ability to obtain and interpret station electrical and mechanical drawings.

Method of Testing: Actual Performance-Classroom Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. Print 60731SH0003, Rev 0033, Operations DWG Safety Injection and Containment Spray

2. Print 60711, Rev 15, Charcoal Filter Spray System

3. Technical Specification 3.6.6, Amendment No. 326 JPM Setup Instructions:

1. Consumable copy of print 60731SH0003, Rev 0033, Operations DWG Safety Injection and Containment Spray

2. Consumable copy of print 60711, Rev 15, Charcoal Filter Spray System

3. Consumable copy of Technical Specifications RO Admin3 Page 2 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 is in Mode 3 at NOP following an uncomplicated Reactor Scram.

2. During a Containment walk through a water leak is observed on 1-CV-4150, 11 CS HDR ISOL CV that requires isolation.

3. Tech Spec 3.6.3 does not apply since 1-CV-4150 is not a Containment Isolation Valve.

4. You are performing the duties of an extra Control Room Operator.

Initiating Cue:

Using the above plant conditions:

1. List the normally open upstream and downstream mechanical isolation points required to be shut to isolate 1-CV-4150, 11 CS HDR ISOL CV.

2. After 1-CV-4150 is isolated, is Unit 1 in any Technical Specification LCOs (Circle one)?

YES NO

3. If applicable, list any required Technical Specification LCO(s).

RO Admin3 Page 3 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

CUE Provide the Examinee with required prints and Technical Specifications.

Candidate correctly locates Candidate identifies 1-CV-4150 identifies 1-CV-4150 is on print __ __

is on print 60731SH0003 60731SH0003 Evaluator Comment CRITICAL STEP*

Candidate determines the Candidate determines and required mechanical isolation documents the following

points: valves are the necessary __ __

1 mechanical isolation points:

1-SI-317 1-SI-315 1-SI-317 1-SI-315 Evaluator Comment CRITICAL STEP*

Candidate determines if Unit-1 is After isolating 1-CV-4150 a in any Technical Specification TS LCO would be __ __

2 LCOs. applicable. Candidate circles YES.

Evaluator Comment CRITICAL STEP*

Candidate determines the Candidate determines and required technical specification documents the required __ __

3 LCOs: 3.6.6 Technical Specification LCO: 3.6.6 RO Admin3 Page 4 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Evaluator Comment TERMINATING CUE:

This JPM is complete when candidate documents the required isolations and technical specification LCO on the Examinees Cue Sheet.

The Examinee is expected to end the JPM.

TIME STOP: _______

RO Admin3 Page 5 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: RO Admin3 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

RO Admin3 Page 6 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 is in Mode 3 at NOP following an uncomplicated Reactor Scram.

2. During a Containment walk through a water leak is observed on 1-CV-4150, 11 CS HDR ISOL CV that requires isolation.

3. Tech Spec 3.6.3 does not apply since 1-CV-4150 is not a Containment Isolation Valve.

4. You are performing the duties of an extra Control Room Operator.

Initiating Cue:

Using the above plant conditions:

1. List the normally open upstream and downstream mechanical isolation points required to be shut to isolate 1-CV-4150, 11 CS HDR ISOL CV.

2. After 1-CV-4150 is isolated, is Unit 1 in any Technical Specification LCOs (Circle one)?

YES NO

3. If applicable, list any required Technical Specification LCO(s).

RO Admin3 Page 7 of 7

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-RO Admin4

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: RO Admin4 Alternate Path: No Task Number: 204.138 Task

Title:

Maintain situational awareness of the plant during Normal, Abnormal, Emergency and ERPIP operations.

Task Standard: This JPM is complete when the Operator has determined the required attachments, announcements, and onsite people/facilities contacted.

K/A

Reference:

2.4.27 (3.4) Knowledge of fire in the plant procedures.

Method of Testing: Actual Performance-Classroom Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. OP-CA-108-3.0, Revision 00301, Immediate Actions JPM Setup Instructions:

1. Consumable copy of OP-CA-108-3.0, Revision 00301, Immediate Actions RO Admin4 Page 2 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Both Unit-1 and Unit-2 are at 100% power.

2. The control room has just received a 911 phone call about a fire in the U-1 VCT Room.

3. The caller has identified a potentially contaminated badly burned employee.

4. You are performing the duties of an extra Control Room Operator.

Initiating Cue:

The Unit Supervisor directs you to perform the following and document on the provided cue sheet:

1. Determine the required attachments from OP-CA-108-3.0, Immediate Actions, to implement.

2. Determine the required announcements, as closely as possible, to notify plant personnel per the applicable attachments from OP-CA-108-3.0. Repeating the announcement is not necessary. (The SM will handle all Emergency Classification announcements, if applicable)

3. Determine the required people/facilities that need to be contacted per the applicable attachments from OP-CA-108-3.0. (The SM will handle all Emergency Classification notifications, if applicable)

4. Are there any questions? You may begin.

RO Admin4 Page 3 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

CUE Provide the Operator with a copy of OP-CA-108-3.0, Immediate Actions Review OP-CA-108-3.0, Reviews OP-CA-108-3.0, Immediate Actions Immediate Actions Evaluator Comment CRITICAL STEP*

Determines the required Determines and documents

attachments from OP-CA-108- that Attachment 15, Personnel Emergency, and __ __

1 3.0, Immediate Actions, to implement. Attachment 16, Fire in the Protected Area, ISFSI, Or MPF are required.

Evaluator Comment CRITICAL STEP*

Determines and documents the following announcements:

(Critical wording is Bolded)

Determine the required announcements, as closely as A personnel emergency

possible, to notify plant exists. A badly burned 2 personnel per the applicable individual is in the U-1 VCT __ __

attachments from OP-CA-108- Room. First Aid Team and 3.0. Repeating the Radiation Protection announcement is not necessary. Technician Respond.

There is a fire in the U-1 VCT Room. Fire Brigade and Radiation Protection Technician respond.

Evaluator Comment RO Admin4 Page 4 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

Determines and documents the following people/facilities:

Site Medical Determines the required people/facilities that need to be CAS/SAS contacted per the applicable Calvert Memorial Hospital __ __

3 attachments from OP-CA-108- Emergency Room or 3.0 Switchboard Site Safety Fire and Safety Watch Radiation Protection Tech Evaluator Comment TERMINATING CUE:

This JPM is complete when the Operator has determined and documented the required attachments, announcements, and people/facilities contacted.

The Examinee is expected to end the JPM.

TIME STOP: _______

RO Admin4 Page 5 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: RO Admin4 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

RO Admin4 Page 6 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Both Unit-1 and Unit-2 are at 100% power.

2. The control room has just received a 911 phone call about a fire in the U-1 VCT Room.

3. The caller has identified a potentially contaminated badly burned employee.

4. You are performing the duties of an extra Control Room Operator.

Initiating Cue:

The Unit Supervisor directs you to perform the following and document on the provided cue sheet:

1. Determine the required attachments from OP-CA-108-3.0, Immediate Actions, to implement.

2. Determine the required announcements, as closely as possible, to notify plant personnel per the applicable attachments from OP-CA-108-3.0. Repeating the announcement is not necessary. (The SM will handle all Emergency Classification announcements, if applicable)

3. Determine the required people/facilities that need to be contacted per the applicable attachments from OP-CA-108-3.0. (The SM will handle all Emergency Classification notifications, if applicable)

4. Are there any questions? You may begin.

1. Required 1.

attachments

2. Required 2.

announcements

3. Required 3.

people/facilities RO Admin4 Page 7 of 7

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-SRO Admin1

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: SRO Admin1 Alternate Path: No Task Number: 204.028 Task

Title:

Verify shift personnel are fit for duty through discussions of the fitness for duty requirements.

Task Standard:

Satisfactory task completion is indicated when the candidate successfully assesses the work hour limits and documents findings on the cue sheet.

K/A

Reference:

2.1.5 (3.9) Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Method of Testing: Actual Performance-Classroom Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. LS-AA-119, Revision 13 JPM Setup Instructions:

1. Consumable copy of LS-AA-119, Revision 13, (Pages 11-17 (Section 5.1, 5.1.1, and 5.1.2)).

SRO Admin1 Page 2 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. The present time/date is 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months on 1/26

2. In accordance with LS-AA-119, Fatigue Management and Work Hour Limits, the Shift Manager has directed the WEC to review the availability of RO #1 to work Dayshift 1/26 for coverage for a downpower for waterbox cleaning.

3. RO #1 was on vacation for two weeks, returning to work on Monday 1/13.

4. RO #1 work history for the previous two weeks is as follows, with all hours having been in posted Licensed Reactor Operator positions.

Monday Tuesday Wednesday Thursday Friday Saturday Sunday 1/13 1/14 1/15 1/16 1/17 1/18 1/19 1800-0600 1800-0600 OFF 1800-1000 1900-0600 OFF OFF 1/20 1/21 1/22 1/23 1/24 1/25 1/26 0600-1800 0600-1800 0600-1800 0600-1800 0600-1800 0600-1800 Request 0600-1800 Initiating Cue:

Using the work history provided:

1. Determine whether RO #1 is able to cover the required shift.

Circle one: Can / Cannot

2. If applicable, document all work hour limits that would be exceeded if RO #1 works Sunday 1/26.

SRO Admin1 Page 3 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1

3. Determine whether RO #1 has already violated any work hour limits.

Circle one: Yes / No

4. If applicable, document all work hour limits that have already been exceeded.

SRO Admin1 Page 4 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

Provide the Examinee with a copy of procedure LS-AA-119, Fatigue CUE Management and Work Hour Limits, sections 5.1, 5.1.1, and 5.1.2.

Review work history and LS-AA- Candidate reviews procedures 119 to determine if able to work for Work Hour limits and __ __

requested shift. reviews work history provided.

Evaluator Comment Determines that working the requested future shift will result in exceeding work hour limits.

Working the 1/26 0600-1800 shift would result in the operator exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day CRITICAL STEP*

period. Circles Cannot on the cue __ __

1

Monday, 1/20 though sheet for question #1.

Saturday, 1/25 shows 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months worked.

Working Sunday would result in exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in the 7-day period.

Evaluator Comment CRITICAL STEP*

Documents that working the Identifies work hour limits requested shift would result

in exceeding work hour exceeded if RO #1 works on __ __

2 limits: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day Sunday 1/26, period (Working Sunday would result in exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in the 7-day period).

SRO Admin1 Page 5 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Evaluator Comment Determines that RO #1 has already violated any work hour limits.

The break between shifts

CRITICAL STEP*

from Thursday 1/16 to Friday 3 1/17 was less than the Circles Yes on the cue __ __

required 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months sheet for question #3.

The hours worked Thursday 1/16 to Friday 1/17 were greater than 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months worked in a 48-hour period Evaluator Comment CRITICAL STEP*

Determines and documents

Identifies work hour limits less than a 10-hour break __ __

4a exceeded due to break length. between 1/16 and 1/17 on the cue sheet for question

4.

Evaluator Comment CRITICAL STEP*

Identifies work hour limits Determines and documents

greater than 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months exceeded due to total work __ __

4b worked (actual of 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months ) hours.

in the 48-hour period over 1/16 to 1/17.

Evaluator Comment SRO Admin1 Page 6 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TERMINATING CUE: This JPM is complete when the review is complete, and the cue sheet has been completed. The Examinee is expected to end the JPM.

TIME STOP: _______

SRO Admin1 Page 7 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SRO Admin1 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

SRO Admin1 Page 8 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. The present time/date is 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months on 1/26

2. In accordance with LS-AA-119, Fatigue Management and Work Hour Limits, the Shift Manager has directed the WEC to review the availability of RO #1 to work Dayshift 1/26 for coverage for a downpower for waterbox cleaning.

3. RO #1 was on vacation for two weeks, returning to work on Monday 1/13.

4. RO #1 work history for the previous two weeks is as follows, with all hours having been in posted Licensed Reactor Operator positions.

Monday Tuesday Wednesday Thursday Friday Saturday Sunday 1/13 1/14 1/15 1/16 1/17 1/18 1/19 1800-0600 1800-0600 OFF 1800-1000 1900-0600 OFF OFF 1/20 1/21 1/22 1/23 1/24 1/25 1/26 0600-1800 0600-1800 0600-1800 0600-1800 0600-1800 0600-1800 Request 0600-1800 Initiating Cue:

Using the work history provided:

1. Determine whether RO #1 is able to cover the required shift.

Circle one: Can / Cannot

2. If applicable, document all work hour limits that would be exceeded if RO #1 works Sunday 1/26.

3. Determine whether RO #1 has already violated any work hour limits.

Circle one: Yes / No

4. If applicable, document all work hour limits that have already been exceeded.

SRO Admin1 Page 9 of 9

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-SRO Admin2

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: SRO Admin2 Alternate Path: No Task Number: 201.072 Task

Title:

Ensure adequate shutdown margin exists with all CEAs operable, in Mode 3 Task Standard: Satisfactory task completion is indicated when the candidate reviews the shutdown margin on attachment 2 and documents findings on the cue sheet.

K/A

Reference:

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

Method of Testing: Actual Performance-Classroom Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. NEOP-301, Revision 01600

2. NEOP-23, Revision 035 JPM Setup Instructions:

1. Consumable copy of NEOP-301, Revision 01600

2. Consumable copy of NEOP-23, Revision 035 SRO Admin2 Page 2 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-2 had been operating at 100% power for 100 days when power was reduced, three days ago, for work requiring 21 SGFP to be secured (work still in progress)

2. At 0900 this morning Unit-2 experienced an uncomplicated reactor trip

3. TAVG is stable at 532°F

4. RCS boron concentration is 1225 PPM per a grab sample obtained at 1400

5. Current time, for purposes of this JPM, is 1500

6. Core Burnup is 13,500 MWD/MTU

7. Start-up is anticipated to occur in approximately 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

8. POWERTRAX is currently unavailable

9. You are performing the duties of the Unit-2 CRS Initiating Cue:

EOP-Attachment 13 requires a shutdown margin calculation be performed. The CRO has performed the required calculation, using the figure method, and has asked you to perform the SRO Review of the Shutdown Margin verification.

Are there any questions? You may begin.

1. Can Attachment 2 be signed? (Circle one)

YES NO

2. If No, List the reason(s) why.

3. What Actions, if any, are required, based on your review of the Shutdown Margin Verification worksheet?

SRO Admin2 Page 3 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

Locates NEOP-301, Operator Locates NEOP-301, Operator Surveillance Procedure and Surveillance Procedure and __ __

proceeds to step 4.1.2.3.B proceeds to step 4.1.2.3.B Evaluator Comment NEOP-301, Operator Surveillance Procedure, Section 4.1.2 Independently verify the Using NEOP-301 and NEOP-3.B __ __

information in Attachment 2 23 Evaluator Comment Conducts review of completed CRITICAL STEP*

Attachment 2, Shutdown Margin Circles NO on the cue __ __

1 Verification sheet for question #1.

Evaluator Comment CRITICAL STEP*

Refers to Figure 2-II.A.3 of NEOP-23. Determines

Conducts review and documents required shutdown boron 2 the reasons why attachment 2 concentration is 1256 PPM. __ __

cannot be signed Notes required boron concentration listed on Att.

2 is in error (value for Mode 5 was used).

Evaluator Comment SRO Admin2 Page 4 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

Determines and documents Conducts SDM calculation using that boration at greater than correct data and determines that or equal to 40 gpm of __ __

3 SDM is not met borated water at or above required Shutdown Boron Concentration is required.

Evaluator Comment TERMINATING CUE:

This JPM is complete when the review is complete, and the cue sheet has been completed.

The Examinee is expected to end the JPM.

TIME STOP: _______

SRO Admin2 Page 5 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SRO Admin2 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

SRO Admin2 Page 6 of 8

Appendix C Job Performance Measure Worksheet EXAMINEES CUE SHEET Initial Conditions:

1. Unit-2 had been operating at 100% power for 100 days when power was reduced, three days ago, for work requiring 21 SGFP to be secured (work still in progress)

2. At 0900 this morning Unit-2 experienced an uncomplicated reactor trip

3. TAVG is stable at 532°F

4. RCS boron concentration is 1225 PPM per a grab sample obtained at 1400

5. Current time, for purposes of this JPM, is 1500

6. Core Burnup is 13,500 MWD/MTU

7. Start-up is anticipated to occur in approximately 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

8. POWERTRAX is currently unavailable

9. You are performing the duties of the Unit-2 CRS Initiating Cue:

EOP-Attachment 13 requires a shutdown margin calculation be performed. The CRO has performed the required calculation, using the figure method, and has asked you to perform the SRO Review of the Shutdown Margin verification.

Are there any questions? You may begin.

1. Can Attachment 2 be signed? (Circle one)

YES NO

2. If No, List the reason(s) why.

3. What actions, if any, are required, based on your review of the Shutdown Margin Verification worksheet?

SRO Admin2 Page 7 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 NEOP-301 Revision 16 Page 20 of 24 Page 1 of 1 Attachment 2, Shutdown Margin Verification Sequence # 1 Unit 2 Cycle 23 Reference Method (NEOP (PDIL+ Tavg Actual Boron Shutdown Figure #, CEA Date/Time Of SDM Valid Until Preparer SRO Review BIAS, Mode Burnup Sample Boron Att. And (°F) Position* Sample (Date/Time) (Init/Date/Time) (Init/Date/Time)

Figure, (MWD/MTU) (ppm)** Conc (ppm)

Seq.#,

Basis)

B09680)

Today @ Tomorrow @ DFL Figure 2.II.A.3 3 532 13,500 IN 1225 1202 1400 1400 today @ 1430

Enter IN, OUT, or PDIL, or Group Enter N/A if in MODE 6

- During MODE 6, this Boron Grab Sample is the minimum value of Refueling Pool or filled portion of the RCS.

SRO Admin2 Page 8 of 8

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-SRO Admin3

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: SRO Admin3 Alternate Path: No Task Number: 204.094 Task

Title:

Determine and apply Tech Spec requirements Task Standard: Candidate documents the required isolations, technical specification LCO and actions, and post maintenance testing on the Examinees Cue Sheet.

K/A

Reference:

2.2.41 (3.9) Ability to obtain and interpret station electrical and mechanical drawings.

Method of Testing: Actual Performance-Classroom Validation Time: 20 minutes Time Critical Task: No References and Tools Required:

1. Print 60731SH0003, Rev 0033, Operations DWG Safety Injection and Containment Spray

2. Print 60711, Rev 15, Charcoal Filter Spray System

3. Technical Specification 3.6.6, Amendment No. 326

4. MA-AA-716-012, Rev 23, Post Maintenance Testing JPM Setup Instructions:

1. Consumable copy of print 60731SH0003, Rev 0033, Operations DWG Safety Injection and Containment Spray

2. Consumable copy of print 60711, Rev 15, Charcoal Filter Spray System

3. Consumable copy of Technical Specifications

4. Consumable copy of MA-AA-716-012, Rev 24, Post Maintenance Testing SRO Admin3 Page 2 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 is in Mode 3 at NOP following an uncomplicated Reactor Scram.

2. During a Containment walk through a water leak is observed on 1-CV-4150, 11 CS HDR ISOL CV that requires isolation.

3. Tech Spec 3.6.3 does not apply since 1-CV-4150 is not a Containment Isolation Valve.

4. You are performing the duties of an extra Unit Supervisor.

Initiating Cue:

Using the above plant conditions:

1. List the normally open upstream and downstream mechanical isolation points required to be shut to isolate 1-CV-4150, 11 CS HDR ISOL CV.

2. After 1-CV-4150 is isolated, is Unit 1 in any Technical Specification LCOs (Circle one)?

YES NO

3. If applicable, list any required Technical Specification LCO(s).

SRO Admin3 Page 3 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1

4. If applicable, list the required action(s) and time(s) (assume RICT cannot be implemented).

5. Mechanical maintenance reports that the packing was adjusted back to previous torque to correct the water leak. What post maintenance testing is required per MA-AA-716-012?

SRO Admin3 Page 4 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

CUE Provide the Examinee with required prints and Technical Specifications.

Candidate correctly locates Candidate identifies 1-CV-4150 identifies 1-CV-4150 is on print __ __

is on print 60731SH0003 60731SH0003 Evaluator Comment CRITICAL STEP*

Candidate determines and Candidate determines the documents the following

valves are the necessary required mechanical isolation __ __

1 mechanical isolation points:

points 1-SI-317 1-SI-315 Evaluator Comment CRITICAL STEP*

Candidate determines if Unit-1 is After isolating 1-CV-4150 a in any Technical Specification TS LCO would be __ __

2 LCOs. applicable. Candidate circles YES.

Evaluator Comment CRITICAL STEP*

Candidate determines the Candidate determines and required technical specification documents the required __ __

3 LCOs Technical Specification LCO: 3.6.6.A SRO Admin3 Page 5 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Evaluator Comment CRITICAL STEP*

Candidate determines and documents the required Candidate determines the

Technical Specification LCO required technical specification __ __

4 actions and times:

LCO actions and times Restore containment spray train to operable status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Evaluator Comment CRITICAL STEP*

Candidate determines and Candidate determines the documents the required required post maintenance Post Maintenance Testing: __ __

5 testing Functional Stroke Test Stroke Time Test Evaluator Comment TERMINATING CUE:

This JPM is complete when candidate documents the required isolations, technical specification LCO and actions, and post maintenance testing on the Examinees Cue Sheet.

The Examinee is expected to end the JPM.

TIME STOP: _______

SRO Admin3 Page 6 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SRO Admin3 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

SRO Admin3 Page 7 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 is in Mode 3 at NOP following an uncomplicated Reactor Scram.

2. During a Containment walk through a water leak is observed on 1-CV-4150, 11 CS HDR ISOL CV that requires isolation.

3. Tech Spec 3.6.3 does not apply since 1-CV-4150 is not a Containment Isolation Valve.

4. You are performing the duties of an extra Unit Supervisor.

Initiating Cue:

Using the above plant conditions:

1. List the normally open upstream and downstream mechanical isolation points required to be shut to isolate 1-CV-4150, 11 CS HDR ISOL CV.

2. After 1-CV-4150 is isolated, is Unit 1 in any Technical Specification LCOs (Circle one)?

YES NO

3. If applicable, list any required Technical Specification LCO(s).

4. If applicable, list the required action(s) and time(s) (assume RICT cannot be implemented).

SRO Admin3 Page 8 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1

5. Mechanical maintenance reports that the packing was adjusted back to previous torque to correct the water leak. What post maintenance testing is required per MA-AA-716-012?

SRO Admin3 Page 9 of 9

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-SRO Admin4

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: SRO Admin4 Alternate Path: No Task Number: 079.009 Task

Title:

Administrative actions for RMS inoperability Task Standard: Candidate documents that TS are not applicable and documents the required actions from CY-CA-170-301 (ODCM) and OP-CA-TRM-100 on the Examinees Cue Sheet.

K/A

Reference:

2.3.15 (3.1) Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Method of Testing: Actual Performance-Classroom Validation Time: 20 minutes Time Critical Task: No References and Tools Required:

1. OI-35, Revision 04501, Radiation Monitoring System

2. CY-CA-170-301, Revision 3, Offsite Does Calculation Manual (ODCM)

3. OP-CA-TRM-100, Revision 00300, Technical Requirements Manual (TRM)

4. RP-CA-300-1004, Revision 1, Response to Unavailable Installed Radiation Monitors JPM Setup Instructions:

1. Consumable copy of OI-35, Radiation Monitoring System

2. Consumable copy of CY-CA-170-301, ODCM

3. Consumable copy of OP-CA-TRM-100, Technical Requirements Manual (TRM)

4. Consumable copy of RP-CA-300-1004, Response to Unavailable Installed Radiation Monitors SRO Admin4 Page 2 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit 1 is at 100% power.

2. The U-1 Main Vent RMS is out of service for I&C Maintenance.

3. The U-1 Wide Range Noble Gas Mon Alarm window J-08 on 1C10 has alarmed.

4. The CRO reports that the U-1 Wide Range Noble Gas Monitor has failed.

5. You are performing the duties of the Unit-1 Unit Supervisor.

Initiating Cue:

1. The Shift Manager has directed you to determine the actions required per OI-35 Section 6.10 steps 1a-1d and document on this cue sheet.

2. Are there any questions? You may begin.

Technical Circle one: YES NO Specifications Applicability If Yes, List Technical Specification and required actions.

TRM Circle one: YES NO Applicability If Yes, List TRM and required actions.

ODCM Circle one: YES NO Applicability If Yes, List ODCM and required actions.

SRO Admin4 Page 3 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

Provide the Examinee a copy of OI-35, Radiation Monitoring System, CUE Section 6.10.

Review OI-35 Section 6.10. Reviews OI-35 Section 6.10. __ __

Evaluator Comment NOTE Area RMS when de-energized with alarm locally.

When radiation monitoring equipment is declared out of service or is to be taken out of Determines below steps are 1 __ __

service for maintenance or applicable testing. Then perform the following:

Evaluator Comment NOTE Containment entry is necessary for air samples when BOTH Containment RMS Pumps are OOS, due to the inability of portable equipment to obtain a representative sample.

Notes Table (1) page 180 is 1a Check Table (1) for applicability __ __

applicable Evaluator Comment CRITICAL STEP*

Determines that no Check Technical Specifications 1b Technical Specifications __ __

for applicability apply. Circles NO on the cue sheet.

SRO Admin4 Page 4 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Evaluator Comment CRITICAL STEP*

Determines that the TRM is applicable. Circles YES on the Examinees Cue Sheet.

TRM: 15.3.1.B Actions:

Initiate the preplanned alternate method of monitoring the appropriate Check TRM for applicability parameter within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . __ __

1c Restore the inoperable channel to operable status within 7 days or perform 15.0.3 evaluation.

Inform the Shift Chem Tech and RP Tech to pursue the pre-planned alternate method of monitoring the appropriate parameter per RP-CA-300-1004.

Evaluator Comment SRO Admin4 Page 5 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

Determines that ODCM is applicable. Circles YES on the Examinees Cue Sheet.

ODCM: 3.3.3.9 Actions: Action 37.

With the number of channels Operable less than required by the minimum channels Operable

requirement, effluent Check ODCM for applicability __ __

1d releases via this pathway may continue provided either (1) grab samples are taken and analyzed for gross activity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or (2) an equivalent monitor is provided.

Inform Shift RP Tech to use Alt Pre-planned method of monitoring PER RP-CA-300-1004.

Evaluator Comment TERMINATING CUE:

This JPM is complete when the Candidate documents that TS are not applicable and documents the required actions from CY-CA-170-301 (ODCM) and OP-CA-TRM-100 on the Examinees Cue Sheet.

The Examinee is expected to end the JPM.

TIME STOP: _______

SRO Admin4 Page 6 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SRO Admin4 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

SRO Admin4 Page 7 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit 1 is at 100% power.

2. The U-1 Main Vent RMS is out of service for I&C Maintenance.

3. The U-1 Wide Range Noble Gas Mon Alarm window J-08 on 1C10 has alarmed.

4. The CRO reports that the U-1 Wide Range Noble Gas Monitor has failed.

5. You are performing the duties of the Unit-1 Unit Supervisor.

Initiating Cue:

1. The Shift Manager has directed you to determine the actions required per OI-35 Section 6.10 steps 1a-1d and document on this cue sheet.

2. Are there any questions? You may begin.

Technical Circle one: YES NO Specifications Applicability If Yes, List Technical Specification and required actions.

TRM Circle one: YES NO Applicability If Yes, List TRM and required actions.

ODCM Circle one: YES NO Applicability If Yes, List ODCM and required actions.

SRO Admin4 Page 8 of 8

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-SRO Admin5

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: SRO Admin5 Alternate Path: No Task Number: 204.097 Task

Title:

Determine appropriate emergency response actions per the Emergency Plan while maintaining an overview of plant conditions.

Task Standard: The Operator will implement the Shift Emergency Director Checklist and determine the EAL classification within the Time Critical limit.

K/A

Reference:

2.4.41 (4.6) Knowledge of emergency action level thresholds and classifications.

Method of Testing: Actual Performance-Classroom Validation Time: 20 minutes Time Critical Task: Yes References and Tools Required:

1. EP-CE-111 Rev 008 Emergency Classification and PAR.

2. EP-AA-112-F-57 Rev D Emergency PA Announcements.

3. EP-AA-112-100-F-50 Rev J Shift Emergency Director Checklist.

4. EP-AA-112-100-F-57 Rev H ERONS Notification Details.

5. EP-AA-113-F-53 Rev B Onsite Protective Measures Flowchart.

6. EP-CE-114-100 Rev 08 Emergency Notifications.

7. EP-CE-114-100-F-01 Rev E CCNPP Initial Notification Form.

8. EP-AA-1011 Addendum 3, Rev 5 CCNPP Emergency Action Levels

9. Tech Spec 3.4.15 RCS Specific Activity JPM Setup Instructions:

1. Ensure the references and tools required are available to the operator.

SRO Admin5 Page 2 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 is operating at 100% power MOC.

2. Chemistry sampled the Reactor Coolant System and has confirmed that RCS Coolant Activity is 180 µCi/cc Dose Equivalent I-131.

3. There are no changes to and no rise on the indicating trends of all effluent radiation monitors.

4. You are performing the duties of the Shift Manager.

5. This JPM is Time Critical.

Initiating Cue:

1. You have been called to the Control Room to review the Emergency Action Levels against the current plant conditions and implement EP-AA-112-100-F-50, Shift Emergency Director Checklist, as necessary.

2. Are there any questions? You may begin.

SRO Admin5 Page 3 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

EVALUATOR NOTE

1. Steps from the Shift Managers checklist may be performed in any order other than listed or they may be omitted if not applicable. The steps of this JPM follow the SM checklist in numerical order.

2. The EAL CLOCK starts after candidate reads Initial Conditions CUE sheet.

EAL CLOCK TIME START: ________

EP-AA-112-100-F-50 SHIFT EMERGENCY DIRECTOR CHECKLIST Identify and locate Shift Locates copy of Shift Step Emergency Director Checklist, Emergency Director Checklist __ __

EP-AA-112-100-F-50. EP-AA-112-100-F-50.

Evaluator Comment 1 INITIAL ACTIONS Determines step is applicable. __ __

Evaluator Comment WHEN requested, acknowledge that the Shift Communicator and Dose CUE Assessor are available in the Control Room.

CALL or DIRECT an available Contacts Shift individual to call the Shift Communicator(s) and Shift 1.1 __ __

Communicator(s) and Shift Dose Dose Assessor(s) to report to Assessor(s) to the Control Room. Control Room.

Evaluator Comment If the event is classified as an 1.2 UNUSUAL EVENT, then Determines step is applicable. __ __

PERFORM the following:

SRO Admin5 Page 4 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Evaluator Comment CRITICAL STEP*

RECORD the EAL and Writes down RU3 and the __ __

1.2.A declaration time.

time declared.

Evaluator Comment CRITICAL STEP*

Announces declaration of an UNUSUAL EVENT per RU3 at (time declared) for (the ANNOUNCE the event

reason) and assumes role of classification, possible escalation Shift Emergency Director. __ __

1.2.B paths, and declaration time to the Upgrade Criteria is the Control Room staff.

following Time declared _______

minus EAL Clock Start Time

_______ = 15 minutes Evaluator Comment If the classification is for a 1.2.C Security Event, then GO to Step Determines step is N/A. __ __

4.1 Security Related Events.

Evaluator Comment If operator elects to perform PA Announcements, inform operator the Unit-2 CUE Unit Supervisor will implement PA announcements, using form EP-AA-112-F-57, Emergency PA Announcement, as necessary.

SRO Admin5 Page 5 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD SELECT the Emergency Public Address Announcements from the form and DIRECT Operator will not perform PA 1.2.D performance of the public announcements per above __ __

address announcement within 15 CUE.

minutes of event classification using EP-AA-112-F-57.

Evaluator Comment CRITICAL STEP*

Selects ERONS notification details form.

DIRECT activation of the ERO Circles Calvert Cliffs and __ __

1.2.E using EP-AA-112-100-F-57.

Unusual Event Directs Shift Communicator to Only Notify ERO.

Evaluator Comment If a higher classification is made prior to transmitting an event notification, the notification for the higher classification can supersede the previous event notification, provided that it can be performed within the 15 minute timeframe of the previous Event.

1.2.G NOTE If the notification of a higher classification cannot be performed within the 15 minute timeframe of the previous event, the previous event notification is required within its 15 minute timeframe, and the subsequent event notification is required within its 15 minute timeframe.

DIRECT performance of Fills out Initial Notification State/Local notifications within 15 Form as shown in the 1.2.G minutes of the event following steps, and direct __ __

classification as required per the Shift Communicator to Notifications procedure. transmit.

Evaluator Comment SRO Admin5 Page 6 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD EP-CE-114-100-F-01 INITIAL NOTIFICATION FORM Complete items 1 through 7 as A Completes items 1 through 7 __ __

follows:

Evaluator Comment

CRITICAL STEP*

Drill or Actual Event: __ __

A.1 Checks is a drill Evaluator Comment

CRITICAL STEP*

Facility: __ __

A.2 Checks Unit - 1 Evaluator Comment

CRITICAL STEP*

Classification: __ __

A.3 Checks Unusual Event Evaluator Comment

CRITICAL STEP*

EAL Number: __ __

A.4 Enters RU3 Evaluator Comment CRITICAL STEP*

Classification Declared at: Time entered is time UE __ __

A.5 declared, not current time.

Date is current date.

SRO Admin5 Page 7 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Evaluator Comment CRITICAL STEP*

Radiological Release Status: Checks box for A.6.a, NO __ __

A.6 radiological release in-progress Evaluator Comment CRITICAL STEP*

Protective Action Checks box for A.7.a, __ __

A.7 Recommendation:

None Evaluator Comment

CRITICAL STEP*

Shift ED/Corporate Name: __ __

Step Prints name and signs form Evaluator Comment CRITICAL STEP*

Hands completed form to Shift Communicator and directs to

PROVIDE completed form to notify State and Local Shift Communicator and DIRECT agencies. __ __

Step him/her to notify State and Local. Time to Shift Communicator

_______ minus time EAL declared _______ = _______

( 15 minutes)

Evaluator Comment SRO Admin5 Page 8 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TERMINATING CUE: This JPM is complete when an EAL classification is determined based on given plant conditions, the initial notification form is completed and the CR Communicator has been requested to recall the ERO and to notify offsite agencies. No further actions are required. The evaluator is expected to end the JPM.

TIME STOP: _______

SRO Admin5 Page 9 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SRO Admin5 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

SRO Admin5 Page 10 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 is operating at 100% power MOC.

2. Chemistry sampled the Reactor Coolant System and has confirmed that RCS Coolant Activity is 180 µCi/cc Dose Equivalent I-131.

3. There are no changes to and no rise on the indicating trends of all effluent radiation monitors.

4. You are performing the duties of the Shift Manager.

5. This JPM is Time Critical.

Initiating Cue:

1. You have been called to the Control Room to review the Emergency Action Levels against the current plant conditions and implement EP-AA-112-100-F-50, Shift Emergency Director Checklist, as necessary.

2. Are there any questions? You may begin.

SRO Admin5 Page 11 of 11

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Simulator1

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Simulator1 Alternate Path: Yes Task Number: 055.012 Task

Title:

Exercise Regulating CEAs Task Standard: This JPM is complete when Regulating CEA #54 in Group 1 has been inserted 7.5 inches per STP O-29-1, the reactor tripped per AOP-1B, and RCS boration commenced due to stuck CEAs.

K/A

Reference:

001 A4.03 (4.0, 3.7)

Method of Testing: Actual Performance - Simulator Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. STP O-29-1, CEA Free Movement Test, Revision 01504

2. AOP-1B, CEA Malfunction, Revision 03005

3. EOP-0-1, Post-Trip Immediate Actions, Revision 01300 JPM Setup Instructions:

1. Reset to IC-34 or the previously saved Exam IC with all CEAs at 133.5 inches.

2. Insert the following overrides/malfunctions or open saved schedule file:

a. P1C05_MANINDSEL to ON on Event 1

b. P1C05_MTNINBBYP to ON on Event 1

c. P1C05_CEAOFF to OFF on Event 1

d. P1C05_CEDSMANUAL after 2 to LOWER on Event 1

e. P1C05_REGGRP1SEL to ON on Event 1

f. P1C05_REGGRP1INB to ON on Event 1

g. ceds010_22 at time zero

h. ceds010_49 at time zero

i. ceds010_61 at time zero

3. Select Shutdown Group C on the CEDS Control Panel.

4. Select CEA #53 in Shutdown Group C and CEA #65 in Regulating Group 1 on the CEDS Control Panel.

5. CEAPDS selected to monitor Shutdown Group C.

6. Secondary CEA Position indication, 1-ZI-5501A, set to read CEA #53.

7. PPC Monitor on 1C05 monitoring CEA Position Ladder.

Simulator1 Page 2 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1

8. A PPC Monitor on 1C04 set to monitor Regulating Group 1 position indications.

9. Raise Charging and Letdown and start a second Charging Pump per OI-2A.

10. STP O-29-1 marked with placekeeping and initials, including Shutdown Group attachments, indicating that Section 6.2 Step C is ready to be performed.

11. RO Cart placed by 1C05 to support STP O-29-1.

12. Black dots placed on 1C05 Alarm windows D-29, D-30, D-31, D-32, D-34, D-36.

13. Obtain Independent Verification for completion of steps 1 through 12.

14. Acknowledge all panel alarms and ensure Horn Off for annunciators.

15. Select Clock time.

16. Place simulator in FREEZE.

17. If desired, Save conditions into available Exam IC slot for continued use.

18. The Operator is allowed to prepare for this JPM prior to its administration.

19. When the JPM is ready to commence, place simulator in RUN.

Simulator1 Page 3 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 is at 100% power.

2. STP O-29-1, CEA Free Movement Test, is in progress.

3. Electrical Maintenance was not required to connect any test equipment for the STP.

4. Chemistry has been informed to ensure requirements of CP-204 related to Co-58 are met.

5. All Shutdown CEA Free Movement Testing has been completed per Step 6.1.

6. The pre-job brief has been completed including a review of OI-42, CEDM System Operation, and the pre-identification of all expected alarms.

7. You are performing the duties of the Unit-1 Reactor Operator.

Initiating Cue:

1. The Unit Supervisor directs you to continue with STP O-29-1. You are to begin the Regulating CEA Free Movement Test per Step 6.2, starting with Regulating Group 1 CEA #54.

2. Are there any questions? You may begin.

Simulator1 Page 4 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

After Examinee reviews Cue Sheet, provide the examinee with the CUE prepared copy of STP O-29-1.

STP O-29-1 CEA FREE MOVEMENT TEST, Section 6.2 Regulating CEA Free Movement Test VERIFY that the Regulating CRITICAL STEP*

Group to be tested (1, 2, 3, 4, Selects Group 1 by OR 5) is the only GROUP depressing 1 pushbutton on __ __

C SELECTED on the CEDS the CEDS Control Panel on control panel at 1C05. 1C05.

Comment CRITICAL STEP*

ENSURE MANUAL Selects Manual Individual by INDIVIDUAL MODE of control depressing MI pushbutton __ __

D is SELECTED. on the CEDS Control Panel on 1C05.

Comment NOTE Steps E through M will annunciate the following alarms:

CRITICAL STEP*

VERIFY the INHIBIT BYPASS Selects Group 1 by pushbutton for the Regulating depressing Group 1 Inhibit

Group being tested is the only Bypass pushbutton and __ __

E INHIBIT BYPASS pushbutton verifies no other Group Inhibit SELECTED on the CEDS Bypass pushbuttons are lit on control panel at 1C05. the CEDS Control Panel on 1C05.

Comment Simulator1 Page 5 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

SELECT the desired CEA in Selects CEA #54 by the Regulating Group being depressing 54 pushbutton __ __

F tested. on the CEDS Control Panel on 1C05.

Comment IF required, THEN CHECK that Determines step is N/A based G the Electricians are recording __ __

on initiating cues.

the selected CEA.

Comment CRITICAL STEP*

DEPRESS and HOLD the Depresses and holds CEA master CEA MOTION INHIBIT MOTION INHIBIT BYPASS __ __

H BYPASS pushbutton. pushbutton on the CEDS Control Panel on 1C05.

Comment If referenced or asked:

CUE The Unit Supervisor will enter Tech Spec 3.1.4 if required.

The following step inserts negative reactivity into the Core. Reactor power shall be closely monitored.

CAUTION Insertion of CEAs greater than 7.5 inches causes entry into T.S. 3.1.4, as applicable.

CRITICAL STEP*

WAIT at least five seconds, THEN LOWER the selected Waits at least five seconds,

then places 1-HS-5502 on CEA 7.5 inches using CEDS __ __

I 1C05 to LOWER and inserts MANUAL CONTR, 1-HS-5502 as required. CEA #54 at least 7.5 inches and not more than 15 inches.

Simulator1 Page 6 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment BEGIN ALTERNATE PATH Evaluator Note As the Operator is withdrawing CEA #54 to its normal All Rods Out position, instruct the Simulator Driver to initiate Event #1. This will start an uncontrolled insertion of CEA #54.

CAUTION The following step inserts positive reactivity into the Core. Reactor power shall be closely monitored.

CRITICAL STEP*

Waits at least five seconds, WAIT at least five seconds to then places 1-HS-5502 on allow CEDS coil cycling to 1C05 to RAISE and complete, THEN RAISE the commences withdrawal of

selected CEA into alignment CEA #54.

J with its group as show on both After Director Event #1 is CEA position systems, using inserted by the Simulator CEDS MANUAL CONTR, 1- Driver, recognizes that CEA HS-5502 as required. #54 is now inserting without Operator action using 1C05 CEA position indications.

Comment After stating/reporting that a CEA is continuously moving:

CUE The Unit Supervisor is implementing AOP-1B. Provide the operator with AOP-1B. Direct the candidate to begin at Block Step IV.A on Page 7.

AOP-1B CEA MALFUNCTION,Section IV.A Control CEA Movement and Stabilize the Unit.

IF the CEAs are moving without Pushes the OFF pushbutton operator action, THEN ensure and determines the CEDS 1 __ __

the CEDS Control System is CONTROL PANEL has not turned OFF. turned off on 1C05.

Simulator1 Page 7 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment IF the CEAs continue to move Determines step is applicable 1.1 without operator action, THEN based on the continuous __ __

perform the following actions: insertion of CEA #54.

Comment If the candidate states/recommends the need to trip the reactor:

CUE The Unit Supervisor directs tripping Unit-1 reactor.

CRITICAL STEP*

Trip the Reactor. Depresses both 1-HS-5835 __ __

1.1.a and 1-HS-5836 REACTOR TRIP pushbuttons on 1C05.

Comment CUE The Unit Supervisor directs implementation of EOP-0.

EOP-0 POST-TRIP IMMEDIATE ACTIONS STEP IV.A Verify the Reactivity Control Safety Function is Satisfied Candidate may again depress Depress ONE set of Manual both 1-HS-5835 and 1-HS-1 __ __

REACTOR TRIP buttons. 5836 REACTOR TRIP pushbuttons on 1C05.

Comment Check the Reactor has tripped Verifies the Reactor has by the following: tripped and Start-Up Rate is 2 __ __

Prompt drop in NI power negative using indications on

Negative SUR 1C05.

Simulator1 Page 8 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment Determines more than one Check that NO more than ONE CEA did not fully insert based 3 __ __

CEA is NOT fully inserted. on CEA mimic and secondary indications on 1C05.

Comment When Boration has been commenced, the Immediate Action for this step is NOTE considered complete.

IF more than ONE CEA fails to fully insert, THEN borate the 3.1 Determines step is applicable. __ __

RCS to at least 2300 ppm as follows:

Comment Shut the VCT M/U valve, 1- Verifies 1-HS-2512 on 1C07 is 3.1.a __ __

CVC-512-CV. in the CLOSE position.

Comment CRITICAL STEP*

Open the BA DIRECT M/U Opens 1-CVC-514-MOV by __ __

3.1.b valve, 1-CVC-514-MOV. momentarily rotating 1-HS-2514 to OPEN.

Comment Open the BAST GRAVITY FD valves: Momentarily rotates 1-HS-2508 3.1.c __ __

1-CVC-508-MOV and 1-HS-2509 to OPEN.

1-CVC-509-MOV Simulator1 Page 9 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment Verify the M/U MODE SEL SW, Verifies 1-HS-210 is in the 3.1.d __ __

1-HS-210, is in MANUAL. MANUAL position.

Comment CRITICAL STEP*

Starts at least one Boric Acid Start a BA PP. by momentarily rotating 1- __ __

3.1.e HS-226X and/or 1-HS-226Y to the START position.

Comment Shut the VCT OUT valve, 1- Places 1-HS-2501 in the 3.1.f __ __

CVC-501-MOV. CLOSE position.

Comment Verifies all 3 Charging Pumps are running. May match 13 3.1.g Start ALL available CHG PPs. __ __

Charging Pump handswitch by rotating to the Start position.

Comment TERMINATING CUE: This JPM is complete when the reactor has been tripped and RCS boration commenced. The Evaluator is expected to end the JPM.

TIME STOP: _______

Simulator1 Page 10 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Simulator1 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Simulator1 Page 11 of 12

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 is at 100% power.

2. STP O-29-1, CEA Free Movement Test, is in progress.

3. Electrical Maintenance was not required to connect any test equipment for the STP.

4. Chemistry has been informed to ensure requirements of CP-204 related to Co-58 are met.

5. All Shutdown CEA Free Movement Testing has been completed per Step 6.1.

6. The pre-job brief has been completed including a review of OI-42, CEDM System Operation, and the pre-identification of all expected alarms.

7. You are performing the duties of the Unit-1 Reactor Operator.

Initiating Cue:

1. The Unit Supervisor directs you to continue with STP O-29-1. You are to begin the Regulating CEA Free Movement Test per Step 6.2, starting with Regulating Group 1 CEA #54.

2. Are there any questions? You may begin.

Simulator1 Page 12 of 12

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Simulator2

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Simulator2 Alternate Path: No Task Number: 048.023 Task

Title:

Verify Validity of CIS actuation.

Task Standard: This JPM is complete when Component Cooling is restored to the Reactor Coolant Pumps.

K/A

Reference:

013 A3.01 (3.7, 3.9)

Method of Testing: Actual Performance - Simulator Validation Time: 10 minutes Time Critical Task: No References and Tools Required:

1. 1C08 Alarm Manual, Revision 03600 JPM Setup Instructions:

1. Reset to IC-34 or the previously saved Exam IC with Unit-1 at 100% power.

2. Place simulator in run.

3. Initiate a CIS Channel B using pushbutton on 1C09.

4. Let simulator run only long enough to allow CC flow alarms on RCPs to actuate.

5. Freeze simulator.

6. If desired, Save conditions into available Exam IC slot for continued use.

7. Obtain Independent Verification for completion of steps 1 through 5.

8. Acknowledge all panel alarms and ensure Horn On for annunciators.

9. When the JPM is ready to commence, place simulator in RUN.

Simulator2 Page 2 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 is at 100% power.

2. Annunciator 1C08 Window G-06 Actuation Sys CIS Trip was just received.

3. You are performing the duties of the Unit-1 Control Room Operator.

Initiating Cue:

1. The Unit Supervisor directs you to respond to the alarm per the 1C08 Alarm Manual.

2. Are there any questions? You may begin.

Simulator2 Page 3 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

After Examinee reviews Cue Sheet, provide the examinee with the 1C08 CUE Alarm Manual.

1C08 Alarm Manual, Window G-06 1 CIS A or B actuation. Determines step is applicable. __ __

Comment Observes multiple indications:

Narrow Range pressure

Wide Range pressure DETERMINE the validity of the

RPS Containment pressure CIS by observing alternate 1.a trip units __ __

channels of indication for the same parameter.

Plant Computer indications Determines CIS is invalid based on actual containment pressure.

Comment 1.b IF the CIS is valid, THEN: Determines step is N/A. __ __

Comment Inform candidate that the RO will monitor RCP temperatures and perform CUE step 1.c.1 if necessary.

IF the CIS is invalid, THEN MONITOR the RCPs Controlled Determines RO will monitor 1.c Bleed-off and bearing RCP temperatures based on __ __

temperatures while performing cue provided.

the following:

Simulator2 Page 4 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment CUE When asked by candidate, grant approval to reset CIS.

With Shift Manager or Control Obtains Shift Manager or Unit Room Supervisor approval, 1.c.2 Supervisor approval to reset __ __

RESET the CIS, by performing CIS.

the following:

Comment ENSURE CC CNTMT SUPPLY Places handswitch for 1-CC-1.c.2.a VLV, 1-CC-3832-CV __ __

3832-CV in CLOSE.

handswitch in CLOSE.

Comment ENSURE CC CNTMT RETURN CRITICAL STEP*

VLV, 1-CC-3833-CV Places handswitch for 1-CC- __ __

1.c.2.b handswitch in CLOSE. 3833-in CLOSE.

Comment ENSURE IA CNTMT ISOL 1-Places handswitch for 1-IA-1.c.2.c IA-2080-MOV handswitch in __ __

2080-MOV in CLOSE.

CLOSE.

Comment ENSURE 1-IA-2080-MOV CIS Ensures 1-HS-2080A 1.c.2.d OVERRIDE, 1-HS-2080A __ __

keyswitch is in NORMAL.

handswitch in NORMAL.

Comment Simulator2 Page 5 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

Depresses both CIS RESET

DEPRESS BOTH CIS RESET pushbuttons.

1.c.2.e pushbuttons.

(Only CIS Channel B Reset needs to be depressed to meet critical task)

Comment CRITICAL STEP*

Operator may reference EOP-ATT or the ESFAS Plaque to determine components to realign.

IF CIS is reset, THEN RETURN

Places handswitch for 1-CC-components to their normal __ __

1.c.2.f 3832-CV in OPEN.

status.

Places handswitch for 1-CC-3833-CV in OPEN.

Places handswitch for 1-IA-2080-MOV in OPEN. (Not Critical)

Comment IF CIS did NOT RESET from 1.c.3 Determines step is N/A. __ __

Control Room, Comment TERMINATING CUE: This JPM is complete when CIS is reset and Component Cooling flow is restored to the RCPs. The Evaluator is expected to end the JPM.

TIME STOP: _______

Simulator2 Page 6 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Simulator2 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Simulator2 Page 7 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 is at 100% power.

2. Annunciator 1C08 Window G-06 Actuation Sys CIS Trip was just received.

3. You are performing the duties of the Unit-1 Control Room Operator.

Initiating Cue:

1. The Unit Supervisor directs you to respond to the alarm per the 1C08 Alarm Manual.

2. Are there any questions? You may begin.

Simulator2 Page 8 of 8

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Simulator3

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Simulator3 Alternate Path: Yes Task Number: 201.059 Task

Title:

Monitor RCS Depressurization Task Standard: This JPM is complete when 12 HPSI Pump is placed in service and proper flow is established based on RCS pressure.

K/A

Reference:

006 A4.07 (4.4, 4.4)

Method of Testing: Actual Performance - Simulator Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. EOP-5-1, Loss of Coolant Accident, Revision 03001 JPM Setup Instructions:

1. Reset to IC-34 with both Units at 100% power or the previously saved Exam IC.

2. Place Simulator in FREEZE.

3. Open Event file to trigger Event 3 on the SIAS actuation: P1C08_G05_LTON.

4. Insert Malfunction 200 gpm RCS Controlled Leak: rcs002 to 200 at time zero.

5. Insert Malfunction 13 HPSI Pump Breaker Failure: si002_03 on Event 3.

6. Insert Remote 11 HPSI Pump Breaker: 152-1108_A to RACKED_OUT.

7. Insert Override Alarm Window H-17 11 HPSI Pump SIAS Blocked/Auto Start:

P1C09_H17_LTON to Off.

8. Insert Remote 1-SI-656-MOV Breaker Open: 1-SI-656-MOV to OPEN.

9. Insert Malfunction 10000 gpm RCS Controlled Leak: rcs002 to 800 on Event 1.

10. Insert Override to prevent SIAS A Block: P1C09_1HS5 to NORMAL.

11. Insert Override to prevent SIAS B Block: P1C10_1HS6 to NORMAL.

12. Caution tag 11 HPSI Pump handswitch in Pull-To-Lock.

13. Shut 1-SI-656-MOV and place a Caution tag on the keyswitch.

14. Place a red dot on annunciator window H-17.

15. Place simulator in RUN.

16. Trip Unit-1 Reactor.

17. Isolate Letdown by placing 1-CVC-515-CV and 1-CVC-516-CV in CLOSE.

18. Start all Containment Air Coolers in High speed and Open all CAC SRW Emergency Outlet Valves.

Simulator3 Page 2 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1

19. Obtain Independent Verification for completion of steps 1 through 18.

20. Acknowledge all panel alarms and ensure Horn On for annunciators.

21. Place simulator in FREEZE.

22. If desired, Save conditions into available Exam IC slot for continued use.

23. When the JPM is ready to commence, place simulator in RUN.

Simulator3 Page 3 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. 11 HPSI Pump is tagged out for discharge valve maintenance.

2. 1-SI-656-MOV is tagged shut to support the maintenance.

3. A LOCA occurred on Unit-1 approximately 15 minutes ago.

4. EOP-5 has been implemented.

5. You are performing the duties of the Unit-1 Reactor Operator.

Initiating Cue:

1. The Unit Supervisor directs you to perform EOP-5, Block Step D, Monitor RCS Depressurization.

2. Are there any questions? You may begin.

Simulator3 Page 4 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

After Examinee reviews Cue Sheet, provide the examinee with EOP-5 CUE Block Step D.

EOP-5 BLOCK STEP D, MONITOR RCS DEPRESSURIZATION IF pressurizer pressure is less Determines step is not than or equal to 1725 PSIA OR applicable based on the current 1 containment pressure is greater pressurizer pressure and __ __

than or equal to 2.8 PSIG, containment pressure not THEN verify SIAS actuation. reaching the SIAS setpoints.

Comment IF pressurizer pressure is Determines step is applicable greater than 1725 PSIA AND based on the current containment pressure is less 2 pressurizer pressure and __ __

than 2.8 PSIG, THEN perform containment pressure not the following actions to block reaching the SIAS setpoints.

SIAS:

Comment Open MAIN and AUX HPSI HDR valves:

MAIN

1-SI-616-MOV CRITICAL STEP*

1-SI-626-MOV

Opens the 8 Main and Aux

1-SI-636-MOV __ __

2.a HPSI Header MOVs.

1-SI-646-MOV (Handswitches spring return to AUX the Normal position)

1-SI-617-MOV

1-SI-627-MOV

1-SI-637-MOV

1-SI-647-MOV Comment Simulator3 Page 5 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

Start 11 and 13 HPSI PPs. Rotates 13 HPSI Pump __ __

2.b handswitch to START.

Comment Ensures all three Charging Pumps are running and/or 2.c Start ALL available CHG PPs. __ __

rotates Charging Pump handswitches to START.

Comment Evaluator Note The candidate may perform Steps 2.d and 2.e simultaneously using 2 handed operation. It is also acceptable to perform these steps prior to the alarm actuation.

The Simulator Driver will insert Event 1 to control the timing of the SIAS actuation.

CUE If notified that SIAS PZR Pressure failed to Block, acknowledge report.

Rotates SIAS PRZR PRESS BLOCK CH-A keyswitch to the WHEN the PZR PRESS BLOCK position. (Keyswitch BLOCK A PERMITTED alarm spring returns to the Normal 2.d __ __

is received, THEN block SIAS position)

A.

May notify the US that SIAS failed to Block.

Comment Rotates SIAS PRZR PRESS BLOCK CH-B keyswitch to the WHEN the PZR PRESS BLOCK position. (Keyswitch BLOCK B PERMITTED alarm spring returns to the Normal 2.e __ __

is received, THEN block SIAS position)

B.

May notify the US that SIAS failed to Block.

Simulator3 Page 6 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment BEGIN ALTERNATE PATH IF SIAS has actuated, THEN 3 Determines step is applicable. __ __

perform the following actions:

Comment Determines 13 HPSI Pump Verify the following pumps are failed to start. May note U-1 running: 4KV ESF MOTOR

11 HPSI PP OVERLOAD alarm on 1C18.

3.a

13 HPSI PP __ __

Verifies both LPSI Pumps

11 LPSI PP running at 1C08 and 1C09.

12 LPSI PP Verifies all three Charging

ALL available CHG PPs Pumps running at 1C07.

Comment Verify safety injection flow:

HPSI flow PER ATTACHMENT (10), HIGH Determines no HPSI Pump is 3.b PRESSURE SAFETY operating and that HPSI flow is __ __

INJECTION FLOW, when insufficient.

pressure is below 1270 PSIA Comment Perform the following actions as necessary: Determines step is not 3.b.1 __ __

IF 11 HPSI PP failed, THEN applicable.

start 12 HPSI PP.

Simulator3 Page 7 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment

IF 13 HPSI PP failed, THEN 3.b.1 align 12 HPSI PP as Determines step is applicable. __ __

follows:

Comment

CRITICAL STEP*

Start 12 HPSI PP. __ __

(1) Starts 12 HPSI Pump.

Comment CRITICAL STEP*

Open HPSI HDR XCONN Places 1-SI-653-MOV __ __

(2) valve, 1-SI-653-MOV.

keyswitch in OPEN.

Comment Shut HPSI HDR XCONN valve, Places 1-SI-655-MOV (3) __ __

1-SI-655-MOV. keyswitch in CLOSE.

Comment TERMINATING CUE: This JPM is complete when 12 HPSI Pump is started and flow established by opening 1-SI-653-MOV. The Evaluator is expected to end the JPM.

TIME STOP: _______

Simulator3 Page 8 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Simulator3 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Simulator3 Page 9 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. 11 HPSI Pump is tagged out for discharge valve maintenance.

2. 1-SI-656-MOV is tagged shut to support the maintenance.

3. A LOCA occurred on Unit-1 approximately 15 minutes ago.

4. EOP-5 has been implemented.

5. You are performing the duties of the Unit-1 Reactor Operator.

Initiating Cue:

1. The Unit Supervisor directs you to perform EOP-5, Block Step D, Monitor RCS Depressurization.

2. Are there any questions? You may begin.

Simulator3 Page 10 of 10

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Simulator4

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Simulator4 Alternate Path: Yes Task Number: 202.026 Task

Title:

Attempt to Correct the Abnormal SDC Condition Task Standard: This JPM is complete when SDC flow is restored using a Containment Spray Pump per AOP-3B.

K/A

Reference:

005 A4.01 (3.6, 3.4)

Method of Testing: Actual Performance - Simulator Validation Time: 20 minutes Time Critical Task: No References and Tools Required:

1. AOP-3B-1, Abnormal Shutdown Cooling Conditions, Revision 03001 JPM Setup Instructions:

1. Reset to IC-07 with Unit-1 is Mode 5 with a PZR Manway removed with the RCS at 110°F and 14.7 PSIA, or the previously saved Exam IC.

2. Set Event Trigger 11 LPSI Pump Start for Event 3: P1C08_1HS302X_SWSTART.

3. Insert Malfunction 11 LPSI Pump Breaker Failure: si003_01 on Event 3.

4. Insert Malfunction 12 LPSI Pump Breaker Failure: si003_02 on Event 1.

5. Insert Remote 11 CS Pump Discharge valve open: 1-SI-314 to 1.0 on Event 2.

6. Insert Remote 11 LPSI Pump RWT Suction valve open: 1-SI-444 to 1.0 on Event 2.

7. Place 12 CS Pump in PTL with an INFO tag.

8. Place a red dot on 1C09 Alarm Window H30, 12 CS Pump SIAS Blocked Auto Start.

9. Insert Override 12 CS Pump in PTL: P1C09_1HS4147 to PTL at time zero.

10. Insert Remote 12 CS Pump breaker racked out: 152-1407_B to RACKED_OUT at time zero.

11. Insert Override Alarm Window H30: P1C09_H30_LTON to Off at time zero.

12. Place Simulator in RUN.

13. Bypass CVCS IXs by placing 1-HS-2520 in the BYP position.

14. Activate Event 1.

15. Place Simulator in FREEZE.

16. Obtain Independent Verification for completion of steps 1 through 15.

17. If desired, Save conditions into available Exam IC slot for continued use.

Simulator4 Page 2 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1

18. Acknowledge all panel and plant computer alarms.

19. Select Horn On for annunciators.

20. Select Clock time.

21. When cued by the Examiner, place simulator in RUN.

22. When directed, activate Event 2 to open 1-SI-314 and 1-SI-444. Report complete after agreed upon delay.

Simulator4 Page 3 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 has been shut down for 5 days and is presently in Mode 5 to repair RCS instrumentation sensing lines.

2. Shutdown Cooling is in service, using 12 LPSI Pump, and RCS temperature is 110°F.

3. RCS pressure is 14.7 PSIA with the Pressurizer Manway removed.

4. The ABO reported smoke coming from 12 LPSI Pump motor.

5. 12 LPSI Pump Breaker has just tripped.

6. You are performing the duties of the Unit-1 Reactor Operator.

Initiating Cue:

1. The Unit Supervisor directs you to respond to the Loss of Shutdown Cooling per AOP-3B, Abnormal Shutdown Cooling Conditions, starting in Section IV, Step A.6.

2. Are there any questions? You may begin.

Simulator4 Page 4 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

CUE After Examinee reviews Cue Sheet, provide the examinee with AOP-3B-1.

AOP-3B, SECTION IV, PRELIMINARY IF SDC is lost due to failure of Determines step is applicable.

the operating LPSI PP, AND Determines 12 LPSI Pump A.6 the cause will NOT result in a __ __

failure will not result in a common mode failure, THEN common mode failure.

complete the following actions:

Comment Placed the failed PP A.6.a Places 12 LPSI in PTL. __ __

handswitch in PULL TO LOCK.

Comment IF RCS purification is in Determines step is not service, THEN place IX BYP A.6.b applicable. May verify 1-HS- __ __

valve handswitch 1-HS-2520 in 2520 is in the BYP position.

the BYP position.

Comment CRITICAL STEP*

Lowers output of 1-HIC-3657

Shut S/D COOLING TEMP on 1C09 to 0%

A.6.c CONTR valve, 1-SI-657-CV. and/or Places 1-HS-3657 keyswitch on 1C09 to CLOSE.

Comment Simulator4 Page 5 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

Place the SHUTDOWN CLG Depresses the A/M FLOW CONTR, 1-FIC-306, in pushbutton until M is __ __

A.6.d MANUAL. displayed to shift 1-FIC-306 on 1C08 to MANUAL (ML).

Comment Adjust the output of the CRITICAL STEP*

SHUTDOWN CLG FLOW Adjusts output of 1-FIC-306 __ __

A.6.e CONTR, 1-FIC-306, to 95%. to between 93% and 97%.

Comment Verify BOTH RAS OVERRIDE switches in OVERRIDE:

Verifies 1-HS-302XA and 1-A.6.f

11 LPSI PP RAS HS-302YA keyswitches are in __ __

OVERRIDE, 1-HS-302XA the OVERRIDE position.

12 LPSI PP RAS OVERRIDE, 1-HS-302YA Comment CAUTION Before starting the standby LPSI PP, the cause for the running LPSI PP failure should be determined to preclude a common mode failure.

CRITICAL STEP*

Rotates 11 LPSI Pump handswitch to the START position.

Start the standby LPSI PP. Determines that 11 LPSI Pump __ __

A.6.g failed to start and alternate actions are required.

May place 11 LPSI Pump in PTL.

Simulator4 Page 6 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment BEGIN ALTERNATE PATH After candidate determines step is applicable:

Unit Supervisor has assigned an extra operator to perform Step B, Page 18.

CUE Unit Supervisor reports Steps C.1 through C.4 have been completed and directs you to begin at Step C.5.

IF the standby LPSI PP does NOT start, THEN assign an Determines step is applicable operator to perform B (Page A.6.g.1 and Step C is the next required __ __

18), AND concurrently step based on cues provided.

PROCEED to Step C (Page 21).

Comment IF NO LPSI PPS are available, C.5 THEN align the CS PPs for Determines step is applicable. __ __

cooling.

Comment To prevent CS PP shaft seal and bearing damage, RCS temperature shall CAUTION be less than 120°F OR the associated ECCS Pump Room Air Cooler shall be functional.

Verify RCS temperature less Verifies that ECCS Pump than 120°F OR the associated C.5.a Room Air Coolers are not Out __ __

ECCS PP Room Air Cooler is of Service.

functional.

Comment Simulator4 Page 7 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CAUTION To prevent over pressurization of the ECCS PP suction headers, RCS pressure shall be less than 170 PSIA.

Check that RCS pressure is Verifies RCS pressure is less C.5.b __ __

less than 170 PSIA. than 170 PSIA.

Comment Check that the SDC HDR RETURN ISOL valves are open: Verifies that 1-SI-651-MOV and C.5.c __ __

1-SI-652-MOV are open.

1-SI-651-MOV

1-SI-652-MOV Comment CRITICAL STEP*

Shut the 11 RWT OUT valves: Places the following

1-SI-4142-MOV handswitches in CLOSE: __ __

C.5.d

1-SI-4143-MOV

1-SI-4142-MOV

1-SI-4143-MOV Comment Isolate CS PP Min Flow to the CRITICAL STEP*

RWT:

Places the following

Place the SI PP RECIRC handswitches to ON: __ __

C.5.e.1 LOCKOUT handswitches to ON

1-HS-3659A

1-HS-3659A

1-HS-3660A

1-HS-3660A Comment Simulator4 Page 8 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

Shut the MINI FLOW RETURN TO RWT ISOL valves: Places the following handswitches to CLOSE: __ __

C.5.e.2

1-SI-659-MOV

1-SI-660-MOV

1-SI-659-MOV

1-SI-660-MOV Comment When the candidate directs an Equipment Operator to perform this step:

CUE Direct the simulator driver to activate Event 2 to open 1-SI-314 and 1-SI-444.

IF 11 CS PP is desired for SDC, THEN open the following valves:

Directs an operator to open 1-C.5.f

11 CS PP Discharge valve, __ __

SI-314 and 1-SI-444.

1-SI-314

11 LPSI PP NORM SUCT ISOL valve, 1-SI-444 Comment C.5.g IF 12 CS PP is desired Determines step is N/A. __ __

Comment Verifies the output of 1-HIC-3657 on 1C09 is 0%

Shut the S/D COOLING TEMP C.5.h and/or __ __

CONTR valve, 1-SI-657-CV.

1-HS-3657 keyswitch on 1C09 is in CLOSE.

Comment Simulator4 Page 9 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Place the SHUTDOWN CLG Verifies 1-FIC-306 on 1C08 is C.5.i FLOW CONTR, 1-FIC-306, in __ __

in MANUAL (ML).

MANUAL.

Comment Adjust the output of the Verifies the output of 1-FIC-306 C.5.j SHUTDOWN CLG FLOW is set to between 93% and __ __

CONTR, 1-FIC-306, to 95%. 97%.

Comment

CRITICAL STEP*

Start the selected CS PP. __ __

C.5.k Starts 11 CS Pump.

Comment Slowly adjust the SHUTDOWN CRITICAL STEP*

CLG FLOW CONTR, 1-FIC- Adjusts the output of 1-FIC- __ __

C.5.l 306, to raise SDC flow to 1500 306 and raises SDC flow to

- 2000 GPM. between 1500 and 2000 gpm.

Comment The Unit Supervisor desires Shutdown Cooling Flow Controller, 1-FIC-306, CUE be placed in auto.

IF desired to place SHUTDOWN CLG FLOW Determines step is applicable C.5.m __ __

CONTR, 1-FIC-306 in AUTO, based on the cue provided.

THEN perform the following:

Comment Simulator4 Page 10 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Adjust the setpoint of 1-FIC-Adjust the setpoint on 1-FIC-C.5.m.1 306 to between 1500 and 2000 __ __

306 to match SDC flow.

gpm.

Comment Depresses the A/M pushbutton C.5.m.2 Place 1-FIC-306 in AUTO. to shift 1-FIC-306 on 1C08 to AUTO (AL).

Comment Do NOT exceed the following cooldown limits in any one hour:

CAUTION Do NOT exceed a heatup rate of 14°F/MIN for the Shutdown Cooling Heat Exchanger as indicated on TI-303X and TI-303Y.

Establishes SDC flow through the SDC Heat Exchangers by Adjust the S/D COOLING adjusting output of 1-HIC-3657 C.5.n TEMP CONTR VALVE, 1-SI- __ __

on 1C09 greater than 0% and 657-CV, as desired.

taking 1-HS-3657 keyswitch on 1C09 to AUTO.

Comment TERMINATING CUE: This JPM is complete when SDC flow has been restored using 11 Containment Spray Pump to between 1500 and 2000 gpm. The Evaluator is expected to end the JPM.

TIME STOP: _______

Simulator4 Page 11 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Simulator4 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Simulator4 Page 12 of 13

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 has been shut down for 5 days and is presently in Mode 5 to repair RCS instrumentation sensing lines.

2. Shutdown Cooling is in service, using 12 LPSI Pump, and RCS temperature is 110°F.

3. RCS pressure is 14.7 PSIA with the Pressurizer Manway removed.

4. The ABO reported smoke coming from 12 LPSI Pump motor.

5. 12 LPSI Pump Breaker has just tripped.

6. You are performing the duties of the Unit-1 Reactor Operator.

Initiating Cue:

1. The Unit Supervisor directs you to respond to the Loss of Shutdown Cooling per AOP-3B, Abnormal Shutdown Cooling Conditions, starting in Section IV, Step A.6.

2. Are there any questions? You may begin.

Simulator4 Page 13 of 13

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Simulator5

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Simulator5 Alternate Path: No Task Number: 012.007 Task

Title:

Placing Emergency SW Discharge Header in Service Task Standard: This JPM is complete when 12 Saltwater Header has been aligned to the SW Emergency Overboard Discharge Header per AOP-7A.

K/A

Reference:

076 A4.04 (3.5, 3.5)

Method of Testing: Actual Performance - Simulator Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. AOP-7A, Loss of Saltwater Cooling, Revision 15 JPM Setup Instructions:

1. Reset to IC-34 or the previously saved Exam IC.

2. Place Simulator in RUN.

3. Insert SW Rupture, sw004_02 at 50% at time zero.

4. Reduce MVARs to 0.

5. Ensure handswitches 1-HS-5150, 1-HS-5209, 1-HS-5210, 1-HS-5152, 1-HS-5211, 1-HS-5212, 1-HS-5153 are in CLOSE as directed by Section V.D, Step 4.

6. Place Simulator in FREEZE.

7. Obtain Independent Verification for completion of steps 1 through 5.

8. If desired, Save conditions into available Exam IC slot for continued use.

9. Acknowledge all panel and plant computer alarms.

10. Select Horn On for annunciators.

11. Select Clock time.

12. When cued by the Examiner, place simulator in RUN.

13. Have AOP-7A, Attachment 2 ready.

Simulator5 Page 2 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 is at 100% power

2. AOP-7A, Loss of Saltwater Cooling, has been implemented.

3. A rupture downstream of 1-SW-5153-CV, 12A/B SRW HX SW OUT, has been diagnosed.

4. You are performing the duties of the Unit-1 Control Room Operator.

Initiating Cue:

1. The Unit Supervisor directs you to perform AOP-7A, Attachment 2, Use of the Emergency Return Discharge Header.

2. Are there any questions? You may begin.

Simulator5 Page 3 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

After Examinee reviews Cue Sheet, provide the examinee with AOP-7A, CUE Attachment 2.

AOP-7A, Attachment 2, Use of the Emergency Return Discharge Header When requested, TS 3.0.3 has been entered and the US is handling all the CUE required actions.

NOTE The use of the Emergency Return Discharge Header renders both SW Headers inoperable.

Therefore, TS 3.0.3 applies, and the Unit must be in Hot Standby within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

NOTE This attachment establishes 12 SRW HX, 12 CC HX and 12 ECCS Cooler in service with 11 SW Supply Header as a discharge path via the Emergency Discharge valve 1-SW-5149-CV.

Expedite restoration of the cooling to 12 SRW HX and 12 CC HX while shifting discharge path.

CAUTION When using the Emergency Discharge Return Header, there is NO temperature control of 12 CC HX.

Ensure open 12 CC HX CC 1 Verifies that 1-CC-3826 is open __ __

OUT valve, 1-CC-3826-CV Comment Ensure open 11 CC HX CC 2 Verifies that 1-CC-3824 is open __ __

OUT valve, 1-CC-3824-CV Comment CRITICAL STEP*

Shut 11 CCHX SW OUT valve, Places controller for 1-SW- __ __

3 1-SW-5206-CV. 5206 to 100% which is full closed.

Simulator5 Page 4 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment When requested, report that an operator is securing SWCA injection to 11 CUE and 12 SW headers per OI-29A.

IF in service, THEN DISPATCH an operator to secure SWCA Directs an operator to secure injection to 11 AND 12 SW 4 SWCA injection to 11 and 12 __ __

HDR's, PER OI-29A, SALT SW headers per OI-29A.

WATER CHEMICAL ADDITION SYSTEM.

Comment NOTE Step 5 should be performed concurrently with the remaining steps in this attachment.

When requested, report that an operator is removing 11 SRW HX from CUE service per attachment 1.

Remove 11 SRW HX from service PER ATTACHMENT Directs an operator to remove 5 (1), REMOVING SRW HXs 11 SRW HX from service per __ __

FROM SERVICE, Step 1 (Page attachment 1.

45).

Comment CRITICAL STEP*

Verify the operating SW PP on Places handswitch 1-HS- __ __

6 11 SW Header is stopped.

5199 in stop.

Comment Simulator5 Page 5 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Open the Emergency Outlet valves, on panel 2C24A:

(12 ECCS AIR CLR) 1-SW- CRITICAL STEP*

5177-CV and 1-SW-5178-CV using 1-HS-5179 Places the following

handswitches to OPEN:

(12 CC HX) 1-SW-5165-CV __ __

7

1-HS-5179 and 1-SW-5166-CV using 1-HS-5167

1-HS-5167

1-HS-5155 (12 SRW HX), 1-SW-5155-CV and 1-SW-5156-CV using 1-HS-5155 Comment WHEN the Emergency SW Discharge Valve, 1-SW-5149, is open, THEN shut the following valves on 12 SW HDR: CRITICAL STEP*

(12 ECCS AIR CLR) 1-SW- Places the following

5174-CV and 1-SW-5175-CV handswitches to CLOSE:

8 using 1-HS-5176

1-HS-5176 (12 CC HX) 1-SW-5163-CV

1-HS-5164 and 1-SW-5208-CV using 1-

1-HS-5153 HS-5164 (12 SRW HX) 1-SW-5153-CV using 1-HS-5153 Comment Simulator5 Page 6 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Shut the following valves on 11 SW HDR:

(11 ECCS AIR CLR) 1-SW- CRITICAL STEP*

5170-CV and 1-SW-5171-CV using 1-HS-5172 Places the following

handswitches to OPEN:

9 (11 CC HX) 1-SW-5160-CV and 1-SW-5206-CV using 1-

1-HS-5172 HS-5161

1-HS-5161

1-HS-5150 (11 SRW HX) 1-SW-5150-CV and 1-SW-5154-CV using 1-HS-5150 Comment IF a SW PP is NOT running on 12 SW header, THEN start a Determines that step is not 10 SW PP on 12 SW header as applicable follows:

Comment Simulator5 Page 7 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD

11. Verify the following valves are OPEN OR in AUTO:

EMERGENCY SW DISCH, 1-SW-5149-CV Verifies the following valves

(12 SRW HX) are Open or in Auto:

1-SW-5152-CV

1-SW-5149-CV 1-SW-5211-CV

1-SW-5152-CV 1-SW-5212-CV

1-SW-5211-CV

1-SW-5212-CV 11 1-SW-5155-CV

1-SW-5155-CV 1-SW-5156-CV

1-SW-5156-CV (12 CC HX)

1-SW-5162-CV

1-SW-5165-CV 1-SW-5162-CV

1-SW-5166-CV 1-SW-5165-CV

1-SW-5173-CV

1-SW-5177-CV 1-SW-5166-CV (12 ECCS AIR CLR) 1-SW-5173-CV 1-SW-5177-CV Comment Verify adequate SW flow to SRW HXs. Verifies that the 12A/12B SRW 12 HX TROUBLE alarm is clear

a. Check "12A/12B SRW HX on 1C13.

TROUBLE" alarm clear.

Comment TERMINATING CUE: This JPM is complete when 12 Saltwater System has been aligned to the Emergency SW Discharge Header. The Evaluator is expected to end the JPM.

TIME STOP: _______

Simulator5 Page 8 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Simulator5 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Simulator5 Page 9 of 10

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 is at 100% power

2. AOP-7A, Loss of Saltwater Cooling, has been implemented.

3. A rupture downstream of 1-SW-5153-CV, 12A/B SRW HX SW OUT, has been diagnosed.

4. You are performing the duties of the Unit-1 Control Room Operator.

Initiating Cue:

1. The Unit Supervisor directs you to perform AOP-7A, Attachment 2, Use of the Emergency Return Discharge Header.

2. Are there any questions? You may begin.

Simulator5 Page 10 of 10

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Simulator6

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Simulator6 Alternate Path: No Task Number: 064.023 Task

Title:

Verify Reactor and Pressurizer Vent Valve Operability Task Standard: This JPM is complete when the Reactor Vessel Vent Valves are cycled, then Quench Tank pressure is restored to normal per OI-1B.

K/A

Reference:

007 A4.04 (2.6, 2.6)

Method of Testing: Actual Performance - Simulator Validation Time: 10 minutes Time Critical Task: No References and Tools Required:

1. STP O-66L-1, Reactor Vessel and Pressurizer Vent Valves Operability Test, Revision 00701 JPM Setup Instructions:

1. Reset to the previously saved IC with Unit-1 in Mode 4 with RCS Pressure between 400 and 1200 PSIA.

2. Place Simulator in FREEZE.

3. Obtain Independent Verification for completion of steps 1 through 2.

4. Obtain and insert keys in PZR to Quench Tank Vent Valve keyswitches, 1-HS-105 and 1-HS-106.

5. Place 1P116 Quench Tank Pressure, 1T116 Quench Tank Temperature, and 1L116 Quench Tank Level on trend on the 1C05 PPC screen.

6. Ensure the starting Quench Tank parameters match the completed STP O-66L-1 Section 6.4 initial parameters recorded.

7. Acknowledge all panel and plant computer alarms.

8. Select Horn On for annunciators.

9. Select Clock time.

10. When cued by the Examiner, place simulator in RUN.

11. Have STP O-66L-1 Section 6.4 ready for use with initial Quench Tank parameters recorded and placekeeping performed to start with Step 6.4.3.

Simulator6 Page 2 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 is in the process of shutting down for a scheduled Refueling Outage and is currently in Mode 4.

2. The Control Room is performing STP O-66L-1, Reactor Vessel and Pressurizer Vent Valves Operability Test, and Sections 6.1, 6.2, and 6.3 have just been completed.

3. The initial Quench Tank parameters have been recorded in Section 6.4.

4. The pre-job brief is complete, all precautions reviewed, and prerequisites met.

5. You are performing the duties of the Unit-1 Control Room Operator.

Initiating Cue:

1. The Unit Supervisor directs you to perform STP O-66L-1, Section 6.4, starting with Step 6.4.3.

2. Are there any questions? You may begin.

Simulator6 Page 3 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

After Examinee reviews Cue Sheet, provide the examinee with the CUE prepared copy of STP O-66L-1 Section 6.4.

STP O-66L-1, Section 6.4, PZR Vapor Space Vent Valves Position Indication and Vent Path Operability Tests Fluid buildup in the valve control chamber could cause the open stroke of NOTE the valve to take as long as 8 seconds.

OPEN PZR TO QT VENT, 1-Places keyswitch 1-HS-105 to 6.4.3 RC-105-SV by placing 1-HS-105 __ __

OPEN.

keyswitch to OPEN.

Comment Fluid buildup in the valve control chamber could cause the open stroke of NOTE the valve to take as long as 8 seconds.

OPEN PZR TO QT VENT B/U, CRITICAL STEP*

1-RC-106-SV by placing 1-HS- *Places keyswitch 1-HS-106 __ __

6.4.4 106 keyswitch to OPEN. to OPEN.

Comment The following step will demonstrate the Operability of the PZR Vapor Space NOTE Vent Valves as a RCS Vent Path AND satisfy the open Position Indication Test for the PZR Vapor Space Vent Valves.

VERIFY flow through 1-RC-105- Determines there is flow SV AND 1-RC-106-SV by through the PZR Vent Valves 6.4.5 observing an increase in TIA- by observing an increase in __ __

102 temperature AND/OR TIA-102 and/or Quench Tank Quench Tank parameters. parameters.

Comment Simulator6 Page 4 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD PERFORM the shut Position Indication Test for the PZR Vapor Space Vent Valves as

CRITICAL STEP*

follows:

6.4.6.1. Places keyswitch 1-HS-105 __ __

a 1. Shut Position Indication Test to CLOSE.

for 1-RC-105-SV:

a. SHUT PZR TO QT VENT, 1-RC-105-SV.

Comment VERIFY there is no flow through Determines there is no flow 1-RC-105-SV by observing a through the PZR Vent Valves 6.4.6.1.

decrease in TIA-102 by observing a decrease in __ __

b temperature AND/OR Quench TIA-102 and/or Quench Tank Tank parameters. parameters.

Comment CRITICAL STEP*

OPEN 1-RC-105-SV. *Places keyswitch 1-HS-105 __ __

6.4.6.2 to OPEN.

Comment VERIFY flow through 1-RC-105- Determines there is flow SV AND 1-RC-106-SV by through the PZR Vent Valves 6.4.6.3 observing an increase in TIA- by observing an increase in __ __

102 temperature AND/OR TIA-102 and/or Quench Tank Quench Tank parameters. parameters.

Comment

2. Shut Position Indication Test CRITICAL STEP*

for 1-RC-106-SV:

6.4.6.4. Places keyswitch 1-HS-106 __ __

a. SHUT PZR TO QT VENT a to CLOSE.

B/U, 1-RC-106-SV.

Simulator6 Page 5 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment VERIFY there is no flow through Determines there is no flow 1-RC-106-SV by observing a through the PZR Vent Valves 6.4.6.4.

decrease in TIA-102 by observing a decrease in __ __

b temperature AND/OR Quench TIA-102 and/or Quench Tank Tank parameters. parameters.

Comment Places keyswitch 1-HS-105 to 6.4.6.5 SHUT 1-RC-105-SV. __ __

CLOSE.

Comment Steps 6.4.6.6 and 6.4.6.7 are necessary to eliminate a hydraulic lock NOTE between 1-RC-105 and 1-RC-106.

Places keyswitch 1-HS-106 to 6.4.6.6 OPEN 1-RC-106-SV. __ __

OPEN.

Comment Places keyswitch 1-HS-106 to 6.4.6.7 SHUT 1-RC-106-SV. __ __

CLOSE.

Comment TERMINATING CUE: This JPM is complete when Section 6.4 has been completed to test the PZR Vapor Space Vent Valves. The Evaluator is expected to end the JPM.

TIME STOP: _______

Simulator6 Page 6 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Simulator6 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Simulator6 Page 7 of 8

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 is in the process of shutting down for a scheduled Refueling Outage and is currently in Mode 4.

2. The Control Room is performing STP O-66L-1, Reactor Vessel and Pressurizer Vent Valves Operability Test, and Sections 6.1, 6.2, and 6.3 have just been completed.

3. The initial Quench Tank parameters have been recorded in Section 6.4.

4. The pre-job brief is complete, all precautions reviewed, and prerequisites met.

5. You are performing the duties of the Unit-1 Control Room Operator.

Initiating Cue:

1. The Unit Supervisor directs you to perform STP O-66L-1, Section 6.4, starting with Step 6.4.3.

2. Are there any questions? You may begin.

Simulator6 Page 8 of 8

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Simulator7

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Simulator7 Alternate Path: No Task Number: 024.005 Task

Title:

Shutdown a Diesel Generator Task Standard: This JPM is complete when 1A EDG has been shutdown and removed from the 11 4KV bus.

K/A

Reference:

064 A4.06 (3.9/3.9)

Method of Testing: Actual Performance - Simulator Validation Time: 10 minutes Time Critical Task: No References and Tools Required:

1. OI-21A-1, Rev 02401 JPM Setup Instructions:

1. Reset to IC-34 with both Units at 100% power or the previously saved Exam IC.

2. Insert the following malfunctions:

a. 1A DG alarm window M-06 on 1C18: P1C18_M06_LTON to ON at time zero.

b. 1A DG alarm window AA01 on 1C18A: P1C18A_AA1_LTON to ON at time zero.

3. 0C DG 4KV Bus 11 Disconnect: 189-1106 to CLOSED at time zero.

4. Place a PINK off normal component tag near the Control Room indication for Disconnect 189-1106.

5. Place 0C DG Bus Feeder Breakers, 1-CS-152-1406, 2-CS-152-2106, and 2-CS-152-2406 in PTL with PINK off normal component tag.

6. Place RMS alarm for 0-RI-5350 in bypass on 1C22H.

7. Start 11 and 12 Post LOCI filter fans, ensure 12 CR HVAC in service, and shift 13 IRU to 14 480V bus.

8. Place the 1A DG on 11 4KV Bus at 5.0 MW, 500 MVAR (Depress emergency start, depress slow start, insert sync stick, momentarily raise speed, parallel, remove sync stick and return to home base, raise speed to 5 MW, adjust voltage)

9. Provide a copy of STP O-8A-1 completed up to Step 6.8.E.

10. Provide OI-21A Section 6.5.4 open with the STP for rapid shutdown preps for the 1A DG.

11. Place Simulator in Run.

12. Obtain Independent Verification for completion of steps 1 through 10.

Simulator7 Page 2 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1

13. Acknowledge all panel alarms and ensure Horn Off for annunciators.

14. If desired, Save conditions into available Exam IC slot for continued use.

15. Place Simulator in Freeze.

16. When the JPM is ready to commence, place simulator in RUN.

Simulator7 Page 3 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 is operating at 100% power.

2. 1A DG is OOS for cylinder inspections.

3. STP O-008A-1 is being performed to return the EDG to service.

4. 1A DG has been loaded for 5 MWe for the last 20 minutes.

5. 1 minute ago, the 1A DG CONTR BOARD 1C18A and the 1A DG alarms were received.

6. The local EDG operator has reported a lube oil leak and recommended a rapid shutdown of the 1A EDG.

7. You are performing the duties of the Unit-1 Control Room Operator.

Initiating Cue:

1. The Unit Supervisor directs you to perform a rapid shutdown of the 1A EDG per OI-21A, Section 6.5.4.

2. Are there any questions? You may begin.

Simulator7 Page 4 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

OI-21A, Section 6.5.4 Rapid Shutdown of the 1A Diesel 1A DG is operating in parallel operation with the 11/17 4KV Determines the initial condition A.1 Bus OR unloaded AND a is met from the initial __ __

condition exists that requires a conditions.

rapid shutdown.

Comment CUE If requested, report the 1A DG is not in Local.

Determines the initial A.2 The 1A DG is NOT in Local. conditions is met from the initial __ __

conditions or the above cue.

Comment NOTE Steps 1 and 2 may be worked in parallel IF 1A DG is running with a SIAS signal present, THEN Determines step is not ENSURE actuation modules applicable due to no SIAS B.1 alarm on 1C08. __ __

are reset locally (at the ESFAS cabinets) prior to 1A DG shutdown.

Comment IF 1A DG is in parallel operation with the 11/17 4KV Determines that step is B.2 __ __

Bus, THEN PERFORM the applicable.

following:

Simulator7 Page 5 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment NOTE Load may be lowered as rapidly as necessary.

LOWER MW AND KVAR loads concurrently to approximately CRITICAL STEP*

0.70 MW AND zero KVARs B.2.a.1 PER the following: Lowers MW load to 0.7 MW using 1-CS-1705.

LOWER MW load using 1A DG SPEED CONTR, 1-CS-1705.

Comment LOWER MW AND KVAR loads concurrently to approximately 0.70 MW AND zero KVARs PER the following: CRITICAL STEP*

MAINTAIN 0 to 500 KVARs Lowers KVARs to ~0 KVARS B.2.a.2 using 1A DG AUTO VOLT using 1-CS-1704.

CONTR, 1-CS-1704 AND FIGURE 1, 1A DIESEL GENERATOR ELECTRICAL LIMITS.

Comment LOWER MW AND KVAR loads concurrently to approximately 0.70 MW AND zero KVARs Monitors 11/17 Bus voltages B.2.a.3 PER the following: and verifies voltage is between __ __

MONITOR 11/17 4KV Bus 4.1 and 4.35 KV.

voltage between 4.1KV and 4.35KV.

Simulator7 Page 6 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment WHEN D/G load is CRITICAL STEP*

approximately 0.7 MW, THEN Places 1-CS-152-1703 to __ __

B.2.b PLACE 1A DG OUT BKR, 1-CS-152-1703, to TRIP. TRIP.

Comment IF 1A DG output breaker 152-1703 is open, THEN PERFORM the following: Verifies that 1A DG voltage is B.3.a __ __

VERIFY 1A DG voltage is between 4.16KV to 4.30KV.

4.16KV (4.16KV to 4.30KV) on 1A DG VOLTS, 1-EI-1701.

Comment CUE Acknowledge report for alternate actions IF 1A DG output breaker 152-1703 is open, THEN PERFORM the following: Checks that 1A DG frequency B.3.b __ __

CHECK 1A DG frequency is is ~ 60 Hz.

approximately 60 Hz on 1A DG FREQUENCY, 1-SI-1701.

Comment Simulator7 Page 7 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD IF 1A DG output breaker 152-1703 is open, THEN PERFORM the following:

CHECK the following alarms B.3.c are clear: Verifies both alarms are clear. __ __

"11, 17 BUS DIESEL BKRS CLOSE BLOCKED"

"1A DG POT VOLT FREQ LO" Comment IF 1A DG output breaker 152-1703 is open, THEN CRITICAL STEP*

PERFORM the following: Presses 1-HS-1709 __ __

B.3.d DEPRESS 1A DG STOP, 1- pushbutton.

HS-1709, pushbutton.

Comment IF 1A DG output breaker 152-1703 is open, THEN PERFORM the following:

Verifies exciter is shutdown as B.3.e VERIFY exciter shutdown as indicated by zero volts on 1-EI- __ __

indicated by zero volts on 1A 1701.

DG VOLTS, 1-EI-1701.

Comment Acknowledge request for an operator to continue with the procedure with CUE step B.3.f.

Simulator7 Page 8 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD IF 1A DG output breaker 152-1703 is open, THEN PERFORM the following:

VERIFY the following Directs an operator to perform B.3.f-o __ __

equipment RUNNING by steps B.3.f-o.

observing the associated red indicating light is illuminated on 1C188:

Comment TERMINATING CUE: This JPM is complete when the 1A EDG has been shutdown and removed from the 11 4KV Bus. The Evaluator is expected to end the JPM.

TIME STOP: _______

Simulator7 Page 9 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Simulator7 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Simulator7 Page 10 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 is operating at 100% power.

2. 1A DG is OOS for cylinder inspections.

3. STP O-008A-1 is being performed to return the EDG to service.

4. 1A DG has been loaded for 5 MWe for the last 20 minutes.

5. 1 minute ago, the 1A DG CONTR BOARD 1C18A and the 1A DG alarms were received.

6. The local EDG operator has reported a lube oil leak and recommended a rapid shutdown of the 1A EDG.

7. You are performing the duties of the Unit-1 Control Room Operator.

Initiating Cue:

1. The Unit Supervisor directs you to perform a rapid shutdown of the 1A EDG per OI-21A, Section 6.5.4.

2. Are there any questions? You may begin.

Simulator7 Page 11 of 11

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Simulator8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Simulator8 Alternate Path: Yes Task Number: 202.015 Task

Title:

Respond to RCS leakage exceeding capacity of one Charging Pump Task Standard: This JPM is complete when the RCS leak has been identified as leakage into the Component Cooling system and alternate actions taken per AOP-2A-1.

K/A

Reference:

008 A4.01 (3.3, 3.1)

Method of Testing: Actual Performance - Simulator Validation Time: 15 minutes Time Critical Task: No References and Tools Required:

1. AOP-2A-1, Excessive Reactor Coolant Leakage, Revision 02701 JPM Setup Instructions:

1. Reset to IC-34 with both units at 100% power or the previously saved Exam IC.

2. Place Simulator in RUN.

3. Insert Malfunction 12A RCP Leak to CC: rcs035_03 to 100 on Event 1.

4. Insert Malfunction 12B RCP Leak to CC: rcs035_04 to 100 on Event 1.

5. Activate Event 1.

6. Isolate Letdown by shutting 1-CVC-515-CV and 1-CVC-516-CV.

7. Place Simulator in FREEZE.

8. Obtain Independent Verification for completion of steps 1 through 7.

9. If desired, Save conditions into available Exam IC slot for continued use.

10. Acknowledge all panel and plant computer alarms.

11. Select Horn On for annunciators.

12. Select Clock time.

13. When cued by the Examiner, place simulator in RUN.

14. Have AOP-2A-1 ready for use with placekeeping performed to start with Section VI, Block Step E, Step 8.

Simulator8 Page 2 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-1 is operating at 100% power.

2. The Control Room has implemented AOP-2A-1 for RCS leakage that just occurred.

3. The Control Room Operator has isolated Letdown, determined a Steam Generator Tube Leak does not exist, and determined a leak on the Charging header does not exist.

4. The Control Room Operator is monitoring the AOP-2A trip criteria.

5. You are performing the duties of the Unit-1 Reactor Operator.

Initiating Cue:

1. The Unit Supervisor directs you to continue AOP-2A-1,Section VI, Block Step E, Attempt to Isolate the Leak, starting with Step 8.

2. Are there any questions? You may begin.

Simulator8 Page 3 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

After Examinee reviews Cue Sheet, provide the examinee with the CUE prepared copy of AOP-2A-1,Section VI, Block Step E.

AOP-2A-1,Section VI, Block Step E, Attempt to Isolate the Leak If candidate directs operators to investigate or attempt to locate the leak:

CUE Inform candidate that the operators have not found any leakage in the Aux Building.

If candidate asks if the crew or STA has quantified the RCS leakage:

CUE Inform candidate the crew has not calculated the RCS leakage at this time.

IF the leak is determined to be 8 Determines step is N/A. __ __

occurring inside Containment Comment CRITICAL STEP*

IF the leak is NOT occurring inside of Containment, THEN Starts 11 Penetration Room perform the following actions: Vent Fan by momentarily placing 1-HS-5283 to Start. __ __

9 a. Place both Penetration Room Exhaust Fans in Starts 12 Penetration Room service. Vent Fan by momentarily placing 1-HS-5284 to Start.

Comment Leakage location may be indicated by sump alarms, room level alarms, or NOTE area RMS alarms.

The candidate may Attempt to locate and isolate the investigate:

9.b __ __

leak.

RMS indications

Head Tank levels Simulator8 Page 4 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Comment Determine that NO leakage into the Component Cooling System is indicated by:

Determines step is N/A based 10

NO rising trends on on rising RMS and head tank __ __

Component Cooling level trends.

Radiation Monitor, 1-RI-3819

CC HEAD TK LVL high alarm clear Comment BEGIN ALTERNATE PATH Once Letdown is isolated with a Component Cooling to Letdown leak CAUTION occurring, dilution of the VCT will occur until Component Cooling to the Letdown Heat Exchanger is isolated.

IF leakage into the Component Cooling System is indicated, Determines step is N/A based AND shutting the Letdown on Pressurizer level or 10.1 __ __

CNTMT Isolation valves stopped Component Cooling head tank the leak, THEN perform the level trends.

following actions:

Comment If candidate requests approval of the Shift Manager or Unit Supervisor:

CUE Ask what the candidate recommends and then acknowledge the recommendation.

Simulator8 Page 5 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD IF leakage into the CC System is indicated, AND shutting the Letdown CNTMT Isolation Determines step is applicable 10.2 valves did NOT stop the leak, based on available __ __

THEN, with the approval of the indications.

SM/CRS, perform the following actions:

Comment If US notified: acknowledge report to trip the reactor.

CUE After notified the reactor is tripped: Unit-1 reactor trip, implement EOP-0.

CRITICAL STEP*

May notify the US of the need

to trip the reactor.

Trip the Reactor. __ __

10.2.a Trips the Reactor using the pushbuttons on 1C05 or 1C15.

Comment If candidate provides a report to the Unit Supervisor upon completing CUE Reactivity Control:

Acknowledge report given.

Perform Reactivity Control Performs the Reactivity immediate actions of EOP-0, 10.2.b Control safety function of __ __

POST TRIP IMMEDIATE EOP-0.

ACTIONS.

Comment Simulator8 Page 6 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD CRITICAL STEP*

Places the following in the Stop or Pull To Lock

position:

Stop ALL RCPs. __ __

10.2.c

1-HS-151

1-HS-161

1-HS-171

1-HS-181 Comment CRITICAL STEP*

Shut the CC CNTMT SUPPLY and RETURN valves: Places the following in the Close position: __ __

10.2.d

1-CC-3832-CV

1-CC-3833-CV

1-HS-3832

1-HS-3833 Comment If the candidate continues with the remaining EOP-0 block steps:

CUE Inform candidate that the crew will complete the remaining EOP-0 steps.

IMPLEMENT EOP-0, POST The candidate may continue 10.2.e __ __

TRIP IMMEDIATE ACTIONS. with the EOP-0 block steps.

Comment TERMINATING CUE: This JPM is complete when the reactor is tripped, all RCPs are secured and Component Cooling supply and return isolation valves are closed. The Evaluator is expected to end the JPM.

TIME STOP: _______

Simulator8 Page 7 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Simulator8 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Simulator8 Page 8 of 9

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-1 is operating at 100% power.

2. The Control Room has implemented AOP-2A-1 for RCS leakage that just occurred.

3. The Control Room Operator has isolated Letdown, determined a Steam Generator Tube Leak does not exist, and determined a leak on the Charging header does not exist.

4. The Control Room Operator is monitoring the AOP-2A trip criteria.

5. You are performing the duties of the Unit-1 Reactor Operator.

Initiating Cue:

1. The Unit Supervisor directs you to continue AOP-2A-1,Section VI, Block Step E, starting with Step 8.

2. Are there any questions? You may begin.

Simulator8 Page 9 of 9

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Plant1

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Plant1 Alternate Path: No Task Number: 036.013 Task

Title:

Align AFW Pump Flow Control to 1C43 Task Standard: This JPM is complete when AFW flow control is aligned to 1C43 per AOP-9A Step AJ.

Time Critical Task: No K/A

Reference:

061 2.1.30 (4.4, 4.0) Ability to locate and operate components, including local controls.

Method of Testing: Simulated-Plant Validation Time: 15 minutes References and Tools Required:

1. AOP-9A-1 Rev 01901, Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire.

JPM Setup Instructions:

1. Consumable copy of AOP-9A-1 Step AJ.

2. Pictures inside hand transfer box.

Plant1 Page 2 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 1-HV-4511 1-HV-4512 1-CV-4512 1-CV-4511 Plant1 Page 3 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 1-HV-4525 1-HV-4535 1-CV-4535 1-CV-4525 Plant1 Page 4 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. The Control Room has been evacuated due to a severe fire.

2. AOP-9A, Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire, has been implemented.

3. You are performing the duties of the Unit-1 TBO.

Initiating Cue:

1. You have just completed Block Step Y and are directed by AOP-9A to go to the SRW Room Upper Level and perform Block Step AJ.

2. Are there any questions? You may begin.

Plant1 Page 5 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

CUE Provide the operator with AOP-9A-1 Block Step AJ.

AOP-9A-1 Step AJ. Align AFW Flow Control to 1C43 WHEN notified to align AFW 1 Determines step is applicable __ __

Flow Control to 1C43, THEN:

In the SRW Room Upper Level, Proceeds with component 1.a Place in POSITION 2 ALL AFW __ __

manipulation as specified System Valves listed below:

Evaluator Comment NORTH WALL (Left to Right)

EVALUATOR NOTE:

1-IA- 4511-HV and 4512-HV are located in a Hand Transfer Box. IF opened, this will cause an alarm at panel 1C04.

All actions are to be simulated when opening the box and placing 4511-HV and 4512-HV to Position 2.

1a 1-IA- 4511-HV and 4512-HV are located in Hand Transfer Box.

NOTE As examinee simulates operation of selected hand transfer valves inform CUE them that - the component you identified is in the position you described.

Plant1 Page 6 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Critical Step*

Simulates placing 1-IA-4511-HV 1-IA-4511-HV 1-IA-4512-HV 1-IA-4512-HV 1-IA-4531-HV 1-IA-4531-HV

1-IA-4521-HV 1-IA-4521-HV 1a 1-IA-4530-HV 1-IA-4530-HV __ __

1st 1-IA-4520-HV 1-IA-4520-HV Bullet 1-IA-4532-HV 1-IA-4532-HV 1-IA-4522-HV 1-IA-4522-HV 1-IA-4533-HV 1-IA-4533-HV 1-IA-4523-HV 1-IA-4523-HV in the Position 2 position.

Evaluator Comment Stanchion L.O.9 between 1-AFW-4525-CV and 1-AFW-4535-CV (In Hand transfer Box)

EVALUATOR NOTE:

1-IA-4525-HV and 4535-HV are located in a Hand Transfer Box. IF opened, this will cause an alarm at panel 1C04.

All actions are to be simulated when opening the box and placing 4525-HV and 4535-HV to Position 2.

As examinee simulates operation of selected hand transfer valves inform CUE them that - the component you identified is in the position you described.

Critical Step*

1-IA-4525-HV *Simulates placing 1a 1-IA-4535-HV 1-IA-4525-HV __ __

2nd 1-IA-4535-HV Bullet in the Position 2 position.

Plant1 Page 7 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Evaluator Comment Southwest Corner next to U-1 to U-2 AFW X-conn CV, 1-AFW-4550-CV (Left to right)

As examinee simulates operation of selected hand transfer valves inform CUE them that - the component you identified is in the position you described.

Critical Step*

1-IA-4070-HV *Simulates placing 1a 1-IA-4071-HV 1-IA-4070-HV 3rd 1-IA-4550-HV 1-IA-4071-HV Bullet 1-IA-4550-HV in the Position 2 position.

Evaluator Comment 1b SWAC TO IA AMP STA ISOL, 1-IA-728 is located directly above the AFW NOTE Air Amplifier in the Unit 1 SRW Room Lower Level.

As examinee simulates operation of valve inform them that - the component CUE you identified is in the position you described.

Critical Step*

Open SWAC TO IA AMP STA 1b *Simulates opening 1-IA- __ __

ISOL, 1-IA-728.

728.

Evaluator Comment Notify 1C43 that AFW flow Notifies 1C43 that AFW flow control is aligned to 1C43 and control is aligned to 1C43 and 2 __ __

SWAC air is aligned to the AFW SWAC air is aligned to the CVs. AFW CVs.

Plant1 Page 8 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Evaluator Comment Informs evaluator that Step AJ GO TO the AFW Pump Room to 3 is complete and their next step __ __

perform step AK.

is to perform Step AK.

TERMINATING CUE: This JPM is complete when AFW flow control is aligned to 1C43 per AOP-9A Step AJ. No further actions are required. The operator is expected to end this JPM unless they continue proceeding to Step AK, then the evaluator should end the JPM.

TIME STOP: _______

Plant1 Page 9 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Plant1 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Plant1 Page 10 of 11

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. The Control Room has been evacuated due to a severe fire.

2. AOP-9A, Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire, has been implemented.

3. You are performing the duties of the Unit-1 TBO.

Initiating Cue:

1. You have just completed Block Step Y and are directed by AOP-9A to go to the SRW Room Upper Level and perform Block Step AJ.

2. Are there any questions? You may begin.

Plant1 Page 11 of 11

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Plant2

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Plant2 Alternate Path: No Task Number: 005/006.013 Task

Title:

Operate MCC Load Breakers Task Standard:

This JPM is complete when MCC-214 breakers are stripped per AOP-9A-2 Block Step AG.

Time Critical Task: No K/A

Reference:

068 AA1.10 (3.7/3.9) Ability to operate and/or monitor the following as they apply to the Control Room Evacuation: Power Distribution - AC and DC.

Method of Testing: Simulated-Plant Validation Time: 15 minutes References and Tools Required:

1. AOP-9A-2 Rev 02000 Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire.

2. SA-CA-129-1001 Rev 002 Electrical Safety Task Matrices/PPE Requirements.

JPM Setup Instructions:

1. Consumable copy of AOP-9A-2 Step AG.

2. Copy of Electrical Safety PPE procedure, SA-CA-129-1001.

Plant2 Page 2 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. The Control Room has been evacuated due to a severe fire.

2. AOP-9A, Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire, has been implemented.

3. Both the 21 and 24 4KV Buses are energized.

4. You are performing the duties of the Unit-2 ABO.

Initiating Cue:

1. You have just completed Block Step AB and are directed by AOP-9A-2 to go to the 69 Ft West Electrical Pen Room and perform Block Step AG.

2. Are there any questions? You may begin.

Plant2 Page 3 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

CUE Provide the operator with AOP-9A-2 Block Step AG.

AOP-9A-2 BLOCK STEP AG, DE-ENERGIZE PZR PORV 402 AND OPEN BREAKERS AT MCC 214R After each breaker is simulated open:

CUE The component you identified is in the position you described.

At Reactor MCC 214R, perform Critical Step*

the following:

Simulates placing breaker __ __

1

Open Pressurizer Relief 2- 52-21449 in the OPEN ERV-402, 52-21449. position.

Evaluator Comment CUE The component you identified is in the position you described.

At Reactor MCC 214R, perform Critical Step*

the following:

*Simulates placing breaker

Open Cntmt Sump to Misc __ __

1 52-21457 in the OPEN Wst Rcvr Tk 2-MOV-5462, position.

52-21457.

Evaluator Comment CUE The component you identified is in the position you described.

At Reactor MCC 214R, perform Critical Step*

the following:

*Simulates placing breaker

Open Volume Control Tank __ __

1 52-21431 in the OPEN Isolation 2-MOV-501, 52-position.

21431.

Evaluator Comment CUE The component you identified is in the position you described.

Plant2 Page 4 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD At Reactor MCC 214R, perform Critical Step*

the following:

Simulates placing breaker __ __

1

Open Boric Acid Gravity Feed 52-21430 in the OPEN 2-MOV-508, 52-21430. position.

Evaluator Comment CUE The component you identified is in the position you described.

At Reactor MCC 214R, perform Critical Step*

the following:

Simulates placing breaker 1

Open Boric Acid Gravity Feed 52-21424 in the OPEN 2-MOV-509, 52-21424. position.

Evaluator Comment CUE The component you identified is in the position you described.

At Reactor MCC 214R, perform Critical Step*

the following:

Simulates placing breaker 1

Open Refueling Water Tank 52-21423 in the OPEN Stop 2-MOV-504, 52-21423. position.

Evaluator Comment CUE 2C43 acknowledges report that Block Step AH is complete.

Simulates contacting 2C43 to Notify 2C43 that Step AG is 2 report that Step AG is __ __

complete.

Evaluator Comment TERMINATING CUE: This JPM is complete when Step AG is complete. The evaluator is expected to end the JPM.

TIME STOP: _______

Plant2 Page 5 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Plant2 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Plant2 Page 6 of 7

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. The Control Room has been evacuated due to a severe fire.

2. AOP-9A, Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire, has been implemented.

3. Both the 21 and 24 4KV Buses are energized.

4. You are performing the duties of the Unit-2 ABO.

Initiating Cue:

1. You have just completed Block Step AB and are directed by AOP-9A-2 to go to the 69 Ft West Electrical Pen Room and perform Block Step AG.

2. Are there any questions? You may begin.

Plant2 Page 7 of 7

Examinee:

Calvert Cliffs Nuclear Power Plant 2020 NRC Initial Licensed Operator Exam JPM-Plant3

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 JPM Number: Plant3 Alternate Path: No Task Number: 202.070 Task

Title:

Respond to a Loss of Instrument Air in Modes 3,4,5,6 or Defueled.

Task Standard: This JPM is complete when the operator has started the standby IA Compressor and bypassed and then isolated the in-service IA Dryer.

Time Critical Task: No K/A

Reference:

065 AA1.04 (3.5/3.4) Ability to operate and/or monitor the following as they apply to the Loss of Instrument Air: Emergency air compressor.

Method of Testing: Simulated-Plant Validation Time: 20 minutes References and Tools Required:

1. AOP-7D-2 Rev 01400 Loss of Instrument Air JPM Setup Instructions:

1. Consumable copy of AOP-7D-2 Step VI.A.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Directions to the Examinee:

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

Hand Examinees Cue Sheet to Examinee at this time.

Initial Conditions:

1. Unit-2 is in Mode 6 performing a core offload.

2. 21 Instrument Air Compressor is in service.

3. 21 IA Dryer is in service.

4. A Loss of Instrument Air is occurring and AOP-7D has been implemented.

5. There are no temporary air compressors available due to a manifold leak.

6. The IA Dryer light is brightly lit in the Control Room.

7. You are performing the duties of the Unit-2 TBO.

Initiating Cue:

1. You have been directed by the Unit-2 Unit Supervisor to perform AOP-7D-2,Section VI, Block Step A while the cause of lowering Instrument Air header pressure is investigated.

2. Are there any questions? You may begin.

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD TIME START: ________

AOP-7D-2, SECTION VI, BLOCK STEP A, ATTEMPT TO MAINTAIN PRESSURE WHILE LOCATING THE PROBLEM CUE Provide the operator with AOP-7D-2,Section VI, Block Step A.

Step Locates AOP-7D-2 Block Step A. Determines step is applicable. __ __

Evaluator Comment If asked:

The temporary air compressors are currently shutdown to repair a large CUE manifold air leak near the temporary compressors. The compressors are not currently available.

IF Temporary Air Compressor is supplying air system, THEN contact Work Control Center to 1 Determines step is N/A. __ __

adjust system pressure OR start Standby Compressor PER OI-18A, PLANT AIR SYSTEM Evaluator Comment If asked:

CUE The Instrument Air problem is not due to a power loss.

IF both instrument air 2 compressors were lost due to Determines step is N/A. __ __

power loss Evaluator Comment 3 ATTACHMENT (1), CRITICAL VALVES CONTROLLED BY IA, NOTE lists the pressure required to control the critical valves.

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD If asked:

IA header pressure is 82 PSIG and slowly lowering, 21 IA Compressor is CUE running as the lead compressor (2-HS-2062 in SPEED) and 22 IA Compressor is the standby compressor (2-HS-2064 in AUTO) but NOT running.

WHEN IA header pressure lowers to 93 PSIG, THEN ensure Determines that only the lead 3 __ __

that the standby Instrument Air IA Compressor (21) is running.

Compressor is running.

Evaluator Comment After 22 IAC is placed in SPEED:

CUE You see the compressor pistons moving up and down and now hear noise from the air compressor.

IF the standby IA Compressor Critical Step*

fails to auto start, THEN place the standby Compressor *Simulates placing 2-HS- __ __

3.1 handswitch to the SPEED 2064 for 22 IA Compressor position. in SPEED.

Evaluator Comment 4 ATTACHMENT (2), VALVES SUPPLIED BY SALTWATER AIR, lists NOTE Saltwater Air loads.

If the Control Room is contacted:

IA header pressure is 81 PSIG and very slowly lowering. The Control Room CUE has started the SWACs.

If a local air pressure gauge is checked:

Point to 81 psig and show a very slowly lowering indication.

IF IA pressure is less than 90 Determines step has been 4 PSIG and lowering, THEN start completed by the Control __ __

21 and 22 SW AIR COMPRs. Room.

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD Evaluator Comment The IA Dryer malfunction light will be brightly lit for the in-service IA Dryer 5

and the dryer will de-energize with both chambers in service if IA Pressure NOTE has lowered to 93 +/- 1 PSIG.

21 IA Dryers handswitch is in start, the panel lights are illuminated and you CUE hear and feel air blowing from the bottom of the dryer towers.

If requested, the control room reports that 21 IA dryer light bulb is brightly lit.

IF IA Dryer is the cause of the 5 lowering IA pressure, THEN Determines step is applicable. __ __

bypass the in service IA Dryer.

Evaluator Comment CUE The component you have identified is in the position you described.

Critical Step*

Open the IA Dryer Bypass Valve,

Simulates opening 2-IA- __ __

5.a 2-IA-134.

134.

Evaluator Comment CUE The component you have identified is in the position you described.

IF 21 Dryer is in service, THEN shut 21 Dryer Inlet and Outlet Critical Step*

valves:

Simulates shutting 2-IA-133 __ __

5.b * (Inlet valve) 2-IA-133 and 2-IA-142.

(Outlet/FI-BYP valve) 2-IA-142 Evaluator Comment

Appendix C Job Performance Measure Worksheet Form ES-C-1 SAT UNSAT STEP ELEMENT STANDARD If asked:

CUE 22 IA Dryers handswitch is in OFF and the panel lights are not illuminated.

5.c IF 22 Dryer is in service, Determines step is N/A. __ __

Evaluator Comment If the Control Room is contacted:

IA header pressure is rising and the Unit Supervisor does not wish to place CUE the standby IA Dryer in service at this time.

If a local IA pressure gauge is checked:

Point to 95 psig and rising to 100 psig and then steady.

5.d Shift to the standby Air Dryer Determines step is N/A. __ __

Evaluator Comment TERMINATING CUE: This JPM is complete when 22 IA Compressor is running and 21 IA Dryer is bypassed and isolated. No further actions are required. The evaluator is expected to end the JPM.

TIME STOP: _______

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: Plant3 Examinee: ____________________________________

NRC Examiner: ____________________________________

Date Performed: ____________________________________

Facility Evaluator: ____________________________________

Number of Attempts: __________________________________

Time to Complete: ____________________________________

Follow up Question(s):

Examinee Response:

Result: SATISFACTORY _____ UNSATISFACTORY _____

Examiners Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEES CUE SHEET Initial Conditions:

1. Unit-2 is in Mode 6 performing a core offload.

2. 21 Instrument Air Compressor is in service.

3. 21 IA Dryer is in service.

4. A Loss of Instrument Air is occurring and AOP-7D has been implemented.

5. There are no temporary air compressors available due to a manifold leak.

6. The IA Dryer light is brightly lit in the Control Room.

7. You are performing the duties of the Unit-2 TBO.

Initiating Cue:

1. You have been directed by the Unit-2 Unit Supervisor to perform AOP-7D-2,Section VI, Block Step A while the cause of lowering Instrument Air header pressure is investigated.

2. Are there any questions? You may begin.

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Examiners: Operators:

Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.

Turnover: 13 AFW Pump is OOS.

Instructions to the crew: Maintain 100% power.

Critical Tasks

1. Identifies 12 S/G as the ruptured SG and isolates 12 S/G within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of the reactor trip.

2. Recognizes SFSC in EOP-6 not met and transitions to EOP-8 within 30 minutes of Loss of All Feedwater initiation.

3. Establishes AFW flow to at least one S/G prior to S/G levels going below (-)350 inches OR Commences OTCC when both S/G levels are below (-)350 inches or Tcold rises uncontrollably by 5°F or greater and prior to CET temperatures reaching 560°F.

Event # Malfunction # Event Type* Event Description I-RO/SRO 1 rcs026_01 Pressurizer Level Transmitter, LT110X, Fails Low T-SRO 2 hdv001_02 C-BOP/SRO 12 Heater Drain Tank Pump trips/AOP-3G 3 ms009_02 C-ALL TBV-3942 Fails Open/AOP-7K ms001_02 C-BOP/SRO 4 R-ATC 12 S/G Tube Leak (100 gpm)/AOP-2A Downpower T-SRO 5 13kv001_01 C-ALL P-13000-1 Transformer Loss/EOP-0 6 ms002_02 M-ALL SGTR (1 tube) in 12 SG/EOP-6 7 afw001_01 M-ALL 11 AFW Pump Trip (Loss of All Feed)/EOP-8 8 2-CV-4550 C-BOP/SRO 23 AFW Pump Trip

(N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Scenario Overview Initial Conditions:

Unit-1 at 100% power, MOC, Unit-2 at 100% power Equipment OOS: 13 AFW Pump.

Abnormal Conditions: None Instructions for shift: Maintain 100% power.

Event 1 - Pressurizer Level Transmitter, LT110X Fails Low, causing the process variable of the in-service PZR level controller to fail low. Alarm Response Manual 1C06 actions will direct the crew to swap Pressurizer Level Controller channels and the Pressurizer Low Level Cut-off switch, and then reset the Proportional Heaters. The crew should reference OP-CA-103-102-0200, enter TS LCO 3.3.10.A, and determine the required action is to restore the indication channel to operable status within 30 days.

Event 2 - 12 Heater Drain Tank Pump trips requiring the crew to enter AOP-3G, Malfunction of Main Feedwater System. The crew will start the third Condensate Booster Pump and ensure adequate Steam Generator Feed Pump suction pressure is maintained.

Event 3 - TBV-3942 Fails Open causing RCS temperatures, MWe, and Pressurizer Level to quickly lower. The crew will enter AOP-7K and take prompt actions to control Reactor Power by inserting CEAs and/or performing an RCS boration as well as lowering turbine load. The crew will then direct the local isolation of the failed open TBV.

Event 4 - 12 S/G will begin to experience tube leakage at 100 GPM. The crew will respond per AOP-2A, Excessive Reactor Coolant Leakage, and will reduce power to reduce TAVE to less than 537F while monitoring for reactor trip criteria. Determines TS LCO 3.4.13.B is applicable with required actions to be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to be in Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Event 5 - During the rapid downpower per AOP-2A, a fault will occur on P-13000-1 13KV Transformer causing an automatic reactor trip. The crew will enter EOP-0, Post Trip Immediate Actions.

Event 6 - During EOP-0, the S/G tube leak will increase to a rupture of 1 S/G tube. The crew is expected to implement EOP-6. The crew will commence a cooldown, at a rate not to exceed 100°F/hr, to prepare to isolate 12 S/G. Once Thot <515°F, the crew will perform the Critical Task to isolate 12 S/G. If plant conditions degrade or the crew is unsure of the diagnosis it is acceptable for them to enter EOP-8 directly from EOP-0. If EOP-8 is entered, all critical tasks still apply unless individual tasks are invalidated by the exam team.

Events 7/8 - After 12 S/G has been isolated, 11 AFW Pump will trip resulting in a Loss of All Feedwater. 23 AFW Pump will fail to start when attempted by the crew. 12 AFW will be unable to be reset when initially requested. The crew is expected to perform the Critical Task to transition to EOP-8 based on the combined SGTR and Loss of All Feedwater in progress. The crew should identify the success paths in EOP-8 (RC-1 Met, VA-1 Met, PIC-4 Met, HR-2 Not Met (Met if SG Levels are in the band), CE-1 Met, RLEC-2 Met) and priority (HR-2 if not met, PIC-4, RLEC-2, RC-1, VA-1, CE-1). Crew will commence HR-2 and PIC-4. As part of HR-2, the crew should attempt to establish AFW flow when available. As part of PIC-4, the crew should pursue lowering RCS pressure to attempt to lower the SGTR leak rate. The scenario will end once AFW flow has been established to 11 Steam Generator after 12 AFW Pump is repaired.

Page 2 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Instructor Scenario Information

_____ 1. Reset to IC-34.

_____ 2. Place simulator in RUN.

_____ 3. Clear PPC Screen trend lines if necessary.

_____ 4. Place simulator in FREEZE.

_____ 5. Enter Triggers:

_____ a. Reactor Trip, CEA_ROD_POSITION(1) < 5, to trigger Event 6.

_____ 6. Enter Malfunctions:

_____ a. rcs026_01 to 2_LOW, PZR Level LT110X Fails Low, on Event 1.

_____ b. hdv001_02, 12 Heater Drain Tank Pump Breaker Failure, on Event 2.

_____ c. ms009_02, TBV-3942 Fails Open, on Event 3.

_____ d. ms001_02 to 100, 12 SG Tube Leak of 100 gpm, on Event 4.

_____ e. 13kv001_01, P-13000-1 13KV Transformer Fault, on Event 5.

_____ f. ms002_02 after 30 to 1.0, 12 SG Tube Rupture of 1 tube with a 30 second delay, on Event 6.

_____ g. afw001_01, 11 AFW Pump trips, on Event 7.

_____ 7. Enter Remote Functions:

_____ a. 2-CV-4550 to OPEN on Event 8.

_____ b. 1-MS-3939-HV to 1C43 on Event 9.

_____ c. 152-1116 to RACKED_OUT at time zero.

_____ 8. Enter Panel Overrides:

_____ a. P1C04_1HS4540 to PTL at time zero.

_____ b. P1C20_S12_LTON after 20 to ON on Event 8.

_____ c. P1C04_W06_LTON to Off at time zero.

_____ d. P1C03_C65_LTON to Off at time zero.

_____ 9. Administrative:

_____ a. Place red dots on W06 on 1C04, Motor Sys L/U Bkr OL Fail and C65 on 1C03, AFW Status Panel.

_____ b. Place an INFO Tag on 13 AFW Pump Handswitch in PTL.

_____ c. Place protected equipment tags NEXT TO 11 & 12 AFW Pumps.

_____ d. Verify ovation screens are reset and working.

_____ e. Verify RMS (SGTR) screens are operating correctly and not bypassed.

_____ 10. Independently verify correct completion of the following:

_____ a. Event Triggers correctly entered Page 3 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020

_____ b. Malfunctions correctly entered

_____ c. Remote Functions correctly entered

_____ d. Panel Overrides correctly entered

_____ e. Administrative actions correctly performed

_____ 11. Place simulator in RUN.

_____ 12. Ensure schedule files are in RUN.

_____ 13. Ensure Trigger files are in RUN.

_____ 14. Ensure SBT Report is running with the SBT Insight file open.

_____ 15. Reset/Acknowledge panel and PPC alarms.

_____ 16. Ensure all PPC screens selected to Main Menu, Alarms, or SPDS Operating Summary page.

_____ 17. Select Clock and ensure Horn On for annunciators.

_____ 18. Brief the Crew:

Unit-1 is at 100% power, MOC.

1. Present plant conditions:

Unit-2 is at 100% power.

Reactor has been at steady state 100% power for the

2. Power history:

last 3 months.

3. Equipment out of 13 AFW Pump is OOS for scheduled work, due back in service: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (IAS 3.7.3.B)

4. Abnormal conditions: None

5. Surveillances due: None

6. Instructions for shift: Maintain 100% power.

_____ 19. Allow crew 3-5 minutes to acclimate themselves with their positions.

Page 4 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020

_____ 20. Instructions for the Booth Operator:

_____ a. Event 1: Activate Event 1, Pressurizer Level Transmitter LT110X Fails Low when directed by the Lead Examiner.

_____ b. Event 2: Activate Event 2, 12 Heater Drain Tank Pump trips when directed by the Lead Examiner.

_____ c. Event 3: Activate Event 3, TBV-3942 Fails Open when directed by the Lead Examiner. Use Remote 1-MS-118 to isolate TBV-3942 as directed by the crew.

_____ d. Event 4: Activate Event 4, 12 SG Tube Leak of 100 gpm when directed by the Lead Examiner. Use Remote functions 1-MS-4024-CV and 1-MS-4021-CV to AUTO if needed.

_____ e. Event 5: Activate Event 5, P-13000-1 13KV Transformer Fault at 80% reactor power or when directed by the Lead Examiner.

_____ f. Event 6: Ensure Event 6 is automatically activated with a 30 second delay, 12 SGTR on the Reactor Trip.

_____ g. Event 7: Activate Event 7, 11 AFW Pump trips after 12 SG is isolated or when directed by the Lead Examiner.

_____ h. Event 8: Activate Event 8, 23 AFW Pump trips upon starting when requested by the crew to start 23 AFW Pump.

_____ i. When 12 AFW Pump becomes available, use remote 1-MS-3988 to start (open) 12 AFW Pump throttle stop valve.

Page 5 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Responses to Crew Requests If a request and response is not listed, delay the response until reviewed with the examiner. If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

Allow 2-3 minutes to perform requests from or to give reports to the Control Room unless otherwise specified.

REQUEST RESPONSE Event 1 - LT110X Fails Low

1. WEC/IM informed of issue/status. Acknowledge request. No further actions are required.

Event 2 - 12 Heater Drain Tank Pump trips

1. WEC/Maintenance informed of Acknowledge request. No further actions are required.

issue/status.

2. TBO investigate 12 HDP pump and After 3 minutes, report the breaker tripped on breaker. overload, no apparent issues with the pump.

3. Chemistry notified that Precoats Acknowledge report. No further actions are required.

have been bypassed.

Event 3 - TBV-3942 Fails Open

1. WEC/Maintenance informed of Acknowledge request. No further actions are required.

issue/status.

After 2 minutes, report TBV is failed open, no air

2. TBO investigate TBV-3942.

leaks.

3. TBO directed to isolate TBV-3942. Use Remote: 1-MS-118 to isolate TBV as directed.

Event 4 - 12 S/G Tube Leak

1. Chemistry - sample both S/Gs for After 10 minutes, report activity present in 12 S/G and activity per CP-436. none in 11 S/G.

2. Rad Protection - informed of issue. Acknowledge request. No further actions are required.

3. TSO/Generation Dispatch - Acknowledge request. No further actions are required.

informed of downpower for casualty.

Acknowledge request.

4. TBO - Standby to operate MSR Panel Loaders during downpower. Use Remote functions 1-MS-4024-CV and 1-MS-4021-CV to AUTO if needed.

Event 5 - Loss of P-13000-1 Transformer/EOP-0

1. Electrical Maintenance/WEC - Acknowledge request.

Investigate the loss of P-13000-1. After 5 minutes, report there is a fault on P-13000-1 Page 6 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 transformer, unknown restoration time.

Event 6 - SGTR/EOP-6 Acknowledge request.

1. Chemistry - sample SGs per CP-436. After 10 minutes, report There is RCS activity in 12 SG. No Activity in 11 SG.

2. TBO - standby in the SWGR Room Acknowledge request. No further actions are required.

Acknowledge request.

2. TBO - Align 12 ADV control to After 2 minutes, initiate Event 9 and report 12 ADV 1C43, in manual, with a 0% output. control has been shifted to 1C43, in manual, with a 0% output.

Acknowledge request.

3. ABO/OSO - Evaluate Safety Valves on Aux Building roof. After 2 minutes, report there are no leaking Safety Valves.

Event 7 - 11 AFW Pump trips/EOP 8 After 1 minute, report 11 AFW tripped on overspeed,

1. TBO investigate 11 AFW Pump.

the reset linkage has broken.

After 1 minute, report throttle/stop valve is stuck shut

2. TBO align 12 AFW Pump for and the handwheel has broken. Recommend service.

contacting Mechanical Maintenance to repair.

Acknowledge request. No further actions are required.

3. WEC/Maintenance informed to After RATs in EOP-8 are assessed, report that investigate the AFW Pumps. Mechanical Maintenance has repaired the 12 AFW throttle stop valve and the TBO is standing by to start the pump.

4. TBO align 12 AFW Pump for Use remote 1-MS-3988 to open 12 AFW throttle stop service. valve.

Event 8 - 23 AFW Pump trips Acknowledge request. Activate Event 8.

1. Unit-2 Control Room - place 23 After 1 minute, report 23 AFW Pump tripped, still AFW Pump in service.

investigating.

Page 7 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Event #1 PZR Level LT110X Fails Low I-ATC/SRO Time Position Applicants Actions or Behavior ATC/BOP Recognizes alarms on 1C06 and notifies the Unit Supervisor.

Directs the ATC/BOP to reference the 1C06 Alarm Manual for SRO Windows E-33 and E35.

ATC Reports PZR level Channel X instrument has failed low.

Shifts PZR LVL CH SEL switch, 1-HS-110, to Channel Y.

Shifts PZR HTR LO LVL CUTOFF SEL switch, 1-HS-100-3, to Y.

ATC

Resets Proportional Heaters and monitors RCS pressure and level is restoring to normal values.

ATC/BOP Refers to 1C06 Alarm Manual to ensure all required actions were taken.

Refers to OP-CA-103-102-0200 for Common Tap Failure Analysis.

SRO Directs the ATC/BOP to check referenced indications for a common tap failure.

SRO May contact WEC/Instrument Maintenance to investigate failure.

Determines Tech Spec LCO 3.3.10.A Post Accident Monitoring SRO Instrumentation applies and that the required action is to restore the indication channel to operable status within 30 days.

Examiner notes:

Event concludes when 12 Heater Drain Tank Pump trips. If SROs understanding of Technical Specification applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

NOTE TO EXAMINER Cue Booth Operator to initiate Event #2, 12 Heater Drain Tank Pump trips.

Page 8 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Event #2 12 Heater Drain Tank Pump trips C-BOP/SRO Time Position Applicants Actions or Behavior BOP Announce Non-Essential 4KV Motor Overload alarm SRO Determine 12 Heater Drain Tank Pump tripped and report to the US.

BOP Refer to the 1C03 Alarm Manual.

Implement AOP-3G Malfunction of Main Feedwater System.

SRO

Direct ATC/BOP to monitor for reactor trip criteria (low S/G level).

Direct BOP to perform Section V Failure of a Pump > 5% Power.

Performs Step V.B.2 Maximize SGFP Suction Pressure as necessary:

Condenser Hotwell Controller 1-LIC-4405 to 50%

BOP

Open Precoat Bypass Valve 1-CD-5818-CV

Checks Open Condensate Demin Bypass Valve 1-CD-4439-MOV Evaluates current reactor power level and may partially insert CEAs to ATC prevent exceeding thermal power limits.

SRO May inform WEC/Maintenance/Chemistry of the issue.

BOP Starts the third Condensate Booster Pump.

SRO Exits AOP-3G and implements OP-3.

Examiner notes:

Event concludes when TBV-3942 fails open.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, TBV-3942 Fails Open, when desired.

Page 9 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Event #3 TBV-3942 Fails Open C-ALL Time Position Applicants Actions or Behavior Recognizes the lowering TCOLD, PZR Level and/or MWe and reports to ATC/BOP the US.

ATC/BOP Determines TBV-3942 has failed open and reports to the US.

Performs immediate stabilizing actions to control reactor power such as ATC/BOP insertion of CEAs and/or lowering Turbine Load to restore RCS temperatures on program.

Directs implementation of AOP-7K, Overcooling Event in Mode One or SRO Two.

SRO May inform WEC/Maintenance of the issue.

SRO Coordinates the plan to locally isolate TBV-3942.

Examiner notes:

Event concludes when 12 S/G Tube leak occurs.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, 12 S/G Tube leak, when desired.

Page 10 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 12 S/G Tube Leak C-ALL, R-ATC Event #4 T-SRO Time Position Applicants Actions or Behavior Refers to Alarm Manual for alarm and evaluates MSLRM and BOP determines indications for 12 SG > 11 SG.

ATC Determines that PZR level is lowering.

SRO Implements AOP-2A, Excessive Reactor Coolant Leakage.

SRO Notifies Radiation Safety that excessive RCS leakage exists.

Directs Chemistry to perform qualitative samples on both SGs for SRO activity per CP-436.

BOP/SRO Determines a S/G Tube Leak is indicated.

ATC/BOP Shuts the L/D Containment Isolation valves.

ATC/BOP Ensures the S/G B/D valves are shut.

ATC May equalize Boron per OP-3.

SRO May inform TSO/Generation Dispatch of Downpower.

Refers to T.S. 3.4.13. Determines T.S. limits of 3.4.13.B has been SRO exceeded. Enters T.S. LCO 3.4.13.B with required actions to be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to be in Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Event #4 continues on the next page Examiner notes:

Page 11 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 12 S/G Tube Leak C-ALL, R-ATC Event #4 T-SRO Time Position Applicants Actions or Behavior Borates to reduce TAVE to < 537° F. Start with 1 minute fast boration with ALL available Charging Pumps then shifts suction to RWT.

Initial boration from the BASTs followed by suction from the RWT:

Open the BA DIRECT M/U valve, 1-CVC-514-MOV.

ATC

Start all available CHG PPs.

Start one BA PP and operate it for approximately one minute.

Shut the BA DIRECT M/U valve, 1-CVC-514-MOV.

Open the RWT CHG PP SUCT valve, 1-CVC-504-MOV.

Shut the VCT OUT valve, 1-CVC-501-MOV.

ATC Inserts CEAs as necessary, to reduce Tave < 537F.

BOP May Open high level dumps for FW heaters.

SRO May declare radiological event per OP-CA-108-3.0.

Adjusts turbine load, as necessary, to maintain S/G pressure between ATC/BOP

~ 800 PSIA and 825 PSIA.

May coordinate MSR shutdown with plant operators stationed locally BOP at the MSR panel loaders.

Examiner notes:

Event concludes with the failure of P-13000-1 and an automatic reactor trip occurs. If SROs understanding of Technical Specification applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, P-13000-1 Transformer Loss.

Page 12 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Event #5 P-13000-1 Transformer Loss/EOP-0 C-ALL Time Position Applicants Actions or Behavior Determines Reactor is tripped and Reactivity Safety Function is met.

ATC Informs the SRO that Reactivity is complete.

SRO May report a partial Loss of Offsite Power occurred.

May report monitoring turbine trip for MSR 2nd Stage MOVs going BOP closed. Determines Turbine Trip is met. Informs the SRO that Turbine Trip is complete.

Determines Vital Auxiliaries Safety Function is met. Informs the SRO BOP that Vital Auxiliaries is complete.

Determines Pressure and Inventory Control Safety Function is not ATC met. Informs the SRO that Pressure and Inventory Control is not met due to low PZR level and pressure.

Determines and reports Core and RCS Heat Removal Safety Function BOP is not met (due to no Reactor Coolant Pumps running).

May take manual control of 12 SG level and lower the feed rate to 12 BOP SG. May take actions to initiate AFW and secure MFW.

SRO May request Chemistry to sample Steam Generators for activity.

Determines Containment Environment Safety Function is met.

ATC/BOP Informs the SRO that Containment Environment is complete.

Determines Radiation Levels External to Containment Safety Function is not met. Informs the SRO that Radiation Levels External ATC/BOP to Containment is not met due to high Condenser Off-Gas alarms and trends.

ATC Verifies the SIAS actuation.

Trip 11A & 12B RCPs or 11B & 12A RCPs when RCS pressure ATC decreases to <1725 PSIA prior to RCS pressure reaching 1300 PSIA.

Evaluates the EOP-0 flowchart and recommends the implementation SRO of EOP-6. Directs implementation of EOP-6.

Examiner notes:

Page 13 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 Event #6 12 SGTR/EOP-6 M-ALL Time Position Applicants Actions or Behavior ATC Verifies RCS boration is in progress.

Commences a rapid cooldown to lower THOT to <515°°F. Shifts BOP ADV/TBV Controller to Manual. Raises output on controller to open ADVs or TBVs. Blocks SGIS.

May lower ADV/TBV output to lower the cooldown rate once RCS BOP temperature is <515°F THOT.

BOP/SRO Identifies 12 SG as the most affected SG.

CRITICAL TASK - Isolates 12 SG within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of the reactor trip:

Directs TBO to Align 12 ADV to 1C43 with a 0% output

Shuts 12 MSIV

Verifying shut 12 MSIV BYP valve, MS-4052

Verifying shut 12 SG FW ISOL valve, FW-4517-MOV

Verifies shut 12 SG AFW STM SUPP & BYPASS valves, MS-BOP 4071-CV and MS-4071A-CV

Shuts the 12 S/G AFW BLOCK valves, AFW-4530-CV, AFW-4531-CV, AFW-4532-CV, AFW-4533-CV

Verify shut 12 SG B/D valves, BD-4012-CV and BD-4013-CV

Shuts the MS UPSTREAM DRN ISOL VLVS with HS-6622 in CLOSE

Directs ABO/OSO - Evaluate for leaking safety valves on 12 SG Examiner notes:

Event concludes when 11 AFW Pump trips.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, 11 AFW Pump trips, after 12 S/G is isolated.

Page 14 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 11 AFW Pump Trip/23 AFW Pump M-ALL Events #7,8 Trip/Loss of All Feedwater/EOP-8 C-BOP/SRO Time Position Applicants Actions or Behavior SRO/BOP Notes 11 AFW Pump trips.

Directs TBO to align 12 AFW Pump to service. Reports to the SRO BOP that 12 AFW Pump is not able to be aligned for service.

Establishes alignment to use 23 AFW Pump for restore feed to Unit-1.

BOP Reports to the SRO that 23 AFW Pump tripped and is unavailable.

CRITICAL TASK - Recognizes SFSC in EOP-6 not met and SRO transitions to EOP-8 within 30 minutes of Loss of All Feedwater.

SRO Directs implementation of EOP-8.

SRO May inform the WEC, Radiation Protection, and Chemistry of issue.

Directs Chemistry to perform samples on both S/Gs and place the SRO Hydrogen Monitors in service.

Evaluates Resource Assessment Table. Determines RC-1 Met, VA-1 ATC/BOP Met, PIC-4 Met, HR-2 Not Met (Met if SG Levels are in the band),

CE-1 Met, RLEC-2 Met. Informs the SRO of assessment results.

SRO Directs the implementation of HR-2 and PIC-4 Safety Functions.

BOP Places 11 SG AFW Block Valves in Open.

ATC May commence Aux Spray to lower RCS pressure.

Events #7/8 continue on the next page Examiner notes:

Page 15 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2020 11 AFW Pump Trip/23 AFW Pump M-ALL Events #7/8 Trip/Loss of All Feedwater/EOP-8 C-BOP/SRO Time Position Applicants Actions or Behavior When 12 AFW Pump becomes available, directs its use to establish SRO AFW flow to 11 SG.

BOP Directs the TBO to align 12 AFW Pump to service.

CRITICAL TASK - Establishes AFW flow to at least one S/G prior to S/G levels going below (-)350 inches OR Commences OTCC when BOP/SRO both S/G levels are below (-)350 inches or TCOLD rises uncontrollably by 5°F or greater and prior to CET temperatures reaching 560°F.

BOP Adjust AFW flow to 11 SG to restore level to normal value.

Examiner notes:

The scenario will terminate once AFW flow is established to at least one SG in EOP-8.

After scenario ends, if desired by Examiner, ask SRO for ERPIP call. The correct Emergency Action Level declaration for this scenario is:

Site Area Emergency, per FS1, due to OTCC in effect (Potential Loss of 2 Barriers).

Page 16 of 19

SHIFT TURNOVER INFORMATION SHEET [B0459]

Date: Today Station: Calvert Cliffs Unit: 1 Mode: Online % Rx Power: 100 MWE: 920 Days On-Line (or Outage): 30 On-Line (or Outage) Risk Level: Green Off Normal Trends:

Production: (include activities through 0900 hrs of next non-holiday business day, start and end times with dates (if not the current day), LCO if applicable, Identifier of step 4.2.4.2 if applicable, On-Line Risk if not Green. Example of desired format is: A Isolation Condenser sensor calibration, 11/01 0700 -11/02 1500, 7 day LCO, (HT), OLR Yellow 13 AFW Pump Unit: 2 Mode: Online % Rx Power: 100 MWE: 906 Days On-Line (or Outage): 230 On-Line (or Outage) Risk Level: Green Off Normal Trends:

Production: (include activities through 0900 hrs of next non-holiday business day, start and end times with dates (if not the current day), LCO if applicable, Identifier of step 4.2.4.2 if applicable, On-Line Risk if not Green. Example of desired format is: A Isolation Condenser sensor calibration, 11/01 0700 -11/02 1500, 7 day LCO, (HT), OLR Yellow Station Event-Free Days: 691 Significant Event Reporting: (on the first business Reactivity Management Event-Free Days: 197 day following a weekend or holiday include the events Configuration Control Event-Free Days: 206 since the last business day):

Critical Component Failure Clock Days: 103 Clearance & Tagging Event-Free Days: 691 No Significant Events Station Duty Manager: Jake Smith Page 17 of 19

SHIFT TURNOVER INFORMATION SHEET [B0459]

MISCELLANEOUS UNIT 1 UNIT 2 S/G Blowdown Status 100 gpm to CW 100 gpm to CW OI-8A Sect 6.7 OI-8A Sect 6.7 VCT Pressure Band 35 - 41 psig H2 33 - 39 psig H2 SPENT FUEL EQUIPMENT CHECKOUTS:

SFHM PE 0-081-01-O-Q New Fuel Elevator OI-25B App A SF Insp. Elev. OI-25B App B Last done Two Months Ago

{C93668376} 6 Months Ago 9 Months Ago PMC-18-107842 extended to semi -annually (DDD Next Year)

COMMON LONG TERM NOTES:

1. None.

SHORT TERM NOTES:

1. None.

Page 18 of 19

SHIFT TURNOVER INFORMATION SHEET [B0459]

UNIT 1 STP O-73A Quarterly Value (Rolling past 3 OI-29 Value quarters) (Date Format - MM/DD/YY) 32.9 psig 32.9 psig 32.8 11 Yesterday 3 Months 33.2 psig Yesterday Sec 6.39 Ago 6 Months Ago Max Header Pressure 30.7 psig 30.8 psig 30.7 psig 30.6 psig PE 1-12-21-O-M 12 Yesterday 3 Months Yesterday 6 Months Ago SW PUMP Sec 6.46 Ago 32.0 psig 13 (11 Hdr) 2 Weeks Ago Sec 6.39 30.2 psig 30.4 psig 29.6 psig 30.6 psig 13 (12 Hdr) Yesterday 3 Months Yesterday 6 Months Ago Sec 6.46 Ago LONG TERM NOTES:

1. None.

SHORT TERM NOTES:

1. 13 AFW Pump OOS due to emergent maintenance, LCO 3.7.3.B entered, expected return in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Page 19 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Examiners: Operators:

Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.

Turnover: 13 CAC is OOS.

Instructions to the crew: The Shift Manager directs the crew to commence RCS Boron Equalization per OI-1H Section 6.6 to support a scheduled reactor downpower next shift.

Critical Tasks

1. Establishes AFW flow to at least one S/G prior to S/G levels going below (-)350 inches.

2. Trips all RCPs within 15 minutes after receiving CIS actuation.

3. Identifies 12 Steam Generator as faulted and isolates 12 S/G.

4. Establishes at least one train of Containment Spray flow to Containment.

Event # Malfunction # Event Type* Event Description 1 N/A N-ATC/SRO Equalize Boron I-BOP/SRO 2 rcs004_03 11A Loop TCOLD 1-TT-112CC Fails High T-SRO C-ALL 3 480v001_08 Loss of 14B 480V Bus/AOP-7I T-SRO U25-11-LCL-BKR C-BOP/SRO 4 Main Transformer Loss of Cooling/AOP-7E R-ATC Downpower 11 SGFP Trip/AOP-3G 5 fw004_01 C-ALL EOP-0 6 fw004_02 C-BOP/SRO 12 SGFP Trip 7 ms010_02 M-ALL Steam Line Rupture in Containment/EOP-4 esfa004_01/02 8 I-ATC/SRO CSAS Auto and Manual Failure esfa005_01/02

(N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Scenario Overview Initial Conditions:

Unit-1 at 100% power, MOC, Unit-2 at 100% power Equipment OOS: 13 CAC Abnormal Conditions: None Instructions for shift: The Shift Manager directs the crew to commence RCS Boron Equalization per OI-1H Section 6.6 to support a scheduled reactor downpower next shift.

Event 1 - The crew will commence RCS Boron Equalization per OI-1H Section 6.6 to support a scheduled reactor downpower next shift.

Event 2 - 11A Loop TCOLD 1-TT-112CC Fails High. Alarm Response Manual 1C05 actions will have crew investigate failure at 1C15. When the failure is recognized, the crew should reference OP-CA-103-102-0200 and bypass RPS Channel C trip units 1,7, & 10 and enter Tech Spec 3.3.1.A with required actions to place trip units in bypass or trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and then restore trip units to operable status or in trip status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Event 3 - Once the trip units are bypassed, a Loss of 14B 480V Bus will occur. The crew will implement AOP-7I Section XXVII, Loss of 14B 480V Bus, which will direct their actions in protecting plant equipment and placing a Charging Pump and 11 Main Vent Fan in service.

Determines Tech Spec LCO 3.8.9.A is applicable with a required action to restore the AC subsystem to operable status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Event 4 - A Loss of Cooling to Main Transformer U-25000-11 will occur. The crew will respond using AOP-7E Section XII, Total Loss of Unit Transformer Cooling, and will commence a reactor downpower per OP-3.

Event 5 - At 90% reactor power during the downpower, 11 SGFP will trip. The crew is expected to implement AOP-3G and monitor for reactor trip criteria. The crew will be unable to reset 11 SGFP and will then trip the reactor.

Event 6 - In EOP-0, 12 SGFP will trip 1 minute after the reactor trip requiring the crew to perform the Critical Task to initiate AFW flow to the Steam Generators based on the loss of Main Feedwater flow.

Event 7 - The major event will be a 12 SG Steam Line Rupture inside Containment that will occur 6 minutes after the reactor trip. In EOP-0, the crew will perform the Critical Task of securing all RCPs after the CIS actuation. In EOP-4, the crew will perform the Critical Task of identifying 12 SG as being faulted and isolating 12 SG.

Event 8 - Both CSAS channels will fail to automatically actuate and manually actuate with the pushbuttons requiring the crew to perform the Critical Task to take manual actions to initiate at least one train of Containment Spray flow.

Page 2 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Instructor Scenario Information

_____ 1. Reset to IC-34.

_____ 2. Place simulator in RUN.

_____ 3. Clear PPC Screen trend lines if necessary.

_____ 4. Place simulator in FREEZE.

_____ 5. Enter Triggers:

_____ a. Reactor Trip, CEA_ROD_POSITION(1) < 5, to trigger Events 6 and 7.

_____ 6. Enter Malfunctions:

_____ a. rcs004_03 to 1_HIGH, 11A Loop TCOLD 112CC Fails High, on Event 2.

_____ b. 480v001_08, Loss of 14B 480V Bus, on Event 3.

_____ c. U25-11-LCL-BKR to both_opn, U-25000-11 Main Transformer Loss of Cooling, on Event 4.

_____ d. fw004_01, 11 SGFP Trip, on Event 5.

_____ e. fw004_02 after 60, 12 SGFP Trip after a 1 minute delay, on Event 6.

_____ f. ms010_02 after 360 to 50, 12 SG Steam Line Rupture in Containment to 50% after a 6 minute delay, on Event 7.

_____ g. esfa004_01, CSAS Channel A Auto Failure, at time zero.

_____ h. esfa004_02, CSAS Channel B Auto Failure, at time zero.

_____ i. esfa005_01, CSAS Channel A Manual Failure, at time zero.

_____ j. esfa005_02, CSAS Channel B Manual Failure, at time zero.

_____ k. afw004_01, AFAS Channel A Failure to Actuate, at time zero.

_____ l. afw004_02, AFAS Channel B Failure to Actuate, at time zero.

_____ 7. Enter Remote Functions:

_____ a. None.

_____ 8. Enter Panel Overrides:

_____ a. P1C10_1HS5301 to STOP at time zero.

_____ b. P1C10_1HS5301_LTGREE to Off at time zero.

_____ 9. Administrative:

_____ a. Ensure 14 CAC is one of the three running CACs.

_____ b. Ensure 12 Charging Pump is the selected running pump.

_____ c. Ensure 12 Main Vent Fan is running.

_____ d. Set Met Tower air temperature to 70°F.

_____ e. Verify ovation screens are reset and working.

_____ 10. Independently verify correct completion of the following:

Page 3 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020

_____ a. Event Triggers correctly entered.

_____ b. Malfunctions correctly entered.

_____ c. Remote Functions correctly entered.

_____ d. Panel Overrides correctly entered.

_____ e. Administrative actions correctly performed.

_____ 11. Place simulator in RUN.

_____ 12. Ensure schedule files are in RUN.

_____ 13. Ensure Trigger files are in RUN.

_____ 14. Ensure SBT Report is running with the SBT Insight file open.

_____ 15. Reset/Acknowledge panel and PPC alarms.

_____ 16. Ensure all PPC screens selected to Main Menu, Alarms, or SPDS Operating Summary page.

_____ 17. Select Clock and ensure Horn On for annunciators.

_____ 18. Allow crew to pre-brief the evolution for commencing RCS Boron Equalization.

_____ 19. Brief the Crew:

Unit-1 is at 100% power, MOC.

1. Present plant conditions:

Unit-2 is at 100% power.

Reactor has been at steady state 100% power for the

2. Power history:

last 3 months.

3. Equipment out of service: 13 CAC is OOS for breaker work. (IAS 3.6.6.B)

4. Abnormal conditions: None

5. Surveillances due: None The Shift Manager directs the crew to commence RCS

6. Instructions for shift: Boron Equalization per OI-1H Section 6.6 to support a scheduled reactor downpower next shift.

_____ 20. Allow crew 3-5 minutes to acclimate themselves with their positions.

Page 4 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020

_____ 21. Instructions for the Booth Operator:

_____ a. Event 1: Call in as the WEC SRO and request that RCS Boron Equalization be placed in service when directed by the Lead Examiner.

_____ b. Event 2: Activate Event 2, 11A Loop TCOLD 112CC Fails High, when directed by the Lead Examiner.

_____ c. Event 3: Activate Event 3, Loss of 14B 480V Bus, when directed by the Lead Examiner.

_____ d. Event 4: Activate Event 4, U-25000-11 Main Transformer Loss of Cooling, when directed by the Lead Examiner.

_____ e. Event 5: Activate Event 5, 11 SGFP Trip, when directed by the Lead Examiner.

_____ f. Event 6: Ensure Event 6, 12 SGFP Trip, activates automatically upon the reactor trip with a 1 minute delay.

_____ g. Event 7: Ensure Event 7, 12 SG Steam Line Rupture in Containment, activates automatically upon the reactor trip with a 6 minute delay.

Page 5 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Responses to Crew Requests If a request and response is not listed, delay the response until reviewed with the examiner. If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

Allow 2-3 minutes to perform requests from or to give reports to the Control Room unless otherwise specified.

REQUEST RESPONSE Event 1 - RCS Boron Equalization

1. Chemistry informed of Boron Acknowledge information. No further actions are Equalization. required.

Event 2 - 11A Loop TCOLD 112CC Fails High

1. WEC/Maintenance informed of Acknowledge request. No further actions are required.

issue/status.

Event 3 - Loss of 14B 480V Bus

1. WEC/Maintenance informed of Acknowledge request. No further actions are required.

issue/status.

3 minutes later report 14B 480V Bus feeder breaker

2. TBO investigate 14B 480V Bus.

has tripped open, unknown reason.

Acknowledge request. Imitate System Lineup cvcs_chgpp13_bus14.sch to align 13 Chg Pp to 14

3. PPO/TBO Align 13 CHG PP to the 480V Bus (expedite schedule per Lead Instructor 14 480V Bus direction). Report completion of activity to Control Room when schedule is complete.

Event 4 - U-25000-11 Main Transformer Loss of Cooling After 1 minute, report alarms hanging are Loss of AC

1. OSO investigate U-25000-11 Main Control Power to both #1 and #2 Group Oil Flow Transformer.

Stop. It appears there is no power to the oil pumps.

Acknowledge request. Note time of reports.

After 1 minute, report Winding temperature is 110°C and Liquid temperature is 80°C, both rising at 1°C per

2. OSO report temperatures on U-minute. Outside air temperature is 95°F. If asked, 25000-11.

there were only four cooler units initially in operation.

Provide updates based on temperature rise as requested by the crew.

Acknowledge request. After 1 minute, report breaker

3. TBO investigate status of feeder 52-1211 (Normal Supply) was found tripped and breakers for U-25000-11 cooling. breaker 52-1311 (Alternate Supply) is closed with no apparent issues.

4. TSO/Generation Dispatch informed Acknowledge report.

Page 6 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 of Unit 1 MVARs to zero.

Acknowledge request/info.

5. WEC/Electrical Maintenance informed of the Loss of Cooling. Report maintenance response will take time due to need to call-in electricians.

6. TSO/Generation Dispatch informed Acknowledge request. No further actions are required.

of downpower for casualty.

7. TBO Standby to operate MSR Panel Acknowledge request. No further actions are required.

Loaders during downpower.

Event 5 - 11 SGFP Trip/EOP-0

1. WEC/Maintenance informed of the Acknowledge request. No further actions are required.

issue.

Event 6 - 12 SGFP Trip

1. WEC informed of the issue. Acknowledge request. No further actions are required.

2. TBO verify AFW Pump running SAT and/or investigate room Acknowledge request. No further actions are required.

temperature.

3. ABO directed to ensure AFW Pump Acknowledge request. No further actions are required.

room emergency ventilation running.

Event 7 - 12 SG Steam Line Rupture inside Containment

1. WEC/Maintenance informed of the Acknowledge request. No further actions are required.

issue.

Event 8 - CSAS Automatic and Manual Actuation Failure

1. WEC/Maintenance informed to the Acknowledge request. No further actions are required.

issue.

Page 7 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Event #1 Commence RCS Boron Equalization N-ATC/SRO Time Position Applicants Actions or Behavior ATC Places the Backup Heater handswitches to ON.

Lowers the setpoint on the selected Pressurizer Pressure Controller to ATC approximately 2205 PSIA (+/-10 PSIA).

Lowers the setpoint on the non-selected Pressurizer Pressure Controller ATC to approximately 2205 PSIA (+/-10 PSIA).

May continue to monitor Pressurizer Pressure and/or make setpoint ATC adjustments to maintain Pressurizer Pressure at its starting value.

May notify Chemistry that RCS Boron Equalization has been placed in ATC/SRO service.

Examiner notes:

Event concludes when 11A Loop TCOLD 112CC Fails High.

NOTE TO EXAMINER Cue Booth Operator to initiate Event #2, 11A Loop TCOLD 112CC Fails High.

Page 8 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Event #2 11A Loop TCOLD 112CC Fails High I-BOP/SRO, T-SRO Time Position Applicants Actions or Behavior ATC/BOP May report Multiple Alarms.

SRO May direct ATC to monitor primary.

Determines and reports that primary is stable but 11A Loop TCOLD ATC indication has failed high.

SRO May direct BOP to check if RPS is calling for a trip.

BOP Determines RPS is not calling for a trip.

Determines and reports that Channel C RPS TCOLD indication has failed BOP high.

SRO May inform WEC/Maintenance of the issue.

May reference OP-CA-103-102-0200, SRO Determines Tech Specs LCO 3.3.1.A applies with required actions to place trip units in bypass or trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and then restore trip units to operable status or in trip status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Bypasses RPS Channel C trip units 1,7,&10 per OI-6 by performing the following for each trip unit:

BOP

INSERT the bypass key in the Trip Unit to be bypassed

TURN the bypass key clockwise to BYPASS

CHECK the BYPASS light illuminates Provides a peer-check, if requested, that proper Trip Units are correctly ATC bypassed.

ATC May place pink tags on affected instruments on the control boards.

Examiner notes:

Event concludes when a Loss of 14B 480V Bus occurs. If SROs understanding of Technical Specification applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

NOTE TO EXAMINER Cue Booth Operator to initiate Event #3, Loss of 14B 480V Bus, when desired.

Page 9 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Event #3 Loss of 14B 480V Bus C-ALL, T-SRO Time Position Applicants Actions or Behavior ATC/BOP May recognize and call multiple alarms and reports to SRO.

May report that Pressurizer Level is lowering due to previously running ATC 12 Charging Pump has lost power.

May report that RPS is not calling for a trip. Determines and reports BOP 14B 480V Bus is deenergized.

Directs crew to implement AOP-7I,Section XXVII for a Loss of 14B SRO 480V Bus.

SRO May inform WEC/Maintenance of the issue.

ATC May direct PPO/TBO to realign 13 Charging Pump to the 14 480V bus.

Starts 11 or 13 Charging Pump per AOP-7I or 1C07 Alarm Manual ATC actions. May secure Letdown if a Charging Pump is not promptly returned to service.

BOP Starts 11 Main Exhaust Fan per OI-22A, Main Exhaust Fan System.

Determines Tech Spec LCO 3.8.9.A is applicable with a required action SRO to restore the AC subsystem to operable status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SRO May reference OP-CA-TRM-100 for Charging flow paths.

Examiner notes:

Event concludes when a U-25000-11 Main Transformer Loss of Cooling occurs. If SROs understanding of Technical Specification applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

NOTE TO EXAMINER Cue Booth Operator to initiate Event #4, U-25000-11 Main Transformer Loss of Cooling, when desired.

Page 10 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Event #4 Main Transformer Loss of Cooling C-BOP/SRO, R-ATC Time Position Applicants Actions or Behavior Recognizes alarm for U-25000-11 on 1C01, refers to alarm manual, and BOP dispatches OSO to investigate.

Directs implementation of AOP-7E Main Turbine Malfunction Section SRO XII for Main Transformer Loss of Cooling.

BOP Lowers Unit-1 Main Generator reactive load MVARs to zero.

BOP/SRO Directs OSO to report Transformer Winding and Liquid temperatures.

SRO Directs the crew to perform a rapid downpower.

Commences a rapid downpower per OP-3 by use of RCS boration ATC and/or the insertion of CEAs.

Lowers Main Turbine load to maintain RCS TCOLD on program during BOP the downpower.

Examiner notes:

Event concludes when 11 SGFP trips.

NOTE TO EXAMINER At approximately 90% reactor power, cue Booth Operator to initiate Event #5, 11 SGFP trip, when desired.

Page 11 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Event #5 11 SGFP Trip / EOP-0 C-ALL Time Position Applicants Actions or Behavior BOP Recognizes 11 SGFP Trip alarm on 1C03 and notifies SRO.

Directs implementation of AOP-3G, Malfunction of Main Feedwater SRO System.

BOP Attempts to reset 11 SGFP by depressing both reset pushbuttons.

SRO Directs the ATC to trip the reactor. Implements EOP-0.

ATC Trips the reactor by depressing one set of trip pushbuttons.

Determines Reactor is tripped and Reactivity Safety Function is met.

ATC Informs the SRO that Reactivity is complete.

May report monitoring turbine trip for MSR 2nd Stage MOVs going BOP closed. Determines Turbine Trip is met. Informs the SRO that Turbine Trip is complete.

Determines Vital Auxiliaries Safety Function is met. Informs the SRO BOP that Vital Auxiliaries is complete.

Determines Pressure and Inventory Control Safety Function is met.

ATC Informs the SRO that Pressure and Inventory Control is complete.

Examiner notes:

Event concludes when 12 SGFP trips.

NOTE TO EXAMINER One minute after the reactor trip, Event #6 will initiate automatically to trip 12 SGFP.

Page 12 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 Event #6 12 SGFP Trip/EOP-0 C-BOP/SRO Time Position Applicants Actions or Behavior Determines 12 SGFP has also tripped and/or Main Feed has been lost.

BOP Performs the alternate actions to initiate AFW flow to the SGs.

CRITICAL TASK BOP Establishes AFW flow to at least one SG prior to SG levels going below (-)350 inches.

Determines Core and RCS Heat Removal Safety Function is met.

BOP Informs the SRO that Core and RCS Heat Removal is complete.

May determine Containment Environment Safety Function is met.

ATC/BOP Informs the SRO that Containment Environment is complete (depending on timing of Event #7).

May determine Radiation Levels External to Containment Safety ATC/BOP Function is met. Informs the SRO that Radiation Levels External to Containment is complete (depending on timing of Event #7).

Examiner notes:

Event concludes when the 12 SG Steam Line Rupture inside Containment occurs.

NOTE TO EXAMINER Six minutes after the reactor trip, Event #7 will initiate automatically to initiate a 12 SG Steam Line Rupture inside Containment.

Page 13 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 12 SG Steam Line Rupture/CSAS Auto Events #7,8 M-ALL and Manual Failure/EOP-4 Time Position Applicants Actions or Behavior Determines an additional transient is occurring based on RCS ATC/BOP temperatures, PZR level and pressure, and Containment parameters.

SRO May direct the re-assessment of EOP-0 Safety Functions.

ATC Verifies the SIAS and CIS actuations.

CRITICAL TASK ATC Trips all RCPs within 15 minutes after receiving CIS actuation.

Determines that Containment pressure is greater than the CSAS setpoint and that the automatic and manual CSAS actuations failed.

ATC

May determine the validity of the CSAS by observing alternate channels of indication for the same parameter.

May Push CSAS Manual Initiation pushbuttons and recognize/report ATC failure of manual pushbutton to the SRO.

May utilize ESFAS action placard OR Alarm manual actions to verify CSAS actuation:

ATC

VERIFY CSAS actuation by performing the following:

o CHECK CS HDR ISOL CVs open.

o CHECK Condensate Booster Pumps tripped.

CRITICAL TASK ATC Establishes at least one train of Containment Spray flow to Containment.

Determines Pressure and Inventory Control Safety Function is not ATC met. Informs the SRO that Pressure and Inventory Control is not met due to low PZR level and pressure.

Determines Core and RCS Heat Removal Safety Function is not met.

BOP Informs the SRO that Core and RCS Heat Removal is not met due to no RCPs running and low 12 SG pressure and TCOLD.

Event #7 continues next page.

Examiner notes:

Page 14 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #2 OP-Test # 2020 12 SG Steam Line Rupture/CSAS Auto Events #7,8 M-ALL and Manual Failure/EOP-4 Time Position Applicants Actions or Behavior May lower the AFW flow to 12 SG based on the Steam Line Rupture BOP event.

Determines Containment Environment Safety Function is not met.

ATC/BOP Informs the SRO that Containment Environment is not met due to high Containment temperature and pressure.

Evaluates the EOP-0 flowchart and recommends the implementation SRO of EOP-4. Directs implementation of EOP-4.

May direct Block Step D to verify proper operation of ECCS Pumps SRO upon the SIAS actuation.

Verifies all available HPSI, LPSI, and Charging Pumps are in ATC operation.

BOP/SRO Identifies 12 SG as the most affected SG.

CRITICAL TASK - Isolates 12 SG within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of the reactor trip:

Directs TBO to Align 12 ADV to 1C43 with a 0% output

Verifies shut 12 SG FW ISOL valve, 1-FW-4517-MOV.

Verifies shut 12 MSIV BYP valve, 1-MS-4052-MOV.

Shuts 12 SG Blowdown valves, BD-4012-CV and BD-4013-CV BOP

Shuts 12 SG AFW STM SUPP & BYPASS valves, MS-4071-CV and MS-4071A-CV

Shuts 12 S/G AFW BLOCK valves, AFW-4530-CV, AFW-4531-CV, AFW-4532-CV, AFW-4533-CV

Shuts the MS UPSTREAM DRN ISOL VLVS with 1-HS-6622 in CLOSE

Directs ABO/OSO to evaluate for leaking safety valves on 12 SG Examiner notes:

Event concludes when CSAS is manually actuated and the affected SG is isolated.

NOTE TO EXAMINER Scenario ends when CSAS is actuated and the affected SG is isolated, when directed by the Lead Examiner.

Page 15 of 18

SHIFT TURNOVER INFORMATION SHEET [B0459]

Date: Today Station: Calvert Cliffs Unit: 1 Mode: Online % Rx Power: 100 MWE: 920 Days On-Line (or Outage): 90 On-Line (or Outage) Risk Level: Green Off Normal Trends:

Production: (include activities through 0900 hrs of next non-holiday business day, start and end times with dates (if not the current day), LCO if applicable, Identifier of step 4.2.4.2 if applicable, On-Line Risk if not Green. Example of desired format is: A Isolation Condenser sensor calibration, 11/01 0700 -11/02 1500, 7 day LCO, (HT), OLR Yellow 13 CAC OOS Unit: 2 Mode: Online % Rx Power: 100 MWE: 906 Days On-Line (or Outage): 230 On-Line (or Outage) Risk Level: Green Off Normal Trends:

Production: (include activities through 0900 hrs of next non-holiday business day, start and end times with dates (if not the current day), LCO if applicable, Identifier of step 4.2.4.2 if applicable, On-Line Risk if not Green. Example of desired format is: A Isolation Condenser sensor calibration, 11/01 0700 -11/02 1500, 7 day LCO, (HT), OLR Yellow Station Event-Free Days: 691 Significant Event Reporting: (on the first business Reactivity Management Event-Free Days: 197 day following a weekend or holiday include the events Configuration Control Event-Free Days: 206 since the last business day):

Critical Component Failure Clock Days: 103 Clearance & Tagging Event-Free Days: 691 No Significant Events Station Duty Manager: Jake Smith Page 16 of 18

SHIFT TURNOVER INFORMATION SHEET [B0459]

MISCELLANEOUS UNIT 1 UNIT 2 S/G Blowdown Status 100 gpm to CW 100 gpm to CW OI-8A Sect 6.7 OI-8A Sect 6.7 VCT Pressure Band 35 - 41 psig H2 33 - 39 psig H2 SPENT FUEL EQUIPMENT CHECKOUTS:

SFHM PE 0-081-01-O-Q New Fuel Elevator OI-25B App A SF Insp. Elev. OI-25B App B Last done Two Months Ago

{C93668376} 6 Months Ago 9 Months Ago PMC-18-107842 extended to semi -annually (DDD Next Year)

COMMON LONG TERM NOTES:

1. None.

SHORT TERM NOTES:

1. None.

Page 17 of 18

SHIFT TURNOVER INFORMATION SHEET [B0459]

UNIT 1 STP O-73A Quarterly Value (Rolling past 3 OI-29 Value quarters) (Date Format - MM/DD/YY) 32.9 psig 32.9 psig 32.8 11 Yesterday 3 Months 33.2 psig Yesterday Sec 6.39 Ago 6 Months Ago Max Header Pressure 30.7 psig 30.8 psig 30.7 psig 30.6 psig PE 1-12-21-O-M 12 Yesterday 3 Months Yesterday 6 Months Ago SW PUMP Sec 6.46 Ago 32.0 psig 13 (11 Hdr) 2 Weeks Ago Sec 6.39 30.2 psig 30.4 psig 29.6 psig 30.6 psig 13 (12 Hdr) Yesterday 3 Months Yesterday 6 Months Ago Sec 6.46 Ago LONG TERM NOTES:

1. None.

SHORT TERM NOTES:

1. 13 CAC is OOS for breaker maintenance, expected return in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Page 18 of 18

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Examiners: Operators:

Initial Conditions: Unit-1 is at 3% power, MOC. Unit-2 is at 100% power.

Turnover: 13 CBP is OOS.

Instructions to the crew: Raise reactor power and stabilize at 8% per OP-3.

Critical Tasks

1. Commences an RCS Cooldown not to exceed 100°F in any one hour.

2. Trip 11A & 12B RCPs or 11B & 12A RCPs when RCS pressure decreases to <1725 PSIA prior to RCS subcooling being less than 20°F for 4 minutes.

Event # Malfunction # Event Type* Event Description N-BOP/SRO 1 N/A Raise Reactor Power R-ATC 2 rcs023_02 I-ATC/SRO 1-PT-100Y PZR Pressure PV Fails High C-BOP/SRO 3 sw002_01 11 Saltwater Pump Trip/AOP-7A T-SRO 4 ia001 C-BOP/SRO Instrument Air Leak/AOP-7D C-ALL RCS Leak Unisolated/AOP-2A 5 rcs003 T-SRO EOP-0 6 rcs002 M-ALL LOCA (800 gpm)/EOP-5 7 esfa010_01/02 C-ATC/SRO CIS Auto Failure

(N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Scenario Overview Initial Conditions:

Unit-1 at 3% power, MOC, Unit-2 at 100% power Equipment OOS: 13 Condensate Booster Pump.

Abnormal Conditions: None Instructions for shift: Raise reactor power and stabilize at 8% per OP-3.

Event 1 - The crew will perform a normal evolution of raising reactor power.

Event 2 PT-100Y, Pressurizer Pressure Controller process variable will fail high. Alarm Response Manual 1C06 actions will have the crew swap Pressurizer Pressure controllers to control RCS pressure.

Event 3 - 11 SW Pump Breaker will trip. The crew will implement AOP-7A, Loss of Saltwater Cooling, which will direct their actions in protecting plant equipment and aligning and starting 13 SW Pump. The crew will determine the following Tech Spec LCOs are applicable: 3.5.2.A with a required action to restore ECCS train to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (this LCO was already entered); 3.6.6.A with a required action to restore containment spray train to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; 3.6.6.B with a required action to restore containment cooling train to operable status within 7 days; 3.7.5.A with a required action to restore Component Cooling loop to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; 3.7.6.B with a required action to restore SRW subsystem to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and 3.7.7.A with a required action to restore SW subsystem to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Event 4 - An Instrument Air Leak will occur. The crew will implement AOP-7D, Loss of Instrument Air, which will direct the crew to start the Saltwater Air Compressors and ensure backup Instrument Air systems respond. When operators are dispatched to investigate the issue, the air leak will be quickly isolated.

Event 5 - An RCS Leak inside Containment of 70 gpm will occur. The crew will respond using AOP-2A, Excessive Reactor Coolant Leakage, and will not be able to isolate the leak at which point the reactor will be tripped. EOP-0, Post-Trip Immediate Actions will be implemented.

Determines Tech Spec LCO 3.4.13.A is applicable with a required action to reduce leakage to within limits of the LCO with a completion time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . It is acceptable to enter LCO 3.4.13.B with the assumption that pressure boundary leakage exists.

Event 6 - After the reactor trip, an 800 gpm RCS LOCA inside Containment will occur. The crew is expected to implement EOP-5 based on the LOCA in progress. The actions in EOP-5 will be to commence an RCS cooldown and depressurization to minimize the leakage and control RCS subcooling.

Event 7 - A failure of CIS Channels A and B to automatically actuate will occur. The crew is expected to recognize the failure and manually actuate CIS using either the pushbuttons or manually operate the components necessary.

Page 2 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Instructor Scenario Information

_____ 1. Reset to IC-09.

_____ 2. Place simulator in RUN.

_____ 3. Clear PPC Screen trend lines if necessary.

_____ 4. Place simulator in FREEZE.

_____ 5. Enter Triggers:

_____ a. Reactor Trip, CEA_ROD_POSITION(1) < 5, to trigger Event 6.

_____ 6. Enter Malfunctions:

_____ a. rcs023_02 to 1_HIGH, PT-100Y PZR Pressure Fails High, on Event 2.

_____ b. sw002_01, 11 Saltwater Pump Trips, on Event 3.

_____ c. ia001 to 14 in 60, Instrument Air Leak of 14%, 1 minute ramp, on Event 4.

_____ d. rcs003 to 70, RCS Leak inside Containment of 70 gpm, on Event 5.

_____ e. rcs002 after 10 to 800, LOCA of 800 gpm after 10 seconds, on Event 6.

_____ f. esfa010_01, CIS Channel A Auto Failure, at time zero.

_____ g. esfa010_02, CIS Channel B Auto Failure, at time zero.

_____ 7. Enter Remote Functions:

_____ a. 152-1304 to TRIP, 13 CBP, at time zero.

_____ b. 1-SW-115 to 0, Shut 13 SW Pump to 12 SW Hdr, on Event 7.

_____ c. 1-SW-113 after 30 to 1, Open 13 SW Pump to 11 SW Hdr, on Event 7.

_____ 8. Enter Panel Overrides:

_____ a. P1C03_1HS4467 to PTL, 13 CBP handswitch, at time zero.

_____ b. P1C07_F07_LTON to Off on Event 8.

_____ 9. Administrative:

_____ a. Place an INFO Tag on 13 CBP handswitch in the PTL position.

_____ b. Place Protected Equipment tags on 11 and 12 CBP handswitches.

_____ c. Verify CVCS integrators all read 0.

_____ d. Verify ovation screens are reset and working.

_____ e. 11 SGFP aligned to Aux Steam placard in place.

_____ 10. Independently verify correct completion of the following:

_____ a. Event Triggers correctly entered.

_____ b. Malfunctions correctly entered.

_____ c. Remote Functions correctly entered.

_____ d. Panel Overrides correctly entered.

Page 3 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020

_____ e. Administrative actions correctly performed.

_____ 11. Place simulator in RUN.

_____ 12. Ensure schedule files are in RUN.

_____ 13. Ensure Trigger files are in RUN.

_____ 14. Ensure SBT Report is running with the SBT Insight file open.

_____ 15. Reset/Acknowledge panel and PPC alarms.

_____ 16. Ensure all PPC screens selected to Main Menu, Alarms, or SPDS Operating Summary page.

_____ 17. Select Clock and ensure Horn On for annunciators.

_____ 18. Allow crew to pre-brief the evolution of raising reactor power per OP-3.

_____ 19. Brief the Crew:

Unit-1 is at 3% power, MOC.

1. Present plant conditions:

Unit-2 is at 100% power.

Reactor power is being returned to 100% after a 5 day

2. Power history:

maintenance outage.

3. Equipment out of 13 Condensate Booster Pump is OOS for breaker work.

service:

4. Abnormal conditions: None

5. Surveillances due: None

6. Instructions for shift: Raise reactor power and stabilize at 8% per OP-3.

_____ 20. Allow crew 3-5 minutes to acclimate themselves with their positions.

_____ 21. Instructions for the Booth Operator:

_____ a. Event 1: Call as Shift Manager and inform the Unit Supervisor that the OCC is requesting power be raised and stabilized at 8% for testing.

_____ b. Event 2: Activate Event 2, PZR Pressure Channel Y Fails High, when directed by the Lead Examiner.

_____ c. Event 3: Activate Event 3, 11 SW Pump Trip, when directed by the Lead Examiner.

_____ d. Event 4: Activate Event 4, Instrument Air Leak, when directed by the Lead Examiner.

_____ e. Event 5: Activate Event 5, RCS leak inside CTMT, when directed by the Lead Examiner.

_____ f. Event 6: Verify Event 6 Actuates to increase RCS Leak rate on the Rx Trip.

Page 4 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Responses to Crew Requests If a request and response is not listed, delay the response until reviewed with the examiner. If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

Allow 2-3 minutes to perform requests from or to give reports to the Control Room unless otherwise specified.

REQUEST RESPONSE Event 1 - Up Power Acknowledge request and report sampling is in

1. Chemistry perform RCS Boron Sample. progress, expect to report results in about 45 minutes.

Event 2, PZR Press Controller Y PV fails high

1. WEC/Maintenance informed of Acknowledge request. No further actions are issue/status. required.

Acknowledge request. No further actions are

2. ABO investigate Letdown System.

required.

Event 3 - 11 SW Pump Trip

1. WEC/Maintenance informed of Acknowledge request. No further actions are issue/status. required.

Acknowledge. Wait 2 minutes and report as TBO

2. OSO/TBO investigate trip of 11 you have overcurrent dropped flag. As OSO, Saltwater Pp.

report pump motor is hot when touched.

Acknowledge. Wait 2 minutes then activate

3. OSO/PPO align 13 SW Pp to 11 header. Event 7 to align 13 SW Pp to 11 SW header.

Report complete to control room.

Event 4 - Instrument Air Leak Acknowledge report. Upon Lead Evaluators cue, report that the Instrument Air leak is located at the in-service Instrument Air Dryer. The AOP-7D

1. Operators dispatched to investigate actions to bypass and isolate the IA Dryer will be Instrument Air leak. performed to restore IA header pressure.

When SWAC are started and on Lead Evaluators cue, REMOVE malfunction ia001 and report IA Air Dyer is isolated.

2. WEC/Maintenance notified of the Acknowledge report.

Instrument Air leak.

Event 5 - RCS Leak inside Containment/ EOP-0

1. Chemistry sample SGs per CY-CA-180- Acknowledge request.

Page 5 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 436, Qualitative Determination of After 5 minutes, report There is no RCS activity Affected S/G in a Tube Leak Event. in either 11 or 12 SG.

2. Equipment Operators dispatched to Acknowledge request.

investigate for an RCS leak in the Aux After 3 minutes, report there are no indications of Building. a leak in the Aux Building.

3. Radiation Protection informed of an RCS leak and radiation may change Acknowledge information.

throughout the plant.

4. Generation Dispatch informed of Unit-1 Acknowledge information.

being taken offline.

Event 6- LOCA in containment/ EOP-5 Acknowledge request. No further actions

1. WEC informed of issue/status.

required.

Acknowledge request. No further actions

2. RadCon/Chemistry informed of leak.

required.

Acknowledge request.

3. Pull Alarm Cards for nuisance alarms.

Override selected annunciator and report Alarm Card for Window # has been pulled.

Acknowledge request. No further actions

4. Verify SRW Pp Room Ventilation.

required.

5. Chem-Place CTMT Hydrogen Monitors Acknowledge request. No further actions in service. required.

Event 7 - CIS Failure Acknowledge request. No further actions

1. WEC informed of issue/status.

required.

Page 6 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Event #1 Raise Rx Power N-BOP/SRO, R-ATC Time Position Applicants Actions or Behavior Directs crew to raise power and stabilize at 8%. May provide specific SRO reactivity control directions and stop criteria.

ATC Withdraws CEAs and/or performs RCS dilution to raise reactor power.

ATC May reset the VOPT setting every 2 to 4 percent increase in power.

May periodically compare all indications of power. IF at any time an unexplained difference exists between NI, Delta-T or calorimetric ATC power, then stop increasing Reactor power until the discrepancy is resolved.

May periodically verify that Pressurizer Programmed Level is within ATC the acceptable PZR level band per Figure (3). (Computer points for Tavg are 1T191 and 1T192).

May periodically MONITOR ASI to ensure oscillations will not reach ATC the ASI pre-trip value.

Monitors Tc. If deviates greater than 2 °F from program Tc, TEMPERATURE PROGRAM CURVE, THEN:

INFORM Control Room Supervisor.

INITIATE necessary corrective actions.

To lower Tc:

ATC RAISE steam demand.

LOWER reactor power by inserting CEAs or raising RCS boron concentration.

To raise Tc:

REDUCE steam demand.

RAISE reactor power by withdrawing CEAs or reducing RCS boron concentration.

Examiner notes:

Event concludes when alarms on 1C05 actuate for PZR Pressure failure.

NOTE TO EXAMINER Cue Booth Operator to initiate Event #2, 1-PT-100Y, Pressurizer Pressure Controller PV fails high.

Page 7 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Event #2 PZR Press Controller PV fails high I-ATC/SRO Time Position Applicants Actions or Behavior Notes E-29 PZR CH 100 Press alarm. Determines 1-PT-100Y or PIC-ATC/BOP 100Y process variable has failed high. Notifies US.

SRO May direct ATC to monitor primary.

Performs stabilizing actions to swap PZR Pressure control from ATC Channel Y to X.

ATC/BOP May refers to Alarm manual 1C06 for E-29 actions.

May refer to OP-CA-103-102-0200 Att-4, Tech Spec Implementation SRO Matrix and Attachment 5 Common Tap Analysis.

Determines no common mode or Tech Specs apply.

ATC May place pink tags on affected instruments at 1C06.

Examiner notes:

Event concludes when 11 SW Pump Trips.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction: Event #3, 11 SW Pump Trip, when desired.

Page 8 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Event #3 11 SW Pump Failure / AOP-7A C-BOP/SRO, T-SRO Time Position Applicants Actions or Behavior May notes plant computer alarm indicating loss of 11 SW Pump.

ATC/BOP Informs the US.

May note 1C13/1C19 alarms and indications confirming loss of 11 SW BOP Pump. Informs the US.

Implements AOP-7A, Loss of Saltwater in Modes 1 OR 2,Section V.

SRO Assigns hard card trip criteria per AOP-7A to RO.

ATC/BOP May directs TBO to investigate 11 SW Pump.

ATC Monitors Step V.A trip criteria.

SRO Directs crew to implement AOP-7A, Loss of Salt Water.

SRO May inform WEC/Maintenance of the issue.

BOP Places 13 SW Pump in PTL. May also place 11 SW Pump in PTL.

BOP Directs TBO to mechanically align 13 SW Pump to 11 SRW Header.

BOP Starts 13 SW Pump.

SRO May inform WEC/Maintenance to rack out breaker for 11 SW Pump.

The crew will determine the following Tech Spec LCOs are applicable:

3.5.2.A with a required action to restore ECCS train to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (this LCO was already entered); 3.6.6.A with a required action to restore containment spray train to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; 3.6.6.B with a required action to restore containment cooling SRO train to operable status within 7 days; 3.7.5.A with a required action to restore Component Cooling loop to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; 3.7.6.B with a required action to restore SRW subsystem to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and 3.7.7.A with a required action to restore SW subsystem to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Examiner notes:

Event concludes when Inst Air Leak alarms or indications are recognized. If SROs understanding of Technical Specification applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Event #4, Inst Air Leak, when desired.

Page 9 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Event #4 Instrument Air Leak C-BOP/SRO Time Position Applicants Actions or Behavior Refers to Alarm Manual for alarm and determines a loss of IA is BOP occurring.

ATC Monitors the Primary.

ATC/BOP May monitor Air Pressure on the plant computer and/or 1C13.

Implements AOP-7D, Loss of Instrument Air. Assigns trip criteria SRO monitoring.

SRO Directs BOP to perform AOP-7D starting at Section V.B.

ALL Notify field operators to investigate for cause of lower IA Pressure.

Starts SWACs when <90 PSIG and bypasses Condensate Precoats and BOP Demins when <80 PSIG.

When malfunction removed, monitors and reports IA pressure BOP/ATC restoring.

May brief crew on follow-up actions to restore I/A system to normal SRO lineup: Shuts 1-PA-2061-CV, opens 1-PA-2059-CV, secures 12 I/A Compressor and places it back in Auto. Secures SWACs.

Examiner notes:

Event concludes when air pressure is reported as restoring.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Event #5, RCS leak in CTMT.

Page 10 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Event #5 CTMT RCS Leak / AOP-2A / EOP-0 C-ALL, T-SRO Time Position Applicants Actions or Behavior ATC Determines PZR level is lowering and reports to crew.

SRO Directs ATC to Monitor the Primary.

May recognize and report start of backup Charging pump and notify ATC SRO leakage exceed the capacity of the running pump.

Reports CTMT Normal Sump Alarm and may respond per the ALM BOP Manual.

Directs implementation of AOP-2A for RCS exceeding capacity of SRO one charging pump. Assign Trip Criteria.

Direct Chemistry to perform qualitative samples on both SGs for SRO activity per CY-AA-180-436.

Shuts the L/D CNTMT ISOL valves, 1-CVC-515-CV and 1-CVC-ATC 516-CV.

Performs AOP-2A VI.D to check for SG Tube Leakage. Evaluates BOP RMSs and determines no tube leakage is indicated.

BOP/ATC Evaluates and determines NO PORV leakage.

Evaluates Charging header leakage by securing all but one charging BOP/ATC pump and observing Charging Header pressure remains higher than RCS Pressure. Determines no Charging Header leakage.

Evaluates for CTMT leakage by observing Pressure/ Temp / Humidity BOP trends and WRNG and Main Vent Gaseous RMS are not in alarm.

Determines leak is in CTMT and reports to crew.

BOP Starts All available CNMT Air Coolers in High.

Open the CNTMT CLR EMER OUT valves for the operating BOP CNTMT AIR CLRs.

BOP May Evaluate Component Cooling for leakage.

Examiner notes:

Event #5 continues next page.

Page 11 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Event #5 CTMT RCS Leak / AOP-2A / EOP-0 C-ALL, T-SRO Time Position Applicants Actions or Behavior Determines Tech Spec LCO 3.4.13.A is applicable with a required action to reduce leakage to within limits of the LCO with a SRO completion time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . It is acceptable to enter LCO 3.4.13.B with the assumption that pressure boundary leakage exists.

Determines Leak cannot be isolated and exceed one charging pump SRO capacity. Directs ATC to trip the RX and Implementation of EOP-0.

ATC Trips the reactor.

Determines Reactor is tripped and Reactivity Safety Function is met.

ATC Informs the SRO that Reactivity is complete.

May report monitoring turbine trip for MSR 2nd Stage MOVs going BOP closed. Determines Turbine Trip is met. Informs the SRO that Turbine Trip is complete.

Determines Vital Auxiliaries Safety Function is met. Informs the SRO BOP that Vital Auxiliaries is complete.

Determines Pressure and Inventory Control Safety Function is not ATC met. Informs the SRO that Pressure and Inventory Control is not met due to low PZR level and lowering PZR pressure.

Determines and reports Core and RCS Heat Removal Safety Function BOP is met.

Determines Containment Environment Safety Function is not met.

ATC/BOP Informs the SRO that Containment Environment is not met due to trends on pressure / Temp / and humidity.

Determines Radiation Levels External to Containment Safety ATC/BOP Function is met. Informs the SRO that Radiation Levels External to Containment is complete.

Examiner notes:

Event #5 continues next page.

Page 12 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 Event #5 CTMT RCS Leak / AOP-2A / EOP-0 C-ALL, T-SRO May Align AFW per EOP-0 due to pending loss of Main Feedwater BOP due to SIAS.

ATC Verifies the SIAS actuation.

CRITICAL TASK - Trip 11A & 12B RCPs or 11B & 12A RCPs ATC when RCS pressure decreases to <1725 PSIA prior to RCS subcooling being less than 20oF for 4 minutes.

May implement AOP-2A, Excessive RCS Leakage after all EOP-0 panel actions are complete by directing actions for exceeding the capacity of a Charging Pump in Mode 3.

SRO

May direct open Main and Aux HPSI Header MOVs

May direct start 11 and 13 HPSI Pumps

May direct block SIAS PZR PRESS If Mode 3 AOP-2A actions are assigned:

ATC

May open Main and Aux HPSI Header MOVs

May start 11 and 13 HPSI Pumps

May block SIAS PZR PRESS Evaluates the EOP-0 flowchart and recommends the implementation SRO of EOP-5.

Examiner notes:

NOTE TO EXAMINER Event concludes when EOP-5 is entered.

Page 13 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 6: M-ALL Events #6 & 7 LOCA in CTMT / EOP-5 / CIS 7: C-ATC/SRO Time Position Applicants Actions or Behavior SRO Directs implementation of EOP-5.

Monitors RCS depressurization/Verifies SIAS:

ATC

Verifies open Main and Aux HPSI Header MOVs

Verifies 11 and 13 HPSI Pumps and all Chg PPs are running

May block SIAS PZR PRESS if not actuated May Performs RCP Trip Strategy if not already done:

ATC

Determines RCS pressure is lowering and is not under Operator control

Trips 11A&12B or 11B&12A RCPs Maintains Containment Environment:

BOP

Verifies all CNTMT AIR CLRs are running

Verifies all CNTMT CLR EMERG OUT valves are open Determines CIS has not actuated automatically:

ATC

Determines CTMT Pressure > 2.8 PSIG

Notifies SRO CIS failed to actuate Monitors EOP Attachment 1 RCS Pressure Temperature Limits.

ATC IF RCS pressure drops below the minimum pump operating limits, THEN trip ALL RCPs.

SRO May Directs manual actions to initiate CIS.

Manually Initiates CIS:

May Depress both CIS Actuation Pushbuttons ATC

May manually close CC CTMT isolation valves (1-CC-3832 and 1-CV-3833)

Secures All RCPs Examiner notes:

Events #6 & 7 continue on next page.

Page 14 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 6: M-ALL Events #6 & 7 LOCA- CTMT / EOP-5 / CIS 7: C-ATC/SRO Time Position Applicants Actions or Behavior ATTEMPT LEAK ISOLATION by:

Verify L/D CNTMT ISOL valves are shut.

Check there is NO PORV leakage.

Shut RCS SAMPLE ISOL valve, 1-PS-5464-CV.

Shut RX VESS VENT valves: 1-RC-103-SV &1-RC-104-SV.

ATC/BOP

Shut PRZR VENT valves: 1-RC-105-SV & 1-RC-106-SV.

Verifies LOCA inside containment by:

o Rise in containment temperature, pressure, humidity or sump level.

o UNIT 1 WIDE RANGE NOBLE GAS MON and UNIT 1 MAIN VENT GASEOUS alarms clear.

BOP Ensures both CCHXs have cooling from the control room.

BOP Verifies SRW Pump Room Ventilation in service per OI-15.

BOP Ensures Chemistry has been directed to place H2 Monitors in service.

Verify Boration: 1-CVC-514 is Open, 1-CVC-508 & 509 are Open, ATC All BA PPs are running, 1-CVC-501 is Shut, All Chg PPs running.

May Alert Crew to use adverse CTMT parameter specifications ({ }

SRO numbers based on elevated CTMT parameter.

Examiner notes:

Event #6 continues the next page Page 15 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #3 OP-Test # 2020 6: M-ALL Events #6 & 7 LOCA- CTMT / EOP-5 / CIS 7: C-ATC/SRO Time Position Applicants Actions or Behavior Directs RCS cooldown to less than 300°F using TURB BYP valves or SRO ADVs, maintain RCS cooldown less than 100°F in any one hour.

Initiates Cooldown by Throttling Opening TBVs.

BOP

May Open ADVs if SGIS Actuated.

CRITICAL TASK BOP Commences an RCS Cooldown not to exceed 100°F in any one hour.

May Block SGIS A/B if they have not already actuated when the BOP "SGIS A BLOCK PERMITTED" alarm is received.

Directs RCS Depressurization to maintain RCS Subcooling between SRO 30-140°F.

Raise subcooling by any of:

Energize the Pressurizer HTR(s).

IF HPSI flow has been reduced, THEN raise HPSI flow by ATC opening HPSI HDR valves which have been throttled or starting HPSI PPs which have been stopped.

Raise RCS cooldown rate, while NOT exceeding 100°F in any one hour.

Examiner notes:

NOTE TO EXAMINER Scenario terminates when cooldown control is established and when Lead directs.

Page 16 of 19

SHIFT TURNOVER INFORMATION SHEET [B0459]

Date: Today Station: Calvert Cliffs Unit: 1 Mode: Online % Rx Power: 3 MWE: Offline Days On-Line (or Outage): 0 On-Line (or Outage) Risk Level: Green Off Normal Trends:

Production: (include activities through 0900 hrs of next non-holiday business day, start and end times with dates (if not the current day), LCO if applicable, Identifier of step 4.2.4.2 if applicable, On-Line Risk if not Green. Example of desired format is: A Isolation Condenser sensor calibration, 11/01 0700 -11/02 1500, 7 day LCO, (HT), OLR Yellow 13 CBP OOS Unit: 2 Mode: Online % Rx Power: 100 MWE: 906 Days On-Line (or Outage): 230 On-Line (or Outage) Risk Level: Green Off Normal Trends:

Production: (include activities through 0900 hrs of next non-holiday business day, start and end times with dates (if not the current day), LCO if applicable, Identifier of step 4.2.4.2 if applicable, On-Line Risk if not Green. Example of desired format is: A Isolation Condenser sensor calibration, 11/01 0700 -11/02 1500, 7 day LCO, (HT), OLR Yellow Station Event-Free Days: 691 Significant Event Reporting: (on the first business Reactivity Management Event-Free Days: 197 day following a weekend or holiday include the events Configuration Control Event-Free Days: 206 since the last business day):

Critical Component Failure Clock Days: 103 Clearance & Tagging Event-Free Days: 691 No Significant Events Station Duty Manager: Jake Smith Page 17 of 19

SHIFT TURNOVER INFORMATION SHEET [B0459]

MISCELLANEOUS UNIT 1 UNIT 2 S/G Blowdown Status 100 gpm to CW 100 gpm to CW OI-8A Sect 6.7 OI-8A Sect 6.7 VCT Pressure Band 35 - 41 psig H2 33 - 39 psig H2 SPENT FUEL EQUIPMENT CHECKOUTS:

SFHM PE 0-081-01-O-Q New Fuel Elevator OI-25B App A SF Insp. Elev. OI-25B App B Last done Two Months Ago

{C93668376} 6 Months Ago 9 Months Ago PMC-18-107842 extended to semi -annually (DDD Next Year)

COMMON LONG TERM NOTES:

1. None.

SHORT TERM NOTES:

1. None.

Page 18 of 19

SHIFT TURNOVER INFORMATION SHEET [B0459]

UNIT 1 STP O-73A Quarterly Value (Rolling past 3 OI-29 Value quarters) (Date Format - MM/DD/YY) 32.9 psig 32.9 psig 32.8 11 Yesterday 3 Months 33.2 psig Yesterday Sec 6.39 Ago 6 Months Ago Max Header Pressure 30.7 psig 30.8 psig 30.7 psig 30.6 psig PE 1-12-21-O-M 12 Yesterday 3 Months Yesterday 6 Months Ago SW PUMP Sec 6.46 Ago 32.0 psig 13 (11 Hdr) 2 Weeks Ago Sec 6.39 30.2 psig 30.4 psig 29.6 psig 30.6 psig 13 (12 Hdr) Yesterday 3 Months Yesterday 6 Months Ago Sec 6.46 Ago LONG TERM NOTES:

1. None.

SHORT TERM NOTES:

1. 13 CBP is OOS for scheduled maintenance, expected return in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Page 19 of 19

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Examiners: Operators:

Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.

Turnover: 12 Boric Acid Pump is OOS, 0C DG is OOS.

Instructions to the crew: The Shift Manager has directed the crew to shift disconnects for 13 IRU to the 14B 480V Bus per OI-5B Section 6.2.

Critical Tasks

1. Establishes AFW flow to at least one S/G prior to S/G levels going below (-)350 inches.

2. Recognizes SFSC in EOP-2 not met and transitions to EOP-7 within 30 minutes of Station Blackout conditions.

3. Restores power to 11 or 14 4KV Bus prior to 11 or 22 DC Bus voltages going below 106V.

Event # Malfunction # Event Type* Event Description N-BOP/SRO 1 N/A 13 IRU Shift Disconnects T-SRO C-ATC/SRO 2 rcs027_02 PORV-404 Leakage T-SRO 3 480v001_04 C-BOP/SRO Loss of 12B 480V Bus/AOP-7I tg017 C-BOP/SRO 4 High Turbine Vibrations/AOP-7E Downpower R-ATC 5 cvcs014_01 C-ATC/SRO 11 Boric Acid Pump Trips EOP-0 6 swyd002 M-ALL Loss of Offsite Power/EOP-2 7 dg001_02 C-ALL 1B EDG Trips 8 dg002_02 M-ALL Station Blackout/EOP-7

(N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Scenario Overview Initial Conditions:

Unit-1 at 100% power, MOC, Unit-2 at 100% power Equipment OOS: 12 Boric Acid Pump. 0C DG.

Abnormal Conditions: None Instructions for shift: The Shift Manager has directed the crew to shift disconnects for 13 IRU to the 14B 480V Bus per OI-5B Section 6.2.

Event 1 - The crew will shift disconnects for 13 IRU to the 14B 480V Bus per OI-5B. During the evolution, the crew will enter Tech Spec 3.6.8.A with a required action to restore the Iodine Removal System train to operable status with a completion time of 7 days.

Event 2 - Leakage from PORV-404 into the Quench Tank will occur. Alarm Response Manual 1C06 actions will have crew shut the Block Valve for PORV-404 and verify the leakage has been isolated. The crew is expected to enter Tech Spec 3.4.11.A for PORV-404 being declared inoperable with a required action to close and maintain power to associated block valve with a completion time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Event 3 - After PORV-404 is isolated, a loss of 12B 480V Bus will occur. The crew will implement AOP-7I Section XV, Loss of 12B 480V Bus, which will direct their actions in protecting plant equipment and pursue tying MCCs 106 and 116.

Event 4 - The Main Turbine will begin to experience high vibrations on Bearing #4 ramping in from 6.5 mils to 11 mils over a 5 minute period. The crew will respond using AOP-7E, Main Turbine Malfunction, and will commence a reactor downpower in an attempt to lower turbine vibrations. The turbine vibrations will eventually reach trip criteria and EOP-0, Post-Trip Immediate Actions will be implemented.

Event 5 - When a rapid downpower is commenced, 11 Boric Acid Pump will immediately trip upon starting. The crew is expected to continue the downpower using one of the alternate boration steps of OP-3.

Event 6 - After the reactor trip in EOP-0, a Loss of Offsite Power will occur. The crew will verify the safety related buses are energized by their Emergency Diesel Generators and is expected to restart a Component Cooling Pump.

Event 7 - After the implementation of EOP-2, the 1B EDG will trip. The crew will pursue tying underlying MCCs and ensure proper operation of remaining equipment available.

Event 8 - Then, 8 minutes after the loss of the 1B EDG, the 1A EDG will trip causing Station Blackout conditions on Unit-1. The crew is expected to perform the Critical Task of transitioning to EOP-7, Station Blackout. When the 1A EDG is repaired, the crew will perform the Critical Task to energize 11 4KV Bus.

Page 2 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Instructor Scenario Information

_____ 1. Reset to IC-34.

_____ 2. Place simulator in RUN.

_____ 3. Place simulator in FREEZE.

_____ 4. Enter Triggers:

_____ a. 11 Boric Acid Pump HS to Start (P1C07_1HS226X_SWCLOSE) on Event 5.

_____ b. Reactor Trip - CEAs on Bottom (CEA_ROD_POSITION(1) < 5) on Event 6.

_____ 5. Enter Malfunctions:

_____ a. rcs027_02, PORV-404 Leakage from 1% to 3%, 20 second ramp, on Event 2.

_____ b. 480v001_04, Loss of 12B 480V Bus, on Event 3.

_____ c. tg017 from 6.5 to 11 in 300, Turbine Vibrations, on Event 4.

_____ d. cvcs014_01, 11 Boric Acid Pump Trips, on Event 5.

_____ e. swyd002, Loss of Offsite Power after 10 seconds, on Event 6.

_____ f. dg001_02, 1B EDG Trips, on Event 7.

_____ g. dg002_02, 1A EDG Trips, on Event 8.

_____ h. cvcs014_02, 12 Boric Acid Pump Fails, at time zero.

_____ i. dg002_01, 0C DG Start Failure, at time zero.

_____ j. afw004_01, AFAS Channel A Failure to Actuate, at time zero.

_____ k. afw004_02, AFAS Channel B Failure to Actuate, at time zero.

_____ l. dg001_01, 2A EDG Start Failure, at time zero.

_____ 6. Enter Remote Functions:

_____ a. 52-10601 to OPEN, MCC-106 Feeder Breaker, on Event 9.

_____ b. 52-10650 after 5 to CLOSED, Tie MCC-106 to MCC 116, on Event 9.

_____ c. 1-CAR-6717-MO to CLOSED, Breaker 52-11618, on Event 10.

_____ d. RESET_EMERG-J37 to RESET, Reset the 1A EDG, on Event 11.

_____ 7. Enter Panel Overrides:

_____ a. P1C07_1HS226Y to PTL at time zero.

_____ b. P1C07_F38_LTON to Off at time zero.

_____ c. P1C19C_AC1_LTON to Off at time zero.

_____ d. P1C19C_AC3_LTON to Off at time zero.

_____ e. P1C19_R06_LTON to Off at time zero.

_____ 8. Administrative:

_____ a. Place an INFO Tag on 0C DG Output Breaker HS, 0-CS-0703 in PTL.

Page 3 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020

_____ b. Place INFO Tags on 0C DG Start pushbuttons.

_____ c. Place red dots on alarm windows AC1 and AC3 on 1C19C and R06 on 1C19.

_____ d. Place a red dot on F38, 12 Boric Acid Pump, on 1C07.

_____ e. Place an INFO Tag on 12 Boric Acid handswitch in the Pull to Lock position.

_____ f. Verify CVCS integrators all read 0.

_____ g. Verify ovation screens are reset and working.

_____ 9. Independently verify correct completion of the following:

_____ a. Event Triggers correctly entered.

_____ b. Malfunctions correctly entered.

_____ c. Remote Functions correctly entered.

_____ d. Panel Overrides correctly entered.

_____ e. Administrative actions correctly performed.

_____ 10. Place simulator in RUN.

_____ 11. Ensure Schedule files and Trigger files are in RUN.

_____ 12. Ensure SBT Report is running with the SBT Insight file open.

_____ 13. Reset/Acknowledge panel and PPC alarms.

_____ 14. Ensure all PPC screens selected to Main Menu, Alarms, or SPDS Summary page.

_____ 15. Select Clock and ensure Horn On for annunciators.

_____ 16. Allow crew to pre-brief the evolution for shifting 13 IRU disconnects.

_____ 17. Brief the Crew:

Unit-1 is at 100% power, MOC.

1. Present plant conditions:

Unit-2 is at 100% power.

Reactor has been at steady state 100% power for the

2. Power history:

last 3 months.

3. Equipment out of 12 Boric Acid Pump is OOS for breaker work.

service: 0C DG is OOS for scheduled maintenance.

4. Abnormal conditions: None

5. Surveillances due: None The Shift Manager has directed the crew to shift

6. Instructions for shift: disconnects for 13 IRU to the 14B 480V Bus per OI-5B Section 6.2.

_____ 18. Allow crew 3-5 minutes to acclimate themselves with their positions.

Page 4 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020

_____ 19. Instructions for the Booth Operator:

_____ a. Event 1: Call in as WEC, request 13 IRU be shifted to the 14B 480V Bus to support EM breaker inspections.

_____ b. Event 2: Activate Event 2, rcs027_02, PORV-404 Leakage when directed by the Lead Examiner.

_____ c. Event 3: Activate Event 3, 480v001_04, Loss of 12B 480V Bus, when directed by the Lead Examiner.

_____ d. Event 4: Activate Event 4, tg017, Turbine Vibrations, when directed by the Lead Examiner.

_____ e. Event 5: Activate Event 5, cvcs014_01, 11 Boric Acid Pump Trips, when directed by the Lead Examiner.

_____ f. Verify Event 6: Loss of Offsite Power, activated on Rx Trip trigger (10 sec Delay)

_____ g. Event 7: Activate Event 7, dg001_02, 1B EDG Trips, when directed by the Lead Examiner.

_____ h. Event 8: Activate Event 8, dg002_02, 1A EDG Trips, 8 minutes after Event 7 AND when directed by the Lead Examiner.

Page 5 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Responses to Crew Requests If a request and response is not listed, delay the response until reviewed with the examiner. If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

Allow 2-3 minutes to perform requests from or to give reports to the Control Room unless otherwise specified.

REQUEST RESPONSE Event 1 - IRU Shift Acknowledge report. No further actions are

1. Notify WEC/EM 13 IRU on 14B bus.

required.

Event 2 - PORV 404 leakage

1. WEC/Maintenance - informed of Acknowledge request. No further actions are issue/status. required.

2. Radiation Protection - Quench Tank Acknowledge request. No further actions are Venting. required.

Event 3 - 12B 480V loss Acknowledge request. After 1 minute, report the feeder breaker is tripped and appears to be

1. WEC/Maintenance informed of damaged. No evidence of fire, smoke or issue/status. explosion.

Wait 5 minutes then EM reports a failure of the breaker & damaged bus work.

3 minutes later report 14B 480V Bus feeder

2. TBO investigate 14B 480V Bus.

breaker has tripped open, unknown reason.

Acknowledge, wait 1 minute then Tie 106T to 116T by initiating Event #9:

3. WEC/PPO/TBO tie MCC 106T to

FDR TO MCC 106T: 52-10601, to OPEN.

MCC-116T.

52-10650, to CLOSED.

Report MCC-106T and MCC-116T are tied with MCC-116T supplying.

Acknowledge and report. 1 minute later, Report

4. WEC/E&C/TBO/take total amp reading amp reading is 350 amps total using local (or on MCC-116T.

clamp-on) ammeter.

Acknowledge report. No further actions are

5. TBO Verify 12 Gland Exhaust Blower required.

Page 6 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Event 4 - MT Vibrations Acknowledge. Wait 1 minute and report that you

1. PPO/TBO contacted to investigate can feel vibration from bearing #4 and rumbling turbine vibration on bearing #4.

on the turbine deck.

2. WEC/System Engineer contacted for Acknowledge request. No further actions are assistance on vibration. required.

3. PPO/TBO go standby breaker 52-11618 Acknowledge request.

(Main Condenser Vacuum breaker).

If not pre-staged, Wait 2 Minutes, otherwise:

4. PPO/TBO Close Vacuum Breaker- CLOSE Main Condenser Vacuum breaker, 1-Breaker. CAR-6717-MO (52-11618 BREAKER POSITION) And Report 52-11618 breaker is closed.

Acknowledge request.

5. PPO/TBO - Standby to operate MSR Panel Loaders during downpower. Place 1-MS-4024-CV and 1-MS-4021-CV to AUTO if needed.

Acknowledge request. No further actions are

6. Chemistry - power change >15%.

required.

7. SO/TSO - U1 power reduction due to Acknowledge request. No further actions are MT vibrations. required.

Event 5 - 11 BA Pump trip

1. WEC/Maintenance - informed of Acknowledge request. No further actions are issue/status. required.

Event 6 - EOP-0 / LOOP Acknowledge request. No further actions

1. WEC - informed of issue/status.

required.

Acknowledge request. After 1 minutes override

2. WEC - Pull Alarm Cards for nuisance selected annunciator and report Alarm Card for alarms.

Window # has been pulled.

3. SO/TSO - estimate time until power is No determination yet, will let you know when restored. determination is made.

4. ABO - Verify SWGR ventilation in Acknowledge request, after 2 minutes report service per OI-22H. SWGR ventilation in service per OI-22H.

Page 7 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Event 7 - EOP-2 / DG Trips Acknowledge request. After 2 minutes, report 1B EDG tripped and appears to be a generator

1. OSO - Investigate the 1B EDG.

electrical fault, there is an acrid odder at generator end, no smoke or fire evident.

Acknowledge request. No further actions

2. WEC/EM - Investigate/repair 1B EDG.

required.

Acknowledge request, after 2 minutes report

3. TBO - Verify AFW Pp ventilation in AFW ventilation in service, Rm Temperature service.

maintaining 101°F.

Acknowledge request. After 1 minutes, report no

4. OSO - Investigate 0C EDG start failure. apparent reason 0C EDG tripped we need Maintenance/SE support to investigate.

Acknowledge request. No further actions

5. WEC/EM - Investigate/repair 0C EDG.

required.

Acknowledge. Report that the FLS has given you

6. PPO/OSO - Close 0C DG 14 4KV the key and you are in route to Close 189-1406.

Disconnect 189-1406. Wait 2 minutes, Close use Remote to 189-1406 and report 189-1406 is closed.

After 2 minutes, use remote to open breaker 252-

7. OSO - Verify 252-1106 breaker is open.

1106 and report breaker 252-1106 is open.

8. ABO - Take local control of ADVs and After 1 minute, report new position of ADVs.

position as requested. Use remotes for manual jacking open each ADV.

Wait 1 minute then call the CR and report Tying 1Y10 to 1Y09.

9. PPO/TBO tie 1Y10 to 1Y09.

Use remote function 1SY09 and select TO 1Y09 to tie 1Y10 to 1Y09. Report to CR complete.

Acknowledge direction. Wait 1 minute, use remote function 52-10401 to open MCC-104

10. PPO/ABO - Tie MCC 104 to 114.

feeder and 52-10420 to CLOSED to tie MCC-104 to MCC-114 and report Buses are tied.

Page 8 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Event 8 - EOP-7 SBO

1. ABO - Take local control of ADVs and After 1 minute, report new position of ADVs. Use position as requested. remotes for manual jacking open each ADV.

Acknowledge request. After 2 minutes override

2. WEC - Pull Alarm Cards for nuisance selected annunciator and report Alarm Card for alarms.

Window # has been pulled.

3. SO-TSO - estimate time until power is No determination yet, will let you know when restored. determination is made.

Acknowledge request. No status update at this

4. WEC/Gen Dispatch - SMECO Status.

time. No Further actions.

Report that you were outside bldg on EDG trip, 1A

5. OSO - Investigate the 1A EDG. EDG tripped due small oil leak on pressure switch.

Need Maintenance support.

Acknowledge request. Wait 1 minute, report as WEC that MM says they think they can fix the 1A

6. WEC/Maintenance Priority.

EDG in a few minutes. On Lead Cue, Remove Maintenance on 1A EDG oil pressure malfunction dg002_02, 1A EDG fault and Reset switch fitting leak.

the 1A EDG by initiating Event 11 (RESET_EMERG-J37 to RESET).

Acknowledge request. After 4 minutes shut 1-CD-

7. TBO - Shut 11 B/D HX HDR ISOL 410 using Remotes and report 1-CD-410 and 1-valves 1-CD-410 and 1-CD-411.

CD-411 are both shut.

8. ABO - Verify SWGR ventilation in Acknowledge request, after 2 minutes report service per OI-22H. SWGR ventilation in service per OI-22H.

9. TBO - Align N2 to AFW control valves and control AFW discharge Report each task complete after about 2 minutes.

pressure locally.

Page 9 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Event #1 13 IRU Shift Disconnects N-BOP/SRO, T-SRO Time Position Applicants Actions or Behavior ATC Refers to OI-5B, CTMT IRUs, Section 6.2.

ATC Places 13 IODINE FILT FAN HS 1-HS-5297 in PULL-TO-LOCK.

Places 11 BUS DISC IODINE FILT 13 keyswitch 1-HS-5297A in ATC OPEN, and removes key.

ATC May check 11 BUS green light is off above 13 IODINE FILT FAN HS.

Inserts key in 14 BUS DISC IODINE FILT 13 keyswitch 1-HS-5297B, ATC and places keyswitch in CLOSE.

Places 13 IODINE FILT FAN HS in normal, and check the following:

ATC

13 CNTMT FILT SIAS BLOCKED AUTO START alarm is clear

14 BUS green light is on above 13 IODINE FILT FAN HS Evaluates the Tech Specs and Determines Tech Spec 3.6.8.A with a SRO required action to restore the Iodine Removal System train to operable status with a completion time of 7 days.

Examiner notes:

Event concludes when IRU is on 14B 480V bus. If SROs understanding of Technical Specification applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

NOTE TO EXAMINER Cue Booth Operator to initiate Event #2, PORV Leakage when desired.

Page 10 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Event #2 PORV-404 Leakage C-ATC/SRO, T-SRO Time Position Applicants Actions or Behavior ATC Responds to Acoustic Monitor Alarm per the Alarm Manual.

Determines RCS pressure is lowering or Quench Tank parameters are ATC rising. Informs the SRO taking alternate actions for lowering pressure.

Notes elevated PRESSURIZER RV FLOW MONITOR indications for ATC both PORV-404 and RV-201.

May Shut PORV 404 Block Valve, RC-405-MOV or places PORV 404 ATC OVERRIDE, HS-1404, in Override to Close.

May monitor computer points 1T106, 1T107 and 1T108 for leak-off BOP Temperatures.

Determines:

ATC

RCS pressure is rising

Quench Tank parameters are no longer rising

PRESSURIZER RV FLOW MONITOR indications return to zero May restore Quench Tank parameters by cycling RC-401-CV per OI-ATC 1B.

Evaluates the Tech Specs and Determines Tech Spec 3.4.11.A for PORV-404 being declared inoperable with a required action to close SRO and maintain power to associated block valve with a completion time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Examiner notes:

Event concludes when PORV isolated. If SROs understanding of Technical Specification applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Event #3, 12B 480V loss, when desired.

Page 11 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Event #3 Loss of 12B 480V Bus/AOP-7I C-BOP/SRO Time Position Applicants Actions or Behavior ATC/BOP May recognize and call multiple alarms and reports to SRO.

Acknowledges U-1 480V Alarm. Verifies no trip conditions exist on BOP RPS. Notes multiple alarms and determines a loss of 12B 480V Bus.

May report that RPS is not calling for a trip. Determines and reports BOP 14B 480V Bus is deenergized.

Implements AOP-7I, Loss of 4KV, 480 Volt or 208/120 Volt SRO Instrument Bus Power.

SRO May assign AOP 7I section IV, Preliminary, to the BOP.

Determine loss of 12B 480V Bus. Verifies no indication of other bus BOP faults.

SRO May inform WEC/Maintenance of the issue.

Direct PPO/ABO to Tie MCC 106 to 116 per AOP-7I, page 100 Step BOP XV.A.3.

BOP Verifies Emergency H2 Seal Oil Pump is running.

BOP May Place Cond Min Flow Controller in Manual, 1-FIC-4438.

Determines Tech Spec LCO 3.8.9.A is applicable with a required action SRO to restore the AC subsystem to operable status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

BOP Places 11 and 12 CAR PPs in PTL and Starts 13 CAR.

BOP Verify that 12 CEDM CLG FAN is running.

BOP May direct TBO to verify that 12 Gland Exhaust Blower is running.

ATC/BOP May place Pink off normal tags of affected equipment controls.

Examiner notes:

Event concludes when MCC is Tied.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Event #4, MT Vibration, when desired.

Page 12 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 4: C-BOP/SRO, R-ATC Event #4 & 5 High Turbine Vibrations/11 BA PP Trip 5: C-ATC/SRO Time Position Applicants Actions or Behavior Responds to Turbine Vibration alarm on 1C02 per Alarm Manual.

BOP Reports Bearing #4 elevated vibrations. Recognizes alarm is valid due to adjacent Bearing trends.

Implements AOP-7E, Main Turbine Malfunction and directs a down-SRO power to lower vibration or take turbine off line.

SRO Assigns trip criteria per AOP-7I.

May inform WEC to make matrix notifications for down power SRO required for high vibration on bearing #4 and for S-SO and SE assistance.

BOP May direct the PPO/TBO investigate high vibration on bearing #4.

May Hold Mn Cond Vac breaker HS, 1-HS-6717, in Close and Direct BOP PPO/TBO to CLOSE Mn Cond Vac breaker, 52-11618, Then release HS when Breaker reported closed by field.

Directs ATC to commence down-power to lower vibration or take SRO turbine off line.

SRO/ATC May notify Chemistry of power change >15%.

Examiner notes:

Event continued next page.

Page 13 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 4: C-BOP/SRO, R-ATC Event #4 & 5 High Turbine Vibrations/11 BA PP Trip 5: C-ATC/SRO Time Position Applicants Actions or Behavior BOP May Directs PPO/TBO to standby the MSR Panel Loader for direction.

When boration in initiated, Notes 11 BA Pump Trip. May place 11 BA ATC PP HS in PTL.

Notifies SRO of 11 BA fault and continue boration with alternate ATC method per OP-3.

ATC Inserts CEAs consistent with Reactivity Placard.

SRO May Notify Bulk Power of required power reduction.

SRO May notify WEC to investigate 11 BA Pump Trip.

Recognizes trip criteria (> 10 mils for 15 minutes or reaches 12 mils BOP/ATC whichever occurs first) is met and reports to SRO.

Directs a manual reactor trip. May direct BOP to monitor MT vibrations SRO are lowing on trip or direct Cond Vacuum lowed to 24 by cycling Vacuum Breaker, HS-6717, if vibrations exceed 50 mils.

Examiner notes:

Event concludes when unit is Tripped.

NOTE TO EXAMINER Event #6, Loss of Offsite Power, will initiate automatically 10 seconds after the reactor trip.

Page 14 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Event #6 EOP-0, LOOP M-ALL Time Position Applicants Actions or Behavior Determines Reactor is tripped and Reactivity Safety Function is met.

ATC Informs the SRO that Reactivity is met.

May report monitoring turbine trip for MSR 2nd Stage MOVs going closed. Shuts MSIVs due to loss of power.

BOP

Determines Turbine Trip is met and vibrations are lowering.

Informs the SRO that Turbine Trip is complete.

Determines Vital Auxiliaries Safety Function is met. Informs the SRO that Vital Auxiliaries is complete and indications of LOOP.

BOP

Starts a Component Cooling pump.

Directs TBO to verify SWGR Ventilation operation.

Determines Pressure and Inventory Control Safety Function is met ATC and reports as complete.

Takes Alternates Actions for HR:

BOP

Initiates AFW flow to both S/Gs.

Operates ADVs to control TCOLD.

CRITICAL TASK - Establishes AFW flow to at least one S/G prior BOP to S/G levels going below (-)350 inches.

Determines and reports Core and RCS Heat Removal Safety Function BOP is not met. Informs the SRO that HR Cannot Be Met due to no RCPs.

May report ADV manual control.

Determines Containment Environment Safety Function is not met.

ATC/BOP Informs the SRO that Containment Environment Cannot Be Met due to unable to assess, loss of power effects.

Determines Radiation Levels External to Containment Safety ATC/BOP Function is not met. Reports Containment Environment Cannot Be Met, unable to assess due to loss of power effects.

Evaluates the EOP-0 flowchart and recommends the implementation SRO of EOP-2. Directs implementation of EOP-2.

Examiner notes:

Event terminates when EOP-2 is initiated.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Event #7, 1B EDG trips, when desired.

Page 15 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Event #7 EOP-2 /EDG Loss C-ALL Time Position Applicants Actions or Behavior IF 13 AFW PP in running, Ensures 11 or 12 AFW PP is operating, BOP THEN secure 13 AFW PP.

ATC/BOP If CC not Started in EOP-0, Restores CC flow per EOP-2 IV.E BOP If MSIVs are Open, Shuts MSIVs.

ATC/BOP Shuts S/G B/D valves and MS upstream drain, 1-HS-6622.

Establish RCS Heat Sink by:

ADV to Manual, positioned to control Tc, 525 to 535 F.

BOP

Stm driven AFW speed so AFW is 100PSIG > S/G Pressures.

S/G trending towards -24 to 30.

AFW Pp Rm ventilation maintaining < 130 F.

Maintains PZR level 101-180 inches:

ATC

If no letdown, Operates Chg PPs to maintain level.

Maintains RCS Subcooling 30-140 F:

ATC

Operates PZR Htrs and Spray. Resets 11 and 13 Backup Htrs

Adjust Cooldown Rate not to exceed 100 F in any one hours Respond to Alarms, Recognize loss of B train buses due to 1B EDG ATC/BOP trip.

Attempts to Start 0C DG. Reports 0C DG failed to start.

BOP

May dispatch PPO/OSO to investigate Start Failure.

SRO Prioritizes and assigns EOP-2 Block step M to tie MCC 104 to 114.

ATC/BOP Directs ABO to Ties MCC 104 to 114 per EOP-2 IV.M.1 Examiner notes:

Event concludes when Event #8, 1A EDG trips (8 minutes after 1B trip).

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Event #8, 1A EDG trips, when desired.

Page 16 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Event #8 1A EDG Trip / EOP-7, SBO M-ALL Time Position Applicants Actions or Behavior ATC/BOP Responds to Alarms and diagnosis 1A EDG trip and SBO condition.

CRITICAL TASK SRO Recognizes SFSC in EOP-2 not met and transitions to EOP-7 within 30 minutes of Station Blackout conditions.

Protects the condenser from overpressure and minimizes S/G ATC/BOP inventory loss. Shuts both MSIVs, SGBD valves, and MS upstream drains.

Establishes RCS Heat Sink:

Directs local operation of ADVs ATC/BOP

Establishes AFW flow to at least one S/G

Secures the Main Feedwater System BOP Aligns electrical system for power recovery.

CRITICAL TASK BOP Restores power to 11 or 14 4KV Bus prior to 11 or 22 DC Bus voltages going below 106V.

Examiner notes:

Scenario concludes when 11 4KV bus is restored per the Lead Evaluator.

Page 17 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 Date: Today Station: Calvert Cliffs Unit: 1 Mode: Online % Rx Power: 100 MWE: 920 Days On-Line (or Outage): 30 On-Line (or Outage) Risk Level: Green Off Normal Trends:

Production: (include activities through 0900 hrs of next non-holiday business day, start and end times with dates (if not the current day), LCO if applicable, Identifier of step 4.2.4.2 if applicable, On-Line Risk if not Green. Example of desired format is: A Isolation Condenser sensor calibration, 11/01 0700 -11/02 1500, 7 day LCO, (HT), OLR Yellow 12 Boric Acid Pump 0C DG Unit: 2 Mode: Online % Rx Power: 100 MWE: 906 Days On-Line (or Outage): 230 On-Line (or Outage) Risk Level: Green Off Normal Trends:

Production: (include activities through 0900 hrs of next non-holiday business day, start and end times with dates (if not the current day), LCO if applicable, Identifier of step 4.2.4.2 if applicable, On-Line Risk if not Green. Example of desired format is: A Isolation Condenser sensor calibration, 11/01 0700 -11/02 1500, 7 day LCO, (HT), OLR Yellow Station Event-Free Days: 691 Significant Event Reporting: (on the first business Reactivity Management Event-Free Days: 197 day following a weekend or holiday include the events Configuration Control Event-Free Days: 206 since the last business day):

Critical Component Failure Clock Days: 103 Clearance & Tagging Event-Free Days: 691 No Significant Events Station Duty Manager: Jake Smith Page 18 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 MISCELLANEOUS UNIT 1 UNIT 2 S/G Blowdown Status 100 gpm to CW 100 gpm to CW OI-8A Sect 6.7 OI-8A Sect 6.7 VCT Pressure Band 35 - 41 psig H2 33 - 39 psig H2 SPENT FUEL EQUIPMENT CHECKOUTS:

SFHM PE 0-081-01-O-Q New Fuel Elevator OI-25B App A SF Insp. Elev. OI-25B App B Last done Two Months Ago

{C93668376} 6 Months Ago 9 Months Ago PMC-18-107842 extended to semi -annually (DDD Next Year)

COMMON LONG TERM NOTES:

1. None.

SHORT TERM NOTES:

1. 0C DG is OOS for scheduled maintenance, expected return in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Page 19 of 20

Appendix D Scenario Outline Form ES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #4 OP-Test # 2020 UNIT 1 STP O-73A Quarterly Value (Rolling past 3 OI-29 Value quarters) (Date Format - MM/DD/YY) 32.9 psig 32.9 psig 32.8 11 Yesterday 3 Months 33.2 psig Yesterday Sec 6.39 Ago 6 Months Ago Max Header Pressure 30.7 psig 30.8 psig 30.7 psig 30.6 psig PE 1-12-21-O-M 12 Yesterday 3 Months Yesterday 6 Months Ago SW PUMP Sec 6.46 Ago 32.0 psig 13 (11 Hdr) 2 Weeks Ago Sec 6.39 30.2 psig 30.4 psig 29.6 psig 30.6 psig 13 (12 Hdr) Yesterday 3 Months Yesterday 6 Months Ago Sec 6.46 Ago LONG TERM NOTES:

1. None.

SHORT TERM NOTES:

1. 12 Boric Acid Pump OOS for scheduled maintenance, expected return in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Page 20 of 20

v t e Letter Sequence Draft Other
CAC:000500, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML20055D883, ML20055E009, ML20057E559, ML20057E560, ML20087G852, ML20087H514, ML20184A247, ML20184A248, ML20240A318, ML20240A322, ML20254A128, ML20254A272, ML20268A322, ML20268B437, ML20268C197, ML20274A136, ML20279A331, ML20297A306, ML20300A556, ML20301A632, ML20302A234, ML20302A235, ML20303A011, ML20303A016, ML20307A010, ML20307A019, ML20321A279, ML20322A350, ML20323A018, ML20325A031, ML20328A162, ML20329A432, ML20329A442, ML20350B716, ML20350B723, ML20350B739, ML20350B785, ML21012A270, ML21025A073, ML21025A143, ML21025A403, ML21025A405, ML21025A414, ML21040A471, ML21040A483, ML21043A207, ML21050A084, ML21050A119, ML21050A227, ML21056A220... further results
MONTHYEAR2020-03-12 [Table View]

ML20274A066

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