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Seabrook - Final Operating Exam (Section a, B, and C) (Folder 3)
	ML13206A350
Person / Time
Site:	Seabrook
Issue date:	07/11/2013
From:	Silk D M; Operations Branch I
To:	; NextEra Energy Seabrook
	Jackson D E
Shared Package
ML13059A103	List: IR 05000443/2013301; ML13071A568; ML13149A164; ML13149A185; ML13149A188; ML13184A016; ML13206A323; ML13206A339; ML13206A343; ML13206A350; ML13235A111; ML13235A120;
References
	TAC U01870
	Download: ML13206A350 (274)
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EN JOB PERFORMANCE MEASURE 2013 !\IRC EXAM RO-ADM,.lPM01, QPTR CALCULATION N42 Student Name: LMS#: Evaluator Name: SAT UNSAT o OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

o JOB PERFORMANCE

1. Task Number and Description Position RO SBK 0150200501 Perform a Manual QPTR Calculation

2. Conditions: Plant is now at 100% power after recovering a dropped rod at EOL. The Main Plant Computer has been inoperable since yesterday (It was inoperable when the rod dropped). Power Range NI N42 failed and was declared INOP 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. The QPTR surveillance is required to be performed on this shift. Incore/Excore calibration was performed yesterday (before the rod dropped).

3. Standards:

Perform a manual QPTR surveillance in accordance with RX 1703 Quadrant Power Tilt Ratio Surveillance.

4. Student Materials:

Copy of Tear Off Sheet. Copy of RX1703 Quadrant Power Tilt Ratio Surveillance, Rev 07 Chg 02 Copy of RE-17 Rev 01-16-06 Copy of Data Sheet for RO ADMIN JPM 01 Calculator

5. Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the ..

Page 2 of 13 JOB PERFORMANCE

6.

References:

Procedures:

RX 1703, Quadrant Power Tilt Ratio Surveillance, Rev 07 Chg 02.

OS1000.05 Power Increase.

ON1251.01 Loss of Plant Computer.

Value Sys Description RO/SRO 015 A1.04 Ability to monitor changes in QPTR 3.5/3.7 015 K5.12 Knowledge of 3.2/3.6 015 K5.16 Definition and calculation of QPTR 2.9/3.4 Ability to evaluate plant performance and 4.4/4.7 make operational judgments based on the operating characteristics, reactor behavior, and instrument interpretation.

7. Setting: Classroom.

1. Give student a copy of the data sheet for 100% power NI cabinet values. 2. Use values listed in RE-17. 8. Safety Considerations:

None. 9. Approximate Completion Time: 20 minutes Page 3 of 13 JOB PERFORMANCE

10. Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for multiple You are the Primary Operator.

You are going to perform the QPTR surveillance. The following information is provided to you: The plant is now at 100% power following of a dropped rod at EOL. The main plant computer has been inoperable since yesterday (It was inoperable when the rod dropped). Power Range NI N42 failed and was declared INOP 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. The QPTR surveillance, per Tech Spec Surveillance Requirement 4.2.4.1(b), has been entered and the work order has been generated. Incore/Excore calibration was performed yesterday (before the rod dropped). We will begin after the Initiating Cue is read. 11. Initiating Cue: Unit Supervisor to Primary Operator, "Primary Operator (or student's name), perform the QPTR surveillance per RX1703 section 4.1. Discuss the results with me."

Page 4 of 13 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

'" denotes a critical step '" denotes a critical step SAT UNSAT 1. Start time _____ I nitiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available Peer Check your actions. Please continue with the When the student demonstrates the ability to obtain a controlled copy of RX1703, QPTR surveillance, provide the student with a copy. Student should refer to section 4.1 QPTR alarm inoperable above 50% RTP surveillance. Provide student with data sheet that has the values for detector currents.

Detector current units are in microamps.

Student should make the determination that one Power Range detector is inoperable when given the detector current data. P Power range channel is inop. Record Records INOP in rows 1, 2, 3, and INOP in rows 1, 2, 3, and 5 on Form A fpr for the inoperable Provide the student with a copy of RE-17 NIS Channel and Loop Delta-T Scaling when asked for. P Record time, date, and RE-17 revision Records tirne, date, and date on Form A. revision date on Form pqge 5 of 13 PERFORMANCE D=Discuss ELEMENT/STEP P=Perform 3=Simulate

denotes a critical step S Record the current output in microamperes for the operable top (A) and bottom (8) detectors of each power range channel on Form A Quadrant Power Tilt Calculation Sheet Row 1:

EVALUATION

denotes a critical SAT UNSAT Records the current output in microamperes for the operable top (A) and bottom (8) detectors of each power range channel on Form A Quadrant Power Tilt Calculation Sheet Row 1: N41 top (A) detector current N42 top (A) detector current (INOP should be recorded)

N43 top (A) current N44 top (A) detector current N41 bottom (B) detector current N42 bottom (B) detector current (INOP should be recorded)

N43 bottom (B) detector current N44 bottom (8) detector current CUE: When the student asks for independent verification of the va.lues recorded on Form A, provide the following cue, evaluator to student, "Form A detector currents have been independently verified."

Page 6 of 13 PERFORMANCE D=Discuss ELEMENT/STEP P=Perform 3=Simulate

denotes a critical step P Record on Form A row 2 the 100% power 0% AFD current for the operable top and bottom detectors for each power range channel using TDB Figure RE-17:

EVALUATION

denotes a critical SAT UNSAT Records on Form A row 2 the 100% power 0% AFD current for the operable top and bottom detectors for each power range channel using TDB Figure RE-17: N41 top (A) detector N42 top (A) detector (INOP should be recorded)

N43 top (A) detector N44 top (A) detector N41 bottom (8) detector N42 bottom (8) detector (INOP should be recorded)

N43 bottom (8) detector N44 bottom (8) detector Page 7 of 13 PERFORMANCE CHECt<:LlST D=Discuss ELEMENT/STEP P=Perform 3=Simulate

denotes a critical step P Calculate the normalized detector currents by dividing each operable detector current (row 1) by its 100% power 0% AFD current (row 2) and record on Form A row 3: STANDARD EVALUATION

denotes a critical step SAT UNSAT Calculates the normalized detector currents by dividing each operable detector current (row 1) by its 100% power 0% AFD current (row 2) and records on Form A row 3: N41 top (A) nl)rmalized detector current N42 top (A) normalized detector current (INOP should be recorded)

N43 top (A) normalized detector current N44 top (A) n()rmalized detector current N41 bottom (B) normalized detector current N42 bottom (B) normalized detector current (INOP should be recorded)

N43 bottom (B) normalized detector current N44 bottom (B) normalized detector current Page 8 of 13 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

__im_u_la_t_e

___

___________

__ S_A_T__U_N_S_A_T

_____________

__ 7. P Calculate the average normalized detector currents as follows: a. Divide the sum of the operable top normalized detector currents by the number of operable top detectors and record on Form A row 4. b. Divide the sum of the operable bottom normalized detector currents by the number of operable bottom detectors and record on Form A row 4. *8. P Calculate the QPTR for each detector as follows: *a. Divide each operable top normalized detector current (row 3) by the top average normalized detector current (row 4) and record on Form A row 5: Calculates average normalized detector currents as follows: Divides the sum of the operable top normalized detector currents by the number of operable top detectors and records on Form A row 4. Divides the sum of the operable bottom normalized detector currents by the number of operable bottom detectors and records on Form A row 4. Calculates thH QPTR for each detector as follows: Divides each operable top normalized detector current (row 3) by the top average normalized detector current (row 4) and records on Form A row 5: tap (A)

N42 top (A) (INOP should be N43 top (A)

N44 tap (A)

Page 9 of 13 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT *b. Divide each operable bottom normalized detector current (row 3) by the bottom average normalized detector current (row 4) and record on Form A row 5. *b. Divides each operable bottom detector current (row 3) by the bottom average detector current (row 4) and records on Form A row 5. N41 bottclm (8) detector N42 bottom (8) detector (INOP should be recorded)

N43 bottom (8) detector N44 bottc)m (8) detector NOTE: If the student expresses a rounded off value, then that VailUE! shall be compared against the standard.

The only value that is critical is the out of tolerance QPTR value. 9. P Indicates the maximum QPTR by circling the largest QPTR in row 5. Circles the largest QPTR in row 5. CUE: When the student asks for independent verification of the calculations for Form A, provide the following cue, evaluator to student, "Form A calculations have been independently verified." *10. P Determines if LCO 3.2.4 is/is not met based on maximum QPTR. *a. Notify US/SM that LCO 3.2.4 is/is not met. *a. Notifies LJS/SM that LCO 3.2.4 is/is not met CUE: When US/SM notified, repeat back information provided by student concerning QPTR and LCO 3.2.4. *b. On Form A row 6 circle YES/NO *b. On Form A row 6 circles YES/NO NOTE: Information given must agree with results shown on the key. See key for the correct item to circle in row 6.

Page 10 of 13 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

___________

____________

__ CUE: "The JPM is complete." 11. Stop time ________ Time to complete task 20 minutes Evaluator calculates time to complete task Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM.

Page 11 of 13 PERFORMANCE Provide comments on unsatisfactory performance of an elemenUstep or for any deviation from performance as stated. Record interruptions in performance SUCl1 as retraining, shift change, and processing of procedure changes, Recommend remedial traininfl, if necessary.

RO-ADMJPM01 Page 12 of 13

TEAR OFF SHEET FOR RO A[)MIN ..IPM Directions To The Student: You are the Primary Operator.

You are going to perform the QPTR surveillance. The following information is provided to you: The plant is now at 100% power following recovery of a dropped rod at EOL. The main plant computer has been since yesterday (It was inoperable when the rod dropped). Power Range NI N42 failed and was declarecilNOP 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. The QPTR surveillance, per Tech Spec Surve!illance Requirement 4.2.4.1 (b), has been entered and the work order has been gemerated. Incore/Excore calibration was performed yl3sterday (before the rod dropped). We will begin after the Initiating Cue is read. Initiating Cue: Unit Supervisor to Primary Operator, "Primary Operator (or student's name), perform the QPTR surveillance per RX1703 section 4.1. Discuss the results with me."

Page 13 of 13

SEABROOK JOB PERFORMANCE MEASURE 2013 NRC EXAM RO-ADMJPM02, SHUTDOWN MARGIN qf-LCULATION (MODE Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED' ON TO THE 2013 NRC . INITIAL EXAM SECURITY AGREEMENT.

o PREPARED BY: APPROVED BY:

JOB PERFORMANCE Task Number and Description Position RO SBK 0010100401 Perform Shutdown Margin Calculation Conditions:

A. The plant is in Mode 3 at 55rF following a trip from 100% 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ago. B. An inadvertent dilution has occurred. Standards:

Using RX1707 Shutdown Margin Surveillance calculate the boron concentration required to satisfy SOM for the present conditions using the figures from the Primary Tech Data Book provided by the instructor. Student Materials:

Copy of Tear Off Copy of RX1707, Shutdown Margin Surveillance Rev '7 Chg Copy of Primary TDB, Figure RE-2 Shutdown Boron Concentration vs.

Rev Copy of Primary TDB, Figure RE-18 Shutdown Margin Values, Rev Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the Page 2 of 9 JOB PERFORMANCE

6.

References:

Procedures:

RX1707, Shutdown Margin Surveillance.

Technical Specifications:

3.1.1.1 Shutdown Margin greater than 200°F. Manuals:

Primary TDB, Figure RE-2 Shutdown Boron vs. Temperature.

Primary TDB, Figure RE-18 Shutdown Margin Values. Value Sys KA Descri pti on RO/SRO 192002 K1.13 Calculate SDM using pre)cedures and 3.5/3.7 given plant parameter

s. 2.2.12 Knowledge of Surveill an Ge Procedures 3.7/4.1 7. Setting: Use the simulator or the classroom.

A key must be setup using RE curves (RE curves may not be the latest revision).

The required RE curves are included in the student material package and must be given to the student when reaching for the Primary Tech Data Book. Failure to do this will cause unrealistic numbers for the student. Since an inadvertent dilution has occurred, pick a value for the Gurrent boron concentration that is below the value required by RE-2. SDM mayor may not be adequate depending on the value selected (i.e., how large the dilution was). 8. Safety Considerations:

None. 9. Approximate Completion Time: 20 minutes RO-ADMJPM02 Page 3 of 9 JOB PERFORMANCE

10. Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for multiple You are the Primary Operator.

An inadvertent dilution has occurred.

The chemist has sampled the RCS for the current boron concentration.

Determine the boron concentration required, taking credit for xenon, to satisfy the SDM. State if the shutdown margin is adequate or not. The following information is provided to you: The plant is in Mode 3 at 55rF following a trip from 100% 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ago. An inadvertent dilution has occurred. Chemistry reports that the RCS boron concentration is 1220 ppm. Cycle burnup is 9600 MWD/MTU. Xenon worth is 5850 pcm. We will begin after the Initiating Cue is read. 11. Initiating Cue: Unit Supervisor to Primary Operator, "Primary Operator (or student's name), an inadvertent dilution has occurred.

Determine the required boron concentration to satisfy SDM requirements for the current ReS conditions taking credit for xenon. Using RX1707, determine if SDM is satisfactory.

Discuss the results with me." RO-ADMJPM02 Page 4 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

___________

____________

NOTE: When student demonstrates the ability to obtain a controlled copy of RX1707, Shutdown Margin Surveillance provide the student with RX1707, Shutdown Margin Surveillance.

1. P Start time _____ Initiating cue read CUE: If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." P For the existing RCS temperature, obtain the required shutdown boron concentration from Primary TDB, Figure RE-2 Shutdown Boron Concentration vs. Temperature.

For the existing RCS temperature, obtains the required shutdown boron concentration from Primary TOB, Figure RE-2 Shutdown Boron Concentration vs. Temperature.

NOTE: See key for all values that student should enter on Form A hne 1. *3. P Record RCS T avg and the corresponding RE-02 required shutdown boron concentration value (A) on Form A Shutdown Margin Determination

-Modes 3, 4, and 5. 4. P Obtain xenon worth from the MPCS point C0036 or from Reactor Engineering.

Record the xenon worth value (B) on Form A. *5. P Obtain the correct value of differential boron worth (DBW) from Primary TOB, Figure RE-18 Shutdown Margin Values. Record the OBW value (C) on Form A. Records ReS T avg and the corresponding RE-02 required shutdown boron concentration value (A) on Forrn A Shutdown Margin Determination

-Modes 3, 4, and 5. Obtains xenon worth from the MPCS pOint C0036 or from Reactor Engineering.

Record the xenon worth value (B) on Form A. Obtains correct value of differential boron worth (OBW) from Primary TDB, Figure RE-18 Shutdown Margin Values. Records the DBW value (C) on Form A.

Page 5 of 9 PERFORMANCE D;::Discuss ELEMENT/STEP P;::Perform

,3;::Simulate

denotes a critical step *6. P Using the equation as shown on Form A calculate the shutdown boron concentration (xenon credit) value (D). Record the calculated value (D) on Form A. If number is negative record zero. STANDARD EVALUATION

denotes a critical step SAT UNSAT Using the E:quation as shown on Form A calculatEis the shutdown boron concentration (xenon credit) value (D). Record thE! ccllculated value (D) on Form A. If number is negative records zero. NOTE: SDM mayor may not be adequate depending on the value of the current RCS boron concentration determined by the evaluator in the setup and required shutdown boron concentration obtained from RE-2. P Record the existing RCS concentration value (E) on Form *8. Check if existing RCS boron value (E) is greater than the shutdown boron concentration (xenon credit) (D). Mark the associated block yes or no as applicable.

Records the RCS boron concentration value (E) on Form A. Checks if existing RCS boron value (E) is greater than the shutdown boron concentration (xenon credit) (0). Marks thE: associated block yes or no as applicable.

CUE: If student asks for independent verification, provide the following cue, "Form A has been independently verified.

Please continue." P If existing Res boron is less than shutdown boron concentration (xenon credit) (D), notify SM/US that the shutdown margin surveillance is not being satisfied.

If existing RCS boron is less than shutdown boron concentration (xenon credit) (D), notifies SM/US that the shutdown margin surveillance is not being satisfied.

Page 6 of 9 PERFORMANCE D=Discuss ELEMENT/STEP EVALUATION P=Perform

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______ .......rit:......:ic'--'-ac....1 s.:...;t.:...;e.c...p

______

CUE: "The ..IPM is complete." 10. Stop time ____ Time to complete task :5 20 minutes Evaluator calculates time to complete task Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM.

Page 7 of 9 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial if necessary.

Page 8 of 9 TEAR OFF SHEET FOR RO ADMIN JPM Directions To The Student: You are the Primary Operator.

An inadvertent dilution has occurred.

The chemist has sampled the RCS for the current boron concentration.

Determine the boron concentration required, taking credit for xenon, to satisfy the SDM. State if the shutdown margin is adequate or not. The following information is provided to you: The plant is in Mode 3 at 55rF following a trip from 100% 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ago. An inadvertent dilution has occurred. Chemistry reports that the RCS boron concentration is 1220 ppm. Cycle burnup is 9600 MWD/MTU. Xenon worth is 5850 pcm. We will begin after the Initiating Cue is read. Initiating Cue: Unit Supervisor to Primary Operator, "Primary Operator (or student's name), an inadvertent dilution has occurred.

Determine the required boron concentration to satisfy SDM requirements for the current: RCS conditions taking credit for xenon. Using RX1707, determine if SDM is !iatisfactory.

Discuss the results with me." RO-ADMJPM02 Page 9 of 9

SEABROOK JOB PERFORMANCE MEASURE 2013 NRC EXAM RO-ADMJPM03, FINAL SPENT FUEL POOL BLENDED MAKEUP CALCULATION Student Name: LMS#: Evaluator Name: SAT UNSAT o OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED ------TRA----I o

JOB PERFORMANCE Task Number and Description Position RO SBK 0040100601 Perform a boron change calculeltion. Conditions:

A. A manual blended makeup to the Spent Fuel Pool is required to raise pool level. Standards:

Calculate the required flow controller and totalizer setpoints for a 550 gallon manual blended makeup to the Spent Fuel Pool. Student Materials:

Copy of Tear Off Copy of RS 1735, Reactivity Calculations, Rev Daily Chemistry Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures:

RS1735, Reactivity Calculations, Rev 6 Value Sys Descri ption RO/SRO Knowledge of procedl Jres, guidelines, or 4.3/4.6 limitations associated with reactivity management.

RO-ADMJPM03 Page 2 of 7 JOB PERFORMANCE Setting: Classroom. Use values listed in Daily Chemistry Report. Safety Considerations:

None. Approximate Completion Time: 15 minutes Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for rnultiple You are the Primary Operator.

You are going to calculations for a 550 gallon blended makeup to the Spent Fuel Pool. The following information is provided to you: A 550 gallon manual blended makeup to Spend Fuel Pool is required for pool inventory addition. Makeup total flow rate will be 50 gpm. The makeup boron concentration will be at the current Spent Fuel Pool boron concentration. 'A' Boric Acid Storage Tank will be used for the blended makeup. The makeup line contains a blend from a previous SFP makeup based on the same SFP and BAST values. We will begin after the Initiating Cue is read. I will act as the Unit Supervisor and provide cue-s and communications for this JPM. Do you have any questions? Initiating Cue: Unit Supervisor to Primary Operator, "Primary Operator (or student's name), determine the required flow controller and totalizer setpoints for a 550 gallon manual blended makeup to the Spent Fuel Pool. Discuss the results with me."

Page 3 of 7 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT 1. Start time _____ Initiating clle read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." When the student demonstrates the ability to obtain a controlled copy of RS1735, Reactivity Calculations, provide the student with a copy. Student should refer to section 4.4 Blended Makeup Calculation (Form E, Blended Makeup Worksheet) and the Daily Chemistry Report to determine Spent Fuel Pool (SFP) and boric acid storage tank boron concentration. P Determine the required flow and totalizer setpoints for a 550 manual blended makeup to the Fuel Enters the desired makeup boron ENTER the desired makeup concentration (C MU) for the SFP boron concentration (C MU)' 1. from the Daily Chemistry Report in step 1 of Form E. (2512 ppm) Enters the desired makeup flow 2.

2. rate SETPOINT:

FIQ-111 (F ToT) ra e : -TOT* in step 2 of Form E. (50 gpm) Enters the actual Boric Acid ENTER the actual Boric Acid Storage Tank concentration

3. Storage Tank concentration

3. (C BAST) from the Daily Chemistry (C BAST)' Report in step 3 of Form E. (7361 ppm) Enters the desired makeup ENTER the desired makeup quantity TARGET: FIQ-111 4. quantity TARGET: FIQ-111 4. (G TOTin step 4 of Form E. (550 (G TOT). gallons)

Page40f7 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION D=Perform

__im_u_la_t_e

___

___________

__ S_A_T__U_N_S_A_T

_____________

__ *5. CALCULATE the boric acid flow rate SETPOINT:

FIQ-111 (F BA): *6. CALCULATE the boric acid quantity TARGET: FIQ-111 (G BA): 7. Calculated By signature and Date. *5. Enters thl3 values from steps 1, 2 & 3 in the' equation and calculates the boric acid flow rate SETPOINT:

FIQ-111 (FBA)' *6. Enters thl3 values from steps 1, 3 & 4 in the equation and calculates the bOiric acid quantity TARGET: FIQ-1 'II 1 (G BA). 7. Signs .and dates the Calculated By signature and Date line. CUE: If the student asks for an Independent Verification of Form E during the JPM respond, "For the purpose of this JPM an independent verification will not be performed." CUE: "The ..IPM is complete." Stop time ____ Evaluator calculates time to complete task Obtain from student: Tear Off sheets and any other training materials used in performance of this ..IPM. Time to complete task :S;15 minutes Page 5 of 7 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

RO-ADMJPM03 Page 6 of7 TEAR OFF SHEET FOR RO ADMIIN JPM Directions To The Student: You are the Primary Operator.

You are going to perform calculations for a 550 gallon blended makeup to the Spent Fuel Pool. The following information is provided to you: A 550 gallon manual blended makeup to the Spend Fuel Pool is required for pool inventory addition. Makeup total flow rate will be 50 gpm. The makeup boron concentration will be at current Spent Fuel Pool boron concentration. 'A' Boric Acid Storage Tank will be used for the blended makeup. The makeup line contains a blend from a previous SFP makeup based on the same SFP and BAST values. We will begin after the Initiating Cue is read. Initiating Cue: Unit Supervisor to Primary Operator, "Primary Operator (or student's name), determine the required flow controller and totalizer setpoints for a 550 gallon manual blended makeup to the Spent Fuel P04:>1. Discuss the results with me."

Page 7 of 7

SEABROOK JOB PERFORMANCE MEASURE 2013 NRC EXAM RO-ADMJPM04, INITIATE A LIQUID EFFLUENT WASTE SAMPLE Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY: ______________

--__----___DATE: TRAINING SUPERVISOR

" ' JOB PERFORMANCE WORKSHEET

1. Task Number and Description Position RO SBK 2. Conditions: The plant is in MODE 1 with two ocean Service Water and two Circulating Water pumps running with no expected change of configuration. WL-TK-63A, "An Waste Test Tank has been filled to 18,000 gallons. WL-TK-63A, "A" Waste Test Tank, was placed on recirculation at 0800 today per ON1018.07 , Waste Test Tank Recirculation. WL-TK-63A, "A" Waste Test Tank has to be sampled to prepare a LEW permit for a release to the transition Structure. Projected release start time is normally 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after placing the tank on recirc. 3. Standards:

Using CP-4.1. Effluent Sampling Program and ON1018.07, Waste Test Tank Recirculation.

initiate the following: Form CP4.1A. Liquid Effluent Waste Sample Request 4. Student Materials:

Copy of Tear Off Copy of CP-4.1, Effluent Sampling Copy of ON1018.07 , Waste Test Tank

5. Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the 6.

References:

Procedures: CP-4.1, Effluent Sampling Program ON1018.07 , Waste Test Tank Recirculation Page 2 of7 JOB PERFORMANCE Value Sys Description RO/SRO 2.3.11 i Ability to control radiation rele?sec.::.s,,-.

__-'-3::...:

....::.8,1'--'4..:...:.3=-----

__ Setting: Simulator or Classroom. Safety Considerations:

None. Approximate Completion Time: 15 minutes Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for multiple You are the Primary Operator.

You are going to initiate a Liquid Effluent Waste Sample Request. The following information is provided to you: The plant is in MODE 1 with two ocean Servicl::

Water and two Circulating Water pumps running with no expected change of configuration. WL-TK-63A, "A" Waste Test Tank has been fWed to 18,000 gallons. WL-TK-63A, "A" Waste Test Tank, was placed on recirculation at 0800 today per ON1018.07 , Waste Test Tank Recirculation. WL-TK-63A, "A" Waste Test Tank has to be sampled to prepare a LEW permit for a release to the transition Structure. Projected release start and time is normally 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after placing the tank on recirc. We will begin after the Initiating Cue is read. I will act as the Unit Supervisor and provide the cues and communications for this JPM. Do you have any questions? Initiating Cue: Unit Supervisor to Primary Operator, "Primary Operator (or students name), initiate a Liquid Effluent Waste Sample Request for WL-TK-63A, 'A' Waste Test Tank. Discuss the results with me." RO*ADMJPM04 Page 30f7 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

___________

____________

__ When the student demonstrates the ability to obtain a controlled copy of CP-4.1, Effluent Sampling Program and ON1 018.07, Waste Test Tank Recirculation, provide the student with the required document(s).

1. P Start time _____Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." It is assumed that the student will use CP 4.1 to process through the verification and check ON1018.07 to verify the tank volumes and recirculation flow rate. The student may choose to verify the tank volume and recirculation rate prior to referring to CP 4.1. These steps can be performed in any order as long as all steps are completed correctly.

2. P Complete section 1 of CP Name of tank, sump, or a. Enters WTT 'A'. a. demin vessel to be sampled. If the student wants to verify the amount of liquid in the 'A' Waste Test Tank using the Plant Computer, tell them that the MPCS indicates 18,000 Verifies and enters 18,000 Total tank or sump volume to be b. gallons for total tank or sump b. discharged or transferred.

volume. The recirculation rate for WTT 'A' is 150 gpm. Enters the recirculation rate of *c. 150 gpm and calculates the c. Recirculation rate. recirculation required time to be 240 minutes.

Page 4 of 7 PERFORMANCE CHECKLllST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

___________

__________

__ Recirculation starting time and d. date. e. Sample date and time, f. Disposition of tank. The projected CW and SW pump g. combination for the discharge.

Projected release start date and h. time. Date, time of request, and initials i. of originator.

Date, time, and initials of individual that performed verification of operational data. CUE: "The JPM is complete." Stop time ____ Evaluator calculates time to complete task Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. Enters 0800 and today's date. Enters 12,00 and today's date. Enters DISCHARGE as f.

Enters 2 CW pumps and 2 g. pumps. Enters 16100 and today's date. Enters time, date and initials are. Hands form to Unit Supervisor for j. verificcltion.

Time to complete task :s; 15 minutes Page 5 of 7 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial if necessary.

of 7 JOB PERFORMANCE Directions To The Student: You are the Primary Operator.

You are going to initiate a Liquid Effluent Waste Sample Request. The following information is provided to you: The plant is in MODE 1 with two ocean Senlicf3 Water and two Circulating Water pumps running with no expected change of configuration. WL-TK-63A, "AI! Waste Test Tank has been fililed to 18,000 gallons. WL-TK-63A, "AI! Waste Test Tank, was plac:ed on recirculation at 0800 today per ON1018.07 , Waste Test Tank Recirculation. WL-TK-63A, "N Waste Test Tank has to sampled to prepare a LEW permit for a release to the transition Structure. Projected release start time is normally 8 h()urs after placing the tank on recirc. We will begin after the Initiating Cue is read. I will act as the Unit Supervisor and provide the cues and communications for this JPM. Do you have any questions?

Initiating Cue: Unit Supervisor to Primary Operator, "Primary Operator (or students name), initiate a Liquid Effluent Waste Sample Request for WL-TK-63A, 'A' Waste Test Tank. Discuss the results with me." RO-ADMJPM04 Page 7 of 7 JOB PERFORMANCE MEASURE 2013 NRC E)()l,M SRO-ADM..IPM01, VERIFY QPTR CALCULATION N42 Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: _____________

DATE: APPROVED BY: ----=TRA=-:-::-:I N--:-:-:I JOB PERFORMANCE

1. Task Number and Description Position SRO SBK 1190202602 Review Results of Surveillance Tests 2. Conditions: Plant is now at 100% power after recovering a d.ropped rod at EOL The main plant computer has been inoperable since yesterday (It was inoperable when the rod dropped). Power Range NI N42 failed and was declared INOP 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. The QPTR surveillance has been entered and the work order has been generated. Incore/Excore calibration was performed yesterday (before the rod dropped). The Primary Operator has completed the QPTR surveillance. The Secondary Operator has completed the independent verification. The Secondary Operator has given the complet 9d forms to you for your verification.

'3. Standards:

Verify a manual QPTR surveillance in accordance with RX1703 Quadrant Power Tilt Ratio Surveillance.

4. Student Materials:

Copy of Tear Off Sheet. Copy of RX 1703, Quadrant Power Tilt Ratio Surveillance, Rev 07 Chg 02 Copy of RE-17 Rev 01-16-06 Copy of Data Sheet for SRO ADMIN JPM 01 Copy of completed QPTR surveillance form. Calculator

5. Limitations On Performance:

Verify all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the Page 2 of 13 JOB PERFORMANCE WORKSHEET

6.

References:

Procedures: RX1703, Quadrant Power Tilt Ratio 8urveillanc43, Rev 07 Chg 02. 081000.05 Power Increase. ON1251.0'1 Loss of Plant Computer.

Value 8ys Descri pti()n RO/8RO 015 A1.04 Ability to monitor char sin QPTR 3.5/3.7015 K5.12 Knowledge of QPTR 3.2/3.6 015 K5.16 Definition and calcula tior 10fQPTR 2.9/3.4 Ability to evaluate pial ,t )erformance and 4.4/4.7 make operational Ime based on the operating characterist ics , reactor behavior, and instrum en1: interpretation.

7. Setting: Classroom. Give student a copy of the data sheet for 100% power NI cabinet values. Examiner must prepare a completed RX1703 Form A in advance. It shall reflect the ...IPM values for the NI cabinet detector currents and RE-17 100% values. Use values listed in RE-17. 8. Safety Considerations:

None. 9. Approximate Completion Time: 20 minutes Page 3 of 13 JOB PERFORMANCE

10. Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for multiple You are the Unit Supervisor.

You are going to vl3rify the QPTR surveillance. The following information is provided to you: The plant is now at 100% power following recovery of a dropped rod at EOL. The main plant computer has been inoperable since yesterday (It was inoperable when the rod dropped). Power Range NI N42 failed and was declared INOP 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. The QPTR alarm surveillance has been entered and the work order generated. Incore/Excore calibration was performed yesterday (before the rod dropped). The Primary Operator has completed the surveillance. The Secondary Operator has completed the independent verification. The Secondary Operator has given the completed forms to you for your verification. We will begin after the Initiating Cue is read. 11. Initiating Cue: Shift Manager to Unit Supervisor, "Unit Supervisor (or student's name), verify the QPTR surveillance per RX1703. Record any issues that you find on the tear-off sheet. Correct any issues that you find. Discuss the results with me."

Page 4 of 13

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

____________

__________

__ 1. Start time _____ I nitiating cue read If the student requests a Peer Check at any time during the ..IPM respond, "No one is available Peer Check your actions. Please continue with the When the student demonstrates the ability to obtain a controlled copy of RX1703, QPTR surveillance, provide the student with a copy. Student should refer to section 4.1 QPTR alarm inoperable above 50% RTP surveillance. Provide student with data sheet that has the values for detector currents.

Detector current units are in microamps.

Student should make the determination that one Power Range detector is inoperable when given the detector current data. P Power range channel is inop. Record Verifies that INOP in rows 1, 2, 3, INOP in rows 1, 2, 3, and 5 on Form A 5 for N42 has been for the inoperable NOTE: Provide the student with a copy of RE-17 NIS Channel and Loop Delta-T Scaling when asked for. 3. P Record time, date, and RE-17 revision Verifies time, date, and RE-17 date on Form A. revision date ,on Form A.

Page 5 of 13

D=Discuss ELEMENT/STEP P=Perform 3=Simulate

denotes a critical step S Record the current output in microamperes for the operable top (A) and bottom (8) detectors of each power range channel on Form A Quadrant Power Tilt Calculation Sheet Row 1:

EVALUATION

denotes a critical SAT UNSAT Verifies the current output in microamperes for the operable top (A) and bottom (B) detectors of each power range channel on Form A Quadrant Power Tilt Calculation Sheet Row 1 have been recorded:

N41 top (A) detector current N42 top (A) detector current (INOP should be recorded)

N43 top (A) detector current N44 top (A) dE,tector current N41 bottom (B) detector current N42 bottom (B) detector current (INOP should be recorded)

N43 bottom (B) detector current N44 bottom (B) detector current Page 6 of 13 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform c;;;..3_=S.=..::.:..:im..:..;:u=la=t.;;;..e

__* .;;;..de..:..;:n..:..;:o;...;.te..:..;:s,-a.:....-=-c,-rit,-ic;...;.a,-I s..:..;:t:.;;..e.L:-p

______* ...:..;de..:..;:n",-o;...;.t..:..;:es:.....;;Cl, cr..:..:cit:....:.ic.:..:.al'--'s:....:.te

.::...tp=--

______P Record on Form A row 2 the 100% power 0% AFD current for the operable top and bottom detectors for each power range channel using TDB Figure RE-17: Verifies on Form A row 2 the 100% power 0% AFD current for the operable top and bottom detectors for each power range channel using TDB Figure RE-17 have been recorded:

N41 top (A) detector N42 top (A) (INOP should be recorded)

N43 top (A) detector N44 top (A) detector N41 bottom (8) detector N42 bottom (8) detector (INOP should be recorded)

N43 bottom (8) detector N44 bottom (B) detector Page 7 of 13

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

____________

__ P Calculate the normalized detector currents by dividing each operable detector current (row 1) by its 100% power 0% AFD current (row 2) and record on Form A row 3: Verifies calculation for the normalized detector cUlrre'nts by dividing each operable distector current (row 1) by its 100% powtsr 0% AFD current (row 2) and verifies values have been recorded on Form A row 3: N41 top (A) normalized detector current N42 top (A) normalized detector current (INOP should be recorded)

N43 top (A) normalized detector current N44 top (A) normalized detector current N41 bottom (8) normalized detector current N42 bottom (8) normalized detector current (INOP should be recorded)

N43 bottom (8) normalized detector current N44 bottom (8) normalized detector current Page 8 of 13 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT P Calculate the average normalized detector currents as follows: Divide the sum of the operable top normalized detector currents by the number of operable top detectors and record on Form A row 4. Divide the sum of the operable bottom normalized detector currents by the number of operable bottom detectors and record on Form A row 4. Verifies calculations for the average normalized de!tector currents as follows: Divides the sum of the operable top normalized detector currents by the number of operable top detectc)rs and verifies values have been recorded on Form A row 4. Divides the sum of the operable bottom normalized detector currents by the number of operable bottom detectors and verifies values have been recorded on Form A row 4. *8. Calculate the QPTR for each detector as follows: Divide each operable top normalized detector current (row 3) by the top average normalized detector current (row 4) and record on Form A row 5: Verifies calculations for the QPTR for each detector as follows: Divides e;ach operable top normalized detector current (row 3) by the top average normalized detector current (row 4) and verifies values have been recordlad on Form A row 5: top (A)

N42 top (A) (INOP should be N43 top (A)

N44 top (A)

Page 9 of 13 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT Divide each operable bottom *b. Verifies calculations that divide normalized detector current (row each operable bottom normalized

3) by the bottom average detector current (row 3) by the normalized detector current (row bottom average normalized

4) and record on Form A row 5. detector current (row 4) and verifie!:;

v;:llues have been recorded on Form A row 5. bottom (8) detector N42 bottom (8) detector (INOP should be recorded)

N43 bottc)m (8) detector N44 bottom (8) detector If the student expresses a rounded off value, then that shall be compared against the standard.

The only value that is critical is the out of tolerance (circled)

QPTR value. P Indicates the maximum QPTR by Verifies that the largest QPTR in circling the largest QPTR in row 5. 5 has been If the Shift Manager (Evaluator) is informed tha1 the LCO statement performed by the Operator is incorrect, say "Use your corrected LCO statement and complete the

10. Determines if LCD 3.2.4 is/is not based on maximum Notify US/SM that LCD 3.2.4 is/is *a. Notifies SM that LCO 3.2.4 is/is not met. not mElt When SM notified, repeat back information provided by student concerning QPTR and LCO 3.2.4. *b. On Form A row 6 circle YES/NO Verifies on Form A row 6 YES/t\IO has been circled. Information given must agree with results shown on the See key for the correct item to circle in row 6. SRO-ADMJPM01 Page 10 of 13

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

....=3_=--=S-,-,im-,-,-,-ul--=-a-,-,te,--_*_d,-e,-n--"o--=-te,-s,-a,---,-cr_it:....cic....::.a_1

-'-st--'-e.Lp

______*_d'-e'-n--'o--'-te---'s_a cl_"it_ic_a_1 s_t_eL..p________S_A_T---'-U_N--=S_A_T_

CUE: "The ..IPM is complete." Stop time ____ Time to complete task S 20 minutes Evaluator calculates time to Obtain from Tear Off sheets and any other materials used in performance of SRO-ADMJ PMOPage 11of 13 PERFORMANCE Provide comments on unsatisfactory performance of an elemenUstep or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial if necessary.

Page 12 of 13 TEAR OFF SHEET FOR SRO ADMIN JPM Directions To The Student: You are the Unit Supervisor.

You are going to the QPTR surveillance. The following information is provided to you: The plant is now at 100% power following recovery of a dropped rod at EOL. The main plant computer has been inoperable since yesterday (It was inoperable when the rod dropped). Power Range NI N42 failed and was declared INOP 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. The QPTR alarm surveillance has been and the work order has been generated. Incore/Excore calibration was performed yesterday (before the rod dropped). The Primary Operator has completed the QPTR surveillance. The Secondary Operator has completed the independent verification. The Secondary Operator has given the completed forms to you for your verification. We will begin after the Initiating Cue is read. Initiating Cue: Shift Manager to Unit Supervisor, "Unit Supervisor (or student's name). verify the QPTR surveillance per RX1703. Record any issues that you find on the tear-off sheet. Correct any issues that you find. Discuss the results with me."

Page 13 of 13

ENER.. . SEABROOK JOB PERFORMANCE MEASURE 2013 NRC EXAM SRO-ADMJPM02, REVIEW SHUTDOWN MARGIN CALCULATION (MODE Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNEDI ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY: DATE: ________

JOB PERFORMANCE

1. Task Number and Description Position SRO SBK 1190202602 Review Results of Surveillance Tests 2. Conditions:

A. The plant is in Mode 3 at 55rF following a trip from 100% 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ago. B. On the trip, rod H-8 remained fully withdrawn.

Rod! H-8 will not move. C. An inadvertent dilution has occurred.

D. Chemistry reports that the RCS boron concentration is 1220 ppm. E. Cycle burnup is 9600 MWD/MTU. F. MPCS point C0036 Xenon worth is 5850 pcm. 3. Standards:

Using RX1707, Shutdown Margin Surveillance, review the boron concentration required to satisfy SDM for the present conditions using the figures from the Primary Tech Data Book provided by the instructor.

4. Student Materials:

Copy of Tear-Off Sheet Copy of RX1707, Shutdown Margin Surveillance Rev 7 Chg 7 Completed RX1707, Shutdown Margin Surveillance Form A Copy of Primary TDB, Figure RE-2, Shutdown Bomn Concentration vs. Temperature, Rev 01-16-06.

Copy of Primary TDB, Figure RE-18, Shutdown Margin Values, Rev 01-16-00.

Calculator

5. Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the 6.

References:

Procedures:

RX1707, Shutdown Margin Surveillance.

Technical Specifications:

3.1.1.1 Shutdown Margin greater than 200°F. Manuals:

Primary TDB, Figure RE-2 Shutdown Boron Concentration vs. Temperature.

SRO-ADMJPM02 Page 2 of 11 JOB PERFORMANCE WORKSHEET

Primary TDB, Figure RE-18 Shutdown Margin Values.

Page 3 of 11 JOB PERFORMANCE Value Sys Descri pti(m RO/SRO 192002 K1.13 Calculate SDM using I pre Icedures and 3.5/3.7 given plant parameter

s. 2.2.12 Knowledge of Surveill; an<Procedures 3.7/4.1 7. Setting: Use the simulator or the classroom.

A key must be setup using RE curves (RE curves may not be the latest revision).

The required RE curves are included in the student material package and must be given to the student when reaching for the Primary Tech Data Book. Failure to do this will cause unrealistic numbers for the student. Since an inadvertent dilution has occurred, pick a value for the current boron concentration that is below the value required by RE-2. SDM mayor may not be adequate depending on the value selected (i.e., how large the dilution was). 8. Safety Considerations:

None. 9. Approximate Completion Time: 20 minutes 10. Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for multiple You are the Unit Supervisor.

An inadvertent dilution has occurred.

Review the completed RX1707, Shutdown Margin Form A. State if the shutdown margin is adequate or not. The following information is provided to you: The plant is in Mode 3 at 557°F following a trip from 100% 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ago. On the trip, rod H-8 remained fully withdrawn.

H-8 will not move. An inadvertent dilution has occurred. Chemistry reports that the RCS boron concentration is 1220 ppm. Cycle burnup is 9600 MWD/MTU. Xenon credit is desired. MPCS point C0036 worth is 5850 pcm. The board operators have performed and independently verified a Shutdown Margin Surveillance per RX1707, Shutdown Margin Surveillance. We will begin after the Initiating Cue is read. SRO-ADMJPM02 Page 4 of 11 JOB PERFORMANCE I will act as the Shift Manager and provide cues and communications for this JPM. Do you have any questions?

11. Initiating Cue: Shift Manager to Unit Supervisor, "Unit Supervisor (or student's name), an inadvertent dilution has occurred.

Review the c:ompleted RX1707, Shutdown Margin Surveillance form. Record any issues that you find on the tear-off sheet. Correct any issues that you find. Discuss the results with me." SRO*ADMJPM02 Page 5 of 11 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

_-=>=."'=_S.=...;,;,.;im..:..,:u::..;,.la=.;t:.,=.e

__*--=-d:..=.e.:....:.n-=-ot::..=e-=..s--=-a,-c:..;..r.:..:citi-=-ca=l,--,s:....:.te

.:...Jp"---

______*....::.d--'-e_no-=--t:....:.e...:........:s a c'_"it_ic_a_1 s_t_e.L..p

________When student demonstrates the ability to obtain a controlled copy of RX1707, Shutdown Surveillance provide the student with RX1707, Shutdown Margin P Start time -----Initiating cue ,"ead If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task.," If the Shift Manager (Evaluator) is informed that the board operators did not factor in the stuck rod in the Shutdown Margin Surveillance respond, "The board operators are unavailable, use the correct forms and complete the Shutdown Margin Surveillance." Student recognizes that section 4.4, Shutdown Margin With Inoperable Rod(s) Immovable, Untrippable Or Dropped, is correct and that the plant is in Mode 3 and proceeds to step 4.4.2. COMPLETE Part II of Form Shutdown Margin Determination Immovable, Untrippable or P Number of Immovable and a. Enters 1 rod for Untrippable P Boron Equivalent Worth of Worst b. Enters H5 ppm/rod from RE-18 Case Immovable or Untrippable for (h)" Rod (Figure RE-18) P Required Increase in Shutdown c. Performs calculation and enters Boron Concentration 175 ppm (value i). [g X h = i] P Completed By signature.

d. Signs block. When the student requests the Independent Verification respond, "Independent Verification has been performed.

Please continue with the task." SRO-ADMJPIVI02 Page 6 of 11 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

_.::>-=-"'_=S..::....:..:.cim,-,-u:.:..:.lac:....t:..c:.e

__*--" d....:.e_n-=-otc:....:ce....::..s--"a,-c"-r--,,iti....:.c-=--al_s:....:.te

..:..Jp"--

______*--"d....:;.e_n-=--ot.:....;.e....:....-s a cl_rit....:.ic

....:.a_1-'-st:....;..e-'-p

_______S:.....A_T----"-U_N--'S....:.A..:..cT_

3. P For the existing RCS temperature, obtain the required shutdown boron concentration from Primary TDB, Figure RE-2 Shutdown Boron Concentration vs. Temperature.

4. *P RECORD the RCS Tavg and the corresponding RE-02 required shutdown boron concentration value (F) on Form 0, Shutdown Margin Verification

-MODEs 3, 4 And 5 With Inoperable Rod(s). 5. *P TRANSFER the value (i) from Form C, Shutdown Margin Determination Immovable, Untrippable or Dropped Rod(s), to item (G) on Form 0, Shutdown Margin Verification

-MODEs 3, 4 And 5 With Inoperable Rod(s). 6. *P On Form 0, Shutdown Margin Verification

-MODEs 3, 4 And 5 With Inoperable Rod(s), ADD together items (F) and (G) to calculate the adjusted shutdown boron concentration (H). For the existing RCS temperature, obtains the required shutdown boron concentratlion from Primary TDB, Figure RE-2 Shutdown Boron Concentration vs. Temperature.

Records the RCS Tavg of 557°F and the corresponding RE-02 required shutdown boron concentration value of 1410 ppm (F) on Form 0, Shutdown Margin Verification

-MODEs 3, 4 And 5 With Inoperable Rod(s). Transfers

'Ile; ppm from Form C, Shutdown Margin Determination Immovable, Lintrippable or Dropped Rod(s), to item (G) on Form 0, Shutdown Ma.rgin Verification

-MODEs 3, 4 And 5 With Inoperable Rod(s). On Form D, Shutdown Margin Verification

-MODEs 3, 4 And 5 With Inoperable Rod(s), Adds together items (F) and (G) to calculate the adjusted shutdown boron concentration (H) and enters 1585 ppm.

Page 7 of 11 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform s::....::t-=..Jepl:.....-

_____*_d.:::...e::..:.n..:..,:o:...:,.te::....::s:.....,:a cl..:..:*it.:.-=ic-=.:a.:,...1 s::....::t-=..Jepl:.....-

_______7. If credit for xenon is desired, Xenon credit is desired. PERFORM the following:

P a. OBTAIN the xenon worth from a. Obtains the xenon worth from the MPCS point C0036 or from MPCS point C0036 as stated in Reactor Engineering.

the student information.

P b. RECORD the xenon worth value b. Enters th'8 xenon worth value (J) (J) on Form D, Shutdown Margin of 5850 pcm on Form D, Verification

-MODEs 3, 4 And 5 Shutdown Margin Verification

-With Inoperable Rod(s). MODEs 4 And 5 With Inoperable Rod(s). P c. OBTAI N the correct value of c. Records the DBW value (K) of Differential Boron Worth (DBW) 8.596 on Form D, Shutdown from TDB Figure RE Margin Verification

-MODEs 3, 4 RECORD the DBW value (K) on And 5 With Inoperable Rod(s). Form D, Shutdown Margin Verification

-MODEs 3, 4 And 5 With Inoperable Rod(s). *P d. Using the equation [L = H -(J/K)] d. Performs calculation and records as shown on Form D, Shutdown the Adjus.ted Shutdown Boron Margin Verification

-MODEs 3, 4 Concentration value (L) of 904 And 5 With Inoperable Rod(s), ppm on Form D, Shutdown CALCULATE the Adjusted Margin V'8rification

-MODEs 3, 4 Shutdown Boron And 5 With Inoperable Rod(s). RECORD the Adjusted Shutdown Boron Concentration value (L) on Form D, Shutdown Margin Verification

-MODEs 3, 4 And 5 With Inoperable Rod(s). If the number is negative, RECORD a zero. 8. P RECORD the Existing RCS Boron Record the Existing RCS Boron value value (M) on Form D, Shutdown (M) of 1220 ppm on Form D, Margin Verification

-MODEs 3, 4 And Shutdown Margin Verification 5 With Inoperable Rod(s). MODEs 3,4 And 5 With Inoperable Rod(s).

Page 8 of 11 PERFORMANCE D=Discuss P=Perform 3=Simulate ELEMENT/STEP

denotes a critical step 9. *P CHECK if existing RCS Boron (M) is greater than the Shutdown Boron (L) and mark the associated block as Yes or No as applicable.

10. Performed by initials.

CUE: "The JPM is complete." Stop time ____ Evaluator calculates time to complete task Obtain from student: Tear Off sheets and any other training materials used in performance of this ..IPM. STANDARD

denotes a ctitical step Checks it RCS Boron (M) is greater than the Shutdown Boron (L) and mark the associated block as YES. EVALUATION SAT UNSAT Initials Performed by line. Time to complete task S 20 minutes Page Sot 11

, , PERFORMANCE SUMMAFlY Provide comments on unsatisfactory performance of an or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Page 10 of 11 y, TEAR OFF SHEET FOR SRO ADMIN JPM 02 Directions To The Student: You are the Unit Supervisor.

An inadvertent dilution has occurred.

Review the completed RX1707, Shutdown Margin Surveillance Form A. State if the shutdown margin is adequate or not. The following information is provided to you: The plant is in Mode 3 at 55r'F following a trip from 100% 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ago. On the trip, rod H-8 remained fully withdrawn.

Rod H-8 will not move. An inadvertent dilution has occurred. Chemistry reports that the RCS boron concentration is 1220 ppm. Cycle burnup is 9600 MWD/MTU. Xenon credit is desired. MPCS point C0036 Xenon worth is 5850 pcm. The board operators have performed and independently verified a Shutdown Margin Surveillance per RX1707, Shutdown Margin Surveillance. We will begin after the Initiating Cue is read. I will act as the Shift Manager and provide cues and communications for this JPM. Do you have any questions?

Initiating Cue: Shift Manager to Unit Supervisor, "Unit Supervisor (or student's name), an inadvertent dilution has occurred.

Review the completed RX1707, Shutdown Margin Surveillance form. Record any issues that you find on the tear-off sheet. Correct any issues that you find. Discuss the results with me."

Page 11 of 11 JOB PERFORMANCE MEASURE 2013 NRC EXAM SRO-ADMJPM03, FINAL APPROVE SPENT FUEL POOL BLENDED MAKEUP CALCULATION Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: ______-------------TRAINING JOB PERFORMANCE Task Number and Description Position RO SBK 0040100601 Perform a boron change calculation. Conditions:

A. A manual blended makeup to the Spent Fuel Pool is required to raise pool level. Standards:

Approve a calculation of the required flow controller and totalizer setpoints for a 550 gallon manual blended makeup to the Spent Fuel POCII. Student Materials:

Copy of Tear Off Copy of RS1735, Reactivity Calculations,'

Rev Copy of RS1735, Reactivity Calculations completed Form Daily Chemistry Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures:

RS1735, Reactivity Calculations, Rev 6 Value Sys KA I RO/SRO i 2.1.37 Knowledge of procedures, guidelines, or 4:]limitations associated with reactivity management.

Page 2 of 8 JOB PERFORMANCE Setting: Classroom. Give student a copy of the RS1735, Reactivity Calculations completed Form E. Examiner must prepare a completed RS1735, Reactivity Calculations, Form E in advance. It shall reflect the JPM values for the values listed in Daily Chemistry Report. Safety Considerations:

None. Approximate Completion Time: 15 minutes Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for multiple Ensure task is done correctly. You may be asked follow up questions to confirm knowledge of the task. You are the Unit Supervisor.

You are going to approve calculations for a 550 gallon blended makeup to the Spent Fuel Pool on RS1735, Reactivity Calculations, Form E. The following information is provided to you: A 550 gallon manual blended makeup to the Spend Fuel Pool is required for pool inventory addition. Makeup total flow rate will be 50 gpm. The makeup boron concentration will be at the! current Spent Fuel Pool boron concentration. 'A' Boric Acid Storage Tank will be used for thf9 blended makeup. The makeup line contains a blend from a prevIous SFP makeup based on the same SFP and BAST values.

Page 3 of 8 JOB PERFORMANCE We will begin after the Initiating Cue is read. I will act as the Shift Manager and provide cues and communications for this JPM. Do you have any questions?

11. Initiating Cue: Shift Manager to Unit Supervisor, "Unit Supervisor (or student's name), approve calculations for a 550 gallon blended makeup to the Spent Fuel Pool on RS1735, Reactivity Calculations, Form E. Record any issues that you find on the tear-off sheet. Correct any issues that y(>u find. Discuss the results with me."

Page 4 of 8 PERFORMANCE D=Discuss ELEMENT/STEP EVALUATION 0=Perform 3=Simulate

denotes a critical step

denotes a critical SAT UNSAT 1. Start time _____ Initiating cue read If the student requests a Peer Check at any during tl1e JPM respond, "No one is available to Peer Check your actions. Please continue with the task." When the student demonstrates the ability to obtain a controlled copy of RS1735, Reactivity Calculations, provide the student with a copy. Student should refer to section 4.4 Blended Makeup Calculation (Form E, Blended Makeup Worksheet) and the Daily Chemistry Report to determine Spent Fuel Pool (SFP) and boric acid storage tank boron concentration. P Approve calculations for a 550 blended makeup to the Spent Pool on RS1735, Calculations, Form Verifies the desired makeup 1 ENTER the desired makeup boron concentration (C MU) for the . boron concentration (C MU)' 1. SFP from the Daily Chemistry Report in step 1 of Form E. ENTER the desired makeup flow Verifies the desired makeup flow 2. rate SETPOINT:

FIQ-111 (F). 2. rate SETPOINT:

FIQ-111 (F TOT)ToT in step 2 ()f Form E. (50 gpm) Verifies the actual Boric Acid ENTER the actual Boric Acid Tank concentration

3. Storage Tank concentration

3. (C SAST) fmm the Daily Chemistry (C BAST)' Report in step 3 of Form E. Verifies the desired makeup ENTER the desired makeup quantity TARGET: FIQ-111 4. quantity TARGET: FIQ-111 4. (G TOT) in step 4 of Form E. (550 (G TOT). gallons) Verifies the values from steps 1, 2 & 3 are I;mtered in the equation *5. CALCULATE the boric acid flow *5. and the calculated value for the rate SETPOINT:

FIQ-111 (F BA): boric acid flow rate SETPOINT: (F sA) is correct. SRO-ADMJPM03 Page 5 of 8 PERFORMANCE CHECtCLIST D=Discuss ELEMENT/STEP P=Perform

.3=Simulate

denotes a critical step CALCULATE the boric acid *6. quantity TARGET: FIQ-111 (G BA): 7 SRO Approval By signature and . Date. CUE: "The JPM is complete." Stop time ____ Evaluator calculates time to complete task Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. STANDARD EVALUATION

denotes a critical step SAT UNSAT *6. Verifies the values from steps 1, 3 & 4 are entered in the equation and calculated value for the boric acid quantity TARGET: FIQ-111 (G BA) is correct. Signs and dates the Approval By 7. signature and Date line. Time to complete task :$15 minutes Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an elementlst,sp or for any deviation from performance as stated. Record interruptions in performance such ciS retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Page? of 8 TEAR OFF SHEET FOR RO ADMIN JPM Directions To The Student: You are the Unit Supervisor.

You are going to approve calculations for a 550 gallon blended makeup to the Spent Fuel Pool on RS1735, Reactivity Calculations, Form E. The following information is provided to you: A 550 gallon manual blended makeup to the Spend Fuel Pool is required for pool inventory addition. Makeup total flow rate will be 50 gpm. The makeup boron concentration will be at the current Spent Fuel Pool boron concentration. 'A' Boric Acid Storage Tank will be used for the blended makeup. The makeup line contains a blend from a previous SFP makeup based on the same SFP and BAST values. We will begin after the Initiating Cue is read. I will act as the Shift Manager and provide cues cmd communications for this JPM. Do you have any questions?

Initiating Cue: Shift Manager to Unit Supervisor, "Unit Supervisor (or student's name), approve calculations for a 550 gallon blended makeup to the Spent Fuel Pool on RS1735, Reactivity Calculations, Form E. Record any issues that you find on the tear-off sheet. Correct any issues that you find. Discuss the results with me."

Page 8 of 8

JOB PERFORMANCE MEASURE 2013 NRC EXAM VERIFY A LIQUID EFFLUENT WASTE SAMPLE Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

JOB PERFORMANCE

1. Task Number and Description Position SRO SBK 0690301502 Authorize a release of liquid waste. 2. Conditions: The plant is in MODE 1 with two ocean Service Welter and two Circulating Water pumps running with no expected change of configuration. WL-TK-63A, "A" Waste Test Tank has been filled to 18,000 gallons. WL-TK-63A, "A" Waste Test Tank, was placed on recirculation at 0800 today per ON1018.07 , Waste Test Tank Recirculation. WL-TK-63A, "A" Waste Test Tank has to be samplf3d to prepare a LEW permit for a release to the transition Structure. Projected release start time is normally 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months aftl3r placing the tank on recirc. The Primary Operator has completed Section 1 of CP 4.1A, Liquid Effluent Waste Sample Requests.

3. Standards:

Using CP-4.1, Effluent Sampling Program and ON1 01 8.07, Waste Test Tank Recirculation, verify the following: Form CP4.1A, Liquid Effluent Waste Sample Request 4. Student Materials:

Calculator Copy of Tear Off Sheet. Copy of CP-4.1, Effluent Sampling Program Copy of blank Form CP4.1A, Liquid Effluent Waste Sample Request Copy of ON1018.07 , Waste Test Tank Recirculation Copy of completed Form CP4.1A, Liquid Effluent Waste Sample Request 5. Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the 6.

References:

Procedures: CP-4.1, Effluent Sampling Program ON1018.07 , Waste Test Tank Recirculation Value Sys Description RO/SRO SRO-ADMJPM04 Page 2 of 8 JOB PERFORMANCE Setting: Simulator or Classroom. Safety Considerations:

None. Approximate Completion Time: 15 minutes Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for multiple Ensure task is done correctly. You may be asked follow up questions to confirm knowledge of the task. You are the Unit Supervisor.

You are going to perform the verification of a Liquid Effluent Waste Sample Request, using the information provided. The following information is provided to you: The plant is in MODE 1 with two ocean Service Water and two Circulating Water pumps running with no expected change of configuration. WL-TK-63A, "A" Waste Test Tank has been filh9d to 18,000 gallons. WL-TK-63A, "AI) Waste Test Tank, was placed on recirculation at 0800 today per ON1018.07 , Waste Test Tank Recirculation. WL-TK-63A, "AI) Waste Test Tank has to be sampled to prepare a LEW permit for a release to the transition Structure. Projected release start time is normally 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after placing the tank on recirc. The Primary Operator has completed Section 1 of CP 4.1A, Liquid Effluent Waste Sample Request. SRO-ADMJPM04 Page 3 of 8 JOB PERFORMANCE We will begin after the Initiating Cue is read. I will act as the Shift Manager and provide the cues and communications for this JPM. Do you have any questions?

11. Initiating Cue: Shift Manager to Unit Supervisor, "Unit Supervisor (c,r student's name), Section 1 of Form CP 4.1A is complete.

Please perform the verification.

Record any issues that you find on the tear-off sheet. Correct any issues that you find. Discuss the results with me."

Page 4 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION o:;:Perform

___

___________

__________

__ When the student demonstrates the ability to obtain a contmlled copy of CP-4.1, Effluent Program and ON1018.07, Waste Test Tank Recirculation, provide the student with the

1. Start time _____ Initiating cue read If the student requests a Peer Check at any time during the .JPM respond, "No one is available to Peer Check your actions. Please continue with the It is assumed that the student will use CP 4.1 to process through the verification and ON1018.07 to verify the tank volumes and recirculation flow rate. The student may choose to the tank volume and recirculation rate prior to referring to CP 4.1. These steps can be performed any order as long as all steps are completed

2. Section 1 of CP 4.1A is completed Operations and provides the Name of tank, sump, or SG a. Verifies 'I'm "An is entered. a. demin vessel to be sampled. If the student wants to verify the amount of liquid in the "A" Waste Test Tank using the Plant Computer, tell them that the MPCS indicates 18,000 Notes 18,000 gallons are Total tank or sump volume to be b. consistent with initial conditions

b. discharged or transferred.

and indications. The recirculation rate for WIT A is actually 150 gpm. Waste Holdup Sump recirculation rate is gpm. The student must correct this mistake to ensure adequate tank recirculation prior to If the Shift Manager (Evaluator) is informed that the recirculcltion rate is incorrect, say "The Primary Operator must have been thinking about the Waste Holdup Sump recirculation rate." If the student (Unit Supervisor) gives the form back to the Primary Operator to correct, say: "Use your corrected values and complete the verification." SRO*ADMJPM04 Page 5 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION D=Perform

--=.-'_=-=-S::..:..:im:...:..:u::..:.la=-t:..::e

__*--=d:..::e..:...,:n-=-ot.::..,:e-=.s--=a.:,...c::..:.r..:..:.iti:..,:.c.::.:.a:....,;1 s:...,:te.=..JPI:.....-

______*--=d:..,:.e..:...,:n..:..ot.::..,:e-=.s....::;a cr:...:..:iti..:..ca=-l--=s-=.te

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_____----"'S.:,...A:....:.T_L=--

'N:....:....:..SA

.....:...:...T_

Corrects the recirculation rate to Recirculation rate. *c. 150 gpm ;and the recirculation required time to be 240 minutes. Recirculation starting time and d. Verifies 0:300 and today's date. date. e. Sample date and time, Corrects sample time to 1200. Verifies DISCHARGE asDisposition of tank. f. disposition.

The projected CW and SW pump Verifies 2 CW pumps and 2 SW g.combination for the discharge.

pumps entered. Projected release start date and Corrects projected start time toh.2000. Date, time of request, and initials Verifies time, date and initials are i.of entered. Date, and initials of individual that performed

j. Enters date, time, and initials.

verification of operational data. CUE: "The ..IPM is complete." 3. Stop Time to complete task :S 15 minutes Evaluator calculates time to Obtain from Tear Off sheets and any other materials used in performance of Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial if necessary.

Page 7 of 8

-f .. TEAR OFF SHEET FOR SRO ADMIN JPM 04 Directions To The Student: You are the Unit Supervisor.

You are going to perform the verification of a Liquid Effluent Waste Sample Request, using the informaltion provided. The following information is provided to you: The plant is in MODE 1 with two ocean Service Water and two Circulating Water pumps running with no expected change of configuration. WL-TK-63A, "A" Waste Test Tank has been filled to 18,000 gallons. WL-TK-63A, "A" Waste Test Tank, was placed on recirculation at 0800 today per ON1018.07 , Waste Test Tank Recirculation. WL-TK-63A, "A" Waste Test Tank has to be sampled to prepare a LEW permit for a release to the transition Structure. Projected release start time is normally 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after placing the tank on recirc. The Primary Operator has completed Section 'I of CP 4.1A, Liquid Effluent Waste Sample Request. We will begin after the Initiating Cue is read. I will act as the Shift Manager and provide the cues and communications for this ,JPM. Do you have any questions?

Initiating Cue: Shift Manager to Unit Supervisor, "Unit Supervisor (or student's name), Section 1 of Form CP 4.1A is complete.

Please perform the verification.

Record any issues that you find on the tear-off sheet. Correct any issue's that you find. Discuss the results with me." SRO-ADMJPM04 Page 8 of 8 JOB PERFORMANCE MEASURE 2013 NRC EXAM SRO-ADMJPM05, GENERAL EMERGENCY PROTECTIVE ACTION REQUIREMENTS Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: __________ DATE: APPROVED BY: __________ TRAINING JOB PERFORMANCE

1. Task Number and Description SRO SBK Perform Required Notification of On-Site and Off-Site Personnel for Emergency Events 2. Conditions: The plant has tripped from 100% power due to CI LOP today at 1300. The US has transitioned from E-O to ECA-O.O. No Emergency Diesel Generators or SEPS Diesels are available. The event has been classified as a General Eml3rgency based on EAL SG1, Prolonged loss of both AC emergency buses. Rlestoration of either emergency bus is not expected within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The time of E-Plan declaration was 1323. A release has not occurred. The Remote Monitoring Area (RMA) has not beEm activated. Form ER 2.0B, State Notification Fact Sheet is c:omplete and the states were notified at 1333. There is a 10 mph wind. LOWER wind direction is coming FROM 285 UPPER wind direction is coming FROM 305 The appropriate PAR Group A has been recomrnended to the states. At 1355 the Shift Manager is re-assessing plant conditions in accordance with ER 1.20, General Emergency Checklist

-STED, Step 11, Follow up PAR Assessment. Critical Safety Functions (CSF) have been verifiled and are as follows: CORE COOLING (C) ORANGE Path -go to FR-C.2 HEAT SINK (H) RED Path -go to FR-H.1 CONTAINMENT (Z) RED Path -go to FR-Z.1 INVENTORY (I) YELLOW Path -go to FR-H.1 3. Standards: The student will start in ER 1.2, Emergency Plan Activation, Form 0, General Emergency Checklist

-STED, Step 11. The student will transition to ER 1.2G, General Emergency PAR Worksheet, to determine if upgraded protective action recommendations are warranted. The student will notify the STED of the PAR recommendation within 15 minutes. 4. Student Materials:

Copy of Tear-Off Sheet Copy of Form ER 2.0B, State Notification Fact SheE!t Copy of ER 1.2, Emergency Plan Activation, Form D, General Emergency Checklist STED, place kept up to Step 11. SRO-ADMJPM05 Page 2 of 10 JOB PERFORMANCE Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the ..

References:

Procedures: ER 1.2, Emergency Plan Activation ER 2.0, Emergency Notification Documentation Forms Procedure Sys Knowledge of emergency plan p action recommendations. Setting: Simulator or Classroom Safety Considerations:

None. Approximate Completion Time: 15 minutes Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for multiple This is a TIME CRITICAL task. You are the Work Control Supervisor.

The STED directs you to re-assess plant conditions in accordance with ER 1.2D, General Emergency Checklist

-STED, Step 11, Follow up PAR Assessment, to determine if upgraded protective action recommendations are warranted.

If upgraded PARs are warranted, inform the STED of your upgraded PAR recommendation at the completion of ER 1.2G, step 4.

Page 3 of 10 JOB PERFORMANCE The following information is provided to you: The plant has tripped from 100% power due to a LOP today at 1300. The US has transitioned from E-O to ECA-O.D. No Emergency Diesel Generators or SEPS Diesels are available. The event has been classified as a General Emergency based on EAL SG1 , Prolonged loss of both AC emergency buses. Restoration of either emergency bus is not expected within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The time of E-Plan declaration was 1323. A release has not occurred. The Remote Monitoring Area (RMA) has not activated. Form ER 2.0B, State Notification Fact Sheet is complete and the states were notified at 1333. There is a 10 mph wind. 10. LOWER wind direction is coming FROM 28Ei

11. UPPER wind direction is coming FROM 305 degrees. 12. The appropriate PAR Group A has been recommended to the states. 13. At 1355 the Shift Manager is re-assessing pilant conditions in accordance with ER 1.20, General Emergency Checklist

-STED, Step 11, Follow up PAR Assessment.

14. Critical Safety Functions (CSF) have been verified and are as follows: CORE COOLING (C) ORANGE Path -to FR-C.2 HEAT SINK (H) RED Path -go to FR-H.1 CONTAINMENT (Z) RED Path -go to FR-Z.1 INVENTORY (I) YELLOW Path -go to FR-H.1 We will begin after the Initiating Cue is read. I will act as the Short Term Emergency Director (STED) and provide the cues and communications for this JPM. Do you have any qUI;lstions?

11. Initiating Cue: STED to Work Control Supervisor, "Work Control Supervisor (or student's name): Re-assess plant conditions in accordance with ER 1.20, General Emergency Checklist

-STED, Step 11, Follow up PAR to determine if a PARs upgrade is warranted. If upgraded PARs are warranted, inform me I:>f your upgraded PAR recommendation at the completion of ER 1.2G, step 4. This is a TIME CRITICAL task. Record any issues that you find on the tear-I)ff sheet. Discuss the results with me."

Page 4 of 10 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION D=Perform

---=-->_=S.::...i:..:..cm..:....:u.:..:..:la:..:..ct

..::....e__* ..::....de-=--n--=0c...::.te-=--s,-a,,---,-cr_it:.....:ic--=-a_1 s.:....:t...::...eL

...p______* _de_n_o_te_s_a cri_tic_a_l_s_te-'-p

_______S_A_T_L_IN_SA_T_ This is a TIME CRITICAL task. A new PAR recommendation is required within 15 minutes of starting the JPM. 1. Start time _____ Initiating cue nead If the student requests a Peer Check at any tim.e during the .JPM respond, "No one is available to Peer Check your actions. Please continue with the ta!.k." P Student starts at with ER 1.20, Student transitions to form ER General Emergency Checklist

-General Emer!;]ency PAR STED, Step 11, Follow up Assessment to determine if a upgrade is P Using form ER 1.2G, Emergency PAR Worksheet, determines if upgraded action recommendations Block 1: Student mcognizes the plant is in1.

a GENERAL EMERGENCY.

Block IS THE CORE Student mcognizes that NO, COOLING CSFST 2. CORE COOLING CSFST is PROCEEDING ALONG A RED ORANGE.PATH? Block IS THE CONTAINMENT Student that YES, 3. CSFST PROCEEDING ALONG A 3. CONTAIt\IMENT CSFST is RED..RED PATH? Student identifies transition to PAR GROUP B *4. PAR Group B and goes to Page 2 GO TO PAGE 2 OF THIS FORM of Form G.

Page 5 of 10 PERFORMANCE D=Discuss ELEMENT/STEP D=Perform 3=Simulate

denotes a critical step P For a PAR Group B selection, the student uses the following instructions and table to determine Protective Action Recommendations.

If a release is in progress from the plant vent, enter the current upper wind. If a release from the plant vent is NOT in progress, enter the current lower wind direction.

Identify the appropriate PAR GROUP B column based on the above wind direction to determine the towns to be evacuated and sheltered.

Check off the evacuated and sheltered towns and evacuated

4. and closed beaches on form ER 2.0B, Block 4. Check off "Implement KI plans for the general public" on form ER 2.0B, Block 4. 4. Student informs STED of new PAR recommendation.

End time _____ STANDARD EVALUATION

- .denotes a critical step SAT UNSAT Student identifies no release is in 1. progress from the plant vent. Studer:lt enters the current lower 2. wind direction of 285 degrees. Student identifies the correct PAR GROUP B column based on the above wind direction and determines the towns to be evacuated and sheltered.

Student checks off the evacuated and sheltered towns and 4. evacuated and closed beaches on form ER 2.0B, Block 4. Student checks off "Implement KI plans for the general public" on form ER 2.0B, Block 4. Time to complete task S 15 minutes Page 6 of 10 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION o=Perform

___________

____________

__ CUE: "The JPM is complete." 5. Stop time ____ Time to complete task S 15 minutes Evaluator calculates time to complete task Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM.

Page 7 of 10 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such aB retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Page 8 of 10 JOB PERFORMANCE Directions To The Student: This is a TIME CRITICAL task. You are the Work Control Supervisor.

The STED directs you to re-assess plant conditions in accord.:mce with ER 1.20, General Emergency Checklist

-STED, Step 11, Follow up PAR Assessment, to determine if upgraded protective action recommendations are warranted.

If upgraded PARs are warranted, inform the STED of your upgraded PAH recommendation at the completion of ER 1.2G, step 4. The following information is provided to you: The plant has tripped from 1 00% power due to a LOP today at 1300. The US has transitioned from E-O to ECA-O.O. No Emergency Diesel Generators or SEPS Diesels are available. The event has been classified as a General Emergency based on EAL SG1, Prolonged loss of both AC emergency buses.

of either emergency bus is not expected within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The time of E-Plan declaration was 1323. A release has not occurred. The Remote Monitoring Area (RIVIA) has not bf:!en activated. Form ER 2.0B, State Notification Fact Sheet is complete and the states were notified at 1333. There is a 10 mph wind. 10. LOWER wind direction is coming FROM 28:5 degrees. 11. UPPER wind direction is coming FROM 3m; degrees. 12. The appropriate PAR Group A has been recommended to the states. 13. At 1355 the Shift Manager is re-assessing plant conditions in accordance with ER 1.20, General Emergency Checklist

-STED, Step 11, Follow up PAR Assessment.

14. Critical Safety Functions (CSF) have been verified and are as follows: CORE COOLING (C) ORANGE Path -to FR-C.2 HEAT SINK (H) RED Path -go to FR-H.1 CONTAINMENT (Z) RED Path -go to FR-Z.1 INVENTORY (I) YELLOW Path -go to FR-H.1 We will begin after the Initiating Cue is read. I will act as the Short Term Emergency Director (STED and provide the cues and communications for this JPM. Do you have any questions?

Page 9 of 10 JOB PERFORMANCE Initiating Cue: STED to Work Control Supervisor, "Work Control Supervisor (or student's name): Re-assess plant conditions in accordance with ER 1.20, General Emergency Checklist

-STED, Step 11, Follow up PAR to determine if a PARs upgrade is warranted. If upgraded PARs are warranted, inform me of upgraded PAR recommendation at the completion of ER 1.2G, step 4. This is a TIME CRITICAL task. Record any issues that you find on the tear-off sheet. Discuss the results with me." SRO-ADMJPM05 Page 10 of 10

CONTROL ROOM JOB PERFORMANCE MEASURE 'A', PRESSURZER LEVEL CHANNEL Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINA'TION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: ------=TRA::::-:--:-:c l N--:-:-:I NC-:-:G=--S::-:-"U"""'P-=ER:-:-V":'::"":I JOB PERFORMANCE Task Number and Description Position RO SBK 0110400101 Identify A Pressurizer Instrument Failure Conditions:

A. The plant is at 100% power and all systems are n()rmal. Standards:

Identify a failed Pressurizer level instrument channel and restore the system per OS1201.07 , PZR Level Instrument Failure. Student Materials:

Copy of Tear Off Copy of OS1201.07, PZR Level Instrument Failure Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures:

OS1201.07 , PZR Level Instrument Technical

3.3.1 Reactor Trip System Instrumentation. 3.3.3.6 Accident Monitoring Instrumentation.

Value Sys Descriptkm RO/SRO 011 A2.11 Ability to (a) predict the impacts of the 3.4/3.6 following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct control, or mitigate the consequences of those malfunctions or operations:

Failure of PZR level instrument

-low Control Room Page JOB PERFORMANCE Setting: Simulator:

Reset the simulator to IC #154 or any 100% IC which contains the following: Initialize the simulator to a 100% power IC. Place the simulator in RUN. Ensure that L T -459 is selected for master PZR levlel control and for the PZR level recorder.

Malfunctions have additional time added so that alarms can be acknowledged.

Do not exceed 60 seconds of run time during setup to ensure malfunctions do not initiate.

Place the simulator in FREEZE. Safety Considerations:

None. Approximate Completion Time: 20 minutes Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Primary Operator.

An event will occur. You are expected to identify the event and recommend actions and/or procedunes to implement. The following information is provided to you: The plant is at 100% power and all systems are normal. We will begin after the Initiating Cue is read. I will provide cues and communications for this JPM. Do you have any questions? Initiating Cue: US to Primary Operator, "You are the Primary Operator respond to any condition that arises." Control Room 'A' Page 3 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT 1. Start time _____ I nitiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." Insert PZR Level 459 fails low as SELECT: Malfunction SELECT: Reactor Coolant SELECT: ItRCSL T SELECT: Fails SELECT: If student recommends using 'Skill of the Operator' to reduce charging to seals only, US respond, "I concur." P Recognize and report that LT-459 is Recognizes and reports that L T-459 failed low. failed If student recommends entering OS1201.07 PZR Level Instrument Failure, US respond. "I concur." Give the student a copy of 081201.07 , PZR Level Instrument Failure. P Check PZR level channels: Controlling channel failed Backup channel failed

Recorder channel failed. Checks PZIR level channels and reports L T-459 is the controlling channel and is; failed low. Control Room 'A' Page 4 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

___________

__ S_A_T__U_N_S_A_T*_d_e_n_ot_e

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__ NOTE: Caution and Note prior to step 2 of OS1201.07 should be* read. *4. PRealign PZR level instruments: Manually control PZR level at program: Select an alternate level channel for Control/Backup as necessary. Select an alternate level channel for recorder as necessary.

5. Verify PZR heaters ON as follows: Reset or manually control PZR heaters as necessary. P Check if letdown was isolated:

Letdown isolation valves -closed RC-LCV-459 RC-LCV-460

7. Check if normal letdown can established: Verify charging flow -greater than 50 gpm. PZR level -greater than 17% Realigns PZR level instruments: Reduces charging flow. seal injection flow as Selects alternate level channels L-461/ L-460. Selects an alternate level channel for recorcier as necessary: L-461 Resets the PZR control group of heaters. Checks if was isolated and identifies that RC-LCV-459 is closed. Checks if normal letdown can be established: Verifies or adjusts charging flow greater trlan 50 gpm. Verifies PZR level -greater than 17%. Control Room 'A' Page 5 of 9

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

__3_=S im_u_la_t_e

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__ S_A_T U_N_S_A_T__ ___ *_d_e_n_ot_e

_____________

__ __ P Establish normal letdown: Establishes normal letdown: Align PCCW to the letdown heat a. exchanger: CC-V-341 -open CS-TK-130

-auto Close letdown flow control valves: *b. CS-HCV-189 CS-HCV-190 Open letdown isolation valves: *c. a) RC-LCV-459

b) RC-LCV-460 c) CS-V-145

Verifies PCCW to the letdown heat exchanger CC-V-341-open CS-TI<-130

-auto Closes/checks closed letdown flow control valves: CS-HCV-189 CS-HCV-190 Opens/checks open letdown isolation valves: a) RC-LCV-459 b) RC-LCV-460 c) CS-V-145 The student should take manual control of CS-PK-131 and open CS-PCV-131 to approximately 20%, then slowly open a flow control to establish letdown flow. When CS-PK-131 input pressure equals setpoint pressure (about 350 psig), the student should return CS-PK-131 to auto. Manually control or monitor PK-131 response and establish letdown flow using letdown flow control valve(s). CS-HCV-189 CS-HCV-190 Manually controls or monitors CS-PK-1 :31 response and letdown flow using letdown f10w control valve(s). CS-HCV-189 CS-HCV-190 Control Room 'A' Page 6 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT CUE: "The JPM is complete." Stop time ____ Time to complete task :S 20 minutes Evaluator calculates time to Obtain from Tear Off sheets and any other materials used in performance of Control Room 'A' Page 7 of 9 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Control Room 'A' Page 8 of9 TEAR OFF SHEET FOR CONTROL ROOM 'A' JPM Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Primary Operator.

An event will occur. You are expected to identify the event and recommend actions and/or procedures to implement. The following information is provided to you: The plant is at 100% power and all systems are normal. We will begin after the Initiating Cue is read. I will provide cues and communications for this JPM. Do you have any questions?

Initiating Cue: US to Primary Operator, "You are the Primary Operator respond to any condition that arises." Control Room 'A' Page 9 of 9

CONTROL ROOM JOB PERFORMANCE MEASURE 'B', TRANSFER SERVICE TO THE COOLING Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINA'TION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: ------=TRA::-:-:-::I N-:-:-:I N:-:-:G=-S=-=-U"7-:=P=-:E R=-=-V-:-:-:I JOB PERFORMANCE

1. Task Number and Description RO SBK Switch From SW To Cooling Tower Operation

2. Conditions: The plant is operating at 100% power. On line maintenance needs to be done on the Service Water system Train A. The Shift Manager requested that Service Water Train A be transferred to the Cooling Tower until the job is complete in approximately 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Local pre-starts are complete on the "An Cooling Tower pump. 3. Standards:

Place the Cooling Tower in operation per OS1016.05, Service Water Cooling Tower Operation.

4. Student Materials: Copy of Tear-Off Sheet Copy of OS1016.05 , Service Water Cooling Tower Operation, Rev. 23 Copy of OS1016.05 , Service Water Cooling Tower Operation, Pre-Job Brief Copy of 001-5 Pump Prestart Guidelines

-SW-P-110A Rev. 01 Copy of OS1216.01 , Degraded Ultimate Heat Sink, Rev. 22 5. Limitations On Performance:

Simulate/Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the ..6.

References:

Procedures: OS1016.05 , Service Water Cooling Tower Operation Value Sys Oescri ptic m RO/SRO 076 A2.01 Ability to predict the in 1pa ct of and use 3.5/3.7 procedures to control alo ss ofSW. 076 Knowledge of the effe ctt hat a loss or 3.4/3.6 malfunction of SW will he Ive on closed cooling water system. Control Room 'B' Page 2 of 14 JOB PERFORMANCE Setting: Simulator:

Reset the simulator to IC #154 or any 100% IC which contains the following: Initialize the simulator to a 100% power IC. Place the simulator in RUN. Insert/verify inserted Service Water (Component) malfunction csSWV20, fail as is. Place the simulator in FREEZE. Safety Considerations:

None. Approximate Completion Time: 30 minutes Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Secondary Operator. The following information is provided to you: The plant is operating at 100% power. On line maintenance needs to be done on the Service Water system Train A. The Shift Manager requested that Service Water Train A be transferred to the Cooling Tower until the job is complete in approximately 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Initial Cooling Tower level has been recorded on Form L, Cooling Tower flush NPDES tracking sheet. Local pre-starts are complete on the "An Cooling Tower pump. Previous pump start was two days ago. Perform the task using OS1016.05, Service Walter Cooling Tower Operation. The US will provide cues and communications fc)r this JPM. Do you have any questions?

Control Room 'B' Page 3 of 14 JOB PERFORMANCE

11. Initiating Cue: US to Secondary Operator, "Secondary Operator (oir student's name), all Prerequisites are complete.

Review OS1016.05lPrecautions and the Service Water Cooling Tower Operation Pre-Job Brief. Then tr,ansfer Service Water Train A from the Ocean to the Cooling Tower per OS1016.05 section 4.3." Control Room 'B' Page 4 of 14 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT CUE: Student will perform a Pre-Job Brief for this evolution.

When student responds that his review of OS1016.05 Prerequisites and Precautions and the Service Water Cooling Tower Operation, Pre-Job Brief is complete, respond "Prerequisites are complete.

Please continue with the task." 1. P Start time _____ When student is directed to continue with the task. CUE: If the student requests a Peer Check at any time during the ,JPM respond, "No one is available to Peer Check your actions. Please continue with the task.'" 2. OS1016.05, section 4.3, Transferring Only Train A Service Water System From the Ocean to the Cooling Tower P Record initial cooling tower level on Form L, Cooling Tower Flush NPDES Tracking Sheet. P 2 Perform pump pre-starts for 2 Performs control room pre-start P-110A, Cooling Tower pump A, checks for SW-P-11 O-A per as determined by the US. 5. P 3 Verify SW-V-5, SW isolation to 3 Verifies SW-V-5 is open. secondary loads is open. P 4 Verify SW-V-139, SW Cooling 4 Verifies SW-V-139 is open. Tower Train A spray bypass recirculation is open *P 5 Close SW-V-4, SW isolation to 5 Closes S\N-V-4. secondary loads. Control Room 'B' Page 5 of 14 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

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S_A_T_U_N__S_A_T__ P Check closed/Close SW-V-74, 6 Checks closed SW-V-74. turbine building SW connect to PAB. If requested by student make a plant announcement, "St.:utiing Service Water pump 110A." *P 7 Start SW-P-110-A, Cooling Tower pump A. *P 8 Place the Train A standby SW pump control switch in Lock. *P 9 Shutdown the running Train A SW pump and place its control switch in Pull-To-Lock.

P 10 Open SW-V-54, Cooling Tower pump A discharge isolation.

P 11 When SW-V-54 indicates full open place SW-V-54 control switch in auto. P 12 Verify SW-V-56, Cooling Tower Train A spray header test, auto closed. 7 Starts SW-P-110-A.

8 Places SW-P-41 C in PTL. 9 Stops S\I\I-P-41 A and places control switch in PTL. 10 Opens SW-V-54. 11 When SW-V-54 is full open places control switch in auto. 12 Verify S\I\I-V-56 auto closed. After the student reads the step to manually control PCCW heat exchanger outlet temperature using CC-TK-2171 (Train A), provide cue, "The Primary Operator is monitoring PCCW heat exchanger outlet temperature." Control Room 'B' Page 6 of 14 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD

__u_la_te___*_d_e_n_o_te_s_a

__

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_d_e_n_o_te_s

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__ P 13 If required, manually control PCCW heat exchanger outlet temperature using CC-TK-2171 (Train A) *P 14 Flush the Train A SW system to 14 Flushes to the ocean for at least discharge transition structure for 103 seconds prior to proceeding at least 103 seconds, then to the next step. continue with next step. After candidate starts timing of flush give the following, "103 seconds have elapsed." *P Open SW-V-34, SW Train A 15 Opens return to Cooling *P 16 Close SW-V-20, SW Train A to 16 Places SW-V-20 switch to close. discharge structure.

Identifiles that SW-V-20 does not close. ****BEGIN ALTERNATE PATH**** If the student dispatches the Primary NSO to close SW-V-20, then respond, "This is the Primary NSO, I am at SW-V-20 and there appears to be a probllem with the actuator.

SW-V-20 cannot be repositioned." STUDENT DECISION POINT Student will recognize boundary valve issue. Student has thle two following optional procedure paths: OS1 016.05, section 4.4, Transferring Train A Service Water System From the Cooling Tower to the Ocean per precaution 3.10 OS1216.01 , Degraded Ultimate Heat Sink per pre-job briefing sheet or OS1216.01 entry If student selects path 1, go to JPM step 3 (page If student selects path 2, go to JPM step 4 (page Control Room '8' Page 7 of 14

__ ___ ____________

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__ PERFORMANCE D=Discuss ELEMENT/STEP STANDARD

_d_e_n_o_te_s

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_d_e_n_o_te_s

__S_A_T_L_IN_S_A T__ Path 1: OS1016.05 , section 4.4, Transferring Train A Water System From the Cooling Tower to the Ocean P CHECK SW Train A and SW 1 Student mcognizes only one train Train 8 is aligned to the cooling of SW is aligned to the cooling tower, DO NOT PROCEED if this tower and proceeds to next step .. is the case. Inform student, "Initial Cooling Tower level has been mcc.rded on Form L, Cooling Tower flush NPDES tracking sheet." P Record initial cooling tower on Form L, Cooling Tower NPDES Tracking Inform student, "SW-V-44 is open and de-energized." P If SW-V-44, SW isolation from intake structure is Perform the following:

Open V-44 and lock open its US to student, "Pre-starts will not be done at this time.. C,ontinue with the next step." P Perform SW ocean pump starts as determined by the If the student asks about SW-V-20 position, then respond, "SW-V-20 is stuck open. Continue with the next step." P Open SW-V-20, SW train A to 5 Student mcognizes that SW-V-20 discharge structure.

is stuck open and proceeds.

P Close SW-V-34, SW train A 6 Closes return to cooling Control Room '8' Page 8 of 14 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

____________

_d_e_n_o_te_s

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S_A_T_U_N__S_A_T__ *P Simultaneously place and hold 7 Simultane!ously closes SW-V-54 the control switch for SW-V-54, and opens SW-V-56. Cooling Tower Pump A Discharge Isolation, to throttle close, and the control switch for SW-V-56, Cooling Tower Train A Spray Header Test, to open until the valves reposition.

P Start the desired train A ocean 8 Starts SW-P-41A OR SW-P-41 C. SW pump. P Check the selected SW pump 9 Verifies SW-V-2 OR discharge valve opens . SW-V-.22 opens. SW-V-2, discharge isolation SW-V-22, discharge If student selected path 1, then the JPM is complete.

CUE: "The JPM is complete." 10 Stoptime ___Time to complete task s30 minutes Evaluator calculates time complete Obtain from Tear Off sheets and any training materials used performance of this Control Room '8' Page 9 of 14

___ __ ____________

__ ______________

__

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

_3_=_S_im__u_la_te *_d_e_n_o_te_s

_d_e_n_o_te_s S_A_T_U N_S_A_T__ 4. Path 2: OS1216.01 , Degraded Ultimate Heat Sink CUE: Provide copy of OS1216.01 , Degraded Ultimate Heat Sink, to student. P Determine Appropriate 1 Student goes to OS1216.01, Step Response:

IF affected SW train 8. aligned to the cooling tower, THEN Go to Step 8. 2 Check For Cooling Tower Failure: 2 P 2a Cooling tower pump discharge 2a Student checks Cooling pressure >40 psig pump discharge pressure P Check cooling tower boundary 2a Student identifies SW-V20 is intact: NOT CLOSED and Cooling tower Check cooling tower boundary basin is DECREASING.

valves -CLOSED: Student goes to RNO column. SW-V4 SW-V20 o Check cooling tower level -STABLE P Manually or locally close 3 Student identifies SW-V20 cannot boundary valve(s) for affected be closed and cooling tower train. IF any boundary valve can basin is decreasing.

NOT be closed OR cooling tower level is decreasing, THEN: *P Place the affected cooling tower 3a Stops SW-P-11 OA and pump in PULL TO LOCK within control switch in 10 minutes of boundary Control Room 'B' Page 10 of 14 PERFORMANCE CHECK:LlST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

-=3'-=--'S_im----'-u--'-la....:...te-'--_*_d.;,...e_n_o_te_s_a_c_rit_ic_a_l_st_e.J....P

______*_ denotes c:t cr_iti_c_al_s_te---'p'--

______S_A_T_U_N_S_A_T_ US to student, "I will refer to 051212.01. Continue with the next step." P Refer to OS1212.01, System Malfunction for Cooling while continuil1g with P IF a suction source is 3b Student goes to Attachment B. AVAILABLE from intact intake tunnels, THEN transfer the affected train to the ocean: ATTACHMENT B, Transfer Train A Service Water to Ocean ATTACHMENT B, Transfer A Service Water to P 4a Reset TA signal, as necessary. Student may reset the TA or vocaliz:e that it is not necessary.

Either is acceptable. If the student asks about SW-V-20 position, then responcl, "SW-V-20 is stuck open. Continue with the next step." P Open SW-V20, SW Train A to 4b Student that SW-V-20 discharge structure.

is stuck open and proceeds.

P Close SW-V34, SW Train A 4c Closes return to cooling *P Close SW-V54, Cooling tower 4d Closes pump discharge Control Room 'B' Page 11 of 14 PERFORMANCE CHECK,LlST D=Discuss ELEMENT/STEP P=Periorm

=Simulate

denotes a critical step *P 4e Open SW-V56, Cooling tower spray header test. *P 4f Start one SW Ocean pump: SW-P-41A OR SW-P-41C.

STANDARD

denotes a critical step EVALUATION SAT UNSAT 4e Opens S\JV-V-56.

4f Starts SW-P-41A OR SW-P-41 C. NOTE: If student selected path 2, then the JPM is complete.

CUE: "The JPM is complete." 5 Stop time ____ Evaluator calculates time to complete task Obtain from student: Tear Off sheets and any other training materials used in periormance of this JPM. Time to complete task s30 minutes Control Room '8' Page 12 of 14 PERFORMANCE Provide comments on unsatisfactory performance of an element/stEIp or for any deviation from performance as stated. Record interruptions in performance such a:s; retraining, shift change, and processing of procedure changes. Recommend remedial if necessary.

Control Room '8' Page 13 of 14 TEAR OFF SHEET FOR CONTROL ROOM 'B' Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Secondary Operator. The following information is provided to you: The plant is operating at 100% power. On line maintenance needs to be done on the Service Water system Train A. The Shift Manager requested that Service Water Train A be transferred to the Cooling Tower until the job is complete in approximately 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Initial Cooling Tower level has been recorded on Form L, Cooling Tower flush NPDES tracking sheet. Local pre-starts are complete on the "A" Cooling Tower pump. Previous pump start was two days ago. Perform the task using OS1016.05, Service Water Tower Operation. The US will provide cues and communications for this JPM. Do you have any questions?

Initiating Cue: US to Secondary Operator, "Secondary Operator (or student's name), all Prerequisites are complete.

Review OS1016.05 Precautions and the Service Water Cooling Tower Operation Pre-Job Brief. Then transfer Service Water Train A from the Ocean to the Cooling Tower per OS1016.05 section 4.3." Control Room '8' Page 14 of 14

SEABRC)OK CONTROL ROOM JOB PERFORMANCE MEASURE 'e', POST LoeA PORV Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

JOB PERFORMANCE Task Number and Description Position RO SBK 0100400201 Operate The PORV/Block Valve To Control RCS Pressure Conditions: The reactor tripped from 100% due to a LOCA and Safety Injection has actuated. All actions were completed in E-O and E-1. The crew is presently at step 11 in ES-1.2, Post LOCA Cooldown And Depressurization. An RCS cooldown to cold shutdown is in progress. Standards:

Refill the pressurizer to >30% [44% adverse] per ES-1.2, Post LOCA Cooldown And Depressurization. Student Materials:

Copy of Tear Off Copy of ES-1.2, Post LOCA Cooldown And Depressurization Rev. Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures: ES-1.2, Post LOCA Cooldown And Depressurization.

Value Sys DescriptionRO/SRO 009 Ability to operate and monitor PORV and 3.9/4.1 PORV block valve as they apply to a small break LOCA. I 009 EA2.04 Ability to determine or interpret PZR level 3.8/4.0 I as they apply to a small break LOCA. Control Room 'C' Page 2 of 8 JOB PERFORMANCE

7. Setting: Reset the simulator to IC #155 or any 100% IC which contains the following: Initialize to an IC at 100% power. Insert malfunction mfRC049D RCS Cold Leg 4 leak 0-17S000gpm Final Value=1200. Run the simulator and allow the reactor to trip and SI to actuate. Complete E-O and E-1 through step 12 for ES-1.2 transition. Open EFW mini-flow valves and throttle EFW flow. Reset SI. Shut down and reset EDGs. Isolate SW to EDGs Trip all RCPs. Transition to ES-1.2 and perform steps 1-10. Ensure RHR pumps are secured. Modify mfRC049D to 1000 gpm to restore subcooling to >40°F. Place the simulator in FREEZE. 8. Safety Considerations:

None. 9. Approximate Completion Time: 10 minutes 10. Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Primary Operator.

You are going to the RCS to refill the pressurizer. The following information is provided to you: The reactor tripped from 100% due to a LOCA and Safety Injection has actuated. All actions were completed in E-O and E-1. The crew is presently at step 11 in ES-1.2, Post LOCA Cooldown And Depressurization. An RCS cooldown to cold shutdown is in progress.

Control Room 'C' Page 3 of 8 JOB PERFORMANCE C. Perform the task using ES-1.2, Post LOCA Cooldcwn And Depressurization.

D. We will begin after the Initiating Cue is read. E. I will provide cues and communications for this .JPIVI. Do you have any questions?

11. Initiating Cue: Evaluator to Primary Operator, "Primary Operator (or student's name), depressurize the RCS to refill the pressurizer using step 11 of ES-1.2." Control Room 'C' Page 4 of 8

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT 1. P Start time ____Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." Read the note prior to step 11 of ES-1.2. *2. Depressurize the RCS to refill PZR level less than 30% [44% a. Verifies PZR level less than 30% adverse].

[44% cldverse]. The student should recognize that the pressurizer spray valves cannot be used due to RCPs being secured and transition to the RNO. If the student opens the normal spray valve(s), then they should subsequently be closed and transition to the RNO for satisfactory completion of the JPM. Open normal PZR spray valve(s) b. Verifies normal spray is not to refill PZR. available.

- - - BEGIN ALTERNATE PATH**** RNO step 11 b. *b1) Uses ol1e PZR PORV to refill Use one PZR PORV to refill PZR. Opens one PZR PORV PZR. (with associated block valve open). PZR level greater than 30% [44% c. Verifies and reports that PZR level is not greater than 30% [44% cldverse]. US (Instructor) provide the following cue if decision to continue with step 12, "Monitor PZR level to see what the effects of depressurizing the RCS are 011 PZR level." PZR level should come on scale within a minute. Stop the RCS depressurization:

d. Closes PZR If PORV in use then close Control Room IC' Page 5 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

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__ CUE: "The JPM is complete." 3. Stop time ____ Time to complete task :S 10 minutes Evaluator calculates time to complete task Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. Control Room "C' Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an element'ste:p or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial if necessary. Page 7 of B TEAR OFF SHEET FOR CONTROL ROOM 'C' Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Primary Operator.

You are going to depressurize the RCS to refill the pressurizer. The following information is provided to you: The reactor tripped from 100% due to a LOCA and Safety Injection has actuated. All actions were completed in E-O and E-1. The crew is presently at step 11 in ES-1.2, Post LOCA Cooldown And Depressurization. An RCS cooldown to cold shutdown is in progress. Perform the task using ES-1.2, Post LOCA Cooldown And Depressurization. We will begin after the Initiating Cue is read. I will provide cues and communications for this JPM. Do you have any questions?

Initiating Cue: Evaluator to Primary Operator, "Primary Operator (or student's name), depressurize the RCS to refill the pressurizer using step 11 of ES-1.2." Control Room 'C' Page 8 of 8

CONTROL ROOM JOB PERFORMANCE MEASURE 'D', PLACE FAH IN FUEL HANDLING Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNEDI ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: ____

__-. TRAINING JOB PERFORMANCE Task Number and Description Position RO SBK 1100100101 Shift Ventilation Lineups Between Normal And FAH Conditions: The plant is at 100% power and all systems are normal. Reactor Engineering and Westinghouse will be performing an inspection of the RCCA change out tool in the Fuel Storage Building. Normal Fuel Storage Building ventilation is in Standards:

Place FAH in the fuel handling mode per OS1023.63, Fuel Storage Building Ventilation System Operation. Student Materials:

Copy of Tear Off Copy of OS1 023.63, Fuel Storage Building Ventilation System Operation Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested, no Peer Checks will be provided during the

References:

Procedures: OS1023.63 , Fuel Storage Building Ventilation System Operation.

Sys KA 2.1 2.1.44 Description Value RO/SRO Knowledge of RO duties in the control room during 3.9/3.8 fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

Control Room '0' Page 2 of9 JOB PERFORMANCE Setting: Simulator: Initialize the simulator to IC #155 OR 100% power IC OR any IC that does not interfere with FAH operations. FAH is in the normal lineup (i.e. FAH-FN-124 running). Safety Considerations:

None. Approximate Completion Time: 20 minutes Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Primary Operator.

In response to activities about to occur in the Fuel Storage Building, the US has directed you to place FAH in the fuel handling mode. The following information is provided to you: The plant is at 100% power and all systems an9 normal. Reactor Engineering and Westinghouse will be! performing an inspection of the RCCA change out tool in the Fuel Storage Building. Normal Fuel Storage Building ventilation is in service. A sign has been hung on door F202 prohibiting the use of any fossil fueled equipment in the FSB. Control Room 'DJ Page 3 of 9 JOB PERFORMANCE Perform the task using OS1023.63, Fuel Storage Building Ventilation System Operation. We will begin after the Initiating Cue is read. The US will provide cues and communications for this JPM. Do you have any questions?

11. Initiating Cue: US to Primary Operator, "Primary Operator (01/' student's name), place Train "A" Fuel Storage Building ventilation in the fuel handling mode in accordance with OS1023.63. All Prerequisites and Initial Conditions are complete." Control Room 'D' Page 4 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

__im_u_la_t_e

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___________

____________

S_A_T_U__N_S_A_T__ 1. Start time ______ Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." NOTE: Student should review the Note prior to step 4.4.1 of OS1 023.63 NOTE: Student should review the Note and Caution prior to step 4.3.1 of OS1 023.63 P Locally place PAH-DP-1003, Directs NSO to place PAB/FSB balancing damper, to the to the fuel handling fuel handling NSO to Primary Operator, "I copy, place PAH-DP-1003 in the fuel handling position." After completion of communication to place PAH-DP-1003 to the fuel handling position, NSO Primary Operator,"1 have placed PAH-DP-1003 in the fuel handling

3. Place the control switch for FAH-DP-Places the control switch for 14, FSB normal exhaust damper, to 14 to close. close. Exhaust fan FAH-FN-124 is interlocked with FAH-DP-14 and will (Observes FAH-FN-124 stops when stop when the damper reaches the full FAH-DP-14 is full closed) closed position.

4. Place the control switches for Places the following control switches DP-13A and FAH-DP-13B, FSB to close: supply dampers, to close.

FAH-DP-13A

FAH-DP-13B.

Control Room 'D' Page 5 of 9 PERFORMANCE D=Discuss ELEMENT/STEP P=Perform S=Simulate

denotes a critical step *5. Place both Train A and Train B Fuel Storage Building ventilation mode control switches to fuel handling. P Verify FAH-DP-13A and FAH-DP-13B, FSB supply dampers indicate closed. P Verify FAH-DP-14, FSB normal exhaust damper, is fully closed. If not full closed, the damper must be closed manually at the damper (FSB 64 ft elevation)

denotes a critical SAT UNSAT Places the following switches to fuel handling:

Train A mode switch

Train B mode switch. Verifies closed:

FAH-DP-13A

FAH-DP-13B Verifies FAH-DP-14 is closed. CUE: If asked, US to Primary Operator,"Place Train A air cleaning unit in service." NOTE: Student should review Caution prior to step 4.4.6.1 of OS 1023.63. NOTE: Placing FAH-DP-366 to start will start FAH-FN-11A when FAH-DP-366 starts to open. *8. P If fan FAH-FN-11A and its associated air cleaning unit, 41, are to be placed in service, perform the following:

Performs the following:

a. Place the control switch for DP-366, FSB cleaning unit exhaust damper to start. *a. Places control switch for FAH-DP-366 to start. NOTE: FAH-DP-13A will modulate to mid-position (20% open). Control Room 'D' Page 6 of9

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

__

____________

_de_n_o_te_s

__

_____________

S_A_T__U_N_S_A_T__ *b. Place the control switch for DP-13A, FSB supply damper to open. The damper will open to a preset position to maintain FSB internal pressure at a negative value. *b. Positions FAH-DP-13A control switch to open. *c. At MCB, place the FAH-F-41, cleaning unit heater, control switch to auto. *c. Positions FAH-F-41, cleaning unit heater control switch to auto. CUE: "The JPM is complete." 9. Stop time ____ Time to complete task::; 20 minutes Evaluator calculates time to complete task 10. Obtain from student: Tear Off sheets and any other training materials used in performance of this ..IPM. Control Room 'D' Page 7 of 9 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial trainingl, if necessary.

Control Room '0' Page 8 of 9

TEAR OFF SHEET FOR CONTROL R()OM '0' JPM Directions To The Student: You are the Primary Operator.

In response to activities about to occur in the Fuel Storage Building, the US has directed you to place FAH in the fuel handling mode. The following information is provided to you: The plant is at 100% power and all systems are normal. Reactor Engineering and Westinghouse will be peri:orrning an inspection of the RCCA change out tool in the Fuel Storage Building. Normal Fuel Storage Building ventilation is in servic:e. A sign has been hung on door F202 prohibiting the use of any fossil fueled equipment in the FSB. Perform the task using OS1023.63, Fuel Storage Building Ventilation System Operation. We will begin after the Initiating Cue is read. The US will provide cues and communications for this .JPM. Do you have any questions?

Initiating Cue: US to Primary Operator, "Primary Operator (or student's name), place Train "A" Fuel Storage Building ventilation in the fuel handling mode in accordance with OS1023.63. All Prerequisites and Initial Conditions are complete." Control Room '0' Page 9 of 9

....gj SEABROOK CONTROL ROOM JOB PERFORMANCE MEASURE

'E', FAILED OPEN Student Name: LMS #: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATIION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: DATE: ----:T=RA::-:-:-:--:I N:-::-I N:-::::-G-:::"S-:-:-:UP=E=RV:-::I-=--SO=R:----<

JOB PERFORMANCE Task Number and Description Position RO SBK 0390101501 OPERATE ASDV'S FROM MCB OR RSS Conditions:

A. The plant is at 100% power and all systems are nClrmal. Standards:

Identify a failed open ASDV and restore the system pe!r VAS D5214 ASDV A NOT FULL CLOSED or hardwire alarm MM-UA-53, A-7 ATMOS 8TM DUMP VALVE OPEN. Student Materials:

Copy of Tear Off Sheet. Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures:

VAS D5214 ASDV A NOT FULL CLOSED

Hardwire alarm MM-UA-53, A-7 ATMOS STM DUMP VALVE Technical

3.7.1.6 Atmospheric Relief Valves Value Sys Description I RO/SRO 035 K6.02 Knowledge of the effect of a loss or 3.1/3.5 malfunction on the following will have on i the S/Gs: Secondary PORV Control Room 'E' Page 2 of7 JOB PERFORMANCE Setting: Simulator:

Reset the simulator to IC #156 or any 100% IC: Initialize the simulator to a 100% power IC. Fail A ASDV controller to stay in Auto as follows: SELECT: Panel Overview section FF SELECT: Insert Override SELECT: MS-PK-3001 manual push button CANCEL first screen that pops up to get to second screen Change Final value to MANUAL SELECT: Insert Place the simulator in RUN. Safety Considerations:

None. Approximate Completion Time: 15 minutes Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Secondary Operator.

An event will occur. You are expected to identify the event and recommend actions and/or procedures to implement. The following information is provided to you: The plant is at 100% power and all systems am normal. We will begin after the Initiating Cue is read. I will provide cues and communications for this ..IPM. Do you have any questions? Initiating Cue: US to Secondary Operator, "You are the Secondary Operator respond to any condition that arises." Control Room 'E' Page 3 of 7 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

.3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT 1. Start time _____ Initiating cue read If the student requests a Peer Check at any time during the ,JPM respond, "No one is available to Peer Check your actions. Please continue with the task." MS-PV-3001, 'N SG Atmospheric Dump Valve fails open to a mid SELECT: MF SELECT: Main Steam SELECT:

SELECT: FAIL OUTPUT SET VALUE: SET RAMP: SELECT: *2. Recognize and report that an ASDV Recognizes and reports that 'A' has failed open. has failed CUE: If student requests 'Skill of the Operator' to close the ASDV, US respond, "I concur". CUE: If student using VAS 05214 or hardwire alarm resonse close the ASDV, US respond, "I concur". NOTE: The remaining steps are performed using VAS 05214 ASDV A NOT FULL CLOSED or hardwire alarm response for MM-UA-53, A-7 ATMOS STM DUMP VALVE OPEN. Note prior to step 1.1 of VAS 05214 ASDV A NOT FULL CLOSED or hardwire alarm response for MM-UA-53, A 7 ATMOS STM DUMP VALVE OPEN should be read. *3. P VERIFY SG pressures and ASDV Checks SG pnessures are less than controller setpoint.

1125 psig and ASDV controller NOTE: ASDV controllers are normally setpoint set at 1125 psig. set for 1125 psig in auto. 4. P ADJUST ASDV controllers and/or Acknowledges step requires no TRANSFER steam loads to actions. condenser steam dumps as Control Room 'E' Page 4 of 7 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

=Simulate

denotes a critical step

denotes a critical step SAT UNSAT necessary. P If an ASDV has failed OPEN: Verifies that an ASDV has PLACE controller for failed ASDV 1 Places controller for failed ASDV in manual/minimum.

in manual/minimum. PLACE affected ASDV control *2 Places thE! affected ASDV control switch to switch to close and verifies that the ASDV closes. Reports ASDV closed to US. If the student dispatches an NSO to the West Pipe Chase to locally isolate the 'A' ASDV "This is Primary NSO (or name) responding to the West Pipe Chase to locally isolate the 3 Locally ISOLATE ASDV as necessary.

3 Dispatches an NSO to the West Pipe Chase to locally isolate the 'A' ASDV. 6. P Observes for proper ASDV response.

Informs US that the 'A' ASDV is closed. CUE: "The JPM is complete." 7. Stop time ____ Time to complete task minutes Evaluator calculates time to complete task 8. Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. Control Room 'E' Page 5 of 7 PERFORMANCE Provide comments on unsatisfactory performance of an elemenUstep or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Control Room 'E' Page 6 of 7

TEAR OFF SHEET FOR CONTROL R()OM 'E' JPM Directions To The Student: You are the Secondary Operator.

An event will occur. YOll are expected to identify the event and recommend actions and/or procedures to implement. The following information is provided to you: The plant is at 100% power and all systems are normal. We will begin after the Initiating Cue is read .. I will provide cues and communications for this JPM. Do you have any questions?

Initiating Cue: US to Secondary Operator, "You are the Secondary Operat.or respond to any condition that arises." Control Room 'E' Page 7 of 7

ENER....-_. SEABRIQOK CONTROL ROOM JOB PERFORMANCE MEASURE 'F', RAISE SI ACCUMULATOR Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS J,ND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

JOB PERFORMANCE Task Number and Description Position RO SBK 0060100201 Monitor The Safety Injection System Conditions: The uN Accumulator pressure has decreased to the low pressure alarm setpoint due to normal system leakage. The Roving NSO is available at the nitrogen skid. Standards:

Pressurize the "A" Accumulator to above the low pnessure alarm, and within the limitations of Technical Specifications.

(610 psig +10 psig/-0 psig) Student Materials:

Copy of Tear Off Copy of OS1005.05 Safety Injection System Operation Rev. 16 Pages 9-11 & Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures:

OS1005.05 Safety Injection System Technical

3.5.1.1 ECCS Accumulators

-Hot Standby, Startup, and Power Operation Drawings 1-SI-820455 Safety Injection System Value Sys Descriptil)n RO/SRO 006 Ability to predict and/or monitor changes 3.5/3.7 in parameters (to prevent exceeding design limits) associaited with operating the ECCS controls including:

Accumulator pressure.

Page 2 of 9 JOB PERFORMANCE

7. Setting: Reset the simulator to IC #156 or any 100% IC which Gontains the following: Initialize to an IC at 100% power. Vent the "A" Accumulator (using the vent valves), to approximately 590 psig, until UA-50 hardwire alarm Accum Press Hillo and VAS alarm D4505 are in alarm. Use "GD ACCUMS" on MPCS to view Accumulator level and pressure "A" points. D. OPEN NG-V-30 as follows: SELECT: RF List SELECT: Nitrogen Gas SELECT: rfNG003 NG-V30 Nitrogen to SI accumulators manual isolation SELECT: Final Value=OPEN SELECT: INSERT Freeze the simulator.

8. Safety Considerations:

None. 9. Approximate Completion Time: 15 minutes 10. Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Primary Operator and you are tel pressurize the "An Accumulator to within limits of Tech. Specs. (610 psig +10 psig/-0 psig). You may use MPCS Group Display "GD ACCUMS n to view Accumulator level and pressure "An points or SVD A0414 for "A" Accumulator pressure. The following information is provided to you: The "AI! Accumulator pressure has decreased due to normal system leakage. All applicable prerequisites of OS1 005.05 Safety Injection System Operation are complete. Nitrogen is being supplied via a tube truck. Perform the task using OS1005.05 Safety Injection System Operation. We will begin after the Initiating Cue is read. I will provide cues and communications for this JPM. Do you have any questions?

11. Initiating Cue: Page 3 of 9 JOB PERFORMANCE US to Primary Operator, "Primary Operator (or student's name), Pressurize the "An Accumulator to 610 psig +10 psig 1-0 psig." Page 4 of 9

D=Discuss ELEMENT/STEP STANDARD EVALUATION O=Perform S=Simulate

denotes a critical step

denotes al critical step SAT UNSAT 1. Start time _____ Initiating cUie read If the student requests a Peer Check at any time during theJPM respond, "No one is available to Peer Check your actions. Please continue with the talsk." P Verify a N2 source is available from Determines if a nitrogen source the N2 truck or the N2 bottle banks per ON1024.01 Startup and Shutdown Nitrogen Gas When the student attempts to determine if a nitrogen source is available, inform the "Nitrogen is being supplied via a tube *3. P Open the following valves *a. NG-V-13, nitrogen to SI accumulator ORC isolation.

a. Opens NG-V-13, nitrogen to SI accumulator ORC isolation.

b. NG-V-14, nitrogen to SI accumulator IRC isolation.

b. Opens NG-V-14, nitrogen to SI accumulator IRe isolation.

4. P Slowly opens NG-V-30, nitrogen inlet isolation to the accumulators.

Directs NSO to slowly open NG-V-30, nitrogen inlet isolation to the accumulators.

CUE: When candidate asks NSO to slowly open NG-V-30, then report, "NG-V-30 is open." CUE: If the student requests US direction, respond, "Pressurize the "A" Accumulator to 610 psig +10 psig/ -0 psig." *5. P Open the nitrogen header isolation valve for the desired accumulator.

NG-V-17 Accumulator "A" nitrogen isolation.

Opens NG-V-17 Accumulator "A" nitrogen isolation.

6. When pressure reaches desired When pressure reaches desired value, close NG-V-30, nitrogen inlet value, directs NSO to close NG-V-30, isolation to the accumulators.

nitrogen inlet Isolation to the Page 5 of9 PERFORMANCE O=Discuss ELEMENT/STEP STANDARD EVALUATION o=Perform

___________

____________

__ accumulators.

CUE: When candidate directs NSO to close NG-V-30, then repc)rt, "NG-V-30 is closed." *7. P Check closed/close the following valves: *a. NG-V-17 Accumulator "A" *a. Closes NG-V-17 Accumulator "A" nitrogen isolation.

nitrogen isolation.

b. NG-V-19 Accumulator b. Check clc1sed NG-V-19 nitrogen Accumulator "8" nitrogen isolation.

c. NG-V-21 Accumulator c. Check closed NG-V-21 nitrogen Accumulator "C" nitrogen isolation.

d. NG-V-23 Accumulator d. Check closed NG-V-23 nitrogen Accumulator "D" nitrogen isolation.

Page 6 of9 PERFORMANCE D=Discuss P=Perform 3=Simulate ELEMENT/STEP

denotes a critical step STANDARD

denotes a critical step EVALUATION SAT UNSAT "A" Accumulator final pressure ______ psig at completion of task 610 psig +10 psig/-0 psig." *8. P Close the following valves: *a. NG-V-13, nitrogen to SI accumulator ORC isolation

b. NG-V-14, nitrogen to SI accumulator IRC isolation.

CUE: "The JPM is complete." 9. Stop time ____ Evaluator calculates time to complete task 10. Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. *a. Closes NG-V-13, nitrogen to SI accumulator ORC isolation.

b. Closes NG-V-14, nitrogen to SI accumulator IRC isolation.

Time to complete task::; 15 minutes Page 70f9 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial if necessary.

Page 8 of 9 TEAR OFF SHEET FOR CONTROL ROOM IF' Directions To The Student: You are the Primary Operator and you are going to pressurize the "A" Accumulator to within limits of Tech. Specs. (610 psig +10 psig/-0 psig). You mlay use MPCS Group Display "GD ACCUMS" to view Accumulator level and pressure "A" pOints or SVD A0414 for "A" Accumulator pressure. The following information is provided to you: The "A" Accumulator pressure has decreased due to normal system leakage. All applicable prerequisites of OS1005.05 Safety Injection System Operation are complete. Nitrogen is being supplied via a tube truck. Perform the task using OS1005.05 Safety Injection Sysitem Operation. We will begin after the Initiating Cue is read. E. I will provide cues and communications for this JPM. Do you have any Initiating US to Primary Operator, "Primary Operator (or student's name), Pressurize the Accumulator to 610 psig +10 psig 1-0 Page 9 of 9

CONTROL ROOM JOB PERFORMANCE MEASURE 'G', FINAL ESTABLISH CHARGING AND LETDOWN (HlCV-189/190 FAIL) Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINA-TION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: ______________

__ DATE: APPROVED BY: TRAINING JOB PERFORMANCE

1. Task Number and Description RO SBK 0040104801 Establish Charging And Seal Injection SBK 0040104901 Establish Normal Letdown 2. Conditions:

A. A manual Safety Injection was initiated due to a SG tube rupture. B. The control room executed E-O and transitioned to E-3. C. The crew identified SG "C" as the ruptured SG. D. The crew has completed E-3 up to and including step 21. E. A Loss of Offsite Power occurred on the reactor trip. F. Offsite power has been restored.

G. Bus 5 and 6 are powered by the 'A' and 'B' Eme!rgEmcy Diesel Generators.

3. Standards:

Establish normal charging and letdown in accordance with E-3, SG Tube Rupture. 4. Student Materials:

Copy of Tear-Off Copy of E-3 SG Tube Rupture, Rev. 5. Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the ..6.

References:

Procedures:

E-3, SG Tube Rupture

Westinghouse Background Document, E-3. Value Sys Descri ption RO/SRO 038 EK3.06 Knowledge of bases for actions contained 4.2/4.5 in EOP for RCS water inventory balance. 038 Ability to operate and monitor PZR 3.2/3.3 level/pressure indicators, gauges, and recorders.

038 Ability to operate and monitor CVCS tank 3.5/3.3 indicators and water charging sources. Control Room 'G' Page 2 of 10 JOB PERFORMANCE

7. Setting: Reset the simulator to IC #157 or any 100% IC which contains the following: Initialize to any 100% IC and place the simulator in RUN. Insert malfunction mfSG001 C SG C DBl END Tube Rupture Hot Side (0 -1150gpm) for a 425 gpm tube rupture on "C" SG. When RDMS alarms due to the tube rupture manually trip the reactor and initiate a manual SI. Execute E-O. Open EFW mini-flow valves and isolate EFW to "C" SG when level is adequate (E-O OAS page). Transition to E-3 and execute steps 1-21. Using Panel Graphics insert override to close HCV-189 and HCV-190. Override both the potentiometer and meter for each valve. Insert malfunction mfED038 loss of offsite power and allow Bus 5 and 6 to be powered by the 'N and 'B' Emergency Diesel Generators. Delete malfunction mfED038 loss of offsite power. Stop CS-P-2-B and place in Standby. Set boric acid flow to 40 GPM. FREEZE the simulator.

8. Safety Considerations:

None. 9. Approximate Completion Time: 20 minutes Control Room 'G' Page 3 of 10 JOB PERFORMANCE

10. Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Primary Operator.

You are going to re*,establish charging and letdown per E-3, SG Tube Rupture. The evaluator will act as the Unit Supervisor.

The student will read and execute the procedure. The following information is provided to you: A manual Safety Injection was initiated due to a SG tube rupture. The control room executed E-O and transitioned to E-3. The crew identified SG "c" as the ruptured SG. The crew has completed E-3 up to and including step 21. A Loss of Offsite Power occurred on the reactor trip. Offsite power has been restored. Bus 5 and 6 are powered by the 'A' and 'B' Emergency Diesel Generators. Perform the task using E-3, SG Tube Rupture. We will begin after the Initiating Cue is read. I will provide cues and communications for this ,IPM. Do you have any questions?

11. Initiating Cue: Evaluator to Primary Operator, "Primary Operator (or student's name), you will be establishing letdown in accordance with E-3. You will begin performance of E-3, starting at step 22." Control Room 'G' Page 4 of 10 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION D=Perform

___

___________

__________

__ When student is ready to begin place the simulator in Student begins at step 22 of 1. P Start time _____Initiating cue read If the student requests a Peer Check at any time during the .JPM respond, "No one is available to Peer Check your actions. Please continue with the task." P Restore normal charging path:

Open CS-V-142

Open CS-V-143 *3. Establish normal charging flow: *a. Isolate CCP to RCS Cold Legs:

Close SI-V-138

Close SI-V-139 Opens charging line isolation valves:

Open CS-V-142

Open CS-V-143 Isolates CCP to RCS Cold Legs:

Close SI-V-138

Close SI-V-139 It is not necessary to establish exactly 60 gpm charging flow. The evaluator judges that the intent is met if enough flow is established to supply letdown regenerative cooling, and not too much flow established such that Pressurizer level is adversely affected.

b. Establish 60 gpm charging flow. Establishes adequate charging flow by adjusting CS-FCV-121. If necessary, provide the following cue, US to PSO: "6-10 glPm is the desired seal injection flow rate." Adjust seal injection flow as *c. Adjusts injection flow to 6-10 necessary using CS-HCV-182.

gpm CS-HCV-182. The intent of the next step is met if the student is into the RCS via CS-FCV-121.

It is a continuous action step. Control of charging flow is specifical.ly addressed after letdown is established (step 30 of E-3). 4. P Control charging flow to maintain Controls charging flow to maintain Pressurizer level. Pressurizer level. Control Room 'G' Page 5 of 10 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

___________

________.__

5. P Verify ECCS flow not required:

RCS subcooling greater than 40°F

PZR level greater than 7%. 6. P Check VCT makeup control system Makeup set for greater than RCS boron concentration

.. Makeup set for automatic control. Verifies ECCS flow not required:

RCS subcooling greater than 40°F

PZR level !;Ireater than 7%. Checks boric acid controller maximum 40 Checks makeup in automatic and armed. NOTE: The instructor (acting as the BOP) should maintain RCS temperature using steam dumps or AS DVs. *7. P Check if letdown can be established: Check PZR level greater than 30%. Establish letdown: Open CC-V-341 letdown HX cooling water outlet. Close letdown flow control valves:

CS-HCV-189

CS-HCV-190.

b3) Open letdown line Phase A isolation valves: *

CS-V-149 *

CS-V-150. Checks PZR level greater than 30%. Opens CC-V-341 letdown HX cooling water outlet. Closes letdown flow

CS-I-ICV-189

CS-I-ICV-190.

"'b3) Open letdown line Phase A isolation valves: *

CS-\/-149

'"

CS-V-150.

Control Room 'G' Page 6 of 10 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT Open letdown line isolation valves: a) RC-V-81 b) RC-LCV-459 c) RC-LCV460 d) CS-V-145 Opens letdown line isolation valves: a) RC-V-81 b) RC-l.CV-459 c) RC-LCV-460 d) CS-V-145 CUE: US to PSG, "Take manual control of CS-PK-131 as necessary to establish flow in the letdown line. " NOTE: The student may place CS-PCV-131 in manual and open the valve about 20%, ****BEGIN ALTERNATE PATH**** Throttle open letdown flow control valve. RNO: Establish Excess Letdown per ATTACHMENT E. b5) Attempts to throttle open CS-HCV-189, Determines that valve will not open, Attempts to throttle open CS-HCV-190, Determines that valve will not open. Transitions to step 27b RNO. Determines Excess Letdown per An"ACHMENT E is required.

Control Room 'G' Page 7 of 10 PERFORMANCE D=Discuss STANDARD o=Perform 3=Simulate

denotes a critical

denotes a critical step *8. P Establish excess letdown: NOTE: The student reads the CAUTION prior to step 1:

Excess letdown HX outlet temperature of 175°F should nClt be exceeded .

Excess letdown HX outlet pressure of 150 psig should not be exceeded. Open all four B PCCW loop a. Checks open all four B PCCW containment isolation valves. loop containment isolation valves. Open CC-V434, excess letdown b. Opens CC-V434, excess letdown HX cooling water outlet. HX cooling water outlet. Open RCP seal return isolation

c. Opens RCP seal return isolation valves: CS-V167 and CS-V168. valves: CS-V167 and CS-V168. Open RCDT outlet isolation

d. Opens RCDT outlet isolation valves: WLD-V81 and WLD-V82. valves: WLD-V81 and WLD-V82. Close CS-HCV-123.

e. Closes CS-HCV-123. Open excess letdown isolation

f. Opens excess letdown isolation valves: CS-V175 and CS-V176. valves: CS-V175 and CS-V176. Align CS-V170 to RCDT. g. Aligns CS-V170 to RCDT. Throttle open CS-HCV-123 to h.

open CS-HCV-123 to establish desired excess letdown establish desired excess letdown pressure and temperature.

pressure .:md temperature.

CUE: "The JPM is complete." 8. Stop time ___Time to complete task::;; 20 minutes Evaluator calculates time to Obtain from Tear Off sheets and any other materials used in performance of ..Control Room Page 8 of SAT PERFORMANCE Provide comments on unsatisfactory performance of an element'stElp or for any deviation from performance as stated. Record interruptions in performance sucl1 as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Control Room 'G' Page 9 of 10 TEAR OFF SHEET FOR CONTROL ROOM 'G' Directions To The Student: You are the Primary Operator.

You are going to re-estslblish charging and letdown per E-3, SG Tube Rupture. The evaluator will act as the Unit Supervisor.

The student will read and execute the procedure. The following information is provided to you: A manual Safety Injection was initiated due to a SGi tube rupture. The control room executed E-O and transitioned to E<L The crew identified SG "C" as the ruptured SG. The crew has completed E-3 up to and including step 21. A Loss of Offsite Power occurred on the reactor trip. Offsite power has been restored. Bus 5 and 6 are powered by the 'A' and 'B' Emergency Diesel Generators. Perform the task using E-3, SG Tube Rupture. We will begin after the Initiating Cue is read. I will provide cues and communications for this JPM. DIO you have any questions?

Initiating Cue: Evaluator to Primary Operator, "Primary Operator (or student's name), you will be establishing letdown in accordance with E-3. You will begin performance of E-3, starting at step 22." Control Room 'G' Page 10 of 10

SEABROOK CONTROL ROOM JOB PERFORMANCE MEASURE 'H', FINAL OFFSITE POWER RESTORATION Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: DATE: _______ APPROVED BY: ________________

_ TRAINING JOB PERFORMANCE Task Number and Description Position RO SBK 0640402501 Restore Offsite Power to Bus E5/E6. Conditions:

A. The A manual Safety Injection was initiated due, to a SG tube rupture. B. The control room executed E-O and transitioneci to E-3. C. The crew identified SG "C" as the ruptured SG. D. The crew has completed E-3 up to and including step 21. E. A Loss of Offsite Power occurred on the reactor trip. F. Offsite power has been restored.

G. Bus 5 and 6 are powered by the 'A' and 'B' Emergency Diesel Generators. Standards:

Student will restore offsite power to bus 6 using E-3, SG Tube Rupture, attachment H. Student Materials:

Copy of Tear-Off Copy of Attachment H of E-3, Offsite Power Restorcaticm to Bus E5 and E6, Rev. Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures:

E-3, SG Tube Rupture, attachment H Sys KA Description Value RO/SRO 062 K1.04 Knowledge of offsite power sources. 3.7/4.2 062 A4.01 Ability to manually operate and/or monitor breakers.

3.3/3.1 062 A4.07 Synchronizing and paralleling of different AC supplies.

3.1/3.1 Control Room 'H' Page 20f9 JOB PERFORMANCE

7. Setting: Reset the simulator to IC #157 or any 100% IC which contains the following: Initialize to any 100% IC and place the simulator in RUN. Insert malfunction mfSG001C SG C DBL END Tube Rupture Hot Side (0 -1150gpm) for a 425 gpm tube rupture on "e" SG. When RDMS alarms due to the tube rupture manually trip the reactor and initiate a manual SI. Execute E-O. Open EFW mini-flow valves and isolate EFW to "C" SG when level is adequate (E-O, OAS page). Transition to E-3 and execute steps 1-21. Using Panel Graphics insert override to close HCV-189 and HCV-190. Override both the potentiometer and meter for each valve. Insert malfunction mfED038 loss of offsite and allow Bus 5 and 6 to be powered by the 'A' and 'B' Emergency Diesel Generators. Delete malfunction mfED038, loss of offsite power. Stop CS-P-2-B and place in Standby. FREEZE the simulator.

8. Safety Considerations:

None. 9. Approximate Completion Time: 20 minutes 10. Directions To The Student: Evaluator gives Tear Off sheet to the student. Evaluator reads the following to student: You are the Secondary Operator.

You will restore ()ffsite power to Bus 6 using E-3, SG Tube Rupture, attachment H. The following information is provided to you: The A manual Safety Injection was initiated due to a SG tube rupture. The control room executed E-O and transitioned to E-3. The crew identified SG "C" as the ruptured SG. The crew has completed E-3 up to and including step 21. A Loss of Offsite Power occurred on the reactclr trip. Offsite power has been restored. The system dispatcher reports grid conditions iare now stable, and are expected to remain stable. Bus 5 and 6 are powered by the 'A' and 'B' Emergency Diesel Generators.

Control Room 'H' Page 3 of 9 JOB PERFORMANCE C. Perform the task using E-3, SG Tube Rupture, attachment H. D. We will begin after the Initiating Cue is read. E. I will provide cues and communications for this JPM. Do you have any questions?

11. Initiating Cue: US to Secondary Operator, "Secondary Operator (or student's name), restore offsite power to Bus E6 using E-3, SG Tube Rupture, attachment H. Control Room 'H' Page 4 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD

_d_en_o_t_es

__ __

____________

______ __ ____________

de_n_o_t_es

1. P Start time _______Initiating clle read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." 2. IF AC emergency bus is powered by emergency diesels 1A11 B, THEN restore offsite power as follows: *P a Raise DG frequency to 60.2 to 60.4 Hz. *P b Place DG sync. selector switch in the RAT or UAT position.

P c Reset RMO. *P d Adjust DG voltage to match INCOMING VOLTS with RUNNING VOLTS. *P e Adjust DG frequency so that the sync. meter is going slowly in the fast direction.

P f Close the RAT or UAT breaker when synchronized.

a Raises DG frequency to 60.2 to 60.4 Hz. b Places DG sync. selector switch in the RAT or UAT position.

c Resets RIMa. d Adjusts DG voltage to match INCOMING VOLTS with RUNNING VOLTS. e Adjusts DG frequency so that the sync. meter is gOing slowly in the fast direction.

f Closes the RAT or UAT breaker when synchronized. (sync. meter approximcately 12 o'clock position)

P g Place the sync. selector switch in g Places the sync. selector switch OFF. in OFF. NOTE: The evaluator should observe that the operator maintains control over the generator VARs while Control Room 'H' Page 5 of9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT unloading.

Due to simulator bus voltage settings, it is expected that leading VAR loading will initially be observed.

Until this issue can be corrected, the followlng cue must be stated to the student: "Due to simulator bus voltage settings, it is expected that you will initially see leading VARs after paralleling.

The response of KVARS to DG voltage adjustments will be reversed.

Adjust DG KVARS to 1000 lagging at this time. This adjustment is not part of the evaluation." Inform the student: "For the purposes of this JPM, the 10 minute unloading period can Shutdown DG by performing the h Shuts down DG by performing following:

the following:

P Over a 10 minute period lower h1 Over a 10 minute period, lowers KVARS to less than 200 lagging KVARS to less than 200 lagging and lower load to 75 to 125 KW. and lower load to 75 to 125 KW. *P Open DG breaker. h2 Opens DG breaker. *P Adjust DG voltage to 4160 volts. h3 Adjusts DG voltage to 4160 volts. When the above step is completed, inform the student: "For the purpose of this JPM, ten minutes have elapsed and the DG is cooled sufficiently to shutdown the engine." *P After running DG unloaded for 10 h4 Runs DG unloaded for 10, then minutes to cool the engine, shuts down the diesel by shutdown the diesel by depressing both emergency stop depressing both emergency stop buttons simultaneously.

buttons simultaneously. When the above step is completed and DG rpm is Zer4), inform the student: "For the purpose of this JPM, two minutes have elapsed and the DG has s_to-'p-'-p_e_d_r_o_lI_in

......glL._"__________ Control Room 'H' Page 60f9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT *P h5 After waiting two minutes to allow h5 Resets the DG. time for diesel to stop. reset the DG. *P h6 Close SW-V-16 for DG A, or h6 Closes SW-V-18 for DG B. V-18 for DG B. CUE: "The JPM is complete." 3. Stop time ____ Time to complete task s20 minutes Evaluator calculates time to complete task 4. Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. Control Room 'H' Page 7 of 9 PERFORMANCE Provide comments on unsatisfactory performance of an elementistep or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, ii: necessary.

Control Room 'H' Page 80f9 TEAR OFF SHEET FOR CONTROL ROOM 'H' Directions to the Student: You are the Secondary Operator.

You will restore offsi1:e power to Bus 6 using E-3, SG Tube Rupture, attachment H. The following information is provided to you: The A manual Safety Injection was initiated due to a SG tube rupture. The control room executed E-O and transitioned to E<3. The crew identified SG UC" as the ruptured SG. The crew has completed E-3 up to and including step 21. A Loss of Offsite Power occurred on the reactor trip. Offsite power has been restored. The system dispatcher reports grid conditions are now stable, and are expected to remain stable. Bus 5 and 6 are powered by the 'A' and 'B' Emergency Diesel Generators. Perform the task using E-3, SG Tube Rupture, attachment H. We will begin after the Initiating Cue is read. I will provide cues and communications for this JPM. Do you have any questions?

Initiating Cue: US to Secondary Operator, "Secondary Operator (or student's name), restore offsite power to Bus E6 using E-3, SG Tube Rupture, attachment H. Control Room 'H' Page 9 of9

SEABR()OK IN-PLANT JOB PERFORMANCE MEASLIRE 'A', DC START OF ELGAR Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

.. 1. 2. 3. 4. 5. 6. JOB PERFORMANCE Task Number and Description Position NSO SBK 0620100304 Place In/Remove From Service A Static Inverter Conditions: The plant is in mode 5. UPS EDE-I-1 E(F) was shutdown during the previous shift to support an inspection performed by Engineering Support Staff. UPS 1-EDE-I-1 E(F) was shutdown using OS1 047.01, Vital Inverter Operation. PP-1 E(F) was transferred to its maintenance supply per OS1047.02, Transferring Power Supplies To 120 VAC Vital Instrument Buses prior to inverter shutdown. On the other train PP-1 F(E) is energized from its inverter connected to the respective DC bus. Standards:

Simulate restart of UPS-1-EDE-I-1 E{F). Student Materials:

Copy of Tear Off Sheet. Copy of OS1047.01 , Vital Inverter Operation Rev 14 Operator Aid 90-0019 Inverter 1 E, PP-1 E Power Supplies Operator Aid 90-0020 Inverter 1 F, PP-1 F Power SuppHes Limitations On Performance:

Simulate all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures: OS1047.01 , Vital Inverter Operation

OS1047.02 , Transferring Power Supplies To 120 VAC Vital Instrument Buses Technical Specifications: 3.8.3.1 On Site Power Distribution

-Operating 3.8.3.2 On Site Power Distribution

-Shutdown Page 2 of 12 In-Plant 'A' JOB PERFORMANCE Drawings: Operator Aid 90-0019 Inverter 1E, PP-1E Power Supplies Operator Aid 90-0020 Inverter 1 F, PP-1 F Power Supplies Value Sys Description RO/SRO 062 Knowledge of AC distribution system 3.1/3.5 design features and/or interlocks which provide for uninterruptible AC power sources. 2.1.23 Ability to perform specific system and 3.9/4.0 integrated plant procedures during all modes of operation.

7. Setting: Plant. Essential Switchgear Room. 8. Safety Considerations:

Energized electrical equipment.

9. Approximate Completion Time: 25 minutes 10. Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to You are the Secondary NSO. You are going to :simulate restart of 1 E(F). The following information is provided to you: The plant is in mode 5. UPS EDE-I-1 E(F) was shutdown during the previous shift to support an inspection performed by Engineering Support Staff. UPS 1-EDE-I-1 E(F) was shutdown using OS1047.01, Vital Inverter Operation. Vital PP-1 E(F) was transferred to its maintenance supply per OS1047.02, Transferring Power Supplies To 120 VAC Vital Instrument Buses prior to inverter shutdown. On the other train PP-1 F(E) is energized from its inverter connected to the respective DC bus. In-Plant 'A' Page 3 of 12 JOB PERFORMANCE Perform the task using OS1 047.01, Vital Inverter Operation. We will begin after the Initiating Cue is read. I will act as the Unit Supervisor and provide cues alnd communications for this JPM. Do you have any questions?

11. Initiating Cue: US to Secondary NSO, "Secondary NSO (or student's name), simulate restarting UPS-1-EDE-I-1E(F} using OS1047.01, Vital Inverter Operation, section 4.11 (4.12). All ofthe procedure are complete." In-Plant 'A' Page 4 of 12 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a. critical step SAT UNSAT When student demonstrates the ability to obtain a controlled copy of OS1047.01, Vital Inverter Operation provide the student with OS1 047.01, Vital Inverter Operation. P Start time _____ Initiating cue read If the student requests a Peer Check at any time during the ,JPM respond, "No one is available Peer Check your actions. Please continue with the S Verify reverse transfer light on Simulates verifying reverse CP-1 E(F), static transfer switch, is light on EDE-GP-1 E(F), static energized.

switch, is When student simulates verifying light is energized, evaluator to student, "The reverse transfer light is illuminated." *3. Close the following breakers to 1-EDE-I-1 When student locates UPS-1E(F)

AC supply at MCC-512(612) node DD3(DD5), evaluator to student, "The AC supply breaker to the inverter indicates open." Simulates closing UPS-1 E(F) AC supply at MCC-512(612) node DD3(DD5). When student simulates closing UPS-1E(F)

AC supply at MCC-512 (612) node DD3(DD5), evaluator to student, "The breaker closes." When student locates UPS-1E(F)

DC supply at DC bus 1'lA(B) node DM7(DNO), evaluator to student, "The DC supply breaker to the inverter indicates open!' Simulates closing UPS-1 E(F) DC supply at DC bus 11A(B) node DM7(DNO), When student simulates closing UPS-1E(F)

DC supply at DC bus 11A(B) node DM7(DNO), evaluator to student, "The breaker closes." In-Plant 'A' Page 5 of 12 PERFORMANCE D=Discuss ELEMENT/STEP EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical SAT UNSAT Student should review caution prior to step 4.11.3(4.12.3).

If student elects not to perform step 4.11.3(4.12.3), then next step is not required.

Inverter can be placed in service without pre-charge but it is the preferred method. If student asks if pre-charge is desired, evaluator to student,"Pre-charge inverter 1-EDE-I-1E(F)." S Pre-charge inverter 1-EDE-I-1E(F): Simulates; depressing Pre-charge pushbutton. (If performed)

When student simulates depressing pushbutton, evaluator to student, "The Pre-charge pushbutton has been depressed." Waits OnE! minute to allow DC bus capacitor to charge. After student recognizes time requirement, evaluator to student, "One minute has elapsed." *5. Close AC input breaker (100 amp) start UPS as Simulates; closing AC input breaker ('100 amp) to start UPS. When student simulates closing AC input breaker (100 amp), evaluator to student, "The When the AC input breaker is shut, the rectifier and inverter sections begin startup. This JPM sets up conditions described in the note prior to step 4.11.5(4.12.5).

Normally when the AC input breaker is shut, output voltage and frequency will rise. In the JPM, Olutput voltage and frequency rise momentarily and return to the low peg. The UPS will again try to restart. Voltage and frequency rise and then fall to the low peg a second time. The UPS will "lock out" when this occurs In-Plant 'A' Page 6 of 12

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

__________

___________

__ Checks output voltage and frequency Begin Alternate Path CUE: When student checks output voltage and frequency, evaluator to student, "Output voltage and frequency rise toward normal, and then fall off. They rise again a second time and fall off to the low peg. The following alarms are lit. at the UPS:

DCINPUTOVERVOLTAGE

DC INPUT BREAKER OPEN

INV OUTPUT LlNDERVOLTAGE

FREQUENCY OUT OF UMITS." NOTE: Student should review note prior to step 4.11.5(4.12.5). S Recognize that inverter is "locked Recognizes that inverter is out." When student determines that UPS has a "lock out" condition and section 4.13(4.14) must be used to restart the UPS, acknowledge and respond as appropriate

(,either as evaluator or US), "Continue with restart ofthe UPS." *7. Check open/open the breakers on 1-EDE-I-1 Simulates checking open/opening UPS-1E(F)

AC input breaker (100 amp). When student simulates opening UPS-1 E(F) AC input breaker (1 00 amp), evaluator to student, "The AC input breaker is open." Simulates checking open 1 E(F) battery input breaker (400 amp). When student simUlates checking open UPS-1 E(F) battery input breaker (400 amp), evaluator student, "The battery input breaker is In-Plant 'A' Page 7 of 12 PERFORMANCE D=Discuss ELEIVIENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT S Ensure UPS-1 E(F) DC supply breaker Simulates ensuring UPS-1 E(F) on bus 11A(8) node DM7(DNO) is supply breaker on bus 11A(8) closed. DM7(DNO) is CUE: When student simulates ensuring UPS-1 E(F) DC supply breaker on bus 11A(8) node DM7(DNO) is closed, evaluator to student, "The breaker is closed." *9. S Pre-charge inverter 1-EDE-I-1 E(F): *a. Simulates depressing Pre-charge pushbutton.

CUE: When student simulates depressing Pre-charge pushbutt,on, evaluator to student, "The Pre*charge pushbutton has been depressed." b. Simulates verifying pre-charge LED is energized.

CUE: When student simulates verifying pre-charge LED is energized, evaluator to student, "The charge LED is illuminated." *c. Waits one minute to allow DC bus capacitor to charge. CUE: After student recognizes time requirement, evaluator to student, "One minute has elapsed." *10. S Close the battery input breaker (400 amp). Simulates closing the battery input breaker (400 amp). CUE: When student simulates closing UPS-1 E(F) battery input breaker (400 amp), evaluator to student, "The battery input breaker is closed." In-Plant 'A' Page 8 of 12

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

__________

__ S Check UPS output voltage and Simulates che;cking UPS frequency.

voltage and When student simulates checking UPS output voltage and frequency, evaluator to student, "Output is 120 volts and 60 Hz." S Verify LEDS are energized for the Simulates verifying LEDS following:

energized for the

AC INPUT BKR

AC INPUT BKR OPEN

I NV FED FROM

INV FEO FROM BATT

FREQ OUT OF

FREQ OUT OF LIMITS When student simulates verifying LEOS are energized, evaluator to student,"LEDS are energized." *13. Close the UPS AC input breaker (100 Simulates closing the UPS AC amp). breaker (100 When student simulates closing UPS AC input breaker (100 amp), evaluator to student, "The breaker is closed." 14. Depress the alarm reset pushbutton Simulates depressing the alarm reset and verify no alarm LEOs pushbutton and verifying that no alarm LEOs are lit When student simulates depressing the alarm reset pushbutton and verifying that no alarm LEDs are lit, evaluator to student, "All alarms are clear." *15. Close the AC output breaker (400 Simulates closing the AC amp). breaker (400 When student simulates closing UPS AC breaker (400 amp), evaluator to student, breaker is In-Plant 'A' Page 9 of 12 PERFORMANCE CHECI<:LlST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT CUE: "The JPM is complete." Stop time ____ Time to complete task S 25 minutes Evaluator calculates time to Obtain from Tear Off sheets and any other materials used in performance of In-Plant 'A' Page 10 of 12 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

In-Plant 'A' Page 11 of 12

.... TEAR OFF SHEET FOR IN-PLANT 'A' JPM Directions To The Student: You are the Secondary NSO. You are going to simulate restart of 1 E(F). The following information is provided to you: The plant is in mode 5. UPS EDE-I-1 E(F) was shutdown during the previous shift to support an inspection performed by Engineering Suppc,rt Staff. UPS 1-EDE-I-1 E(F) was shutdown using OS1047.01, Vitatlnverter Ope,ration. Vital PP-1E(F) was transferred to its maintenance supply per OS1047.02, Transferring Power Supplies To 120 VAC Vital Instrument Buses prior to inverter shutdown. On the other train PP-1 F(E) is energized from its inverter connected to the respective DC bus. Perform the task using OS1047.01, Vital Inverter Operation. We will begin after the Initiating Cue is read. I will act as the Unit Supervisor and provide cue,s and communications for this ..IPM. Do you have any questions?

Initiating Cue: US to Secondary NSO, "Secondary NSO (or student's name), simulate restarting UPS-1-EDE-I-1E(F) using OS1047.01 , Vital Inverter Operation, section 4.11 (4.12). All of the procedure prerequisites are complete." In-Plant 'A' Page 12 of 12

IN-PLANT JOB PERFORMANCE MEA.SURE 'B', LOCALLY CLOSE AN Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: ______________

_ TRAINING JOB PERFORMANCE Task Number and Description Position NSO SBK 0400100504 Locally close an MSIV Conditions: The plant has tripped from 100% power. SG C pressure is decreasing in an uncontrolled manner and has been identified as faulted. The US has transitioned from E-O to E-2 step 1. SG C MSIV is open. Standards:

Simulate locally closing the C MSIV in accordance with OS 1090.01 Manual Operation of Remote Operated Valves. Student Materials:

Copy of Tear Off Copy of OS1090.01 , Manual Operation of Remote Operated Valves, Rev Precautions (pages 5-9) and section 4.7 (pages Limitations On Performance:

Simulate all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures: OS 1090.0'1 Manual Operation of Remote Operated Valves E-2 Faulted S/G Isolation. Description I Value I KA _____________

+,.__ROffiRO . Knowledge of local auxilic3ry operator 3.8/4.0 I 2.4.35 tasks during an emergency and the resultant operational effects. In-Plant 'B' Page 2 of 9 I JOB PERFORMANCE Setting: Plant. East Pipe Chase. Safety Considerations:

Pipe chases safety requirements as posted for noise and steam exposure. Approximate Completion Time: 20 minutes Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional fCJr multiple A You are the Roving NSO. You are going to simulate locally closing an The following information is provided to The plant has tripped from 100%power. SG C pressure is decreasing in an uncontrolled manner and has been identified as faulted, The US has transitioned from E-O to E-2 step 1. SG C MSIV is open, Simulate the task using OS 1090,01 Manual Operation of Remote Operated Valves. We will begin after the Initiating Cue is read. I will act as the Unit Supervisor and provide cues and communications for this JPM. Do you have any questions? Initiating Cue: US to Roving NSO, "Roving NSO (or student's name), using OS 1090.01 Manual Operation of Remote Operated Valves go to the East pipe chase and locally close MS-V-90 the C MSIV." In-Plant 'B' Page 3 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes <:1 critical step SAT UNSAT When student demonstrates the ability to obtain a controlled copy of OS1090.01 Manual Operation of Remote Operated Valves provide the student with the required portions of OS1090.01 Manual Operation of Remote Operated Valves. P Start time _____ Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available Peer Check your actions. Please continue with the S Close the air isolation valves on Close MS-V-90-V-4C C MSIV IA a. Close MS-V-90-V-4C C MSIV IA isolation isolation When the student simulates CW motion to close the valve, evaluator to student, "The valve Close MS-V-90-V-4D C MSIV IA b. Close MS-V-90-V-4D C MSIV IA isolation isolation When the student simulates CW motion to close the valve, evaluator to student, "The valve Student should review the caution and note prior to step 4.7.3.2. The MSIV shuts when one solenoid is overridden, but the procedure and local operator aid has the operator override both solenoids.

To successfully complete the task only one of the solenoids has to be overridden. Local operator aid does not reflect recent procedure change. Noun names on tags do not match procedure noun names. In-Plant '8' Page 4 of 9

" , PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

___________

____________

__ *3. Manually open MS-FY-89A-3 dump pilot solenoid Remove threaded metal cap a. Removes threaded metal cap covering override assembly covering I:>verride assembly When student simulates CCW motion to remove the cap, evaluator to student, "The metal cap has been removed." Using ratchet wrench turn the *b. Using ratchet wrench turns the manual override hex nut manual override hex nut clockwise until the hydraulic fluid clockwise until the hydraulic fluid is bled off. is bled off. When the student simulates CW motion to bleed off the hydraulic fluid, evaluator to student, hydraulic fluid is bleeding off. The MSIV is Reinstall threaded metal cap c. Reinstalls threaded metal cap covering the override assembly covering the override assembly When the student simulates reinstalling the metal cap, evaluator to student, "The metal cap been

4. Manually open MS-FY-89B-3 main dump pilot solenoid valve: Remove threaded metal cap a. Removes threaded metal cap covering override assembly covering override assembly CUE: When student simulates CCW motion to remove the cap, evaluator to student, "The metal cap has been removed." In-Plant 'B' Page 5 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

___________

__ __

__________

S_A_T Using ratchet wrench turn the *b. Using ratchet wrench turns the manual override hex nut screw manual override hex nut clockwise until the hydraulic fluid clockwise-until the hydraulic fluid is bled off. is bled off. When the student simulates CW motion to bleed off the hydraulic fluid, evaluator to student, hydraulic fluid has bled off. The MSIV is Reinstall threaded metal cap c. Reinstalls threaded metal cap covering the override assembly covering the override assembly When the student simulates reinstalling the metal cap, evaluator to student, "The metal cap been S Close MSIV hydraulic supply isolation Simulates closing MSIV valve supply isolation valve When student correctly simulates closing MS-V-434, evaluator to student, "MS-V-434 is closed." If the student states that the MSIV hydraulic air motor should start, the hydraulic supply isolation valve was just shut, therefore, the air motor should not start. "The JPM is complete." Stop time ____ Time to complete task S 20 minutes Evaluator calculates time to 7 Obtain from Tear Off sheets and any other materials used in performance of In-Plant '8' Page 6 of9 IN-PLANT "8' JPM*ATTACHMENT MANUAL MSIV MSIV HYDRAULIC MAIN DUMP MAIN DUMP IA ISOLATIONS ISOLATION PILOT SOL 1 PILOT SOL 2 8 MS-V-435 MS-FY -89A-2 MS-FY -89B-2 MS-V-88-V4C,V4D C MS-V-434 MS-FY -89A-3 MS-FY -89B-3 MS-V-90-V4C,v4D In-Plant 'B' Page 7 of 9 PERFORMANCE Provide comments on unsatisfactory performance of an elementlstelp or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial if necessary.

In-Plant 'B' Page 8 of9 TEAR OFF SHEET FOR IN-PLANT 'B' Directions To The Student: Student: You are the Roving NSO. You are going to simulate locally closing an MSIV. The following information is provided to you: The plant has tripped from 100%power. SG C pressure is decreasing in an uncontrolled manner and has been identified as faulted. The US has transitioned from E-O to E-2 step 1. SG C MSIV is open. Simulate the task using OS 1090.01 Manual Operation of Remote Operated Valves. We will begin after the Initiating Cue is read. I will act as the Unit Supervisor and provide cues and communications for this JPM. Do you have any questions?

Initiating Cue: US to Roving NSO, "Roving NSO (or student's name), using OS 1090.01 Manual Operation of Remote Operated Valves go to the East pipe chase and locally close MS-V-90 the C MSIV." In-Plant 'B' Page 9 of9

ENER...

SEABROOK IN-PLANT JOB PERFORMANCE MEASURE 'C', ALIGN ALTERNATE (DEMIN WATER) COOLING TO CCP LUBE OIL Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2013 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: DATE: ______

N'-:-I JOB PERFORMANCE

1. Task Number and Description NSO SBK Align/Remove Alternate Cooling To Charging pump Lube Oil Coolers 2. Conditions:

A. Plant is in Mode 4. B. CS-P-2A is not available.

C. Train B PCCW has been lost. D. The US has entered OS1212.01, PCCW System Malfunction.

3. Standards:

Simulate manually aligning alternate cooling from DEMIN to CS-P-2B per OS1002.02, Operation Of Letdown, Charging, and Seal Injection.

4. Student Materials:

Copy of Tear Off Copy of OS1002.02 , Operation Of Letdown, Charging, and Seal Rev 5. Limitations On Performance:

Simulate all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the 6.

References:

Procedures:

OS1212.01 , PCCW System Malfunction.

OS1002.02 , Operation Of Letdown, Charging, and Seal Injection Value Sys Description RO/SRO 008 Ability to (a) predict the impacts of the 3.3/3.6 following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or opl3rations:

Loss of PCCW pump. I In-Plant IC' Page 2 of 10 JOB PERFORMANCE Setting: Plant. PAB 25 ft and PAB 7 ft. Safety Considerations:

Health Physics postings and ALARA. Approximate Completion Time: 20 minutes Directions To The Student: Evaluator gives Tear Off sheet to the Evaluator reads the following to student (Optional for multiple You are the Primary NSO. You are going to simulate locally aligning Oemin water (OW) as alternate cooling to CS-P-2B lube oil cooler. The following information is provided to you: Plant is in Mode 4. CS-P-2A is not available. Train B PCCW has been lost. The US has entered OS1212.01, PCCW System Malfunction. OS1212.01 Attachment A Shift Charging Pump/Align Cooling step 1 RNO instructs crew to align alternate cooling to charging pump lube oil cooler per OS1002.02 , Operation Of Letdown, Charging, and Seal Injection. The Roving NSO and a Fire Fighter have been dispatched to connect the drain hose from the Charging Pump lube oil coolers outlet to a storm drain and the drain hose has been connected at the storm drain end (OS1002.02 step 4.21.2). Chemistry has generated the Non-Rad release permit and it is in the control room." All applicable Tech Specs have been entered. Perform the task using OS1002.02, Operation Of L.etdown, Charging, and Seal Injection. We will begin after the Initiating Cue is read. I will act as the Unit Supervisor and provide cues and communications for this JPM. 00 you have any questions?

In-Plant Page 3 of JOB PERFORMANCE

11. Initiating Cue: US to Primary NSO, "Primary N80 (or student's name), simulate aligning Demin water as alternate cooling to C8-P-2B lube oil cooler using 081002.02 section 4.21. Inform the control room as soon as cooling flow has been established." In-Plant 'e' Page 4 of 10 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform 3=Simulate

denotes a critical step

denotes a critical step SAT UNSAT When student demonstrates the ability to obtain a controlled copy OS1002.02, Operation Of Letdown, Charging, and Seal Injection provide the student with the required portions OS1002.02, Operation Of Letdown, Charging, and Seal Injection. P Start time _____ Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available Peer Check your actions. Please continue with the Student should review CAUTION prior to step 4.21.1. S Notify Chemistry to issue a Non-Rad Initial conditions state Chemistry has release issued a Non-Rad release permit and it is in control room. S Connect a drain hose from Charging Initial conditions states Roving pump lube oil cooler outlet to the and a Fire Fighter have connected storm drain. drain hose from Charging pump oil cooler outlet. S Refer to listed Technical Simulates informing control room to Specifications for refer to Technical Specifications for applicability.

In-Plant "C' Page 5 of 10

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

__________

___________

__ 5. Check that CS-P-2B is in Pull To Simulate checking that CS-P-2B is in S Lock. Pull To CUE: When student checks on the status of CS-P-2B, US to NSO,"CS-P-2B is in Pull To Valves CC-V-315, CC-V-318, CC-V-1292, DM-V-793, and CC-V-1294 are all located along the outside the degassifier room in the main passageway of the PAB 25 ft. across from the If the student requests permission to unlock and close CC-V-318, PCCW return from CS-P-2B oil cooler and CC-V315, supply to CS-P-2B oil cooler, US to NSO, "You have permission to unlock and close CC-V-318 and CC-V-31S." Required keys would be on the Primary NSO key ring. *6. S Unlock and close the following *a. Simulates unlocking and CC-V-318, PCCW return CS-P-2B oil When student simulates unlocking and closing CC-V-318, evaluator to student, "The valve unlocked.

The valve is Simulates unlocking and closing CC-V315, PCCW supply to 2B oil cooler. When student simulates unlocking and closing CC-V-315, evaluator to student, "The valve unlocked.

The valve is In-Plant 'C' Page 6 of 10 PERFORMANCE D=Discuss ELEMENT/STEP EVALUATION P=Perform S=Simulate

denotes a critical step

denotes .a critical SAT UNSAT *7. Demin water is to be aligned to CS-P-2B oil cooler. Aljgn the Simulate::;

releasing locking pin and opening CC-V-1292 demin alternate cooling supply to CS-P-2B oil coolers. When student simulates releasing the locking pin and opening CC-V-1292, evaluator to student, "The locking pin releases.

The valve is open." If student does not simulate release of locking pin, cue, "The valve does not move." Simulatel:;

opening DM-V-793 demin alternate cooling supply to Charging pump oil coolers. When student simulates opening DM-V-793, evaluator to student, "The valve is open." NOTE: Student should not perform step 4.21.7. Demin water is being used for alternate cooling. NOTE: Student should review NOTE prior to step 4.21.8. *8. Throttle CC-V-1294 CS-P-2B oil Simulates locking pin cooler alternate cooling outlet as throttling open CC-V-1294 necessary to maintain 10-30 gpm. oil cooler alternate cooling When student simulates releasing the locking pin and throttling CC-V-1294, evaluator to "The locking pin releases.

The valve is throttled open. You hear flow." If student does simulate release of locking pin, cue, "The valve does not In-Plant 'C' Page 7 of 10 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

___

_d_e_no_t_e

__ __________.

T_______________

____ __ S Check flow on CC-FISL-2218.

Simulates checking flow When student simulates checking flow, evaluator to student, "The indicator shows 25 gpm." S Inform control room that alternate Simulates informing control room cooling using Demin water has been alternate cooling using Demin established to CS-P-2B oil cooler at has been established to CS-P-2B 25 gpm. cooler at 2t) US to I\ISO, "I copy, alternate cooling using Demin water has been established to CS-P-2B oil cooler at 25 gpm. We will enter this on the Non-Rad release permit. We will monitor Charging pump temperatures." "The JPM is complete." 11. Stop time ___Time to complete task S 20 minutes Evaluator calculates time to Obtain from Tear Off sheets and any other materials used in performance of In-Plant 'C' Page 8 of 10 PERFORMANCE SUMMAFty Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial if necessary.

In-Plant 'C' Page 9 of 10 TEAR OFF SHEET FOR

'C' JPM Directions To The Student: You are the Primary NSO. You are going to simulate locally aligning Oemin water (OW) as alternate cooling to CS-P-28 lube oil clJoler. The following information is provided to you: Plant is in Mode 4. CS-P-2A is not available. Train 8 PCCW has been lost. The US has entered OS1212.01, PCCW System Malfunction. OS1212.01 Attachment A Shift Charging Pump/Align Cooling step 1 RNO instructs crew to align alternate cooling to charging pump lube oil cooler per OS1002.02 , Operation Of letdown, Charging, and Seal Injection. The Roving NSO and a Fire Fighter have been dispatched to connect the drain hose from the Charging Pump lube oil coolers outlet to a storm drain and the drain hose has been connected at the storm drain end (OS1 002.02 step 4.21.2). Chemistry has generated the Non-Rad release, permit and it is in the control room." All applicable Tech Specs have been Perform the task using OS1002.02, Operation Of Letdown, Charging, and Seal Injection. We will begin after the Initiating Cue is read. I will act as the Unit Supervisor and provide cues elnd communications for this JPM. 00 you have any questions?

Initiating Cue: US to Primary NSO, "Primary NSO (or student's name), simulate aligning Demin water as alternate cooling to lube oil cooler using OS1002.02 section 4.21. Inform the control room as soon as coolin!g flow has been established." In-Plant 'C' Page 10 of 10 SIMULATOR EXERCISE GUIDE SITE: Seabrook Revision #: FINAL LMS 10: LMS Rev. Date: SEG TITLE: 2013 LOIT NRC SIM Exam 1 SEG TYPE: o Training Evaluation PROGRAM: o LOCT o Other: DURATION:

90 minutes Developed by: Instructor/Developer Date Reviewed by: Instructor (Instructional Review) Date Validated by: SME (Technical Review) Date Approved by: Training Supervision Date Approved by: Training Program Owner (Line) Date TR-AA-230-1003-F06 Revision 0 Page 1 of 26 2013 LOIT NRC SIM Exam 1 SEG UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003)

I made to the material after initial approval.

Or use separate Update Log form TR-AA-230-1003-F16.

DESCRIPTION OF CHANGE REASON FOR CHANGE ARlTWR# PREPARER REVIEWER DATE DATE i -I I i i i i I i TR-AA-230-1003-F06 Revision 0 Page 2 of 26

",;:><'era

'. ENE 2013 LOIT NRC SIM Exam 1 SEG OVERVIEW I SEQUENCE OF EVENTS OVERVIEW The crew will take the watch at MOL 55% power with, stable xenon, boron concentration at 1314 ppm, CB D at 205 steps and both Main feed Pumps and one Heater Drain pump in service. CBS-P-9-A is tagged out for maintenance.

The crew will begin a power increase at 5%/hr to 75% power. 'A' SG Level Instrument controlling channel will fail low. The crew will then experience CC-V-341 failing closed which will force them to use excess letdown. A seismic event will cause rod HS to drop. CBS -P-9-B loss of all oil. Two CBS pumps INOP. T.S. 3.0.3 entry. While I&C is checking fuses for dropped rod recovery, rod FS drops, requiring a manual reactor trip. On the reactor trip the 'C' SG will fault inside containment.

The auto isolation for 'C' SG EFW flow control valves will be defeated and manual action to close the valves will be required.

When the SI occurs, CS-P-2-A will trip and lockout. CS-P-2-B will not auto start and must be manually started by the PSO. With no CBS pumps containment pressure will increase >1Spsig and Z will go ORANGE requiring FR-Z.1 entry. SEQUENCE OF EVENTS Event # Description i 1. Crew begins a 5%/hr power increase.

2. FW-LT-551, 'A' SG Level Instrument controlling channel fails low. 3. CC-V-341 fails closed. Crew is forced to use excess letdown. 4. Seismic event causes rod HS to drop. 5. I Loss of all oil to CBS-P-9-B.

T.S.3.0.3 entry. 6. While I&C is checking fuses for dropped rod recovery, rod FS drops, requiring a manual reactor trip. On reactor trip the 'C' SG faults inside containment.

7. When SI occurs, CS-P-2-A trip and lockout. CS-P-2-B blocked from starting on SI. B must be manually started by PSO. S. Defeat the auto isolation for the 'C' SG EFW flow control valves FW-FV-4234-A and FV-4234-B.

Manual action to close the valves will be required.

I TR-AA-230-1003-F06 Revision 0 Page 3 of 26 2013 LOIT NRC 81M E:x:am 1 SEG SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the Simulator Setup Checklist.

General Instructions

a. Provide extra copies of procedures to Examiners

b. Reset to IC #150 c. Place simulator in Run d. Verify the following have been inserted OR reset to IC #38 and insert the following:

1. B Train is Protected, SV C0755, '2' 2. Tagout CBS-P-9-A

SELECT: RF List

SELECT: Containment Spray (Component)

SELECT: cCBSP9A

SELECT: RACK OUT

SELECT: INSERT 3. Block CS-P-2-B from starting on SI:

SELECT: MF List

SELECT: Chemical and Volume Control

SELECT: mfCS002

SELECT: INSERT 4. Defeat the auto isolation for the 'C' SG EFW flow control valve FW-FV-4234-A:

SELECT: Scenario

OPEN: Sim Support

SELECT: C SG EFW Auto Isolation Defeat

SELECT: Run

SELECT: OK e. Insert Event Trigger

SELECT: Event Triggers

OPEN: Sim Support

SELECT: SG FAULT

SELECT: Activate TR-AA-230-1003-F06 Revision 0 Page 4 of 26 i\,jt:xrera*

2013 LOIT NRC SIM Exam SEG FIHT Place tag on CBS-P-9-A control switch. Depress the CBS Train A BypassllNOP pushbutton on ECCS Train A BypassllNOP section. h. Ensure that FW-L-551 is the contrOlling channel for 'A' SG L Advance logger and tear off any sheets with Procedure OS1000.05, Power Increase is being performed and is completed to step 4.2.39. Provide appropriate shift turnover documentation, TR-AA-230-1003-F06 Revision Page 5 of 26

_____

___________ __ __ __________2_0_1_3_L_O_IT N_R_C_S_IM E_Xan_11 SHIFT TURNOVER INFORMATION

See Turnover Sheet TR-AA-230-1003-F06 Revision 0 Page 6 of 26 rera 2013 LOIT NRC SIM Exam 1 l SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT Event 1 PSO (R), BOP (N), US (N) Allow the students to increase plant power Start Crew Begins the Power increase lAW MPE Procedure OS1000.05, to the extent that a significant manipulation is The crew should prepare for and initiate a power increase at 5%/hr. Unit Supervisor:

A brief reactivity review will take place discussing the temperature limits for Tavg to be used in the power increase.

The temperature band will normally be + 1.5°F with rods in Auto or + 3°F with rods in manual. Dilution will be used for temperature control during the power increase.

Control rods will be used for AFD and temperature control. Turbine Operations:

The BOP will increase turbine load using automatic DEHC operations..*

Using the laminated sheets, Figure 19 of OS 1000.10, . The basic steps are:

Check the Load Set is in Hold mode.

Insert the desired loading Rate.

insert the desired Power Level. I

VVhen ReS temperature begins to Increase, Select "Load."

Monitor turbine loading using "Load Status" is Loading and "Load Actual" increases.

The BOP should verify the change with control valve position change, temperature change and power change.

At any time during the automatic loading, the power increase can be stopped by activating the "Hold" function.

TR-AA-230-1003-F06 Revision 0 Page 7 of 26 1--2013 LOll NRC SIM Exam SEG J TIME/NOTES Power Increase (continued)

SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS i INSTRUCTOR EXPECTED STUDENT RESPONSE Reactor Power change: The crew will use dilution to increase temperature during the turbine load increase.

A dilution value will be determined to change the boron concentration and increase power/temperature.

If control rods are used in manual to control AFD I temperature, the operator will verify rod speed, place the Rod Motion Selector (In-Hold-Out) switch to the OUT direction and withdraw the rods a maximum of three steps. The PSO will monitor temperature and power as confirmation of actions. Using the laminated sheets of OS 1008.01, Figure 2, Dilution Check List, the PSO will set up the controllers for the required dilution volume and rate. The high level steps are:

Verify the pumps are in AUTO

Verify the makeup valves are in AUTO

Place Blender Mode Start Switch to STOP

Place the Mode Selector Switch to DILUTE or ALT DILUTE

Set the quantity and flow rate on CIS-FIQ-111 controller During validation the crew used a dilution value of 950 gallons in approximately 240 gallon batches every 15 minutes.

If not desired, select OFF for the "Stepback Feature"

Set the Mode Start Switch to START

Verify the pumps and valves respond

Verify Plant Response.

Restore System to Automatic control TR-AA-230-1003-F06 Revision Page 8 of 26

2013 LOIT NRC SIM Exam 1 SEG FU'ET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES Event 2 After Power I ncrease or At Lead Examiner's Discretion INSTRUCTOR ACTIVITY FW-L T-551 , 'A' SG Level Instrument controlling channel fails low:

SELECT: MF List

SELECT: Feedwater (Component)

SELECT: ItFWL T551

SELECT: FAIL LOW

SELECT: INSERT If the crew calls the WCSIWWM for the FW-L T -551, then respond "Understand that FW-L T -551 has failed low. A troubleshooting team is being formed." EXPECTED STUDENT RESPONSE BOP (I), US (I, FW-L T -551, 'A' SG Level Instrument controlling channel fails Initial 04770 SG A LVL REF 04876 SG A LEVEL F4756 SG A LEVEL F5871 SG LEVEL LO ATWS CHANNEL UA-53 A-3 SG A LEVEL US will ask BOP if a controlling

'A' SG Level channel has failed. BOP identify that FW-LT-551, 'A' SG Level Instrument controlling channel failed low. US will direct BOP to take manual control of the 'A' SG control valve and return 'A' SG level to 45% to 55%. BOP will inform when 'A' SG level is under his US enters 081235.03 , 8G Levei instrument Faiiure and directs the foiiowing I actions: Step 1: Check Steam Generator Water Level Control:

BOP will report FW-L T-551 failed low.

BOP will report 'A' SG feed control valve in manual.

BOP will control 'A' SG level to 45% to Step 2: Realign Steam Generator Level

BOP will select an alternate controlling channel for 'A' SG Step 3: Align Steam Generator Water Level

BOP will check steam flow/feed flow signals matched, 'A' SG level 50%, proper controller setpoint and then place the controller in TR-AA-230-1003-F06 Revision Page 9 of26 era 2013 LOIT NRC SIM Exam SEG ,fo P #* NUCtEAR Fl.liET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES FW-LT-5S1, 'A' SG Level Instrument controlling channel fails low. (continued)

INSTRUCTOR ACTIVITY If the crew calls the WCSIWWM for I&C, then respond "I&C is on their way to the control room." IF NEEDED at OS1235.03, step 6:

SELECT: Panel Overview

SELECT: AMSAC CP-519

SELECT: SG A (L551) EXPECTED STUDENT RESPONSE Step 4: Verify redundant channels bistables not tripped:

PSO will report redundant channels bistables not tripped on UL-1 and 6.

BOP will report redundant channels bistables not tripped on UL-12. Step 5: US will verify technical specification compliance:

T.S. 3.3.1, Reactor Trip System Instrumentation; Action 6

T.S. 3.3.2, Engineered Safety Features Actuation System Instrumentation; Action 18

US will coordinate with I&C to place bistables to bypass for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Step 6: US will direct BOP to verify A TWS Mitigation Input Status:

BOP will verify that 551 is the failed channel.

BOP will check UL-28 bistables per US direction. US will direct I&C to place failed channel in 1-MM-CP-519, mitigation system cabinet to -OPERATE TR-AA-230-1003-F06 Revision Page 10 of 26

2013 LOIT NRC SIM Exam SEG ",/fo"'<"" SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES Event 3 After T.S. Call is made (Can be left for post scenario)

INSTRUCTOR ACTIVITY CC-V-341 fails closed: SELECT: MF List SELECT: Primary Component Cooling (Component) SELECT: cCCV341 SELECT: Fail Closed SELECT: INSERT

If the crew dispatches an NSO to 341, respond "This is Primary NSO, go toCC-V-341 and let you know what I find." If the crew dispatches an NSO to 341, wait 2 minutes then respond "This is the NSO, I am at CC-V-341 is closed and the airline appears to have failed." If the crew calls the WCSNVWM for maintenance support for CC-V-341 , then respond "I will inform maintenance that CC-V-341 airline appears to have failed." If the crew calls Chemistry, then respond "Chemistry understands that letdown cooling has been lost (OR lost letdown)." EXPECTED STUDENT RESPONSE PSO (C), US CC-V-341, PCCW to Letdown Heat Exchanger, fails Initial 04692 LTON HX OUTLET TEMPERATURE 04695 L TON HX TEMP HIGH &OEMIN "Skill of the operator" may be utilized to close CS-V-145 and reduce to seal PSO may review 04692, LTON HX Outlet Temperature High and under US direction will complete the following Step 1: PSO will verify high temperature on Step 2: PSO will verify CS-TK-130 proper Step 3: PSO will find CC-V-341 closed and attempt to NOTE: At this time the US may direct PSO to isolate letdown by closing V-145 due to loss of letdown temperature control and enter Loss of Step 4: US, PSO or BOP will contact Step 5: US will direct transfer to Excess Step 6: PSO will monitor RCP TR-AA-230-1003-F06 Revision Page 11 of26

---rera 2013 LOIT NRC SIM Exam 1 SEG NUClEAR FlEET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE 3 minutes after CC-V-341, PCCW to Letdown Heat Exchanger, fails closed. Alarm: Letdown Heat D4698 VCT TEMP HIGH Exchanger, fails closed. PSO or BOP may review D4698, VCT Temp Hi and under the US direction will complete the following actions: Step 1: PSO will verify VCT high temperature on CS-Step 2: PSO will verify CS-TK-130 proper Step 3: PSO will find CC-V-341 closed and attempt to Step 4: PSO will inform US that letdown temperature cannot be controlled setpoint and recommend isolating letdown by closing CS-V-145

US will direct PSO to close CS-V-145 .

After CS-V-145 is closed, US will direct PSO to reduce charging flow to the RCP seals only (approximately 32 gpm). I Step 5: US will enter OS1202.01, Loss of Letdown. I Step 6: PSO will monitor RCP parameters.

TR-AA-230-1003-F06 Revision 0 Page 12 of 26 era' 2013 LOIT NRC SIM Exam 1 ,,-,/fi'" SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECIED STUDENT RESPONSE CC-V-341, US enters OS1202.01, Loss of Letdown and directs the following actions: PCCWto Step 1: Check for Letdown Isolation:

Letdown Heat

PSO will report pressurizer level (>17%) Exchanger, closed.

US will go to Step 2 per the (continued)

Step 2: Check Letdown System

PSO or BOP will verify radiation levels are normal. Step 3: Check Status Of Letdown:

PSO will report Normal Letdown is not in service.

US will direct PSO to adjust charging flow to control PZR level on program, as necessary.

US will go to Step 4 per the RNO. Step 4: Check Normal Letdown Flowpath Alignment:

PSO will verify valves as requested by US or tell US that normal letdown is not available.

PSO will report BTRS is in OFF. Step 5: Check VCT Makeup Control System: I

PSO will check blended makeup boron concentration set at required RCS boron concentration.

PSO will align makeup for automatic control. Step 6: Check If Normal Letdown Can Be Established:

PSO will verify charging flow and pressurizer level as requested by US or tell US that normal letdown is not available.

US will go to Step 7 per the RNO. -TR-AA-230-1003-F06 Revision 0 Page 13 of 26

2013 LOIT NRC SIM Exam 1 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY CC-V-341, PCCWto Letdown Heat Exchanger, fails closed. ( continued)

-!f the crew calls the waste NSO to inform 1 him that they are flushing excess letdown to the RCDT, respond "This is Waste NSO, you are flushing excess letdown to the RCOT. I will monitor the service PDT level during the RCOT pump down." EXPECTED STUDENT RESPONSE US will read CAUTION prior to Step 7:

Do NOT exceed excess letdown heat exchanger outlet temperature

Do NOT exceed excess letdown heat exchanger outlet pressure of 150 PSIG. Step 7: Establish excess letdown:

PSO will open CC-V-434, excess letdown heat exchanger cooling

PSO will check open RCP seal return containment isolation valves: 167 and CS-V-168.

PSO will check closed CS-HCV-123.

PSO will open excess letdown containment isolation valves:

and

PSO will flush excess letdown heat exchanger to RCDT by performing the following:

o Align CS-V-170 to the RCDT position.

() Slowly throttle CS-HCV-123 open and flush to RCDT for greater than five minutes. o Close CS-HCV-123.

PSO will align CS-V-170 to the SEAL RET HDR position.

PSO will establish desired excess letdown flow by throttling open HCV-123 while monitoring excess letdown heat exchanger temperature and

PSO will remove normal letdown flow input to plant calorimetric by deleting from scan A0620, CS-E-4 LETDN OUTL FLOW. Step 8: Restore Normal Pressurizer Level Control:

PSO will control charging and letdown flow to maintain pressurizer at program level and control RCP seal injection flow between 8 and gpm to each TR-AA-230-1003-F06 Revision 0 Page 14 of 26

3 LOIT NRC SIM Exam 1 I SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES Event 4 After Excess Letdown is established or at Lead Examiner's Discretion INSTRUCTOR ACTIVITY Simultaneous Events Seismic Event:

SELECT: MF List

SELECT: Seismic Monitoring

SELECT: mfSM001

SELECT: INSERT Rod H8 Drop:

SELECT: MF List

SELECT: Rod Control and Position

SELECT: mfCP018

SELECT: INSERT EXPECTED STUDENT RESPONSE PSO (C), BOP (C), US (C, TS) Seismic Event coincident with rod H8 drop. Initial Alarms: 05452 SEISMIC EVENT IN PROGRESS 07753 CONTROL ROD DEVIATION 07730 ONE ROD ON BOTTOM B7457 ROD MOTION DETECTED F8105 DRPI/DEMAND DEVIATION

-12 STEPS IF rod control is in Auto, rods may step out. In this case the US will instruct the BOP to check generator load stable and then direct the PSO to place rods in rJlanual.

PSO identifies to US that rod H8 has dropped from DRPI and temperature response as seen on TavglTref indication.

US enters OS1210.05, Dropped Rod and directs the following actions: Step 1 : Stabilize Plant Conditions:

PSO will check ONLY one rod dropped and report H8 has dropped.

PSO will place rod bank selector switch in MANUAL.

BOP will reduce turbine load and maintain TavglTref matched.

BOP will check C-7A TURB LOAD REDUCTION status light on

PSO will the reactor is critical.

TR-AA-230-1003-F06 Revision 0 Page 15 of 26

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2013 LOIT NRC SIM Exam 1 SEG /"",y;<} NUClEAR FLEET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Seismic Event Step 2: Evaluate Conditions For Dropped Rod Recovery:

coincident with

Verify Technical Specification compliance rod H8 drop_ o T.S. 3.1.3.1, Movable Control Assemblies ( continued)

Consult with the Shift Manager and Reactor Engineering to evaluate the recovery_

If the crew calls the SM or RE to recovery, then respond "Recover dropped rod as soon Seismic Event If the crew calls the WCSIWWM for I&C, Step 3: Notify I&C To Check Rod Control System Status: coincident with then respond "I&C is on their way to 'A'

US will have I&C verify power to the dropped rod is available by checking rod H8 drop_ essential switchgear to check for a for blown fuse at the rod control cabinets. (continued) blown fuse at the rod control cabinets." I -. .* US Will have I&C venfy rod control cabinet alarms are clear for: o Logic Ilf the crew calis I&C to verify rod o All five power cabinets cabinet alarms are clear, then "All rod control cabinet alarms are TR-AA-230-1003-F06 Revision 0 Page 16 of 26 I 2013 LOIT NRC SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Seismic Event When the crew calls the SM to refer to ER-When the plant is stable PSO or BOP will review D5452, Seismic Event in coincident with 1.1, respond "I will review ER-1.1." Progress, and under the US direction will complete the following actions: rod H8 drop. Step 1: PSO will check the Event Light (yellow) or the OBE Light (red) is lit (continued) at SM-CP-58.

When the crew calls plant respond "Perform ES1802.001, Step 2: PSO and BOP will check the MCB and plant conditions for Earthquake Response."

Step 3: PSO will contact I&C to perform IX1670.905.

When the crew calls National Earthquake Step 4: US will inform SM to refer to ER-1.1, Classification of Emergencies.

Information Center, acknowledge the Step 5: US will contact plant engineering to perform ES1802.001, report. "Earthquake Response".

Step 6: US will refer to TR21-4.3.3.3.2, Seismic Instrumentation.

When the crew calls the NSOs to ensure Step 7: US will report the seismic event to the National Earthquake safety, respond "All NSOs are in NSO Information Center at 1-303-273-8500.

central." Step 8: PSO or BOP will perform a radio check with all NSOs to ensure safety. TR-AA-230-1003-F06 Revision 0 Page 17 of 26

2013 LOIT NRC SIM Exam 1 SEG Event 5 US (TS) CUE: Mechanic calls control room and Loss of reports: "Control this is Scott Lavoie.9-B

Crew should recognize that with both CBS pumps inoperable, We are working on CBS-P-9-A, but we got on the wrong train and drained all

Tech Spec 3.0.3. entry required.

of the oil out CBS-P-9-B."

Good operator practice will be to place the CBS-P-9-B control switch in PTL CUE: If US asks Mechanic or WCS how long to replace the oil in CBS-P-9-B, respond: "It will take us about 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the pump is tagged out." CUE: If US asks Mechanic or WCS the status of CBS-P-9-A, respond: "No work has been performed." CUE: If US asks WCS to restore A, respond: "I will start releasing tags now." TR-AA-230-1003-F06 Revision 0 Page 18 of 26 2013 LOIT NRC 81M Exam 1 SEG fl£Er Event 6 During I&C check of Rod Control System Status at Step 3 or at Lead Examiner's Discretion Rod Fa drops:

SELECT: MF List

SELECT: Rod Control and Position

SELECT: mfCP009

SELECT: INSERT PSO (M), BOP (M), US (M) While I&C is checking fuses for dropped rod recovery, rod Fa Initial 07749 TWO OR MORE RODS ON 04421 TAVG-TREF PSO identifies to US that rod Fa has also US will go back to continuous action step 1 of OS1210.05, Dropped Rod directs the following Step 1: Stabilize Plant

PSO will check ONLY one rod dropped and report Fa has also and there are now 2 dropped

US will direct manual reactor trip.

US will direct crew to enter E-O, Reactor Trip or Safety Injection and perform their immediate TR-AA-230-1003-F06 Revision 0 Page 19 of 26

\j:::xrera 2013 LOll NRC 81M Exam 1 I SEGJNUCLEAR FLEET When crew trips the Reactor Event 7 Critical Task Simultaneous Events will occur from Event Trigger SG FAULT OR insert the following:

'C' SG faults inside containment: SELECT: MF List SELECT: Main Steam SELECT: mfMS049C SELECT: Set Final Value to 0.03

SELECT: INSERT CS-P-2-A trip and lockout when SI occurs: SELECT: MF List SELECT: Chemical and Volume Control SELECT: mfCS016 SELECT: IN$ERT E-O, Reactor Trip or Safety Injection US will direct crew to enter E-O, Reactor Trip or Safety Injection and to perform their immediate actions. 'C' SG faults inside containment which will cause a Safety Injection on Containment pressure in approximately 15 seconds. This will result in Adverse Containment.

Step 1: Verify Reactor Trip:

PSO will check Rod bottom lights lit, reactor trip and bypass breakers open and neutron flux Step 2: Verify Turbine

BOP will check all stop valves or all control valves closed and the generator breaker Step 3: Verify Power To AC Emergency

BOP will check both AC emergency busses Step 4: Check If SI Is

PSO will check both SI annunciators lit. NOTE: US will direct PSO and BOP to bring up their alarms and notify him of any immediate plant concerns and share any pertinent plant information.

At I this time the PSO may identify that CS-P-2-A tripped and is locked out and that CS-P-2-B is not running. US may direct PSO to start CS-P-2-B by of the Step 5: Perform ESF actuation verification per Attachment

PSO will perform Attachment PSO

When SI occurs, CS-P-2-A will trip and lockout. CS-P-2-B is blocked from starting on SI. CS-P-2-B must be manually started by PSO. TR-AA-230-1003-F06 Revision Page 20 of 26

2013 LOll NRC SIM Exam [mE-O, Reactor PSO performing Attachment A while US and BOP process E-O. Trip or Safety PSO will verify Containment Isolation Phase A Actuation by Injection checking all status panel lights lit for both trains. ( continued) PSO will verify Safeguard Equipment Alignment by checking proper alignment by status panel for both trains. If not previously done, PSO will identify CS-P-2-A trip and lockout and CS-P-2-B failure to auto start and will start B. PSO will verify Feedwater Isolation by checking proper alignment by status panel. PSO will verify a PCCW Pump running in both loops. PSO will verify ECCS Flow by checking: CCP indicated flow to RCS cold legs. RCS pressure <1700 psig, SI pump indicated flow to both trains . . RCS pressure >300 psig, go to Step 6. PSO will verify MS-V-129 is open. 7. PSO will verify a SW Pump running in both trains. I 8. PSO will verify SW flow to Train A and Train B Diesels >900 gpm. I PSO will check all main steamlines isolated with containment pressure >4 psig. 10. PSO will check Containment Pressure has remained <18 pSig by pressure recording.

11. PSO will verify Total EFW flow >500 gpm. 12. PSO will not need to reset RMO .. 13. PSO will notify US of Actuation Verification Status. Attachment A is complete.

TR-AA-230-1003-F06 Revision Page 21 of 26

---era' ENEBQY_& 2013 LOll NRC SIM Exam 1 SEG NUGI.EAR ftEET E-O, Reactor Step 6: Monitor RCS Temperature stable at or trending to 55rF. Trip or Safety

BOP will report temperature less than 557°F and decreasing.

Injection

US will direct the following actions: (continued) o Stop dumping steam to condenser and atmosphere.

o Check MS to MSRs isolated.

BOP (e)Event 8 NOTE: The following 2 steps may have been performed per the E-O OAS Critical Task page. Additionally, the BOP may stop all flow to the faulted 'C' SG by closing FW-V-4234A and/or FW-V-4234B.

o If cooldown continues, then open EFW pump mini flow valves and throttle total feed flow to maintain greater than 500 GPM. o When SG level is adequate based on 15% narrow range in at least one SG (Adverse Containment) then throttle feed flow to maintain SG narrow range level between 15% and 50% (Adverse Containment).

o If cooldown continues, then close MSIVs, MSIV bypass valves and upstream drains Step 7: Check RCS Isolated:

BOP will check CS-V-145, both PORVs and both normal PZR spray valves closed. Step 8: Check If RCPs Should Be Stopped: Whenllf CBS-P-9-B starts( approx. 5

BOP will check at least one running ECCS pump and report RCS minutes following reactor trip} , trip pump. subcooling greater than 40°F. Critical Task SELECT: Malfunction list. NOTE: At 18 psig in containment the P signal will actuate. This will SELECT: Containment Spray System. isolate all PCCW to containment.

Per the E-O OAS page the PSO will secure all RCPs.SELECT: mfsCBS003 Step 9: Check If SG Pressure Boundary Is Faulted: SELECT: Enter

BOP will check pressures in all SGs and report 'C' SG pressure decreasing in an uncontrolled manner.

US will direct ent to E-2, Faulted Steam Generator Isolation,

1. TR-AA-230-1003-F06 Revision Page 22 of 26 NEXT era flEET FR-Z.1, Response to High Containment Pressure 2013 LOIT NRC 81M Exam 1 SEG NOTE: US will direct crew to enter E-2, Faulted Steam Generator Isolation.

US, PSO or BOP will announce that Critical Safety Functions (CSFs) are in effect. At 18 psig in containment the P signal will actuate. CBS pumps will not operate and containment pressure will remain >18psig. This will signal an Orange path on the CSF for containment.

The US will direct entry to Z.1, Response to High Containment Pressure.

FR-Z.1, Response to High Containment Pressure Step 1: PSO will verify Containment Isolation Phase A Actuation by checking all status panel lights lit for both trains. Step 2: Check If Containment Spray Is Required:

PSO will report containment pressure >18 psig .

PSO will report containment isolation Phase B (,pI signal) and containment spray actuated but all Phase B status lights are not '0 PSO will actuate BOTH CBS/P/CVI manual actuation switches for each train. o PSO will manually report no CBS pumps running or available.

o PSO wiii check CBS pump suction alignment and report CBS-V-2 & 5 open and CBS-V-8 & 14 closed. o If not previously performed, PSO will stop all RCPs. Step 3: PSO will verify At Least One Containment Enclosure Cooling Fan, EAH-FN-5A or 5B running. Step 4: PSO will verify MSIV, MSIV Bypass Valves And MSIV Upstream Drains are Step 5: If not previously performed, BOP will isolate the faulted 'C' SG line and EFW TR-AA-230-1003-F06 Revision 0 Page 23 of 26

>Clera 2013 LOIT NRC SIM Exam 1 SEG ..'" F1.£E1 FR-Z.1, Step 6: Check Hydrogen Concentration Response to CUE: If US asks WCS to place hydrogen

BOP will report no hydrogen analyzers in service and will align at least High analyzer in service, respond: "I will have ONE hydrogen monitor and place in Analyze Mode per OS 1023.71, Containment the TSC place the hydrogen analyzer in Operation of the Hydrogen Analyzers.

Continue with Step 9. When Pressure service." hydrogen concentration available, Then do Step 6b. ( continued)

Step 9: Return To Procedure And Step In Effect

US will direst en!!y to E-2, Faulted Steam Generator Isolation, 1. TR-AA-230-1003-F06 Revision 0 Page 24 of 26

era 2013 LOll NRC SIM Exam 1 SEG all'1'*' E-2, Faulted Steam Generator Isolation E-2, Faulted Steam Generator Isolation US will direct crew to enter E-2, Faulted Steam Generator Isolation.

US, PSO or BOP will announce that Critical Safety Functions are in effect. If RCS temperature starts increasing, then the US may direct RCS temperature be stabilized by dumping steam per the E-2 OAS page Step 1: Check main steamline isolation and bypass valves of all SGs closed Step 2: Check If SG Pressure Boundary Is Intact:

PSO will check pressure in all SGs and report any stable or Step 3: Identify Faulted

BOP will check pressures in all SGs and report 'C' SG decreasing in an uncontrolled Step 4: Check Faulted SG(s)

BOP BOP will check the faulted 'C' SG: feed line, EFW floW, ASDV, Main Steam Drain and blowdown are all isolated.

Step 5: Check CST Level greater than 250,000 gallons I = BOP will check CST level. Step 6: Check Secondary Radiation:

BOP will check main steamline, condenser air evacuation and generator blowdown radiation all

BOP will check no uncontrolled SG narrow range level Step 6: Check If ECCS Flow Should Be

PSO will check RCS subcooling

>40°F.

BOP will check secondary heat sink available.

PSO will check RCS pressure or stable or increasing.

PSO will check PZR level greater than 7% (28% for adverse containment)

US will entry to ES 1.1, SI TERMINATION, Step 1. TR-AA-230-1003-F06 Revision 0 Page 25 of 26

'---____l 2013 LOlr NRC SIM Exam 1 SEG ES 1.1. SI Termination Terminate the scenario when the crew starts to estabiish normal charging fiow in ES-1.1, or at the discretion of the lead examiner.

ES 1.1, SI Termination.

US will direct crew to enter ES 1.1, SI Termination.

US, PSO or BOP announce that Critical Safety Functions are in Step 1: Reset Step 2: Stop All But One CCP And Place In Step 3: Check RCS Pressure stable or increasing by pressure Step 4: Restore Normal Charging

PSO will open CS-V-142 and 143. Step 5: Establish Normal Charging Flow:

PSO will close SI-V-138 and 139.

PSO will establish 60 GPM charging flow using CS-FCV-121.

PSO will adjust seal injection flow for 6 GPM to 10 GPM using 182. Step 6: Control Charging Flow To Maintain PZR Level

PSO will reduce charging flow to the RCP seals only (apprOXimately 32 gpm). *** END OF SCENARIO TR-AA-230-1003-F06 Revision a Page 26 of 26 WORLD CLASS 2013 LOIT NRC SIM Exam 1 PERFORMANCE

....... expectit!

OPERATIONS DEPARTMENT Plant Status Plant is in Mode 1 At 55% Power. The Security Threat Level is Yellow Protected Train Current PRA Risk is Green Aggregate risk is 2 LOW B Reactivity RCS Boron concentration is 1314 ppm Performing A 30 Gal Dilution Every 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Rod control is in Auto With Control Bank "0" at 205 Steps Tave Band (Oeg. F) 573-573.3 Dilution Amount Required To Raise Tave By 1 Oeg. F (Gal): '191 Boration Amount Required To Lower Tave By 1 Oeg. F (Gal): :35 SG Blowdown Lineup: H otwe lis At 60 GPM/SG Cation Run (Minutes):Mids -6 Days -6 Cation Flowrate:

Full Flow 8FP: Time To 200F is 31 Hours and Risk is Turbine Controls:

Make adjustments as required to maintain 8 Hour thermal power between MW and 3647.9 MW. The 1 Hour thermal power average will be maintained below 3648 Control Rods will be manipulated per Reactor Engineering recommendations and will normally left in automatic control. Utilize 081000.10 Fig. 11, Rod Motiion 001 56 Values for NEPEX Contingency Amount Of Boration Needed To reduce Output to 1200 Mwe Net (C6123) Is 100 Amount Of Boration Needed To reduce Output to 800 Mwe Net (C6123) Is 776

Activities that may affect reactivity.

Today 0:00 *TURNOVER

'3y: eelOh Increase power to 75% at 5%/hour. Maintain AFD on target. Dilute as required to establish and maintain a power increase to 75% at 5%/hour. CB D at 205 ste s with rods in Auto. General Plant Status General Plant Info Non Watchstation Specific)

Today 0:00 *TURNOVER By: CB8-P-9-A was tagged out 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago for maintenance. T8 3.6.2.1 was entered 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. TS 3.6.2.1 requires CBS pump restoration within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Evolutions List non-tagging evolutions and surveillances in progress or planned Today 0:00 *TURNOVER INFORMATION*

By: eelOhll 1. Procedure 081000.05 , Power Increase, is being performed and is completed to step 4.2.39. Both Main feed Pumps and one Heater Drain pump in service. Second heater drain um start is be in briefe<:!..!!y OCC and will be started prior at 75%. Work Control RSS Today 0:00 *TURNOVER Primary NSO Name: =FBRSSMED Today 0:00 *TURNOVER INFORMATION*

By: ( Secondary NSO FB RSS MED Today 0:00 *TURNOVER I Rover NSO FB RSS MED Today 0:00 *TURNOVER I Waste NSO FBRSSMED Today 0:00 *TURNOVER I Field Support NSO FB RSS MED Today 0:00 *TURNOVER I Fire Brigade Leader Name: Today 0:00 *TURNOVER I Unit Name =*TURNOVER INFORMATION* Name: Today *TURNOVER INFORMATION*

By:

SIMULATOR EXERCISE GUIDE SITE: Seabrook Revision #: FINAL LMS ID: LMS Rev. Date: SEG TITLE: 2013 LOIT NRC SIM Exam 2 SEG TYPE: D Training !8J Evaluation PROGRAM: D LOCT !8J LOIT Other: DURATION:

90 minutes Developed by: I nstructorlDeveloper Date Reviewed by: , -Instructor (Instructional Review) Date Validated by: SME (Technical Review) Date Approved by: Training Supervision Date Approved by: Training Program Owner (Line) Date TR-AA-230-1003-F06 Revision 0 Page 1 of 22 2013 LOIT NRC SIM I-v","ft'1I UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval.

Or use separate Update Log form TR-AA-230-1003-F16.

DATE# DESCRIPTION OF CHANGE REASON FOR CHAN.GE A DATE

1 TR-AA-230-1003-F06 Revision 0 Page 2 of 22

2013 LOIT NRC SIM Ex:am 2 OVERVIEW I SEQUENCE OF EVENTS OVERVIEW The crew will take the watch at MOL 75% power with stable Xenon, Boron Concentration at 1206 ppm, CB D at 207 steps and both Heater Drain pumps in service. The crew will begin a power increase at 10%/hr to 90% power. MS-PT-505 fails high causing outward rod motion. After recovery from the instrument failure, SW-P-41-A will trip and lockout The standby pump SW-P-41-C fails to auto start and cannot be manually started requiring manual TA. SW-V-20 will fail to auto actuate but can be manually aligned. 'A' RGP vibration will ramp up, requiring a reactor trip. When 'A' RCP is secured after the E-O immediate actions a 300 gpm RCP seal leak (Simulated with int leg leak) will occur simultaneously with a loss of offsite power. 'N EDG will fail to auto start and the operator will be required to emergency start 'A' EDG using the slave relay in ECA-O.O. SW-V-16 will fail to automatically open the BOP will be required to open manually to establish cooling to operating

'A' DG. 'B' EDG will trip due to lube oil failure. 11-A will fail to auto start. RMO must be reset and either A Train CC pump may be started manually.

SEQUENCE OF EVENTS Event' I Description

1. Crew begins a 1 O%/hr power increase.

'I 2.

MS-PT-505 fails high causing outward rod motion. 3. SW-P-41-A trip and lockout, standby pump SW-P-41-G fails to auto start and cannot be manually started requiring manual TA. SW-V-20 fails t<:::> auto actuate but can be manually aligned. 4. 'N RCP vibration ramps up, requiring a reactor trip. 5. When 'A' RCP is secured after immediate actions, trigger starts 300 gpm RCP seal leak (simulated with int leg leak). Also triggers a loss of offsite power. '8' EDG trips due to lube oil failure. 6. 'A' EDG fails to auto start, Operator emergency starts using the slave relay in EGA-O.O. SW-V-16 fails to automatically open and may be opem3d manually.

7. GC-P-11-A fails to auto start. RMO must be reset and either 'A' Train CC pump may be I started manually. ) TR-AA-230-1003-F06 Revision 0 Page 3 of 22 i

___________

____________S_I_M_E_Xam_2 SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the Simulator Setup Checklist.

General Instructions

a. Provide extra copies of procedures to Examiners

b. Resetto IC #151 c. Place simulator in Run d. Verify the following have been inserted OR reset to IC #32 and insert the following:

1. A Train is Protected, SV C0755, '1' 2. Defeat the 'A' EDG auto start:

SELECT: MF List

SELECT: Electrical Distribution

SELECT: mfED031}

SELECT: INSERT 3. Defeat the 'A' EDG emergency start:

SELECT: Panel Overview

SELECT: Panel GF

SELECT: A DG Emergency Start Pushbutton

SELECT: Release

SELECT: INSERT 4. 'B' EDG Trip:

SELECT: MF List

SELECT: Electrical Distribution

SELECT: mfED034

SELECT: INSERT 5. Block SW-P-41-C from Auto start:

SELECT: MF List

SELECT: Service Water

SELECT: mfSW014 )

SELECT: INSERT 6. Defeat SW-V-16 Auto Open:

SELECT: Scenario

SELECT: Sim_Support

SELECT: Defeat Auto Open SW-V-16

SELECT: RUN TR-AA-230-1003-F06 Revision 0 Page 4 of 22 2013 LOIT NRC 81M Exam SEG Block CS-P-2-B from starting on LOP:

SELECT: MF List

SELECT: Chemical and Volume Control

SELECT: mfCS002

SELECT: INSERT Block CC-P-11-A from Auto start:

SELECT: MF List ')

SELECT: Primary Component Cooling

SELECT: mfCC012

SELECT: INSERT Defeat the auto actuation of SW-V-20:

SELECT: Scenario

OPEN: SW folder

SELECT: SW-V-20 auto failure

SELECT: Run

SELECT: OK 10. Block SW-P-41-C from manual start:

SELECT: Panel Overview

SELECT: GF

SELECT: Insert OR

SELECT: SW-P-41-C switch

SELECT: Set Final Value to PTL

SELECT: INSERT ')Insert Event Trigger

SELECT: Event Triggers

OPEN: Sim Support

SELECT: RCP TRIP

SELECT: Activate Advance logger and tear off any sheets with print. Procedure OS1000.05, Power Increase is being performed and is completed to step 4.2.49. Provide appropriate shift turnover documentation.

TR-AA-230-1003-F06 Revision Page 5 of 22 2013 LOIT NRF 81M E)(am 2 SEG SHIFT TURNOVER INFORMATION

See Turnover Sheet TR-AA-230-1003-F06 Revision 0 Page 6 of 22 2013 LOIT NRC SIM Exam 2 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1 PSO (R), BOP (N), US (N) Start Allow the students to increase plant power I Crew Begins the Power increase lAW MPE Procedure OS1000.05, Power to the extent that a significant reactivity manipulation is demonstrated.

.) .) Increase.

The crew should prepare for and initiate a power increase at 10%/hr. Unit Supervisor:

A brief reactivity review will take place discussing the temperature limits for Tavg to be used in the power increase.

The temperature band will normally be + 1.5°F with rods in Auto or + 3°F with rods in manual. Dilution will be used for temperature control during the power increase.

Control rods will be used for AFD and temperature control. Turbine Operations:

The BOP will increase turbine load using automatic DEHC operations.

Using the laminated

sheets, 19 of OS 1 000.1 0, The basic steps are:

Check the Load Set is in Hold mode.

Insert the desired loading Rate.

Insert the desired Power Level.

When ReS temperature begins to increase, Select "load."

Monitor turbine loading using "Load Status" is Loading and "Load Actual" increases.

The BOP should verify the change with control valve position change, temperature change and power change.

At any time during the automatic loading, the power increase can stopped by activating the "Hold" TR-AA-230-1003-F06 Revision 0 Page 7 of 22 2013 LOIT NRC SIM Exam 2-'..

.*." FrnT'---____-L-____________________

1__..................SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR EXPECTED STUDENT RESPONSE Power Reactor Power change: The crew will use dilution to increase temperature during the turbine load increase.

A dilution value will be determined to change the boron concentration and increase power/temperature.

If control rods are used in manual to control AFD I temperature, the operator will verify rod speed, place the Rod Motion Selector (In-Hold-Out) switch to the OUT direction and withdraw the rods a maximum of three steps. The PSO will monitor temperature and power as confirmation of actions. Using the laminated sheets of OS1008.01 , Figure 2, Dilution Check List, the PSO will set up the controllers for the required dilution volume and rate. The high level steps are:

Verify the pumps are in AUTO

Verify the makeueJ'alves are in AUTO ..>

Place Blender Mode Start Switch to STOP

Place the Mode Selector Switch to DILUTE or ALT DILUTE

Set the quantity and flow rate on CIS-FIQ-111 controller During validation the crew used a dilution value of 1600 gallons in approximately 400 gallon batches every 15 minutes.

If not desired, select OFF for the "Stepback Feature"

Set the Mode Start Switch to START

Verify the pumps and valves respond

Verify Plant Response.

Restore System to Automatic control TR-AA-230-1003-F06 Revision Page 8 of 22 rers' ENE£l9ya,.

2013 LOIT NRC SIM Exam 2 SEG HUClf.AR FlEET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES Event 2 During Power Increase with Rods in Auto or At Lead Examiner's Discretion J INSTRUCTOR ACTIVITY MS-PT-505 fails high:

SELECT: MF List

SELECT: Feedwater (Component)

SELECT: ptFWPT505

SELECT: FAIL HIGH

SELECT: INSERT J TR-AA-230-1003-F06 Revision 0 EXPECTED STUDENT RESPONSE PSO (I), BOP (I), US (I, MS-PT-505, Turbine Impulse Pressure, fails high causing outward Initial D4421 TAVG-TREF B7457 ROD MOTION US will direct BOP to check generator electrical load stable. BOP will identify that generator electrical load is stable. US will direct PSO to place rods in manual. PSO will place rod control in manual and auto rod motion will stop. PSO or BOP will identify that MS-PT -505 has failed high. I.J US enters OS1235.05, Turbine Impulse Pressure PT 505 or PT 506 Instrument Failure and directs the following actions: I Step 1: Check PT-505 FAILED:

BOP wiii report MS-PT-505 iaiied high.

PSO will report rods in manual.

PSO or BOP will report Tavg at program temperature.

If not at program temperature, US may direct rod Step 2: Check Condenser Steam

BOP will report steam dump valves are closed.

BOP will transfer steam dumps to the steam pressure mode: o BOP will verify steam dump controller MS-PK-507 in manual/minimum.

o BOP will place steam dump control mode selector to steam pressure mode. o BOP will adjust steam dump controller setpoint to 1092 psig. o BOP will place MS-PK-507 in AUTO. Page 9 of 22 2013 LOIT NRC SIM Exam 2 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES MS-PT -505 fails high (continued)

INSTRUCTOR ACTIVITY If the crew calls the WCSIWWM for the MS-PT -505, then respond "Understand that MS-PT -505 has failed high. A troubleshooting team is being formed." If the crew calls the WCSIWWM for I&C, then respond "I&C is on their way to the control room." .:J If needed at OS1235.05, step 5:

SELECT: Panel Overview

SELECT: AMSAC CP-S19 I * . TS IMP (P505) I EXPECTED STUDENT RESPONSE OS1235.05 , Turbine Impulse Pressure PT 505 or PT 506 Instrument Failure. (continued)

Step 2: Check Condenser Steam Dumps: (continued)

BOP will verify both steam dump interlock selector switches positioned NA RESET NA BYPASS Step 3: Verify Proper P-13 Status By Status light TURBINE PWR BELOW P-13 UL-6 N-5:

BOP will report that with turbine power above 10%, the status light is deenerg ized. Step 4: Verify Technical Specification Compliance:

T.S. 3.3.1 Reactor Trip System Instrumentation; Table 3.3 1, Item 18.f Action 8. Requirerttents of this action are met when step 3 is completed . .:J Step 5: US will direct BOP to verify A TWS Mitigation Input Status:

US will direct I&C to place failed channel in 1-MM-CP-519, ATWS mitigation system cabinet to -OPERATE BYPASS I

BOP wiii verify proper status light indication for C-20 ATWS SYS ARMED at UL-28 B-1. With turbine power above 20%, the light is TR-AA-230-1003-F06 Revision 0 Page 10 of 22

---),lera" NUClEAR FLEET TIME/NOTES Event 3 After 505 failure or at Lead Examiner's Discretion f 2013 LOIT NRC SIM Exam 2 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS I'Nrong with SW-P-41A." When the crew dispatches an NSO to essential switchgear, respond "This is the secondary NSO. I am on my way to essential switchgear verify relay actuation for SW-P-41 A." After 5 minutes, respond, "This is secondary NSO, SW-P-41A has an INSTRUCTOR ACTIVITY SW-P-41-A trip and lockout:

SELECT: MF List

SELECT: Service Water

SELECT: mfSW001

SELECT: INSERT It the crew dispatches an NSO to the Service Water Pump House, respond "This is the roving NSO. I am on my way to the Service Water Pump House to check on SW-P-41A." '".J After 5 minutes, respond "This is the roving NSO. I see don't see anything EXPECTED STUDENT RESPONSE BOP (C), US (C, SW-P-41-A trip and lockout and SW-P-41-C fails to Initial 05523 SW PMP A BKR TRIP F7192 SWTA TRAIN A FAIL TO NOTE: US may use 'Skill of the Operator' to attempt to start the back-up pump OR take initial actions using 05523 alarm response or Degraded Ultimate Heat Sink. All are acceptable.

US may place the power increase on PSO will review 05523, SW PMP A BKR TRIf5-f./O and under the direction will complete the following Step 1: BOP will verify SW Pump A tripped by amber light indication on i Step 2: BOP will verify started/start SW Pump C. Step 3: If SW Pump C is not available, BOP will initiate Train A actuation from Step 4: BOP will verify SW Pump A discharge valve SW-V-2 Step 5: BOP will place the control switch for SW-P-41A in pull to Step 6: US will refer to and enter OS1216.01, Degraded Ultimate Heat Step 7: BOP will dispatch an operator to verify relay actuation for SW-P-41 BKR at Bus 5 Step 8: US will refer to technical specifications for the service water T.S. 3.7.4a action a will be entered. TR-AA-230-1003-F06 Revision 0 Page 11 of 22 I

2013 LOIT NRC SIM Exam 2 SEG ruET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES SW-P-41-A trip and lockout and SW-P-41-C fails to auto start. (continued)

INSTRUCTOR ACTIVITY It the crew dispatches an NSO to perform a cooling tower fill, respond "This is the roving NSO. Commence a cooling tower fill from potable water." After 5 minutes, respond, "This is the roving NSO, I started a coaling tower fill from potable water at 50 gpm." .) IF NEEDED for Cooling Tower fill:

SELECT: RF List

SELECT: Service \Nater

SELECT: rfSW001 PVV or FP

SELECT: Set FINAL VALUE to 50

SELECT: INSERT EXPECTED STUDENT RESPONSE US enters OS1216.01, Degraded Ultimate Heat Sink and directs following Step 1: Determine Appropriate

If entered upon initial failure, then go to Step 2.

If entered after processing 05523 alarm response and affected SW aligned to the cooling tower, then go to Step

If entered after processing D5523 alarm response and Tower actuation is in progress, then got to Step 4. Step 2: Check For Ocean System Failure:

BOP will check one ocean service water pump running per train associated discharge valve

With no Train ocean SW pump running the BOP will perform the I.,.;) following:

o Manually start SW Pump C. o SW Pump C can not be started and BOP will actuate Train A tower actuation.

o Go to Step 4. Step 4: Verify Tower Actuation Sequence:

BOP will verify proper TA alignment by UL-16 status panel indication.

o BOP will identify that SW-V-20 failed to auto close and will close the valve if not previously performed.

BOP will check cooling tower boundary intact by verifying SW-V-4, 20 and 74 are closed and cooling tower basin level is stable or increasing.

Step 5: Determine Step Transition:

With one cooling tower pump in service, US will go to Step 7. TR-AA-230-1 003-F06 Revision 0 Page 12 of 22

2013 LOIT NRC SIM Exam SEG. flHT SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT SW-P-41-A trip OS1216.01 , Degraded Ultimate Heat Sink and lockout Step 7: Align equipment with one cooling tower pump ,in SW-P-41-C

BOP will place both Train A ocean SW pump control switches in PTL. to auto start.

BOP will place running Train A CT pump control switch in NA START.(continued)

BOP will reset Train A tower actuation.

BOP will operate cooling tower spray and fans per Attachment A. Step 8: Check For Cooling Tower Failure:

BOP will report Cooling tower pump discharge pressure >40 psig.

BOP will check cooling tower boundary intact: o BOP will check SW-V-4, 20 and 74 are closed, identify that SW-V-20 failed to auto close and will close the valve if not previously performed.

J J

BOP will check cooling tower basin level itfstable or increasing.

BOP will verify Cooling tower basin level >43.5 feet.

BOP will operate cooling tower spray and fans per Attachment A, as necessary.

Step 9: Determine S'v"V Systern status: T.S. 3.7.4a action a will be entered.

I TR-AA-230-1003-F06 Revision Page 13 of 22

2013 LOIT NRC SIM Exam 2 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY Event 'A' RCP vibration ramps After Step 7 8 of

SELECT: MF OS1216.01 , SELECT: Reactor Coolant *at Lead SELECT: mfRC020 Examiner's

Discretion

SELECT: Set Ramp Time to 600 seconds and Final Value to 21

SELECT: INSERT NOTE: alarm comes approximately minutes failure I _J EXPECTED STUDENT RESPONSE PSO (C), US 'A' RCP vibration ramps up, which will require a manual reactor Initial 88300 RCP A MTR FRAME VI8 VERT ROC 88301 RCP A MTR FRAME VI8 HORIZ ROC 88308 RCP A SHAFT VI8 VERT ROC 88309 RCP A SHAFT VI8 HORIZ ROC US enters OS1201.01, RCP Malfunction and directs the following Step 1: Determine Appropriate Procedure Step

With vibration level US will go to Step 2. w Step 2: Monitor RCP Vibration less than alert and danger limit

Determine If RCP vibration indication is valid using applicable indication as o 80P will perform Attachment A to confirm RCP vibration rack module output is valid o PSO will use MPCS to obtain RCP vibration readings.

o PSO will check RCP seal leak off flows. o PSO will check RCP bearing temperatures.

US and PSO determine valid RCP vibration are greater than alert danger limits requiring a reactor

US directs manual reactor trip and states that 'A' RCP will be tripped immediate actions are

US will direct crew to enter E-O, Reactor Trip or Safety Injection perform their iml11§!diate TR-AA-230-1003-F06 Revision 0 Page 14 of 22 I I

2013 LOIT NRC SIM Exam 2 SEG /" NUCUAA FUfl SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Crew trips the E-O, Reactor Trip or Safety Injection Rx Step 1: Verify Reactor Trip:

PSO will check Rod bottom lights lit, reactor trip and bypass breakers open and neutron flux decreasing.

Step 2: Verify Turbine Trip:

BOP will check all stop valves or all control valves closed and the generator breaker open. Step 3: Verify Power To AC Emergency Busses:

BOP will check both AC emergency busses energized.

Step 4: Check If SI Is Actuated:

c-::J u

PSO will check and report no SI annuncil8tors lit.

Check if SI is required o PSO checks RCS pressure <1800 psig, o PSO checks pressurizer level <7%, o PSO checks containment pressure >4 pSig, o PSO checks RCS subcooling

<40°F, o BOP checks any SG pressure <585 pSig and o SI is not required.

Immediate actions are complete.

US will direct the PSO to stop the 'A' RCP.

TR-AA-230-1003-F06 Revision 0 Page 15 of 22 I

---i',!FXrera RUT 2013 LOIT NRC SIM Exam 2 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR EXPECTED STUDENT RESPONSE PSO (M), BOP (M), US (M) Simultaneous Events When 'A' RCP Loss of offsite power, Station Blackout and 300 gpm RCP seal is secured after Loss of offsite

SELECT: MF NOTE: Crew may reassess E-O, Reactor Trip or Safety Injection, step 3 for actions SELECT: Electrical Distribution LOP, then go to ECA-O.O, Loss of all AC Power, OR go directly to ECA-O.O,* Loss of all AC Power, step 1. Either transition path is correct.

SELECT: mfED038

SELECT: INSERT Step 3: Verify Power To AC Emergency Busses: 350 gpm RCP seal leak (simulated intermediate leg leak):

BOP will check at least one AC emergency bus SELECT: MF

BOP will attempt to emergency start both emergency EDGs. *

SELECT: Reactor o 'A' EDG will not start. o 'B' EDG witt:start and trip due to lube oil failure u* w SELECT: mfRC050A

US will direct crew to enter ECA-O.O, Loss of all AC Power and perform SELECT: Set Final Value to their immediate

SELECT: INSERT TR-AA-230-1003-F06 Revision Page 16 of 22

2013 LOIT NRC SIM Exam 2 SEG .-HIlCI£Al\.' Flffi .... SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES ECA-O.O, Loss of all AC Power Event 6 Critical Task INSTRUCTOR ACTIVITY 'J When BOP simulates actuating Slave relay K603 test switch S909 "Relay test switch has been actuated.

Indications are as seen on the MeB." Slave relay start of 'A' EDG:

SELECT: Scenario

SELECT: Sim_Support

SELECT: Start E DG Slave Relay

SELECT: Run EXPECTED STUDENT RESPONSE ECA-O.O, Loss of all AC Power Step 1: Verify Reactor Trip:

PSO will check reactor trip and bypass breakers open and neutron flux decreasing.

Step 2: Verify Turbine Trip:

BOP will check all stop valves or all control valves closed and the generator breaker open. Step 3: Check If RCS Is Isolated:

PSO will check PORVs, CS-V-145, Excess letdown isolation valves RCS sample valves closed. Step 4: BOP will verify EFW Flow >500 Step 5: Try To Restore Power to any AC Emergency

BOP will place Bus 5 & 6 UA T and RAT supply breaker control switches in PTL. BOP (C)

BOP will manually start emergency diesel generator(s) from the main control room: o Emergency start (will not work) o Slave relay K603 test switch S909

BOP will verify diesel generator is running with normal voltage

BOP will verify diesel generator breaker is closed and EPS is and

Check equipment loaded: TR-AA-230-1003-F06 Revision 0 Page 17 of 22 rera*

2013 LOIT NRC SIM Exam 2 SEG J"#'",'" NUClfAR FLEET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES ECA-O.O, Loss of all AC Power ( continued)

Event 6 Critical Task E-O, Reactor Trip or Safety Injection, Step 4 INSTRUCTOR ACTIVITY If the crew dispatches an NSO to DG room to investigate, respond "This is the roving NSO. I am in the 'B' DG room and there is a large amount of oil on the floor." If the crew directs NSO to Place 'B' DG in MAINTENANCE, respond "Place 'B' DG in MAINTENANCE."

the 'B' DG in MAINTENANCE:

SELECT: Local Panels

SELECT: DG System

SELECT: DG B @ SELECT: SS-9710 Maintenance EXPECTED STUDENT RESPONSE ECA-O.O, Loss of all AC Power, Step 5 (continued)

Check equipment loaded: o PSO reports 'A' Charging Pump running. o PSO reports 'A' Thermal Barrier Pump running. PSO (C) o PSO will identify CC-P-11-A failure to auto start.

BOP will reset RMO (after EPS sequencing is complete).

PSO will start CC-P-11-A or C. o BOP reports 'A' EFW pump running. BOP (C) J J o BOP reports 'A' Cooling Tower Pump running

BOP may identify that SW-V-16 is closed, but should be open.

US directs BOP using 'Skill ofthe Operator' to open SW-V-16.

BOP opens SW-V-16.

BOP reports Bus 5 is energized.

BOP reports only one AC emergency bus is energized.

BOP reports Bus 5 is energized from its Emergency Diesel.

US directs return to E-O, Reactor Trip or Safety Injection, Step 4. Step 4: Check If SI Is Actuated:

PSO will check and both SI annunciators lit. US will direct PSO and BOP to bring up their alarms and notify him of any immediate plant concerns and share any pertinent plant information.

Step 5: Perform ESF actuation verification per Attachment A:

PSO will perform Attachment A. TR-AA-230-1003-F06 Revision 0 Page 18 of 22 era' ENERj,ix.a 2013 LOIT NRC SIM Exam 2 SEG HIJClEAft Ft.m SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS I TIME/NOTES INSTRUCTOR EXPECTED STUDENT RESPONSE E-O, Reactor PSO performing Attachment A while US and BOP process E-O. Trip or Safety 1. PSO will verify Containment Isolation Phase A Actuation by I'njection checking all status panel lights lit for both trains. (continued) PSO will verify Safeguard Equipment Alignment by checking proper alignment by status panel for both trains. PSO will verify Feedwater Isolation by checking proper alignment by status Event PSO Critical NOTE: US may direct PSO to start CC-P-11-A or C after Step 4 of E-O using Skill of the Operator. PSO will verify a PCCW Pump running in both loops.

PSO will identify CC-P-U-A failure to auto start. u

PSO will reset RMO.

PSO will start CC-P-11-A or C. PSO will verify ECCS Flow by checking: CCP indicated flow to RCS cold legs. RCS pressure <1700 psig, SI pump flow to both trains. RCS pressure >300 psig, go to Step 6. PSO will verify MS-V-129 is open. PSO will verify a SW Pump running in both trains. PSO will verify SW flow to Train A and Train B Diesels >900 gpm. PSO will check all main steamlines isolated with containment pressure >4 psig. 10. PSO will check Containment Pressure has remained <18 psig 11. PSO will verify total EFW flow >500 gpm. 12. PSO will reset RMO if not previously done. 13. PSO will notify US of Actuation Verification Status. Attachment A is complete.

TR-AA-230-1003-F06 Revision 0 Page 19 of 22

2013 LOIT NRC SIM Exam 2 FLEET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES E-O, Reactor Trip or Safety Injection (continued)

INSTRUCTOR ACTIVITY When the BOP dispatches an NSO to open FW-V-347, B EFW pump miniflow, respond "'This is the roving NSO. Open FW-V-347, B EFW pump miniflow." After 2 minutes open FW-V-347:

SELECT: SIM diagrams

SELECT: FW3

SELECT: FW-V-347

SELECT: Manual Adjust

SET: Final Value = 1 P

SET: Ramp =30

SELECT: Insert After FW-V-347 is open, respond, "This is I -nr-.r'l. '11 h k CS " 145 b th POR"----' t.._.o.h I PZR -. -the roving NSO FW-V-347 is open." 1

cur WI C ec -v-,0 eUiU UUl norma 1 , valves closed. Step 8: Check If RCPs Should Be Stopped:

BOP will check at least one running ECCS pump and report RCS subcooling greater than 40°F. Step 9: Check If SG Pressure Boundary Is Faulted:

BOP will check pressures in all SGs and report pressures as expected.

Step 10: Check If SG U Tubes Are Intact:

BOP will check pressures and levels in all SGs and report pressures and levels as expected.

Step 11: Check If RCS Is Intact:

BOP will report abnormal containment radiation and pressure.

US will direct entry to E-1, Loss of Reactor or Secondary Coolant. EXPECTED STUDENT RESPONSE Step 6: Monitor RCS Temperature stable at or trending to 557°F.

BOP will report less than 55rF and decreasing.

US will direct the following actions: o Stop dumping steam to condenser and atmosphere.

o Check MS to MSRs isolated.

NOTE: The following 2 steps may have been performed per the E-O OAS page. o If cooldown continues, then open EFW pump mini flow valves and throttle total feed flow to maintain greater than 500 GPM. o When SG level is adequate based on 15% NR in at least one SG (Adverse Containment), then throttle feed flow to maintain SG narrow range level between 15% and 50% (Adverse Containment).

o If cooldown continues, then close MSIVs, MSIV bypass and upstream drains. Step 7: Check RCS Isolated:

TR-AA-230-1003-F06 Revision 0 Page 20 of22 era**

2013 LOIT NRC SIM Exam 2 SEG SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY E-1, Loss of Reactor or Secondary Coolant ;) D E-1, Loss of Reactor or Secondary Coolant ( continued)

TR-AA-230-1003-F06 Revision 0 EXPECTED STUDENT RESPONSE E-1, Loss of Reactor or Secondary Coolant US will direct crew to enter E-1, Loss of Reactor or Secondary Coolant and direct the following actions. US, PSO or BOP will announce that Critical Safety Functions are in effect. Step 1: Check If RCPs Should Be Stopped:

PSO will check one charging pump running.

PSO will check RCS subcooling

>40°F. Step 2: Check If SG Pressure Boundary Is Faulted:

BOP will check pressures in all SGs and report pressures as expected.

Step 3: Check Intact SG Levels:

BOP will verify 15% NR in at SG (Adverse Containment).

BOP will open EFW pump mini flow valves AND control feed flow to maintain NR level between 15% and 50% (adverse containment).

Step 4: Check Secondary Radiation:

BOP wi!! check main steam!ine, condenser air evacuation and generator blowdown radiation all

BOP will check no uncontrolled SG narrow range level increase.

Step 5: Check PZR PORV And Block Valves:

BOP will verify block valves have power and are open and both PORVs are closed. Step 6: Check If ECCS Flow Should Be Reduced:

PSO will check RCS subcooling greater than 40°F.

BOP will check secondary heat sink available.

PSO will check RCS pressure or stable or increasing.

PSO will check PZR level greater than 28% (adverse containment)

US will entry to ES 1.1, SI TERMINATION, Step 1. Page 21 of 22

2013 LOIT NRC SIM Exam 2 SEG FLEU SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT Terminate the scenario after the check If ECCS flow should be reduced step 6 Of E-1, or at the discretion of '--lead examiner.

- - END OF SCENARIO *** Q Q Q Revision 0 Page 22 of 22 WORLD CLASS 2013 LOIT NRC SIM Exam 2 PERFORMANCE

....... expectit!

OPERATIONS DEPARTMENT TURNOVER Plant Status -Plant is in Mode 1 At 75% Power. Current PRA Risk is Green Protected Train Aggregate risk is 0 LOW The Security Threat Level is Yellow Reactivity RCS Boron concentration is 1206 ppm Performing A 30 Gal Dilution Every 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Rod control is in Auto With Control Bank "0" at 207 Steps RCS Tave Band (Oeg. F) 581-581.3 Dilution Amount Required To Raise Tave By 1 Oeg. F (Gal): 191 Boration Amount Required To Lower Tave By 1 Oeg. F (Gal): 35 SG Blowdown Lineup: Hotwells At 60 GPM/SG Cation Run (Minutes):Mids -6 Days -6 Cation Flowrate:

Full Flow SFP: Time To 200F is 31 Hours and Risk is Low Turbine Controls:

Make adjustments as required to maintain 8 Hour thermal power between 3646.0 MW and 3647.9 MW. The 1 Hour thermal power average will be maintained below 3648 MW. Control Rods will be manipulated per Reactor Engineering re!commendations and will normally be left in automatic control. Utilize OS1 000.1 0 Fig. 11, Rod Motion Checklist.

00156 Values for NEPEX Contingency Oownpower

-Amount Of Boration Needed To reduce Output to 1200 Mwe Net (C6123) Is 100 Gal. Amount Of Boration Needed To reduce Output to 800 Mwe Net (C6123) Is 776 Gal. -

I Reactivity Activities that may affect reactivity.

Today 0:00 *TURNOVER INFORMATION*

'3y: eelOh 11 1. Increase power to 90% at 10%/hour.

2. Maintain AFD on target. 3. Dilute as required to establish and maintain a power increase to 90% at 10%/hour.

4. CB D at 207 ste s with rods in Auto. General Plant Status General Plant Info Non Watchstation Specific)

Today 0:00 *TURNOVER INFORMATION*

By: eelOh11 1. Power increase in ro ess. Evolutions List non-ta in evolutions and surv!!!lances in progress or planned Today 0:00 *TURNOVER INFORMATION*

By: eelOhll 1. Procedure OSI000.05 , Power Increase, is being performed and is completed to step 4.2.49. 2. Both Heater Drain urn s are in service. Work Control Name: RSS Today 0:00 *TURNOVER INFORMATION'" By: I Primary NSO Name: FB RSS MED Today 0:00 *TURNOVER INFORMATION*

By: I Secondary NSO Name: FB RSS MED Today 0:00 "'TURNOVER INFORMATION*

By:

NSO Name: FB RSS MED Today 0:00 "'TURNOVER INFORMATION*

By: I Waste NSO Name: FB RSS MED Today 0:00 "'TURNOVER INFORMATION'" By: I Field Support NSO Name: FB RSS MED Today 0:00 *TURNOVER INFORMATION*

By: I Fire Brigade Leader Name: Today 0:00 *TURNOVER INFORMATION'" By: I Unit Supervisor Name Today 0:00 *TURNOVER INFORMATION'" By: I Shift Manager Name: Today 0:00 *TURNOVER INFORMATION'" By:

SIMULATOR EXERCISE GUIDE REEl SITE: Seabrook Revision #: FINAL LMS 10: LMS Rev. Date: SEG TITLE: 2013 LOIT NRC SIM Exam 4 SEG TYPE: o Training [gj Evaluation o PROGRAM: 0 LOCT [gj LOIT 0 Other: DURATION:

90 minutes Developed by: I nstructor/Developer Date Reviewed by: Instructor (Instructional Review) Date Validated by: , SME (Technical Review) Date 0 Approved by: Training Supervision Date Approved by: Training Program Owner Date TR-AA-230-1003-F06 Revision 0 Page 1 of 28 I ",:F.xrera' 2013 LOIT NRC 81M Exam 4 SEG fLeET UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval.

Or use separate Log form PREPARER DATE# DESCRIPTION OF CHANGE REASON FOR CHANGE: ARlTWR# REVIEWER DATE I o TR-AA-230-1003-F06 Revision 0 Page 2 of28

.

2013 LOIT NRC SIM Exam 4 SEGf!.ffi OVERVIEW I SEQUENCE OF EVENTS OVERVIEW The crew will take the watch at MOL 100% power with, Rods in Auto, boron concentration at 1100 ppm, CB D at 230 steps. The crew will begin a power decrease at 10%/hr to 50% power due to FW-P-32-A vibration issues. CC-P-322-A trips and standby pump fails to auto start, but can be started manually.

The crew will then experienCE!

a loss of EDE-PP-1A due to EDE-I-1A failure. Instrument Bus 1A can be recovered on its maintenance supply. This event will require manual control of FRV's and charging.

AR-P-50-B will then trip with auto start of third AR pump blocked, but it' can be manually started. FW-P-32-A trips and power level is too high for Setback to be successful.

Auto and Manual Rx trips are blockecl, n3sulting in A TWS. Auto rod insertion is blocked and manual rod insertion will be required.

On the manual turbine trip, turbine Stop Valve 2 and Control Valve 2 will stick open, manual MSI. SEQUENCE OF EVENTS Event # Description

1. Crew begins a 1 O%/hr power decrease due to FW-P<-I2-A vibration issues. I 2. CC-P-322-A trips and standby pump fails to auto start, can be started manually.

3. Loss of EDE-PP-1A due to EDE-I-1A failure. Instrument Bus 1A recovered on maintenance

supply. Requires manual control of FRV's and charging.

4. On loss of EDE-PP-1A, PC-PT-455 will fail low. This will be discovered when Instrument Bus 1A is recovered on its maintenance supply. I 5. AR-P-50-B trips, auto start of third but can be manually started. Vacuum will i continue to decrease requiring downpo r to maintain 25 inches of Hg.i I . 6. FW-P-32-A trips. Power level too high for Setback to be successful.

Auto and Manual Rx . trips blocked resulting in A TWS. 7. Auto rod insertion blocked, manual rod insertion required.

I 8. On manual turbine trip, turbine Stop Valve 2 and Control Valve 2 stick open, requiring manual MSI. I 9. When crew enters ES-0.1 the A PORV will fail open. This will require the PSO to close the I I A PORV. It will not close and the PSO will close the A PORV Block Valve. TR-AA-230-1003-F06 Revision 0 Page 3 of28 2013 LOIT NRC SIM Exam 4 SEG , SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the Simulator Setlff> Checklist.

General Instructions

a. Provide extra copies of procedures to Examiners

b. Reset to IC #153 c. Place simulator in Run d. Verify the following have been inserted OR reset to IC #30 and insert the following:

1. A Train is Protected, SV C0755, '1' 2. Block MS-SV-2 Main Stop Valve closure:

SELECT: MF List

SELECT: Main Steam (Component)

SELECT: avMSVSV2

SELECT: FAIL OPEN

SELECT: INSERT 3. Block MS-CV-2 Main Turbine Control Valve clm;ure:

SELECT: MF List

SELECT: Main Steam (Component)

SELECT: avMSVCV2 n

SELECT: FAIL OPEN

SELECT: INSERT 4. Block standby Air Removal pump start:

SELECT: MF List

SELECT: Condenser Air Evacuation

SELECT: mfAR006C

SELECT: INSERT e. Advance logger and tear off any sheets with print. f. Procedure OS1 000.056, Power Decrease is being performed and is completed to step 4.3. Provide appropriate shift turnover documentation. TR-AA-230-1003-F06 Revision 0 Page 4 of28 I . ENE:!j1iUi 2013 LOIT NRC SIM Exam 4 SEG SHIFT TURNOVER INFORMATION

See Turnover Sheet n o TR-AA-230-1003-F06 Revision 0 Page 5 of 28

---I 2013 LOIT NRC SIM Exam 4 SEGSIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1 PSO (R), BOP (N), US (N) AII9w the students to decrease plant Start Crew begins the power decrease lAW MPE Procedure OS1000.06, Power power to the extent that a significant reactivity manipulation is The crew should prepare for and initiate a power decrease at 10%/hr. Unit Supervisor:

A brief reactivity review will take place discussing the temperature limits for Tavg to be used in the power increase.

The temperature band will normally be + 1.5°F. Soration will be used for temperature control during the power decrease.

Control rods will be used for AFD and temperature control. Turbine Operations:

The SOP will decrease turbine load using automatic c:::> DEttC operations.

Using the laminated sheets, Figure 19 WOS1 000.1 0, The basic steps are:

Check the Load Set is in Hold mode.

Insert the desired Ramp Rate. I

Insert the desired Power LeveL

V'v'hen RCS tern perature begins to decrease, Seiect "Load."

Monitor turbine unloading using "Load Status" is Unloading and "Load Actual" decreases.

The SOP should verify the change with control valve position change, temperature change and power change.

At any time during the automatic unloading, the power decrease can be stopped by activating the "Hold" function.

TR-AA-230-1003-F06 Revision 0 Page 6 of 28 2013 LOIT NRC SIM Exam 4 SEG I..

Nuct£AJl , FIHl SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Reactor Power change: The crew will use boration to decrease temperature during the turbine load decrease.

A boration value will be . determined to change the boron concentration and decrease power/temperature.

If control rods are used in manual to control AFD / temperature, the operator will verify rod speed, place the Rod Motion Selector (In-Hold-Out) switch to the IN direction and insert the rods. The PSO will monitor temperature and power as confirmation of actions. Using the laminated sheets of OS1008.01, Figure 3, Boration Checklist, the PSO will set up the controllers for the required boration volume and rate. The high level steps are:

Verify the pumps are in AUTO

Verify the makeup valves ar;;;in AUTO t:::) t:::)

Place Blender Mode Start Switch to STOP

Place the Mode Selector Switch to BORATE

Set the quantity and flow rate on CIS-FIQ-111 controller I Note: During validation the crew used a boration value of 300 gallons in approximately 75 gallon batches every 15 minutes.

If not desired, select OFF for the "Stepback Feature"

Set the Mode Start Switch to START

Verify the pumps and valves respond

Verify Plant Response

Restore Svstem to Automatic control TR-M-230-1003-F06 Revision 0 Page 7 of 28 rera*

2013 LOIT NRC SIM Exam SEG .,,,,,,<,,,,,,,,,,,*, ** SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES Event 2 At Lead Examiner's Discretion Q INSTRUCTOR ACTIVITY trips: SELECT: Scenario OPEN: CC folder SELECT: TB loss with failure of 322B to start SELECT: Run SELECT: OK EXPECTED STUDENT RESPONSE PSO(C), US (C) CC-P-322-A,.

'A' Thermal Barrier Pump trips and CC-P-322-B, 'B' Thermal Barrier Pump fails to auto start. Initial Alarms: B5208 THERM BARR PMP NB OUTLET FLOW LOW 85219 THERM BARR PMP NB OUTLET FLOW LOW F8017 RCP A THERM BARRIER COOLING FLOW LOW F8018 RCP B THERM BARRIER COOLING FLOW LOW F8019 RCP C THERM BARRIER COOLING FLOW LOW F8020 RCP D THERM BARRIER COOLING FLOW LOW Q PSO identifies that CC-P-322-A, 'A' Thermal Barrier Pump trips and 322-B, 'B' Thermal Barrier Pump failed to auto start. NOTE: US may decide to take initial actions using "Skill of the Operator" or any of the above iisted aiarm responses or go directly to OS1212.01, PCCW Malfunction or OS1201.01, RCP Malfunction.

Any method is acceptable.

US may place the plant down power on hold. If the US chooses to use "Skill of the Operator":

US will direct the PSO to start CC-P-322-B using "Skill of the Operator".

PSO will start CC-P-322-B.

PSO will verify alarms clear and report the conditions to the US. TR-AA-230-1003-F06 Revision Page 8 of 28

---rera 2013 LOIT NRC SIM Exam 4 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CC-P-322-A, 'A' PSO may review 85208 or B5219, THERM BARR PMP AlB OUTLET Thermal Barrier LOW. If the US chooses to use B5208 or B5219 alarm response, then he Pump trip . direct the PSO to complete the following PSO will read NOTE prior to Step 1 This alarm is generated from the transmitter supplying point A0283. standby pump auto start is supplied independently from the bistable at 120 Step 1: Verify Thermal Barrier Pump AlB outlet flow low conditions using

A0283, CC-P-322A

&B OUTLET FLOW

A0284, CC-P-322A

&B OUTLET FLOW D Step 2: Check one thermal ba=itier coolant pump running. D

US may direct PSO to start CC-P-322-B using "Skill of the Operator".

Step 3: If continued low flow conditions exist, go to OS1212.01, PCCW System Ma!function.

TR-AA-230-1003-F06 Revision 0 Page 9 of 28

2013 LOIT NRC SIM Exam 4 SEG J" SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT I *CC-P-322-A, 'A' PSO may review F8017 (F8018, F8019 or F8020), RCP A (B, C or D) Thermal Barrier THERM BARRIER COOLING FLOW LOW. If the US chooses to use F8017 .Pump trip (F8018, F8019 or F8020) alarm response, then he will direct the PSO (continued) complete the following PSO will read NOTE prior to Step 1 CC-P-322A, Thermal Barrier Coolant Pump A is the preferred pump and normally be in service. CC-P-322B, Thermal Barrier Coolant Pump B normally be kept in auto as the standby Step 1: Verify CC-P-322A or B, thermal barrier coolant pump in service OS1012.08 , Thermal Barrier Cooling Water System

-PSO verifies no thermal barrier pumps

(;:) -eelS may direct PSO to start CC-P-322-B using "Skill ofcthe Operator".

PSO will read NOTE prior to Step 2: RCP thermal barrier outlet isolation valves are normally open and deenergized to avoid redundant high flow closure on a single loop failure. I I Step 2: Verify Thermal Barrier Pump Outlet Flow Normal (180 to 220 gpm) using the following:

-A0283, CC-P-322A

&B OUTLET FLOW -A0284, CC-P-322A

&B OUTLET FLOW Step 3: Refer to the following procedures as applicable:

OS1201.01 , RCP Malfunction

-OS1212.()j!PCCW TR-AA-230-1003-F06 Revision 0 Page 10 of28

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2013 LOIT NRC SIM Exam 4 SEG/#-.Y;>0#

__ _ >M"J* SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY CC-P-322-A, 'A' Thermal Barrier Pump trip (continued)

Q EXPECTED STUDENT RESPONSE If the US chooses to go directly to OS1212.01, PCCW Malfunction, he direct the following US will read CAUTION prior to Step The reactor and affected RCPs must be tripped within 10 minutes of all PCCW flow to affected Step 1: Determine Appropriate Procedure

IF PCCW system FLOW is degraded, THEN go to step 2. Step 2: Check PCCW Flow

PSO will check PCCW pumps, one pump running per loop.

PSO will check PCCW system flow >6000 gpm.

PSO will check RCP motof::tlow alarms reset. Q

PSO will check RCP motor temperatures are normal: o Motor bearing temperatures

<195°F. o Motor stator winding temperature

<302°F.

PSO wi!! check at least one thermal barrier cooling pump running: o PSO will manually start pump. o PSO will verify alarms clear and report the conditions to the US. NOTE: The remaining steps check on PCCW system status. The US will process the AOP to Step 8 where he will return to procedure and step in effect. TR-AA-230-1003-F06 Revision 0 Page 11 of 28

[ ,',FXlera ENEBQya 2013 LOIT NRC SIM Exam 4 SEG SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT CC-P-322-A, 'A' If the US chooses to go directly to OS1201.01, RCP Malfunction, he will Thermal Barrier direct the following actions: . . .Pump trip ( continued)

Step 1: Determine Appropriate Procedure Step Transition:

IF RCP seal package cooling is degraded, THEN go to Step 14. Step 14: Monitor Rep Seal And Bearing Cooling Inlet Temperature:

PSO will check Rep seal and bearing inlet temperature indication is available to each Rep.

PSO will monitor RCP seal water inlet temperature

<230°F

PSO will monitor Rep seal water inlet temperature

<184°F Step 15: Monitor for minimum RCP seal cooling system requirements:

D (II) PSO will check Rep No.1 Seal injection flow >6 gpm:to each RCP. US will read CAUTION prior to Step 16 to A loss of seal injection event may cause Rep seal and bearing to reach 230°F within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Thermal barrier cooling may not adequate cooling to RCP seals with leakoff rates less than 2.5 I I Step 16: Check Seal Water Cooling System Status:

PSO will check RCP No.1 Seal injection flow >6 gpm to each RCP.

PSO will check Rep seal water injection temperature

<135°F

PSO will check at least one thermal barrier cooling pump running: o PSO will manually start pump. o PSO will verify alarms clear and report the conditions to the US.

PSO will check RCP thermal barrier supply temperature

<105°F

PSO will check thermal barrier head tank level between 30 and 45 inches. Step 17: Go to Step 19. Step 19: Verify Tech Spec compliance.

Step 20: Verifies normal RCP parameters.

END AOP TR-AA-230-1003-F06 Revision 0 Page 12 of 28 NUCUAA FLEET TIME/NOTES Event 3 After start of CC-P-322-B or at Lead Examiner's Discretion Event 4 Prior to energizing EDE-PP-1A on its maintenance supply 2013 LOIT NRC SIM Exam SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTOR ACTIVITY EXPECTED STUDENT PSO (C), BOP (C), US (C, TS) Loss of Loss of vital instrument panel PP-1A 9ue to UPS-I-1A failure.

SELECT: MF List Initial Alarms:

SELECT: Electrical Distribution Many alarms associated with the loss of ED-PP-1-A.

SELECT: mfED025

SELECT: INSERT Due to FW-PT-505 failing low from the loss of power, rods in auto will start inserting.

The US will direct BOP to check generator electrical load stable. RC-PT-455 Failed BOP will identify that generator electrical load is stable. US will direct PSO to place rods in manual. PSO will place rod control in manual and auto rod

SELECT: MF List motion will stop.

SELECT: Reactor Coolant (component)

Due to SG Water Level cOnHPlling channel failing from the loss of power, SG c:::>* SELECT:'PtRCPT 455 NR levels will increase from program level. The US will direct the BOP to SELECT: FAIL LOW manually control feed regulating valves to restore SG level to program. to 55%) and to manually control main feed pump master speed controller SELECT: restore programmed DP, as TR-AA-230-1003-F06 Revision Page 13 of 28

2013 LOIT NRC SIM Exam SEG TIME/NOTES Loss of PP-1A ( continued)

(::) SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When the crew dispatches an NSO to 'A' With the plant stabilized the US enters OS 1247.01, Loss of a 120 VAC Vital essential switchgear to check the status of PP-1A and UPS-I-1A, respond "This is the secondary NSO, I am on my way to 'A' essential switchgear to check the status of PP-1A and UPS-I-1A." After 5 minutes, respond "Control, this is the secondary NSO, UPS-I-1A appears dead." When the crew directs the NSO to repower PP-1A from its maintenance Instrument Panel (PP1A, 1 B, 1 C OR 1 D) and directs the following actions: . US will read NOTE prior to Step 1 to BOP: 120 VAC Instrument bus can be energized at any time per Attachment D. US will give BOP Attachment D and direct him to repower PP-1A. NO!E: P.P-1A may be fro:n its maintenance supply at any time dunng this procedure.

Repowenng Will cause a spurious containment evacuation alarm. Step 1: Check Rod Control System: supply using Attachment D, respond "This c; BOP will check generator electrical load stable. (::) is the secondary NSO, repower PP-1 A from its maintenance supply using Attachment D." Ensure MF for RC-PT -455 inserted.

To place ED-PP-1A on its Maintenance supply:

SELECT: RF List

SELECT: Electrical Distribution

SELECT: rfED021

SELECT: INSERT After repowering PP-1A, respond "Control, this is the secondary NSO, PP-1A is on its Maintenance supply."

PSO will place the Rod Bank Selector Switch in Manual. Step 2: Check Steam Generator Water Level Control:

BOP will check controlling channel is failed.

BOP will manually control feed regulating valves to restore SG level

BOP will manually control main feed pump speed controller to programmed DP, as

BOP will restore steam generator water level control to automatic A IT ACHMENT A, as time NOTE: When PP-1A is repowered from its maintenance supply the crew discover RC-PT -455 failed low. The US may decide to enter OS1201.06, PZR Pressure Instrument I Component Failure at this time or complete the current AOP. The steps for RC-PT-455 failure follow the PP-1A failure in the Expected Student Response section. TR-AA-230-1003-F06 Revision Page 14 of 28

.*.

2013 LOIT NRC SIM Exam SEG ..,-'

-. fUU SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY Loss of (

c Loss of PP-1A (continued)

TR-AA-230-1003-F06 Revision 0 EXPECTED STUDENT RESPONSE BOP performing Attachment A to align SG level control to automatic as follows, while US and PSO continue in OS1247.01, Loss of a 120 VAC Vital Instrument Panel (PP1A, 1 B, 1 C OR 1 D). BOP will manually restore SG level to program level using: Feed regulating valve control OR Main feed water speed control, if necessary

2. BOP will select alternate control channel as necessary: SG level Steam flow Feed flow 3. WHEN SG level returns to program, THEN perform the following: Return feedq:egulating valve control to automatic. Return main feed pump speed control to automatic, as necessary.

Attachment A is Step 3: Check Rod Control

BOP will check Steam Dump o Condenser steam dump valves closed. o Reset C-7A steam dump arming signal, as necessary.

Step 4: Check Pressurizer Pressure Control:

PSO will check controlling channel is failed.

PSO will manually control the Master pressurizer pressure controller Heaters and spray valves to restore pressurizer pressure to

PSO will check pressurizer pressure is stable or trending to program.

PSO will restore pressurizer pressure control to automatic ATTACHMENT B, as time Page 15 of 28 c 2013 LOIT NRC SIM Exam 4 TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Loss of PP-1A PSO performing Attachment B to align pressurizer pressure control to ( continued) automatic as follows, while US and BOP continue in OS1247.01, Loss of a 120 VAC Vital Instrument Panel (PP1A, 1B, 1C OR 10).

PSO will manually restore pressurizer pressure to program using:

Master pressurizer pressure controller OR Heaters and spray valves PSO will select alternate pressure channel for control/backup as necessary. PSO will select an alternate pressure channel for recorder as necessary. PSO will select an alternate AT, OT, OP channel for recorder as necessary. c: WHEN pressurizer pressure returns to program, THEN perform the following: Place PZR master pressure controller in automatic Place PZR spray controllers in automatic If required, reset pressurizer controi group heaters. Attachment B is complete.

Loss of PP-1A Step 5: Check Pressurizer Level Control: (continued)

PSO will check controlling/backup/programmed level channel is failed.

PSO will manually control the Master level controller OR CS-FK-121 controller to restore pressurizer level to program.

PSO will select an alternate level channel for control and backup.

PSO will restore pressurizer level control to automatic per An ACHMENT C, as time permits. TR-AA-230-1003-F06 Revision Page 16 of 28 2013 LOIT NRC SIM Exam SEG NUCWR FlEET SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY Loss of PP-1A (continued) . C) I EXPECTED STUDENT RESPONSE PSO performing Attachment C to align pressurizer level control to automatic as follows, while US and BOP continue in OS1247.01, Loss of a 120 VAC Vital Instrument Panel (PP1A, 1 B, 1 C OR 1 D) . PSO will manually restore pressurizer level to program using: Master level controller OR CS-FK-121 controller PSO will select alternate level channel for control and backup. PSO will select an alternate level channel for recorder PSO will verify control rods are in manual PSO will depress affected loop Tavg channel defeat pushbutton WHEN level returns to program, THEN perform the 1;3 following: Adjust RC-LK-459 as needed to match the input and setpoint signals on CS-FK-121 Piace CS-FK-121 in AUTO Adjust RC-LK-459 input to match program level setpoint Place RC-LK-459 in AUTO 7. If required, reset pressurizer control group heaters. Attachment C is complete.

TR-AA-230-1003-F06 Revision Page 17 of28 I

2013 LOIT NRC SIM Exam SEG .p"".......""' FU£T SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Loss of PP-1A Step 6: Check If E Plan Classification is required: ( continued)

PSO.will report PP-1 C is energized and the US will go to

7. Step 7: Check If Letdown Was Isolated:

PSO will report that RC-LCV-459 is closed. Step 8: Check If Normal Letdown Can Be Established:

Verify charging flow >50 gpm: o PSO will report charging to the RCP seals only. o PSO will increase charging flow to >50 gpm. PSO will report pressurizer level >17% and increaSing. PSO will establish normal letdown as follows:

PSO will open/check open CC-V-341 and check CS-TK-130 in AUTO to C;:) c:t align PCCW to the letdown heat exchanger.

C;:) PSO will close letdown flow control valves CS-HCV-189 and 190.

PSO will open/check open letdown line isolation valves RC-LCV-459 and 460 and CS-V-145 . PSO will manually control CS-PK-131 AND estabiish ietdown fiow using letdown flow control valve CS-HCV-189 or 190.

US will go to Step 10. Step 10: Defeat Affected Loop ilT and Tavg inputs: PSO will depress affected loop il T channel defeat pushbutton. PSO will verify control rods are in manual. PSO will depress affected loop Tavg channel defeat pushbutton. PSO will select a non affected channel for il T, OT, OP recorder.

TR-AA-230-1003-F06 Revision Page 18 of 28

I lera" 2013 LOIT NRC SIM Exam 4 SEG /"' SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT Loss of Step 11: Restore 120 VAC Instrument . NOTE: Power may already be ret?tored .

BOP will report that he is working with an NSO in the field to place PP-1A on its maintenance supply per Attachment D OR

BOP will report that PP-1A is energized on its maintenance supply per Attachment D. Step 12: Restore Normal System Alignment:

PSO will reset affected power range NI rate trip.

PSO will restore any defeated loop Tavg, t\T channels.

PSO will restore pressurizer pressure control channels for preferred alignment, as necessary.

0

PSO will verify 1°F OF Tref.

Under specific US direction, PSO will restore control rods to desired position, as necessary.

PSO will place rod control to AUTO.

PSO will reset SSPS power supply per ATTACHMENT E as follows: oAt MM-CP-12, Train A Logic Cabinet, on PS 501, PSO will Press the Reset Push Button oAt MM-CP-12, Train A Logic Cabinet, PSO will verify PS 501 "OK" LED is illuminated

US will restore other systems to automatic control using applicable attachments as necessary.

Step 13: Verify Technical Specification Compliance:

T.S 3.8.3.1, Onsite Power Distribution Operating TR-AA-230-1003-F06 Revision 0 Page 19 of 28 I

2013 LOIT NRC SIM Exam 4 FI,HT SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RC-PT-455 PSO (I), US (I, TS) Failure Low . RC-P.T-455, controlling pressurizer pressure instrument fails.low . Initial Alarms: (alarms stay energized after powering PP-1A on its maintenance supply) F5298 OTDT CHAN TRIP F7434 PZR PRESSURE LOW CHANNEL LOW (RX) F7435 PZR PRESSURE LOW CHANNEL TRIP (SI) UL 1-F10 PZR PRESS LO SI UL6-A3 RCS LOOP OT T UL6-A5 PRESSURIZER PRESS LO c:::> c:::> c:::> US enters OS1201.06, PZR Pressure Instrument I Component Failure and directs the following actions: I US will read NOTE prior to Step 1 to PSO: A reactor trip may occur on OT T setpoint if RCS pressure significantly decreases below normal operating pressure.

Step 1: Check PORVs closed: The crew calls the WCSIWWM for the

PSO will report both PORVs closed. PT-455, respond "Understand that RC-Step 2: Check Normal PZR Spray Valves closed: PT -455 has failed low. A troubleshooting team is being formed."

PSO will report both Normal PZR Spray valves are closed or redponding correctly. TR-AA-230-1003-F06 Revision 0 Page 20 of 28

2013 lOIT NRC SIM Exam SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE RC-PT-455 US will read NOTE prior to Step 3 to PSO: Failure Low Channel P-455/P-456 is selected for pressure control because a .(continued) failed LOW -RC-PT -458 (selected for backup) or RC-PT-457 (selected for control), will prevent automatic operation of both pressurizer PORVs. Step 3: Check PZR Pressure Channels:

Controlling/Backup/Recorder channel failed:

PSO reports no Controlling/Backup/Recorder channel failed, but that PT -455 has failed low. US will read CAUTION prior to Step 4 to PSO: Channel Selection of alternate pressurizer pressure control channel OR recorder channel uses a "make before break" circuit that can result in control system transient if a significant deviation exists between the channels.

Q Step 4: Realign Pressurizer Pressure Instruments:

PSO reports that 457/456 or 458/456 for is selected for control/backup.

PSO reports that 456. 457 or 458 is selected for the pressure channel recorder.I

PSO reports that an alternate 8 T. OT, OP channel is selected for the recorder.

Step 5: Align Pressurizer Pressure control:

PSO reports that RCS pressure is trending to 2235 psig and the master pressure controller, RC-PK-455A is in auto. Step 6: Verify redundant channels bistables not tripped:

PSO will report redundant channels bistables not tripped on UL-1 and 6 bistables.

TR-AA-230-1003-F06 Revision Page 21 of28 rera*

2013 LOIT NRC SIM Exam 4 SEG c-SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RC-PT-455 Step 7: Verify Technical Specification Failure

3.3.1, Reactor Trip System Instrumentation; Table 1, Items 7,9 (continued)" and 10. Enter action 6 .

T.S. 3.3.2, Engineered Safety Features Actuation System Instrumentation; Table 3.3-3, Items 1.d. Enter action 18. US will coordinate with I&C to place bistables to bypass for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . c;:::) c;:::) c;:::) TR-AA-230-1003-F06 Revision 0 Page 22 of 28

1-2013 LOIT NRC SIM Exam 4 SEG J SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY Event 5 Simultaneous At Lead Examiner's AR-P-50-B trips: Discretion SELECT: MF List SELECT: Condenser Air Evacuation SELECT: mfAR005B

SELECT: INSERT Vacuum Leak: SELECT: SIM Diagrams SELECT: C01 SEE:eCT: mfC0026 SELECT: Set Final Value to 0.035 (adjust as necessary) SELECT: INSERT When the crew dispatches an NSO to P-50-B, respond "This is the secondary NSO, I am on my way to AR-P-50-B." After 2 minutes, respond "Control, this is the secondary NSO, AR-P-50-B is not running and the suction valve is open." When the crew directs the NSO to shut AR-P-50-B suction valve, respond "Close AR-P-50-B suction valve." TR-AA-230-1003-F06 Revision 0 EXPECTED STUDENT RESPONSE BOP (C), US AR-P-50-B trips and loss of cOl1denser Initial F5118 MECH VAC PMP B BOP identifies that AR-P-50-B tripped. BOP will review F5118 VAS. VAS directs the crew to start the standby mechanical vacuum pump A OR US will direct the BOP to start the standby mechanical vacuum pump A C. Vacuum will continue to decrease.

US enters ON1233.01, Loss of Condenser Vacuum and directs the following actions: c::;) c: Step 1: Check Mechanical Vacuum Pump Status:

BOP will report all available vacuum pumps are running.

BOP will report vacuum seal water pump running lights are on. Step 2: Check Condenser Vacuum -DECREASING

BOP will report condenser vacuum is decreasing.

Step 3: Decrease Plant Power To Restore Vacuum:

BOP will report generator output is >360 MWe.

BOP will reduce generator load until EITHER of the following conditions is met: o Load decrease to 360 MWe OR o Condenser vacuum can be maintained

>25 inches of Hg vacuum.

BOP will check steam generator tubes are intact.

BOP will shift mechanical vacuum pump discharge to atmosphere, Page 23 of 28

---era J AC ,' NUCLEAR* FlEET TIME/NOTES After vacuum restored insert these malfunctions as set up for the major event in the next step. D 2013 LOIT NRC SIM Exam SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Block Auto Rod insertion(with rods in auto): SELECT: Scenario OPEN: CP folder SELECT: Auto Rod Failure SELECT: Run SELECT: OK Block Auto Rod insertion(with rods in manual): SELECT: Panel overview SELECT: Section DF SELECT: Insert override D D SELECT: Rod Bank SELECT: Final Value Manual

SELECT: !NSERT Block Reactor Trip: SELECT: Scenario OPEN: CP folder SELECT: Trip Breakers fail to open SELECT: Run SELECT: OK TR-M-230-1003-F06 Revision Page 24 of28

2013 LOll NRC SIM Exam 4 SEG /ff'P*' NIIJCtfAR c" flEeT --------------------SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES Event 6 Once the crew starts to decrease plant power to restore vacuum or at Lead Examiner's Discretion Critical Task Critical Task INSTRUCTOR ACTIVITY FW-P-32-A trips: *

SELECT: MF List

SELECT: Feed Water

SELECT: mfFW038

SELECT: INSERT o I EXPECTED STUDENT RESPONSE PSO (M), BOP(M), US (M) FR-S.1, Response to Nuclear Power FW-P-32-A Initial D4716 MFP A TURBINE BEARING OIL D4718 MFP A PUMP BEARING OIL PRESS D4720 MFP A TURBINE D4854 MFP A ELECTRICAL D6045 TURB SETBACK LOSS OF ONE FW

BOP will report FW-P-32-A trip and a setback is in progress.

0* BOP will report alFSG levels are rapidly decreasing and approaching the reactor trip setpoint.

US will direct the PSO to manually trip the reactor. -* The reactor will not trip M.6,NUALL Y or AUTOMATICALLY when the auto 1 trip signa! from SG Leve! La-La actuates.

The US will declare that he is entering FR-S.1, Response to Nuclear Power Generation/A TWS, and direct the crew to perform their immediate actions. o Auto rod insertion is failed and the PSO will manually insert control rods. o BOP will manually trip the turbine. o Turbine Stop Valve 2 and Control Valve 2 will stick open. o BOP will manually actuate MSI. TR-AA-230-1003-F06 Revision 0 Page 25 of 28 lera' 2013 LOIT NRC SIM Exam 4 SEG SIMULATOR EXERCISE GUIDE SCENARIO TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT Response .Nuclear Pbwer Generationl (continued)

PSO Step 1: Verify Reactor Event 7

PSO will report Rod bottom lights not lit.

PSO will continue to manually insert control rods. BOP (C) EventS Step 2: Verify Turbine Trip:

BOP will report that Turbine Stop Valve 2 and Control Valve 2 are stuck 0 0 open. Locally trip the

BOP will report that he manually actuated MSI. SELECT: Scenario

BOP will report that the generator breaker is open. OPEN: CP folder I SELECT: 120 second delay then I NOTE: After the Immediate Actions are complete, the US or BOP win clear fault and trip reactor direct any available NSO to locally trip the reactor. SELECT: Run SELECT: OK Step 3: Check EFW Pumps Running:

BOP will report that the Motor driven pump is running. When the reactor is tripped, respond

BOP will report that the Turbine-driven pump is running. "Control, this is the secondary NSO, I Step 4: Initiate Emergency Boration Of RCS: locally tripped the reactor."

BOP will report that one charging pump is running. I-TR-AA-230-1003-F06 Revision Page 26 of 28

2013 LOIT NRC SIM Exam 4 ._,""""", SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS I TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE FR-S.1,

Align boration Response o BOP will start a boric aciq pump and open Nuclear

Align charging flow path:

ATWS o BOP will place CS-FK-121 in manual and charge at maximum (continued) o BOP will open CS-LCV-112D and E to align CCP suction to RWST. o BOP will close CS-LCV-112B and C to isolate the VCT. o BOP will report PZR pressure <2385 psig. Step 5: Verify Containment Ventilation Isolation:

PSO will report COP-V-1, 2, 3 &4 and CAP-V-1, 2, 3 &4, Containment purge isolation valves, are closed. US will read CAUTION prior to Step 6: c::> If an SI signal exists::br occurs, ATTACHMENT A of E-O, REACTOR TRIP c::> OR SAFETY INJECTION should be performed while continuing with this procedure.

Step 6: Check If The Following Trips Have Occurred: i

PSO will report the reactor is tripped. I

BOP will report the turbine is tripped. Step 7: Check If Reactor Is Subcritical:

PSO will report power range channels <5%.

PSO will report intermediate range flux rate is zero or negative.

PSO will report gammametrics intermediate range flux level <5%.

PSO will report gammametrics intermediate range flux rate is zero or negative.

US will direct PSO to continue boration to obtain adequate shutdown margin during subsequent actions. NOTE: US will exit FR-S.1 and direct the crew to go back to E-O and perform their immediate actions. TR-AA-230-1003-Jf06 Revision 0 Page 27 of 28 2013 LOIT NRC SIM Exam SEG Event PSO (C), US (C) When crew enters ES-O.1 fail open the A The PSO will report A PORV open with RCS pressure low. PORV as Follows: The US will direct PSO to close the A PORV per "Skill of the Operator". SELECT: MF List The PSO will attempt to close the A PORV. When the A PORV fails to close SELECT: Reactor Coolant the PSO will report, The A PORV failed to close." (Component)

The US will direct the PSO to close the A PORV Block valve per, "Skill of the SELECT: avRCPCV456A Operator." Critical Task SELECT: Fail open The PSO will close the A PORV Block Valve. SELECT: INSERT The PSO will report the A PORV Block valve is closed. Terminate the scenario when the crew finishes FR-S.1 and returns to E-O, or at the discretion of the lead examiner.

- - END OF SCENARIO *** TR-AA-230-1003-F06 Revision Page 28 of 28 WORLD CLASS 2013 LOIT NRC SIM I::xam 4 PERFORMANCE

....... expectit!

OPERATIONS DEPARTMENT TURNOVER Plant Status -Plant is in Mode 1 At 100% Power. The Security Threat Level is Yellow Protected Train Current PRA Risk is Green Aggregate risk is 6 LOW A Reactivity RCS Boron concentration is 1100 ppm Performing A 30 Gal Dilution Every 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Rod control is in Auto With Control Bank "0" at 230 Steps RCS Tave Band (Deg. F) 589-589.3 Dilution Amount Required To Raise Tave By 1 Deg. F (Gal): 191 Boration Amount Required To Lower Tave By 1 Deg. F (Gal): 35 SG Blowdown Lineup: Hotwells At 60 GPM/SG Cation Run (Minutes):Mids -6 Days -6 Cation Flowrate:

Full Flow SFP: Time To 200F is 31 Hours and Risk is Low Turbine Controls:

Make adjustments as required to maintain 8 Hour thermal power between 3646.0 MW and 3647.9 MW. The 1 Hour thermal power average will be maintained below 3648 MW. Control Rods will be manipulated per Reactor Engineering recommendations and will normally be left in automatic control. Utilize OS1 000.1 0 Fig. 11, Rod Motion Checklist.

001 56 Values for NEPEX Contingency Oownpower Amount Of Boration Needed To reduce Output to 1200 Mwe Net (C6123) Is 100 Gal. Amount Of Boration Needed To reduce Output to 800 Mwe Net (C6123) Is 776 Gal.

Reactivity Activities that may affect reactivity.

Today 0:00 '"TURNOVER INFORMATION*

By: eelOhll General Plant Status General Plant Info Today 0:00 *TURNOVER INFORMATION*

By: eelOhll 1. 2. 3. Evolutions Today 0:00 By: I Work Control Name: RSS Today 0:00 *TURNOVER INFORMATION*

By: I Primary NSO Name: FB RSS MED Today 0:00 *TURNOVER INFORMATION*

By: I Secondary NSO Name: FB RSS MED Today 0:00 *TURNOVER INFORMATION*

By: I Rover NSO Name: FB RSS MED Today 0:00 *TURNOVER INFORMATION*

By: I Waste NSO Name: FB RSS MED Today 0:00 *TURNOVER INFORMATION*

By: I Field Support NSO Name: FB RSS MED Today 0:00 '"TURNOVER INFORMATION*

By: I Fire Brigade Leader Name: Today 0:00 *TURNOVER INFORMATION"'

By: I Unit Supervisor Name Today 0:00 *TURNOVER INFORMATION*

By: I Shift Manager Name: Today 0:00 *TURNOVER INFORMATION*

By:

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