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Draft Operating Exam (Sections a, B, and C) (Folder 2)
	ML14304A727
Person / Time
Site:	Calvert Cliffs
Issue date:	10/21/2014
From:	Christopher Lally; Operations Branch I
To:	; Constellation Energy Nuclear Group
Shared Package
ML14079A469	List: IR 05000317/2014301; ML14092A008; ML14304A680; ML14304A721; ML14304A727; ML14307B005; ML14307B051; ML14307B072; ML14307B104; ML15043A709; ML15146A207;
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APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERA TOR EXAM JPM #: RO-ADMIN-1

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-1 Task

Title:

Ensure adequate shutdown margin exists with all CEAs operable, in Mode 3 Task Number: 201.072 KIA

Reference:

2.1.37 (4.3, 4.6)

Method of testing:

Simulated Performance: D Actual Performance: ~

Classroom: ~ Simulator: D Plant: D Read to the examinee:

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

Initial Conditions:

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

2. Today at 0800, Unit-2 experienced an uncomplicated reactor trip

3. TAvG is stable at 532°F

4. Core Bumup is 13,500 MWD/MTU on Cycle 20

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

6. RCS boron concentration is 1300 PPM per a grab sample obtained at 1100

7. POWERTRAX is currently unavailable

8. Current time, for purposes ofthis JPM, is 1130

9. 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 that shutdown margin is adequate, using the figure method, for the present plant conditions per NEOP-301. Are there any questions? You may begin.

Task Standard:

Adequate shutdown margin is verified for the stated core conditions, with all CEAs operable, in Mode 3

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

1. NEOP-301, Operator Surveillance Procedure

2. NEOP-23, Technical Data Book (U-2)

General

References:

Procedures and manuals normally available in the Control Room Time critical task:

No Validation Time:

20 minutes Simulator Setup:

None

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START:

0 Locates NEOP-301, Operator Surveillance Procedure Same as element 0 Selects NEOP-301, Operator Surveillance Procedure, Same as element Section 6.1, Shutdown Margin (All CEAs Operable)

CAUTION The allowable times to verify SDM in Step 6.1.1 are applicable for T AYG greater than or equal to 515°F with a steady or increasing soluble Boron concentration. With T AYG greater than or equal to 515°F and with steady or increasing Boron concentration, 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 must be verified prior to decreasing TA VG below 515°F or reducing Boron concentration. Initiating a cooldown to below aT AVG of 515°F or reducing soluble Boron concentration prior to verifying SDM will invalidate the times to verify SDM in Step 6.1.1 and may lead to a loss of adequate shutdown margin.

A Xenon report has yet to be provided by Reactor Engineering. The CRS wishes you to CUE proceed with verification of Shutdown Margin.

0 6.1.1 - DETERMINE the allowable time to verify Selects 6.1.1.1. based on shutdown margin by performing Step 6.1.1.1. OR information provided in Cues Step 6.1.1.2:

References the table and determines 0 6.1.1.1. - Reference the following table ... SDM must be verified within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 0 6.1.1.2.- MODEL the trip using the XENON Determines step is N/A code (or POWERTRAX).

NOTE Either of Steps 6.1.2 or 6.1.3 below may be performed to calculate the required SDM for MODE 3 with TAvG greater than or equal to 300°F.

NOTE Precautions 5.4 and 5.5 describe the differences between the various methods below which can be used to determine the required boron concentration.

0 6.1.2 - MODE 3, 4, or 5 (Figure Method) 0 6.1.2.1. - DETERMINE the required Selects 6.1.2.1.a. based on shutdown boron concentration by using one of information provided in Cues the two following methods:

Appendix C Job Performance Measure Worksheet Form ES-C-1 STANDARD Refers to Figure 2-II.A.3 ofNEOP-D. 6:~f.z.I:a~~,RE}{;ERtoFigure l-II.A.3 of

23. Determines required shutdown

NE~f-"lf(Flgu,re2-Il.A.3 ofNEOP-:23).

boron concentration is 1231 PPM 0 6.1.2.1.b.- DETERMINE using Determines step is N/A POWERTRAX.

0 6.1.2.1. - VERIFY AND DOCUMENT the following bulleted conditions on Attachment 2 Obtains copy of within the time period determined in Step Attachment 2 6.1.1. AND at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter:

Sequence number for NEOP-23, Attachment 2 is "1"

Logs Sequence #: 1 (not critical)

Logs Unit#: 2 (not critical)

Logs Cycle #: 20 (not critical)

,Logs RCS 'TA.vo!'53~;F.N"':

LogsJviode: 3: :*.* . **' J~:,

'~\~.~*~ i:)i:, ,.*

. . RCS';l'Av:o is** acceptable for current

Logs Bumup: 13,500 MWD/MTU

'*:qpera.tiilg NIQDK

Logs CEA po$itioh?*I~***i~.*~'>

b "rAsql~Bl~ ~or~p cbncentration sample

Logs boron cone: rfaoo:

frorilhhiiRc*s has been obtained.

Logs date/time~. of~~uripr'

' *-.."-,*~ - ,'\<<

at 1100 * ' '2* *

.RCS sol,!J,bl~ Boron concentration is greater.

Logs req' d boron cont.:

that1 or e'qmtlto the required Shutdown

PPM "** ,,. ,, .

Bor3n.oncentration.

Logs method used: Figure

Logs figure used: 2-II.A.3

Logs SDM valid until: tomorrow at 1130

Enters initials/date/time as preparer (date/time not critical)

TERMINATING CUE: This JPM is complete when the status of core shutdown margin has been determined and recorded. No further actions are required. The evaluator is expected to end the JPM.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: RO-ADMIN-1 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response:

Result: SAT _ _ _ _ __ UNSAT - - - - - - - - - - - - - - -

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEE'S 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 which required 21 SGFP to be secured (work still in progress).

2. Today at 0800, Unit-2 experienced an uncomplicated reactor trip

3. TAvG is stable at 532°F

4. Core Bumup is 13,500 MWD/MTU on Cycle 20

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

6. RCS boron concentration is 1300 PPM per a grab sample obtained at 1100

7. POWERTRAX is currently unavailable

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

9. 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 that shutdown margin is adequate, using the figure method, for the present plant conditions, per NEOP-301.

Are there any questions? You may begin.

Appendix C Job Performance Measure Worksheet Form ES-C-1 OPERA TOR SURVEILLANCE PROCEDURE NEOP-301 Revision 01201 Page 27 of 32 Page 1 of 1 Attachment 2, Shutdown Margin Verification Sequence # _ __

Unit - - - Cycle _ __

CEA Method figure Used or T,wG Burnup Boron Sample Date/Time Req'd Boron SDM Valid Until Preparer SRO Review MODE Position (PDIL+BIAS Attachment and (T) (MWD/MTU) (ppm)** Of Sample Cone (ppm) (Date/Time) (!nit/Date/Time) (!nit/Date/Time)

Or Figure) Sequence#

Enter IN, OUT, or PDIL. 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.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-ADMIN-2

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-2 Task

Title:

Determine Containment Closure requirements Task Number: None KIA

Reference:

103Kl.02 (3.9/4.1)

Method of testing:

Simulated Performance: 0 Actual Performance: cg]

Classroom: cg] Simulator: 0 Plant: 0 Read to the examinee:

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

Initial Conditions:

1. Unit-2 is Mode 5 Refueling Outage

a. Containment Closure is set

b. RCS is not intact

c. Time to Boil is 53 minutes

2. Component Cooling containment penetration was verified by flow through penetrations for STP 0-55A-2

3. STP 0-66D-2, Section 6.1 is scheduled for PMOT

4. You are performing the duties of the Unit-2 RO Initiating Cue:

Determine if a containment closure deviation is required for performing STP 0-66D-2 "Component Cooling Containment Isolation Valve Operability" Sect.6.1 for PMOT.

Task Standard:

Candidate correctly completes N0-114 Attachment 2

Appendix C Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

1. N0-1-114 Containment Closure

2. STP-0-66D-2 Component Cooling Containment Isolation Valve Operability

3. STP-0-55A-2 Containment Closure Verification General

References:

Procedures and manuals normally available in the control room Time critical task:

No Validation Time:

15 minutes Simulator Setup:

None

Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START: _ __

*: ',, ;"'. ,* " - . . " -*:,. *~.,., ~ ~ ;_.! ><. ***:* ,,,, '! . ?*; >~ '* '~'"

0 Revie\Vs $TP'Q-<?:6D~2S~ct. 6>l'~A, *

al1d.~et~m1i1ie#itowWil1,~~~~, * ' Same as element deviation \Vill'e CUE: CRS directs RO to complete required paperwork to pursue performing the STP 0 Locates N0-114 Containment Closure Same as element CUE:

owe will update status board when deviation sheet given to him/her for review and filing 0 5.l.D.l.- DETERMINE the requirements for tracking closure deviations.

Completing Deviation Sheets Same as element

Tracking status on tracking board

Monitor TTB

Other methods for LLRT 0 Attachment 1 "Instructions for Deviation Sheet" & Uses Att 1 to fill out Att. 2 Attachment 2 "Containment Closure Deviation Sheet" 0 1.a. Control Room 1.b. STP-0-66D-2

2. Place handswitch for 2-CC-o, 2.

3832 to open 0 3. <53 minutes May log anything <53 min 0 4. Time to Boil 4. 53 minutes

5. N/A (Restoration is from 0 5. Personnel Protective Equipment outside containment) 0 6. Work Group Designated to Restore Closure 6. Operations CUE: CRS will print and sign after form completed and given to him for review

Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded= CRITICAL STEP) STANDARD Shift - Dayshift Start Time/Date- 0600 Today Stop Time/Date - 1800 Today Shift- Nightshift Start Time/Date - 1800 Today Stop Time/Date- 0600 Today Designated Contact- U-2 CRO 0 7. Work Group Contacts to Restore Closure Print Name- Examinee Name Work Group - Ops Contact Number- x5901 Workleader Name -leave blank until submitted for review Signature - leave blank until submitted for review Work Group - Ops 0 8. RWP #for Containment Entry during a Sustained

8. N/A Loss ofSDC 9.- Leave blank until submitted for 0 9. SST, OWC SRO, or CRS Review review

10. -Leave blank until submitted 0 10 Shift Manager Approval for review

11. N/A 0 11. GS-SO Approval is required if Reduced Inventory

12. N/A 0 12. GS-SO Approval if Restricted Closure 0 13.- OWC SRO Deviation Sheet Closeout 13. N/A Penetration # - 16 Valve/Component- 2-CC-3832 STP 0-55A position- Flow/Open 0 Table on Page 4 Inside/Outside Closure - Outside Verify Position Sign and Date -

Leave Blank until performed

Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded = CRITICAL STEP) STANDARD TERMINATING CUE: This JPM is complete when the Attachment 1 is given to CRS for review and approval. No further actions are required.

I TIME STOP:---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number: RO-ADMIN-2 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT - - - - - - - UNSAT --------

Examiner's Signature and Date:

Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET Initial Conditions:

Initial Conditions:

1. Unit-2 is Mode 5 Refueling Outage

a. Containment Closure is set

b. RCS is not intact

c. Time to Boil is 53 minutes

2. Component Cooling containment penetration was verified by flow through penetrations for STP 0-55A-2

3. STP 0-66D-2, Section 6.1 is scheduled for PMOT

4. You are performing the duties ofthe Unit-2 RO Initiating Cue:

Determine if a containment closure deviation is required for performing STP 0-66D-2 "Component Cooling Containment Isolation Valve Operability" Sect.6.1 for PMOT.

APPLICANT:---

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-ADMIN-3

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: RO-ADMIN-3 Task

Title:

Apply Technical Specifications to a failed Containment Pressure Transmitter Task Number: 204.129 KJA

Reference:

2.2.42- Ability to recognize system parameters that are entry-level conditions for Technical Specifications (3.9, 4.6)

Method of testing:

Simulated Performance: 0 Actual Performance: ISJ Classroom: ISJ Simulator: D Plant: D Read to the examinee:

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

Initial Conditions:

1. Unit-1 is at 100% power.

2. The U -1 ABO reports that a scaffold builder in U-1 45 East Penetration Room has bumped pressure transmitter, 1-PT-5313A and it appears that the wires coming from the transmitter are separated.

3. The ABO also reports that he is in the process of writing a CR and he will be indicating that it does affect operability Initiating Cue:

You are directed to determine which Tech Spec LCO's apply, the LCO actions that must be taken and the completion time limits for these actions Applicable prints and the technical specifications are provided Task Standard:

Determine the TS LCO's that apply and the LCO actions that must be taken including required completion times.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. This JPM evaluates an RO's expected level ofknowledge regarding the application of Tech Specs

2. All critical steps completed (denoted by shading).

3. All sequential steps completed in order.

4. All time-critical steps completed within allotted time.

5. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

1. 60723SH0002 (OM-65-SH-2) Operations DWG Ventilation System

2. 1E-058 ESFAS Logic Diagram

3. 1E-058A ESFAS Logic Diagram

4. Technical Specifications

5. Technical Specification Basis

6. N0-1-200 Control of Shift Activities Attachment 11 General

References:

1. 60723SH0002 (OM-65-SH-2) Operations DWG Ventilation System

2. 1E-058 ESFAS Logic Diagram

3. 1E-058A ESFAS Logic Diagram

4. Technical Specifications

5. Technical Specification Basis Time critical task:

No Validation Time:

15 minutes Simulator Setup:

None

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START: _ __

0 Review prints and initial conditions. Same as element.

0 Refer to Technical Specifications Same as element Examiner Note:

None.

Determines TS LCO 3.3.1 Action A applies for RPS Trip Unit 9 (Table 3.3.1-1) & 3.3.4 ESF AS ZD Sensor Module SIAS CP (Table 3.3.4-1)

Determines that the required action is to Trip or Bypass affected RPS-Trip Unit or ESF AS-Sensor Module JJetennihes that the initial requiredc()mpletion time is 1 hourfor both channels. And to restore the Channel to Operable status or place the affected RPS Trip Unit or ESF AS Sensor in Trip within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months (the 48 hr action is not critical, only the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action)

TERMINATING CUE: This JPM is complete when applicant has determined applicable TS LCO, LCO Action required, and completion time. No further actions are required.

I TIME STOP:---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number: RO-ADMIN-3 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Q u e s t i o n : - - - - - - - - - - - - - - - - - - - - - - - - -

Applicant Response: - - - - - - - - - - - - - - - - - - - - - - - - - -

Result: SAT _ _ _ _ __ UNSAT _________

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET Initial Conditions:

4. Unit-1 is at 100% power.

5. The U-1 ABO calls in that a scaffold builder in 45 East J;>enetration Room has bumped pressure detector 1-PT-5313 A and it appears that the wires coming from the detector are separated.

6. The ABO also reports that he is in the process of writing a CR and he will be indicating that it does affect operability Initiating Cue:

You are directed to determine which Tech Spec LCO's apply, the LCO actions that must be taken and the completion time limits for these actions Applicable prints and the technical specifications are provided

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: RO-ADMIN-4

Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded+ * =CRITICAL STEP) STANDARD Job Performance Measure Facility: Calvert Cliffs 1 & 2 RO-ADMIN-4 No.:

Determine Proper Radiological Controls associated with manipulating a Task

Title:

valve in the RCA Task Number: None KIA 2.3. 7 (3 .5/3 .6)

Reference:

Method of testing:

Simulated Performance: D Actual Performance: ~

Classroom: ~ Simulator: D Plant: D Read to the examinee:

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

Initial Conditions:

1. U-1 is in Mode 5 with purification on SDC. You are an extra ABO and have been assigned to enter the RCA and verify 1-CVC-325 is shut to help locate source of slowly lowering RCS level.

2. Identify appropriate radiological controls associated with this evolution, including:

a) Protective Clothing required b) Dosimetry required c) Contaminated areas d) Highest expected dose rate.

Initiating Cue:

The CRS has directed you to verify 1-CVC-325 is shut. The CRS has estimated a total time to accomplish this work of ~5 minutes. Identify all appropriate radiological controls as listed above in preparation for a Pre-Job brief.

Task Standard:

Using correct 01 Valve Lineup, Survey Map and Correct RWP determine appropriate radiological controls.

Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded+*= CRITICAL STEP) STANDARD Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

1. Procedures and manuals normally available in the plant

2. RWP-2 Rev 2

3. Survey MAP for 5' AUX BLDG Unit-1 VCT Room General

References:

1. RWP-2 Rev 2

2. Survey MAP for 5' AUX BLDG Unit-1 VCT Room Time critical task:

No Validation Time:

10 minutes Simulator Setup:

None

Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD TIME START:

Locates appropriate survey map and determines that a contaminated 0 Reviews survey sheet for specific areas to be area must be entered located entered.

around CVC-325 but no need to enter a high radiation area Cue: Provide candidate with several RWP's including RWP# 2 Locates and selects RWP# 2-2.

Cue: Provide the candidate with several MO's including the correct MO.

0 Candidate refers to list ofMO's and selects proper Locates and selects MO MO# OPS-NO-WO After candidate identifies entry into contaminated area they should ask RP Tech for Cue: Dress Requirements respond with "Full Anti-C's due to reaching over contaminated piping" Candidate determines that Full Anti-C's are required.

Is student does not ask RP tech for input they may write "per RP tech" on answer sheet.

Candidate determines that the highest expected dose rate is between 22-40 mr/hr depending on how close they get to pipe.

Candidate determines DLR & ED are required for entry and NO other dosimetry is required TERMINATING CUE: This JPM is complete when candidate has identified all radiological controls listed above for entering the RCA. evaluator will terminate this JPM.

Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded + * = CRITICAL STEP) STANDARD I TIME STOP:---

NOTE TO EXAMINER: Collect the applicant work sheet at the completion of the JPM

Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number: RO-ADMIN-4 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ __

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET Initial Conditions:

3. U-1 is in Mode 5 with purification on SDC. You are an extra ABO and have been assigned to enter the RCA and verify 1-CVC-325 is shut to help locate source of slowly lowering RCS level.

4. Identify appropriate radiological controls associated with this evolution, including:

e) Protective Clothing required f) Dosimetry required g) Contaminated areas h) Highest expected dose rate.

Initiating Cue:

The CRS has directed you to verify 1-CVC-325 is shut. The CRS has estimated a total time to accomplish this work of ~5 minutes. Identify all appropriate radiological controls as listed above in preparation for a Pre-Job brief.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Applicants Work Sheet Identify appropriate radiological controls associated with this evolution, including:

a. Appropriate R WP and Workorder#

b. Protective Clothing required

c. Dosimetry required

d. Contaminated areas

e. Highest expected dose rates

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-1

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-1 Task

Title:

Ensure adequate shutdown margin exists with all CEAs operable, in Mode 3 Task Number: 201.072 KIA

Reference:

2.1.37 (4.3, 4.6)

Method of testing:

Simulated Performance: 0 Actual Performance: IS]

Classroom: IS] Simulator: 0 Plant: 0 Read to the examinee:

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

Initial Conditions:

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. Core Bumup is 13,500 MWD/MTU

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

6. RCS boron concentration is 1210 PPM per a grab sample obtained at 1430

7. POWERTRAX is currently unavailable

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

9. You are performing the duties of an extra SRO Initiating Cue:

BOP-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.

Task Standard:

Candidate correctly determines Shutdown Margin Exists with the Plant in Mode 3

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

NEOP-301, Operator Surveillance Procedure NEOP-23, Technical Data Book (U-2)

General

References:

Procedures and manuals normally available in the Control Room Time critical task:

No Validation Time:

20 minutes Simulator Setup:

None

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded = CRITICAL STEP) STANDARD TIME START: _ __

0 Locates NEOP-301, Operator Surveillance Procedure Same as element and proceeds to Step 6.1.2.3.

Same as element (using NEOP-301, 0 6.1.2.3. -Independently verify the information in Operator Surveillance Procedure Attachment 2 and NEOP-23, Technical Data Book (U-2)

Notes RCS TAVG, Mode, Bumup, CEA position, Boron Sample information, Method and Figure used are entered correctly (not critical)

Refers to Figure 2-II.A.3 ofNEOP-

23. Determines required shutdown boron concentration is 1231 PPM.

Notes required boron concentration listed on Att. 2 is in error (value for Mode 5 was used).

',;)*: ~~/: '?>',, ::~ i>: *:~:'~ ':~;. ,,, .,. ' *:~> ' :* ' ' < ' ,.' ' .

,Qc,o...... ;JFilie"RCS,~oluble Boron concentration is,

,~ *,l~§ ~~* tb~* fe~rilit~d ;snutdown:aorun concentration Directs boration at greater than or

. 'f<>~ th~'~\lrt~~i;,i>~fh\Jl),,'FHEN IMMEDIATELY , equal to 40 gpm of borated water at

. S];~T+.~PJ:ation.atgre~tef tllan orequal to :7l0 gpm of or above required Shutdown Boron

. :~oiate~ y\rater~(:or 'a~ove required Shutdown Boron Concentration

uon¢el1traJion.: *. * *

TERMINATING CUE: This JPM is complete when the status of core shutdown margin has been determined and boration of the RCS directed. No further actions are required. The evaluator is expected to end the JPM.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SRO-ADMIN-1 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: -------------------------------

Time to Complete:

Follow up Question: -----------------------------------------------

Applicant Response: ----------------------------------------------

Result: SAT - - - - - - - - - UNSAT ______________

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet EXAMINEE'S 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. Core Burnup is 13,500 MWD/MTU

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

6. RCS boron concentration is 1210 PPM per a grab sample obtained at 1430

7. POWERTRAX is currently unavailable

8. Current time, for purposes ofthis JPM, is 1500

9. You are performing the duties of an extra SRO Initiating Cue:

EOP-Attachment 13 requires a shutdown margin calculation be perfonned. 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 per NEOP-301, starting at Step 6.1.2.3.

Are there any questions? You may begin.

Appendix C Job Performance Measure Worksheet Form ES-C-1 OPERA TOR SURVEILLANCE PROCEDURE NEOP-301 Revision 0120 1 Page 27 of32 Page 1 of 1 Attachment 2, Shutdown Margin Verification Sequence # _ _..:..__

Unit - - Cycle __2Q Method Figure Used or TA\'(i Burn up *CEA Boron Sample Date/Time Req'd Boron SDM Valid Until Preparer SRO Review MODE (PDIL+BIAS Attachment and (F) (MWD/MTU) Position (ppm)** Of Sample Cone (ppm) (Date/Time) (!nit/Date/Time) (!nit/Date/Time)

Or Figure) Sequence#

532 3 13,500 IN 1210 Today@

1180 Figure 2JLA.3 Tomorrow@ D:JL 1430 1450 today@ 1450

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

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

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-2

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-2 Task

Title:

Ability to implement plant procedures for a Condenser Tube Leak Task Number: 202.008 KIA

Reference:

2.1.34 (2.7, 3.5)

Method of testing:

Simulated Performance: 0 Actual Performance: [Zl Classroom: [Zl Simulator: 0 Plant: 0 Read to the examinee:

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

Initial Conditions:

1) Unit-1 is at 88% reactor power.

2) At 0015, 12A Waterbox was secured lAW AOP-10, Abnormal Secondary Chemistry Conditions, due to a condenser tube leak.

a. Condensate Demineralizers are in service with full flow

b. Condenser High Level Dump is manually isolated

c. S/G Blowdown flow has been maximized

3) At 0045, exceeded Action Level 2 values for sodium in the Steam Generators, 52 ppb in 11 S/G & 55 ppb in 12 S/G.

4) At 1800, Chemistry notifies the Control Room we are still exceeding Action Level 2 values that sodium levels are lowering slowly. Chemistry anticipates exiting Action Level 2 at 0330

5) You are performing the duties of an extra SRO.

Initiating Cue:

The Shift Manager directs you to perform AOP-1 0,Section VI. (Please verbalize progress thru the AOP with the evaluator.)

Task Standard:

This JPM is complete when it is determined a reactor trip is required. No further actions are required. The evaluator is expected to end the JPM.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

AOP-1 0, Abnormal Secondary Chemistry Conditions.

CP-217, Specifications and Surveillance- Secondary Chemistry General

References:

Procedures and manuals normally available in the Control Room Time critical task:

No Validation Time:

15 minutes Simulator Setup:

None

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START:

0 Locates AOP-1 0,Section VI Same as element.

0 VI.A.- Determine If A Reactor Trip Is Required.

0 VI.A.1. -IF Feedwater Sodium is greater than 200 ppb AND Condensate Sodium is greater than 200 ppb, THEN perform the following:

0 VI.A.1.a. - Trip the Reactor Reviews step against information 0 VI.A.1.b. -Perform the Reactivity control provided on the cue sheet.

portion ofEOP-0. Determines no actions are required 0 VI.A.1.c. - Initiate Auxiliary Feed. at this time 0 VI.A.1.d. - Trip BOTH SGFPs 0 VI.A.1.e. - IMPLEMENT the remainder of EOP-0 CUE: I The CRS is directing the Crew in the performance of AOP-1 0,Section VI.B 0 VI.B. - Determine required plant conditions.

0 VI. C.- Actions with power greater than or equal to 50%

NOTE:

If SG chemistry levels are reduced below the Action Level 3 value, before or during the power reduction, power level is still required to be reduced below 5%.

0 VI.C.1. - IF Plant Chemistry determines SG Chemistry is in Action Level 3, as a result of a Condenser tube leak, THEN commence an orderly Determines step is N/ A at this time plant shutdown to be less than 5% power as quickly as safe operation permits PER OP-3 and OP-4.

0 VI.C.2.- IF Plant Chemistry determines that SG Chemistry is in Action Level 2, as a result of a Determines step is applicable Condenser tube leak, THEN perform the following actions:

0 VI.C.2.a. -Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initiating Action Level 2, reduce power to less than Determines power must be reduced 50% PER OP-3, NORMAL POWER to less than 50% by 0045 OPERATION.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD 0 VI.C.2.b. - WHEN the following conditions exist:

The source ofthe impurity ingress is controlled Determines step is N/A at this time

SG Chemistry is less than the value for Action Level 2 THEN the power reduction may be terminated and power stabilized.

0 VI.C.2.c. -IF the SG chemistry level has NOT been reduced to less than Action Level 1 within 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months of entering Action Level 2 THEN consider the SG Chemistry level to be Determines step is N/A at this time in Action Level 3, AND commence an orderly plant shutdown to be less than 5% power as quickly as safe operation permits PER OP-3 and OP-4.

CUE: 12A Waterbox is secured for leak location/repair 0 VI.C.3. -Attempt to locate and repair the tube Determines actions already in leak. progress per Evaluator CUE NOTE TO EVALUATOR: Candidate will have to refer back to Step VI.C.l. to determine actions required based on data provided in the following CUE CUE: Chemistry reports S/G sodium has exceeded Action Level 3 values

-- '~. > ',< .i'" '*,,, :.~~ ': > '\ y D; YLC:~:t:IE Rlant:qhemistry determines SG Chemistry

,* ' ;.is'i'n Actfdn'tevei'3:, .as a result of a Condenser tube

. ; ~~~li:/f:lJFJN':~ornll1tm.ce an ()rcterty plant shutdown to*

Determines a plant shutdown to <5%

power is required.

.

be::~e~s:than'5~ power as quickly as safe operation permitS P]tR OP-3 and OP-4.

NOTE TO EVALUATOR: Candidate will have to refer back to Step VI.A.l. to determine if a Reactor Trip is required based on data provided in the following CUE CUE* Chemistry reports Condensate and Feedwater Sodium levels are 210 ppb and rising

rapidly. The source appears to be 13B Waterbox.

0 VI.A. - Determine If A Reactor Trip Is Required.

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

~, tJ :;V,I~A.l., t IFF'e.~<hvater S(Jdium is greater than

'> ;20l> ppb 1\.N~ Col1densate:S,odiuto is greater than

~06 Pt\b~ ~TJJ~N.peffonh the*follqwing:

,., ;,.*' if,-. - ,.*' - *.* ;~ : ' > ~ ' " *: ,; '

*: ,Q;, Y*I:A.ta. ;. 'fiiRthe Reacttir . ** . . * . .. *. . .

Determines reactor trip is required

\!'!!! ~.J:;~~~~'&rtt.,me'~tiv,\ty, ~ntrol using values for Condensate and Feedwater Sodium levels provided

- ... **;Q~.VI;A.l.c.~Iili,tiate;Auxiliary*Feed; by Evaluator CUE

~D;:Q:*&tA.l.d...,,frip:~QTi,JSQFPs, . *. *

- - fiJ
    
    *\(LAJ:e..; IMPLEMENTtheremainderof

. .*'~ '£o~..:o'. *** *! :. ** ** **% ,..*.* * **

TERMINATING CUE: This JPM is complete when it is detennined a reactor trip is required.

No further actions are required. The evaluator is expected to end the JPM.

I TIME STOP: - - -

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SRO-ADMIN-2 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Q u e s t i o n : - - - - - - - - - - - - - - - - - - - - - - - - -

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT ______________

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEE'S CUE SHEET Initial Conditions:

1) Unit-1 is at 88% reactor power.

2) At 0015, 12A Waterbox was secured lAW AOP-10, Abnormal Secondary Chemistry Conditions, due to a condenser tube leak.

a. Condensate and Feed sodium levels are 50 ppb and 45 ppb respectively

b. Condensate Demineralizers are in service with full flow

c. Condenser High Level Dump is manually isolated

d. S/G Blowdown flow has been maximized

3) At 0045, exceeded Action Level 2 values for sodium in the Steam Generators, 52 ppb in 11 S/G & 55 ppb in 12 S/G.

4) At 0755, Chemistry notifies the Control Room we are still exceeding Action Level 2 values, and sodium levels are lowering slowly. Chemistry anticipates exiting Action Level 2 at 0330 tomorrow.

5) You are performing the duties of an extra SRO.

Initiating Cue:

The Shift Manager directs you to perform AOP-1 0,Section VI. (Please verbalize progress thru the AOP with the evaluator.)

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-3

Appendix C Job Performance Measure Form ES-C-1 Worksheet Job Performance Measure Facility: Calvert Cliffs 1 & 2 SRO-ADMIN-3 No.:

Task

Title:

Apply Technical Specifications to a relay failure Task Number: 204.129 KIA 2.2.42 - Ability to recognize system parameters that are entry-level

Reference:

conditions for Technical Specifications (3.9, 4.6)

Method of testing:

Simulated Performance: D Actual Performance:~

Classroom: ~ Simulator: D Plant: D Read to the examinee:

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

Initial Conditions:

1. Unit-1 is at 100% power.

2. An IM Technician performed a visual inspection of ESF AS ZA Actuation Relay Cabinet.

The technician reports that two SIAS AS power relays are discolored and show signs of deformation possibly due to excessive temperature. These relays CANNOT be considered operable.

3. The affected relays are as follows:

SIAS AS Relay at B5 (11 LPSI)

SIAS A8 Relay at B8 (11 & 12 CAC Fans)

Initiating Cue:

You are directed to determine which Tech Spec LCO's apply, the LCO actions that must be taken and the completion time limits for these actions Applicable prints and the technical specifications are provided Task Standard:

Determine the TS LCO's that apply and the LCO actions that must be taken including required completion times.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

1. 1E-076 Sheet 1, LPSI Pump 11.

2. lE-076 Sheet 11 C Containment Cooling Fan 11

3. lE-076 Sheet 11D Containment Cooling Fan 12

4. 1E-058 ESFAS Logic Diagram

5. 1E-058A ESFAS Logic Diagram

6. Technical Specifications

7. Technical Specification Basis General

References:

1. 1E-076 Sheet 1, LPSI Pump 11.

2. 1E-076 Sheet 11 C Containment Cooling Fan 11

3. 1E-076 Sheet 11D Containment Cooling Fan 12

4. 1E-058 ESFAS Logic Diagram

5. 1E-058A ESFAS Logic Diagram

6. Technical Specifications

7. Technical Specification Basis Time critical task:

No Validation Time:

15 minutes Simulator Setup:

None

Appendix C Job Performance Measure Form ES-C-1 Worksheet ELEMENT (shaded+*= CRITICAL STEP) STANDARD TIME START: _ __

0 Review prints and initial conditions. Same as element.

0 Refer to Technical Specifications Same as element Examiner Note:

Applicant may enter TS LCO's 3.5.2 & 3.6.6 for inoperable components. This action is not necessarily required but may be entered as a conservative application of the Technical Specifications.

Determines TS LCO 3.3.5 Action C applies for loss of Function l.b (SIAS Actuation Logic) in Table 3.3.5-1 Determines that required action is to restore affected Actuation Logic channel(SIAS Channel A) to Operable status Determines that required completion time is 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months TERMINATING CUE: This JPM is complete when applicant has determined applicable TS LCO, LCO Action required, and completion time. No further actions are required.

I TIME STOP:---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number: SRO-ADMIN-3 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: - - - - - - - - - - - - - - - - - - - - - - - - -

Result: SAT - - - - - - - UNSAT _ _ _ _ _ _ __

Examiner's Signature and Date:

Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET Initial Conditions:

1. Unit-1 is at 100% power.

2. An IM Technician performed a visual inspection of ESF AS ZA Actuation Relay Cabinet.

The technician reports that two SIAS A8 power relys are discolored and show signs of deformation possibly due to excessive temperature. These relays CANNOT be considered operable.

3. The affected relays are as follows:

SIAS A8 Relay at B5 (11 LPSI)

SIAS A8 Relay at B8 (11 & 12 CAC Fans)

Initiating Cue:

You are directed to determine which Tech Spec LCO's apply, the LCO actions that must be taken and the completion time limits for these actions Applicable prints and the technical specifications are provided

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-4

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-4 Task

Title:

Approve a Liquid Waste Discharge Permit Task Number: 064.040 KIA

Reference:

2.3.6 (2.0, 3.8)

Method of testing:

Simulated Performance: 0 Actual Performance: kSI Classroom: kSI Simulator: D Plant: 0 Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Unit-1 is in Mode 3 with 11A and 13B Waterboxes removed from service for cleaning

2. Unit-2 is at 88% power with 21A Waterbox removed from service for cleaning

3. 12 RCWMT discharge has been risk assessed and is on the schedule for today.

4. You are performing the duties of the CRS.

Initiating Cue:

The Shift Chemistry Technician has delivered a permit for the discharge of 12 RCWMT for your review and approval. If necessary, identify any issues associated with the planned discharge.

Task Standard:

This JPM is complete when the candidate rejects the permit because the required numbers of Circulating Water Pumps are not operating and RMS values are inconsistent. No further actions are required.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

Procedures and manuals normally available in the plant General

References:

CP-601, Liquid Radioactive Waste Release Permit Time Critical Task:

No Validation Time:

20 minutes Simulator Setup:

None

Appendix C Job Performance Measure Worksheet Fonn ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START:

CUE: Provide the candidate the prepared copy of CP-601, Attachment 2 (12 RCWMT Discharge Permit) 0 Release Criteria is understood: Same as element.

0 Discharge Point Determines Unit 1 is checked.

0 Min# Circ Water Pumps Required Determines 5 CW Pps are required Determines 1,000,000 GPM is 0 Dilution Flow Rate Pre-Release: consistent with 5 CW Pps running 0 Maximum Release Flow Rate: 120 GPM 0 RMS Number: 0-RE-2201 CUE: If checked, RMS reads as stated on permit.

Checks RMS reading for 0 RMS

Background:

agreement with permit value Notes value is above RMS 0 Expected RMS Reading: background

_x F ¥ L Notes that Adjustable Setpoint is

'-,. i .--- **>~;; > * "- lower than Expected Reading Note to Evaluator: Candidate may determine permit criteria not met when reviewing Min# of Circ Water Pumps required.

' ' '>- 1 - - - ,. *. * .. ,. l, ' ** . .!* *' :.:

-. 0 :; I,{~quired plant configuration :for coridl1~tfn~rglea$e; Determines Unit 1 has only 4 CW Pps running and does not meet has bee11 'established * ' '1 * .~ " ; * -

*' :! * *, :, *!' *, *. permit conditions

.. Informs Chemistry Tech of 0*, Chemistry Tech discussed permitwit&*s~o;sM.:~ '* mistakes found on permit and does

- .-*. - ' ' '* " .. (*' : ' : not approve permit.

Terminating Cue: This JPM is complete when the candidate rejects the permit because the required numbers of Circulating Water Pumps are not operating and RMS values are inconsistent. No further actions are required. The evaluator is expected to end the JPM.

I Time Stop:

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SRO-ADMIN-4 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Q u e s t i o n : - - - - - - - - - - - - - - - - - - - - - - - - -

Applicant R e s p o n s e : - - - - - - - - - - - - - - - - - - - - - - - - -

Result: SAT ------- UNSAT --------

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 APPLICANT'S CUE SHEET Initial Conditions:

1. Unit-1 is in Mode 3 with llA and 13B Waterboxes removed from service for cleaning

2. Unit-2 is at 88% power with 21A Waterbox removed from service for cleaning

3. You are performing the duties of the CRS.

Initiating Cue:

The Shift Chemistry Technician has delivered a permit for the discharge of 12 RCWMT for your review and approval. If necessary, identify any issues associated with the planned discharge.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SRO-ADMIN-5

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SRO-ADMIN-5 Task

Title:

Determine Appropriate Emergency Response Actions Task Number: 204.097 KJA

Reference:

2.4.41 (2.9, 4.6)

Method of testing:

Simulated Performance: D Actual Performance: ~

Classroom:~ Simulator: D Plant: D Read to the examinee:

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

Initial Conditions:

1. Unit-~ L was at 100% power when an electrical fault occurred on 14 4KV bus occurred.

2. A reactor trip was manually initiated by de-energizing 480VAC busses when TM/LP trip setpoints reached.

3. EOP-8 was implemented due to multiple events in progress (steam leak and LOCA in containment).

4. CSAS A cannot be verified due to failure of 11 CS pump

5. RI-5317 A & B Containment High Range Rad Monitors are currently reading ~4000 R/hr

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

7. This JPM is TIME CRITICAL.

Initiating Cue:

You have been requested to determine appropriate Emergency Response Actions, per the ERPIP, based on the current plant conditions provided.

Task Standard:

Determines EAL classification, Protective Action Recommendations and completes the initial notification form within prescribed time limits.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within required time (TIME CRITICAL).

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

1. Shift Manager ERPIP Book

-h2.EAL- Hot Chart

&.3.EP-ChLst-MCR01 ~Shift Manager Checklist:

JA,CNG-EP-1.01-1019 ~Shift Emergency Operations" 4SA blank copy ofERPIP 3.0, Attachment 3, "INITIAL NOTIFICATION FORMCNG-EP-

1. 01-1 013 "Emergency Classification and PAR'"'

5,6.ERPIP 3.0 Attachment 4, "GENERAL EMERGENCYACTIONSEP-Form-ALL12 "Onsite Protective Measures Flowchart" L__ERPIP 3.0 Attachment 5, "GENERAL EMERGENCY PROTECTIVE ACTION RECOMMENDATIONSEP-Form-ALL36 "Emergency PA Announcements" 6,8.EP-Fprm-ALL21 "CCNPP ERONS Notification Details" General

References:

Procedures and manuals normally available in the Control Room Time critical task:

Yes Validation Time:

12 minutes Simulator Setup:

None

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded = CRITICAL STEP) STANDARD EVALUATOR NOTE:

The "EAL CLOCK" starts a(ter candidate reads "Initial Conditions" CUE sheet.

TIME START:

EAL CLOCK TIME START:

0 Identify and locate Shift Manager Checklist Same as element 0 1.1 - Entry into the Emergency Plan 0 1.1.1 -Implement Checklist per CNG-EP-1.01-1019 0 1.1.2- Print your name and today's date Same as element 0 1.1.3 - Call or direct an available individual to call the Shift Communicator and Dose Assessor to the Same as element Control Room 0 1.2 - Emergency Classification and PAR and Notifications NOTE: Emergency Classification and declaration shall be completed as soon as possible but no later than 15 minutes from the time indications an EAL threshold being met or exceeded are available in the Control Room 0 1.2.1 - If entry is due to a security event, THEN perform the appropriate actions in the station Determines step is N/A specific procedure in parallel with completing this checklist 0 1.2.2 - Classify the events in progress using CNG-Reference Tab 3, EAL Wall Chart EP-1.01-1013, Emergency Classification and PAR 0 Identify Tab 3 CNG-EP-1.01-1013 0 5.3 - Emergency Classification and Declaration 0 5.3.A- An emergency condition must be assessed, classified, and declared within 15 minutes of the Same as element availability of indications that an EAL has been exceeded 0 5.3.B- Assess and classify abnormal conditions

Appendix C Job Performance Measure Worksheet Form ES-C-1 STANDARD Evaluates EAL HOT CHART and determines a GENERAL EMERGENCY classification is warranted, under EAL F.G.l.l, in

. . .* ,; ""* <' <:;.:. the Fission Product Barrier 0 5.3;Rl - DetermiiJ.iilg *

h Category, based on the loss of all 3

.the.EAL matrbchiiv~. fission product barriers.

' \, c ; .; ' - * ~i; <:.*: :~<:~

0 .. 53:B2 -Classif-ying Fuel Clad Barrier-Containment eniergency*cl~sitic~. Radiation reading> 3500 rern/hr

being metor ex&~edW~)¥

-., <Y ~ *;&~g RCS Barrier- Containment Radiation reading > 6 rem/hr Containment Barrier->4.25psig with less than minimum cooling (2 CAC's, zero CS pumps)

CUE: When a Peer Check of the EAL call is requested, acknowledge the request.

0 Checklist 1.2.2.A- IF time permits, THEN validate the emergency classification with the STA (peer check), if Requests Peer Check from STA available.

0 1.2.2.B- Declare the event by announcing the following:

"I am declaring an (EAL) at (time) Fills out checklist due to (brief reason) and assuming the role as Time < 15 minutesTime < 15 Emergency Director minutes D EAL ClockTime.. Stop'~< . *.):n:dnus EAL Clock Time Starft.'S' .*'* ~~~* j ~. * . . miltutes CUE: DIR 10 = 265°, DIR 60 = 272° 0 1.2.3 - Determine if protective actions for onsite Implement OCA Evacuation and personnel are necessary using EP-FORM-ALL 12, Accountability based on GE and Onsite Protective Measures Flowchart safe to evacuate personnel CUE: Inform candidate the Unit-1 CRS will implement P A announcements as necessary 0 1.2.4 - Announce, or direct P A announcements, for Directs U-2 CRS to perform station personnel as necessary announcements

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD 0 1.2.5 Determine the appropriate PAR per CNG-EP-Reference TAB 3 1.01-1013, Emergency Classification and PAR Reference Attachment 2 for CCNPP 0 Att 2 Step 1.A If a controlled release ..... . Determines step is N/A 0 Att 2 Step 1.B IF the criteria of item A above are NOT met, THEN select appropriate PAR as follows:

0 0 Same as Element 0 SM Checklist 1.3 Notifications for Change in Classification or PAR 0 1.3 .1 IF the ERO has NOT been activated, THEN notify the ERO as follows: Determines step is Applicable and 0 1.3 .LA Complete station specific ERONS Notification references Tab 6 Details Form 0 Tab 6 EP-FORM-ALL21 0 Event Drill 0 General Emergency StaffNormal Emergency 0

Facilities for Emergency Enters time event determination 0

made 0 Message Approval Signs name and enters current time 0 SM Checklist 1.3.1.B (NMP ONLY) .... Determines step is N/ A 0 1.3.1.C Provide completed ERONS form to Shift Gives form to Communicator Communicator AND direct them to notify ERO

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD 0 1.3.1.D IF no one is available ..... Determines step is N/A NOTE: Notification to the state and local are required within 15 minutes ofthe Emergency Declaration or a change in PAR 0 1.3.2.A- Complete station specific initial notification References Tab 8 form EP-FORM-ALL23 0 Complete Item A.1. Checks "is" a drill 0 Checks "Unit~!"

0 Checks "General Emergency" CJ Enters "F.G.l.l" CJ Checks "Yes" 0 Complete Item A.5.a Checks "Yes" 0 Complete Item A.5.b Checks "Airborne" Checks box for "A.6.c", "Evacuate

'

PAZ 1 unless conditions make CJ evacuation dangerous, notify the public in PAZ 1 to take KI, shelter remainder of the 10 mile EPZ."

Time entered is time GE declared CJ not current time. Date is current date.

0 Complete ED name & signature Same as element 0 SM Checklist 1.3.2.A.1 (GNP Only) ..... . Determines step is N/ A CUE: When a Peer Check of the EAL call is requested, acknowledge the request.

0 1.3.2.B- IF time permits, THEN obtain a peer check of Same as element completed form information 0 1.3.2.C- Provide completed form to the Shift Same as element Communicator AND direct them to notify State and Local Time S 15 minutes

Appendix C Job Performance Measure Worksheet Form ES-C-1 STANDARD Q EAL Form'*o Couufi

t~;i .;; .~ .. ):~.b!]*~: . .

EAL '~.Io~k_ !fifu~;Stop:,,. ' >,, *;.~

' '): >~< > ~<.< "* ., minutes

>;;, ';i, 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.

I TIME STOP: - - -

Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number: SRO-ADMIN-5 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Follow up Question:

Applicant Response:

Result: D SAT D UNSA T Examiner's Signature and Date:

Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANT'S CUE SHEET Initial Conditions:

1. Unit-;!--l_was at 100% power when an electrical fault occurred on 14 4KV bus occurred.

2. A reactor trip was manually initiated by de-energizing 480V AC busses when TM/LP pre-trip setpoints reached.

3. EOP-8 was implemented due to multiple events in progress (steam leak and LOCA in containment).

4. CSAS A cannot be verified due to failure of 11 CS pump

5. RI-5317 A & B Containment High Range Rad Monitors are currently reading

4000 R/hr

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

7. This JPM is TIME CRITICAL.

Initiating Cue:

You have been requested to implement Emergency Response Actions, per the ERPIP, based on the current plant conditions provided.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-1 (Alt Path)

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-1 (Alt Path)

Task

Title:

Evaluates Operator's ability to align a LPSI Pp for Core Flush via Hot Leg Injection Task Number: 201.058 KIA

Reference:

005.A4.01 (3.6, 3.4), 011.EA1.11 (4.2, 4.2)

Method of testing:

Simulated Performance: D Actual Performance: ~

Classroom: D Simulator: ~ Plant: D Read to the examinee:

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

Initial Conditions:

1. A Loss of Coolant Accident (LOCA) has occurred on Unit-1.

2. SIAS actuated 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ago.

3. RCS pressure~ 20 PSIA with CETs indicating~ 230° F

4. Containment pressure is~ 5 PSIG.

5. Core flush, using 11 HPSI Pp for Pressurizer Injection via the Charging Header, is aligned thru EOP-5, Step IV.AE.l.h.(4). Current Charging header flow, on 1-FIA-212, indicates 100 GPM.

6. You are performing the duties ofthe Unit-1 CRO.

Initiating Cue:

The CRS directs you to continue with the procedure, beginning at Step IV.AE.l.h.(5) of EOP-5-1.

Task Standard:

Establishes Core Flush, via Hot Leg Injection, using 11 Low Pressure Safety Injection Pump

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

EOP-5, Loss of Coolant Accident (Unit-1)

General

References:

Procedures and manuals normally available in the Control Room Time critical task:

No Validation Time:

25 minutes

Appendix C Job Performance Measure Worksheet Form ES-C-1 Simulator Setup:

1. Reset to IC-24 with both units at 100%

2. Place simulator in RUN.

3. Insert following Malfunctions/Remote Functions:

a. RCS Cold Leg 12B Rupture: rcs001 at 100% at time zero

b. 1-SI-651-MOV Bkr: 1-SI-651-MOV to CLOSED, with a 15 second delay, on Event 1

c. 1-SI-652-MOV Bkr: 1-SI-652-MOV to CLOSED, with a 45 second delay, on Event 1

4. Perform applicable EOP Block steps thru Step R, Prepare for RAS.

5. WHEN RAS actuates, perform StepS, Verify RAS Actuation; Step AD, Perform LOW Temperature Actions; and Step AE.1, Commence Core Flush using Pressurizer Injection.

6. IF required, insert Override P1C07_1FIA212_MT (1-FIA-212 CHRG FLOW MT) to a final value of 100 GPM with no ramp time

7. Place 11 & 12 LPSI Pump Handswitches in PTL.

8. Place simulator in FREEZE.

9. Obtain an Independent Verification for steps 3, 4, 5, and 6.

10. Acknowledge all panel alarms and plant computer alarms and ensure "Horn On" for annunciators.

11. Select "Clock" time.

12. WHEN cued by evaluator, go to RUN.

13. WHEN cued by evaluator, activate Event 1.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded =CRITICAL STEP) STANDARD TIME START:

EXAMINER's NOTE Once applicant has located the correct section of the EOP, provide them with a working copy of the procedure section.

Locates EOP-5-1, Step IV.AE.l.h.(5)

CUE: I Charging Header flow indicates 100 GPM Determines step is D IV.AE.l.h.(5)- IF approximately 150 GPM is NOT Applicable. Proceeds to indicated THEN initiate Hot Leg Injection.

Step IV .AE.1.1 BEGIN ALTERN ATE ACTIONS D IV .AE.1.1 - IF Pressurizer Injection is NOT adequate AND the following conditions are met:

D RCS pressure is less than 270 PSIA {245}

Determines step is D RCS pressure minus containment pressure is less than 75 APPLICABLE.

PSID D HPSI PP(s) are available THEN line up for Hot Leg Injection as follows:

CUE: I The CRS desires that 11 LPSI Pump be used for Hot Leg Injection D IV.AE.Ll.a.- Placethe;selected LPSIPJ? RAS ;:j{';,' ;/

Same as element OVERRIDE switch in OVERRIDE.

~

D IV.AE.l.l.b.- Verify the CNTMT SUMP DISCH valves are open:

0 1-SI-4144-MOV Same as element 0 1-SI-4145-MOV D IV.AE.Ll.c.- Open SDCRECIRC ISOL.valve, 1-SJ,.399-.

Same as element MOV. ;C' D IV.AE.l.l.d.- Shut LPSI HDR valves:

0 1-SI-615-MOV 0 1-SI-625-MOV Same as element 0 1-SI-635-MOV 0 1-SI-645-MOV Acknowledge, as ABO, and activate Event 1 to close the breakers for 1-SI-651-MOV CUE:

(52-11466) and 1-Sl-652-MOV (52-10424) and report completed.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded = CRITICAL STEP) STANDARD 0 IV .AE.1.l.e. - Close the power supply breaker to the SDC HDR RETURN ISOL valves: Contacts ABO to shut D 1-SI-651-MOV breaker, 52-11466 associated breakers 0 1-SI-652-MOV breaker, 52-10424 Evaluator NOTE:

Operator must hold handswitch in OPEN for each valve OR valve will stop moving.

tl tv~AEJ J :f.,_ OpenSDC HDR.

Q ,,f.:*Sl-'651-MOV Same as element

, , 0' 1.-S}--652-MOV Starts 11 LPSI PP per previous CUE.

Verifies from LPSI HDR flow indication, on 1-FIC-306, that adequate flow exists.

END ALTERNATE ACTIONS TERMINATING CUE: This JPM is complete when the operator has determined that adequate flow exists after HOT LEG injection is established. No further actions are required. The evaluator is expected to end the JPM.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SIM-1 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT ----------------

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEE'S CUE SHEET Initial Conditions:

1. A Loss of Coolant Accident (LOCA) has occurred on Unit-1.

2. SIAS actuated 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ago.

3. RCS pressure~ 20 PSIA with CETs indicating~ 230° F

4. Containment pressure is~ 5 PSIG.

5. Core flush, using 11 HPSI Pp for Pressurizer Injection via the Charging Header, is aligned thru EOP-5, Step IV.AE.l.h.( 4). Current Charging header flow, on 1-FIA-212, indicates 100 GPM.

6. You are performing the duties of the Unit-1 CRO.

Initiating Cue:

The CRS directs you to continue with the procedure, beginning at Step IV.AE.l.h.(5) of EOP-5-1.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-2 (Alt Path)

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-2 (Alt Path)

Task

Title:

Respond to CEA(s) Misaligned by 15 inches or more Task Number: 202.008 KIA

Reference:

003AA1.02 (3.6, 3.4)

Method of testing:

Simulated Performance: 0 Actual Performance: [g)

Classroom: 0 Simulator: [g) Plant: 0 Read to the examinee:

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

Initial Conditions:

1. Unit-1 is in Mode 1 at 100% power.

2. STP 0-29-1, MONTHLY CEA PARTIAL MOVEMENT TEST, was in progress. When CEA 01 was being exercised, it became misaligned from its group.

3. AOP-1B has been implemented and all stabilizing actions have been performed.

4. Electrical Maintenance discovered and replaced a faulty power supply during troubleshooting.

5. CEA alignment time expires in 90 minutes.

6. You are performing the duties ofthe Unit-1 RO.

7. You have been assigned the trip criteria of'IF ANY CEAs continue to move without operator action, with CEDS Control System in OFF, then trip the Reactor."

Initiating Cue:

The CRS directs you to realign CEA #1 per AOP-1B Step VI.B. Are there any questions?

You may begin.

Task Standard:

Manually realigns CEA-01 to within 7.5 inches of the remaining CEAs in Group 5.

Trips reactor when CEA-01 and CEA-36 drop into the core.

Verifies Reactor is shut down.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

Procedures and manuals normally available in the control room General

References:

1C05-ALM, Reactivity Control Alarm Manual AOP-1 B, CEA Malfunction Time critical task:

No Validation Time:

15 minutes

Appendix C Job Performance Measure Worksheet Form ES-C-1 Simulator Setup/Booth Operator Instructions:

1. Reset to IC-24 with both units at 100%.

2. Place Simulator in RUN.

3. Select Manual Individual, depress Group 5 Inhibit Bypass, depress and hold CMI Bypass pushbutton, then insert CEA #1 to approximately 110 inches withdrawn.

After 5 seconds release the CMI Bypass pushbutton.

4. Place CEDS control panel in OFF

5. Place the Group 5 Inhibit Bypass to OFF.

6. Verify the button for Group 5 is selected (lit)

7. Verify the individual CEA button for CEA #1 is selected (lit).

8. Allow plant to stabilize.

9. CEA 01 Drop: ceds012_01 on Event 1.

10. CEA 36 Drop: ceds012_36 on Event 1 with a 15 second delay.

11. Obtain Independent Verification for completion of steps 3 through 11.

_ _ 3. CEA #1 inserted to approximately 110 inches withdrawn.

_ _ 4. CEDS control panel in OFF

_ _ 5. Group 5 Inhibit Bypass to OFF

_ _ 6. Group 5 is selected (lit)

_ _ 7. CEA button for CEA #1 is selected (lit)

8. Plant is stabilized

_ _ 9. CEA 01 Drop is assigned to Event 1

_ _ 10. CEA 36 Drop is assigned to Event 1 with 15 second delay

12. Acknowledge all panel and plant computer alarms.

13. Ensure "HORN ON" for annunciation.

14. Select Clock Time and GO TO FREEZE.

15. Place in CONTINUE

16. When cued by evaluator, actuate Event 1.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded = CRITICAL STEP) STANDARD TIME START:

Locates AOP-1 B Section VI.B- ATTEMPT CEA Same as element.

REALIGNMENT 0 VI.B.1 -IF at any time the CEA is realigned, THEN perform the subsequent actions in Section IV., PRELIMINARY, Step Determines step is N/ A.

B, Page 16.

CUE: There is 90 minutes remaining for realignment ofCEA-01.

0 VI.B.2 - IF the CEA alignment time has expired, THEN Determines step is N/ A.

PROCEED to Step B.4, Page 24.

CAUTION CEA movement should be minimized until the cause of the misalignment has been determined.

The electric shop discovered and replaced a faulty power supply during the CUE:

troubleshooting. The CRS directs you to continue the procedure.

The CRS has directed the CRO to maintain power level no higher than the present level CUE:

using boration per OI-2B.

0 VI.B.3 -Attempt to realign the affected CEA(s): Same as element 0 VI.B.3.a. -Maintain Reactor Power as required by :

0 Boration PER OI-2B, CVCS BORA TION, DILUTION Determines no action AND MAKEUP OPERATIONS. needed based on Cue from OR evaluator.

0 Adjust Regulating CEAs.

0 Vl.B.3.b. - Select the desired group. Checks group 5 selected.

0 VI.B.3.c. - Select the desired CEA. Checks CEA 01 selected.

0 VI.B.3.d.- Select Manual Individual Mode.: Same as element 0 VI.B.3.e.- IF CMI is in effect, THEN override CMI as follows: Determines CMI is in effect.

NOTE CMI will be bypassed to the affected group and applied to all other groups, and CMI Bypass annunciation will alarm.

0 VI.B.3 .e.(l) - Depress the Group Inhibit Bypass Same as element pushbutton.

Appendix C Job Performance Measure Worksheet Form ES-C-1 STANDARD 0 VI.B.3~e.(2) -Depress and. holdth~

B)'l:lass pushbutton for at lf!ast 54~e.,, Same as element AND 5 seconds after CEA: inotion:>l<<;

0 ' ~ " ., ', ~:>>'in CAUTION Do NOT allow Reactor Power to rise above the power the unit was stabilized at in Section IV., PRELIMINARY, Step A.2, while the CEA is being realigned. Turbine load shall NOT be raised until the CEA is within its alignment requirements.

0 VI.B.3.f.- Realign the CEA:

0 VI.B.3.f.(l)- IF the CEA must be withdrawn, Determines step is THEN withdraw the CEA using the "Pull and Wait" applicable method:

0 For shutdown CEA's, pull3.75 inches and wait 10 Determines this rate is N/ A.

seconds Determines rate is applicable and commences recovery ofCEA-01 (withdraws CEA no more than 6.75" each time CEA is withdrawn).

0 VI.B.3.f.(2)- IF the CEA must be inserted, then insert the CEA. Determines step is N/A EVALUATOR NOTE:

The intent of this JPM, going forward, is for the OPERATOR to recognize that a Reactor Trip is required when two CEAs become misaligned by greater than 15 inches per Step V .A.1.

criteria.

Signal the booth operator to activate Event 1 to drop CEA-01 to the bottom after the CUE: student has performed a minimum of two pull and wait cycles. CEA-36 will drop when CEA 01 is fully inserted.

The following alarms annunciate when CEA # 01 drops: Operator stops withdrawing 0 Dropped CEA PI, CEA, notes alarms and CEA 0 Primary POlL, 0 Secondary PPDIL, status, and recommends 0 Secondary PDIL, and tripping the reactor 0 CEA deviation alarms annunciate Locates AOP-IB,Section V.A.1- PLANT SHUTDOWN Same as element

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) 0 V .A.1. - IF two or more CEAs are misaligned from the other CEAs in their respective group by greater than 15 Same as element inches, THEN perform the following actions:

CUE* IF the operator recommends tripping the reactor to the CRS, acknowledge tripping the

reactor and implement EOP-0.

Depresses manual reactor 0 trip buttons on 1C05.

Verifies reactor is tripped 0 V.A.1.b.- IMPLEMENT EOP-0, POST TRIP by observing a prompt drop in NI power and a negative IMMEDIATE ACTIONS. startup rate. Reports reactor is tripped.

TERMINATING CUE: This JPM is complete when the manual reactor trip pushbuttons are depressed, the reactor is verified tripped and the reactor is reported tripped. No further actions are required. The evaluator is expected to end the JPM.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SIM-2 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Q u e s t i o n : - - - - - - - - - - - - - - - - - - - - - - - - -

Applicant R e s p o n s e : - - - - - - - - - - - - - - - - - - - - - - - - -

Result: SAT _ _ _ _ __ UNSAT --------------

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET Initial Conditions:

1. Unit-1 is in Mode 1 at 100% power.

2. STP 0-29-1, MONTHLY CEA PARTIAL MOVEMENT TEST, was in progress. When CEA 01 was being exercised, it became misaligned from its group.

3. AOP-1B has been implemented and all stabilizing actions have been performed.

4. Electrical Maintenance discovered and replaced a faulty power supply during troubleshooting.

5. CEA alignment time expires in 90 minutes.

6. You are performing the duties ofthe Unit-1 RO.

7. You have been assigned the trip criteria of' IF ANY CEAs continue to move without operator action, with CEDS Control System in OFF, then trip the Reactor."

Initiating Cue:

The CRS directs you to realign CEA #1 per AOP-1B Step VI.B. Are there any questions? You may begin.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-3 (Alt Path)

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-3 (Alt Path)

Task

Title:

Attempt to Correct the Abnormal SDC Condition Task Number: 202.026 KIA

Reference:

025AK3.03 (3.9, 4.1)

Method of testing:

Simulated Performance: 0 Actual Performance: cgj Classroom: 0 Simulator: cgj Plant: 0 Read to the examinee:

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

Initial Conditions:

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

2. SDC is in service, using 12 LPSI Pp, and RCS temperature is 150°F. The RCS is being cooled down to a temperature band of 100-110°F.

3. RCS pressure is 150 PSIA with a bubble in the Pressurizer. The S/Gs are still available.

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

5. 12 LPSI Pp Breaker has just tripped.

6. You are performing the duties ofthe Unit-1 CRO.

Initiating Cue:

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

Task Standard:

SDC flow is restored, using a Containment Spray Pump, per AOP-3B. Reactor Coolant system temperature is observed to be lowering.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

AOP-3B, Abnormal Shutdown Cooling Conditions General

References:

Procedures and manuals normally available in the control room Time critical task:

No Validation Time:

15 minutes

Appendix C Job Performance Measure Worksheet Form ES-C-1 Simulator Setup/Booth Operator Instructions:

1. Reset to IC-07, (Unit-1 in Mode 5 with a PZR bubble with the RCS at 150° F and 250 PSIA).

2. Insert the following malfunctions/overrides:

_ _ 3. 11 LPSI Pump Bkr Failure: si003_01, on Event 1

_ _ 4. 12 LPSI Pump Bkr Failure: si003_02, on Event 1

_ _ 5. 11 CS PP DISCH: 1-SI-314, to 1.0 on a 60 second ramp, on Event 2

_ _ 6. 11 LPSI RWT SUCTION: 1-SI-444, to 1.0 on a 60 second ramp, on Event 2

7. Place in RUN

8. Lower RCS Pressure to approximately 150 PSIA using Auxiliary Spray.

9. Activate Event 1.

10. Place in FREEZE.

_ _ 11. Obtain Independent Verification for completion of the following steps:

_ _ 5. 11 CS PP DISCH, 1-SI-314, is set to open on Event 2

_ _ 6. 11 LPSI RWT SUCTION, 1-SI-444, is set to open on Event 2

_ _ 8. RCS Pressure has been stabilized at approximately 150 PSIA

_ _ 9. 11 & 12 LPSI Pump Bkr Failures are inserted as Event 1

_ _ 10. Simulator has been placed in FREEZE

_ _ 12.Acknowledge all panel and plant computer alarms.

8. Select "Hom On" for annunciators.

9. Select "Clock" time.

_ _ 10. When cued by evaluator, place in RUN.

_ _ 11. When directed, activate Event 2 to open 1-SI-314 and 1-SI-444. Report complete after agreed upon delay (~60 seconds each).

Appendix C Job Performance Measure Worksheet Forrn ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START:

Locates AOP-3B, Step IV.A.6. Same as element.

IV.A. PRELIMINARY 0 IV .A.6. -IF SDC is lost due to failure of the operating Determines step is LPSI PP AND the cause will NOT result in a common applicable.

mode failure, THEN complete the following actions:

Places 12 LPSI in PTL.

0 IV.A.6.a.- Place the failed PP handswitch in PULL TO Determines 12 LPSI Pump LOCK. failure will not result in a common mode failure.

0 IV .A.6.b. -IF RCS purification is in service, THEN place IX BYP valve handswitch Same as element.

1-HS-2520 in the BYP position.

Lowers output of HIC-657 on 1C09 to zero or places HS-3657 on 1C09 to CLOSE. Checks position indication for SI-657.

Shifts FIC-306 on 1C08 to MANUAL.

Adjusts output ofFIC-306 to 95%.

0 IV.A.6.f.- Verify BOTH RAS OVERRIDE switches in Checks position on HS-OVERRIDE: 302XA and 302Y A on 1C08 and 1C09. If not in 0 11 LPSI PP RAS OVERRIDE, 1-HS-302XA OVERRIDE position, places 0 12 LPSI PP RAS OVERRIDE, 1-HS-302YA. HS in OVERRIDE CAUTION:

Before starting the standby LPSI PP, the cause for the running LPSI PP failure should be determined to preclude a common mode failure.

The CRS states that 11 LPSI is not affected by the same motor issue that caused 12 CUE:

LPSI pump to trip.

Appendix C Job Performance Measure Worksheet Fonn ES-C-1 ELEMENT (shaded = CRITICAL STEP) STANDARD Tries to start 11 LPSI.

Determines pump has not 0 IV.A.6.g. Start the standby LPSI PP.

started. Goes to the alternate action step IV.A.6.g.l.

PERFORM ALTERNATE ACTION(S)

CRS reports he will assign the extra operator to perform B, Page 17.

CUE:

CRS reports steps C.1 thru C.4 have been completed and directs you to begin at Step C.5.

0 IV.A.6.g.l.- IF the standby LPSI PP does NOT Determines extra CRO will start, THEN assign an operator to perform B, Page perform step B and next step 17, AND concurrently PROCEED to Step C, Page is C.5 based 20 on CRS direction.

IV.C. ATTEMPT TO RESTORE FROM ABNORMAL SDC CONDITION 0 IV.C.5.- IF NO LPSI PPs are available, THEN align Determines step is the CS PPs for cooling. applicable.

CAUTION:

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

0 IV.C.5.a.- Verify RCS temperature less than 120° F Checks that ECCS PP Room OR the associated ECCS PP Room Air Cooler is Air Coolers are not OOS.

functional.

CAUTION:

To prevent over pressurization of the ECCS PP suction headers, RCS pressure shall be less than 170 PSIA.

Checks RCS pressure less 0 IV .C.5.b. -Check that RCS pressure is less than 170 than PSIA. 170 PSIA on PI-1 03 and/or PI-1 03-1 on panel 1C06.

0 IV.C.5.c.- Check that the SDC HDR RETURN ISOL valves are open:

Same as element 0 1-SI-651-MOV 0 1-SI-652-MOV

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD Same as element Same as element Same as element CRS directs use of 11 CS PP CUE: Driver: Acknowledge request. Activate Event 2 to open 1-SI-314 and 1-SI-444.

Report complete after agreed upon time delay (;:::;60 seconds each).

0 IV.C.5.f.- IF 11 CS PP is desired for SDC, THEN open the following valves:

Contacts ABO to position 1-0 11 CS PP Discharge valve, 1-SI-314 SI-314 and 1-SI-444 to the open position 0 11 LPSI PP NORM SUCT ISOL valve, 1-SI-444 D IV.C.5.g.- IF 12 CS PP is desired for SDC. .. Determines step is N/ A.

Verifies output of 1-HIC-657 is zero or 1-HS-3657 is in 0 IV.C.5.h.- Shut the S/D COOLING TEMP CONTR CLOSE. Checks position valve, 1-SI-657-CV.

indication for 1-SI-657.

0 IV.C.5.i.- Place the SHUTDOWN CLG FLOW CONTR, 1-FIC-306, in MANUAL.

Same as element

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded = CRITICAL STEP) STANDARD 0 IV.C.5.j.- Adjust the output of the SHUTDOWN CLG FLOW CONTR, Same as element 1-FIC-306, to 95%.

Starts 11 CS PP

,. . )V*t¢.* 5:1:~;S*l~w1y1illju~t:;fhe*SfiUroo WN .*

> QuOFLPWdON[l{;.:r~FrC:3o6;*t<>'raise .* Same as element

'/*SDG*fiow

' <, :"'\d '<~,

io:1soor2otio'tJpi1Ir

',*- :,:;-, : "' ', * -~ ~,, '-

CUE: CRS desires SHUTDOWN CLG FLOW CONTR, 1-FIC-306, be placed in auto 0 IV.C.5.m.- IF desired to place SHUTDOWN CLG FLOW CONTR, 1-FIC-306, in AUTO, THEN perform the following.

0 IV.C.5.m.(l)- Adjust the setpoint on Same as element 1-FIC-306 to match SDC flow 0 IV.C.5.m (2)- Place 1-FIC-306 in AUTO. Same as element CUE: The CRS directs to continue RCS cooldown to a temperature band of 100 to 110 °F IF 1-HS-3657 is in CLOSE, places in AUTO then raises output of 0 IV.C.5.n.- Adjust the S/D COOLING TEMP 1-HIC-3657 to lower RCS CONTR valve, 1-SI-657-CV, as desired. temperature.

Checks RCS temperature slowly lowering (TR-351 on panel 1C09).

ALTERN ATE ACTION(S) COMPLETED TERMINATING CUE: This JPM is complete when SDC has been restored using a CS Pump and SDC temperature is observed to be lowering. The evaluator is expected to end the JPM.

No further actions are required.

I TIME STOP: - -

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SIM-3 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant R e s p o n s e : - - - - - - - - - - - - - - - - - - - - - - - -

Result: SAT - - - - - - - UNSAT _______________

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEE'S 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. SDC is in service, using 12 LPSI Pp, and RCS temperature is 150°F. The RCS is being cooled down to a temperature band of 100-110°F.

3. RCS pressure is 150 PSIA with a bubble in the Pressurizer. The S/Gs are still available.

4. The ABO reported smoke corning from 12 LPSI Pp motor.

5. 12 LPSI Pp Breaker has just tripped.

6. You are performing the duties ofthe Unit-1 CRO.

Initiating Cue:

The CRS directs you to respond to the Loss of SDC per AOP-3B (Abnormal Shutdown Cooling Conditions) starting in Section IV, Step A.6.

Are there any questions? You may begin.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-4 (Alt Path)

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-4 (Alt Path)

Task

Title:

Respond to a Failure of a Pump with Reactor Power < 5%

Task Number: 202.037 KIA

Reference:

054AA1.02 (4.4, 4.4), 054AA2.03 (4.1, 4.2)

Method of testing:

Simulated Performance: 0 Actual Performance: ~

Classroom: 0 Simulator: ~ Plant: 0 Read to the examinee:

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

Initial Conditions:

1. Unit-1 is at ~0.5% power during a plant startup.

2. 13 Condensate pump is tagged out.

1. Annunciator windows C-Ol and C-02 "11 & 12 CONDS PUMP OIL FLOW LO" on 1C03 came into alarm. Shortly thereafter, 11 and 12 Condensate pumps tripped.

3. 11 SGFP subsequently tripped on low suction pressure and annunciator windows C-25 "SGFP(S) SUCT PRESS LO" and C-26 "11 SGFPT TRIP" on 1C03 are in alarm.

4. You are performing the duties of the Unit-1 CRO.

Initiating Cue:

The CRS directs you to respond to the Condensate Pump trip per AOP-3G, Main Feedwater Malfunctions,Section VI, Block Step A.

Task Standard:

Restores S/G levels using the Auxiliary Feedwater per the appropriate plant procedure.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

AOP-2A, Excessive Reactor Coolant Leakage General

References:

Procedures and manuals normally available in the control room Time critical task:

No Validation Time:

20 minutes

Appendix C Job Performance Measure Worksheet Form ES-C-1 Simulator Setup:

1. Reset to IC-9 (U-1 ZPPDIL with 11 SGFP in service).

a. Pull CEA's to criticality and level power at 10-5%

2. Insert the following malfunctions I overrides

a. 13 Cond Pp: P1C03_1HS4428, to PULL, at time zero.

b. 11 Cond Pp Breaker failure: cd004_01 at time zero

c. 12 Cond Pp Breaker failure: cd004_ 02 at time zero

d. 13 AFW Pump Breaker Failure: afwOOS, on Event 1.

3. Place 13 Condensate Pump handswitch in PTL.

4. Place a caution tag on 13 Condensate Pump handswitch.

5. Place simulator in RUN.

6. WHEN 11 SGFP trips, place in FREEZE.

7. Acknowledge all panel and computer alarms.

8. Ensure "Horn On" is selected for annunciators.

9. Ensure "Clock" is selected for time.

_ _ 10. Obtain Independent Verification for completion of steps 2 through 6.

_ _ 2. Malfunctions/Overrides entered as specified.

_ _ 3. 13 Cond Pp H/S is in PTL

_ _ 4. 13 Cond Pp H/S is Caution Tagged in PTL

_ _ 6. 11 SGFP tripped and the Simulator is in FREEZE

_ _ 11. WHEN cued by evaluator, place in RUN.

_ _ 12. WHEN cued by evaluator, activate Event 1.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD EVALUATOR NOTE Cue driver to place simulator in RUN.

TIME START:

0 Identifies and locates AOP-3G Section VI Same as element VI.A. - DETERMINE IF A REACTOR TRIP IS REQUIRED EVALUATOR NOTE Once CRO has determined S/G levels inform operator that the RO will monitor S/G levels for trip strategy.

Monitors S/G levels on 0 VI.A.1 - IF SG level is approaching (-) 40 inches, THEN, 1C03, determines a reactor with the approval of the SM/CRS, perform the following trip is not necessary and that actions ... the RO will monitor for trip criteria.

VI.B. - ESTABLISH A SOURCE OF FEEDW ATER CAUTION Excessive feeding at low power conditions will affect TcoLD and Reactivity.

PZR level and RCS pressure can be affected.

CAUTION A severe waterhammer may result if Main Feedwater flow is restored after it has been stopped for greater than 80 minutes.

I CUE: TBO reports there is no indication of a faulted bus.

0 VI.B.1. -IF the following conditions exist:

Determines step is N/ A.

0 A SGFP has tripped (Standby SGFP is not 0 The standby SGFP is available available due to low suction 0 There is sufficient time available to start the standby pump header pressure trip THEN perform the following actions: ... conditions)

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD CAUTION A severe waterhammer may result if Main Feedwater flow is restored after it has been stopped for greater than 80 minutes.

Determines step is N/ A.

0 VI.B.2.- IF time does NOT permit starting the standby (Tripped SGFP cannot be SGFP, THEN, with the approval of the SM/CRS, ... restarted) 0 VI.B.3.- IF a Condensate Booster Pump has tripped, Determines step is N/ A.

THEN perform the following ... Proceeds to Step 4.

Determines backup Cond 0 VI.B.4. - IF a Condensate Pump has tripped, Pps are NOT available THEN perform the following actions ... based on initiating cue

> L' t, t £, , , 1 "'"' , :;:: ' , ,

, lr,EREP~"M MitT~RNA:T~,

'" "'. ~~~ j, *., *;~ *'~

ACTIONS, CAUTION Starting a pump without determining the cause of the failure could initiate a common mode failure.

0 VI.B.4.a.l -IF a backup Condensate Pump did NOT start, Determines step is N/ A per THEN, with the approval of the SM/CRS, attempt to start Initiating Cue.

the backup Condensate Pump.

CUE: I When requested, direct operator do NOT attempt to start tripped pumps.

0 VI.B.4.a.2- IF a backup Condensate Pump will NOT start, Requests concurrence from THEN, with the approval of the SM/CRS, attempt to start CRS to attempt to start a the tripped Condensate Pump. tripped pump.

ALTERNATEACTIO:NS COMPLETED Determines step is N/ A and 0 VI.B.5.- IF Main Feedwater flow has been restored ... continues to step 6.

NOTE Restoration of Main or Auxiliary Feedwater will affect RCS Tcow.

0 VI.B.6.- Control RCS Tcow by using ANY ofthe following methods, as applicable:

Monitors TcoLD on 1C05 and/or 0 adjusting TBVs 1C06, and TBV operation.

0 adjusting ADV s to maintain the following temperature band:

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD 0 IF the Reactor is critical, THEN within 2°F of Determines Tcowis within 2°F of program T cow program.

0 IF the Reactor is NOT critical Determines step is N/ A 0 VI. B. 7. - IF Main Feedwater will NOT be restored, Determines step is applicable THEN perform the following actions:

CUE: I Once power level evaluated, inform operator that RO will maintain power less than 1%.

NOTE This step should be performed concurrently with the remaining steps.

0 VI.B.7.a.- Reduce power to less than 1% Determines power less than 1%

0 VI.B.7.b.- Shut the S/G BD valves:

0 1-BD-40 10-CV 0 1-BD-4011-CV Same as element 0 1-BD-40 12-CV 0 1-BD-4013-CV 0 VI.B.7.c.- Initiate AFW using 13 AFW PP as Same as element.

follows:

0 VI.B.7.c.(l)- Verify open the motor driven SG AFW Block Valves:

11 SG 0 1-AFW-4522-CV Same as element.

0 1-AFW-4523-CV 12 SG 0 1-AFW-4532-CV 0 1-AFW -4533-CV EVALUATOR NOTE 13 AFW Pp will trip approximately 1 minute after it is started.

0 VI.B.7.c.(2)- Start 13 AFW PP Same as element.

CUE: l Acknowledge pump trip and alternate actions being taken.

Appendix C Job Performance Measure Worksheet Forrn ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD hr '# ... " ::. .. . . . . * :, . ** ' . * . *

'>,lJ~.{ilN*~bTE~ATE A-CTIONS

'"< '" .,,N, }' ' '< ' * ;

0 VI.B.7.c.l -Initiate AFW using 11 or 12 Determines step is applicable.

AFW PP as follows:

0 VI.B.7.c.l(l)- Verify open the steam driven SG AFW Block Valves:

11 SG 0 1-AFW -4520-CV Same as element 0 1-AFW-4521-CV ll_SG 0 1-AFW-4530-CV 0 1-AFW-4531-CV Same as element 0 VI.B.7.c.l(3)- Adjust and maintain 11 or 12 AFW PP discharge pressure at least Same as element 100 PSI greater than SG pressure using the No action required discharge AFW PP SPEED CONTRs:

pressure is > 1OOpsia above S/G 0 (11 AFW) 1-HC-3987A pressure 0 (12 AFW) 1-HC-3989A 0 VI.B.7.c.1(4)- Ensure the feedwater flowrate does NOT cause RCS cooldown to exceed the following limits for any one hour: [BO 126] Monitors RCS temperature.

Adjusts flow as necessary.

0 Greater than 256°F 100°F /hr 0 106°F to 256°F 40°F/hr 0 Less than 106°F 35°F/hr CAUTION Total AFW flow should NOT exceed 600 GPM per unit (300 GPM per unit when feeding both Units from either Unit 1 OR Unit 2).

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD 0 VI.B.7.c.1(5)- Adjust the SG FLOW CONTRs to maintain level at approximately zero inches: Monitors SG level. Adjusts flow to maintain SG level.

0 (11 SG) 1-FIC-4511A 0 (12SG) 1-FIC-4512A 0 VI.B.7.c.l(6)- Operate AFW Pump Room Dispatches Aux Bldg operator to Ventilation, PER OI-32A, AUXILIARY verify AFW ventilation in service FEEDWATER SYSTEM. per OI-32A.

0 VI.B.7.d.- Shut the SG FW ISOL valves:

0 (11 SG) 1-FW-4516-MOV Same as element 0 (12 SG) 1-FW-4517-MOV 0 VI.B.7.e.- Notify Plant Chemistry that the AFW Same as element System is in service.

0 VI.B.8. - IF AFW is maintaining SG levels between

(-)24 inches and (+)30 inches, THEN, with the approval of SM/CRS, perform ONE of the following: Determines step is applicable.

0 Maintain power less than 1% while attempting to Monitors S/G levels and maintains restore the Main Feedwater System. a positive trend to restore between

(-) 24 inches and (+) 30 inches.

0 IMPLEMENT OP-4, PLANT SHUTDOWN FROM POWER OPERATION TO HOT STAND BY to shutdown the Unit.

TERMINATING CUE: This JPM is complete when S/G levels are trending toward between

-24 inches and +30 inches using either steam driven AFW train. No further actions are required.

The evaluator is expected to end the JPM.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SIM-4 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT - - - - - - - UNSAT - - - - - - - - -

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEE'S CUE SHEET Initial Conditions:

1. Unit-1 is at ~0.5% power during plant startup from an extended outage.

2. 13 Condensate pump is tagged out.

3. Annunciator windows C-Ol and C-02 "11 & 12 CONDS PUMP OIL FLOW LO" on 1C03 came into alarm. Shortly thereafter, 11 and 12 Condensate pumps tripped.

4. 11 & 12 SGFP's subsequently tripped on low suction pressure and annunciator windows C-25 "SGFP(S) SUCT PRESS LO" and C-26 "11 SGFPT TRIP" and C-30 "12 SGFPT TRIP" on 1C03 are in alarm.

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

Initiating Cue:

The CRS directs you to respond to the Condensate Pump trip per AOP-3G, Main Feedwater Malfunctions,Section VI, Block Step A.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-5

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-5 Task

Title:

Bleed and Feed to cool the quench tank Task Number: No specific CCNPP task KIA

Reference:

007A1.01, A1.02, A1.03 Method of testing:

Simulated Performance: 0 Actual Performance: [gJ Classroom: 0 Simulator: [gJ Plant: 0 Read to the examinee:

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

Initial Conditions:

1. Alarm Window E-0 1 has just come into alarm due to a long term slowly leaking safety valve which causes alarm every 8-10 hours (CR previously written).

2. You are performing the duties of the Unit-1 CRO.

Initiating Cue:

The CRS directs you to respond to the Quench Tank alarm.

Are there any questions? You may begin.

Task Standard:

Verifies the Operator's Ability to Restore Quench Tank Parameters.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion ofthe task.

Required Materials:

OP-3, Power Operations OI-1B, Quench Tank Operations General

References:

Procedures and manuals normally available in the control room Time critical task:

No Validation Time:

10 minutes Simulator Setup:

1. Reset to IC-24 with both units at 100% in FREEZE.

2. Insert malfunction RCS027_ 01 at 20% until Quench Tank level and pressure come into alarm (~5 seconds@ 100% power), then delete malfunction.

3. Open and start schedule Sim-5

a. Override P1C06_1TIA to 122@ time zero, P1C06_1TIA116_LTHIGH to on@

time zero, P1C06_E01_LTON to On at time zero

b. Override P 1C06 _1 TIA to 115 over 30 seconds on Event 1, P1C06_1TIA116_LTHIGH to off after 10 seconds on Event 1, P 1C06- EO 1- LTON to delete after 40 seconds on Event 1

4. Pump RCDT, then freeze

5. Acknowledge all panel alarms and ensure "Horn On" for annunciators.

6. Select "Clock" time.

7. WHEN cued go to RUN.

Appendix C Job Performance Measure Worksheet Form ES-C-I ELEMENT (shaded= CRITICAL STEP) STANDARD CUE I Have simulator driver place Simulator in RUN TIME START:

0 Identifies Alarm Manual 1-C06, Window E-0 1 Same as Element 1C06 ALM Window E-01 Identifies the following:

0 Determines which parameters are causing alarm. Temp is in alarm high at 122° BEGIN ALARM MANUAL ACTIONS 0 l.a -Shut any open valves listed under leaking or open Verifies all valves shut Possible Causes 0 l.b- IF a PORV is leaking or open and fails to shut when RCS pressure is reduced below its lift setpoint, THEN CONSIDER placing the applicable PORV Override Determines step is N/ A handswitch , 1-HS-1402 or 1-HS-1404, in OVERRIDE or SHUT PORV Block, 1-RC-403-MOV or 1-RC-405-MOV.

0 I.e - RETURN parameter to within normal limits by venting, Locates OI-l B, determines filling, draining or feed and bleed as necessary PER OI -1 B, 6.5 is the correct section Quench Tank Orerations.

CUE I CRS will Evaluate Tech Specs 0 l.d- REFER to Technical Specifications 3.4.11 and 3.4.12 for Determines step is N/ A PORV operability requirements.

CUE I CRS Directs a Feed & Bleed to be performed per OI-IB 0 OI-lB- Section 6.5, Bleed & Feed the Quench Tank

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD CUE j All Initial Conditions Are Satisfied D 6.5.A- Initial Conditions D 6.5 .A.l. - RCS Pressure is greater than 50 PSIA. Satisfied per CUE D 6.5.A.2.- Quench Tank temperature is higher than normal due to leakage or discharge from any of the following:

D Pressurizer Power Operated Relief Valve Satisfied per CUE D Pressurizer Safety Valve D Safety Injection System ReliefValve D Pressurizer Vents D Reactor Vessel Head Vents D 6.5.A.3. -No relief or safety valve discharge to the Satisfied per CUE Quench Tank is in progress.

D 6.5.B - Procedure NOTE Steps 6.5.B.l through 6.5.B.4 may be performed in any order to minimize the amount of liquid or gaseous waste.

CAUTION

Do NOT attempt to adjust the Quench Tank parameters until after the relief or safety valve has completed lifting.

The Sparger Nozzles will become uncovered at approximately 24 inches indicated level and the Quench Tank may experience a rapid increase in pressure if this occurs. The amount of time the Sparger Nozzles will be uncovered should be minimized.

D 6.5.B.l -Drain the Quench Tank as follows:

D 6.5.B.l.a. -PUMP the RCDT PER OI-17C as necessary while draining the Quench Tank to Determines step is not maintain RCDT level below the Hi level alarm necessary setpoint (45 inches)

D 6.5.B.l.b. - OPEN QUENCH TK DRN, Same as element RC-401-CV.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD CAUTION

Quench Tank pressure should be continuously monitored to ensure pressure does NOT exceed 10 psig

Maintain Quench Tank pressure greater than 0 psig to prevent flashing in the discharge piping 0 6.5.B.l.c. - IF a lowering pressure develops in the Quench Tank that prevents draining, THEN PERFORM one ofthe following:

0 OPEN the applicable Containment Nitrogen Supply Valve, 0-Nz-238 Determines step is N/ A OR 0 THROTTLE OPEN N2-6318-PCV Bypass Isolation, O-N2-591, while monitoring pressure at PI-6318 so as not to exceed 10 PSIG NOTE Draining the Quench Tank below the low level alarm is acceptable during the bleed and feed due to the tank being refilled immediately Same as element Same as element CAUTION Quench Tank pressure should be continuously monitored to ensure pressure does NOT exceed 10 PSIG 0 6.5.B.2- PERFORM one ofthe following:

0 OPEN the Containment Nitrogen Supply Valve, 0-Nz-238 OR Determines step is N/ A 0 THROTTLE OPEN 0-Nz-591 Bypass Isolation while monitoring pressure at Pl-6318 so as not to exceed 10 PSIG CAUTION

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD

Quench Tank pressure should be continuously monitored to ensure pressure does NOT exceed 10 psig

Maintain Quench Tank pressure greater than 0 psig to prevent flashing in the discharge p1pmg 0 6.5.B.3.- WHEN QT pressure is at the desired pressure, THEN SHUT Containment Nitrogen Supply Determines step is N/A Valve 0-Nz-238 or Bypass Isolation Valve 0-Nz-591 NOTE DW -5460-CV may be opened on an intermittent basis under administrative control PER T/S 3.6.3.1. This shall be controlled PER N0-1-205.

0 6.5.B.4.- FILL the Quench Tank as follows: Same as element Same as element When fill begins have driver insert Event 1 Determines step is N/A Same as element Same as element 0 6.5.B.5.- REPEAT Steps 6.5.B.l through 6.5.B.4 until Quench Tank temperature is less than 120°F Determines step is N/A AND the Quench Tank high temperature alarm is clear.

0 6.5.B.6.- FILL OR DRAIN the Quench Tank to Same as element approximately 28.5 inches (between the high and low (if performed) level alarm).

0 6.5.B.7.- ENSURE SHUT the Containment Nitrogen Supply Valve O-N2-238 or Bypass Isolation Valve Same as element O-N2-591 0 6.5.B.8.- IF the Quench Tank is going to be vented Determines step is N/ A THEN NOTIFY Rad Con Supervision

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD CAUTION When lowering pressure in the Quench Tank following an energy release event (for example, any event that may have caused steam/condensation buildup in the discharge piping), the venting shall occur in small pressure increments (approximately 2 psi increments), with a wait of approximately 20 minutes in between vents. This is to prevent thermal changes on the Code Safety valve discs (caused by flashing the liquid to steam which has a cooling effect). Too large of a thermal change will cause the Code Safety to leak.

Same as element (if performed) 0 6.5.B.9.- ESTABLISH Quench Tank pressure of less than 10 psig by venting to the Waste Gas header as Candidate may see pressure follows: > 3 psig and decide to lower pressure based on Note in the Procedure 0 6.5.B.9.a.- OPEN the following valves:

0 WGS CNTMT ISOL WGS-2180-CV Same as element 0 WGS CNTMT B/U ISOL WGS-2181-CV (if performed) 0 QUENCH TK VENT RC-400-CV CUE \ CRS directs that quench tank pressure anywhere between 3-10 psig is acceptable NOTE Quench Tank normal operating pressure is 3 PSIG 0 6.5.B.9.b.- WHEN the Quench Tank is at the Same as element desired pressure, THEN SHUT the following (if performed) valves:

0 WGS CNTMT ISOL WGS-2180-CV Same as element (if 0 WGS CNTMT B/U ISOL WGS-2181-CV performed) 0 QUENCH TK VENT RC-400-CV TERMINATING CUE: The JPM is complete when the CRS is informed that Quench Tank parameters are returned to normal. No further actions are required. The examinee is expected to end the JPM. If the examinee performs Step 9 the examiner may end the JPM due to extended time required to vent the Quench Tank.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SIM-S Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Q u e s t i o n : - - - - - - - - - - - - - - - - - - - - - - - - -

Applicant Response: - - - - - - - - - - - - - - - - - - - - - - - - -

Result: SAT _ _ _ _ __ UNSAT ____________

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEE'S CUE SHEET Initial Conditions:

3. Alarm Window E-0 1 has just come into alarm due to a long term slowly leaking safety valve which causes alarm every 8-10 hours (CR previously written).

4. You are performing the duties of the Unit-1 CRO.

Initiating Cue:

The CRS directs you to respond to the Quench Tank alarm.

Are there any questions? You may begin

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-6 (Alt Path)

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-6 Task

Title:

Verify the Vital Auxiliaries Safety Function is Satisfied Task Number: 201.013 KIA

Reference:

062A4.01 (3.3, 3.1)

Method of testing:

Simulated Performance: D Actual Performance: [g]

Classroom: D Simulator: [gl Plant: D Read to the examinee:

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

Initial Conditions:

1. A ground fault on 11-4KV bus has resulted in a reactor trip on Unit-1.

2. Annunciator R03 "U-1 4KV ESF FDR BKR TRIP" is in alarm due to the normal feeder to 14-4KV bus spuriously tripping open.

3. EOP-0 has been implemented and Turbine Trip has been verified.

4. You are performing the duties of the Unit-1 CRO.

Initiating Cue:

You are to perform EOP-0-1, Step IV.C- Verify the Vital Auxiliaries Safety Function is Satisfied.

Task Standard:

Candidate energizes 14 4KV Bus via its Alternate Feeder and reports Vital Auxiliaries as complete.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

EOP-0, Post Trip Immediate Actions General

References:

Procedures and manuals normally available in the control room Time critical task:

No Validation Time:

10 minutes

Appendix C Job Performance Measure Worksheet Form ES-C-1 Simulator Setup:

1. Reset to IC-24

2. Insert the following malfunctions:

a. 11 4KV bus fault: 4kv001 01 at time zero.

_ _ b. 1B DG start failure: dg001_02 at time zero.

3. Place in RUN for approximately one (1) minute, then trip the reactor.

4. After turbine trips SHUT the MSIVs to prevent uncontrolled cooldown of the RCS.

5. OPEN the normal feeder to 14 4KV bus and match its flag back to red (i.e. take its handswitch to close without the synch stick).

6. Place simulator in FREEZE.

7. Obtain an Independent Verification for steps 3, 4, 5, and 6.

_ _ 2. Malfunctions are correctly inserted

_ _ 3. Reactor is tripped

4. MSIVs are shut

_ _ 5. 14 4KV Bus Normal Breaker is open with a "red" flag

8. When cued by evaluator, place in RUN.

Appendix C Job Performance Measure Worksheet Form ES-C-I ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START:

0 Identifies & locates EOP-0-1, Step IV.C or uses plaque Same as element.

located on DG panel IV.C.- VERIFY THE VITAL AUXILIARIES SAFETY FUNCTION IS SATISFIED Determines neither 4KV 0 IV.C.l.- Check 11 OR 14 4KV Vital Bus is energized.

bus is energized.

CAUTION Attempts should NOT be made to re-energize a bus if a fault is suspected.

PERFORM ALTERNATE ACTIONs 0 IV.C.l.l.- IF BOTH 4KV Vital Buses are Determines step is de-energized, THEN energize 11 OR 14 4KV Vital Bus applicable.

from a DG by performing the following:

EVALUATOR NOTE:

The report of taking Alternate Actions can be made at the discretion of the operator but should be reported as soon as practical.

0 IV.C.l.l.a.- Start the OC DG using the OC DG Same as element EMERGENCY START PB, 0-HS-0707.

Report DG status if requested: 1A DG started but did not close in on the bus 11. TBO CUE: reports an apparent fault on 11 4KV bus. IB DG tripped, on start, due to a mechanical problem.

Checks 1A DG voltage and frequency on 1C 18A.

Determines 1A DG is running but did not close in on II 4KV bus due to fault.

May contact OSO to emergency S/D as no power 0 IV.C.l.l.b.- Verify 1A or 1B DG is running. to auxiliaries.

Determines I B DG is not running. Pushes 1B Start pushbutton (1-HS-1424).

Determines both DGs have failed to energize their respective 4KV bus.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD 0 IV.C.l.l.b. (1)- Verify the associated DG OUT Determines that 1A DG BKR closed: breaker will not close due to a fault on the 11 4KV bus 0 11 Bus - 152-1703 and 1B DG will not start 0 14 Bus- 152-1403 due to a DG issue.

NOTE The actions of Step 1.2 may be performed on 11 4KV bus but the alternate feeder will not close due to the existing ground fault.

0 IV.C.l.2.- IF 1A and 1B DGs can NOT be loaded Determines 13KV power is AND 13KV is available, THEN energize 11 OR 14 4KV available and the step is Vital Bus as follows: applicable.

Checks DG output breaker 0 IV.C.l.2.a.- Verify the DG OUT BKR is open. position or may take the breakers to PTL.

Places 14 4KV Bus LOCIISD sequencer manual initiate keyswitch to "ON".

Inserts sync stick into jack for 14 4KV alternate feeder breaker (152-1401) and operates 1-CS-152-140 1 handswitch to close the breaker and energize the bus. May acknowledge the annunciator window "SEQUENCER INITIATED" alarm on 1C08.

NOTE Exit from EOP-0 shall NOT be delayed in anticipation of OC DG availability.

0 IV.C.l.3.- IF 11 and 14 4KV Buses are deenergized, THEN use the OC DG to energize 11 OR 14 4KV Bus as Determines step is N/ A.

follows:

END OF ALTERNATE ACTIONS 0 IV.C.2- IF EITHER 11 OR 14 4KV Vital Bus is NOT Determines step is N/ A.

energized and the OC DG is NOT running ...

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD 0 IV.C.3- Check ALL 125V DC BUS VOLTS greater than 105 volts:

0 11 Checks 125V DC 0 12 bus voltages on 1C24A.

0 21 0 22 0 IV.C.4- Check at least THREE 120V AC Vital Buses are energized:

0 11 Checks 120V AC 0 12 bus voltages on 1C24A.

0 13 0 14 Checks 208/120V instruments AC bus voltage 0 IV .C.5 - Check EITHER 1Y09 OR 1Y1 0 is energized: on 1C24A.

Determines that 1Y 10 is energized.

Starts 12 or 13 CC Pump.

0 Checks CC flow to RCPs by also ensuring 1-CC-3832-CV Same as element and 1-CC-3833-CV are open. The RCPs are not tripped.

0 IV.C.7- IF ANY electrical bus perturbations have occurred, Dispatches operator to THEN dispatch an operator to verify Switchgear Room verify Switchgear Room Ventilation operating PER OI-22H, SWITCHGEAR Ventilation operating per VENTILATION AND AIR CONDITIONING. OI-22H.

Makes appropriate Safety Function Report to the CRS 0 Reports Vital Auxiliaries are complete.

with information regarding status of electrical system.

TERMINATING CUE: This JPM is complete when 14 4Kv bus is powered from its Alternate Feeder, a Component Cooling Pump is started and the Vital Auxiliaries Safety Function is reported as complete. No further actions are required. The trainee is expected to end the JPM.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SIM-6 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Q u e s t i o n : - - - - - - - - - - - - - - - - - - - - - - - - -

Applicant R e s p o n s e : - - - - - - - - - - - - - - - - - - - - - - - - -

Result: SAT _ _ _ _ __ UNSAT _____________

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 APPLICANT'S CUE SHEET Initial Conditions:

1. A ground fault on 11-4KV bus has resulted in a reactor trip on Unit-1.

2. Annunciator R03 "U-1 4KV ESF FDR BKR TRIP" is in alarm due to the normal feeder to 14-4KV bus spuriously tripping open.

3. EOP-0 has been implemented and Turbine Trip has been verified.

4. You are performing the duties of the Unit-1 CRO.

Initiating Cue:

You are to perform EOP-0-1, Step IV .C - Verify the Vital Auxiliaries Safety Function is Satisfied.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-7

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-7 Task

Title:

Shift Component Cooling Heat Exchangers Task Number: 015.003 KIA

Reference:

008.A4.01(3.3, 3.1)

Method of testing:

Simulated Performance: 0 Actual Performance: [ZI Classroom: 0 Simulator: [ZI Plant: 0 Read to the examinee:

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

Initial Conditions:

1. Both Units are at 100% power

2. 11 & 12 Component Cooling Heat Exchanger are in service.

Initiating Cue:

You are performing the duties of Unit 1 CRO. The CRS directs you to secure 11 Component Cooling Heat Exchangers IA W the Operating Instruction in preparation for tagging out 11 Salt water Header.

Task Standard:

Place 11 CCHX in standby in accordance with OI-16 Sect. 6.6

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

None General

References:

OI-16 Component Cooling System Time critical task:

No Validation Time:

10 minutes Simulator Setup:

_ _ 1. Reset to IC-24, both units at 100% power.

_ _ 2. Ensure 11 CCHX in service and 12 CC pump running.

3. Place simulator in RUN.

_ _ 4. Ensure 1-HIC-5208 at 0% output

_ _ 5. Acknowledge all panel and plant computer alarms.

6. Ensure the "HORN ON" is selected for annunciators.

7. Place in FREEZE.

_ _ 8. Obtain Independent Verification for completion of step 2.

_ _ 9. When cued by evaluator, go to RUN.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD CUE I Initial Conditions and General Precautions are satisfied.

TIME START:

0 Identifies OI-16, Section 6.6 Same as element.

0 6.6- SHIFTING FROM 2 COMPONENT COOLING HEAT EXCHANGER OPERATION TO SINGLE COMPONENT COOLING HEAT EXCHANGER OPERATION [CONTINUOUS USE]

0 6.6.A - Initial Conditions 0 6.6.A.1 - Two Component Cooling Heat Exchangers are in service.

CAUTION:

RCS boron concentration will be affected when CVCS ion exchangers are returned to service if the Letdown heat exchanger outlet temperature has changed since they were bypassed.

[B0270]

Lower Letdown system temperature will add positive reactivity .

Higher Letdown system temperature will add negative reactivity .

CUE The CRS desires the CVC Ion Exchangers to be bypassed.

CUE The RO will log stop time in the CVCS Ion Exchanger and Filter Log 0 6.6.B- Procedure 0 6.6.B.1.- IF it is desired to bypass the CVCS ion Places 1-CVC-520-CV in exchangers, THEN PLACE IX BYPASS, 1-CVC-520- Bypass CV, to BYPASS AND RECORD_stop time in the CVCS Ion Exchanger and Filter Log. [B0018] [B0270] RO will log stop time 0 6.6.B.2 - IF two Component Cooling pumps are in service THEN STOP the selected Component Cooling Pump. Determines step is N/ A CAUTION When 13 Component Cooling Pump is running, the associated Component Cooling Pump n aligned to the same power supply shall be placed in PTL. This is to prevent all three pumps from running on a SIAS signal without a UV signal, which could damage the tubes and/or baffle plates ofthe SDC Heat Exchangers. This Caution is NOT applicable when less than three Component Cooling Pumps are available. [B0590]

0 6.6.B.3- IF 13 Component Cooling Pump is running and aligned to 11 480 V Bus, AND 11 and 12 Component Cooling Pumps are in AUTO, THEN PLACE 11 Determines step is N/ A Component Cooling Pump in PTL. [B0590]

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD 0 6.6.B.4 - IF 13 Component Cooling Pump is running and aligned to 14 480 V Bus, AND 11 and 12 Component Determines step is N/ A Cooling Pumps are in AUTO, THEN PLACE 12 Component Cooling Pump in PTL. [B0590]

0 6.6.B.5- IF 13 Component Cooling Pump is NOT running, THEN ENSURE all available Component Same as element Cooling Pumps are in AUTO.

CAUTION Two CC Pumps SHALL NOT be operated with only one CCHX aligned for service, unless for a very short period of time as in bumping a pump or momentary pump shifting.

, J t.lle Com:ponerit G<iJoUng'l1I~a~'ixchan

, . . . J'ieat exchanger being temoveq fio~ servi Shuts 1-CC-3824-CV

- ~! ~t.l'f~~~,.ec.,oiJ't, :l-c~~s8i4~¢Y.. .

'i i;ir l:Q GGHX,CC

' c ,. ,. '1, ,, ' " "'~'

OUT~

1-GG-3826~CV 4 NOTE:

To minimize biological growth in the Saltwater System, Saltwater flow should NOT be aligned to BOTH in-service CCHXs during low heat conditions, unless required to maintain SW PP minimum flow requirements.

iJ~~~!1f~t~f=~~~

'; rerno¥eq ftmn servwe: .. . .*. .. *. . ,. ***.. ... ,

1

~1"(N/~.\~iJ:e~flec1Jl~EN to tnaintl;rip, SW PP*niiriim;pn;l flow)>

Shuts 1-HIC-5206

1>l*COMP CLG HX SALTWAtER)<LoJV:co~rrR:;...

':( li't.Ifle'-5:206 \ ' . . ' . ;; .* ,, ::* : '" .

... '*. . . *i:: :.. :.j:.:fliG-5208 1'2 COMP CLG HX SALTWATER FtCl\V'GONTR,"*

NOTE:

For optimum Reactor Coolant Pump seal life and performance, controlled bleed-off temperature must be maintained between 11 0°F and 180°F.

Maintaining RCP OUT TEMPs at approximately 100°F on 1C 13 will ensure optimal seal life and performance, as well as maintain RCP CBO temperatures between 11 0°F and 180°F.

0 6.2.B.&- ADJUSTthe in-service CCHX SW outletCV to maintain approximately 100°F on the RCP outlet' Monitors CC temperature temperature .indications on 1C 13. and opens 1-HIC-5208 to

11 COMP CLG HX SALTWATER FLOW CONTR, some minimum value 1-HIC-5206 (approximately where OR 1-HIC-5206 was

-.-12 COMP CLG HX SALTWATER FLOW CONTR, previously positioned) 1-HIC-5208

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD CAUTION:

RCS boron concentration will be affected when CVCS ion exchangers are returned to service if the Letdown heat exchanger outlet temperature has changed since they were bypassed.

[B0270]

Lower Letdown system temperature will add positive reactivity.

Higher Letdown system temperature will add negative reactivity.

CUE tThe RO will log start time in the CVCS Ion Exchanger and Filter Log 0 6.2.B.9- IF the CVCS ion exchangers were bypassed in Step B.1, THEN PERFORM the following:

0 6.2.B.9.a.- CHECK the Letdown heat exchanger outlet temperature has stabilized less than or equal to 120DF.

Same as element 0 6.2.B.9.b.- PLACE IX BYPASS, 1-CVC-520-CV, to AUTO.

0 6.2.B.9.c.- RECORD the flowrate in the CVCS Ion Exchanger and Filter Log for the in service ion exchanger and filter. [B0018]

TERMINATING CUE: This JPM is complete when 11 CCHX is removed from service. No further actions are required. The examinee is expected to end the JPM.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SIM-7 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Q u e s t i o n : - - - - - - - - - - - - - - - - - - - - - - - - -

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT _ _ _ _ _ ___

Examiner's Signature and Date: --------------------~

Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET Initial Conditions:

1. Both Units are at 100% power

2. 11 & 12 Component Cooling Heat Exchanger are in service.

Initiating Cue:

You are performing the duties ofUnit 1 CRO. The CRS directs you to secure 11 Component Cooling Heat Exchangers IA W the Operating Instruction in preparation for tagging out 11 Salt water Header.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: SIM-8

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: SIM-8 Task

Title:

Test Gaseous Waste Discharge RMS Channel RI-2191 Task Number: 079.018 KIA

Reference:

071A4.09 (3.3, 3.5)

Method of testing:

Simulated Performance: D Actual Performance: [SI Classroom: D Simulator: [SI Plant: D Read to the examinee:

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

Initial Conditions:

1. Both Units are at 100% power

2. You are performing the duties of an extra Licensed Operator.

3. A pre-job brief has been completed for the performance of STP-0-101-0 Gaseous Waste Discharge RMS Channel RI-2191, Semi-Annual Functional Test.

4. The Prerequisites, Section 4.0 of STP-0-1 01-0, have been completed Initiating Cue:

The Unit-1 CRS directs you to complete performance ofSTP-0-101-0, Gaseous Waste Discharge RMS Channel RI-2191, Semi-Annual Functional Test, beginning with a review of the Precautions, Section 5, and continuing through Section 6.1, Functional Test OfRMS Channel RI-2191.

Task Standard:

Successfully complete STP-0-1 01-0 Sect. 6.1.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

STP-0-101-0, Gaseous Waste Discharge RMS Channel RI-2191, Semi-Annual Functional Test General

References:

Procedures and manuals normally available in the control room Time critical task:

No Validation Time:

15 minutes Simulator Setup:

1. Reset to IC-24, both units at 100% power

2. Place simulator in RUN.

3. Acknowledge all panel and plant computer alarms.

4. Ensure the "HORN ON" is selected for annunciators.

5. Place in FREEZE.

6. When cued by evaluator, go to RUN.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded =CRITICAL STEP) STANDARD TIME START: _ __

CUE* Provide candidate with a marked up copy of STP-0-101-0, Gaseous Waste Discharge

RMS Channel RI-2191, Semi-Annual Functional Test 6.1- Functional Test ofRMS Channel RI-2191 CUE* ABO reports Waste Gas Discharge Filter Outlet Isolation, 0-WGS-629 is SHUT and has

been peer checked 0 6.1.A. -[PC] SHUT Waste Gas Discharge Filter Outlet Requests ABO to shut valve Isolation, 0-WGS-629. and obtain a peer check.

CUE: ABO reports Waste Gas Discharge Filter Outlet Isolation, 0-WGS-630 has been checked shut.

0 6.1.B.- CHECK SHUT Waste Gas Discharge Filter Bypass, Requests ABO to shut 0-WGS-630. valve.

0 6.1.C.- OPEN the following valves at 1C33:

Same as element.

0. 6.1 .D -PLACE the operation~e,l~<;tors~tch for9f3:seous Same as element.

Discharge RMS o~l~l-2191 to CHECKSE>WRCE~

0 6.1.D.l - CHECK proper channel response by observing Same as element.

upscale meter deflection.

0 6.l.E.- PLACE GaseousWasteDischal:g~Ch~tmelO-RI-2191 operation selector switch to PULSE C~Flf\.ND CHECK the Same as element.

following:

0 6.1.E.l.- 0-RI-2191 Channel HIGH ALARM light Same as element.

illuminated.

0 6.1.E.2.- "0-RE-2191", RMS STATUS PNL 1C22H, Same as element.

amber light (ALARM) illuminates.

0 6.1.E.3.- 1C17 "RAD MON PANEL 1C22" annunciator Same as element.

alarms.

0 6.1.E.4.- 0-WGS-2191-CV shuts. Same as element.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded =CRITICAL STEP) STANDARD 0 6.1.E.5.- 0-WGS-2192-CV shuts. Same as element.

0 6.1.F.- POSITION the following handswitches as follows: Same as element.

Same as element.

6tl.G. -PLACE o Iffi~ET.

': ,".:.[:~ ,

thenJo

, ,~, -;_\S/

o*~,, . .,..."'

Same as element.

0 6.1.0.1. -CHECK 1C17 "RAD MON PANEL 1C22" Same as element.

annunciator clears.

0 6.1.0.2. - CHECK HIGH ALARM and RMS Status Same as element.

lights extinguished.

Same as element.

0 6.1.H.l.- 0-RI-2191 Channel LOW ALARM light Same as element.

illuminated.

0 6.1.H.2.- "0-RE-2191 ", RMS STATUS PNL 1C22H, Same as element.

amber light (ALARM) illuminates.

0 6.1.H.3.- 1C17 "RAD MON PANEL 1C22" annunciator Same as element.

alarms.

(J 6JJ.- PLACE ope~~tJorl~ele9t~i'~}Yit6~:for 0-RI-2191 to Same as element.

OPERATEaml CIIE~~the'~foll6Wing: ****.

' . ~' ,' ~"" y,-; ;*, < '

0 6.1.1.1.- CHECK 1C17 "RAD MON PANEL 1C22" Same as element.

annunciator clears.

0 6.1.1.2.- CHECK LOW ALARM and RMS Status lights Same as element.

extinguished.

NOTE TO EVALUATOR Simulator equipment is not modeled such that Steps "J" and "K" can be completed as written.

Cues are provided to have the candidate omit the performance of Step "J" and to perform only the applicable portion of Step "K" CUE: Step 6.1.1 & K. is to be skipped in its entirety.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded =CRITICAL STEP) STANDARD 0 6.1.1.- DEENERGIZE 0-RI-2191 Channel by removing one Step skipped per Evaluator of the fuses from the drawer front at 1C22. CUE Step skipped per Evaluator 0 6.l.K. - INSTALL the fuse removed in the previous step.

CUE 0 6.1.K.l.- PLACE operation selector switch for 0-RI-2191 Step skipped per Evaluator to RESET, then to OPERATE. CUE 0 6.1.K.2.- CHECK 1Cl7 "RAD MON PANEL 1C22" Step skipped per Evaluator annunciator clears. CUE 0 6.l.K.3. - CHECK normal operation of 0-Rl-2191 by Step skipped per Evaluator observing normal channel behavior. CUE.

0 6.l.L. - CHECK all RMS channels to ensure no new alarms Same as element.

actuated during th!s test.

ABO reports Waste Gas Discharge Filter Outlet Isolation, 0-WGS-629 is OPEN and has CUE:

been peer checked 0 6.1.M.- [PC] OPEN 0-WGS-629. Same as element.

TERMINATING CUE: This JPM is complete when the candidate receives the report stating "0-WGS-629 is OPEN and has been peer checked". No further actions are required. The evaluator is expected to end the JPM.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: SIM-8 Applicant: II +I_ _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts; +-----------------

Time to Complete:

1 Follow up Question: - - + - - - - - - - - - - - - - - - - - - - - - - - - -

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT - - - - - - - UNSAT - - - - - - - - - -

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEE'S CUE SHEET Initial Conditions:

5. Both Units are at 100% power

6. You are performing the duties of an extra Licensed Operator.

7. A pre-job brief has been completed for the performance of STP-0-1 01-0 Gaseous Waste Discharge RMS Channel RI-2191, Semi-Annual Functional Test.

8. The Prerequisites, Section 4.0 of STP-0-1 01-0, have been completed Initiating Cue:

The Unit-1 CRS directs you to complete performance ofSTP-0-101-0, Gaseous Waste Discharge RMS Channel RI-2191, Semi-Annual Functional Test, beginning with a review of the Precautions, Section 5, and continuing through Section 6.1, Functional Test OfRMS Channel RI-2191.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #:PLANT-I

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-I Task

Title:

Align the Reserve Battery to 11 DC Bus Task Number: XXXXXX KIA

Reference:

058 AA1.03 (3.1, 3.3)

Method ofT esting:

Simulated Performance: ~ Actual Performance: 0 Classroom: 0 Simulator: 0 Plant: ~

Read to the examinee:

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

Initial Conditions:

1. You are performing the duties an extra Licensed Operator.

Initiating Cue:

The Control Room Supervisor has directed you to align the Reserve Battery to 11 DC Bus per OI-26A, Section 6.10. Are there any questions? You may begin.

Task Standard:

Locates and simulates manual operation of plant components to align the Reserve Battery to 11 DC Bus, per OI-26A, Section 6.1 0.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

OI-26A, 125 Volt Vital DC General

References:

OI-26A, 125 Volt Vital DC Industrial Safety Manual Chapter 12, Electrical Safety Time critical task:

No Validation Time:

12 minutes Simulator Setup:

None

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START:

0 6.10.A- INITIAL CONDITIONS All Initial Conditions have been completed. The Reserve Battery is available for use on 11 125 VDC Bus, Tech Specs 3.8.4 and 3.8.1 have been reviewed for applicability, Risk CUE:

level change has been reviewed (Risk goes from Green to Yellow) and the pre-job briefing has been completed.

0 6.1 O.A 1 -The Reserve Battery is available for use on 11 125 VDC Bus 0 6.10.A 2 -The following Tech Specs have been reviewed for applicability for both units:

3.8.4 DC Sources-Operating

3.8.1 AC Sources-Operating 0 The Risk Level change has been reviewed and briefing completed.

NOTE TO EVALUATOR Candidate should determine PPE requirements using the Industrial Safety Manual, Chapter 12.

For Operating disconnects with enclosure doors closed (opening and closing) the following are required:

No Minimum Arc Rating Required for FR Clothing 100% Cotton Long Sleeve Shirt and Pants, OR 100% cotton short sleeve shirt and pants under FR Lab Coat Safety Glasses NOTE Ask candidate where and how to obtain the Kirk keys for the Disconnect Switches to be operated. Candidate should describe the process of signing out the keys from the Operations Work Control SRO whose office is located in the North Service Building 0 6.1 O.B - PROCEDURE CUE: Inform candidate they have obtained the required keys from the OWC Office 0 6.1 O.B.1 - OBTAIN the Kirk keys for Disconnect Switches ISC1D67-1 RESERVE BATTERY TO DC Same as element BUS 11 and ODISC1D67-2 RESERVE BATTERY TO DC BUS 11 from OWC.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD NOTE Annunciator U-16 11 12 BATT OPEN CIRCUIT DISCONNECTED at 1C34 may alarm.

Acknowledge candidates request for a Peer Check Same as element CUE: Acknowledge candidates request for a Peer Check 0 6.1 O.B.3 - [PC] ENSURE ON Disconnect Switch ODISC1D50 125V BATTERY 01 DISC SW (Located on Same as element Panel 1D50).

CUE: Acknowledge candidates request for a Peer Check

~.-HJ:(;]I::PL~(::E:OHS1D5A ,l25V BATTERY 01 Same as element

~*fr~?~~ted*pn PailelJDSA) toLOAD position.'

NOTE The Kirk Keys are captured when the interlock for ODISC1D67-1 and ODISC1D67-2 have been removed and the disconnects are closed.

~\\> ;{~1,~~:-~/~ {: ,:}2; ~."; L '. \' "

.J?~~ ~r:J,NSE~ll<~tk Key into Disconnect

r"~ " ~* *.

1

@rb61-l RESERVE* BATTERY TO DC Same as element

- - . ftj~neiOPNLID67).

Same as element

~' ~0 ~' .': ~?e.',~{ i+: :Nt~' ;,., *C' ' ,,'. * * ' < * ' ' '

.Q. (Jll().B.7,,;'~'R'0TA1?Etlle:Kirk Key for DisconnectSwitch*

.* *. i*Op~~~i'b6~tl;T$1~SJ3RVE BATTERY TO DC BUS I 1 Same as element

'1,8(} qegrees

~*- ' .. "';. 1:*

in tb,e . "" '

clockwise direction.

Cl *6.10.R~*~~OT~TEilieK.irk Key for Disconnect Switch

'0DISCID61~iltl3SERVE BATTERY TO DC BUS 11 Same as element 180 degree.sifi the clockwise direction.

Acknowledge candidates request for a Peer Check

Appendix C Job Performance Measure Worksheet Form ES-C-1 STANDARD Same as element Acknowledge candidates request for a Peer Check

)1~~\~~~~~;~;~~d&(U'¥' Same as element TERMINATING CUE: This JPM is complete when the Reserve Battery is aligned to 11 DC BUS per OI-26A, Section 6.1 0. No Other Actions Are Required. The student is expected to this JPM.

I TIME STOP:---

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

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT _ _ _ _ __ UNSAT --------

Examiner's Signature and Date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Appendix C Job Performance Measure Form ES-C-1 Worksheet EXAMINEE'S CUE SHEET Initial Conditions:

1. You are performing the duties of an extra Licensed Operator Initiating Cue:

The Control Room Supervisor has directed you to align the Reserve Battery to 11 DC Bus per OI-26A, Section 6.1 0. Are there any questions? You may begin. Are there any questions?

You may begin.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT -2 (Alt Path)

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-2 (Alt Path)

Task

Title:

Locally Operate the MSIVs Task Number: 083.024 KIA

Reference:

2.1.30 (4.4, 4.0)

Method of testing:

Simulated Performance: ~ Actual Performance: 0 Classroom: 0 Simulator: 0 Plant: ~

Read to the examinee:

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

Initial Conditions:

1. A severe fire has resulted in a Control Room evacuation.

2. You are performing the duties ofthe Unit-2 ABO

3. You have obtained the Safe Shutdown key ring and equipment from the Safe Shutdown Key and Equipment Lockers.

Initiating Cue:

You have just completed Step "Y" and are directed, by AOP-9A, to go to the MSIV Room to perform Step "AC", Verify MSIVs are Shut.

Are there any questions? You may begin.

Task Standard:

Verifies MSIVs shut per AOP-9A Step IV.AC

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

AOP-9A-2, Control Room Evacuation and Safe Shutdown Due To A Severe Control Room Fire Key to Safe Shutdown hose locker General

References:

AOP-9A-2, Control Room Evacuation and Safe Shutdown Due To A Severe Control Room Fire Time Critical Task:

No Validation Time:

15 minutes Simulator Setup:

None

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START: _ __

NOTE Candidate should comply with all RP procedures and policies for entering the RCA.

CUE* Once the candidate describes how they would obtain a copy of the procedure provide

them with a copy of AOP-9A-2, Block Step IV.AC.

0 Locates AOP-9A-2, Block Step IV.AC. Same as element 0 Candidate proceeds to U-2 MSIV Room Same as element (27' Aux Bldg)

AC. VERIFY MSIVS ARE SHUT CUE: 2-IA-928, IA to 21 MSIV Hydraulic Pump, is shut.

, *,* . *.. ' <,: /... h*~~ ?';,'\ i~i" ;,;" *. . *. * * , Simulates rotating ball valve

0. AC.l .* Shutlnstnu:hent1Xt~*I atio:tito~l MSIVHydraulic' handle 90 ° to the shut I . Pump, 2-IA-92Sii;: , ':<: *)~ . . . . . . .**.. position

*.*. * .. ~.;_*,-'-'~li"'-----'------'------------------1 CUE: !21 MSIV is OPEN (as indicated)

. . . . . .. . C:*z :'*< itv: *. .

0, AC.2. -IF 21*MSIV ~~;on~n,'T.BEN~* H ' '*o';, .,,. -

0 AC.2.a. '" Remove 1;l,1e pfiJ!ip Sbleho\d Valve Cap on ONE ofthe folloWing: .... * .,*;.. ~~*i

' *

Locates and simulates the removal of cap from either o 2l,MSlYDump"sV'";cfianD.elA~

2-MSH-4042A-SV or 2-2-MSH~4042AtS\t'. , .

MSH-4042B-SV located on OR underside of MSIV 21 o 21 MSIV Dump 2-MSH-4042B-SV . . . .

sv Cha,nndi B/

' c; I **

0 AC.2.b. - Place a wrench on the selected Dump Solenoid Simulates specified stem nut. element.

CUE: 21 MSIV goes shut when hydraulic fluid pressure is bled off 0 AC.2.c- Rotate the wrench in the clockwise direction (approximately five turns) to bleed hydraulic fluid back Simulates specified element.

to the reservoir.

CUE: 2-IA-930. IA to 22 MSIV Hydraulic Pump. is shut.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded = CRITICAL STEP) STANDARD

' < ' ;.; * * *] * {~;. < ' ., < ;:,,.,, **** *... <

Simulates rotating ball valve 0 AC.3~ .,.Shut:~tiliniln~A:it-J~olationto 22 MSIV Hydraulic PumP; 2-I~1Q3.@\l.l ¥£il41,*.<,~7 . *. . . . . . .. . handle 90° to the shut position

..... >i j : .. i':! ,f:..*;. 1:; * **.

CUE: !22 MSIV is SHUT 0 AC.4. - IF 22 MSIV is open, THEN: Determines step is N/ A AC.S.- Notify 2C43 the MSIVs are shut. Same as element TERMINATING CUE: This task is complete when steps AC.l thru AC.5 have been completed. Task completion will be signaled by the evaluator. No further actions are necessary.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: PLANT -2 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Applicant Response: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Result: SAT - - - - - - - UNSAT - - - - - - - -

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEE'S CUE SHEET Initial Conditions:

1. A severe fire has resulted in a Control Room evacuation.

2. You are performing the duties of the Unit-2 ABO

3. You have obtained the Safe Shutdown key ring and equipment from the Safe Shutdown Key and Equipment Lockers.

Initiating Cue:

You have just completed Step "Y" and are directed, by AOP-9A, to go to the MSIV Room to perform Step "AC", Verify MSIVs are Shut.

Are there any questions? You may begin.

APPLICANT: _ __

CALVERT CLIFFS NUCLEAR POWER PLANT 2014 NRC INITIAL LICENSED OPERATOR EXAM JPM #: PLANT-3

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: Calvert Cliffs 1 & 2 Job Performance Measure No.: PLANT-3 Task

Title:

Startup the Instrument Air System using the Fire Main for Compressor cooling Task Number: 019.014 KIA

Reference:

2.1.30 (4.4, 4.0)

Method of testing:

Simulated Performance: [g) Actual Performance: 0 Classroom: 0 Simulator: 0 Plant: [g)

Read to the examinee:

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

Initial Conditions:

1. Unit-1 is in Mode 3.

2. 11 Instrument Air Compressor is in service.

3. The Fire System Booster Jockey Pump is in Auto.

4. Service Water System maintenance requires isolating Service Water to the Unit-1 Instrument Air Compressors.

5. You have received your pre-job brief from the CRS and are perfonning the duties of an extra TBO qualified operator.

Initiating Cue:

The CRS directs you to align the Fire Main for Compressor Cooling to the Instrument Air Compressors per OI-19 Section 6.4.

Task Standard:

Correctly aligns the Fire Main to Air Compressors IA W OI-19

Appendix C Job Performance Measure Worksheet Form ES-C-1 Evaluation Criteria:

1. All critical steps completed (denoted by shading).

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Critical Step Basis:

Critical steps are those that when not performed correctly, in the proper sequence, and/or at the proper time, will prevent the system from functioning properly or preclude successful completion of the task.

Required Materials:

OI-19, Instrument Air, Section 6.4, System Operation Using Fire Main for Compressor Cooling General

References:

Procedures and manuals normally available in the Control Room Time Critical Task:

No Validation Time:

15 minutes Simulator Setup:

None

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD TIME START:

0 Identify & locate 01-19, Section 6.4 Same as element ALL initial conditions and precautions are met. Proceed to Step 6.4.B. A Fire System CUE:

Use Permit has been obtained.

OI-19, System Operation Using Fire Main For Compressor Cooling, Section 6.4.B Determines from Cue that a 0 6.4.B.1.- OBTAIN a Fire System Use Permit. Fire System Use Permit has been obtained.

0 6.4.B.2. - ALIGN the Fire Booster Pumps as follows:

0 6.4.B.2.a. -PLACE BOOSTER JOCKEY PUMP FIRE Same as element.

PROT/SYS, 0-HS-9600, in AUTO.

CUE: WHEN requested, acknowledge as OSO that 0-HS-6227 has been placed in PTL.

0 6.4.B.2.b.- PLACE MAIN PRESSURIZER #13, Requests the OSO or F ASW 0-HS-6227 in PTL. to place 0-HS-6227 in PTL.

WHEN each valve is operated properly report stem has lowered and valve travel has CUE:

stopped.

0 6.4.B.3.- SHUT the following valves AND MONITOR AFW room temperature PER TBO log notes: Locates each valve and shuts it. Initiates AFW Pp 0 INLET TO AUX FD PP RM CLR, 1-SRW-502. RM temperature monitoring.

D OUT FROM AUX FD PP RM CLR, 1-SRW-503.

NOTE:

Compliance with MN-1-11 0, PROCEDURE CONTROLLED ACTIVITIES, is required when using temporary hose connections.

The supply and discharge fire hoses are located in the AOP/EOP locker outside the SRW Room.

Locates AOP/EOP locker 0 6.4.B.4.- ALIGN Fire Main to supply cooling water to the containing required fire Instrument Air Compressors as follows:

hoses.

0 6.4.B.4.a.. - CONNECT a fire hose to the nearest available Fire Hose Station adjacent to AUX WTR SUPP TO Same as element I&P/A COMPR, 1-SRW-182.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD Once Fire Main Supply to the hose has been simulated to be cracked open: a clear CUE:

stream of water is being discharged from fire hose.

0 6.4.B.4.b.- CRACK OPEN Fire Main Supply to the hose Flushes the Fire Hose until connected in Step above AND purge fire main to a drain clear water is discharged until clear water is discharged AND THEN SHUT the and then shuts valve.

supply valve.

EVALUATOR NOTE 1-SRW-182 and fire hose pipe connection is located above 11 lAC north end.

CUE* WHEN valve is operation is properly simulated report: stem has risen and valve travel

has stopped and hose is pressurized.

. i ~Pl6:4.s~~Jr;.. ~P:Ji:l1 te :rire Main Supply valve at the Fire Same as element

\; lfose§tlitiorf;~Jlat wa$.corlneeted to in step 4.a.

' * ' * *, ' ;*',.~" ; ; ; 'c 0* ; ,-..*' * * ' * '

Same as element 0 6.4.B.4.f.- ENSURE the open end of the Fire Hose just connected is DIRECTED to a floor drain and properly Same as element secured.

CUE* WHEN requested, acknowledge, as other TBO, the request to verify that hoses have

been connected properly.

0 6.4.B.4.g. - ENSURE that another TBO qualified operator Same as element INDEPENTLY VERIFIES the hoses connected properly.

0 6.4.B.4.h.- LOG the connection of hose in the Turbine Verbalizes logging the Building Operator's Log hose connections in the TBO Log.

CAUTION:

Steps 4.i, 4j, 4.k and 4.1 must be completed in a timely manner due to the Fire Main and Service Water System being cross-connected.

EVALUATOR NOTE 1-SRW -184 is located above 11 lAC north end.

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD WHEN valve is operation is properly simulated report: Stem has risen and valve travel CUE:

has stopped.

< ,!l)~ 4z<~[D.i.if~i"~~VJS \\1TR FROM I & PIA DiSCH Same as element

><. * **fOMrR~'bi;S *. 84,.. * . . . .

EVALUATOR NOTE 1-SRW-182 is located above 11 lAC north end.

WHEN valve is operation is properly simulated report: stem has risen and valve travel CUE:

has stopped.

I'

'~ ~4:It;<~~J\~ Alf"\\1TR SUPP To 1 & PI~ CoMPR, Same as element

, *1-SRW-1 * *

EVALUATOR NOTE 1-SRW-181 is located above and northeast of 11 lAC.

WHEN valve is operation is properly simulated report: stem has lowered and valve CUE:

travel has stopped.

- .j. : .. :*.****.>* .. *. *'rd.':<: . *

.. *m:,~t~~::;~~i~:VSUPPHDRSTOP'{OI&P/A Same as element EVALUATOR NOTE 1-SRW-183 is located above 11 lAC north end.

WHEN valve is operation is properly simulated report: stem has lowered and valve CUE:

travel has stopped.

[J 6.~;B:t4*F~ SI!JY! SR.W DISCH HDR STOP FROM I & Same as element PIA COMPR, J~SRW-183.

CUE: 11 Instrument Air Compressor is running.

0 6.4.B.5. -IF the Instrument Air Compressors are shutdown, Determines step is N/A THEN START the Instrument Air Compressors as follows from Initiating Cue .

Appendix C Job Performance Measure Worksheet Form ES-C-1 ELEMENT (shaded= CRITICAL STEP) STANDARD NOTE

Optimal Service Water return temperature is 11 oo F . SRW Return Temperature will be lower during colder months.

The IA Compressor TCV bypass valve SHALL be a minimum of Yz-turn open under all normal operating conditions.

Using your pen/pencil or a laser pointer place on meter to indicate approximately 112° F CUE:

allowing operator to interpret value.

D 6.4.B.6. -IF an Instrument Air Compressor is running, Identifies proper TI and recognizes THEN MONITOR the Service Water Outlet SRW outlet temperature is in the Temperature maintaining at 11 oo F (+ 10° F) normal range.

Acknowledge report that fire main water may have been introduced into the SRW CUE:

system D 6.4.B.7.- NOTIFY Chemistry that fire main water Same as element may have been introduced into the SRW system.

TERMINATING CUE: This JPM is complete when the Fire Main has been aligned for Compressor Cooling and 11 Instrument Air Compressor Service Water Outlet Temperature has been checked. No further actions are required.

I TIME STOP:---

Appendix C Job Performance Measure Worksheet Form ES-C-1 Verification of Completion Job Performance Measure Number: PLANT -3 Applicant:

NRC Examiner:

Date Performed:

Facility Evaluator:

Number of Attempts: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Time to Complete:

Follow up Question:

Applicant Response: - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Result: SAT _ _ _ _ __ UNSAT - - - - - - - - - - - - - - -

Examiner's Signature and Date:

Appendix C Job Performance Measure Worksheet Form ES-C-1 EXAMINEE'S CUE SHEET Initial Conditions:

1. Unit-1 is in Mode 3.

2. 11 Instrument Air Compressor is in service.

3. The Fire System Booster Jockey Pump is in Auto.

4. Service Water System maintenance requires isolating Service Water to the Unit-1 Instrument Air Compressors.

5. You have received your pre-job brief from the CRS and are performing the duties of an extra TBO qualified operator.

Initiating Cue:

The CRS directs you to align the Fire Main for Compressor Cooling to the Instrument Air Compressors per 01-19 Section 6.4.

Appendix D Scenario Outline Form ES-D-1 Facility: Calvert Cliffs Nuclear Power Plant Scenario #: 1 OP-Test #: CCNPP 2014 Examiners: Operators:

Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is in Mode 1.

Turnover: 12 MSL and N-16 Monitors, 12 AFW Pump, and the 1B DG are OOS. The OC DG is aligned to 14 4KV Bus per OI-21B. 11 Charging Pump is the lead pump. Instructions for the crew are to maintain power at 100%

Event# Malfunction # Event Type* Event Description 1 152-1206 C- BOP/SRO 11 Heater Drain Pump trip I- ATC 2 rcs026 01 1-LT-110X (selected channel) fails LOW T- SRO 3 srw002 02 M-ALL 12 SRW Header leak in Turbine Bldg 4 fw006 02 C- BOP/SRO 12 MFRV fails as is (mechanical binding) cedsOlO 19 CEAs 19 and 32 fail to insert on Reactor trip. (Boration 5 R-ATC ceds01 0 32 using normal path) 6 swyd002 C-ALL Complete Loss of Offsite Power C- BOP/SRO 7 dg002_02 1A DG Start Failure T-SRO

(N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec Critical Tasks: (shaded)

1. Notes two CEAs faih:~cfto insert, collll!lences RCS boration before exit ofEOP-0.

2. Notes excessive Feed Flow, secures main feed & initiate auxiliary feed before exit ofEOP-0

3. Reenergizes a 4kV Bus with the OC DIG prior to 125 VDC voltage< 106V.

Page 1 of20

Appendix D Scenario Outline Form ES-D-1 OP-Test #: 2014 Scenario#: 1 SCENARIO OVERVIEW SRW LEAK IN TURBINE BLDG I LOSS OF OFFSITE POWER Units 1 and 2 are operating at 100% power. 12 MSL and N -16 Monitors, 12 AFW Pump, and the 1B DG are OOS. The OC DG is aligned to 14 4KV Bus per OI-21B. 11 Charging Pump is the lead pump.

First, a trip of 11 HDP occurs causing crew to implement AOP-3G. The crew should control maximize SGFP suction pressure by bypassing precoats and demins. The crew should start the 3rd Condensate Booster pump then exit AOP-3G.

Next, the selected PZR level control channel will fail LOW requiring the crew to shift channels to regain plant control.

After these actions are completed, a large SRW leak will initiate in the turbine building and the crew will have to isolate turbine building SRW and trip the reactor. Two CEAs will fail to insert on the reactor trip and 12 S/G MFRV will fail to 30% open. Approximately 2 to 3 minutes after the trip, a loss of offsite power will occur. During EOP-0 the ATC is expected to commence boration for the 2 stuck CEA's per the Reactivity Control Plaque. The BOP should recognize that 12 MFRV has failed to close and take action per the Heat Removal Plaque and secure main feed and initiate auxiliary feed.

The crew is expected to initially implement EOP-2. Upon entry into EOP-2, the 1A DG is lost requiring the crew to reenergize 14 4KV bus with the OC DG. If unable to restore power to any 4KV bus the crew will transition to EOP-7, Station Blackout. If plant conditions degrade or the crew is unsure of the diagnosis it is acceptable for them to enter EOP-8. If EOP-8 is entered all critical tasks still apply unless individual tasks are invalidated by the exam team.

Scenario ends after OC DIG aligned to 14 4KV bus.

Page 2 of20

Appendix D Scenario Outline Form ES-D-1 INSTRUCTOR SCENARIO INFORMATION:

1. Reset to IC-24

2. Perform "Switch Check"

3. Place simulator in RUN, advance charts and clear alarm display.

4. Place simulator in FREEZE.

5. Enter Triggers:

a. None

6. Enter Malfunctions:

a. #12 AFW Pump Tripped: afw001_02 at time zero

b. #1B DG Start Failure: dg001_02 at time zero

c. Stuck CEA # 19: ceds010 19 at time zero

d. Stuck CEA # 32: ceds010 32 at time zero

e. 11 Heater Drain Pump trip: 152-1206 to TRIP on Event 1.

f. PZR lvl control channel1-LT-110X fails: rcs026 01 to LOW on Event 2.

_ _ g. 12 SRW Hdr Turb Bldg leak: srw002_02 at 30%, with a 3 minute ramp time, on Event 3.

h. Complete Loss of Offsite Power: swyd002 on Event 4.

1. 1A DG Start Failure: dg002_02 on Event 5

7. Enter Panel Overrides:

a. 12 AFW PP TURB TRIP SW: P1C04- 1HS3988- LTWHIT to OFF at time zero.

b. 12 AFW PP TURB TRIP SW: P1C04- 1STP3988- LTRED to OFF at time zero.

c. 12 AFW PP TURB TRIP SW: P1C04- 1STP3988- LTWHI to OFF at time zero.

d. Mn Stm EffRMS Alarm window: P1C03 C43 LTON to Off at time zero.

e. Mn Stm N-16 RMS Alarm window: P1C03 C47 LTON to Off at time zero.

Page 3 of20

Appendix D Scenario Outline Form ES-D-1

8. Enter Remote Functions I Administrative:

a. 189-1406 (DGOC BUS 14 DISC) to CLOSED at time zero and place a pink tag on control room indication for disconnect.

b. Non-Essential4KV Motor Overload P1C17- L19- LTON to ON on Event 1

c. 12 S/G MFRV: 1-FW-1121-CV to 30% on Event 10

d. Create Event Trigger file:

1. PZR Level <160" as Event 10

e. Tie MCC-104 to MCC-114 as follows:

1. 52-10401 (FDR to MCC 104R) to OPEN as Event 7.

2. 52-10420 (MCC TIE 104R TO 114R/INTERLOCK) to CLOSED with a 30 second delay as Event 7.

f. Tie MCC-114 to MCC-104 as follows:

1. 52-11401 (FDR TO MCC 114R) to OPEN as Event 8.

2. 52-10420 (MCC TIE 104R TO 114R/INTERLOCK) to CLOSED with a 30 second delay as Event 8.

_ _ g. 12 MSL and N-16 Rad Monitors to OFF using the key switch on the monitors (Key stored in lock box by simulator conference room door)

h. Ensure PZR level control handswitch, 1-HS-11 0, selected to X on panel 1C06.

1. Place Yellow Tag on 12 AFW Pump.

_ _ ]. Place Yellow Tag on 1B DG start pushbutton.

k. Place 1B DG OUT BKR, 1-CS-152-1403, in PULL-TO-LOCK and caution tag handswitch.

1. Place pink tags on the OC DG feeder breakers to 4KV Buses 11, 21, & 24.

m. Place a Blue Dot on 1C03 Alarm Window C-43 & C-47

_ _ n. Check all magnetic plaques are correct.

_ _ 9. Independently verify correct completion of the following:

a. Malfunctions and Event Triggers correctly entered

b. Panel Overrides correctly entered

c. Remote Functions I Administrative actions correctly entered/performed

10. Select "Clock" time and ensure "Horn On" for annunciators.

Page 4 of20

Appendix D Scenario Outline Form ES-D-1

11. Place simulator in RUN and reset/acknowledge panel and plant computer alarms.

12. Briefthe Crew:

1. Present plant Unit-1@ 100% power MOC (10,885 MWD/MTU) conditions: Unit-2@ 100% power EOC (17,800 MWD/MTU)

2. Power history: 100% power for previous 128 days

12 AFW Pump for past 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for bearing

3. Equipment out of replacement (back in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ).

serv1ce:

1B DG for cylinder work (back in 1 day), OC is pre-aligned to 14 4KV bus

4. Abnormal conditions: None

5. Surveillances due: OI-49 in 4 hrs.

6. Instructions for shift: Maintain 100% power per OP-3.

13. Allow crew 3 to 5 minutes to walk down control panels.

14. Instructions for the Booth Operator:

a. Activate Event 1 trip of 11 Heater Drain Pump, when cued by Lead Evaluator.

b. Activate Event 2, 1-L T -11 OX failure when cued by Lead Evaluator.

c. Activate Event 3, 12 SRW Header leak in the Turbine Bldg, when cued by Lead Evaluator.

d. Ensure Event 10 triggered, 1-CV -1121 failure, immediately upon reactor trip.

e. Activate Event 4, Complete Loss of Offsite Power after EOP-0 Alternate Actions for excessive feed flow have been completed (AFW flow initiated, SGFPs tripped and MFIVs shut) due to the stuck open MFRV, when cued by Lead Evaluator.

f. Activate Event 5, 1A DG start failure, after implementing EOP-2, or when cued by Lead Evaluator.

15. Post Session- Restore panels to as found conditions by removing administrative aids applied to panels per step 7 (Enter Remote Functions I Administrative).

Page 5 of20

Appendix D Scenario Outline Form ES-D-1 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.

'j~

,, ,\ ,,,

~~~~~>

. '(. ', . **.:*~(jpEst . ., * .**, L 'k. "*. 1

~-.

- - - - . 1' " ." *. .')

Acknowledge and after 2 minutes, report that 11 HDP

1. TBO/PPO investigate loss of 11 Heater bkr is tripped with overload flag dropped.

Drain Pump. After 4 minutes report nothing abnormal at pump other than it is secured

2. OWC/I&C need assistance for failed PZR Acknowledge.

level control channel1-LT-110X.

Acknowledge, wait 1 minute then inform the crew that the leak is on the inlet to the Main Turbine oil cooler downstream of 1-SRW-252 TURB LO CLR SRW

3. TBO investigate SRW Leak.

SUPP. (IF SRW not isolated to TB yet then leak is active, once isolated then flow lessened in pressure until stopping approx 2 min later)

Report that there was a major fault in this area and that

4. Report status of offsite power.

it will take several hours to repair the damage.

Acknowledge wait 1 minute and use remote function

5. TBO tie 1Y10 to 1Y09. 1SY09 (TIE 1Y0911Y10 TO THE LIVE BUS) TO 1Y09. Report complete.

6. ABO tie MCC-104 to MCC-114 Acknowledge and activate Event 7.

Acknowledge. If Event 7 is inserted, delete it from the

7. ABO tie MCC-114 to MCC-104 schedule and activate Event 8.

Acknowledge. WHEN OC DG has reenergized 14 4KV bus then wait 1 minute and use remote function

8. TBO tie 1Y09 to 1Y1 0.

1SY09 (TIE 1Y09/1 Yl 0 TO THE LIVE BUS) TO 1Y10. Report complete.

After 5 minutes, report that there is no apparent cause

9. OSO investigate loss of 1A DG.

for the 1A DG to have tripped.

Page 6 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 1 Event#: 1 Page 7 of20 I:vc;ut

Description:

Trip of 11 Heater Drain Pump Event Type: C-BOP/SRO Time Position Applicant's Actions or Behavior BOP 0 Announce "Non-Essential4KV Motor Overload" alarm BOP 0 Recognize 11 Heater Drain Pump trip and report to SRO BOP 0 Refers to Alarm Manual 0 Implement AOP-3G "Malfunction of Main Feedwater System" SRO 0 Direct BOP/ATC to monitor for trip criteria (S/G level approaching -40")

SRO 0 Direct BOP to perform block step V "Failure of a Pump >5% Power" 0 Perform V.B.2 "Maximize SGFP Suction Pressure" as necessary 0 Condenser Hotwell Controller 1-LIC-4405 to 50%

BOP 0 Open Precoat Bypass valve 1-CD-5818-CV 0 Open Condensate Demin Bypass valve 1-CD-4439-MOV BOP 0 Ask permission of SRO to attempt restart of HDP 0 When asked by BOP to restart HDP respond by not allowing due to SRO unknown reason for trip BOP 0 Start 13 Condensate Booster Pump BOP 0 Inform Chemistry of bypassing Demins & Precoats SRO 0 Exit AOP-3G and implement OP-3 Examiner notes:

Event concludes when actions in AOP-3G complete and crew transitions back to OP-3.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, 1-LT-llOX (PZR Level) failing LOW Page 7 of20

Appendix D Scenario Outline Form ES-D-2 IOp-Test #: 2014 I Scenario #: 1 "-

LV'-UL :2 Page 8 of20 1-ATC Event

Description:

LT-llOX Failure Event Type:

T-SRO Time Position Applicant's Actions or Behavior ATC/BOP 0 Recognizes multiple alarms and reports to SRO 0 Directs ATC to monitor the primary and BOP to check Alarm Manual for E-33 SRO

&E35 0 Reports PZR level Channel X instrument has failed low and actual PZR level is ATC ..

nsmg 0 Refers to the Alarm Manual for following actions:

0 Shifts PZR LVL CH SEL switch, 1-HS-11 0, to Y.

ATC/BOP 0 Shifts PZR HTR LO L VL CUT -OFF SEL switch, 1-HS-1 00-3, to Y.

SRO 0 Refers to N0-1-200 for common tap failure 0 Resets Proportional Heaters and monitors primary pressure and level restoring ATC to normal values.

0 Directs BOP to check containment parameters, Channel X PZR Pressure, and SRO/BOP PT -1 02B to look for common tap failures SRO 0 Contacts OWC/I&C to investigate LT-110X failure 0 Evaluates T.S. 3.3.1 0 Post-Accident Monitoring (PAM) Instrumentation for SRO applicability. May reference STP-0-63-1.

Examiner notes:

Event concludes when ARM actions complete & Common Tap Analysis complete.

If SRO's understanding of Technical Specifications 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, Large SRW Leak in TB, when desired Page 8 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario#: 1 Event#:3 Page 9 of20 I I

Event

Description:

Large SRW Leak in TB Event Type: I M-All I I Time I Position I Applicant's Actions or Behavior BOP 0 Acknowledges alarms. Determines both SRW Head Tanks are rapidly lowering.

SRO 0 Implements AOP-7B, Loss of Service Water SRO 0 Determines Trip Criteria and assigns to ATC/BOP.

BOP 0 Inform SO-TSO and reduces MV ARs to zero.

0 Isolates SRW to turbine building by shutting:

1-SRW-1600-CV BOP 1-SRW-1637-CV 1-SRW-1638-CV 1-SRW-1639-CV 0 Stops 12 SRW PP and place its handswitch in PTL (may not be performed if BOP SRW head tank levels observed to be rising prior to stopping pump)

BOP 0 Starts Salt Water Air Compressors ATC 0 Trips the reactor and implements EOP-0 Examiner notes:

Event concludes when the Reactor is tripped.

If SRO's understanding of Technical Requirements Manual applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

NOTE TO EXAMINER Next malfunctions already inserted (MFRV failure and CEA's 19 & 32 failure to insert)

Page 9 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 cenario #: 1 Event #: 3(cont)/4/5 Page 10 of20 I M-ALL Event

Description:

Reactor Trip Event Type: R-ATC C-BOP/SRO I Time II Position I Applicant's Actions or Behavior A TC 0 Trips the Reactor by depressing the Manual Reactor Trip pushbuttons at 1COS 0 Performs Reactivity Control Safety Function 0 Depress Manual Reactor Trip Pushbutton on 1COS 0 Check Reactor tripped using NI power indications on 1COS 0 Verifies all CEAs fully inserted 0 ,

IF;Jll<ll:'e)tpc "*. : ;RE,A"*{f!il~:tQ :fully .insert, TU:EN borate the RCS to at n~ast2300 . fo . .

Cl 1 ~. rSh~ 'i'"

ATC g ,~;r'~

(CT) 0 d.¥ 0 :~~~:}t .

o *f.>Sllt 'wtValve ilevc-sdr:-MOV.

o :g~ls~ ~vaHalSleHGPPs. * .*. '

0 Verify DI Water Makeup is secured 0 Check 11 & 12 RC makeup Pumps secured on 1C07 0 Check VCT MIU 1-CVC-S12-CV is shut on 1C07 0 If aligned for direct makeup to RCS then shut RWT Charging Pump Suction 1-CVC-S04-MOV on 1C07 0 Reports Reactivity Control Safety Function Complete.

Examiner notes:

Page 10 of20

Appendix D Scenario Outline Form ES-D-2 I Op-Test #: 2014 I Scenario#: 1 Event#: 3/4/5 (cont.) Page 11 of 20 I M-ALL Event

Description:

Reactor Trip Event Type: R-ATC C-BOP/SRO Time Position Applicant's Actions or Behavior 0 Performs Turbine Trip 0 Checks Reactor tripped then:

0 Depresses both Turbine Trip Pushbuttons on 1C02 0 Checks Main Turbine stop Valves shut on MK VI screen 0 Checks Turbine Speed drops on MK VI screen 0 Checks Turbine Generator Output Breakers open BOP 0 11 GEN BUS BKR 0-CS-552-22 on lCOl 0 11 GEN TIE BKR 0-CS-552-23 on lCOl 0 Checks Generator Field Breaker open on 1CO 1 0 Checks Generator Exciter Field breaker open on 1CO 1 0 Ensures MSR 2"d Stage Steam source Valves are shut 0 Reports Turbine Trip Complete 0 Performs Vital Auxiliaries Safety Function 0 Checks 11 or 14 4KV bus energized.

0 Checks ALL 125V DC BUS VOLTS greater than 105 volts on 1C24: (notes failed voltmeter for 11 125V DC Bus)

BOP D 11 D 12 D 21 D 22 0 Checks at least THREE 120V AC Vital Buses are energized on 1C24:

D 11 D 12 D 21 D 22 0 Checks EITHER 1Y09 OR 1Yl 0 energized on 1C24.

0 Verifies Component Cooling Flow to the RCP's 0 Reports Vital Auxiliaries Safety Function Complete Examiner notes:

Page 11 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 1 Event #: 3/4/5 (continued)

I Page 12 of 20 I M-ALL Event

Description:

Event Type: R-ATC Reactor Trip C-BOP/SRO Time Position Applicant's Actions or Behavior 0 Performs Pressure & Inventory Control Safety Function, including alternate actions 0 Checks pressurizer pressure stabilizes between 1850 and 2300 PSIA AND is ATC trending to 2250 PSIA.

0 Determines PORVs not leaking by checking Acoustic Monitor and Quench Tank parameters 0 Reports Pressure and Inventory Safety Function Complete 0 Performs Core & RCS Heat Removal Safety Function 0 Checks TBV s/ADV s controlling S/G pressure 850-920 PSIA and TcoLo 525-535°F 0 Shuts both MSIV s if S/G pressure drops to 800 PSIA 0 Verifies SGIS actuated if S/G pressure drops below 685 PSIA 0 Checks S/G level (-) 170" to (+) 50" on 1C03 0 IF Feedwater flow is lost OR excessive, THEN perform the following BOP actions:

0 :';.:r

,~'-

. . Start: ahAFWLPP

~~>~~ {-~; , "

~:r ;>/ -- ", .

(CT) 0 '" rfip,fue'*S@F};?s .

0, *. Shutthe~SQ.FW !SOL valves 0 Operate the AFW System to restore S/G levels to between (-) 170 and

(+ )3 0 inches 0 Checks at least one RCP is in a loop with a S/G available for heat removal (on 1C06) 0 Checks THOT minus TCOLD is less than 10°F by checking indicators on 1C06 0 Reports Core & RCS Heat Removal Safety Function Complete.

Examiner notes:

Event concludes when the 11 4KV bus is lost due to Loss of Offsite Power NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Loss of Offsite Power, when desired Page 12 of20

Appendix D Scenario Outline Form ES-D-2 I Op-Test #: 2014 I Scenario #: 1 Event#: 6 Page 13 of20 Event

Description:

EOP-0 (LOOP) Event Type: C-ALL Time Position Applicant's Actions or Behavior 0 Notes Loss of Offsite Power. Informs SM, directs the RO and CRO to SRO reevaluate safety functions.

0 RE-evaluates Reactivity Control safety function:

ATC 0 Restarts a charging pumps to restore boration 0 Reports Reactivity Control safety function is still Complete.

0 Re-evaluates PIC safety function:

0 Check pressurizer pressure between 1850 and 2300 PSIA AND trending to 2250 PSIA ATC 0 Check pressurizer level stabilizes between 80 and 180 inches AND is trending to 160 inches 0 Reports Pressure and Inventory safety function as still Complete.

0 Re-evaluates VA safety function 0 Check 11 OR 14 4KV Vital Bus is energized 0 IF EITHER 11 OR 14 4KV Bus is not energized AND the OC DG is NOT running, THEN depress the OC DG EMERGENCY START PB, 0-HS-0707:

0 Check ALL 125V DC BUS VOLTS >105 volts 0 Check at least THREE 120V AC Vital Buses energized BOP 0 Check EITHER 1Y09 OR 1Y1 0 energized 0 Verify Component Cooling flow to the RCP's o Restarts 11 Component Cooling Pump 0 IF ANY electrical bus perturbations have occurred, THEN dispatch an operator to verify Switchgear Ventilation in service per OI-22H

0. Reports VA is Complete (notes 14 4k V bus and 1Y 10 are deenergized).

Examiners notes:

Page 13 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 1 Event #:6 (cont.) Page 14 of20 Event

Description:

EOP-0 (LOOP) Event Type: C-ALL Time Position Applicant's Actions or Behavior 0 Re-evaluates Core and RCS Safety Function 0 Reestablishes RCS Heat Sink by operating the TBVs or ADVs to maintain: (may exceed these bands initially but actions taken to return)

BOP o S/G pressure between 850 and 920 PSIA.

o TCOLD between 525° F and 535° F.

o Restart AFW flow if 13 AFW PP started initially 0 Reports HR safety function Cannot Be Met due to NO RCPs operating.

0 Performs Containment Environment Safety Function 0 Checks Containment Pressure< 0.7 PSIG using narrow range pressure on 1C10 0 Checks Containment Temperature< 120°F using cavity and dome temperature indicators on 1C 10.

BOP 0 Checks Containment Gaseous RMS at 1C22 not in alarm with no abnormal rising trend 0 Reports Containment Environment Safety Function Complete or Cannot be Met due Loss ofPower Effects (based on timing of LOOP) 0 Perform Rad Levels External to Containment Safety Function 0 Check the following RMS alarms are clear with no unexplained rise:

0 U-1 Wide Range Noble Gas Monitor 0 U-1 Condenser Off Gas@ 1C22 BOP 0 U-1 S/G Blowdown@ 1C22 0 U-1 Main Vent Gaseous@ 1C22 0 Reports Rad Levels External to Containment Safety Function Complete or Cannot be Met due to Loss of Power Effects (based on timing of LOOP)

Examiner's notes:

Page 14 of20

Appendix D Scenario Outline Form ES-D-2 IOp-Test #: 2014 ~ Scenario#: I I Event #:6 (cont.) Page 15 of20 IEvent

Description:

EOP-0 (LOOP) I Event Type: C-ALL Time Position Applicant's Actions or Behavior 0 Perform EOP-0 brief 0 Ensures all are attentive 0 Reviews Safety Functions not met 0 HR not met due to no operating RCP's 0 CE (potential) due to loss of power effects 0 RLEC (potential) due to loss of power effects SRO 0 Reviews Safety system Actuations 0 uv 0 SIAS or SGIS if slow to recognize overfeed condition 0 Solicits Input 0 Concludes the brief directing the crew to continue to monitor Safety Functions while the event is diagnosed.

0 Refers to EOP-0 flowchart 0 Core and RCS Heat Removal not met due to low no operating RCP's-Flowchart leads to EOP-2 SRO 0 CE and RLEC potentially not met due loss of power effects - Flowchart leads to EOP-2 0 Implements EOP-2 Examiner notes:

Event conclusion is implementation of EOP-2, Loss of Offsite Power Page 15 of20

Appendix D Scenario Outline Form ES-D-2 IOp-Test#: 2014 I Scenario #: 1 Event#: 7 Page 16 of20 C-BOP/SRO Event

Description:

EOP-2 entry LOOP Event Type:

T-SRO Time Position Applicant's Actions or Behavior I I SRO jo Perform EOP-2 Entry Brief I 0 Verify Shutdown Sequencer loads are operating BOP 0 IF 13 AFW PP starts AND 11 or 12 AFW PP is operating, THEN secure 13 AFWPP.

0 IF COMPONENT COOLING FLOW HAS BEEN LOST, THEN RESTORE BOP FLOW 0 If CC pump not started in EOP-0 then should be started (not expected) 0 IF 500KV OFFSITE POWER HAS BEEN LOST, THEN PROTECT THE CONDENSER FROM OVERPRESSURE AND MINIMIZE S/G BOP INVENTORY LOSS 0 Shut BOTH MSIV s.

0 Shut the S/G BID valves:

0 ESTABLISH RCS HEAT SINK 0 Operate the ATMOSPHERIC DUMP VALVES to maintain the following:

0 S/G pressures between 850 and 920 psia 0 TCOLD between 525 and 535°F 0 Establish Auxiliary Feedwater flow to at least ONE S/G using 11 or 12 AFW BOP PP as follows:

0 Verify the S/G steam driven train S/G AFW BLOCK valves are open with the handswitches in AUTO 0 Open the SG AFW STM SUPP & BYPASS valves 0 IF Main Feedwater is NOT available, THEN secure the Main Feedwater System 0 Operate Charging and Letdown to restore and maintain pressurizer level ATC between 101 and 180 inches Examiner notes:

NOTE TO EXAMINER Cue driver to Initiate Loss of lA DIG as desired after EOP-2 Implementation Page 16 of20

Appendix D Scenario Outline Form ES-D-2 IOp-Test #: 2014 I Scenario #: 1 Event#: 7 (cont.) Page 17 of20 C-BOP/SRO Event

Description:

EOP-2 entry LOOP Event Type:

T-SRO Time Position Applicant's Actions or Behavior 0 MAINTAIN RCS SUBCOOLING BETWEEN 30 AND 140°F ATC -0 Operate Pressurizer HTRs and SPRAY as necessary to maintain RCS subcooling between 30 and 140°F based on CET temperatures:

0 ATTEMPT TO RESTORE POWER 0 IF 11 OR 14 4KV Bus is NOT energized, AND 500KV offsite power is NOT available, THEN perform ANY of the following:

a IF the OC DG is NQT supplying' a vital4KV bus,ANQ it is~sJ:~ire<f tg place the OC DGon 14 4KVBus THEN perform th:~, ftHI~w;ing:,~}, ,*

0 IF the OC DG is NOT running, THEN direct an operator to BOP perform an emergency start from the local panel PER OI-21C, OC DIESEL GENERA TOR.

(CT) a WHEN the.OC DG is up to rated speed and.vo)ta&~;~<:yeii:fY .

the OC DG,OUT BKR, 152-0703 is closed. Y __ ' * '1 i"*'~v:t <t;.ft>

0 WHEN disconnect 189-1406 is closed AND breaker 152-0703 is closed, THEN perform the following:

0 Close 074KV BUS TIE, 152-070L, * ,11, . _ __.. ......

0 Insert the sync *stick AND close the OG:~s;!:J4ttlKV BUSFDR, 152-1406* * .-.* * *. :*~**;; .. _., ,'r. ':'x;,___ *'";;,,

IExaminer notes: I The scenario will end when crew has restored power to 14 4KV Bus and Evaluators are satisfied with crews plant control (Crew may take time to restore 11 4KV bus, this would meet the critical task, but not optimal)

If SRO's understanding of Technical Specification applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

TS LCO 3.8.1.A, 3.8.1.B, 3.8.1.D, 3.8.1.G, 3.8.1.H, 3.8.1.1, 3.8.1.K & 3.0.3 After scenario ends ask SRO for ERPIP call. The correct Emergency Action Level declaration for this scenano 1s:

ALERT, per S.A.l.l for AC Power capability (1 source from Station Blackout)

SITE AREA EMERGENCY. Per S.S.l.l possible ifOC DG not on 14 4KV bus (or 11 4KV bus) within 15 min of 1A DG loss Page 17 of20

SHIFT TURNOVER INFORMATION SHEET JB0459J DATE: Today ON-COMING SHIFT: DAYS MODE OF OPERATION REACTOR POWER(%) 100 100 GENERATION NET (MWe) 890 876 RCS LEAKAGE (gpm) .06 0.05 RCS BORON (ppm) 902 118 UNIT RISK (HIGHEST FOR DAY) CDF: MED LERF: MED CDF: LOW LERF: LOW BULK POWER NOTIFICATIONS Normal NON-ROUTINE SURVEILLANCE REQUIREMENTS and ACTION STATEMENTS [B0/25}

List action statements expiring during the oncoming shift, non-routine, conditional, & mode dependent surveillances (e.g. chemistry samples, operability verifications, ETPs, <7 day STPs)

OD's/RECO's!FA 'sand REF's requested by OPS Date Type Resp.

Unit Description ECD Requested Requested Group Page 18 of20

SHIFT TURNOVER INFORMATION SHEET IB04591 Shift Manager 500KV High Lines k8J5051 k8J5072 k8J5052 500KV Buses k8J BLACK 13KV Supplies k8J P-13000-1 k8J P-13000-2 SMECO Bkr Status k8J 252-2301 DOSH301 k8J OSH302 Site Self Power Feeders D 252-1106 D 252-2106 13KV Buses Voltage Regulators Auto 1102 Auto 2102 Auto 1103 Auto 2103 Auto 1101 Auto 2101 4KV Transformers k8JU-4000-11 k8JU-4000-21 k8JU-4000-12 k8JU-4000-22 k8JU -4000-13 k8JU-4000-23 4KV Buses k8J11 k8J12 k8J13 k8J14 Diesel Generators D1A D1B Doc D2A D2B Doc 480V Buses k8J11A k8J11B k8J14A k8J ~21A ~21B ~24A ~24B 14B 125VDC Battery Chargers k8J11 ~23 k8J12 k8J24 k8J14 k8J22 k8J13 k8J21 125VDC Buses ~11 ~12 ~22 ~21 120V AC Vital Buses ~11 ~21 ~13 ~23 ~14 ~24 ~12 k8J22 12 AFW Pump lB DG Page 19 of20

SHIFT TURNOVER INFORMATION SHEET IB04591 112 MSL Rad Mon 12 N 16 Rad Mon 32 psig 34 psig (yesterday)

(yesterday)

LONG TERM NOTES

1. lAW OD-09-005, maintain containment pressure less than 1.0 psig in order to ensure the containment response to a Design Basis Loss of Coolant Accident inside containment remains within design limits.

SHORT TERM NOTES

1. DO NOT place 13 SWS Pump in service untii1-SWS-126 (13 SWS PP DISCHARGE VENT} is replaced (CR-2012-007257}.

2. IF11 SGFP B/U Lube Oil Pump spurious auto start occurs, notify I&C to retrieve data from the recorder during the next business day.

3. 12 MSL & N-16 Rad Monitors 005

4. 1B DG for cylinder work, 01-49 due in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

5. 12 AFW Pump for past 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for bearing replacement Page 20 of20

Appendix D Scenario Outline Form ES-D-1 Facility: Calvert Cliffs Nuclear Power Plant Scenario #: 2 OP-Test#: CCNPP 2014 Examiners: Operators:

Initial Conditions: Unit-1 is at 100% power, EOC. Unit-2 is in Mode 5.

Turnover: 13 Cond Booster Pump is tagged out for inspection of high vibrations (expect back at end of shift), 12 AFW Pump OOS for governor work (out for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , back in in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) Instructions for the crew are to maintain power at 100%

Event Malfunction # Event Type* Event Description R-ATC Call from ESO to reduce load to 800 MWE in 1 Rapid Downpower N- BOP/SRO <15 min C-All 2 120V003 01 Loss of 1Y01 T-SRO MS018 04 Low C- BOP/SRO S/G Level L T -1114-D variable leg leak in 3

MS010 01 T-SRO containment MS010 01 4 M-All Steam line break in containment I Reactor Trip

.4 to 8 over 5 min ESFA004 01 CSAS A&B Automatic Failure 5 ESFA004 02 I -All SGIS A Automatic Actuation Failure ESFA012 6 Emergency Airlock T-SRO Containment Integrity breached

(N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec

.*];:"**iripsallRCP'swithitl lOtniriut~s bf(f;IS actuation (~oCCJlowto RCP's).

~~:.:>oetermines CSAS failureJmttnianually actuates CSAS pJ:iorto exiting EOP::-0.

- .*.. ~t:;ldentifiesand isolates 11 S/Gprior'to

- ~. .

RCS sub6ooling exceecling.

140°F.

Appendix D Scenario Outline Form ES-D-1 OP-Test #: 2014 DOWNPOWE Initial Conditions: U it-1 is at 100% power. Core Bumup is 17,536 MWD/MTU. Unit-2 is in Mode 5. 13 Condensate Booster Pump is tagged out for inspection of high vibrations (expected back at end of shift) and 12 AFW Pump is tagged out for governor work (expected back in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ). Instructions for the crew are to maintain power at 100%.

First a call from ESO directs power reduction to ::::;800 MWe in :S 15 minutes, crew should perform this downpower and stop effectively, demonstrating good plant control.

Next, a loss of 1Y01 occurs, requiring implementation of AOP-71. The crew is expected to determine associated T.S. LCOs. Affected RPS and ESF AS Channels will be de-energized using the appropriate Operating Instructions.

Next a small leak develops due to a crack in the weld of an instrument sensing leg tap on #11 S/G resulting in LR-1114D failing low. The crew is expected to review N0-1-200 for common tap analysis and associated T.S. LCO's. After several minutes the crack propagates to a major steam leak requiring a reactor trip.

SGIS and CSAS will fail to automatically actuate requiring the operator to manually actuate CSAS and take required actions for SGIS.

The crew is expected to implement EOP-4. If plant conditions degrade or the crew is unsure of the diagnosis it is acceptable for them to enter EOP-8. If EOP-8 is entered all critical tasks still apply unless individual tasks are invalidated by the exam team.

Scenario ends after containment pressure rapidly lowering is recognized and actions taken (EAL implications).

Appendix D Scenario Outline Form ES-D-1 INSTRUCTOR SCENARIO INFORMATION

1. Reset to IC-14.

2. Perform switch check.

3. Place simulator in CONTINUE, advance charts and clear alarm display.

4. Place simulator in FREEZE.

5. Enter Triggers

a. None

6. Enter Malfunctions

a. Failure of SGIS Automatic Actuation ESF A012 at time zero

b. . Failure of CSAS Automatic Actuation ESF A004 01 at time zero ESFA004-02 at time zero

c. Loss of 1Y01 120V003 01 on Event 1

d. S/G Level Transmitter Failure (LT-1114D)

MS018 04 LOW on Event 2

e. 11 Steam Leak Inside Containment MS010_01 from 0.1 to 0.4 over a 3 minute ramp on Event 2

f. 11 Steam Leak Inside Containment MS010_01 from 0.4 to 8 over a 3 minute ramp on Event 3

g. Fail Containment Equipment Hatch EQUIPMENT+HATCH to 20% on Event 4

7. Enter Panel Overrides

a. 12 AFW PP TURB TRIP SW: P1C04- 1HS3988- LTWHIT to OFF at time zero.

b. 12 AFW PP TURB TRIP SW: P1C04- 1STP3988- LTRED to OFF at time zero.

c. 12 AFW PP TURB TRIP SW: P1C04- 1STP3988- LTWHI to OFF at time zero.

d. Main Steam supply to 12 AFW PP 1-MS-107 SHUT at time zero

e. Reactor Regulating System Chan X S 1, RRS-S1(X) to OFF on Event 5

f. Shift 11 ADV to 1C43, 1-MS-3938-HV to 1C43 on Event 6

Appendix D Scenario Outline Form ES-D-1

8. Enter Remote Functions I Administrative

a. Place 13 Cond Booster pump in PTL and caution tag.

b. Place danger tag on 12 AFW PP.

9. Set simulator time to real time, then place simulator in CONTINUE.

10. Allow crew 3-5 minutes to acclimate themselves with their positions.

1. Brief the Crew:

1. Present plant conditions: 100% load at EOC 18,250 MWD/MTU

2. Power history: Long term steady state.

13 Cond Booster Pump is tagged out for inspection of high vibrations (expect back at end of shift)

3. Equipment out of service:

12 AFW Pump OOS for governor work (out for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , back in in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )

4. Abnormal conditions: None

5. Surveillances due: None

6. Instructions for shift: Maintain 100% Power

_ _ 2. Allow crew 3-5 minutes to acclimate themselves with their positions.

_ _ 3. Instructions for the Booth Operator.

a. Call as ESO and inform CRS that due to abnormal conditions at Waugh Chapel a power reduction to 800 MWe is required in <15 minutes.

b. Activate Event 1 (Loss of 1Y01) on Lead Evaluators cue after power stabilized

c. Activate Event 2 Sensing Line leak on LT-1114D 11 S/G Level indicator when cued by lead evaluator (when crew is sending PWS to downpower ESF AS & AF AS).

d. Activate Event 3 (Modify Stm Leak from .4 to 8% over 3 min) to increase the size of the leak when cued by lead evaluator.( 10-15 minutes after initial break)

e. Activate Event 4 for Containment Pressure breach on Lead Evaluators cue after peak containment pressure reached.

Appendix D Scenario Outline Form ES-D-1 Responses to Crew Request 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 ~pecified.

After two minutes, report acrid smell from

1. PWS/TBO investigate loss of 1YO 1.

11 Inverter.

After ten minutes report inverter appears to

2. EM investigate loss of 1YO 1.

have failed and that bus appears OK.

3. Place RCS loop 11 Instruments to RRS After 1 minute, use Event 5.

Channel Y switch S1 to OFF.

Acknowledge Request.

4. Deenergize ESF AS AL cabinet After 10 minutes report complete.

Acknowledge Request.

After 10 minutes use remote function to open

5. Deenergize ESF AS ZD cabinet and close ESF AS doors then report complete.

Acknowledge Request.

6. Deenergize AF AS AL cabinet After 10 minutes report complete Acknowledge Request.

7. PWS bypass AF AS ZD sensor modules.

After 10 minutes report complete

8. SRW Pump Room ventilation lineup Acknowledge request.

verified per OI-15. After 10 minutes report complete After 3 minutes report ZG 11 S/G level

9. PWS check AF AS cabinet for alarms pegged low, ~lso ZD and AL are de-energized.

10. Align the ADV s hand transfer valves for Acknowledge request. After 2-3 minutes, 11 S/G to the 1C43 position. shift control to 1C43 using EVENT 6.

After 2 Minutes report as security that

11. When Emergency Airlock opened per cameras show steam coming from Evaluator cue emergency airlock on west road

SHIFT TURNOVER INFORMATION SHEET JB04s9J Op-Test #: 2014 Scenario#: 2 Event#: 1 Page 6 of20 R-ATC Event

Description:

Rapid Downpower Event Type:

N -BOP/SRO Time Position Applicant's Actions or Behavior SRO 0 Order Rapid Downpower to ~90% in <15 min 0 Borate to RCS by performing the following: (This step may be omitted due to core bumup, downpower could be performed using CEA's only) 0 OPEN the BA Direct M/U Valve, 1-CVC-514-MOV 0 VERIFY two charging pumps are running ATC 0 START a BA PP, AFTER 30 seconds, THEN STOP the operating BA PP 0 SHUT the BA Direct M/U Valve, 1-CVC-514-MOV 0 OPEN the RWT CHG PP Suet Valve, 1-CVC-504-MOV 0 SHUT the VCT Outlet Valve, 1-CVC-501-MOV 0 Review Pre-Prepared Rapid Downpower Plan and inform ATC of SRO target CEA height ATC 0 Insert CEA's per SRO direction 0 Equalize Pressurizer boron as follows:

0 ENERGIZE all Pressurizer Backup Heater Banks ATC 0 ADJUST the setpoint on the selected Pressurizer Pressure Controller, PIC-1 OOX, to maintain Pressurizer pressure at 2250 PSIA 0 REDUCE Turbine Generator load to maintain Tc within 5 °F of BOP program Examiner notes

SHIFT TURNOVER INFORMATION SHEET IB04s9J Op-Test#: 2014 Scenario#: 2 Event#: 1 ( cont) Page 7 of20 R-ATC Event

Description:

Rapid Downpower Event Type:

N -BOP/SRO Time Position Applicant's Actions or Behavior SRO 0 When approaching 800 MWe direct ATC/BOP to secure downpower 0 SECURE borating the RCS by:

ATC 0 VERIFY the VCT Outlet Valve, 1-CVC-501-MOV, is OPEN 0 VERIFY the RWT Suet Valve, 1-CVC-504-MOV, is SHUT BOP 0 Place Turbine Control System back in Manual (if Auto used) 0 Withdraw CEA's as required to maintain Reactor Power (due to ATC Xenon buildup)

Examiner notes Event concludes when Reactor Power is stabilized.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Loss of 1Y01, when desired

SHIFT TURNOVER INFORMATION SHEET JB04S9J Op-Test#: 2014 Scenario #: 2 Event#: 2 Page 8 of20 C-All Event Description Loss of 1Y01 Event Type:

T-SRO Time Position Applicant's Actions or Behavior ATC/BOP 0 Recognizes multiple alarm(s) and reports to SRO BOP 0 Checks RPS and reports "RPS Not Calling for Trip" BOP 0 Check 1C24 and determine only 1YO 1 lost and reports to SRO ATC/BOP 0 Refer to Alarm Manuals SRO 0 Implement AOP-7J and assign steps 0 Selects Channel "Y" on PZR Press, PZR Level, PZR Htr Cutoff, and ATC RRS Channel Selector. Direct OWC to isolate RCS Loop 11 instruments by placing "S 1" switch to off.

ATC 0 Reset Proportional Heaters 0 Isolate LID (Shut CVC-515 & 516) and operate Chg Pp's to control ATC/SRO level 201-225" 0 Restore 11 SW HDR BOP/SRO 0 Verify 12 CCHX in service 0 Verify 11A/11B SRW HX OUT valve HIS's OPEN ATC/BOP 0 Review alarms consistent with loss of 1Y01 SRO 0 Directs OWC to have EM investigate the loss of 1Y01 Bus 0 Review TS. 3.3.1.A & D, 3.3.3.A, 3.3.4.A & C, 3.3.5.A & C, SRO 3.3.6.A, 3.3.9A & B, 3.3.10.A, 3.3.1l.A, 3.4.14.B, 3.8.1.B, 3.8.7.A, 3.8.9.B Examiner notes:

Event concludes when crew directs de-energizing ESF AS & AF AS.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, 11 S/G Level sensing line leak

SHIFT TURNOVER INFORMATION SHEET JB04S9J Op-Test#: 2014 Scenario #: 2 Event#:3 Page 9 of20 Event Type: C- BOP/ SRO Event

Description:

11 S/G level sensing line leak T-SRO Time Position Applicant's Actions or Behavior 0 Notes "AF AS AeTUATED" alarm on 1eo4 and reports to SRO BOP/SRO 0 Reports 1-MS-4070A & 1-MS-4070 opening and l-LT-1114D on 1e04 failed low SRO 0 Directs OWe to check AFAS cabinet for alarms 0 SRO may direct securing AFW flow to S/G's by either shutting BOP/SRO associated block valves or shutting 1-MS-4070 0 After report from OWe checks N0-1-200 common tap analysis, SRO directs BOP to check containment parameters BOP 0 Reports degrading containment parameters SRO 0 Implement AOP-7K Overcooling in Mode 1 BOP 0 Adjust turbine load to maintain Tcow on program I I SRO lo Determine TS 3.3.4.A applicable I

Examiner notes:

Event concludes when crew determines the failure is causing small steam leak in containment.

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Steam Leak in containment worsens

SHIFT TURNOVER INFORMATION SHEET !B0459J Op-Test#: 2014 Scenario #: 2 Event#: 4 Page 10 of20 Event

Description:

Steam Leak in Containment/Reactor Trip Event Type: M - All Time Position Applicant's Actions or Behavior ATC 0 Recognizes lowering T cow and reports to SRO BOP 0 Recognizes degrading containment parameters and reports to SRO SRO 0 Orders Reactor Trip prior to Auto Trip 0 Performs Reactivity Control Safety Function 0 Depress Manual Reactor Trip Pushbutton on 1COS 0 Check Reactor tripped using NI power indications on 1C05 0 Verifies all CEAs fully inserted 0 Verify DI Water Makeup is secured ATC 0 Check 11 & 12 RC makeup Pumps secured on 1C07 0 Check VCT M!U 1-CVC-512-CV is shut on 1C07 0 If aligned for direct makeup to RCS then shut R WT Charging Pump Suction 1-CVC-504-MOV on 1C07 0 Reports Reactivity Control Safety Function Complete 0 Performs Turbine Trip 0 Checks Reactor tripped then:

0 Depresses both Turbine Trip Pushbuttons on 1C02 0 Checks Main Turbine stop Valves shut on MK VI screen 0 Checks Turbine Speed drops on MK VI screen 0 Checks Turbine Generator Output Breakers open BOP 0 11 GEN BUS BKR 0-CS-552-22 on lCOl 0 11 GEN TIE BKR 0-CS-552-23 on 1C01 0 Checks Generator Field Breaker open on 1C01 0 Checks Generator Exciter Field breaker open on 1CO 1 0 Ensures MSR 2nd Stage Steam source Valves are shut 0 Reports Turbine Trip Complete Examiner notes:

SHIFT TURNOVER INFORMATION SHEET (Bo4s9J Op-Test #: 2012 Scenario #: 2 Event#: 4 (cont.) Page 11 of20 Event

Description:

Steam Leak in Containment Event Type: M-All Time Position Applicant's Actions or Behavior 0 Performs Vital Auxiliaries Safety Function 0 Checks 11 or 14 4KV bus energized.

0 Checks ALL 125V DC BUS VOLTS greater than 105 volts on 1C24:

D 11 D 12 D 21 D 22 BOP 0 Checks at least THREE 120V AC Vital Buses are energized on 1C24:

D 11 D 12 D 21 D 22 0 Checks EITHER 1Y09 OR 1Y10 energized on 1C24.

0 Verifies Component Cooling Flow to the RCP' s 0 Reports Vital Auxiliaries Safety Function Complete 0 Performs Pressure & Inventory Control Safety Function, including alternate actions 0 Operates heaters and spray to restore pressurizer pressure between 1850 and 2300 PSIA AND is trending to 2250 PSIA.

ATC 0 Operates charging and letdown to restore PZR level between 80 and 180 inches 0 Ensures RCS subcooling >30°F 0 Reports Pressure and Inventory Safety Function Not Met due to negative trends on PZR level and pressure Examiner notes:

SHIFT TURNOVER INFORMATION SHEET tBo4s91 Op-Test #: 2014 Scenario#: 2 Event #: 5 Page 12 of 20 Event

Description:

SGIS and CSAS failure Event Type: I - All 0 Performs Core & RCS Heat Removal Safety Function 0 Checks TBV s/ADV s controlling S/G pressure 850-920 PSIA and T COLD 525-535°F 0 Shuts both MSIVs when S/G pressure drops to 800 PSIA 0 Verifies SGIS actuated when S/G pressure drops below 685 PSIA (reports SGIS failure to SRO when recognized) 0 Verifies AF AS Block when 115 PSID pressure differential between 11 & 12 S/G's 0 IF Feedwater flow is lost OR excessive, THEN perform the BOP following actions:

(CT) 0 Start an AFW PP, Trip the SGFPs, Shut the SG FW ISOL valves (open block valve if shut earlier) 0 Operate the AFW System to restore S/G levels to between -170 and +30 inches 0 Checks at least one RCP is in a loop with a S/G available for heat removal (on 1C06) 0 Checks T HOT minus T COLD is less than 10°F by checking indicators on 1C06 0 Reports Core & RCS Heat Removal Safety Function Cannot be Met due to Low Tcow, Low S/G pressure and level and no RCP's.

Examiner notes:

SHIFT TURNOVER INFORMATION SHEET tB04S9J Op-Test #: 2014 Scenario#: 2 Event #: 5 (cont) Page 13 of20 Event

Description:

SGIS and CSAS failure Event Type: I - All 0 Performs Containment Environment Safety Function 0 Checks Containment Pressure< 0.7 PSIG 0 Verifies all CAC's operating with Emergency Outlet valves open 0 Verifies SIAS and CIS when pressure >2.8 PSIG ATC

.Elik:fri~~*~l ~~,t*~~u~~~~'

'i"~;r;s}

0 Checks Containment Temperature, verifies CAC's operating 0 Checks Containment Gaseous RMS at 1C22 not in alarm with no abnormal rising trend.

0 Reports Containment Environment Safety Function Cannot be Met due high containment pressure and temperature

SHIFT TURNOVER INFORMATION SHEET tB0459J Op-Test #: 2014 Scenario #: 2 Event#: 5 (cont.) Page 14 of20 Event

Description:

SGIS and CSAS failure Event Type: I - ALL Time Position Applicant's Actions or Behavior 0 Perform Rad Levels External to Containment Safety Function 0 Check the following RMS alarms are clear with no unexplained rise:

0 U-1 Wide Range Noble Gas Monitor BOP 0 U-1 Condenser Off Gas@ 1C22 0 U-1 S/G Blowdown@ 1C22 0 U -1 Main Vent Gaseous @ 1C22 0 Reports Rad Levels External to Containment Safety Function Complete 0 Perform EOP-0 brief 0 Ensures all are attentive 0 Reviews Safety Functions not met 0 PIC not met due to low PZR level and pressure 0 HR not met due low S/G press and level and no operating RCP's SRO 0 CE due to high Containment pressure and temperature 0 Reviews Safety system Actuations 0 SGIS (failed), SIAS, CIS, CSAS (failed), AF AS, AF AS Block 0 Solicits Input 0 Concludes the brief directing the crew to continue to monitor Safety Functions while the event is diagnosed.

0 Refers to EOP-0 flowchart BOP 0 PIC, HR and CE not met- Flowchart leads to EOP-4 0 Implements EOP-4 Examiners notes:

SHIFT TURNOVER INFORMATION SHEET tBo4s9t Op-Test #: 2014 Scenario #: 2 Event#: 5 (cont.) Page 15 of20 Event

Description:

SGIS and CSAS failure Event Type: I - ALL Time Position Applicant's Actions or Behavior SRO 0 Assign step G Identify Isolate and Confirm affected S/G to BOP 0 Identify the affected S/G by observing the following:

0 S/G with the highest steam flow 0 S/G with the lowest pressure 0 RCS loop with the lowest Tcow 0 S/G with the most rapid downward level trend CIJ~~lat't1 tl~~f~e~~~i@

BOP (CTj 0 Direct ABO/OSO to observe no Safety Valves leaking on 11 S/G Examiner's notes:

SHIFT TURNOVER INFORMATION SHEET IB04591 Op-Test#: 2014 Scenario #: 2 Event#: 5 (cont.) Page 16 of20 Event

Description:

SGIS and CSAS failure Event Type: I - ALL Time Position Applicant's Actions or Behavior 0 Maintain RCS Temps 0 IF the difference between unaffected S/G temperature and CET temperature exceeds 25°F during the blowdown, THEN cool the unaffected S/G to within 25°F of CET temperature using the unaffected S/G ADV 0 WHEN the RCS cooldown due to blowdown of the affected S/G has BOP stopped, THEN operate the unaffected S/G ADV to stabilize RCS temperatures as follows:

0 WHEN unaffected S/G temperature is within 25°F of the lowest CET temperature during blowdown, THEN maintain the following:

0 Unaffected S/G pressure approximately constant 0 T coLD approximately constant 0 Commence RCS Boration 0 Ensure VCT M/U shut CVC-512-CV 0 BA Direct MIU valve open CVC-514 ATC 0 BAST Gravity FD valves open CVC-508 & 509-CV's 0 All BA Pumps running 0 VCT Outlet valve shut CVC-501-MOV 0 All Chg Pumps running Examiner notes:

SHIFT TURNOVER INFORMATION SHEET IB0459J Op-Test#: 2014 Scenario #: 2 Event#: 6 (cont.) Page 16 of20 Event

Description:

Containment Failure Event Type: T - SRO Time Position Applicant's Actions or Behavior NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Containment Emergency Air Lock failure 0 Report Containment pressure rapidly dropped from Approximately BOP 10 PSIG to 0 PSIG 0 Recognize failure of containment emergency airlock triggers ERPIP SRO Call ofF.U.l.l and Tech Spec 3.6.l.A & 3.6.2.C Examiner notes:

Scenario concludes when crew recognizes the failure of the containment SRO actions can be done as post scenario questioning

SHIFT TURNOVER INFORMATION SHEET IB04s9J DATE: Today ON-COMING SHIFT: DAYS UNIT STATUS MODE OF OPERATION 1 5 REACTOR POWER(%) 100 w-6 GENERATION NET (MWe) 890 -14 RCS LEAKAGE (gpm) .06 N/A RCS BORON (ppm) 180 2452 UNIT RISK (HIGHEST FOR DAY) CDF: MED I LERF: MED CDF:LOW I LERF: LOW BULK POWER NOTIFICATIONS Normal NON-ROUTINE SURVEILLANCE REQUIREMENTS and ACTION STATEMENTS [BOJ 25]

List action statements expiring during the oncoming shift, non-routine, conditional, & mode dependent surveillances (e.g. chemistry samples, operability verifications, ETPs, <7 day STPs)

I OD's/RECO's/FA 'sand REF's requested by OPS Date Type Resp.

Unit Description ECD Requested Requested Group Shift Manager

500KV High Lines IZJ5051 IZJ5072 IZJ5052 500KV Buses ~BLACK ~RED 13KV Supplies ~ P-13000-1 ~ P-13000-2 SMECO Bkr Status ~ 252-2301 00SH301 ~ OSH302 Site Self Power Feeders D 252-1106 D 252-2106 13KV Buses ~12 1Zl23 ~21 Voltage Regulators Auto 1102 Auto 2102 Auto 1103 Auto 2103 Auto 1101 Auto2101 4KV Transformers ~U-4000-11 ~U-4000-21 ~U-4000-12 ~U-4000-22

~U-4000-13 ~U-4000-23 4KV Buses ~11 ~12 ~13 1Zl14 1Zl21 ~22 ~23 ~24 Diesel Generators 01A 01B Doc 02A 02B Doc 480V Buses ~11A ~11B ~14A ~ ~21A ~21B ~24A ~24B 14B 125VDC Battery Chargers ~11 ~23 ~12 ~24 ~14 ~22 ~13 ~21 125VDC Buses ~22 ~21 120VAC Vital Buses ~11 ~21 ~13 ~23 ~14 ~24 ~12 ~22 12AFWPump 13 Cond Booster PP

(yesterday) 32 PSIG 34 PSIG (yesterday)

(yesterday)

LONG TERM NOTES

1. lAW OD-09-005, maintain containment pressure less than 1.0 PSIG in order to ensure the containment response to a Design Basis Loss of Coolant Accident inside containment remains within design limits.

SHORT TERM NOTES

1. DO NOT place 13 SWS Pump in service untii1-SWS-126 {13 SWS PP DISCHARGE VENT) is replaced (CR-2012-007257).

2. IF11 SGFP B/U Lube Oil Pump spurious auto start occurs, notify I&C to retrieve data from the recorder during the next business day.

3. 12 AFW Pump 005 for past 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for governor work

4. 13 Cond Booster PP 005 for vibration inspection

Appendix D Scenario Outline Form ES-D-1 Facility: Calvert Cliffs Nuclear Power Plant Scenario #: 4 OP-Test #: CCNPP 2014 Examiners: Operators:

Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is @ 100% power.

Turnover: 12 CS Pump OOS for last hour for pump coupling Inspection (back in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ), 11 BA Pump OOS for last 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (bearing seized) (back in 1 day), 1-RC-403-MOV shut due to 1-ERV-402 excessive seat leakage, 23 Aux Feed Pump is OOS for motor bearing repair.

Expected back in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

Event# Malfunction # Event Type* Event Description C-ALL 1 480V002 01 Loss ofMCC-104 (AOP-7I)

T- SRO C- BOP/SRO 2 MS002 01 R-ATC 11 S/G Tube Leak (AOP-2A)

T-SRO 3 M-ALL Trip Reactor and Implement EOP-0 4 MS010 01 C-ALL 11 S/G MSLB in Cntmt (EOP-8) 5 ESFA010 01 C- BOP CIS "A" Failure 1-SI-428@

6 C- ATC/SRO 11 HPSI Discharge valve 15% open 15%

(N)ormal (R)eactivity (l)nstrument (C)omponent (M)ajor (T)ech Spec Critical 'Tasks:, (shaded)

1. Trips all RCP' s after CIS actuates and within 10 minutes of Component Cooling isolation to contaifunent.

2. Isolates 1'1 S/G when it is identified as the most affected S/G and after THoT <515°F

3. Notes insufficient flow from 11 HPSI pump and starts 12 HPSI pump prior to RVLMS 3rd light lit Page I of20

Appendix D Scenario Outline Form ES-D-1 OP-Test #: 2014 Scenario #: 4 SCENARIO OVERVIEW Loss MCC-104, S/G Tube Leak, Steam Line Break in Containment Initial Conditions: Unit-1 & Unit 2 are at 100% power. U-1 is MOC 10,885 MWD/MTU, U-2 is EOC 17,800 MWD/MTU. 12 CS Pump for last hour for pump coupling Inspection (back in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ). 11 BA Pump OOS for last 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (bearing seized, back in 1 day), 23 Aux Feed Pump is OOS for motor bearing repair (expected back in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ). 12 SGFP has a small oil leak on the oil cooler return line, not threatening pump operation First a loss ofMCC 104 occurs. After the crew has stabilized the plant they should realize they have no operable BA Pumps.

A Steam Generator tube leak begins in 11 S/G. The crew should attempt to borate the unit to a Tave of

<537°F using the RWT. The leak size is such that the crew may reach 537°F Tave or they may reach 101" in the PZR, either of which prompts the Reactor Trip.

The reactor will be tripped and EOP-0 implemented. During EOP-0 (approx. 6 min after trip) the steam line break into the containment manifests. CIS A fails to actuate requiring manual actuation. After the crew recognizes the CIS, all RCP's should be secured. The crew is expected to implement EOP-8.

In EOP-8 the crew should identify RLEC-2 is not met and worked immediately (which directs working HR-2). When crew works HR-2 they should isolate 11 S/G lAW HR-2. When ATC is performing PIC-4 the low flow from 11 HPSI must be recognized and 12 HPSI started. The crew will also isolate 11 S/G IAWHR-2.

Page 2 of20

Appendix D Scenario Outline Form ES-D-1 INSTRUCTOR SCENARIO INFORMATION

1. Reset to IC-24

2. Perform "Switch Check"

3. Place simulator in CONTINUE, advance charts and clear alarm display.

4. Place simulator in FREEZE

5. Enter Malfunctions:

_ _ a. Event Triggers:

1. None

b. #12 CS Pump Tripped: si004_02 at time zero

c. #11 BA Pump Tripped: cvcs014_01 at time zero

d. CIS Channel A Auto Failure: esfa010 01 at time zero

e. Loss of MCC-1 04: 480v002 01 on Event 1

f. 11 S/G Tube Leak: ms002 01 from 0.1 to 0.4 over a 5 min ramp on Event 2

g. 11 S/G Rupture in Cntmt: ms010_01 from 30% to 100% over a 5 min ramp on Event 3

6. Enter Panel Overrides:

a. Alarm window H-30: P1C09_H30_LTON (12CONTPP CSAS BLCKDAUTO) to OFF at time zero.

b. 11 BA PP green light: P1C07_1HS226X_LTGREE to OFF at time zero.

c. Alarm window F-26: P1C07_F26_LTON (11BA PP SIAS BLCKD AUTO) to OFF at time zero.

d. 11 HPSI discharge valve 1-SI-428 at 15% open on Event 4 Page 3 of20

Appendix D Scenario Outline Form ES-D-1

7. Enter Remote Functions I Administrative:

a. 12 CS Pp breaker: 152-1407_B to RACKOUT at time zero.

b. Tying 1Y10 to 1Y09 with 1SY09 to 1Y09 on Event 5

c. 11 S/G ATM DUMP VALVE XFER: 1-MS-3938-HV to 1C43 on Event 6.

d. Yell ow Tag 12 Containment Spray Pump in PTL.

e. Yell ow Tag 11 Boric Acid Pump in PTL.

f. Place Red Dots on alarm windows F-26 and H-30.

_ _ g. Shut 1-RC-403-MOV. Place pink tag on H/S.

h. Check ALL magnetic plaques are correct.

_ _ 8. Independently verify correct completion of the following:

a. Malfunctions and Event Triggers correctly entered

b. Panel Overrides correctly entered

c. Remote Functions I Administrative actions correctly entered/performed

9. Select "Clock" time and ensure "Horn On" for annunciators.

_ _ 10. Place simulator in RUN and reset/acknowledge panel and plant computer alarms.

11. Brief the Crew:

U-1@ 100% power MOC 10,885 MWD/MTU

1. Present plant conditions:

U-2 @'! 100% power EOC 17,800 MWD/MTU

2. Power history: U1 @ 100% for previous 100 days

12 CS Pump for last hour for pump coupling Inspection expected back in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

11 BA Pump for last 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (bearing seized)

3. Equipment out of expected back in 1 day service:

23 AFW Pump OOS for motor bearing replacement, expected back in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 12 SGFP has a small oil leak on the oil cooler return

4. Abnormal conditions:

line, not threatening pump operation

5. Surveillances due: None

6. Instructions for shift: Maintain 100% Power

12. Allow crew 3-5 minutes to acclimate themselves with their positions.

Page 4 of20

Appendix D Scenario Outline Form ES-D-1

_ _ 13. Instructions for the Booth Operator:

a. Activate Event 1, Loss ofMCC-104, on lead evaluator's cue.

b. Activate Event 2, 11 S/G tube leak, approximately 10 minutes after loss of MCC-1 04, on lead evaluator's cue.

c. Activate Event 3 (11 S/G Rupture in Containment) 6 minutes after trip

d. Activate Event 4 (11 HPSI discharge valve 15% open) after crew completes RAT in EOP-8 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.

. t.JE ""

. > .. ' i;. 0;J;:v~/~. . :.~1\'

. *A

.. ~Q,*::. s~.; .;<;,: . . *;.

RESPONSE

After three minutes report MCC-1 04 is

1. PWS/E&C investigate the loss of grounded and putting together a MCC-104. troubleshooting plan to locate problem.

After two minutes use Event 5 to tie 1Y1 0 to

2. TBO tie 1Y1 0 to 1Y09. 1Y09.

3. Chemistry sample both S/Gs for activity and After approximately 15 minutes, report that there is activity in 11 S/G and none in 12 Boron. S/G.

After 2-3 minutes activate Event 6 to shift

4. TBO shift 11 ADV to 1C43.

11 ADV control to 1C43.

5. ABO/OSO verify no steam coming from the After 2-3 minutes report no steam coming from any safeties from Auxiliary Building safeties on the Auxiliary Building roof. roof.

Page 5 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event#: 1 Page 6 of20 Event Type: C-All, Event

Description:

Loss ofMCC-104 T-SRO Time Position Applicant's Actions or Behavior 0 Recognizes multiple alarm(s) and reports to SRO. Checks RPS not BOP calling for a trip.

0 Implements AOP-71, directs immediate actions per plaque. Shift SRO Chg Pp suction back to VCT 0 Places 2 charging pumps in PTL, Opens CVC-501 VCT Outlet, ATC Shuts CVC-504 RWT Outlet BOP 0 Adjust Turbine Load to maintain T cow on program 0 Operate Charging pumps as necessary to maintain within 15" of SRO/ATC programmed level NOT to exceed 225" BOP 0 Directs OWC to have E&C investigate loss ofMCC-104 SRO 0 Directs OWC to tie 1Y10 to 1Y09 IA W AOP-7I.

ATC 0 ATC recognize and report to SRO that no BA Pp's available 0 Reference Tech Specs and determine 3.8.9.A due to loss ofMCC-SRO 104 0 After 1Y09 & 1Y10 are tied, Place CVC-501 & CVC-504 ATC Handswitches in Auto ATC 0 Restore Letdown to service IA W OI-2A Examiner notes:

NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, 11 S/G Tube Leak, when restoration of Letdown is directed Event concludes when indications of S/G tube leakage.

If SRO's understanding of Tech Specs and Technical Requirements Manual applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

Page 6 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event#: 2 Page 7 of20 Event Type: C- BOP/SRO Event

Description:

11 S/G Tube Leak R-ATC, T- SRO Time Position Applicant's Actions or Behavior BOP 0 Recognizes RMS alarms and reports to SRO BOP 0 Determines N-16 RMS readings are increasing 0 Notes PZR level lowering with no LID and reports RCS leakage is ATC in excess of 1 charging pump 0 Implement AOP-2A Section VI for RCS leage exceeding capacity of SRO 1 charging pump BOP 0 Determine and report a S/G Tube Leak exists, isolates Blowdown SRO 0 Direct downpower lAW AOP-2A to reduce Tave to <53JCF 0 Give trip criteria ofPZR level <101 ", Tave <537°, PZR Press SRO reaches TM/LP pretrip setpoint 0 Borate using Gravity Feed MOV's:

0 Start ALL available Charging Pumps 0 Open at least ONE Gravity Feed Valve (CVC-508 & 509-MOV's) 0 Shut CVC-501-MOV VCT Outlet for approximately 1 minute, then re-open ATC 0 Verify BOTH Gravity Feed Valve (CVC-508 & 509-MOV's) are shut 0 Open CVC-504-MOV (RWT Outlet) and shut CVC-501-MOV (VCT Outlet) 0 Obtain desired rate of power reduction by using ANY of the following methods:

Adjust boration rate

Use CEA's 0 Reduce Turbine Load as necessary to maintain S/G Pressure BOP approximately 800-825 PSIA Examiner notes:

Page 7 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event #: 2 Continued Page 8 of20 Event Type: C- BOP/SRO Event

Description:

11 S/G Tube Leak R-ATC, T- SRO Time Position Applicant's Actions or Behavior BOP 0 Verify LPFW' s High Level Dumps are Open 0 Monitor Feedwater System and adjust SGFP BIAS as necessary to BOP maintain S/G Levels ATC 0 When Trip Criteria met with CRS permission, TRIP Reactor.

0 Determine Tech Spec applicability. LCO 3.4.13.B Primary to SRO Secondary Leakage > 100 GPD Examiner notes:

Event concludes when Reactor is tripped.

If SRO's understanding of Tech Spec applicability is not clearly observable, follow-up questioning may be required upon completion of the scenario.

Page 8 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test#: 2014 Scenario #: 4 Event#: 3 Page 9 of20 Event

Description:

Reactor Trip (EOP-0) Event Type: M - ALL Time Position Applicant's Actions or Behavior SRO 0 Orders Reactor Trip prior to Auto Trip. Implements EOP-0 0 Performs Reactivity Control Safety Function 0 Depress Manual Reactor Trip Pushbutton on 1C05 0 Check Reactor tripped using NI power indications on 1C05 0 Verifies all CEAs fully inserted 0 Verify DI Water Makeup is secured ATC 0 Check 11 & 12 RC makeup Pumps secured on 1C07 0 Check VCT M/U 1-CVC-512-CV is shut on 1C07 0 If aligned for direct makeup to RCS then shut RWT Charging Pump Suction 1-CVC-504-MOV on 1C07 0 Reports Reactivity Control Safety Function Complete 0 Performs Turbine Trip 0 Checks Reactor tripped then:

0 Depresses both Turbine Trip Pushbuttons on 1C02 0 Checks Main Turbine stop Valves shut on MK VI screen 0 Checks Turbine Speed drops on MK VI screen 0 Checks Turbine Generator Output Breakers open BOP 0 11 GEN BUS BKR 0-CS-552-22 on lCOl 0 11 GEN TIE BKR 0-CS-552-23 on 1COl 0 Checks Generator Field Breaker open on 1CO 1 0 Checks Generator Exciter Field breaker open on 1COl 0 Ensures MSR 2nd Stage Steam source Valves are shut 0 Reports Turbine Trip Complete Examiner notes:

Page 9 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event #: 3 Continued Page 10 of20 Event

Description:

Reactor Trip (EOP-0) Event Type: M - All e Position Applicant's Actions or Behavior 0 Performs Vital Auxiliaries Safety Function 0 Checks 11 or 14 4KV bus energized.

0 Checks ALL 125V DC BUS VOLTS greater than 105 volts on 1C24: (notes failed voltmeter for 11 125V DC Bus)

D 11 D 12 D 21 D 22 BOP 0 Checks at least THREE 120V AC Vital Buses are energized on IC24:

D II D 12 D 21 D 22 0 Checks EITHER 1Y09 OR 1Y1 0 energized on 1C24.

0 Verifies Component Cooling Flow to the RCP's 0 Reports Vital Auxiliaries Safety Function Complete 0 Performs Pressure & Inventory Control Safety Function, including alternate actions 0 Operates heaters and spray to restore pressurizer pressure between 1850 and 2300 PSIA AND is trending to 2250 PSIA.

0 IF PZR Press drops to 1725 psia, THEN verify SIAS 0 Perform RCP trip strategy:

o IF RCS Press <1725 psia THEN trip 2 RCP's (inner or outer pair)

ATC o IF subcooling < 20°F THEN trip all RCP's o IF pressure drops below A TT. 1 Limits, THEN trip all RCP's 0 Operates charging and letdown to restore PZR level between 80 and I80 inches 0 Ensures RCS subcooling >30°F 0 Reports Pressure and Inventory Safety Function Not Met due to negative trends on PZR level and pressure I Examiner notes:

Page 10 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event #: 3 Continued Page 11 of20 Event

Description:

Reactor Trip (EOP-0) Event Type: M - All 0 Performs Core & RCS Heat Removal Safety Function 0 Checks TBV s/ADV s controlling S/G pressure 850-920 PSIA and T cow 525-535°F 0 Shuts both MSIV s if S/G pressure drops to 800 PSIA 0 Verifies SGIS actuated if S/G pressure drops below 685 PSIA 0 Checks S/G level (-) 170" to (+) 50" on 1C03 0 IF Feedwater flow is lost OR excessive, THEN perform the following actions:

BOP 0 Start an AFW PP 0 Trip the SGFPs 0 Shut the SG FW ISOL valves 0 Operate the AFW System to restore S/G levels to between

(-)170 and (+)30 inches 0 Checks at least one RCP is in a loop with a S/G available for heat removal (on 1C06) 0 Checks T HOT minus T COLD is less than 10°F by checking indicators on 1C06 0 Reports Core & RCS Heat Removal Safety Function Complete.

Examiner notes:

Event concludes when the Main Steam Line Break in Containment occurs NOTE TO EXAMINER Cue Booth Operator to insert next malfunction, Main Steam Line Break, when BOP reports Core and RCS Heat Removal Safety Function Complee Page II of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event#: 4 & 5 Page 12 of20 Event

Description:

Main Steam Line Break in Event Type: C -ALL Containment and CIS Failure C-BOP e Position Applicant's Actions or Behavior 0 Recognize Tcold lowering and PZR level and pressure trends ATC changing and report to SRO 0 Re-Assess Core & RCS Heat Removal Safety Function 0 Checks TBV s/ADV s controlling S/G pressure 850-920 PSIA and TcoLD 525-535°F 0 Shuts both MSIV s when S/G pressure drops to 800 PSIA 0 Verifies SGIS actuated when S/G pressure drops below 685 PSIA (reports SGIS failure to SRO when recognized) 0 Verifies AF AS Block when 115 PSID between 11 & 12 S/G's 0 IF Feedwater flow is lost OR excessive, THEN perform the following actions:

BOP 0 Start an AFW PP, Trip the SGFPs, Shut the SG FW ISOL valves 0 Operate the AFW System to restore S/G levels to between

(-)170 and (+)30 inches 0 Checks at least one RCP is in a loop with a S/G available for heat removal (on 1C06) 0 Checks T HOT minus TCOLD is less than 10°F by checking indicators on 1C06 0 Reports Core & RCS Heat Removal Safety Function Cannot be Met due to Low TcoLD, Low S/G pressure and level and no RCP's.

Examiners notes:

Page 12 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test#: 2014 Scenario #: 4 Event#: 4 & 5 Page 13 of20 Event

Description:

Main Steam Line Break in Event Type: C -ALL Containment and CIS Failure C-BOP e Position Applicant's Actions or Behavior 0 Performs Containment Environment Safety Function 0 Checks Containment Pressure< 0.7 PSIG 0 Verifies all CAC's operating with Emergency Outlet valves open 0 Verifies SIAS and CIS when pressure >2.8 psig 0 Recognizes CIS "A" Failure and manually initiates CIS BOP 0 Trips all RCP's due to no CC fltiw (withhi~,,tll;Wilt.ltes},

(CT) '*~:, 'vx:._,,,<:~S~H-~-.z,v, .

0 Verifies CSAS when pressure >4.25 psig 0 Checks Containment Temperature, verifies CAC's operating 0 Checks Containment Gaseous RMS at 1C22 not in alarm with no abnormal rising trend.

0 Reports Containment Environment Safety Function Cannot be Met due high containment pressure and temperature Examiner's notes:

Page 13 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event#: 4 & 5 Page 14 of20 Event

Description:

Main Steam Line Break in Event Type: C -ALL Containment and CIS Failure C-BOP Time Position Applicant's Actions or Behavior 0 Perform Rad Levels External to Containment Safety Function 0 Check the following RMS alarms are clear with no unexplained rise:

0 U-1 Wide Range Noble Gas Monitor 0 U-1 Condenser Off Gas@ 1C22 BOP 0 U-1 SIG Blowdown@ 1C22 0 U-1 Main Vent Gaseous @ 1C22 0 Performa Alternate Action to secure BID due to Condensor Off-Gas and U-1 SIG BID RMS alarms 0 Reports Rad Levels External to Containment Safety Function Cannot be Met due to RMS alarms 0 Perform EOP-0 brief 0 Ensures all are attentive 0 Reviews Safety Functions not met 0 PIC not met due to low PZR level and pressure 0 HR not met due low SIG press and level and no operating RCP's SRO 0 CE due to high Containment pressure and temperature 0 RLEC not met due to RMS alarms 0 Reviews Safety system Actuations 0 SGIS, SIAS, CIS (failed), CSAS, AFAS, AFAS Block 0 Solicits Input 0 Concludes the brief directing the crew to continue to monitor Safety Functions while the event is diagnosed.

0 Refers to EOP-0 flowchart SRO 0 Implements EOP-8 Examiner notes:

Page 14of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event#: 6 Page 15 of20 Event

Description:

EOP-8 & HPSI discharge Event Type: C - ATC & SRO Time Position Applicant's Actions or Behavior 0 Identify Success Paths for Safety Functions performed in EOP-0 ATC 0 RC-1 Met 0 PIC-4 Not Met 0 A TC should immediately start working PIC-4 .

0 Identify Success Paths for Safety Functions performed in EOP-0 BOP 0 VA-l Met 0 HR-2 Not Met 0 BOP should immediately start working HR-2.

0 Identifies Success Paths for all Safety Functions and determines Priority (CRS must perform CE & RLEC since ATC & BOP did not) 0 RLEC-2 Not Met SRO 0 PIC-4 Met 0 HR-2 Met 0 CE-3 Met 0 RC-1 Met 0 VA-l Met 0 Assigns BOP to perform RLEC-2 SRO 0 Assigns ATC to perform PIC-4 Examiner's notes:

Page 15 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event#: 6 Page 16 of20 Event

Description:

EOP-8 & HPSI discharge Event Type: C - ATC & SRO Time Position Applicant's Actions or Behavior 0 Performs PIC-4 ATC (CT)

.* ,@equate,ilow

' '< ; ~' ., ' '{

0 Performs RLEC-2 o Verifies BID isolations valves shut BOP o Verifies no leakage into CC System o Verifies SIAS, CIS, and CSAS o Implements HR-2 to isolate 11 S/G Examiner notes:

Page 16 of20

Appendix D Scenario Outline Form ES-D-2 Op-Test #: 2014 Scenario #: 4 Event#: 6 Page 17 of20 Event

Description:

EOP-8 & HPSI discharge Event Type: : C -A TC & SRO Time Position , Applicant's Actions or Behavior 0 Performs HR-2 o Ensure ATC is verifying SIAS flow lAW Att. 10 o Ensure ATC has commence boration o Commence C/D ofRCS using ADV's (100% Manual) o Verify Natural Circulation in at least 1 RCS loop o Ensure A TC maintaining RCS Subcooling o Wbenl'1I<)~:?s.'<:5'tso}t;1h~;.isalatetll S/G.

- .;-:v*, ..., '*' ."~ . <* ,,<,*.' .-,.-~--

Direct TBO shut 11 ADV in 45' SWGR Room BOP

Verify 11 MSIV Shut (CT)

Verify 11 MSIV Bypass Shut

Verify 11 SG FW Isolation FW-4516-MOV Shut

f .*§1iiltJ~l'S/<l*ft\f~[.S!e1un Supplies Valves MS-4070

& ."*? 01~CV~§;, .*~'

;,*: f I)< '. . . . *. * ** * *. .

lt)ifS. 1' I~ck.¥alves AFW-4520; 4521~

. }:f\52,~?!4 <¥: .. .?\:( 1 :>f : . . . *

Verify 11 S/G BID Valves BD-4010 7 4011-CV's

Close MS Upstream Drain Isolation 1-HS-6622

Direct OSO to check no 11 S/G Safety Valves leaking ATC 0 Maintain RCS subcooling between 25°F and 140°F 0 Direct ATC to maintain subcooling low in band to lower RCS leak SRO rate The scenario will end when 11 S/G is isolated, and crew has evaluated HPSI flow lAW HR-2 After scenario ends ask SRO for ERPIP call. The correct Emergency Action Level declaration for this scenario is:

ALERT, per F.A.l.1 for RCS Barrier loss (RCS subcooling < 2Y F) or potential loss (unisolable RCS leakage> 50 GPM)

Page 17 of20

SHIFT TURNOVER INFORMATION SHEET IB04591 DATE: Today ON-COMING SHIFT: DAYS MODE OF OPERATION 3 REACTOR POWER(%) 75 0 GENERATION NET (MWe) 665 0 RCS LEAKAGE (gpm) 0.01 (net) 0.02 (net)

RCS BORON (ppm) 949 413 UNIT RISK (HIGHEST FOR DAY) CDF: LOW LERF: LOW CDF: LOW LERF: LOW BULK POWER NOTIFICATIONS Normal NON-ROUTINE SURVEILLANCE REQUIREMENTS and ACTION STATEMENTS [BOI 25}

List action statements expiring during the oncoming shift, non-routine, conditional, & mode dependent surveillances (e.g. chemistry samples, operability verifications, ETPs, <7 day STPs)

OD's!RECO's!FA's and REF's requested by OPS Date Type Resp.

Unit Description ECD Requested Requested Group Page 18 of20

SHIFT TURNOVER INFORMATION SHEET IB04591 Shift Manager 500KV High Lines cg)5051 cg]5on cg)5052 500KV Buses cg) BLACK cg)RED 13KV Supplies cg) P-13000-1 cg) P-13000-2 SMECO Bkr Status cgJ 252-2301 DOSH301 cg) OSH302 Site Self Power Feeders D 252-1106 D 252-2106 13KV Buses cg]12 ~23 ~21 cg]22 Voltage Regulators Auto 1102 Auto 2102 Auto 1103 Auto 2103 Auto 1101 Auto 2101 4KV Transformers cg]u -4000-11 cg]u-4ooo-21 ~U-4000-12 ~U-4000-22 cg)U-4000-13 cg)U-4000-23 4KV Buses cgJn cg]12 cg]13 ~14 cg]21 cg]22 cg]23 cg)24 Diesel Generators D1A D1B Doc 02A 02B Doc 480V Buses cg)llA cg)llB cg)14A cg) [g]21A [g]21B [g)24A [g)24B 14B 125VDC Battery Chargers cg]ll cg]23 cg]12 cg)24 cg]14 cg]22 cg)13 cg]21 125VDC Buses cg]12 ~22 cg]21 120VAC Vital Buses ~11 ~21 ~13 ~23 ~14 ~24 ~12 ~22 11 BA Pump 23 AFWPp 12 CS Pump Page 19 of20

SHIFT TURNOVER INFORMATION SHEET JB0459J 32 psig (yesterday) 30 psig 32.5 psig yesterday)

(yesterday)

LONG TERM NOTES

1. IA W OD-09-005, maintain Containment pressure less than 1.0 PSIG in order to ensure the Containment response to a Design Basis Loss Of Coolant Accident inside the Containment remains within design limits SHORT TERM NOTES

1. 12 CS Pump for last hour for pump coupling Inspection expected back in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

2. 11 BA Pump for last 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (bearing seized) expected back in 1 day

3. 23 AFW Pump OOS for motor bearing replacement, expected back in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months Page 20 of20

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