Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML103490648
Person / Time
Site:	Seabrook
Issue date:	11/12/2010
From:	Momm E; NextEra Energy Seabrook
To:	David Silk; Operations Branch I
	Hansell S
Shared Package
ML101870654	List: ML101940088; ML103190314; ML103490482; ML103490486; ML103490487; ML103490490; ML103490597; ML103490620; ML103490635; ML103490648;
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SEABROOK RO ADMIN JOB PERFORMANCE MEASURE* QPTR CALCULATION Rev. 1 Student Name:

- - - - - - - - - - - LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: - - - - - - - - - - - - - DATE:

APPROVED BY: DATE:

---~TRA--IN-IN-G-S~U~P~ER-V~IS-O-R---

JOB PERFORMANCE WORKSHEET 1.0 Task Number and

Description:

Position: RO 0150200501 Perform A Manual QPTR Calculation

2.0 Conditions

A Plant is now at 100% power after recovering from a dropped rod at EOL.

B. The main plant computer has been inoperable since yesterday (It was inoperable when the rod dropped).

C. The seven day QPTR surveillance is scheduled to be done this shift.

D. Incore/Excore calibration was performed yesterday (before the rod dropped).

3.0 Standards

Perform the manual QPTR surveillance per RX1703, QPTR Surveillance.

4.0 Student Materials:

Copy of the Directions Tear-Off Sheet Calculator RX1703, QPTR Surveillance, Rev. 7, Chg. 2.

5.0 Limitations on performance:

Simulate/Perform all steps.

6.0

References:

Procedures RX1703, QPTR Surveillance.

OS1000.05, Power Increase.

ON1251.01, Loss Of Plant Computer.

Page 2 of 11

JOB PERFORMANCE WORKSHEET

7.0 Setting

Classroom

1. Examiner must prepare a completed RX1703A in advance. It shall reflect the JPM values for NI cabinet detector currents and the RE-17 100% power, 0% AFD values.

2. Use values listed in RE-17.

8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

20 minutes 10.0 Directions to the Student(s):

Initial Conditions:

1. Plant is now at 100% power following the recovery of a dropped rod at EOL.

2. The main plant computer has been inoperable since yesterday.

3. The QPTR surveillance is scheduled to be done this shift.

4. Incore/Excore calibration was performed yesterday (before the rod dropped).

5. Detector current readings were taken by the Control Board Monitor at 0800.

TOP(A)DETEcTO_R_S____~----------~

N41 N42 I N43 r.D~et-e-ct-o-r~C~u-rr-e-n-t+-----~1~84--*----L---~~~

N41 Detector Current 177 micoam s Page 3 of 11

JOB PERFORMANCE WORKSHEET 11.0 Initiating Cue:

Perform the QPTR Surveillance per RX1703. The QPTR alarm surveillance work order has been generated.

All independent verifications of calculations will be performed after you are completed. Provide your results to me.

Page 4 of 11

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

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".

NOTE: For performance of JPM in classroom setting the student is provided with a copy of RX1703, Quadrant Power Tilt Ratio Surveillance. Student should refer to section 4.1 Surveillance With QPTR Alarm Inoperable.

2 P RECORD the Figure RE-17 Records today's date and the revision revision and the date and time number of the RE-17 curve used the operable power range currents were taken.

NOTE: Detector current data for upper & lower detectors are provided. Detector Current value units are microamps. Student should be able to determine that all Power Range Detectors are operable when given the detector current data.

3. P RECORD the current output Records detector outputs.

from the top (A) and bottom (8) detector of each channel on Form A, Quadrant Power Tilt Calculation Sheet Row 1.

N41 top (A) detector N42 top (A) detector N43 top (A) detector N44 top (A) detector N41 bottom (8) detector N42 bottom (8) detector N43 bottom (8) detector N44 bottom (8) detector Page 5 of 11

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT CUE: If the student asks for independent verification of the values recorded in Row 1 of Form A, cue, evaluator to student, " Form A Detector currents have been independently verified."

NOTE: The student is provided with a copy of RE-17.

4. P Using data from Technical Data Book Figure RE-17, RECORD the 100% power, 0%

AFD detector current, for the top (A) and bottom (B) detector of each channel on Form A, Quadrant Power Tilt Calculation Sheet Row 2.

a. From Technical Data Book fig RE-17, Records 100% power, 0% AFD values:

4 Top (A) Detectors

b. From Technical Data Book fig RE-17, Records 100% power, 0% AFD values:

4 Bottom (B) Detectors

5. P CALCULATE the normalized detector current by dividing each detector current by its 100% power, 0% AFD current.

RECORD the results on Form A, Quadrant Power Tilt Calculation Sheet Row 3.

Page 6 of 11

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

a. *Calculates and records Normalized Detector Currents:

4 Top (A) Detectors

b. *Calculates and records Normalized Detector Currents:

4 Bottom (B) Detectors

6. P CALCULATE the average normalized detector current for the top detectors and for the bottom detectors. RECORD the results on Form A, Quadrant Power Tilt Calculation Sheet Row 4.

a. *Calculates and records average normalized detector currents:

Top (A) Detectors -- --

b. *Calculates and records average normalized detector currents:

Bottom (B) Detectors --

Page 7 of 11

PERFORMANCECHECKUST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

7. P CALCULATE the Quadrant Power Tilt Ratio for each detector by dividing each normalized detector current by its associated average normalized detector current.

COMPLETE Form A, Quadrant Power Tilt Calculation Sheet.

a. *Calculates and records QPTR for each detector:

4 Top (A) Detectors

b. *Calculates and records QPTR for each detector:

4 Bottom (B) Detectors

8. P Indicate the maximum QPTR *Identifies (circles) the maximum power tilt by circling on Form A Row 5. ratio on Form A Row 5.

CUE: If the student asks for independent verification of the Form A calculations, cue, evaluator to student, "

Form A calculations have been independently verified."

Page 8 of 11

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

9. P Determine if LCO 3.2.4 is/is not met based on maximum QPTR.

a. Identify in step 6 of Form A that LCO 3.2.4 islis not met

b. In Row 6 Form A circle YES/NO NOTE: See answer key for the correct item to circle in row 6 on Form A CUE: "The JPM is complete."

10. Stop time_ _ _ _ __ Time to complete the task s 20 minutes.

Evaluator calculates the time to complete the task.

11. Obtain from student:

Tear Off Sheets and any other training materials used in the performance of the JPM Page 9 of 11

PERFORMANCE

SUMMARY

Provide comments on unsatisfactory performance of an element/step or for 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

TEAR-OFF SHEET FOR JPM 2009 RO-ADMIN#1 Initial Conditions:

1. Plant is now at 100% power following the recovery of a dropped rod at EOL.

2. The main plant computer has been inoperable since yesterday.

3. The QPTR surveillance is scheduled to be done this shift.

4. Incore/Excore calibration was performed yesterday (before the rod dropped).

5. Detector current readings were taken by the Control Board Monitor at 0800.

Initiating Cue:

Perform the QPTR Surveillance per RX1703. The QPTR alarm surveillance work order has been generated.

All independent verifications of calculations will be performed after you are done. Provide your results to me.

Page 11 of 11

RO ADMIN JOB PERFORMANCE MEASURE- CALCULATE BORON CHANGE Rev. 1 Student Name: _ _ _ _ _ _ _ _ _ _ _ LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: ._ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ __

APPROVED BY: _ _ _ _ _ _- - -__- - - DATE: _ _ _ __

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET

1. Task Number and Description Position RO SBK 0040100601 Petform Boron Concentration Change Calculation

2. Conditions:

A. Plant is in Mode 3.

B. The RCS is 500°F and 2235 psig.

C. Pressurizer level is 25%

D. The crew is making preparations to go critical per OS1000.07.

E. RCS born sample is 1500 ppm.

F. The ECP boron concentration is 1120 ppm.

G. The MPCS BoronlDilution program is not available.

H. The boron concentration change will take place at current RCS temperature.

3. Standards:

Calculate total volume required to lower RCS boron concentration (+/- 100 gals) per RS 1735, Reactivity Calculations.

4. Student Materials:

Calculator Copy of Tear Off Sheet.

Copy of RS1735, Reactivity Calculations Rev 4 Chg.B.

Copy of Primary TDB, Figure RE-14 BorationlDilution Tables Rev. 01-00-01 Copy of Primary TDB, Figure RE-15 BorationlDilution Temperature Correction, Rev. 01 00-00.

5. Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

6.

References:

Procedures:

OS1000.07, Approach To Criticality

RS1735, Reactivity Calculations

Primary TDB, Figure RE-14 Boration/Dilution Tables

Primary TDB, Figure RE-15 Boration/Dilution Temperature Correction Page 2 of 7

JOB PERFORMANCE WORKSHEET

7. Setting:

Simulator or Classroom.

8. Safety Considerations:

None.

9. Approximate Completion Time:

15 minutes

10. Directions To The Student:

A. You are the Primary Operator. You are going to perform a boron change calculation.

B. The following information is provided to you:

1. Plant is in Mode 3.

2. The RCS is 500°F and 2235 psig.

3. Pressurizer level is 25%.

4. The crew is making preparations to go critical per OS1000.07.

5. RCS born sample is 1500 ppm.

6. The ECP boron concentration is 1120 ppm.

7. The MPCS Boron/Dilution program is not available.

8. The boron concentration change will take place at current RCS temperature.

11. Initiating Cue:

US to Primary Operator, "Primary Operator, using RS1735, calculate the total volume of RMW required to lower RCS boron concentration from the present boron concentration to that required for the ECP."

Page 3 of 7

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

denotes a critical step

denotes a critical step SAT UNSAT NOTE: When the student demonstrates the ability to obtain controlled copies of RS1735, Reactivity Calculations, Primary TDB, Figure RE-14 BorationlDilution Tables, and Primary TDB, Figure RE-15 Boration/Dilution Temperature Correction provide the student with the required documents.

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."

2. P Obtain Form 0, Dilution worksheet for Obtains Form 0, Dilution worksheet manual calculation of dilution amount. for manual calculation of dilution amountfrom RS 1735, Reactivity Calculations.

NOTE: See key for values that student should enter on Form D.

3. P Enter expected T avg at the time when Enters expected T avg at the time when concentration change is to be made concentration change is to be made on Form 0 item 1. on Form 0 item 1.

4. P Enter the present and desired boron Enter the present and desired boron concentration on Form 0 item 2. concentration on Form 0 item 2.

NOTE: Item 3A requires a set of numbers (FROM, TO, and RMW). A value will be entered for each reading set of RE-14. For instance, changing from 1500~1400, 1400~1300, 1300~1200, and 1200~1120 would require four sets of numbers. See key for values that student should enter on Form 0 for item 3A.

RE-14 has dilution (RMW makeup) values in the upper right and boration values in the lower left (not used for this JPM) for each boron concentration change made of 100 ppm or less.

Page 4 of 7

PERFORMANCE CHECKLIST O=Oiscuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT NOTE: See key for values that student should enter on Form O.

5. P Using TBO Figure RE-14 obtain the Using TBO Figure RE-14 obtains the total required volume of Reactor total required volume of Reactor Makeup Water (RMW) and enter on Makeup Water (RMW) and enter on Form 0 item 3a. Form 0 item 3a.

6. P Temperature correction for dilutions. Temperature correction for dilutions.

Perform one of the following: Performs one of the following:

If T avg is greater than or equal to If T avg is greater than or equal to 55rF then enter 1.0 on Form 0 item 55rF then enters 1.0 on Form 0 item 3b. 3b.

OR OR If Tavg is less than 55rF then use If Tavg is less than 55rF then uses TOB Figure RE-15 to obtain the value TOB Figure RE-15 to obtain the value to enter on Form 0 item 3b. to enter on Form 0 item 3b.

NOTE: See key for values that student should enter on Form o.

7. P Calculate the corrected Total Volume *Calculate the corrected Total Volume of RMW required in units of gallons as of RMW required in units of gallons the product of items 3a and 3b and as the product of items 3a and 3b enters on Form 0 item 3c. and enters on Form 0 item 3c.

CUE: "The ..IPM is complete."

8. Stop time _ _ _ __ Time to complete task s; 15 minutes Evaluator calculates time to complete task

9. Obtain from student:

Tear Off sheets and any other training materials used in performance of this JPM.

Page 5 of 7

PERFORMANCE

SUMMARY

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.

Page 6 of 7

TEAR OFF SHEET Directions To The Student:

A. You are the Primary Operator. You are going to perform a boron change calculation.

B. The following information is provided to you:

1. Plant is in Mode 3.

2. The RCS is 500°F and 2235 psig.

3. Pressurizer level is 25%.

4. The crew is making preparations to go critical per OS1000.07.

5. ReS born sample is 1500 ppm.

6. The ECP boron concentration is 1120 ppm.

7. The MPCS Boron/Dilution program is not available.

8. The boron concentration change will take place at current RCS temperature.

Initiating Cue:

US to Primary Operator, "Primary Operator, using RS1735, calculate the total volume of RMW required to lower RCS boron concentration from the present boron concentration to that required for the ECP."

Page 7 of 7

Examiner Key

r Form D: Dilution Worksheet (Sheet 1 ofl)

1. RCS Temp. (TAvo) 500 OF

2. Desired Boron Change: From i 500 ppm To " 2. 0 ppm

3. Gallons Required 3a. Gallons ofRMW at 5570f RCS Temperature.

RMW From IS-OO ppm To 1400 ppm L./2QY gals.

From tLiOO ppm To

\'000 ppm LI b"!, gals.

From l300 ppm To \200 ppm Llqg~ gals.

From \200 ppm To l12.0 ppm 429 Li gals.

From ppm To ppm gals.

Total a l~lB3 gals.

NOTE IfRCS temperature is greater than or equal to 557 of, then parameter "b" = 1.0 3b. Temperature Correction for TAVG less than 557°F (f ~

TDB Figure RE-15 Correction Factor b = I.. Ob .

lRa~' CIS" Iv I.O"lJ 3c. Corrected Total Gallons Required (a~ls.)X(b 1.0' ) == '~2i-4 gallonsofRMW.

ll<a~ '90Q2 +0 ICfLiSb)

Calculated By:

Date:

Independently Verified By: Date:

RS1735 Rev. 04 Cbg. 08 Page 25 of26

RO ADMIN JOB PERFORMANCE MEASURE- SHUTDOWN MARGIN (MODE 1)

Rev. 1 Student Name: LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: -----------------------

DATE:

AP PROVED BY: ____--=--:::-::-:-.:--:-:-:-:-::--::-:-==-=-:::-:-:-::-::-=-:=-_____ DATE:

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET

1. Task Number and Description Position RO SBK 0010100401 Perform Shutdown Margin Calculation

2. Conditions:

1. The plant is in Mode 1, at 100% RTP.

2. Core age is 12000 MWD/MTU

3. RCS boron concentration is 1300 ppm.

4. During performance of OX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core.

5. Rod H-2 cannot be moved.

6. OS1210.05, Dropped Rod actions are being performed.

3. Standards:

Determine the shutdown margin within +/-0.035%ilKlK.

4. Student Materials:

Copy of Tear Off Sheet.

Copy of RX1707, Shutdown Margin Surveillance Rev 7 Chg.7.

Copy of Primary TDB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration Rev. 01-14-00.

Copy of Primary TDB, Figure RE-18 Shutdown Margin Values, Rev. 01-14-00.

Copy of Primary TDB, Figure RE-19 Control Bank Worth At RIL vs. Power Rev. 01-14 00.

Copy of Core Operating Limit Report SSTR Rev. 121.

Calculator.

5. Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

6.

References:

Procedures:

OS1210.05, Dropped Rod

RX 1707, Shutdown Margin Surveillance Page 2 of 8

JOB PERFORMANCE WORKSHEET Curves:

Primary TDB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration

Primary TDB, Figure RE-18 Shutdown Margin Values

Primary TDB, Figure RE-19 Control Bank Worth At RIL vs. Power Technical SpecificationslTRM:

3.1.3.1 Moveable Control assemblies Group Height

3.1.3.6 Control Rod Insertion Limits

3.1.1.1 Shutdown Margin >200°F

Core Operating Limit Report

7. Setting:

Classroom.

8. Safety Considerations:

None.

9. Approximate Completion Time:

15 minutes

10. Directions To The Student:

1. The plant is in Mode 1, at 100% RTP.

2. Core age is 12000 MWD/MTU

3. RCS boron concentration is 1300 ppm.

4. During performance of OX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core.

5. Rod H-2 cannot be moved.

6. OS1210.05, Dropped Rod actions are being performed.

11. Initiating Cue:

US to student (or student's name), "Perform a shutdown margin calculation per RX1707, Shutdown Margin Surveillance."

Page 3 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT NOTE: When the student demonstrates the ability to obtain controlled copies of RX1707, Shutdown Margin Surveillance, Primary TDB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration, Primary TDB, Figure RE-18 Shutdown Margin Values, Primary TDB, Figure RE-19 Control Bank Worth At RIL vs. Power, and Core Operating Limit Report, provide the student with the required documents when requested.

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."

2. P Refer to section 4.4 of RX1707 Refers to section 4.4 of RX1707 Shutdown Margin Surveillance to Shutdown Margin Surveillance to complete Form C Shutdown Margin complete Form C Shutdown Margin Determination Immovable, Determination Immovable, Untrippable, Or Dropped Rod(s) Part Untrippable, Or Dropped Rod(s) Part

1. 1.

NOTE: See key for all values that student should enter on Form D.

3. P Determine number of Determines number of immoveable,untrippable or dropped immoveable,untrippable or dropped rod(s) and enter on Form C block (a). rod(s) and enters on Form C block (a).

4. P Determine maximum worth of Determines maximum worth of individual immoveable,untrippable or individual immoveable,untrippable or dropped rod(s) using Primary TDB dropped rod(s) using Primary TDB figure RE-18 and enter on Form C figure RE-18 and enters on Form C block (b). block (b).

5. P Calculate total unavailable rod worth Calculates total unavailable rod worth by multiplying (a) by (b) and enter on by multiplying (a) by (b) and enters on Form C block (c). Form C block (c).

Page 4 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT CUE: If student requests boron concentration, reply, "RCS boron concentration is 1300 ppm."

6. P Determine total power defect for Determines total power defect for current relative power using Primary current relative power using Primary TDB figure RE-8 and enter on Form C TDB figure RE-8 and enters on Form block (d). C block (d).

7. P Determine worth of the control banks Determines worth of the control banks inserted to the rod insertion limit for inserted to the rod insertion limit for current relative power using Primary current relative power using Primary TDB figure RE-19 and enter on Form TDB figure RE-19 and enters on Form C block (e). C block (e).

8. P Determine total control and shutdown Determines total control and rod worth minus stuck rod and less shutdown rod worth minus stuck rod 10% uncertainty using Primary TDB and less 10% uncertainty using figure RE-18 and enter on Form C Primary TDB figure RE-18 and enters block (t). on Form C block (t).

9. P Calculate shutdown margin: Calculates shutdown margin:

[f - (c + d + e)] /1,000. [f - (c + d + e)] /1,000.

CUE: If student asks for independent verification, provide the following cue, "Form C Part 1 has been independently verifed. Please continue."

CUE: If student fails to report the shutdown margin adequacy determination, provide the cue, "Is shutdown margin adequate?"

10. P Notify SM/US if the shutdown margin Notifies SM/US if the shutdown is less than the limit specified in the margin is less than the limit specified Core Operating Limits Report. in the Core Operating Limits Report.

Page 5 of 8

PERFORMANCE CHECKLIST D;;:Discuss ELEMENT/STEP STANDARD EVALUATION P;;:Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT CUE: "The JPM is complete."

11. Stop time _ _ __ Time to complete task S 15 minutes Evaluator calculates time to complete task

12. Obtain from student:

Tear Off sheets and any other training materials used in performance of this JPM.

Page 6 of 8

PERFORMANCE

SUMMARY

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.

Page 7 of 8

TEAR OFF SHEET Directions To The Student:

1. The plant is in Mode 1, at 100% RTP.

2. Core age is 12000 MWD/MTU

3. RCS boron concentration is 1300 ppm.

4. During performance of OX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core.

5. Rod H-2 cannot be moved.

6. OS1210.05, Dropped Rod actions are being performed.

Initiating Cue:

US to student (or student's name), "Perform a shutdown margin calculation per RX1707, Shutdown Margin Surveillance."

Page 8 of 8

RO ADMIN JOB PERFORMANCE MEASURE- COP Exhaust RM Setpoints Rev. 1 Student Name: _ _ _ _ _ _ _ _ _ _ _ LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: - - - - - - - - - - - - - DATE:

APPROVED BY: DATE:

---=TR~A~IN~IN~G~S~U~P=ER~V~IS~O~R---

JOB PERFORMANCE WORKSHEET 1.0" Task Number and

Description:

Position: RO/SRO Task: 0290100401 Adjust Containment Pressure Using the COP System.

0290100401 Start-Up the COP System.

0710101302 Authorize Release of Gaseous Waste.

2.0 Conditions

A. Plant is in Mode 1.

B. The previous shift has made preparations to place COP in service per OS 1023.69 section 4.2.

3.0 Standards

Verify COP Exhaust Radiation Monitors' Alert and Alarm setpoints prior to gaseous effluent release per OS1023.69 section 4.2.

4.0 Student Materials:

Copy of the Tear-Off sheet.

Copy of CS0917.02C GEW Containment Purge Release Permit Copy of OS1023.69, Containment On-Line Purge System Operation 5.0 Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

6.0

References:

Procedures:

CS0917.02, Gaseous Effluent Releases, Rev. 10, Chg. 12.

OS1023.69, Containment On-Line Purge System Operation, Rev. 11.

CP-4.1 Effluent Surveillance Program

MA-4.6, ROMS Data Base Item Control Sys KA Description Value RO/SRO Generic A2.3.11 Ability to Control Radiation Releases 2.7/3.2

7.0 Setting

Classroom 8.0 Safety Considerations:

Page 2 of 8

JOB PERFORMANCE WORKSHEET None 9.0 Approximate Completion Time:

20 minutes 10.0 Directions To The Student(s):

A. You are the Primary Operator. You are going to verify the alert and alarm setpoints of the COP Exhaust Radiation Monitors prior to placing COP in service.

B. The following information is provided to you:

1. Plant is in Mode 1.

2. The previous shift has made preparations to place COP in service per 081023.69, section 4.2.

C. Perform the task per 081023.69 Containment On-Line Purge Operation, section 4.2.

D. Prerequisites for performance of 081023.69 section 4.2 have been completed.

E. C80917.02C, release permit, has already been approved.

11.0 Initiating Cue:

U8 to Primary Operator, "Primary Operator, after reviewing the Gaseous Effluent Waste Containment Purge Release Permit, continue with preparations to place COP in service per OS1 023.69 step 4.2.

Page 3 of 8

PERFORMANCE CHECKLIST 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.

CUE: If the student requests a Peer Check at any time during the ...IPM respond: "No one is available to peer check your actions. Please continue with the task."

2. P RECORDS the expected RECORDS the value 9.1 as Expected radiation monitor response Radiation Monitor Response per from the Gaseous Effluent step 4.2.3.

Waste (GEW) Containment Purge Release Permit, CH L524.

3. P DETERMINES the New COP Per step 4.2.4, ADDs the Monitor Background Levels Expected Radiation Monitor (CPM) Response value to the Current COP radiation monitor background levels recorded in step 4.2.2

RECORDS 2.0BE+01 (+/- 4 CPM) for 1 RM-6527A-1

RECORDS 2.05E+01 (+/- 4 CPM) for 1 RM-6527A-2

RECORDS 2.03E+01 (+/- 4 CPM) for 1 RM-6527B-1

RECORDS 1.96E+01 (+/- 4 CPM) for 1 RM-6527B-2 Page 4 of B

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

denotes a critical step

denotes a critical step SAT UNSAT CUE: After student determines that it is necessary to make RDMS data base changes, "Step 4.2.6.1 will be performed by the BOP operator and is in progress. Continue with step 4.2.6.2" NOTE: If the student determines that it is not necessary to perform step 4.2.6, then the ...IPM is complete and the JPM is a failure.

4. P DETERMINES the Need to *DETERMINES that it is Make RDMS Data Base necessary to perform step 4.2.6 Changes.

5. P CALCULATES the New ALERT Per step 4.2.6.2, multiplies ALARM setpoint for each the New COP Monitor Channel. Background Level recorded in step 4.2.4 by 1.5

*RECORDS 3.12E+01 (+/- 6 CPM) for 1 RM-6527A-1

*RECORDS 3.08E+01 (+/- 6 CPM) for 1 RM-6527A-2

*RECORDS 3.05E+01 (+/- 6 CPM) for 1 RM-6527B-1

*RECORDS 2.94E+01 (+/- 6 CPM) for 1 RM-6527B-2 Page 5 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT

6. P CALCULATES the New HIGH Per step 4.2.6.3, multiplies ALARM setpoint for each the New COP Monitor Channel. Background Level recorded in step 4.2.4 by 1.95

*RECORDS 4.06E+01 (+/- 8 CPM) for 1 RM-6527A-1

*RECORDS 3.99E+01 (+/- 8 CPM) for 1 RM-6527A-2

*RECORDS 3.96E+01 (+/- 8 CPM) for 1 RM-6527B-1

*RECORDS 3.82E+01 (+/- 8 CPM) for 1 RM-6527B-2 CUE: "The JPM is complete."

7. Stop time Time to complete the task s 30 minutes.

Evaluator calculates time to complete task.

Page 6 of 8

PERFORMANCE

SUMMARY

Provide comments on unsatisfactory performance of an element/step or for 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 7 of 8

TEAR-OFF SHEET Directions to the Student:

A. You are the Primary Operator. You are going to verify the alert and alarm setpoints of the COP Exhaust Radiation Monitors prior to placing COP in service.

B. The following information is provided to you:

1. The plant is in Mode 1.

2. The previous shift has made preparations to place COP in service per OS1023.69 section 4.2.

C. Perform the task per per OS1023.69 Containment On-Line Purge Operation, section 4.2.

D. Prerequisites for performance of OS1023.69 section 4.2 have been completed.

E. CS0917.02C, release permit, has already been approved.

Initiating Cue:

US to Primary NSO, "Primary Operator, after reviewing the Gaseous Effluent Waste Containment Purge Release Permit, continue with preparations to place COP in service per 051023.69 step 4.2.3."

Page 8 of 8

SEABROOK SRO ADMIN JOB PERFORMANCE MEASURE* VERIFY QPTR CALCULATION Rev. 1 Student Name: _ _ _ _ _ _ _ _ _ _ _ LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: - - - - - - - - - - - - DATE:

APPROVED BY: DATE:

=TR~A~IN~IN~G~S~U~P~ER~V~IS~O~R---

JOB PERFORMANCE WORKSHEET 1.0 Task Number and

Description:

Position: RO 0150200501 Perform A Manual QPTR Calculation

2.0 Conditions

A Plant is now at 100% power after recovering from a dropped rod at EOL.

B. The main plant computer has been inoperable since yesterday (It was inoperable when the rod dropped).

C. The seven day QPTR surveillance has been performed by an RO.

D. Incore/Excore calibration was performed yesterday (before the rod dropped).

3.0 Standards

Verify the results of the manual QPTR surveillance per RX 1703, QPTR Surveillance.

4.0 Student Materials:

Copy of the Directions Tear-Off Sheet Calculator RX1703, QPTR Surveillance, Rev. 7, Chg. 2.

Completed Form A: Quadrant Power Tilt Calculation Sheet 5.0 Limitations on performance:

Simulate/Perform all steps.

6.0

References:

Procedures RX1703, QPTR Surveillance.

OS1000.05, Power Increase.

ON1251.01, Loss Of Plant Computer.

Page 2 of 11

JOB PERFORMANCE WORKSHEET

7.0 Setting

Classroom

1. Use values listed in RE-17.

2. Give the student the completed copy of Form A: Quadrant Power Tilt Calculation Sheet.

8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

20 minutes 10.0 Directions to the Student(s):

Initial Conditions:

1. Plant is now at 100% power following the recovery of a dropped rod at EOL.

2. The main plant computer has been inoperable since yesterday.

3. The QPTR surveillance has been performed by an RO.

TOP (A) DETECTORS I N41 N42 N43 N44 I Detector Current 184 182 181 179 I I micoamps BOTTOM (B) DETECTORS N41 N42 N43 N44 Detector Current 177 197 191 187 micoamps Page 3 of 11

JOB PERFORMANCE WORKSHEET 11.0 Initiating Cue:

Verify the results of the completed QPTR Surveillance per RX1703. The QPTR alarm surveillance work order has been generated.

Provide your results to me.

Page 4 of 11

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

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".

NOTE: For performance of JPM in a classroom setting the student is provided with a copy of RX1703, Quadrant Power Tilt Ratio Surveillance.

2 P RECORD the Figure RE-17 Records today's date and the revision revision and the date and time number of the RE-17 curve used the operable power range currents were taken.

NOTE: Detector current data for upper & lower detectors are provided. Detector Current value units are microamps. Student should be able to determine that all Power Range Detectors are operable when given the detector current data.

3. P VERIFY that the current output Verifies outputs.

from the top (A) and bottom (8) detector of each channel was correctly recorded on Form A, Quadrant Power Tilt Calculation Sheet Row 1.

N41 top (A) detector N42 top (A) detector N43 top (A) detector N44 top (A) detector N41 bottom (8) detector N42 bottom (8) detector N43 bottom (8) detector N44 bottom (8) detector Page 5 of 11

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT CUE: If the student asks for independent verification of the values recorded in Row 1 of Form A, cue, evaluator to student, " Form A Detector currents have been independently verified."

NOTE: The student is provided with a copy of RE-17.

4. P Using data from Technical Data Book Figure RE-17, VERIFY that the 100% power, 0% AFD detector current, for the top (A) and bottom (B) detector of each channel was recorded correctly on Form A, Quadrant Power Tilt Calculation Sheet Row 2.

a. From Technical Data Book fig RE-17, Records 100% power, 0% AFD values:

4 Top (A) Detectors

b. From Technical Data Book fig RE-17, Records 100% power, 0% AFD values:

4 Bottom (B)Detectors

5. P VERIFY that the normalized detector current was calculated correctly by dividing each detector current by its 100%

power, 0% AFD current.

VERIFY the results from Form A, Quadrant Power Tilt Calculation Sheet Row 3.

Page 6 of 11

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

a. Calculates and verifies Normalized Detector Currents:

4 Top (A) Detectors

b. Calculates and verifies Normalized Detector Currents:

4 Bottom (B)Detectors

6. P VERIFY that the average normalized detector current for the top detectors and for the bottom detectors was calculated correctly. VERIFY the results from Form A, Quadrant Power Tilt Calculation Sheet Row 4.

a. Calculates and records average normalized detector currents:

Top (A) Detectors

Candidate should identify that the calculated normalized detector current for the top detectors is incorrect.

b. Calculates and records average normalized detector currents:

Bottom (B) Detectors Page 7 of 11

PERFORMANCE CHECKLIST O=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

7. P VERIFY that the Quadrant Power Tilt Ratio for each detector was calculated correctly by dividing each normalized detector current by its associated average normalized detector current.

VERIFY the results from Form A, Quadrant Power Tilt Calculation Sheet.

a. Calculates and records QPTR for each detector:

4 Top (A) Detectors

The student should identify that the calculated QPTR for each top detectors is incorrect.

b. Calculates and records QPTR for each detector:

4 Bottom (B) Detectors

8. P VERIFY that the maximum Verifies (circled) the maximum power tilt ratio QPTR was circled on Form A on Form A Row 5.

RowS.

The student should identify that the calculated maximum QPTR should be from top detector N-42.

CUE: If the student asks for independent verification of the Form A calculations, cue, evaluator to student, "

Form A calculations have been independently verified."

Page 8 of 11

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

9. P Determine if LC03.2.4 is/is not met based on maximum QPTR.

a. Identify in step 6 of Form A that LCO 3.2.4 is/is not met

b. In Row 6 Form A circle YES/NO

The student should identify that the QPTR value for channel N-41 and N-42 top detectors exceed 1.02 and that Tech.

Spec. 3.2.4 LCO is NOT met.

NOTE: See answer key for the correct item to circle in row 6 on Form A CUE: "The JPM is complete."

10. Stop time _ _ _ _ __ Time to complete the task

~ 20 minutes.

Evaluator calculates the time to complete the task.

11. Obtain from student:

Tear Off Sheets and any other training materials used in the performance of the JPM Page 9 of 11

PERFORMANCE

SUMMARY

Provide comments on unsatisfactory performance of an element/step or for 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

TEAR-OFF SH~ET FOR JPM 2009 RO-ADMIN#1 Initial Conditions:

1. Plant is now at 100% power following the recovery of a dropped rod at EOl.

2. The main plant computer has been inoperable since yesterday.

3. The QPTR surveillance has been performed by an RO.

TOP (A) DETECTORS N41 N42 N43 N44 i Detector Current 184 182 181 179 !

micoamps BOTTOM (B) DETECTORS N41 N42 N43 N44 Detector Current 177 197 191 187 micoamps Initiating Cue:

Verify the results of the completed QPTR Surveillance. The QPTR alarm surveillance work order has been generated.

Provide your results to me.

Page 11 of 11

EN RG SEABROOK SRO ADMIN JOB PERFORMANCE MEASURE- VERIFY SHUTDOWN MARGIN (MODE 1)

Rev. 1 Student Name: _ _ _ _ _ _ _ _ _ _ _ LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: _ _ _ _ _ _ _ _ _ _ _ _ _ DATE:

APPROVED BY: _______-:--::--:---=--=-____--:------ DATE:

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET

1. Task Number and Description Position RO SBK 0010100401 Perform Shutdown Margin Calculation

2. Conditions:

1. The plant is in Mode 1 at 100% RTP and stable.

2. Core age is 12000 MWD/MTU

3. RCS boron concentration is 1300 ppm.

4. During performance of OX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core.

5. Rod H-2 cannot be moved.

6. OS1210.05, Dropped Rod actions are being performed.

7. The RO has completed RX1707, "Shutdown Margin Surveillance.

3. Standards:

Verify that results of the shutdown margin calculation are correct within +/-0.035%L'iKlK.

4. Student Materials:

Copy of Tear Off Sheet.

Copy of RX1707, Shutdown Margin Surveillance Rev 7 Chg.7.

Copy of Primary TOB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration Rev. 01-14-00.

Copy of Primary TOB, Figure RE-18 Shutdown Margin Values, Rev. 01-14-00.

Copy of Primary TDB, Figure RE-19 Control Bank Worth At RIL vs. Power Rev. 01-14 00.

Copy of Core Operating Limit Report SSTR Rev. 121.

Calculator.

Copy of completed Form C: Shutdown Margin Determination Immovable, Untrippable or Dropped Rod.

5. Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

6.

References:

Procedures:

OS1210.0S, Dropped Rod

RX 1707, Shutdown Margin Surveillance Page 2 of 8

JOB PERFORMANCE WORKSHEET Curves:

Primary TDB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration

Primary TDB, Figure RE-18 Shutdown Margin Values

Primary TDB, Figure RE-19 Control Bank Worth At RIL VS. Power Technical SpecificationsrrRM:

3.1.3.1 Moveable Control assemblies Group Height

3.1.3.6 Control Rod Insertion Limits

3.1.1.1 Shutdown Margin >200°F

Core Operating Limit Report

7. Setting:

Classroom.

8. Safety Considerations:

None.

9. Approximate Completion Time:

15 minutes

10. Directions To The Student:

A. The following information is provided to you:

1. The plant is in Mode 1 at 100% RTP and stable.

2. Core age is 12000 MWD/MTU

3. RCS boron concentration is 1300 ppm.

4. During performance of OX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core.

5. Rod H-2 cannot be moved.

6. OS121o.oS, Dropped Rod actions are being performed.

7. The RO has completed RX1707, "Shutdown Margin Surveillance.

11. Initiating Cue:

Evaluator to student (or student's name), "Review the shutdown margin calculation and report your findings."

~--------------------------------

Page 3 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT NOTE: When the student demonstrates the ability to obtain controlled copies of RX1707, Shutdown Margin Surveillance, Primary TDB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration, Primary TDB, Figure RE-18 Shutdown Margin Values, Primary TDB, Figure RE-19 Control Bank Worth At RIL vs. Power, and Core Operating Limit Report, provide the student with the required documents when requested.

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."

2. P Refer to section 4.4 of RX1707 Refers to section 4.4 of RX 1707 Shutdown Margin Surveillance to Shutdown Margin Surveillance to complete Form C Shutdown Margin complete Form C Shutdown Margin Determination Immovable, Determination Immovable, Untrippable, Or Dropped Rod(s) Part Untrippable, Or Dropped Rod(s) Part

1. 1.

NOTE: See key for all values that student should enter on Form D.

3. P Verify the correct number of Verifies the correct number of immoveable,untrippable or dropped immoveable,untrippable or dropped rod(s) were entered on Form C block rod(s) were entered on Form C block (a). (a).

4. P Verify that the correct value for Verifies that the correct value of --

maximum worth of individual maximum worth of individual immoveable,untrippable or dropped immoveable,untrippable or dropped rod(s) was entered on Form C block rod(s) (using Primary TDB figure RE (b). 18) was entered on Form C block (b).

5. P Verify that the calculation of total Verifies that the calculation of total unavailable rod worth was performed unavailable rod worth was performed correctly and entered on Form C block correctly (by multiplying (a) by (b>>

(c). and entered on Form C block (c).

Page 4 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT CUE: If student requests boron concentration, reply, "RCS boron concentration is 1300 ppm."

6. P Verify that the correct value for total Verifies that the correct value for total power defect is entered on Form C power defect for current relative block (d). power using Primary TDB figure RE-8 and enters on Form C block (d).

7. P Verify that the correct value of "worth Verifies that the correct value of of the control banks inserted to the "worth of the control banks inserted to rod insertion limit for current relative the rod insertion limit for current power" is entered on Form C block relative power" (using Primary TDB (e). figure RE-19) is entered on Form C block (e).

8. P Verify that the correct value of "total Verifies that the correct value of "total control and shutdown rod worth minus control and shutdown rod worth minus stuck rod and less 10% uncertainty" is stuck rod and less 10% uncertainty" entered on Form C block (t). (using using Primary TDB figure RE

18) is entered on Form C block (t).

9. P Verify that the shutdown margin Verifies shutdown margin calculation calculation was performed correctly: performed correctly:

[f - (c + d + e)] /1,000. [f - (c + d + e)] /1,000.

Student should identify that the shutdown margin calculation was NOT performed correctly. Student should provide corrected calculation of shutdown margin.

(See answer key for correct answer).

CUE: If student fails to report the shutdown margin adequacy determination, provide the cue, "Is shutdown margin adequate?"

10. P Notify SM/US if the shutdown margin Notifies SM/US if the shutdown is less than the limit specified in the margin is less than the limit specified Core Operating Limits Report. in the Core Operating Limits Report.

Page 5 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT CUE: "The JPM is complete."

11. Stop time _ _ __ Time to complete task S 15 minutes Evaluator calculates time to complete task

12. Obtain from student:

Tear Off sheets and any other training materials used in performance of this JPM.

Page 6 of 8

PERFORMANCE

SUMMARY

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.

Page 7 of 8

TEAR OFF SHEET Directions To The Student:

A. The following information is provided to you:

1. The plant is in Mode 1 at 100% RTP and stable.

2. Core age is 12000 MWD/MTU

3. RCS boron concentration is 1300 ppm.

4. During performance of OX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core.

5. Rod H-2 cannot be moved.

6. OS1210.05, Dropped Rod actions are being performed.

7. The RO has completed RX1707, "Shutdown Margin Surveillance.

Initiating Cue:

Evaluator to student (or student's name), "Review the shutdown margin calculation and report your findings."

Page 8 of 8

N XTera~

ENER~

SEABROOK SRO ADMIN JOB PERFORMANCE MEASURE-TECHNICAL SPECIFICATION DETERMINATION AND REQUIRED OFF-SITE NOTIFICATIONS Rev. 1 Student Name: _ _ _ _ _ _ _ _ _ _ _ LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INI1-IAL EXAM SECURITY AGREEMENT.

PREPARED BY:

- - - - - - - - - - - - - - - - - - DATE: - - - - - - -

APPROVED BY: ________- - - - - - - - DATE: _ _ _ __

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET 1.0 Task Number and

Description:

Position: SRO

2.0 Conditions

1. The plant is operating at full power.

2. The Shift Manager informs you that Charging Pump, CS-P-2A and Safety Injection Pump, SI-P-6B are both INOPERABLE.

3.0 Standards

Identify the correct TS determination and identify the required off-site notifications and time periodicities in accordance with the Regulatory Compliance Manual (NARC).

4.0 Student Materials:

Copy of the Tear-Off Sheet Seabrook Technical Specifications Regulatory Compliance Manual (NARC) 5.0 Limitations on performance:

Perform all steps. Verbalize all actions to the evaluator.

6.0

References:

Seabrook Technical Specifications Regulatory Compliance Manual (NARC)

Emergency Response Manual (SSER)

OS1000.06, POWER DECREASE

7.0 Setting

Classroom 8.0 Safety Considerations:

None.

9.0 Approximate Completion Time:

20 minutes Note to Evaluator - Obtain Tear-Off Sheets from student foliowinQ JPM completion (Ops only).

PaQe 2 of 7

JOB PERFORMANCE WORKSHEET 10.0 Directions to the Student:

The following information is provided to you:

1. The plant is operating at full power.

2. The Shift Manager informs you that Charging Pump, CS-P-2A and Safety Injection Pump, SI-P-6B are both INOPERABLE.

11.0 Initiating Cue: Shift Manager to Work Control Supervisor (or name), "For the given plant conditions what regulatory notifications are required, if any, and justify your answer."

Note to Evaluator - Obtain Tear-Off Sheets from student foliowinQ JPM completion (Ops onlv).

Page 3 of 7

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

1. P Start time _ _ __ Initiating cue read.

2. P Obtains a copy of Technical

Determines that there is no action Specifications and references statement for two inoperable trains of applicable TS based on given ECCS (TS 3.5.2) and therefore TS plant conditions. 3.0.3 applies.

NOTE: Continue with this JPM only if the correct TS call was made above, otherwise CUE that this JPM is complete.

CUE: SM to WCS, "Using the Regulatory Compliance Manual (NARC), identify the required offsite notifications and time limits. The required shutdown (TS 3.0.3 action) began at 0200 this morning."

NOTE: The student may refer to ER-1.1A to confirm there is no E-Plan implication.

NARC ACTIONS Outlined Below

3. P Refer to the IMMEDIATE Refers to the IMMEDIATE NOTIFICATION tab and NOTIFICATION tab and reporting reporting requirements table in requirements table in the NARC:

the NARC to identify the following:

NOTE: If student asks if the shutdown has begun state "The required shutdown began at 0200."

NRC Operations Center

Identifies notification to NRC within four hours Operations Center is required within 4 Hrs (Initiation of a TS required Shutdown)

CUE: If student wants to reference the OPMM or NAP-402, inform him it is not necessary.

Note to Evaluator - Obtain Tear-Off Sheets from student foliowinQ JPM completion (Ops only).

Page 4 of 7

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT NOTE: The student may also determine that the following on-site notifications should be made:

NRC Resident Inspector - Identifies NRC Resident Inspector ASAP/1 hour ASAP (when any 4 Qour notification or less is reported to the NRC or due to the additional notification section within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

OPS.! ASST. OPS. Mgr Identifies OPS.! ASST. OPS. Mgr ASAP/1 hour ASAP (any transient event/major equipment failure or due to the additional notifications section within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

Licensing - ASAP Identifies Regulatory Compliance ASAP (when any 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification or less is reported to the NRC)

FPLE Communications - Identifies FPLE Communications ASAP/1 hour ASAP (any off-normal condition or due to the additional notifications section within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months )

CUE: The ~IPM is complete.

4. Stop time Start - Stop time is ~ 25 minutes.

Evaluator calculates the time to complete the task.

Note to Evaluator - Obtain Tear-Off Sheets from student foliowinQ JPM completion (Ops only).

Page 5 of 7

PERFORMANCE

SUMMARY

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

Note to Evaluator - Obtain Tear-Off Sheets from student foliowinQ JPM completion (Ops only).

PaQe 6 of 7

TEAR-OFF SHEET Directions to the Student:

The following information is provided to you:

1. The plant is operating at full power.

2. The Shift Manager informs you that Charging Pump, CS-P-2A and Safety Injection Pump, SI-P-6B are both INOPERABLE.

Initiating Cue:

Shift Manager to Work Control Supervisor (or name), "For the given plant conditions what regulatory notifications are required, if any, and justify your answer."

Note to Evaluator - Obtain Tear-Off Sheets from student followin!:l JPM completion (Ops only).

Paqe 7 of7

EN SRO ADMIN JOB PERFORMANCE MEASURE- EMERGENCY DOSE LIMIT EXTENSION Rev. 1 Student Name: LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE:

APPROVED BY: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE:

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET 1.0 Task Number and

Description:

Position: SRO SSK 1190402303 Direct Emergency Response as Short Term Emergency Director.

2.0 Conditions

1) The plant has suffered a large break LOCA.

2) The core has uncovered.

3) The TSC previously dispatched a team to the PAS Mechanical Penetration Area to perform emergency repair work on COP-V-4.

4) One of the workers at COP-V-4 is having severe chest pains.

5) The TSC is dispatching a team to perform life saving activities on the individual.

6) Radiation readings taken at the doorway to the Mechanical Penetration Area are 2 REM/Hr. Dose at COP-V-4 is conservatively estimated at 15 REM/Hr

7) The OSC conservatively estimates 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to perform the lifesaving activity,

3.0 Standards

Authorize an Emergency Dose Limit Extension per ER 4.3, Radiation Protection During Emergency Conditions.

4.0 Student Materials:

Copy of the Directions Tear-Off Sheet Calculator ER 4.3, Radiation Protection During Emergency Conditions 5.0 Limitations on performance:

Even if requested no Peer Checks will be provided during the JPM.

6.0

References:

Procedures ER 4.3, Radiation Protection During Emergency Conditions.

7.0 Setting

Classroom 8.0 s::n',..T\I Considerations:

Page 2 of 7

JOB PERFORMANCE WORKSHEET None 9.0 Approximate Completion Time:

20 minutes 10.0 Directions to the Student(s):

Initial Conditions:

1) The plant has suffered a large break LOCA.

2) The core has uncovered.

3) The TSC previously dispatched a team to the PAS Mechanical Penetration Area to perform emergency repair work on COP-V-4.

4) One of the workers at COP-V-4 is having severe chest pains.

5) The TSC is dispatching a team to perform life saving activities on the individual.

6) Radiation readings taken at the doorway to the Mechanical Penetration Area are 2 REM/Hr. Dose at COP-VA is conservatively estimated at 15 REM/Hr

7) The OSC conservatively estimates 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to perform the lifesaving activity.

11.0 Initiating Cue:

You are the Short Term Emergency Director (STED).

Emergency Dose Limit Extensions have been requested for a three person team to enter the Mechanical Penetration Area to perform lifesaving activities.

Review the Emergency Dose limit Extensions and provide approval if appropriate.

Provide the completed Forms to me.

Page 3 of 7

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

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".

NOTE: Provide the student with the 3 completed Emergency Dose Limit Extension sheets and a copy ER 4.3, Radiation Protection During Emergency Conditions. Students will evaluate and authorize the completed dose extensions.

NOTE: JPM task is approval of a task that is administrative in nature. Student may perform steps in any order, provided that critical tasks are all accomplished.

2 P ER 4.3, step 5.1.2, 2a: a Dose extension for NSO 24000 mrem Verifies dose extension for all workers exceeds 4500 mrem/yr (minimum level requiring STED approval) b Dose extension for Site EMT 24000 mrem c Dose extension for HP Technician 24000 _ _

mrem 3 P ER 4.3, Step 5.1.2, 2b, and a Dose extension for NSO 24000 mrem Figure 2 Verifies dose extension is 25 rem or less for "Lifesaving" category b Dose extension for Site EMT 24000 mrem c Dose extension for HP Technician 24000 _ _

mrem 4 P ER 4.3, Step 5.1.2, 2c, and a NSO has signed figure 4.

Figure 3 Verifies dose extension is up to 25 rem only for Volunteers fully aware of risks for "Lifesaving" category, and signified by Page 4 of 7

PERFORMANCECHECKUST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT employee signature on figure 4.

b Site EMT has signed figure 4.

c HP Technician has signed figure 4.

5 *P Authorizes Dose Extensions *a Dose extensions signed.

CUE: "The JPM is complete."

6. Stop time _ _ _ _ __ Time to complete the task s 20 minutes.

Evaluator calculates the time to complete the task.

7 Obtain from student:

Tear Off Sheets and any other training materials used in the performance of the JPM Page 5 of 7

PERFORMANCE

SUMMARY

Provide comments on unsatisfactory performance of an element/step or for 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 6 of 7

TEAR-OFF SHEET Initial Conditions:

1) The plant has suffered a large break LOCA.

2) The core has uncovered.

3) The TSC previously dispatched a team to the PAS Mechanical Penetration Area to perform emergency repair work on COP-V-4.

4) One of the workers at COP-VA is having severe chest pains.

5) The TSC is dispatching a team to perform life saving activities on the individual.

6) Radiation readings taken at the doorway to the Mechanical Penetration Area are 2 REM/Hr.

Dose at COP-V-4 is conservatively estimated at 15 REM/Hr.

7) The OSC conservatively estimates 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to perform the lifesaving activity.

Initiating Cue:

You are the Short Term Emergency Director (STED).

Emergency Dose Limit Extensions have been requested for a three person team to enter the Mechanical Penetration Area to perform lifesaving activities.

Review the Emergency Dose limit Extensions and provide approval if appropriate.

Provide the completed Forms to me.

Page 7 of 7

SRO ADMIN JOB PERFORMANCE MEASURE-POST SCENARIO EMERGENCY PLAN CLASSIFICATION AND NOTIFICATION Rev. 1 Student Name: LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: DATE:

APPROVED BY: DATE:

=TR~A~IN~IN~G~S~U~P~E~RV~IS~O~R~---

JOB PERFORMANCE WORKSHEET 1.0 Task Number and

Description:

Position: SRO 1190402003 Perform required notifications of on-site and off-site personnel for emergency events.

2.0 Conditions

A. As applicable to associated simulator scenario.

3.0 Standards

Classify the emergency condition and complete the State Notification Fact Sheet.

4.0 Student Materials:

Copy of the Tear-Off Sheet.

E-Plan folder drawer or copies of the following:

ER-1.1, Classification of Emergencies ER-1.1A, Emergency Classification Flow Chart ER-1.2, Emergency Plan Activation 5.0 Limitations On Performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator.

6.0

References:

Procedures:

RE-1.1, Classification of Emergencies

ER-1.2, Emergency Plan Activation

7.0 Setting

Simulator, post scenario in FREEZE.

Notes To Evaluator

Because this JPM is done with the simulator in freeze the Control Board clock cannot be used to track time. The digital clock on the Communications Console or a wristwatch must be used. There is a reminder cue in the body of the JPM.

8.0 Safety Considerations:

Note to Evaluator - Obtain Tear Off Sheets from student following JPM completion (Ops only).

Page 2 of 8

JOB PERFORMANCE WORKSHEET None 9.0 Approximate Completion Time:

30 minutes 10.0 Directions To The Student(s):

A. You are the Work Control Supervisor.

B. The following information is provided to you:

1) The plant was initially in Mode 1.

c. The evaluator will act as the Shift Manager and provide the cues and communications for this JPM. Do you have any questions?

11.0 Initiating Cue:

Shift Manager to Work Control Supervisor, "Work Control Supervisor, classify the Emergency Condition based on the most severe condition experienced during the scenario and complete the State Notification Fact Sheet."

Note to Evaluator - Obtain Tear Off Sheets from student following JPM completion (Ops only).

Page 3 of 8

PERFORMANCECHECKUST 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.

2. Performs ER-1.1 Section 5.1 Emergency Classification for Post Scenario Evaluation NOTE: ER-1.1, Step 2, Dose Projection is not applicable.

P Review applicable forms: Reviews applicable forms.

ER-1.1A: Emergency Initiating Condition Matrix Modes 1,2, 3 and 4.

ER-1.1C, Fission Product Barrier Degradation Matrix Modes 1, 2, 3 and 4.

ER-1.1 B, Emergency Initiating Condition Matrix, Modes 5, 6, and Defueled P Circle the potential emergency Circles the potential emergency initiating initiating condition(s) on each condition.

form.

P For category A, E, H, Sand C Verifies that the EAL is met or the intent is events, refer to initiating met.

condition EAL(s) in Figure 1 and verify that the EAL is met or the intent is met.

P Identify the most severe *Identifies the most severe (highest)

(highest) emergency emergency classification.

classification for which the EAL(s) is met or the intent of the initiating condition is met.

P If an emergency classification Implements procedure ER-1.2.

is warranted, immediately implement Station Emergency Response Procedure ER 1.2, Emergency Plan Activation.

Note to Evaluator - Obtain Tear Off Sheets from student following JPM completion (Ops only).

Page 4 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT NOTE: The student is expected to use the applicable Emergency Plan binder from the drawer.

INSTRUCTOR CUE: DO NOT RESET THE SIMULATOR UNTIL THE CANDIDATE HAS AQUIRED THE DATA TO DETERMINE THE E-PLAN CLASSIFICATION!

CUE: If the sim is in freeze, when the student looks at the MCB clock, inform them that "The MCB clock is not running. Please use the Communications Console clock or your wristwatch to determine the time."

3. P Acquires applicable binder. Acquires binder.

NOTE: Expected emergency classification is identified at the end of each simulator exam scenario description.

CUE: Shift Manager to Work Control Supervisor, "There is no Code Yellow condition imminent or in progress".

P Determine if a Code Yellow

Determines if a Code Yellow condition condition exists. exists.

P Declare emergency via a crew *Declares emergency and records time of update. update.

Time of Declaration____ When student performs the update.

EVALUATOR CUE: Ask the candidate if they still need the simulator for data for this JPM. If not then direct the simulator operator to reset the simulator.

4. P Complete ER-2.0B, State Completes ER-2.0B:

Notification Fact Sheet.

Block 1-Leave Blank

Block 1- Leaves blank.

CUE: If asked, STED to WCS, "Time of declaration was _ _ _ _ based on your update."

Note to Evaluator - Obtain Tear Off Sheets from student following JPM completion (Ops only).

Page 5 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT

Block 2- Check (applicable *. Block 2- Checks emergency plan "Declared" and classification) . checks (applicable emergency plan classification) and enters time declared.

Block 3- Enter emergency initiating condition.

. Enters appropriate initiating condition.

Block 4- Use applicable *. Checks applicable PARS.

protective action recommendations.

NOTE: The candidate should determine if there has been a release based upon scenario conditions.

Determines if a release has *

Block 5-checks a occurred. release has/has not occurred.

NOTE: When student presents form for authorization: Make no comments of any sort on the information recorded. Evaluator should sign form as STED

Block 6-Self explanatory.

Block 6- STED authorizes by signing and dating the form.

Time State Notification Fact Sheet completed._ _ _ _ _,

Time State Notification Fact Sheet Completed - Time of Declaration =

_ _ _ _ (Must be <15 minutes)

CUE: "The JPM is complete."

5. Stop time Time to complete the task s 30 minutes.

Note to Evaluator Obtain Tear Off Sheets from student following JPM completion (Ops only).

Page 6 of 8

PERFORMANCE

SUMMARY

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

Note to Evaluator - Obtain Tear Off Sheets from student following JPM completion (Ops only).

Page 7 of 8

TEAR-OFF SHEET Directions to the Student:

Evaluator gives Tear-Off sheet to the student.

A. You are the Work Control Supervisor. You are going to activate the emergency plan based on the following information.

B. The following information is provided to you:

1) The plan was initially in Mode 1.

C. The evaluator 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 Work Control Supervisor, "Work Control Supervisor, classify the Emergency Condition based on the most severe condition experienced during the scenario, and complete the State Notification Fact Sheet."

Note to Evaluator - Obtain Tear Off Sheets from student following JPM completion (Ops only).

Page 8 of 8

SRO ADMIN JPM POST SCENARIO EMERGENCY PLAN CLASSIFICATION AND NOTIFICATION ANSWER KEY:

SIMULATOR EXAM #1

'::)ill\u\aAtv bX4tr.l

~!4y sb-t lfr3 EMERGENCY INITIATING CONDITION MATRIX Modes 1, 2, 3 and 4 Any UNPLANNED release of gaseous Actual or projected offsite dose> 100 Actual or projected offsite dose>

or liquid radioactivity to the environment mRem TEDE or 500 mRem Thyroid 1,000 mRem TEDE or 5,000 mRem

> 200 times the ODCM limits for:<: 15 CDE Thyroid CDE Op. Modes: All Op. Modes: All Damage to irradiated fuel or loss of water level that has or will result in the uncovering of irradiated fuel outside the reactor vessel Modes: All Unexpected increase in plant radiation Op. Modes: All Natural and destructive phenomena Natural and destructive phenomena affecting the PROTECTED AREA affecting the plant VITAL AREA Modes: All Modes: All FIRE within PROTECTED AREA FIRE or EXPLOSION affecting the boundary not extinguished within 15 operability of plant safety systems minutes of detection required to establish or maintain safe Op. Modes: All shutdown Modes: All Release of a toxic, corrosive, asphyxiant or flammable gas within or contiguous to a VITAL AREA affecting equipment required to maintain safe operations, or establish or maintain safe shutdown Modes: All Notification of HOSTILE ACTION Security event resulting in loss of within the PROTECTED AREA physical control of the facility Modes: All j._ ..**.._._*.__*._._.. _._._..***._ ***. - -.-.-.. - ..-.-.-.,

Other conditions existing which in the Other conditions existing which in the Other conditions existing which in judgment of the STED/SED warrant judgment of the STED/SED warrant the judgment of the STEDISED declaration of an Unusual Event declaration of an Alert warrant declaration of General Op. Modes: All Op. Modes: All Emergency Modes: All Loss of all offsite power to AC Power to AC emergency buses Loss of both AC emergency buses emergency buses for> 15 minutes reduced to a single power source for for> 15 minutes Op. Modes: 1, 2, 3, 4 > 15 minutes such that any additional Op. Modes: 1, 2, 3, 4 single failure would result in station blackout

°e.:J:!J!.d..~E;_!.!.3;_3.:.._4___'.'."_"_'_'._'.'__

ATWS and manual reactor shutdown ATWS and manual reactor shutdown ATWS and all manual actions to from the MCB was successful from the MCB was NOT successful shutdown the reactor were NOT Op. Modes: 1, 2, 3 Op. Modes: 1. 2 successful, AND extreme challenge to Core Cooling or Heat Sink Modes: 1 2 Inability to reach required shutdown within Technical Specification limits Modes:

Inability to monitor a SIGNIFICANT TRANSIENT in progress Op. Modes: 1, 2, 3, 4 r -

I I Modes 1, 2. 3 and 4

__________________ 1 ER 1.1A Rev. 46

S, r1\ I,A tt~ WctWl -::fr 1

<D~~-b 3cF~

Seabrook Station State Notification Fact Sheet Time Notification Initiated: NH MA Block 1: This is: _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ at Seabrook Station.

- :;i~;D~~;2~~~

I

~-~s~~~~;e~~--_~i~l_~

[ J Alert :

1---------------------,

I Time Terminated: :

I I

I

[ ) Site Area Emergency:

I [ I General Emergency : IL L __________________________________________ _ _____________________ I The emergency initiating condition is _ _ _,-",5,--'--'u=---!l_'___

We recommend the ~wing protective actions:

~ None [ ) As follows New Hampshire Massach usetts ERPA Town Shelter Evacuate ERPA Town Shelter Evacuate A. Seabrook [ ) [ ) B. Amesbury [ ) [ I Hampton Falls [I [I Salisbury [J [I

c. Kensington [I [ ) E. Merrimac [ I [ )

S. Hampton [ I [ ) Newburyport [ ) [ )

Newbury [I [ I D. Hampton [ I [ ) West Newbury [I [ I N. Hampton [ I [I Beaches F. Brentwood [ ) [ ) Evacuate E. Kingston [I [I [ ) Seabrook Beach Exeter [ ) [ ] [I Hampton Beach Newfields [I [I Newton [ ) [ ) Close Kingston [ ) [ ) [I Parker River National Wildlife Refuge LI Plum Island Beach G. Greenland [ ) [I [J Salisbury Beach Stratham [I [I Rye [ ) [I Potassium Iodide (General Emergency only)

New Castle [ ) [ ) [ ) Implement KI plans for the general public Portsmouth [ ) [ )

Block 5: A radiological release V

[ )

Has not occurred Has occurred and is continuing

[ ) Occurred but has been terminated Block 6: Authorized by: _ _ _ _ _ _ _ _ _ __

STED I SED I RM Date Time Block 7: Acknowledge receipt of this message with your name.

New Hampsbire: _ _:-::-_-:-::::-:-_ _ _ _ _ __ Massachusetts: _----,-,--_----,-_ _ _ _ _ _ __

Name of Dispatcher Name of Dispatcher ER2.0B Rev. 31 Page 1 of 1

SRO ADMIN JPM POST SCENARIO EMERGENCY PLAN CLASSIFICATION AND NOTIFICATION ANSWER KEY:

SIMULATOR EXAM #2

EMERGENCY INITIATING CONDITION MATRIX Modes 1, 2, 3 and 4 Actual or projected offsite dose>

1,000 mRem TEDE or 5,000 mRem Thyroid CDE Op. Modes: All Unexpected increase in plant radiation Op. Modes: All Natural and destructive phenomena affecting the PROTECTED AREA Modes: All FIRE within PROTECTED AREA boundary not extinguished within 15 minutes of detection Op. Modes: All Release of toxic, corrosive, asphyxiant or flammable gases deemed detrimental to normal operation of the plant Op. Modes: All Confirmed security event which indicates a potential degradation in the level of safety of the plant Modes: All Security event resulting in loss of physical control of the facility

_.-"._. -Modes: All Control Room evacuation has been initiated Op. Modes: All Other conditions existing \(IIhich the Other conditions existing which in the Other conditions existing which in judgment of the STED/SED warrant judgment of the STED/SED warrant the judgment of the STED/SED declaration of an Unusual Event declaration of an Alert warrant declaration of General Op. Modes: All Op. Modes: All Emergency Modes: All loss of all offsite power to AC Power to AC emergency buses Prolonged loss of both AC emergency buses for> 15 minutes reduced to a single power source for emergency buses Op. Modes: 1, 2, 3, 4 > 15 minutes such that any additional Op. Modes: 1, 2, 3, 4 single failure would result in station blackout 0e:-"~c:d..e~:_.~ 3... __4._._._._

ATWS and manual reactor shutdown ATWS and all manual actions to from the MCB was successful shutdown the reactor were NOT Op. Modes: 1, 2, 3 successful, AND extreme challenge to Core Cooling or Heat Sink

_~e:,_IV!P~I!~ !!..~ ____~ __~____.

Inability to reach required shutdown within Technical Specification limits

":!9..C!..eE~._2!...~~_4____._._.._._.*..._.._; _.._._. -.- - -'---'-"-'-"-'-.-..---..-.,-.. -.

UNPLANNED loss of most or all UNPLANNED loss of most or all safety Inability to monitor a SIGNIFICANT safety system annunciation or system annunciation or indication in TRANSIENT in progress indication in the Control Room for Control Room with either (1) a Op. Modes: 1, 2, 3, 4

> 15 minutes SIGNIFICANT TRANSIENT in Op. Modes: 1, 2, 3, 4 progress, or (2) compensatory indicators are unavailable Modes: 4 r- -

Modes 1. 2. 3 and 4

- - - - - - - - - - - - - - - ______ 1 ER 1.1A Rev,46

ER 1.1 Page 52 Rev. 48 Figure 1 Initiating Conditions and Emergency Action Levels SYSTEM MALFUNCTION Initiating Condition -- SITE AREA EMERGENCY ATWS and manual reactor shutdown from the MCB was NOT successful Operating Mode Applicability: 1 and 2 Emergency Action Levels:

An automatic reactor trip signal did NOT result in neutron flux < 5%.

AND Manual action(s) taken at the MCB did NOT result in neutron flux < 5%.

NOTE Manual action is considered "not successful" ifaction away from the Main Control Board (MCB) is required to shutdown the reactor.

Seabrook Station State Notification Fact Sheet Time Notification Initiated: NH _ _ _ __ MA _ _ _ __

Block 1: This is: _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ at Seabrook Station.

Name Title

,------------------------------- ---------, ,---------------------1 Block 2: : Time Declared: ( ) Unusual Event : !I Time Terminated: :

I I,'

~_____________________ L!

[J .;fert : I I

I VSite Area Emergency:I I I

I I

~ General Emergency : I ,

~--------------- ______ I Block 3: The emergency initiating condition is _ _---'-.::""'-_~__.

Block 4: We recommend the following protective actions:

IV None IJ As follows New Hampshire Massachusetts ERPA Town Shelter Evacuate ERPA Town Shelter Evacuate A. Seabrook (J IJ B. Amesbury IJ I J Hampton Falls I J I J Salisbury [ ] I ]

C. Kensington I] I] E. Merrimac [I I I S. Hampton I J I ] Newburyport [ ] I I Newbury I ] I I D. Hampton (I I I West Newbury ( J ( J N. Hampton ( J [I Beaches F. Brentwood [J [ ) Evacuate E. Kingston [I [J II Seabrook Beach Exeter [I ( ) (I Hampton Beach Newfields I I ( )

Newton II I ) Close Kingston [I IJ II Parker River National Wildlife Refuge (J Plum Island Beach G. Greenland [ I I J (J Salisbury Beach Stratham [1 I J Rye I J I] Potassium Iodide (General Emergency only)

New Castle [1 IJ [ I Implement KI plans for the general public Portsmouth I] II Block S: A radiological release I~ Has not occurred

( ) Has occurred and is continuing I ] Occurred but has been terminated Block 6: Authorized by: _ _: - _ : -_ _ _ __

STED I SED I RM Time Block 7: Acknowledge receipt ofthis message with your name.

New Hampshire: _--:::-:-_-::-::::-:-_:--______ Massachlllletts: _--:::--_-:-::-:----::-_ _ _ __

Name of Dispatcher Name of Dispatcher ER2.0B Rev. 31 Page 1 of I

SRO ADMIN JPM POST SCENARIO EMERGENCY PLAN CLASSIFICATION AND NOTIFICATION ANSWER KEY:

SIMULATOR EXAM #3

I 51 rf\ ul(~'~{ 9'a(;n=tts Sheet J- J""+

EMERGENCY INITIATING CONDITION MATRIX Modes 1, 2, 3 and 4 Any UNPLANNED release of Any UNPLANNED release of gaseous gaseous or liquid radioactivity to the or liquid radioactivity to the environment environment:> 2 times the ODCM :> 200 times the ODCM limits for:l: 15 limits for :l: 60 minutes Modes: All Damage to irradiated fuel or loss of water level that has or will result in the uncovering of irradiated fuel outside the reactor vessel Modes: All Unexpected increase in plant radiation Op. Modes: All Confirmed security event which indicates a potential degradation in the level of safety of the plant Modes: All Notification of HOSTILE ACTION Security event resulting in loss of within the PROTECTED AREA physical control of the facility

-.:-.. ~":-:.- --- _- _._-_. __ __

Modes: _._All.. _.. . ._ Modes: AI!

Notification of an airborne attack threat

.°e:_r:!<:.(}!'~:J!"_._._. ___ ._.. _.__ . _.._. __._....~

Other conditions existing which in the Other conditions existing which in judgment of the STEDISED warrant the judgment of the STEDJSED declaration of an Unusual Event warrant declaration of General Op. Modes: All Emergency Modes: All Loss of all offsite power to AC Power to AC emergency buses emergency buses for:> 15 minutes reduced to a single power source for Op. Modes: 1, 2, 3, 4 :> 15 minutes such that any additional single failure would result in station blackout MOdeE:_!.:..?d_4__ .__ --'---'-711'--.

ATWS and manual reactor shutdown from the MCB was NOT successful r- ----------~--------------~

_ _ _ _ _ _ _Modes

______ 1,_ _2._ _3_and

____ 4_ _ _ _ JI ER 1.1A Rev. 46

ER 1.1 Page 49 Rev. 48 Figure 1 Initiating Conditions and Emergency Action Levels SYSTEM MALFUNCTION Initiating Condition -- ALERT UNPLANNED loss of most or all safety system ~nunciation or indication in Control Room with either (1) a SIGNIFICANT TRANSIENT in progress, or (2) compensatory indicators are unavailable Operating Mode Applicability: 1, 2, 3 and 4 Emergency Action Levels:

a. UNPLANNED loss of approximately 75% or more ofUA annunciators for> 15 minutes.

OR

b. UNPLANNED loss of approximately 75% or more of Main Control Board indications for>

15 minutes.

OR

c. UNPLANNED loss of approximately 75% or more of radiation monitor indications for> 15 minutes.

AND

2. Either of the following: (a or b)

~ASIGNlFICANTTRANS~~

OR

b. Compensatory indications are unavailable.

NOTE SIGNIFICANT TRANSIENT is an UNPLANNED event involving one or more ofthe following: (1) automatic turbine runback >25% thermal reactor power, (2) electrical load rejection >25% full electrical load, (3) Reactor Trip, (4) Safety Injection Activation, or (5) thermal ower oscillations> I 0%

ER 1.1 Page 50 Rev. 48 Figure 1 Initiating Conditions and Emergency Action Levels SYSTEM MALFUNCTION Initiating Condition ** ALERT Power to AC emergency buses reduced to a single power source for> 15 minutes such that any additional single failure would result in station blackout Operating Mode Applicability: 1. 2, 3 and 4 Emergency Action Levels:

Note: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

At least one AC emergency bus is energized. Bus E5 AND/OR Bus E6.

AND

2. Only one power source is available to the energized buslbuses such that the loss of this source would result in a station blackout.

AND 15 minutes has elapsed with only one power source available.

NOTE There are six power sources to consider:

Newington 345 kV offsite power

Skobie Pond 345 kV offsite power

Tewksbury 345 kV offsite power

Emergency Diesel Generator A

Emergency Diesel Generator B

SEPS. For SEPS to be considered available, both SEPS diesel generator sets must be functional.

Seabrook Station State Notification Fact Sheet Time Notification Initiated: NH _ _ _ __ MA _ _ _ __

_ _ _ _ _ _ _ _ _ _ at Seabrook Station.

Name Title Time Declared: I lJJnusual Event I :

Time Terminated: :

IV' Alert I OR I

I I

II Site Area Emergency :I I* I

,______________________I_! _<?~~~~~I_~~_e!~~~~~_l

- _____________________ tI I

I Block 3: The emergency initiating condition is SALt orsAS Block 4: We recommend the fonowing protective actions:

1.(' None I] As follows New Hampshire Massach usetts ERPA Town Shelter Evacuate ERPA Town Shelter Evacuate A. Seabrook I J II B. Amesbury II I ]

Hampton Falls I ] II Salisbury [J I ]

C. Kensington I ] I] E. Merrimac [I I I S.Hampton I ] II Newburyport II I I Newbury (I I I D. Hampton I I II West Newbury [ J I I N. Hampton II II Beaches F. Brentwood [I II Evacuate E. Kingston II II ( J Seabrook Beach Exeter ( J (I I) Hampton Beach Newfields II II Newton I J II Close Kingston I J I) [ ] Parker River National Wildlife Refuge II Plum Island Beach G. Greenland I ) I] II Salisbury Beach Stratham II [ J Rye I J [ ) Potassium Iodide (General Emergency only)

NewCastle I ] [J [ ) Implement KI plans for the general public Portsmouth [I II Block 5: A radiological release ~ Has not occurred Has occurred and is continuing "J

I Occurred but has been terminated Block 6: Authorized by: _ _ _ _ _ _ _ _ __

STED I SED I RM Date Time Block 7: Acknowledge receipt oftbis message with your name.

New Hampshire: _--:::-:--_-::=-:-----::- _ _ _ __ Massachusetts: _--::-:--_-:-::--:--_ _ _ _ _ __

Name of Dispatcher Name of Dispatcher ER2.0B Rev. 31 Page I of 1

-# IF Is /}'lIlli/is ~4J eJrvd !/.<f1 sfoJ-cJ e~S- tJt1kJ S"tfJ /yea/!4r Ctbull~ &'1'10_0.

EMERGENCY INITIATING CONDITION MATRIX S

Modes 1, 2, 3 and 4 Any UNPLANNED release of gaseous Actual or projected offsite dose>

or liquid radioactivity to the environment 1,000 mRem TEDE or 5,000 mRem

> 200 times the ODCM limits for ~ 15 Thyroid CDE minutes Op. Modes: All Modes: All

---~----.- ...._-------_ ...-.... - .._....._--.----

Unexpected increase in plant radiation Op. Modes: All Natural and destructive phenomena affecting the PROTECTED AREA Modes: All FIRE within PROTECTED AREA boundary not extinguished within 15 minutes of detection Op. Modes: All Release of toxic, corrosive, Release of a toxic, corrosive, asphyxiant or flammable gases asphyxiant or flammable gas within or deemed detrimental to normal contiguous to a VITAL AREA affecting operation of the plant equipment required to maintain safe Op. Modes: All operations, or establish or maintain safe shutdown Modes: All -.-- -_._ ........... _._., .'-'-'._-

- ....".--- ....----.-...--."."... --.-.. c*.. ****....*--*

Confirmed security event which indicates a potential degradation in the level of safety of the plant Modes: All Notification of HOSTILE ACTION Security event resulting in loss within the PROTECTED AREA physical control of the facility Modes: All Modes: All Nnl',I,,,,,llrm of an airborne attack threat

. All Control Room evacuation has been initiated Op. Modes: All Other conditions existing ~ich in the Other conditions existing which in the Other conditions existing which in judgment of the STED/SED warrant judgment of the STED/SED warrant the judgment of the STED/SED declaration of an Unusual Event declaration of an Alert warrant declaration of General Op. Modes: All Op. Modes: All Emergency Modes: All Prolonged loss of both AC emergency buses Op. Modes: 1, 2, 3, 4 4

ATWS and manual reactor shutdown ATWS and all manual actions to from the MCB was successful shutdown the reactor were NOT Op. Modes: 1, 2, 3 successful, AND extreme challenge to Core Cooling or Heat Sink

. Modes: 1, 2 Inability to reach required shutdown within Technical Specification limits Modes: 1, 2, 3, 4 UNPLANNED loss of most or all safety system annunciation or indication In the Control Room for

> 15 minutes Op. Modes: 1, 2, 3, 4 r---

Modes 1, 2. 3 and 4 _.

ER 1.1A Rev. 46

SlmtAct\t ~iQ{N\~3 ~t 6: cJ ~

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()nfd CEfJi &eakly c!;;Bdr;;:a?4--o.o? ERl.1 Page51 Rev. 48 Figure 1 Initiating Conditions and Emergency Action Levels SYSTEM MALFUNCTION Initiating Condition -- SITE AREA EMERGENCY Loss of both AC emergency buses for> 15 minutes Operating Mode Applicability: 1,2,3 and 4 Emergency Action Levels:

Note: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the a licable time.

BOTH AC emergency buses E5 AND E6 are de-energized.

AND 15 minutes has elapsed with BOTH AC emergency buses E5 AND E6 de-energized.

NOTE For a bus to be considered energized from SEPS, both SEPS diesel generator sets must be functional.

Time Notification Initiated: NH _ _ _ __ MA _ _ _ __

Block 1: This is: _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ at Seabrook Station.

Name Title Block 2: : Time Declared: ( ) Unusual Event : : Time Terminated:

'S.::,

,__---y-;"'"!: ( ].Alert IY :

Site Area Emergency:

~ _____________________!_! _<?~~~~~I_~~_e~~~~~_l

£: C.,I

~---------------------.

I Block 3: The emergency initiating condition is _ _....~""-=..)::.-:.L Block 4: We recommend thej>lIowing protective actions:

M None 11 As follows New Hampshire Massach usetts ERPA Town Shelter Evacuate ERPA Town Shelter Evacuate A. Seabrook I ) I] B. Amesbury I] [ )

Hampton Falls [ ] ( ] Salisbury I] I J C. Kensington I ) I] E. Merrimac I J I )

S. Hampton I ) [J Newburyport (J ( )

Newbury I J [ J D. Hampton [ ) (I West Newbury (I (I N. Hampton I ] (J Beaches F. Brentwood [ J ( ] Evacuate E. Kingston [ ] ( ] ( ] Seabrook Beach Exeter I J I J (J Hampton Beach Newfields I ] I )

Newton ( I ( 1 Close Kingston I ) I J II Parker River National Wildlife Refuge IJ Plum Island Beach G. Greenland I J ( ] II Salisbury Beach Stratham I J (J Rye (J I J Potassium Iodide (General Emergency only)

NewCastle II rI I I Implement KI plans for the general public Portsmouth [ )

Block S: A radiological release II (J

Has not occurred Has occurred and is continuing I J Occurred but has been terminated Block 6: Authorized by: _ _= ___-:-:-::__-:--":_,_-

STED I SED I RM Date Time Block 7: Acknowledge receipt of this message with your name.

New Hampshire: _ ___::-:---:-::,_:__-:------ Massachusetts: _--,..,..-_...,.-_ _ _ _ _ _ __

Name of Dispatcher Name of Dispatcher ER2.0B Rev. 31 Page 1 of 1

SRO ADMIN JPM POST SCENARIO EMERGENCY PLAN CLASSIFICATION AND NOTIFICATION ANSWER KEY:

SIMULATOR EXAM #4*

~

FISSION PRODUCT BARRIER DEGRADATION MATRIX Modes 1, 2, 3 and 4 Fuel Clad Barrier Reactor Coolant System Barrier Containment Barrier SUb-CatEl9 0 ry Potential Loss Loss Potential Loss Potential Loss Loss RCS Integrity (P) Red Core Cooling (C) Orange Core Cooling (C) Red (wI RCS press> 300 psig)

1. CSF Status OR OR Containment (Z) Red I Emergency Coolant Recirculation (F) Orange Heat Sink (H) Red

a. Core Exit TCs ;:: 1,100° F AND

b. FR-C.1 not effective within 15 minutes.

QR

2. Core Exit TCs Core Exit TCs ?: 725 0 F Core Exit TCs ?: 1,100° F a. Core Exit TCs ?: 725 0 F AND

b. RVLlS full range level $ 40%

AND RVLlS dynamic head

$ 44% with 4 RCPs running

s 30% with 3 RCPs running

3. Reactor Vessel Level * $ 20% with 2 RCPs running

s 13% with 1 RCP running RVLlS full range level

s 40% with no RCP runnin

4. RCS Activity

5. RCS Leakage of containment OR

6. SIG Rupture or Fault Primary-to-Secondary leak rate> 10 gpm with unisolable steam release from affected S/G to the environment Rapid unexplained pressure decrease following initial increase

7. Containment Pressure OR Containment pressure response not consistent with LOCA conditions

8. Containment Radiation Monitor

9. Containment Isolation Valves

10. STED/SED I

of the STED/SED Any condition in the opinion of the STED/SED indicates a Potential Loss of the Fuel Clad that indicates a Loss of the Fuel Clad Barrier Any condition in the that indicates a Potential Loss of the RCS Any condition in the opinion of the STED/SED that indicates a Loss of the RCS Barrier Any condition in the opinion of the STED/SED that indicates a Loss of the Containment Judgment

.:::r- Barrier (consider inability to monitor barrier). (consider inability to monitor barrier). Barrier (consider inability to monitor barrier). (consider inability to monitor barrier). Barrier (consider inability to monitor barrier) .

~ Enter a ,..h.,,,l<m,,,rl< for each "Potential Loss" or "Loss" noted above. When all checkmarks have been

~<""\J SJ

\;)~

.-k

-i~

\fJ ER 1.1C Rev. 46

Seabrook Station State Notification Fact Sheet Block 4: We recommend the following protective actions:

~ None [J As follows New Hampshire Massach usetts ERPA Town Shelter Evacuate ERPA Town Shelter Evacuate A. Seabrook I J (J B. Amesbury I ] [I Hampton Falls II ( ) Salisbury I) I I C. Kensington I I I] E. Merrimac I I ( I S. Hampton I ] [I Newburyport ( ] ( I Newbury [ ] I )

D. Hampton [I I ] West Newbury I ] ( J N. Hampton I ] I]

Beaches F. Brentwood I ] IJ Evacuate E. Kingston ( ] I] I] Seabrook Beach Exeter (I ( ) (I Hampton Beach Newfields I ] I )

Newton [ ] [1 Close Kingston ( ) I] II Parker River National Wildlife Refuge

[I Plum Island Beach G. Greenland [ I (J [ ] Salisbury Beach Stratham I ) I ]

Rye ( ] I] Potassium Iodide (General Emergency only)

NewCastle [ I I ] [ I Implement KI plans for the general public Portsmouth [I I)

~

Block 5: A radiological release Has not occurred Has occurred and is continuing

[ ] Occurred but has been terminated Block 6: Authorized by: ----:==-:-:--:-=-:-=-:--c---

STED I SED I RM Date Time Block 7: Acknowledge receipt of this message with your name.

New Hampshire: _---:~-~---:-:------_ Massachusetts: _----:-.,,----___- - - - - - -

Name ofDispatcber Name of Dispatcher ER2.0B Rev. 31 Page I of 1

JOB PERFORMANCE MEASURE Sa Rev. 1 FR-H.1 BLEED AND FEED Student Name:

- - - - - - - - - - - - LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: - -

- - - - - - - - - - - - - - DATE: -------

APPROVED BY: - - - - - - - - - - - - - - - - DATE: - - - - -

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET 1.0 Task Number and

Description:

Position: RO 0060401501 Monitor The Safety Injection System When Activated 0060501201 Feed And Bleed The RCS During Inadequate Core Cooling

2.0 Conditions

A. A reactor trip has occurred.

B. A loss of all feedwater capability has forced a transition to FR-H.1, Response to Loss of Secondary Heat Sink.

3.0 Standards

Initiate bleed and feed per FR-H.1, Response To Loss Of Secondary Heat Sink.

4.0 Student Materials:

Copy of the Tear-Off Sheet FR-H.1, Response to Loss Of Secondary Heat Sink, Rev. 34.

5.0 Limitations on performance:

Perform all steps. Verbalize all actions to the evaluator.

Even if requested, no Peer Checks will be provided during the JPM.

6.0

References:

Procedures:

FR-H.1, Response To Loss Of Secondary Heat Sink.

Sys KA Description Value RO/SRO EPE 074 EK3.04 Tripping RCPs. 3.9/4.2 EPE 074 EK3.05 Activating HPJ system. 4.2/4.5 EPE 074 EK3.11 Guidance contained in EOP for inadequate core 4.0/4.4 cooling Sa Page 2 of 8

JOB PERFORMANCE WORKSHEET

7.0 Setting

If performed as a pair with .JPM Sh, Reset to IC # 81 or IC #382.

For stand alone, reset the simulator to IC #382 or any 100% IC which contains the following:

1. Initialize to the 100% IC and place simulator in RUN.

2. Insert malfunctions mfRPS001 and mfRPS002 failure of automatic reactor trip Train A & B.

3. In panel graphics section PCF07 insert override for RC-PCV-456B control switch to AUTO.

4. Insert remote function rmvMSV129 Value=O

5. Insert malfunctions mfFW039 and mfFW041 FW-P113 trip (faulty 86 device) Bus 4&5.

6. Insert component remote function bkFW37B RF: rack-out, Rack out breaker for FW-P37B and mvFW347 RF: open breaker to deenergize breaker for FW-V347 EFW mini-flow valve. Place FW-P37B control switch in PTL

7. Insert malfunctions mfFW038 and mfFW054 Delay 10 seconds to trip both MFPs on low LO pressure.

8. Complete all actions of FR-S.1 and when S/G WR levels <30% trip the reactor.

9. Place the simulator in FREEZE.

Place simulator in RUN (only as long as needed) to ensure all alarms are acknowledged prior to start of JPM.

Ensure 3 S/G WR levels <30%, conditions for immediate Bleed and Feed exist.

Place danger tags on the motor-driven EFW pump and mini-flow valve control switches.

8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

15 minutes 10.0 Directions to the Student(s):

1. You are the Secondary Operator.

2. The motor-driven EFW pump is tagged out.

3. A transition from FR-S.1 to FR-H.1, Response To Loss Of Secondary Heat Sink, has occurred.

4. You are the only Operator in the control room and you must perform all control board operations.

11.0 Initiating Cue:

"Implement FR* H.1."

Sa Page 3 of 8

PERFORMANCE CHECKLIST D::::Discuss ELEMENT/STEP STANDARD EVALUATION P::::Perform '"denotes a '"denotes critical S::::Simulate critical step standard SAT UNSAT NOTE: Ensure that student is ready to begin the JPM before placing simulator in run.

1. 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".

2. P Check If Secondary Heat Sink Is Required:

RCS pressure - GREATER

Checks RCS pressure - GREATER THAN ANY THAN ANY NON-FAULTED SG NON-FAULTED SG PRESSURE PRESSURE

RCS hot leg temperature

Checks RCS hot leg temperature GREATER THAN 350°F GREATER THAN 350°F

3. P Check CCP Status - AT Checks CCP Status - AT LEAST ONE LEAST ONE AVAILABLE AVAILABLE

4. P Student identifies need for Identifies 3 SG wide range levels <30%.

RCS bleed and feed as described in Step 3, Caution.

5. P Check RCP status:

All RCPs - STOPPED.

Verifies RCPs all running

(RNO) Stop all RCPs. *

Stops all RCPs

6. P Actuate SI. *Actuates SI

7. P Verifies RCS Feed Path:

a. Check pump status: a. Verifies at least one CCP or SI pump

CCPs - AT LEAST running.

ONE RUNNING

-OR

SI pumps - AT LEAST ONE RUNNING

b. Check valve alignment for b. Verifies proper valve alignment for operating pumps operating pumps on both status PROPER EMERGENCY panels:

ALIGNMENT ON STATUS PANEL

TRAIN A - Cold Leg Sa Page 4 of 8

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT Injection

TRAIN B - Cold Leg Injection

8. P Establish RCS Bleed Path: Establishes RCS bleed path:

a. Verify power to PZR PORV a. Verifies power to PORV block valves block valves - AVAILABLE available.

b. Verify PZR PORV block b. Verifies PORV block valves both open.

valves - BOTH OPEN

c. Open both PZR PORVs

c. Performs the following:

Opens PORV-455A.

. Attempts to open PORV-455B.

9. P Verify Adequate RCS Bleed Path:

PORVs - BOTH OPEN

Verifies A PORV is open.

Recognizes B PORV is closed.

PZR PORV block valves

Verifies both block valves open BOTH OPEN

10 P Perform the following:

a. Open reactor head vent a. Opens reactor head vents isolations:

isolations:

RC-FV-2881 *. RC-FV-2881

RC-V323 *. RC-V323 CUE: "The JPM is complete."

11. Stop time _ _ _ __ Time to complete the task s 15 minutes.

Evaluator calculates the time to complete the task.

12. Obtain from student:

Tear Off Sheets and any other Sa Page 5 of 8

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT training materials used in the performance of the JPM Sa Page 6 of 8

PERFORMANCE

SUMMARY

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

Sa Page 7 of 8

TEAR OFF SHEET FOR JPM Sa Directions to the Student:

1. You are the Secondary Operator.

2. The motor-driven EFW pump is tagged out.

3. A transition from FR-S.1 to FR-H.1, Response To Loss Of Secondary Heat Sink, has occurred.

4. You are the only Operator in the control room and you must perform all control board operations.

Initiating Cue:

Implement FR-H.1.

Sa Page 8 of 8

JOB PERFORMANCE MEASURE JPM Sb Rev. 1 RECOVER FROM A CRFRM ACTUATION Student Name:

LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: DATE:

APPROVED BY: DATE:

=TRA~IN~IN~G~S~U=P=ER~V~IS~O~R----- --------

JOB PERFORMANCE WORKSHEET 1.0 Task Number and

Description:

Position: RO 1050400301 Remove the control room ventilation system from the filter recirculation mode.

2.0 Conditions

A. The plant is at 100% power.

B. I&C was performing maintenance on control room east air intake rad monitor RM 6506A2. It was in HIGH alarm due to this maintenance procedure. The appropriate paperwork and Tech. Specs. were in place for performance of this maintenance.

C. A spurious RDMS HIGH radiation alarm was subsequently received on control room east air intake rad monitor RM-6506A 1. This resulted in an "A" train CRFRM ESF actuation.

D. F7009, CTL RM MAKEUP AIR FLTR RECIRC MODE, is in alarm.

E. While the US was executing OS1252.02, AIRBORNE HIGH RADIATION, based on the HIGH rad signal on RM-6506A1, I&C reported that the HIGH rad signals on RM 6506A 1 & RM-6506A2 were due to the maintenance activities. After consultation with HP, the US has determined that the CRFRM Actuation was spurious.

F. The US is now executing step 11 of OS 1223.01, LOSS OF CONTROL ROOM VENTILATION OR AIR CONDITIONING.

3.0 Standards

A. Secure from the CRFRM per OS1023.51, CONTROL ROOM VENTILATION AND AIR CONDITIONING SYSTEM OPERATION.

B. Align control room ventilation to the normal makeup mode per OS1023.51 , CR VENTILATION AND AIR CONDITIONING SYSTEM OPERATION.

4.0 Student Materials:

Copy of the Tear-Off Sheet.

OS 1023.51, Control Room Ventilation and Air Conditioning System Operation, Rev 15 Pages 1-5 and 39-40.

5.0 Limitations on performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator.

JPM Sb Page 2 of 9

JOB PERFORMANCE WORKSHEET 6.0

References:

Procedures 051223.01, Loss of Control Room Ventilation or Air Conditioning.

051023.51, Control Room Ventilation and Air Conditioning System Operation.

Technical Specifications 3.3.3.1, RAD MONITORING FOR PLANT OPS.

3.7.6, CR AREA VENTILATION.

Sys KA Description Value RO/SRO 013 K1.13 HVAC. 2.8/3.1 013 K1.18 Premature Reset of ESF actuation. 3.7/4.1 013 K4.10 Safeguards equip control reset. 3.3/3.7 013 A3.02 Operation and actuated equipment. 4.1/4.2 2.1 2.1.30 Ability to locate and operate components. 4.3/4.4 2.1 2.1.23 Ability to perform integrated specific plant 4.4/4.0 procedures all modes.

072 K1.04 Control Room Ventilation. 3.3/3.5

7.0 Setting

If performed as a pair with JPM Sd, Reset to IC # 82.

For stand alone, reset the simulator to IC #398 or any 100% IC which contains the following:

1. Initialize to the 100% IC

2. Train A of normal CBA running and Train B of normal CBA in standby per OS1023.51 , CR VENTILATION AND AIR CONDITIONING SYSTEM Operation.

3. Insert malfunctions mfRM014 RM-6506A-1 Final Value=200and mfRM015 RM 6506A-2 Final Value=200 to actuate HIHI alarm

4. Place the simulator in RUN.

5. Ensure this 2 of 2 "A" train CRFRM Signal resulted in the following CBA line-up:

CBA-FN-27A is OFF.

CBA-DP-53A remains OPEN (closes on liB" train CRFRM signal).

CBA-FN-27B remains OFF.

CBA-DP-53B remains CLOSED.

CBA-DP-27A OPENS and CBA-FN-16A STARTS.

CBA-DP-27B remains CLOSED and CBA-FN-16B remains OFF.

CBA-DP-28 shuts.

CBA-FN-15 is tripped.

CBA-DP-1058 remains OPEN

6. Delete the high rad malfunctions on RM-6506A 1 & RM-6506A2. Acknowledge CP-295 to ensure rad monitors are "green".

7. Override the Green Light for CBA-DP-28 to ON.

8. Place the simulator in FREEZE.

Place the simulator in RUN. Acknowledge all alarms.

,.rPM Sb Page 3 of 9

JOB PERFORMANCE WORKSHEET 8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

25 minutes 10.0 Directions to the Student(s):

1. You are the Primary Operator.

2. The US is executing step 11 of 051223.01, LOSS OF CONTROL ROOM VENTILATION OR AIR CONDITIONING.

11.0 Initiating Cue:

Shutdown the "A" train of control room ventilation from filter recirculation mode and place the "A" train of the control room normal makeup and ventilation supply system in service per OS1 023.51. All procedural Prerequisites have been completed.

JPM Sb Page 4 of 9

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

1. Start time _ _ _ __ Initiating cue read.

NOTE: Student should use OS1023.51 , sections 4.17 and 4.18.

2. P CHECK/PLACE the following Checks the following switches in auto:

control switches to AUTO:

CR MAKE-UP AIR

CR MAKE-UP AIR TRAIN A FILTER TRAIN A FILTER RECIRC MODE.

RECIRC MODE

CR MAKE-UP AIR

CR MAKE-UP AIR TRAIN B FILTER TRAIN B FILTER RECIRC MODE.

RECIRCMODE NOTE: Both control switches should be in AUTO.

NOTE: When CBA-DP-27A goes full closed, CBA-FN-16A stops. When CBA-FN-16A stops, the CRFRM actuation signal resets. If the student does not wait until CBA-DP-27A is closed, which in turn stops CBA-FN-16A, the "A" train CRFRM actuation will reinitiate, causing CBA-DP-27A to re-open.

3. P PLACE the following control Performs the following:

switches to STOP, and HOLD until the exhaust damper CLOSES:

CBA-DP-27A EMER MU *. Positions and holds CBA-DP-27A FLTR DAMPER control switch in STOP until the damper closes

CBA-DP-27B EMER MU

Observes CBA-DP-27B already closed.

FLTR DAMPER (Placing switch to close not required)

CUE: US to student: "Use OS1023.51, section 4.18 to place Train A CSA Normal Ventilation In Service.".

4. CHECK CLOSED/CLOSE Verifies CBA-DP-53B closed.

CBS-DP-53B, CR MU AIR DAMPER.

JPMSb Page 5 of 9

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

5. P CHECK OPEN/OPEN CBA Verifies open CBA-DP-53A DP-53A, CR MU AIR DAMPER

6. P START CBA-FN-27 A, Control *Starts CBA-FN-27A.

Room makeup air fan NOTE: CTL RM STATIC PRESS CONTROLLER is on CP-23. CP-23 is not simulated.

CUE: When the student identifies actions for the CTL RM STATIC PRESS CONTROLLER on CP-23, Evaluator to student, "CTL RM STATIC PRESS CONTROLLER is in AUTO and set at 0.3 inches."

7. S At CP-23, CHECK or PLACE Checks the CTL RM STATIC PRESS the CTL RM STATIC PRESS CONTROLLER in auto set at 0.3 inches.

CONTROLLER to AUTO set at 0.3 inches.

8. P CHECK OPEN/OPEN Verifies CBA-DP-1058 is open.

CBA-DP-1058, Control Room exhaust isolation damper.

9. P CHECK/PLACE the control Verifies CBA-FN-15 switch is in auto.

switch for CBA-FN-15, Control Room exhaust fan in AUTO CUE: When the student identifies actions for the CTL RM STATIC PRESS CONTROLLER on CP-23, Evaluator to student, "CTL RM STATIC PRESS CONTROLLER is in auto with input pressure indication at 0.3 inches WC."

10. S At CP-23, CHECK or PLACE Checks the CTL RM STATIC PRESS the CTL RM STATIC PRESS CONTROLLER in auto set at 0.3 inches.

COI\JTROLLER to AUTO set at 0.3 inches.

11. P PLACE and MAINTAIN the *Places CBA-DP-28 to open until control switch for CBA-DP-28, intermediate is indicated, and then releases Control Room exhaust to auto.

modulate damper to OPEN until intermediate position of the damper is indicated, then allow the switch to spring return to AUTO JPMSb Page 6 of 9

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform *denotes a *denotes critical S=Simulate critical step standard SAT UNSAT

12. P VERIFY CBA-FN-15, Control Verifies CBA-FN-15 starts Room exhaust fan STARTS.

13. S VERIFY CBA-DP-28, Control Verifies CBA-DP-28 modulates to control Room exhaust modulate pressure.

damper MODULATES to control pressure.

CUE: (If required) Evaluator to student, "CTL RM STATIC PRESS CONTROLLER input pressure indication is 0.3 inches WC and stable. II CUE: "The JPM is complete."

14. Stop time _ _ _ __ Time to complete the task s;; 25 minutes.

Evaluator calculates the time to complete the task.

15. Obtain from student:

Tear Off Sheets and any other training materials used in the performance of the JPM JPM Sb Page 7 of 9

PERFORMANCE

SUMMARY

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

JPM Sb Page 8 of 9

TEAR OFF SHEET FOR JPM Sb Directions to the Student:

1. You are the Primary Operator.

2. The US is executing step 11 of OS1223.01, LOSS OF CONTROL ROOM VENTILATION OR AIR CONDITIONING.

Initiating Cue:

Shutdown the "A" train of control room ventilation from filter recirculation mode and place the "A" train of the control room normal makeup and ventilation supply system in service per 051023.51. All procedural Prerequisites have been completed.

Page 9 of 9

JOB PERFORMANCE MEASURE JPM New Sc Rev. 1 Loss of Containment Instrument Air Student Name: _ _ _ _ _ _ _ _ _ _ _ LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL "rHAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY:

- - - - - - - - - - - DATE: -----

APPROVED BY: DATE:

- - -TRAINING

- - -SUPERVISOR

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

denotes a critical step

denotes a critical step SAT UNSAT

1. Task Number and

Description:

NA

2. Conditions:

A. The plant is at about 95% power.

B. SA-C-4B is tagged out of service for motor replacement.

3. Standards:

Restore a containment instrument air compressor to service.

4. Student Materials:

Copy of the Tear-Off sheet.

ON 1242.02, Rev 11

5. Limitations on performance:

Simulate all steps. Verbalize all actions to the evaluator.

Even if requested, no Peer Checks will be provided during the JPM.

6.

References:

Procedures:

ON1242.02, Loss Of Containment Instrument Air Sys KA Description Value RO/SRO 078 K1.03 Knowledge of the physical connections and/or 3.3/3.4 cause-effect relationships between the lAS and Containment Air 078 K3.01 Knowledge of the effect that a loss or malfunction of 3.1/3.4 the lAS will have on the Containment air syatem 078 A3.012 Ability to mnonitor automatic operation of the lAS, 3.1/3.2 including Air pressure I Page 20f7

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

denotes a critical step

denotes a critical step SATUNSAT

7. Setting:

If performed as a pair with JPM Sg. Reset the simulator to IC# 84.

For stand alone performance, reset the simulator to IC #30 or any IC which contains the following:

A. Initialize to any 100% IC and place the simulator in RUN.

B. Reduce power to 95%

C. Place SA-C-4B control switch to OFF and Tag D. Rack out the breaker for SA-C-4B as Follows:

SELECT Component Remote Functions SELECT SERVICE AIR (Component)

DOUBLE CLICK cSAC4B, SA Compressor 4b 460V MCC E631 D95 SELECT RACKOUT INSERT E. Place the simulator in FREEZE.

8. Safety Considerations:

None.

9. Approximate Completion Time:

10 mins

10. Directions to the Student:

1. You are the Secondary Operator

2. SA-C-4B is tagged out due to a motor replacement.

11. Initiating Cue:

"Respond to your indications."

JPMSc Page 3 of 7

DATA SHEET FORJPM Sc 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".

1. Start time _ _ _ __ Initiating cue read Simulator Operator:

Trip SA-C-4A as Follows:

SELECT Component Remote Functions SELECT SERVICE AIR (Component)

DOUBLE CLICK cSAC4A, SA Compressor 4A 460V MCC E531 093 SELECT RACKOUT INSERT

2 P Respond to D-Point Alarm 05068. Refers to 05068 VPRO

Verify Cont Air Compressor A

Verifies Cont Air Compressor tripped at MCB A tripped at MCB

Check Contm 1A hdr press on

Checks Contm 1A hdr press IA-PI-8024 at MCB or on station on IA-PI-8024 at MCB or on computer (A09??). station computer (A09??).

CUE: When directed to cycle breaker, respond: "Understand, cycle the breaker for SA-C-4A at MCC 531, Node <093>." Verify that the control switch for SA-C-4A is in OFF.

NOTE: If the breaker is cycled using the abnormal procedure, this VPRO step is not critical.

Dispatch an operator to ESS SWGR to reset compressor by

. Dispatches an operator to ESS-SWGR to reset cycling the breaker at MCC-531 compressor by cycling the

<093> breaker at MCC-531 <093>

Refer to ON1242.02, Loss Of

Refers to ON1242.02, Loss Containment Instrument Air. Of Containment Instrument Air.

3. P Check Containment Instrument Air System:

NOTE: The performance of either bulleted step below will allow transition to the RNO.

Containment instrument air

Checks Containment pressure - GREATER THAN instrument air pressure 95 PSIG AND INCREASING GREATER THAN 95 PSIG AND INCREASING, answer is; No OR JPMSc Page 4 of?

OATASHEETFORJPM Sc

Containment instrument air

Checks Containment compressors - BOTH instrument air compressors RUNNING BOTH RUNNING, answer is; None running.

4. P Perform The following: Student refers to Step 1 RNO

a. Cross connect containment *a. Opens IA-V530 instrument air system with instrument air by opening the following valve:

IA-V530 NOTE: The following step is a long-term action and is met by determining instrumentation/MPCS points that will be used.

Monitor containment

Monitors containment pressure pressure for instrument air for instrument air header header leakage. leakage.

CUE: When directed to cycle breaker, respond: "Understand, cycle the breaker for SA-C-4A at MCC 531, Node <093>." Verify that the control switch for SA-C-4A is in OFF.

NOTE: If the breaker was cycled using the VPRO, this step should be already completed.

5. P IF a compressor has tripped, reset * *Oirects NSO to cycle the the compressor by cycling the supply breaker for SAC-4A at supply breaker: MCC 531, Node <093>

SAC-4A MCC-531, Node <093>

Simulator Operator: After IA-V530 has been opened and verification that the control switch is in off: Oelete Component Remote Function: csAC4A SA Compressor 4a 460V MCC E531 093. Notify the candidate: "The breaker for SA-C-4A has been cycled open and closed."

IF a compressor has tripped, reset

Recognizes that SAC-4B is the compressor by cycling the tagged out. Breaker cannot be supply breaker: cycled.

SAC-4B MCC-631 ,Node <095>

NOTE: With low IA header pressure indicated, the compressor will start when the control switch is taken to the AUTO position.

Manually restart compressor. * *Places the SA-C-4A control switch to AUTO.

JPMSc Page 5 of 7

DATA SHEET FOR JPM Sc CUE: "The JPM is complete."

6. Stop time _ _ _ __ Time to complete the task s 10 minutes.

Evaluator calculates the time to complete the task.

7. Obtain from student:

Tear Off Sheets and any other training materials used in the performance of the JPM JPMSc Page 6 of7

PERFORMANCE

SUMMARY

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

JPM Sc Page 7 of 7

TEAR OFF SHEET FOR JPM Sc Directions to the Student:

1. You are the Secondary Operator

2. SA-CAB is tagged out due to a motor replacement.

Initiating Cue:

Respond to your indications.

Page 8 of 8

JOB PERFORMANCE MEASURE JPM Sd Rev. 1 TRANSFER SERVICE WATER FROM THE COOLING TOWER TO THE OCEAN Student Name:

- - - - - - - - - - - LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: _ _ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ __

APPROVED BY: _ _--=--~___=--=--------:~~--- DATE:

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET

1. Task Number and Description Position RO SBK 0760103401 Switch From SW To Cooling Tower Operation

2. Conditions:

A. The plant is operating at 100% power.

B. On line maintenance/retests are complete on the Service Water system Train A pump house valves.

C. The SM has directed that Train A Service Water be transferred back to the ocean from the cooling tower.

D. All pre-starts are complete for the A" Service Water pump (SW-P-41 A).

U

3. Standards:

Perform steps of OS1016.05 to restore Service Water to the ocean and respond to events as warranted.

4. Student Materials:

Copy of Tear Off Sheet.

Copy of OS1016.05 Service Water Cooling Tower Operation, Rev. 10, Section 2 and 3 pages 5-9, Section 4.4 pages 26-28, Figures 1-5 pages 55-61, and Form L.

001-05 Pump Pre-start guidelines SW-P-41A page 49, Rev. 00

5. Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

Even if requested no Peer Checks will be provided during the JPM.

6.

References:

Procedures:

OS1016.05 Service Water Cooling Tower Operation Value Sys KA Description RO/SRO 076 A2.01 Ability to predict the impacts of loss of SW 3.5/3.7 and use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

076 K3.01 Knowledge of the effect that a loss of SW 3.4/3.6 will have on closed cooling water. i

,JPM Sd Page 2 of 8

JOB PERFORMANCE WORKSHEET

7. Setting:

If performed as a pair with JPM Sb, Reset to IC # 82.

For stand alone, Reset the simulator to IC #363 or any 100% IC which contains the following:

A. Initialize to any 100% IC and place the simulator in RUN.

B. Place Train A Service Water on the cooling tower per OS1016.05, Service Water Cooling Tower Operation.

C. Insert component malfunction cSWV22 460V MCC E514 CR7 fail closed.

D. Place SW -P-41 C control switch in PTL.

E. Insert component remote function cSWP41 C 4.16KV Bus E5 AQ4 RF:rackout.

F. Insert component remote function cSWV22 460V MCC E514 CR7 RF:open breaker.

G. Insert malfunction mfSW001 SW-P-41A DC trip.

Place the simulator in RUN. Acknowledge all alarms. Place tags on SW-P-41 C and SW V-22 control switches.

8. Safety Considerations:

None.

9. Approximate Completion Time:

20 minutes

10. Directions To The Student:

1. You are the Secondary Operator.

2. All prerequisites, limitations, and pre-starts for SW-P-41A are complete.

11. Initiating Cue:

Transfer Train A Service Water from the Cooling Tower to the ocean using OS1016.05, section 4.4.

JPM Sd Page 3 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT

1. 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."

NOTE: Student may re-verify prerequisites, precautions & limitations and pre-starts.

CUE: If student asks, state: "The fire protection system has not been used to fill the cooling tower, no chemistry sampling is required."

CUE: Inform student: "Form L, Cooling Tower Flush NPDES Tracking Sheet has been recorded and tracked by US."

NOTE: Student may put up color graphic on the MPCS for Service water.

2. P Check SW Train B is aligned to the Checks SW Train B is aligned to the ocean. ocean.

3 P Record initial Cooling tower level from Records initial Cooling tower level either SW-Ll-6139 or A1537 and from either SW-Ll-6139 or A1537 and record on Form L. record on Form L.

CUE: When student attempts to determine the position of SW-V-44, provide cue, "SW-V-44 is open."

4. P If SW-V-44, SW isolation from the Investigates the position of SW-V-44 intake structure is closed, perform the following:

CUE: If the student begins to perform pump pre-start checks, provide cue, "All pre-starts are complete."

CUE: If the student inquires about the prestart checklist requiring SW-V-20, 34, and 54 in a different position, respond: "SW-V-20, 34, and 54 are repositioned by the performance of the procedure, continue with the procedure."

5. P Perform SW ocean pump pre-starts Inquires / Determines that the control as determined by the US. room pre-start checks are complete.

6. P Open SW-V-20, SW Train A to *Opens SW-V-20, SW Train A to discharge structure. discharge structure.

JPM Sd Page 4 of 8

PERFORMANCE CHECKLIST D=Oiscuss ELEMENTISTEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SATUNSAT

7. P Close SW-V-34, SW Train A return to *Closes SW-V-34, SW Train A return cooling tower. to cooling tower.

8. P Simultaneously place and hold control *Simultaneously manipulate switches switch for SW-V54, cooling tower until valves reposition as follows:

pump A discharge to throttle close

SW-V-54 control switch to throttle and control switch for SW-V-56, close cooling tower Train A spray header

SW-V-56 control switch to open test to open until valves reposition CUE: If requested to make a plant announcement, inform the student; "The announcement for starting Service Water pump 41A has been made."

CUE: If informed that the cooling tower basin low level alarm has been received, inform student; "Copy, low cooling tower basin level. I will dispatch a field operator to initiate fill of the cooling tower basin."

9. P Start the desired Train A ocean SW *Starts SW-P-41A.

pump.

CUE: If student informs US that SW-P41A tripped, respond; "What is your recommendation to proceed"

10. P Verify the selected SW pump Recognizes SW-V-2 not open and discharge valve opens. SW-P-41A tripped NOTE: The student may use VPRO for 05513 to initiate a TA and open SW-V-54 or Abnormal Procedure OS1216.11, Degraded Ultimate Heat Sink step 8 RNO to open SW-V-54.

11. P In accordance with caution prior to *Re-opens SW-V-54 step 4.4.9:

Reopen SW-V-54 CUE: "The JPM is complete."

12. Stop time _ _ __ Time to complete task ~ 20 minutes Evaluator calculates time to complete task

13. Obtain from student:

"IPMSd Page 5 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT Tear Off sheets and any other training materials used in performance of this JPM.

JPM Sd Page 6 of 8

PERFORMANCE

SUMMARY

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.

JPMSd Page 7 of 8

TEAR OFF SHEET FOR JPM Sd Directions To The Student:

1. You are the Secondary Operator.

2. All prerequisites, limitations, and pre-starts for SW-P-41A are complete.

Initiating Cue:

Transfer Train A Service Water from the Cooling Tower to the ocean using 051016.05, section 4.4.

80f8

JOB PERFORMANCE MEASURE JPM Se Rev. 1 LOWER SI ACCUMULATOR LEVEL Student Name:

LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ __

APPROVED BY: _ _~=_:_:_::_~~-:-::::-:::::-:~~--- DATE: _ _ _ _ _ __

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET 1.0 Task Number and Description Position RO SBK 0060100201 Monitor The Safety Injection System

2.0 Conditions

2.1 The "Au Accumulator Level has increased to above the Technical Specification Limit due to containment / system temperature increase.

3.0 Standards

Decrease the "Au Accumulator level to clear the High Level Alarm.

4.0 Student Materials:

Copy of Tear Off Sheet.

Copy of OS1005.05 Safety Injection System Operation Rev. 12, Pages 32-34.

5.0 Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

Even if requested no Peer Checks will be provided during the JPM.

6.0

References:

Procedures:

OS1005.05 Safety Injection System Operation Technical Specifications:

3.5.1.1 ECCS Accumulators - Hot Standby. Startup. and Power Operation Drawings

1-SI-B20455 Safety Injection System Value Sys KA i Description RO/SRO 006 A1.13 Ability to predict and/or monitor (to 3.5/3.7 prevent exceeding design basis limits) accumulator pressure, level, boron concentration.

I JPM Se Page 2 of 8

JOB PERFORMANCE WORKSHEET

7.0 Setting

If performed as a pair with JPM Sf, Reset to IC # 83.

For stand alone, Reset the simulator to any 100%IC which contains the following:

A. Initialize to an IC at 100% power.

B. Raise "A" Accumulator level to > 6473 Gallons. Verify F5498, SI Accumulator Level High alarm is in.

C. Use "GO ACCUMS" on MPCS to view Accumulator level and pressure "A" points.

D. Verify "A" Accumulator pressure is 640- 660 psig., or adjust as necessary.

E. Using Safety Injection Local Panel, OPEN SI-V-67.

F. Freeze the simulator.

8.0 Safety Considerations:

None.

9.0 Approximate Completion Time:

20 minutes 10.0 Directions To The Student:

1. You are the Primary Operator

2. You are going to the lower the "An Accumulator level.

3. All applicable prerequisites of OS1005.05 Safety Injection System Operation are complete.

4. The Primary NSO is standing by to support local valve manipulations.

11.0 Initiating Cue:

Lower the 'A' Accumulator level to clear the high level alarm, using 051005.05, Safety Injection System Operation .

. .I PMSe Page 3 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT

1. 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."

CUE: If the student inquires about consideration for initially raising accumulator pressure, respond; "Pressure appears to be sufficient, continue with lowering level and monitor pressure as appropriate. "

CUE: If the student exhibits inability to locate the specific accumulator MPCS points, provide the direction to use Group Display "GD ACCUIVIS" or Single Value Display SVD A0413.

2. P If desired, PRESSURIZE the Determines that Accumulator accumulator to be drained per Section pressure is sufficient to support the 4.4, Pressurizing an Accumulator. drain-down evolution.

CUE: If student requests leak testing status, respond, "Check valve leak testing is not in progress."

3. P VERIFY that check valve leak testing VERIFIES that check valve leak is not in progress. testing is not in progress.

4. P CHECK CLOSED/CLOSE SI-V-157, CHECKS CLOSED SI-V-157, SI --

SI accumulator fill. accumulator fill.

5. P CHECK CLOSED/CLOSE SI-V-62, CHECKS CLOSED SI-V-62, test line test line header isolation ORC. header isolation ORC.

6 P CHECK CLOSED/CLOSE SI-V-131, CHECKS CLOSED SI-V-131, test --

test iso for SI cold legs 1,2,3,4 iso for 81 cold legs 1,2,3,4.

checks.

CUE: If the student indicates that they would use an electronic database to determine valve locations for the following step, respond; "The Primary NSO is standing by to perform local actions for SI-V-67 and 69."

7. P ALIGN the SI test header to the PDT by performing the following:

CUE: When the Primary NSO is directed to check open/open SI-V-67, provide repeat-back and respond:

"SI-V-67 has been verified open."

JPM Se Page 4 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT

CHECK OPEN/OPEN SI-V-67,

Directs local actions to CHECK isolation for PDT and boron OPEN/OPEN SI-V-67, isolation for recovery storage tanks 66A and PDT and boron recovery storage 66B. tanks 66A and 66B.

CUE: When the Primary NSO is directed to check closed/close SIN-69, provide repeat-back and respond:

"SI-V-69 is closed."

CHECK CLOSED/CLOSE

Directs local actions to CHECK SI-V-69, test line isolation for CLOSED/CLOSE SIN-69, test RWST. line isolation for RWST.

CUE: If student inquires respond, "51 test header pressure will not be monitored at this time."

8. P If SI test line pressure is to be Inquires / determines that SI test line monitored, then UNLOCK and OPEN pressure will not be monitored.

SI-V-61, SI-PI-929/PT-2491 isolation.

9 P OPEN SI-V-70, testline header *OPENS SI-V-70, test line header isolation IRC. isolation IRC.

10 P OPEN the valve for the accumulator *OPENS SI-V-15, accumulator A drain _ _

to be drained: / fill isolation.

SI-V-15, accumulator A drain/fill isolation NOTE: Accumulator level Tech. Spec. limits are 6121 gallons to 6596 gallons, with an alarm setpoint of 6473 gallons.

11 P CYCLE OPEN and CLOSED SI-V-62, *CYCLES OPEN and CLOSED test line header isolation ORC and SI-V-62, test line header isolation MONITOR accumulator level and ORC and MONITORS accumulator pressure. level and pressure.

12 P When accumulator has been drained

When accumulator High Level to the desired level, CLOSE the valve alarm resets, Closes SI-V-15, opened in step 4.6.9: accumulator A drainlfill isolation.

SI-V-15, accumulator A drain/fill isolation

JPMSe Page 5 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT CUE: "The JPM is complete."

13. Stop time _ _ __ Time to complete task S 20 minutes Evaluator calculates time to complete task

14. Obtain from student:

Tear Off sheets and any other training materials used in performance of this JPM.

JPMSe Page 6 of 8

PERFORMANCE

SUMMARY

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.

JPMSe Page 7 of 8

TEAR OFF SHEET FOR JPM Se Directions To The Student:

1. You are the Primary Operator

2. You are going to the lower the "A" Accumulator level.

3. All applicable prerequisites of OS1005.05 Safety Injection System Operation are complete.

4. The Primary NSO is standing by to support local valve manipulations.

Initiating Cue:

Lower the 'A' Accumulator level to clear the high level alarm, using OS1005.05, Safety Injection System Operation.

1 of 8

JOB PERFORMANCE MEASURE JPM Sf Rev. 1 EMERGENCY TRIP OF DIESEL GENERATOR 1B Student Name:

LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: DATE:

APPROVED BY: DATE:

=TRA~IN~IN~G~S~U~P=ER~V~IS~O~R----- --------

JOB PERFORMANCE WORKSHEET 1.0 Task Number and

Description:

Position: RO 0640402501 Restore off-site power to Bus E5/E6

2.0 Conditions

A. Bus E6 was being supplied by the RAT (Reserve Auxiliary Transformer) to support a scheduled UAT (Unit Auxiliary Transformer) breaker inspection. The tagging clearance for the UAT breaker had not been started.

B. A failure on the Bus 6 RAT breaker caused the breaker to trip open.

C. DG "B" started and restored power to bus E6.

D. Plant conditions have stabilized. The Shift Manager has directed the Unit Supervisor to transfer bus E6 to the UAT and shutdown DG "B".

E. The SM and US have decided to use Attachment L of OS1246.01, LOSS OF OFFSITE POWER-PLANT SHUTDOWN, as guidance in restoring off-site power to bus E6.

3.0 Standards

Attempt to restore off-site power to bus E6 and respond to degraded DG "B" condition as necessary.

4.0 Student Materials:

Copy of the Tear-Off Sheet.

Attachment L of OS1246.01, LOSS OF OFFSITE POWER-PLANT SHUTDOWN, Rev. 15 5.0 Limitations On Performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator. Even if requested, no peer checks will be provided during the JPM.

6.0

References:

Procedures: Attachment L of OS1246.01, LOSS OF OFFSITE POWER-PLANT SHUTDOWN Sys KA Description Value RO/SRO 064 A4.07 Ability to manually operate and/or monitor in the 3.4/3.4 control room: Transfer EDG with load to grid.

7.0 Setting

JPM Sf Page 2 of 7

JOB PERFORMANCE WORKSHEET Simulator:

If performed as a pair with JPM Se, Reset to IC # 83.

For stand alone, Initialize the simulator to any 100% power IC with the following setup:

A. Place the simulator in RUN.

B. Transfer Bus E6 to the RAT. Place the UAT breaker in Normal After Stop.

C. Remove CS-P-2B from service by placing Danger Tags and racking out the breaker.

CS-P-2B is removed from service so it does not interfere with the JPM. The CCP's start on a LOP.

SELECT: Component Remote Functions SELECT: bkCS1P2B 52 RACKOUT D. Insert component malfunction: bkEDE6RAT, 4160V Bus E6 A72 trip.

E. Check for the following:

EPS sequenced loads start, as applicable with the plant remaining at power.

SGBD isolated.

SW-V-5 closed.

F. Clear RAT amber light and PLACE RAT breaker in PTL G. Establish a 4-Point trend for the following Analog Points:

A2732 DG 1B Vlts

A2734 DG 1B Gen Field Amps

A2735 DGB Watts

A2736 DG1B Vars 8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

20 minutes 10.0 Directions To The Student(s):

1. You are the Secondary Operator

2. While supplying Bus 6 for maintenance activities, a failure on the Bus 6 RAT breaker caused the breaker to trip open.

3. DG "B" started and restored power to bus E6.

4. The US has decided to use Attachment L of OS1246.01, LOSS OF OFFSITE POWER-PLANT SHUTDOWN, as guidance in restoring off-site power to bus E6.

5. Due to a radio system failure, an NSO is standing by at telephone extension 4082 to assist.

11.0 Initiating Cue:

"Restore offsite power to bus E6, via the UAT, using Attachment L of 051246.01, LOSS OF OFFSITE POWER-PLANT SHUTDOWN."

JPMSf Page 3 of 7

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

denotes a critical step

denotes a critical step SAT UNSAT 1 Start time Initiating cue read.

Evaluator CUE: If the student asks if the grid is stable, respond: "The grid is stable."

2 P IF AC emergency bus is Recognizes that Bus 6 is energized and deenergized, THEN restore continues with step 2.

offsite power as follows:

3 P Raise DG frequency to 60.2 to Raises "B" DG frequency to 60.2 to 60.4 Hz.

60.4 Hz.

4 P Place the DG synch. Selector *Places the Bus 6 synch. Selector switch in switch in the RAT or UAT the UAT position.

position.

5 P Reset RMO (Remote Manual *Resets "B" Train RMO.

Override).

6 P Adjust EDG voltage to match Matches "B" EDG voltage +/-..1 0 Kv INCOMING VOLTS with RUNNING VOLTS

7 P Adjust EDG frequency so that

Adjusts "B" EDG speed as required.

the synch meter is going slowly in the fast direction.

8 P Close the RAT or UAT *Closes the Bus 6 UAT breaker when Transformer breaker when synchronized.

synchronized.

9 P Place the synch selector switch Places the Bus 6 synch selector switch in in OFF. OFF.

Instructor NOTE: The DB B Lube Oil Pressure Low and DG B Aux. Lube Oil Pump Running alarms should be initiated before the EDG can be unloaded.

Instructor CUE: Run scenario: Len / Len, DG LOP Test

-or-Insert malfunction: sv06608DGB f:1 Insert malfunction: svo6611 DGB f:1 JPM Sf Page 4 of 7

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

denotes a critical step

denotes a critical step SAT UNSAT Floor Evaluator NOTE: Wait for the associated low lube oil pressure alarms to go into alarm prior to providing the following CUE.

Floor Evaluator CUE: Before the candidate starts unloading the EDG, notify the candidate that the Roving NSO makes an urgent report to the Control Room via the telephone; "There is a large amount of lube oil spraying from the Bravo diesel engine."

NOTE: On a low lube oil condition the emergency diesel engines should automatically trip. This scenario simulates failure of the automatic trip. Based on the VAS (Video Alarm System) alarm and report from the field, it is expected that the candidate will perform a manual emergency shutdown of the diesel generator.

10 P Acknowledge the report from Acknowledges the report from the field.

the field and the MPCS VAS (Video Alarm System) alarm Acknowledges the MPCS VAS alarm condition. condition.

Evaluator NOTE: The intention of the JPM is for the student to identify and recommend/perform an emergency shutdown of EDG 18.

Evaluator CUE: If the student recommends stopping the diesel generator, say: "I Concur."

11 P Perform emergency shutdown *Performs an emergency of DG-1B by simultaneously shutdown of DG-1 B by simultaneously pressing BOTH Emergency pressing BOTH Emergency Stop Stop push buttons. pushbuttons.

Evaluator CUE: "The JPM is complete."

12 Stop time Start-Stop is ~20 minutes.

Evaluator calculates the time to complete the task.

13 Obtain from student:

Tear Off sheets and any other training materials used in performance of this JPM.

JPM Sf Page 5 of 7

PERFORMANCE

SUMMARY

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

JPM Sf Page 6 of 7

TEAR OFF SHEET FOR JPM Sf Directions to the Student:

1. You are the Secondary Operator

2. While supplying Bus 6 for maintenance activities, a failure on the Bus 6 RAT breaker caused the breaker to trip open.

3. DG "B" started and restored power to bus E6.

4. The US has decided to use Attachment l of OS1246.01, lOSS OF OFFSITE POWER-PLANT SHUTDOWN, as guidance in restoring off-site power to bus E6.

5. Due to a radio system failure, an NSO is standing by at telephone extension 4082 to assist.

Initiating Cue:

Restore offsite power to bus E6, via the UAT, using Attachment L of OS1246.01, lOSS OF OFFSITE POWER-PLANT SHUTDOWN.

Page 7 of 7

JOB PERFORMANCE MEASURE JPM S9 Rev. 1 RECOVER A DROPPED ROD Student Name: _ _ _ _ _ _ _ _ _ _ _ _ LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: DATE:

APPROVED BY: _ _-=-:::--:-:-:-~,...--::--=-:.........,-:-:~--- DATE: _ _ _ _ __

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET

1. Task Number and Description Position RO SBK 0010400301 Operate single full length control rod (misalignment)

2. Conditions:

A. The plant is at approximately 95% power following a dropped rod in control bank 0 (CBD) group 2, identified as H-8.

B. The plant has been stabilized using turbine load control, with rod control in manual.

C. I&C has completed replacing a blown fuse on the stationary gripper.

3. Standards:

Align the dropped rod with its bank per OS1210.05 Dropped Rod.

4. Student Materials:

Copy of Tear Off Sheet.

Copy of OS1210.05 Dropped Rod Rev 13.

5. Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

Even if requested no Peer Checks will be provided during the JPM.

6.

References:

Procedures:

OS1210.05 Dropped Rod Technical Specifications:

3.1.1.1 SDM Tavg Greater Than 200 0

3.1.3.1 Moveable Control Assemblies Group height

3.1.3.2 Moveable Control Assemblies Position Indication Systems

3.1.3.5 Shutdown Rod Insertion Limit

3.1.3.6 Control Rod Insertion Limit

3.2.1 Axial Flux Difference

3.2.4 Quadrant power Tilt Ratio Drawings:

1-N HY-509049 Rod Control

..IPMSg Page 2 of 9

JOB PERFORMANCE WORKSHEET Value Sys KA Description RO/SRO 001 K4.09 Knowledge of CRDS design features 3.9/4.1 I

I and/or interlocks which provide for I recovery of a drol2ped rod

7. Setting:

Simulator:

If performed as a pair with ..IPM Sc, Reset the simulator to IC# B4.

For stand alone, Reset the simulator to IC# 300 or any 100% IC and reduce power to

-95% power. Complete simulator setup by performing the following:

A. Insert malfunction mfCP01B, Dropped Rod H-B.

B. Place the simulator in RUN and stabilize the plant per OS121 0.05

1. Place rods in MANUAL.

2. Match TavelTref by reducing turbine load.

3. Acknowledge alarms.

C. Verify Bank Demand Counters reflect expected plant conditions.

D. Delete malfunction mfCP01B, Dropped Rod H-B.

Place the simulator in RUN as long as needed to ensure all alarms are acknowledged prior to start of the JPM.

8. Safety Considerations:

None

9. Approximate Completion Time:

20 minutes

10. Directions To The Student{s):

1. You are the Primary Operator.

2. We have a dropped rod in control bank D (CBD) group 2, identified as H-B.

3. The plant has been stabilized using turbine load control, with rod control in manual.

4. I&C has completed replacing blown fuses on the stationary gripper.

11. Initiating Cue:

"Continue with OS1210.05 at step 4, to recover the dropped rod."

.JPM Sg Page 30f9

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

denotes a critical step

denotes a critical step SAT UNSAT

1. 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."

CUE: Note prior to step 4 should be reviewed, if student contacts SM or RE for rod recovery recommendation, respond: "Recover the dropped rod in an expeditious manner."

2. P Check rod control urgent failure alarm Checks rod control urgent failure

- RESET alarm - RESET

D7746

D7746

Contacts NSO and Inquires about

Local power cabinet Local power cabinet alarm.

Contacts NSO and Inquires about

Local logic cabinet Local logic cabinet alarm CUE: When student requests the NSO to locally verify logic and power cabinet alarms, respond, "There are currently no alarms on the logic or power cabinets."

3. P Align rod control system for dropped rod recovery:

a. Place the rod bank selector *a. Place the rod bank selector switch to - Affected Bank switch to - CBD Position

b. Except for the dropped rod, place *b. Places all the lift coil disconnect all the lift coil disconnect switches switches for the Control Bank D for the affected bank to - Rod to - Rod Disconnected except for Disconnected rod H-8

c. Record the affected group step c. Records the CBD group 2 step counter position. counter position JPM Sg Page 4 of9

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

denotes a critical step

denotes a critical step SAT UNSAT CUE: Due to differences between the simulator and the plant if student asks for direction on how to reset counter position, respond, "Depress step counter 'RS' pushbutton."

d. Reset the affected group step *d. Resets the CBD group 2 step counter to zero counter position to zero

e. Hold and maintain the pulse to *e. Directs NSO to hold and maintain analog converter Auto-Man the pulse to analog converter switch in Man until rod withdrawal Auto-Man switch in Man until rod is complete withdrawal is complete CUE: Simulator Operator: When directed NSO to Primary Operator, "I copy, hold the PIA converter Auto-Man switch to Man until rod withdrawal is complete."

NOTE: Simulator Operator Place PIA converter switch in Man as follows:

Select Local Panels Select Rod Drive System Select Pulse to Analog Converter Select Hold in Manual CUE: Simulator Operator: NSO to Primary Operator, "The PIA converter Auto-Man switch is being held in Man."

4. P Withdraw the dropped rod until the step counter reaches the previously recorded position:

a. Verify that the dropped rod is the *a. Verifies that only rod H-8 is only rod moving by DRPI withdrawing.

CUE: When asked for method of maintaining Tavg on program, US to Primary Operator, "The Secondary Operator will maintain Tavg with turbine load adjustments while you withdraw the control rod."

b. Maintain programmed Tavg using b. Discusses controlling Tavg with boration and/or turbine loading as the US.

recommended by Reactor Engineering.

JPMSg Page 5 of 9

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

denotes a critical step

denotes a critical step SATUNSAT

c. Withdraw rod to previously *c. Withdraws rod H-8 to previously recorded position. recorded position.

5. P Align rod control system for normal operation:

a. Return the Pulse to Analog *a. Directs NSO to return the Pulse Converter Auto-Man switch to to Analog Converter Auto-Man Auto. switch to Auto.

CUE: Simulator Operator: NSO to Primary Operator, "I copy, return The PIA converter Auto-Man switch to Auto."

NOTE: Simulator Operator Place PIA converter switch in Auto as follows:

Select Local Panels Select Rod Drive System Select Pulse to Analog Converter Select Hold in Automatic CUE: Simulator Operator: NSO to Primary Operator, "The PIA converter Auto-Man switch is in Auto."

b. Reset the rod control urgent *b. Depresses the rod control alarm failure alarm by depressing the reset pushbutton.

rod control alarm reset pushbutton.

c. Place all the lift coil disconnect *c. Places all the lift coil disconnect switches to Rod Connect. switches for Control Bank D to Rod Connect.

d. Return Rod Bank Selector Switch *d. Returns Rod Bank Selector to Man. Switch to Man.

e. If necessary, reset the power e. If necessary, rotates rate mode range rate trip. reset switch to reset for affected Nls.

--~-----------.-- .. --

JPMSg Page 6of9

PERFORMANCE

SUMMARY

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.

JPM 89 Page 8 of9

TEAR OFF SHEET FOR JPM S9 Directions To The Student:

1. You are the Primary Operator.

2. We have a dropped rod in control bank D (CBD) group 2, identified as H-8.

3. The plant has been stabilized using turbine load control, with rod control in manual.

4. I&C has completed replacing blown fuses on the stationary gripper.

Initiating Cue:

Continue with OS1210.05 at step 4, to recover the dropped rod.

Page 90f9

JOB PERFORMANCE MEASURE .JPM Sh Rev. 1 START HYDROGEN RECOMBINERS Student Name: _ _ _ _ _ _ _ _ _ _ _ LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: _~_ _ _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ __

APPROVED BY: _ _---=:-:~-:-:-:-:::-:::-:-:::-:=-:-:---:~--- DATE: _ _ _ __

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET 1.0 Task Number and

Description:

Position: RO 0280500201 Start lA' H2 Recombiner From The Main Control Room.

2.0 Conditions

A. A reactor trip with SI occurred from 100% power due to a large break LOCA.

B. The US transitioned through E-O, E-1, ES-1.3, and back to E-1 and is now at step 17.

C. Hydrogen concentration in containment is 3.4%

3.0 Standards

Place a hydrogen recombiner in service.

4.0 Student Materials:

Copy of the Tear-Off Sheet.

Copy of OS1023.40, Hydrogen Recombiner Operation, Rev. 7, Chg. 2.

Calculator.

5.0 Limitations On Performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator.

Even if requested, no Peer Checks will be provided during the JPM.

6.0

References:

Procedures:

E-1. Loss of Reactor or Secondary Coolant

OS1023.40, Hydrogen Recombiner Operation.

Sys KA Description Value RO/SRO 028 A2.02 LOCA condition and concern over hydrogen. 3.5/3.9 028 A2.03 The hydrogen/air concentration in excess of limit 3.4/4.0 flame propagation or detonation with resulting equipment damage in containment.

2.1 2.1.23 Ability to perform specific system and integrated 4.3/4.4 plant procedures during all modes of operation.

2.1 2.1.8 Ability to coordinate personnel activities outside the 3.4/4.1 control room.

2.1 2.1.31 Ability to locate control room switches, controls, and 4.6/4.3 indications, and determine that they are correctly reflecting the desired plant lineup.

JPMSh Page 2 of 9

JOB PERFORMANCE WORKSHEET

7.0 Setting

If performed as a pair with JPM Sa, reset the simulator to IC-81. When run as a pair, simulator conditions will not reflect the conditions identified below.

If running as a stand alone ..IPM, Reset the simulator to IC #356 or any 100% IC which contains the following:

A. Initialize to the 100% IC and place simulator in RUN.

B. Insert malfunction mfRC024A RCS Cold Leg 12 LOCA (double ended shear).

C. Run the simulator while performing the following per E-O and E-1:

1. Trip RCPs.

2. Reset SI.

3. Throttle EFW back to approximately 150 gpm per generator.

4. Shutdown both EDGs. Close SW-V16, and 18. Reset both engines.

5. Swap to cold Jeg recirculation when RWST level decreases to 120,478 gallons lAW ES-1.3. Insert component remote function mvCS1LCV112D 460V MCC-512 breaker open and mvCS1LCV-112E 460V MCC-612 breaker open when required in ES-1.3.

6. Complete the actions of E-1 through step '17.

7. Using panel graphics display sections PGR06A and PGR06B insert overrides on Hydrogen Analyzer A meter AND Hydrogen Analyzer B meter. Override to 3.4 for both meters.

8. Insert the following overrides Safety Injection Analog outputs for Containment pressure:

IOOZMAOSIPI2576 Final Value=4 IOOZMAOSIPI2577 Final Value=4 IOOZMAOSIPR934B Final Value=4 IOOZMAOSIPR934R Final Value=4 IOOZMAOSIPR935B Final Value=4 IOOZMAOSIPR935R Final Value=4 IOOZMAOSIPI934 Final Value=4 IOOZMAOSIPI935 Final Value=4 IOOZMAOSIPI936 Final Value=4 IOOZMAOSIPI937 Final Value=4 D. Place the simulator in FREEZE.

The simulator must be in RUN to allow the PWR OUT meter to respond to the potentiometer.

Verify the "PWR OUT" potentiometer is at MINIMUM prior to beginning the JPM.

8.0 Safety Considerations:

None 9.0 Approximate Completion Time:

20 minutes JPM Sh Page 3 of 9

JOB PERFORMANCE WORKSHEET 10.0 Directions To The Student(s):

1. You are the Secondary Operator.

2. You are going to place Hydrogen Recombiner 'A' in service.

3. The crew is presently at step 17 of E-1 Loss of Reactor or Secondary Coolant and they have checked containment H2 concentration, which is 3.4 %.

4. Containment Pressure is 4 psig on SI-PI-934 and SI-PI-935.

11.0 Initiating Cue:

Place Hydrogen Recombiner 'A' in service per 051023.40, Hydrogen Recombiner Operation.

JPMSh Page 4 of 9

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

denotes a critical step

denotes a critical step SAT UNSAT NOTE: When the student is ready to begin place the simulator in run.

1. Start time_ _ _ _ __ Initiating cue read.

CUE: If the student request a Peer Check at any time during the JPM, respond: "No one is available to peer check your actions. Please continue with the task".

CLlE: If asked by the student, "The electrical lineup has been completed".

2. P Verify the white PWR. IN Verifies the PWR. IN AVAIL. light is AVAIL. light is energized. energized.

3. P Set the PWR. ADJ. Turns PWR ADJ pot to 000.

potentiometer to zero.

4. P Place the PWR. OUT SW. *

Moves switch to ON position.

switch to the ON position and VERIFY that the red light on the switch plate comes on.

Verifies the red light is on.

CUE: At each power level, inform the student; "The stated time has elapsed."

5. Energize the Hydrogen Energizes the recombiner:

Recombiner heater by PERFORMING the following:

P a. TURN the PWR. ADJ. *a. Turns the PWR ADJ pot clockwise until 5 _ _

Potentiometer clockwise kW is indicated.

until 5 kW is indicated on the PWR. OUT meter.

MAINTAIN the 5 kW value for at least 10 minutes.

P b. TURN the PWR. ADJ. *b. Turns the PWR ADJ pot clockwise until Potentiometer clockwise 10 kW is indicated.

until 10 kW is indicated on the PWR. OUT meter.

MAINTAIN the 10 kW value for at least 10 minutes.

JPM Sh Page 50f9

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

denotes a critical step

denotes a critical step SAT UNSAT P c. TURN the PWR. ADJ. *c. Turns the PWR ADJ pot clockwise until Potentiometer clockwise 20 kW is indicated.

until 20 kW is indicated on the PWR. OUT meter.

MAINTAIN the 20 kW value for at least 5 minutes.

P d. DETERMINE the d. Refers to Form A.

recombiner power setting per Form A, Power Out Setpoint Calculation.

P e. Calculate the H2 recombiner power setpoint by performing the following:

P DETERMINE the current

Determines the current containment containment pressure from pressure from the "Directions to the SI-PI-934 or SI-PI-935, Student" section of the JPM Tear-Off MCB containment pressure Sheet provided.

indicators.

P Current Containment *

Converts cntmnt pressure to psia and Pressure + 14.7 psi = psia records on data sheet (= 18.7 psia).

P

Using containment absolute *. Determines Cp and Records on data pressure, pre-accident sheet - (C p = 1.17 - 1.20).

containment average temperature and Figure 2, Enter student Cp value:

Recombiner Power Cp =

Correction Factor Curve determine the Pressu re Factor (C p )'

P

MULTIPL Y the Pressure *

Multiplies Cp by the reference power.

Factor (C p ) by Reference Records on data sheet - (52.9 - 54.3 Power (45.24 kW). kW).

(C p ) x 45.24 = Power Enter student Setting kW KW value:

KW=

CUE: If the student requests a second person verification, respond: "For the purpose of this evaluation, a second verification will not be performed. Please continue with the procedure."

JPM Sh Page 6 of9

PERFORMANCE CHECKLIST D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate .. denotes a critical step .. denotes a critical step SAT UNSAT

Have a second person

Requests second person verification.

VERIFY the power setting calculation.

P f. Turn the PWR. ADJ. *f. Turns the PWR ADJ pot clockwise until potentiometer clockwise the power setpoint is indicated on the until the power setpoint, as PWR OUT meter.

calculated in Step 4.2.4.4, is indicated on the PWR OUT meter.

CUE: When student mentions that conference with the TSC is necessary to determine recombiner effectiveness, inform the student, "The SM is aware of this and in contact with the TSC on this matter."

P g. CONFER with the TSC to g. Attempts to confer with the TSC.

determine recombiner effectiveness and the need to make adjustments to recombiner power.

CUE: "The JPM is complete."

6. Stop time _ _ _ __ Time to complete the task :<s; 20 minutes.

Evaluator calculates the time to complete the task.

7. Obtain from student:

Tear Off Sheets and any other training materials used in the performance of the JPM JPMSh Page 7 of9

PERFORMANCE

SUMMARY

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

JPM Sh Page 8 of 9

TEAR OFF SHEET FOR JPM Sh Directions to the Student:

1. You are the Secondary Operator.

2. You are going to place Hydrogen Recombiner 'A' in service.

3. The crew is presently at step 17 of E-1 Loss of Reactor or Secondary Coolant and they have checked containment H2 concentration, which is 3.4 %.

4. Containment Pressure is 4 psig on SI-PI-934 and SI-PI-935.

Initiating Cue:

Place Hydrogen Recombiner 'A' in service per OS1023.40, Hydrogen Recombiner Operation.

90f9

SEABROOK IN-PLANT JOB PERFORMANCE MEASURE 'A' Rev. 1 LOCAL REACTOR TRIP Student Name: LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE:

APPROVED BY: _ _-=:=-:--:-:--:-,,--::--:--:::---:--~----- DATE:

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET 1, Task Number and Description SBK 0010101604 Locally Operate Reactor Trip Breaker SBK 0010150204 Trip Rod Drive Motor Generator Sets SBK 0120100104 Locally Trip Reactor trip Breaker and Bypass Breaker 2, Conditions:

A. The crew has entered FR-S.1, Response To Nuclear Power Generation/ATWS B. The reactor cannot be tripped from the main control room.

C. The reactor trip bypass breakers are open and racked out.

3, Standards:

Simulate locally tripping the reactor.

4. Student Materials:

Copy of Tear Off Sheet.

5, Limitations On Performance:

Simulate all steps. Verbalize all actions to the evaluator.

Even if requested no Peer Checks will be provided during the JPM.

6,

References:

Procedures:

FR-S.1 Response To Nuclear Power Generation/ATWS.

NAP-402 Conduct Of Operations Value Sys/Proc KA Description RO/SRO 007- EA2.04 If the reactor should have tripped but has 4.4/4.6 Reactor Trip not, carry out actions in ATWS EOP.

2.4- 2.4.35 Knowledge of local NSO tasks during 3.8/4.0 Emergency emergency operations.

Proc.lPlan In-Plant 'A' Page 2 of9

JOB PERFORMANCE WORKSHEET

7. Setting:

In-Plant. Train 'A' Essential SWitchgear Room.

8. Safety Considerations:

Do NOT permit opening of reactor trip breaker cubicles or rod drive MG set cubicles.

9. Approximate Completion Time:

5 minutes

10. Directions To The Student:

Evaluator gives Tear Off sheet to the student.

Initial Conditions:

A You are the Secondary NSO.

B. The following information is provided to you:

1. The crew has entered FR-S.1, Response To Nuclear Power Generation/ATWS

2. The reactor cannot be tripped from the main control room.

3. The reactor trip bypass breakers are open and racked out.

11. Initiating Cue:

US to Secondary NSO, "Secondary NSO, locally trip the reactor."

In-Plant 'A' Page 3 of 9

PERFORMANCE CHECKLIST 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 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."

CUE: If required upon arrival at the reactor trip breakers, US to Secondary NSO, "Secondary NSO, locally open the reactor trip breakers."

NOTE: CAUTION DO NOT allow the student to depress the trip plate because this will cause an actual reactor trip.

CUE: Evaluator to student, "The reactor trip breakers indicate closed."

2. S Open the reactor trip breakers locally:

a. Depress red trip plate for reactor a. Simulates depressing red trip trip breaker RTA. plate for reactor trip breaker RTA.

CUE: When student simulates depressing red trip plate for reactor trip breaker RTA, evaluator to student, "The reactor trip breaker does not open."

Depress red trip plate for reactor b. Simulates depressing red trip trip breaker RTB. plate for reactor trip breaker RTB.

CUE: When student simulates depressing red trip plate for reactor trip breaker RTB, evaluator to student, "The reactor trip breaker does not open."

3. S Inform the control room that the Inform the control room that the reactor trip breakers will not open. reactor trip breakers will not open.

CUE: US to Secondary NSO,"I understand, the reactor trip breakers will not open. What action do you recommend?"

In-Plant 'A' Page 4 of9

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

denotes a critical step

denotes a critical step SAT UNSAT NOTE: The student should recommend opening the Rod Drive, MG Set input/output breakers (preferred method) or may recommend opening the Rod Drive MG Set supply breakers located at US-11 and US-23 (alternate method). Either method is acceptable.

4 Provide recommended action to Student provides recommended examiner. action to examiner.

CUE: . If the student recommends one of the acceptable methods then state "I understand, continue with your recommended actions."

. If the recommendation does not include one of the acceptable methods then state "The JPM is complete."

CAUTION: DO NOT allow the student to actually open or jar the MG set breakers.

NOTE: If the student recommends actions to open the Rod Drive MG Set motor/generator breakers (preferred method) then go to JPM step 5.

If the student recommends actions to open the Rod Drive MG Set supply breakers at US-11 and US-23 then go to JPM step 9.

NOTE: The order in which the breakers are opened is not critical. At least one breaker being opened (motor or generator) for each MG set is critical.

5. S Open the input (motor) and/or output (generator) breaker for both MG sets:

a. Open "A" MG set motor and/or *a. Simulates opening "A" MG set generator breaker. motor and/or generator breaker.

CUE: When student simulates rotating each breaker handle switch to TRIP, evaluator to student,"Red light extinguishes and green light illuminates. The breaker opens."

b. Open "8" MG set motor and/or *b. Simulates opening "8" MG set generator breaker. motor and/or generator breaker.

CUE: When student simulates rotating each breaker handle switch to TRIP, evaluator to student,"Red light extinguishes and green light illuminates. The breaker opens."

In-Plant 'A' Page 5 of9

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

denotes a critical step

denotes a critical step SAT UNSAT

6. S Inform the control room that the input Informs the control room that the input and output breakers for both rod drive and output breakers for both rod drive MG sets are open. MG sets are open.

CUE: US to Secondary NSO,"I copy, the input and output breakers for both rod drive MG sets are open. All control rods are inserted."

CUE: "The JPM is complete."

7. Stop time _ _ __ Time to complete task ~ 20 minutes Evaluator calculates time to complete task

8. Obtain from student:

T ear Off sheets and any other materials used.

NOTE: The order in which the Rod Drive MG Set supply breakers are opened is not critical, however both breakers must be opened.

9 Open the Rod Drive MG Set supply Opens the Rod Drive MG Set breaker at US-11 (Node AG5) supply breaker at US-11 (Node AG5)

10 Open the Rod Drive MG Set supply Opens the Rod Drive MG Set breaker at US-23 (Node AM6) supply breaker at US-23 (Node AM6)

CUE: When the student notifies the control room that the Rod Drive MG Set supply breakers are both open state: "I copy, both Rod Drive MG Set supply breakers are open. All control rods are inserted" CUE: "The JPM is complete."

11 Stop time_ _ _ __ Time top complete task ~ 20 minutes Evaluator calculates time to complete task In-Plant 'A' Page 6 of 9

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

denotes a critical step

denotes a critical step SAT UNSAT 12 Obtain from student:

Tear Off sheets and any other materials used.

In-Plant 'A' Page 7 of 9

PERFORMANCE

SUMMARY

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 lA' Page 8 of 9

TEAR OFF SHEET FOR JPM In-Plant 'A' Directions To The Student:

A. You are the Secondary NSO.

B. The following information is provided to you:

1. The crew has entered FR-S.1, Response To Nuclear Power Generation/ATWS

2. The reactor cannot be tripped from the main control room.

3. The reactor trip bypass breakers are open and racked out.

Initiating Cue:

US to Secondary NSO, "Secondary NSO, locally trip the reactor In-Plant 'A' Page 9 of 9

IN-PLANT JOB PERFORMANCE MEASURE 'B' Rev. 1 HYDROGEN ANALYZER LOCAL OPERATION Student Name: LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE:

APPROVED BY: __________________._____ DATE: ________

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET

1. Task Number and Description SBK 0280101104 Align Hydrogen Analyzer to the Analyze Mode

2. Conditions:

1. The reactor tripped from 100% power due to a large break LOCA.

2. The crew transitioned to FR-C.1, Response to Inadequate Core Cooling.

3. Both hydrogen analyzers have been in standby for> 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

4. Chemistry has installed the sample vessel for the Train A Hydrogen Analyzer.

S. General dose rates are 10 mr/hr and no indications of radiation streaming are present. It is safe to enter the hydrogen analyzer room and no SCBA is required.

3. Standards:

Simulate placing the hydrogen analyzer in the ANALYZE mode per OS1023.71, Operation of the H2 Analyzers.

4. Student Materials:

Copy of Tear Off Sheet.

Copy of OS 1023.71 , Operation of the H2 Analyzers.

5. Limitations On Performance:

Simulate all steps. Verbalize all actions to the evaluator.

Even if requested no Peer Checks will be provided during the JPM.

6.

References:

Procedures:

OS 1023.71, Operation of the H2 Analyzers

FR-C.1, Response to Inadequate Core Cooling

ECA-0.2 Loss Of All AC Power Recovery With SI Required Technical Specifications:

3.6.1.1 Containment Integrity In-Plant 'B' Page 2 of 8

JOB PERFORMANCE WORKSHEET

7. Setting:

Plant. H2 Analyzer Room.

8. Safety Considerations:

Hearing protection.

9. Approximate Completion Time:

1Sminutes

10. Directions To The Student:

Evaluator gives Tear Off sheet to the student.

Initial Conditions:

1. The reactor tripped from 100% power due to a large break LOCA.

2. The crew transitioned to FR-C.1, Response to Inadequate Core Cooling.

3. Both hydrogen analyzers have been in standby for> 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

4. Chemistry has installed the sample vessel for the Train A Hydrogen Analyzer.

5. General dose rates are 10 mr/hr and no indications of radiation streaming are present. It is safe to enter the hydrogen analyzer room and no SCBA is required.

11. Initiating Cue:

OSC Coordinator to NSO, uNSO, simulate placing Train A H2 analyzer in the ANALYZE mode per OS1023.71, Operation of the H2 Analyzers."

In-Plant 'B' Page 3 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT NOTE: When student demonstrates the ability to obtain a controlled copy of OS1023.71, Operation of the H2 Analyzers provide the student with a copy of OS1023.71, Operation of the H2 Analyzers

1. P Start time _ _ __ Initiating cue read CUE: If the student requests a Peer Check at any time during the ..IPM respond, "No one is available to Peer Check your actions. Please continue with the task."

2. S Notify HP and Chemistry Simulates notifying HP and Chemistry NOTE: The requirements of OS1090.05 shall be waived during the implementation of EOPs. Configuration control will be re-established during recovery operations.

CUE: If student requests permission to unlock and open CGC-V3 and V10, provide cue, "you have permission to unlock and open CGC-V3 and V10 per step 4.3.1.2 of 051023.71."

3. S Unlock and open the following valves:

Simulates unlocking and opening

a. CGC-V3 CUE: When student simulates unlocking and opening CGC-V3, evaluator to NSO, "The valve is unlocked, the handwheel turns and the valve opens."

b. Simulates unlocking and opening CGC-V10 CUE: When student simulates unlocking and opening CGC-V10, evaluator to NSO, "The valve is unlocked, the handwheel turns and the valve opens."

4. S Open CGC-V-12 hydrogen analyzer A *Simulates opening CGC-V-12 train supply ORC isolation. hydrogen analyzer A train supply ORC isolation.

CUE: When student simulates opening CGC-V12, evaluator to NSO, "The handwheel turns and the valve opens."

In-Plant 'B' Page 4 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT NOTE: DO NOT allow the student to open the cabinet when simulating alignment of the sample vessel.

CUE: If asked, the Chemistry Tech reports, "The sample vessel is installed in the Train A H2 analyzer."

CUE: If the student inquires about gloves for operation of potentially hot sample vessel isolation valves, then provide cue, "Gloves have been obtained."

5 S Open the following valves:

a. Simulates opening CGC-V58 hydrogen analyzer A Train sample vessel inlet isolation.

CUE: When student simulates opening CGC-V58, evaluator to NSO, "The handwheel turns and the valve opens."

b. Simulates opening CGC-V59 hydrogen analyzer A Train sample vessel outlet isolation.

CUE: When student simulates opening CGC-V59, evaluator to NSO, "The handwheel turns and the valve opens."

6. S Place the main power switch on Simulates informing control room that CP-173A to ANALYZE main power switch at CP-173A must be placed to ANALYZE CUE: When NSO calls the control room, US to NSO, "The main power switch has been placed in ANALYZE."

CUE: "The JPM is complete."

7. Stop time _ _ __ Time to complete task S 15 minutes Evaluator calculates time to complete task In-Plant '8' Page 5 of 8

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

denotes a critical step

denotes a critical step SAT UNSAT

8. Obtain from student:

Tear Off sheets and any other training materials used in performance of this JPM.

In-Plant 'B' Page 6 of 8

PERFORMANCE

SUMMARY

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 '8' Page 7 of 8

TEAR OFF SHEET FOR In-Plant 'B' Directions To The Student:

1. The reactor tripped from 100% power due to a large break LOCA.

2. The crew transitioned to FR-C.1, Response to Inadequate Core Cooling.

3. Both hydrogen analyzers have been in standby for> 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

4. Chemistry has installed the sample vessel for the Train A Hydrogen Analyzer.

5. General dose rates are 10 mr/hr and no indications of radiation streaming are present. It is safe to enter the hydrogen analyzer room and no SCBA is required.

Initiating Cue:

OSC Coordinator to NSO, "NSO, simulate placing Train A H2 analyzer in the ANALYZE mode per OS1 023.71, Operation of the H2 Analyzers."

-------- -------~---

In-Plant 'B' Page 8 of 8

SEABROOK IN-PLANT JOB PERFORMANCE MEASURE 'c' Rev. 1 ALIGN ALTERNATE (FIREWATER) COOLING TO CCP LUBE OIL COOLER Student Name:

LMS#:

Evaluator Name:

SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: DATE:

INSTRUCTOR APPROVED BY: DATE:

TRAINING SUPERVISOR

JOB PERFORMANCE WORKSHEET

1. Task Number and Description Position NSO SBK 0040160004 Align/Remove Alternate Cooling To Charging pump Lube Oil Coolers

2. Conditions:

A. Plant is in Mode 3.

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 to CS-P-2B per OS1002.02, Operation Of Letdown, Charging, and Seal Injection.

4. Student Materials:

Copy of Tear Off Sheet.

Copy of OS1002.02, Operation Of Letdown, Charging, and Seal Injection.

Section 4.21 pages 64 - 65.

5. Limitations On Performance:

Simulate all steps. Verbalize all actions to the evaluator.

Even if requested no Peer Checks will be provided during the JPM.

6.

References:

Procedures:

OS1212.01, PCCW System Malfunction.

OS1002.02, Operation Of Letdown, Charging, and Seal Injection Value Sys KA Description RO/SRO 004 K1.18

Knowledge of the physical connections 2.9/3.2 and/or cause-effect relationships I"\OT1,./o£.n the CVCS and the following systems:

~ .. _ ..... ~ .~ ___ CCWS _ _ _ _ _ _ _ _ ..

..L-=-::...:...::.-=- _~ ..... ....._ _

~ . . L __ _ __ _ _

In-Plant 'C' Page 2 of 9

JOB PERFORMANCE WORKSHEET

7. Setting:

Plant. PAB 25 ft and PAS 7 ft.

8. Safety Considerations:

Health Physics postings and ALARA.

9. Approximate Completion Time:

20 minutes

10. Directions To The Student:

Evaluator gives Tear Off sheet to the student.

Initial Conditions:

A. You are the Primary NSO.

B. The following information is provided to you:

1. Plant is in Mode 3.

2. Train S PCCW has been lost.

3. The crew is taking actions to align alternate cooling to the 2B charging pump lube oil cooler.

4. The Roving NSO and a Fire Fighter have been dispatched to connect the drain hose from the Charging Pump lube oil cooler outlet to a storm drain.

11. Initiating Cue:

US to Primary NSO, "Primary NSO (or student's name), simulate aligning Fire Protection (FP) water as alternate cooling to CS-P-2B lube oil cooler using OS1002.02 section 4.21. Inform the control room as soon as cooling flow has been established."

In-Plant 'c' Page 30f9

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

denotes a critical step

denotes a critical step SAT UNSAT NOTE: 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.

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."

NOTE: Student should review CAUTION prior to step 4.21.1.

2. S Notify Chemistry to issue a Non-Rad Simulates informing control room to realease permit. have Chemistry issue a Non-Rad realease permit.

CUE: When student simulates informing control room, US to NSO,"Chemistry has generated the Non Rad release permit and it is in the control room."

3. S Connect a drain hose from Charging Reads step for connecting a drain pump lube oil coolers outlet to the hose from Charging pump lube oil storm drain. coolers outlet to the storm drain.

CUE: If the student inquires about the drain hose, evaluator to student,"The drain hose has been connected by the Roving NSO and Fire Fighter."

4. S Refer to listed Technical Simulates informing control room to Specifications for applicability. refer to Technical Specifications for applicability.

CUE: If student informs control room to refer to Technical Specifications, US to NSO, "All applicable Tech Specs have been entered."

In-Plant 'C' Page 4 of 9

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

denotes a critical step

denotes a critical step SAT UNSAT

5. Check that CS-P-2B is in Pull To Simulate checking that CS-P-2B is in S

Lock. Pull To Lock.

CUE: When student checks on the status of CS-P-2B, US to NSO,"CS-P-28 is in Pull To lock."

NOTE: Valves CC-V-315, CC-V-318, Ce-V-1292, DM-V-793, and CC-V-1294 are all located along the wall, outside the degassifier room in the main passageway of the PAB 25 ft. across from the sampling room.

CUE: If the student requests permission to unlock and close CC-V-318, PCCW return from eS-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."

NOTE: Required keys would be on the Primary NSO key ring.

6. S Unlock and close the following valves:

a. Simulates unlocking and closing CC-V-318, PCCW return from CS-P-2B oil cooler.

CUE: When student simulates unlocking and closing CC-V-318, evaluator to student,"The valve is unlocked. The valve is closed."

b. Simulates unlocking and closing CC-V315, PCCW supply to CS-P 2B oil cooler.

CUE: When student simulates unlocking and closing Ce-V-315, evaluator to student,"The valve is unlocked. The valve is closed."

NOTE: Student should not perform step 4.21.6. Fire Protection water is being used for alternate cooling.

In-Plant 'e' Page 5 of 9

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

denotes a critical step

denotes a critical step SAT UNSAT

7. S Fire protection water is to be aligned to the CS-P-2B oil cooler. Align the following valves

a. Simulates closing CC-V-1297 FP alternate CCP cooling tell tale drain.

CUE: When student simulates closing CC-V-1297, evaluator to student, "The valve is closed."

b. Simulates releasing locking pin and opens FP-V-1129 Charging pump oil coolers alternate supply.

CUE: When student simulates releasing the locking pin and opening FP-V-1129, 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."

c. Simulates releasing locking pin and opens CC-V-1290 Fire water alternate cooling supply to CS-P 2B oil cooler.

CUE: When student simulates releasing the locking pin and opening CC-V-1290, 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."

NOTE: Student should review NOTE prior to step 4.21.8 ..

8. S Throttle CC-V-1294 CS-P-2B oil Simulates releasing locking pin and cooler alternate cooling outlet as throttling open CC-V-1294 CS-P-2B necessary to maintain 10-30 gpm. oil cooler alternate cooling outlet.

CUE: When student simulates releasing the locking pin and throttling CC-V-1294, evaluator to student, "The locking pin releases. The valve is throttled open. You hear flow." If student does not simulate release of locking pin, cue, "The valve does not move."

In-Plant 'c' Page 6 of 9

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

denotes a critical step

denotes a critical step SAT UNSAT

9. S Check flow on CC-FISL-221B. Simulates checking flow on Ce-FISL-221B.

CUE: When student simulates checking flow, evaluator to student, "The indicator shows 25 gpm."

10. S Inform control room that alternate Simulates informing control room that cooling using Fire Protection water alternate cooling using Fire Protection has been established to CS-P-2B oil water has been established to es-p cooler at 25 gpm. 2B oil cooler at 25 gpm.

CUE: "The JPM is complete."

11. Stop time _ _ __ Time to complete task:::; 20 minutes Evaluator calculates time to complete task

12. Obtain from student:

Tear Off sheets and any other training materials used in performance of this JPM.

In-Plant 'e' Page 7 of 9

PERFORMANCE

SUMMARY

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 'C' Page 8 of 9

TEAR OFF SHEET FOR JPM IN-PLANT 'C' Directions To The Student:

A. You are the Primary NSO.

B. The following information is provided to you:

1. Plant is in Mode 3.

2. Train B PCCW has been lost.

3. The crew is taking actions to align alternate cooling to the 2B charging pump lube oil cooler.

4. The Roving NSO and a Fire Fighter have been dispatched to connect the drain hose from the Charging Pump lube oil cooler outlet to a storm drain.

Initiating Cue:

US to Primary NSO, "Primary NSO (or student's name), simulate aligning Fire Protection (FP) water as alternate cooling to CS-P-2B lube oil cooler using 051002.02 section 4.21. Inform the control room as soon as COOling flow has been established. "

In-Plant 'C' Page 9 of 9

Appendix D Scenario Outline Form ES-D-1 Seabrook StatIOn 201 0NRC Exam-Slmulator Scenanos Facility: Seabrook Scenario No.: 1 Op-Test No.:

Examiners: ----!D~.!...:!S~I!.!:lk!..-_ _ __ Operators:

Initial Conditions: MOL 50% power. Both Main feed Pumps and one Heater Drain pump is in service.

Turnover:

Plant is at 55% power.

FW-FK-S20, "B" SG FRV controller has experienced a failure of its auto tracking driver card. This failure prevents automatic operation of the "B" FRV. The controller is currently in manual requiring operator intervention to control "B" SG water level. Additional manpower for feed station operations is not available at this time.

Procedure OS1000.0S, Power Increase is being performed and is completed to step 4.3.10.

Maintain AFD on target.

Increase power to 75% at 5%/hour.

SW-P-41 C tagged out f or motor re~Iacement.

Event Malf. No. Event Event No. Type* Description 1 IOOZMDIF BOPC FW-FK-520, "8" SG FRV controller had previously experienced WFK520M a failure of its auto tracking driver card. This failure prevents automatic operation of the "8" FRV. The controller is in manual requiring 80P intervention to control the "8" SG level during the following At-Power events.

2 PSOR Crew begins a 5%/hr. power increase BOPN USN I 3 ptFWPT505 PSOI Turbine Impulse Pressure PT-505 Fails Low causing automatic USI, TS rod insertion i

BOPI 4 RCLT459 PSO I RC-U-459 PZR Level, Channel 1 Fails High, requiring manual US I, TS control of charging and letdown.

5 mfRC049C PSOC Crew responds to a 20 GPM RCS Leak. Supports E Plan US C,TS Classification (End of scenario) 6 mfHF001 PSOM Crew responds to sequential loss of EHC pumps with complete mfHF002 USM loss producing an automatic Turbine/Reactor trip signal. A sv07186HF BOPM turbine trip - Reactor trip will occur when EHC pressure decays rvMSAVR36 below 1100 psig or when MANUALLY tripped by the crew.

rvMSAVRSO When the MSIVs are shut, two SG safeties will fail open causing the need for a SI.

7 avMSVSV2 BOPC One Turbine Stop and Control valve sticks Open requiring a avMSVCV2 Manual MSI.

mfRPS019 mfRPS020 8 mfSI003 PSOC SI pumps A & 8 will fail to auto-start on the SI signal and mfSI004 require manual actions to start

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Note: Anticipated AOP/EOP flow-path: OS1235.05, OS1201.07, OS1201.02, E-O, E-2, ES 1.1 or E-1 1

2009*2010 LOIT NRC SIMULATOR EXAMINATION # 01 Rev. 2 OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: _ _ _ _-:--_.,.--_ _ _ _ DATE:

INSTRUCTOR APPROVED BY: _ _ _ _ _ _ _ _ _ _ _ DATE:

TRAINING SUPERVISOR REVIEWED BY: _ _ _----::-::-~:-=-::-:-:-::----:--_- DATE:

SME (OPTIONAL)

201 LOIT 01 2 SCENARIO The Scenario begins with the plant at 55% power. SW-P-41 C is danger tagged out for motor replacement. Both Main feed Pumps and one Heater Drain pump are in service.

FW-FK-520, uB" SG FRV controller has experienced a failure of its auto tracking driver card.

This failure prevents automatic operation of the "B" FRV. The controller is currently in manual requiring operator intervention to control the "B" SG level. Additional manpower for feed station operations is not available at this time.

After the crew begins to increase power, FW-PT-505 fails low. This is addressed in Abnormal Procedure OS1235.05, 'Turbine Impulse Pressure PT-505 or PT-506 Instrument Failure."

RC-LT-459 will fail high. The crew should take manual control of charging flow. This failure is addressed with Abnormal Procedure OS1201.07, "PZR Level Instrument Failure." Also during this failure, a 20 gpm RCS leak will develop on the instrument sensing line. After initially addressing, or in parallel with the instrument failure, it is expected that the crew will address the RCS leak using Abnormal Procedure OS1201.02, "RCS Leak."

The running EHC pump will trip and the standby EHC pump will start. The standby pump will have a sheared shaft and EHC pressure will continue to decrease. The crew will need to recognize the decreasing EHC pressure and manually trip the reactor or respond to an automatic turbine trip/reactor trip demand. The #2 turbine stop and control valves will stick "as is" on the trip. Automatic Main Steam Isolation (MSI) will fail to actuate, requiring the crew to manually close the main steam isolation valves to prevent an excessive cooldown.

When the Main Steam Isolation Valves are shut. one safety valve on "B" & "C" Steam Generators will open and subsequently stick open, requiring a manual or an automatic Safety Injection. SI-P-6A and SI-P-6B will fail to start on the Safety Injection, requiring a manual start.

The crew will enter E-O, "Reactor Trip or Safety Injection" and may enter ES-0.1, "Reactor Trip Response" before transitioning back to E-O and then to E-2, "Faulted Steam Generator", to address the depressurization of the "B" & "C" Steam Generators.

Anticipated AOP/EOP flow-path: OS1235.05, OS1201.07', OS1201.02, E-O, E-2, ES 1.1 or E-1 Page 2 of 21

o LOIT 01 Rev. 2 SIMULATOR SETUP

1. Reset the simulator to 50-55 % power with both MFPs in service, Middle of Core Life condition. This setup has been snapped into password protected IC# 90. Alternately, any other 55% IC can be used, and conditions established using Scenario Sim test EV1 or manually entered as described below.

2. D Set Protected Train as "8" on MPCS and MCB.

3. Tag out SW-P-41C by inserting the following:

D Override cSWP41C SW-P-41C breaker racked out D Remote Function cSWV22 SW-V-22 breaker open D Tag the Control Switch for SW-P-41 C

4. D Verify Pressurizer Level Channel LT-459 is Selected for control.

5. Actuate the following scenario to insert malfunctions and activate triggers for the exam setup:

D SELECT: Scenarios D SELECT: Demo exams D SELECT: Exam #01 setup D SELECT: RUN Verif the followin were inserted and activated:

D mfS1003, SI PUMP 6A FAILS TO AUTO START D mfS1004, SI PUMP 68 FAILS TO AUTO START D avMSVSV2, t:1 d:O, MT STOP VLV #2 FAILS OPEN D mfRPS019, MS ISOLATION FAILS TO ACTUATE (TRN A)

D mfRPS020, MS ISOLATION FAILS TO ACTUATE TRN 8 Verify the following event trigger has been activated. This will insert malfunctions to fail open SG safety valves on '8' and 'C' Steam Generators when Main Steamline Isolation Train "8" switch is turned to ACTUATE:

D SELECT: Event Triggers (Top bar)

D SELECT: Demo Exams/Exam 01 MSI Band C D VERIFY: Activated

6. USing Panel Graphic Section E, FW-FK-520 controller, Fail the "8" FRV controller to Manual as follows:

D SELECT: Insert OR D SELECT: FW-FK-520 "Manual" pushbutton D When the initial override window appears, SELECT: Cancel D When the next window appears for IOOZMDIFWFK520M enter final value: "Manual" D SELECT: Insert Continued on next page Page 3 of 21

Rev. 2 7 Disable the B EHC Pump trouble alarm 07'186 as follows:

o SELECT: D-Points o SELECT: Hydraulic Fluid o SELECT: sv07186HF o =

SELECT: Final Value Return o SELECT: Insert Page 4 of 21

2010 LOIT 01 Rev. 2 SHIFT TURNOVER

Plant is at 55% power.

FW-FK-520, "B" 8G FRV controller has experienced a failure of its auto tracking driver card.

This failure prevents automatic operation of the "8" FRV. The controller is currently in manual requiring operator intervention to control "8" SG water level. Additional manpower for feed station operations is not available at this time.

Procedure 081000.05 is being performed and is completed to step 4.3.10.

Maintain AFD on target.

Increase power to 75% at 5%/hour.

8W-P-41C tagged out for motor replacement.

Page 5 of 21

2010 LOIT 01 Rev. 2 SCENARIO OUTLINE EVENT INSTRUCTION COMMENTS Shift Turnover Shift turnover information as stated.

Event 1 BOP (C)

FW-FK-520, "8" SG FRV controller had previously experienced a failure of its auto tracking driver card.

This failure prevents automatic operation of the "8" FRV.

The controller is currently in manual requiring BOP intervention to control the "B" SG level during the following At-Power events.

Event 2 PSO (R), US (N), BOP (N) 5%/hr. power Crew 8egins the Power increase lAW MPE Procedure increase OS1000.05, Power Increase.

Shift Turnover Shift turnover information as stated.

The crev.; 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 Tave to be used in the power increase. The temperature band will normally be +/- 1.5°F with rods in Auto or +/- 3 of 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.

Page 6 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Turbine Operations: The BOP will increase turbine load using automatic DEHC operations. Using the laminated sheets, Figure 9 of OS1000.05, The basic steps are:

Check the Load Set is in Hold mode.

Insert the desired loading Rate.

Insert the desired Power Level.

When RCS 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.

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.

Page 7 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Using the laminated sheets 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 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 Note: During validation the crew used a dilution value of 775 gals at 13 gpm.

If not desired, select OFF for the "Step back Feature"

Set the Mode Start Switch to START

Verify the pumps and valves respond

Verify Plant Response.

Restore System to Automatic control Allow the crew to demonstrate a power increase or at Chief Examiners discretion, enter the next Event:

Page 8 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Event 3 PSO(I), US(I, TS), BOP(I)

FW-PT-505 Enter the Turbine Impulse Press Channel FW-PT-505 Turbine Impulse Pressure FW-PT-505 fails low. If fails low Failure as follows: Control Rods are selected to auto, automatic rod oI SEL-E-C-T-.-M=F=L:-::i-st:--------------II Alarms:

insertion occurs.

. B7457 Rod Motion Detected o SELECT: FEEDWATER (Component) I 04421 Tavg -Tref Deviation o .SELECT: ptFWPT505 US may direct termination of the dilution and plaCing o Double Click rods in manual.

o SELECT: Fails Low Crew Enters OS1235.05, Turbine Impulse Pressure PT-o SELECT: Insert 505 or PT- 506 Instrument failure.

~~_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _---' Step 1: Check FW-PT-505 Failed:

The BOP checks FW-PT-505 Failed using FW-PI-505 or Tref indication.

PSO places rods in manual.

PSO/BOP monitor Tavg at program temp., using Tavg indication or RCS cold leg temperature.

The Crew will likely withdraw rods in 3-step increments or reduce turbine load to restore temperature.

Step 2: BOP Checks Condenser Steam Dumps:

Checks Steam dump valves closed.

Transfers Steam dump control to the STM Press Mode.

Adjust Steam dump controller output, places in AUTO.

Verifies interlock switches in NA RESET Page 9 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Step 3: PSO verifies P~13 Status Ught for Turbine Power above 10%.

Step 4: US verifies TS compliance and determines:

T.S. 3.3.1, Table 3.3~1, Item 18.f, Action 8, is applicable.

Place FW*PT*505 in Bypass as follows: Step 5: Crew verifies ATWAS Mitigation Input Status:

US directs I&C to place the failed channel in o SELECT: Panel Overview Operate Bypass.

o SELECT: AMSAC CP*519 Alarm: 07899 ATWAS Mitigation Sys ByplTrouble

BOP verifies UL~28 B~1, Turbine power above o I SELECT: TB IMP 505 20%

status light energized.

' - - - - - - - - - - - - - - - - - - - - - - - - " US may contact Ops. Management with regards to continuing with the power increase.

Instructor Cue: If Ops. Management contacted regarding the power increase, respond to continue the power increase.

Allow the crew to complete ON1235.05 or at Chief Examiners discretion prior to entering the next Event:

Page 10 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Event 4 PSO{I), US{I,TS)

RC-L T-459 Failure RC-Ll-459, PZR Level, channel 1, fails high, requiring manual control of charging and letdown. No letdown isolation occurs due to the failure of the channel high.

Enter the pressurizer Level Channel failure over 5 minutes Crew may take manual control of charging and/or as follows: letdown flow and I or isolate letdown due to flashing, using Skill Of The Operator.

o -SELECT: MF list Alarms:

o SELECT: REACTOR COOLANT (Component)

D4436 PZR LVL De~iation High &.BU Htrs On

F7861 PZR Level High Channel triP o SELECT: ItRCLT459 Crew Enters OS1201.07, PZR Level Instrument Failure.

o Double Click Step 1: P~O checks Pressurizer controlling channel farled.

o SELECT: FAIL TO SPECIFIED VALUE Step 2: PSO Realigns PZR Level Instruments:

DENTER: 100%

Manu~lIy controls level using Letdown and Charging o ENTER: Ramp Rate of 300 secs

Selects an alternate level channel for control o I SELECT' INSERT

Selects an aiternate level channel for recorder oI . Step 3: PSO will not need to Reset heaters Input Event 5 as a simultaneous failure. Step 4: PSO checks letdown NOT isolated, US goes to L . . -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _---' step 7.

Step 7: PSO aligns pressurizer level control by verifying controller setpoint and placing RC-LK-459 and CS-FK SIMULATOR OPERATOR CUE: Shortly after initiating Event 4, Insert 121 in Auto. (Time dependent).

malfunctions for Event 5. Step 8: PSO verifies redundant bistables on UL-6, Pressurizer Level High, NOT tripped.

Page 11 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Step 9: US verifies TS compliance and determines the following are applicable:

T.S. 3.3.1, Reactor Trip System Instrumentation; Table 3.3-1, Item 11, Action 6 is applicable

T.S. 3.3.3.6, Accident Monitoring Instrumentation; Table 3.3.10, Item 5, Action A for PAM indication

T.S. 3.3.3.5, Remote Shutdown Systems; Table 3.3-9, Item 5, Action A for RSSD indication To place LB-459A in Bypass perform the following: US Coordinates with I&C to place bistables in r-::--_...._--:--=------___- - - - - - - - - - - - , bypass or tripped.

D SELECT: CP1 Bypass Cabinet D SELECT: Door Open D SELECT: Enable D SELECT: Panel Overview D SELECT: BTl CP1 Position the following switches to bypass:

~I U I LB* 459, High Reactor Trip BS*1 D SELECT: CP1 Bypass Cabinet D SELECT: Door Closed D SELECT: Enable Page 12 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Event 5 PSO{C), US{C,TS) 20 gpm RCS Shortly after initiating Event 3, insert the following Supports E-Plan UE call on SUS (End of Scenario)

Leak malfunction for a 20 gpm leak ramped in over 5 minutes, Crew responds to a 20 gpm RCS leak lAW Abnormal simulating a leak on the pressurizer instrument sensing Procedure OS 1201.02, RCS Leak line:

o I Select: MF List ROMS Alarms:

o I Select: Reactor Coolant

Containment Particulate High and High High

Containment Gaseous High and High High D Select: mfRC049C

Containment Backup Gas High and High High Step 1: PSO Checks If Pressurizer Level Can Be Select: Final Value =20 Maintained by:

Select: Ramp = 600

controlling charging D I Select: Insert

controlling letdown

checking level stable or increasing.

Step 2: US makes notation to discuss with SM, ER1.1, If an NSO is sent to the RSS panel to check indication, Classification Of Emergencies, SUS.

after 2 minutes, Inform the control room that RC-LT Step 3: US determines step 4 is the appropriate step 7334 indicates off-scale high. (common instrument Transition for a suspected RCS leak.

sensing Step 4: PSO Isolates Potential RCS Leakage Sources:

Checks Safety or PORV ieakage using PORV NOTE: Due to no SM immediately available for the crew, it tailpipe temps, and Acoustic monitor alarms is not expected that the US will investigate ER 1.1,

Checks reactor head vents isolated, RC-FV-2881 Classification of Emergencies, as directed by OS1201.02, and RC-V323 step #2. A notation to follow up with the SM is sufficient at

Checks Excess Letdown isolated, CS-V17S and this point in the scenario. CS-V176

Checks Phase A Status lights for RCS sample lines indicate valves are closed

Checks reactor vessel flange leakoff temperature Normal

Checks valve stem leakoff header temperature, 07805 and 07804 not in alarm.

BOP checks SG tubes intact using rad monitors for MS line, SG blowdown, and Condenser air Page 13 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS evacuation. Calls Chemistry for sample.

PSO checks SI discharge header pressure< 800 psig

US determines RCS leakage is NOT isolated and goes to step 16.

Step 16: US continues efforts to determine leak source by considering plant walk-downs or containment entry.

Step 17: Estimate RCS Leak Rate:

Crew stabilizes Tavg

PSO maintains Pzr level stable

Crew estimates leak rate using VCT level, Containment sump levels, and/or PZRlVCT mass balance.

Step 18: US verifies TS Compliance and determines the following apply:

T.S. 3.4.6.2, Reactor Coolant System Leakage, Action b. Action a will have to be evaluated once the exact leak location is determined.

T.S. 3.4.10, Structural Integrity, will have to be evaluated once the exact leak location is determined.

Allow the crew to estimate the leak size and determine Tech. Spec. Compliance or at Chief Examiners discretion, enter the next sequence of Events:

Page 14 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Event 6 Insert the following to fail Turbine control valve #2 As-Is, EHC Pumps partially open, following the impending turbine trip.

Trip with EOP Entry o SELECT: Sim Diagram MS3 D SELECT: CV2 D I SELECT: Fail As Is o I SELECT: INSERT RUN the following scenario to initiate loss of both EHC pumps:

o I SELECT: Scenario PSO(M),US(M),BOP(M) o SELECT: Demo exams Crew Responds to sequential loss of EHC pumps with o SELECT: Exam #01 EHC eventual complete loss producing an automatic Turbine/Reactor trip signal.

o SELECT: RUN Malfunction mfHF001, HF-P-54A, "An EHC Pump Over Alarms:

Current Trip will actuate. 07185 EHC PUMP A TROUBLE. Crew is expected to monitor HF pressure and dispatch an NSO to the EHC skid.

The crew may choose to have the BOP start the standby pump using "skill of the operator" or VPRO direction.

IF the crew does not start the standby EHC pump, it will start Alarms:

automatically at 1300 psig. 07180, EHC HEADER PRESSURE LOW 07183, EHC STANDBY PUMP AUTO START Page 15 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS The Crew should refer to 07185 VPRO for additional guidance:

Verify startedlstart EHC Pump B and leave control switch in run.

Stop EHC Pump A.

Verify EHC system operation per ON1031.10, Operation of Electro-Hydraulic control system.

Have an NSO check HF-P-54A or the breaker on MCC-141 <C66>

Following the loss of the "A" EHC pump, three minutes into The BOP should determine that HF pressure is Event 5, a combination of 1/0 overrides and malfunctions will decreasing. It is expected that the crew will trip the plant make it appear that there is a "problem" with the "B" EHC pump. based on continuously decreasing EHC pressure.

The scenario first simulates internal pump mechanical problems (loss of load and low amps) that eventually lead to a sheared Alarms:

shaft. 07180, EHC HEADER PRESSURE LOW A turbine trip - Reactor trip will occur when EHC pressure decays below 1100 psig or when MANUALLY tripped by the crew. The #2 turbine stop & control valves stick open requiring the crew to manually close the MSIVs to stop the cooldown. When the MSIVs are shut, two SG safeties, one on B and one on C steam lines will fail open.

The steam flow I cooldown will cause a safety injection (automatic or manual).

US will transition to E-2 at step 9 of E-O after SI has actuated.

The Crew will enter E-O:

Step 1: PSO verifies Reactor Trip Page 16 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Event 7 Step 2: BOP verifies Turbine Trip Turbine trip BOP(C), CCT*1: #2 Stop and #2 Control valves are failure stuck as-is. The BOP will have to recognize this from valve position and/or excessive cooldown, attempt a manual turbine trip, and then isolate steam by using MSIVs.

Step 3: BOP verifies power to emergency busses Step 4: PSO verifies SI is NOT actuated, and checks if SI is required:

RCS pressure <1800

Pressurizer Level < 7%

Containment Pressure> 4 pSig

RCS subcooling< 40 degrees

SG pressure < 585 PSO manually actuates SI, if automatic SI has not yet occurred.

NOTE: Skill of the operator could be used to start SI pumps at this point.

NOTE: Normally the PSO will be assigned actions to complete Attachment "An of E-O, while the BOP continues processing of E-O. It is possible that these roles could be reversed.

Step 5: PSO completes ESF Attachment A:

Verifies Phase A actuation by Status Panel

Verifies Safeguard Equipment alignment by Status Panel. Uses RNO to manually start SI pumps.

Page 17 of 21

2010 LOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Event 8 PSO{C)

SI pumps A & B SI pumps A & B will fail to auto-start on the SI signal and start failure require manual actions to start.

Verifies Feedwater isolation by Status Panel

Verifies both trains of PCCW Pumps running

Verifies ECCS flow (Based upon timing, if RCS pressure has decreased to <1700 psig, this step provides an additional opportunity to start SI pumps if not previously done, to meet CCT)

Verifies MS-V129 open

Verify both trains of Service Water Pumps operating

Verifies Service Water flow to EDGs > 900 GPM

Checks if Main Steam Lines should be isolated.

This should have been completed earlier based upon turbine control valve stuck open. Goes to next step.

Checks Containment pressure < 18 psig

Verifies EFW flow total> 500 gpm

Reset of RMO is not required

Notifies US of verification status including manual actions to start SI pumps.

Step 6: BOP monitors RCS temperature NOT stable, US refers to RNO:

Stops dumping steam

Checks MSR steam isolated

Monitors cooldown and adjust EFW flow to above 500 gpm

Throttles to maintain SG levels> 6% Narrow range in at least 1 SG.

With cooldown continuing, verifies MSIVS and Bypasses closed, and closes Upstream drain valves MSD-V-44 and 45.

Page 18 of 21

2010 lOIT 01 Rev. 2 EVENT INSTRUCTION COMMENTS Step 7: BOP Checks RCS isolated.

Step 8: BOP Checks if RCPs should be stopped and based upon subcooling > 40 degs. US Goes to step 9.

Step 9: BOP determines SG pressure boundary is NOT intact, based upon B & C SG pressures decreasing in an uncontrolled manner.

US proceeds to E-2, Faulted Steam Generator Isolation.

Step 1: BOP checks MSIVS and Bypasses Closed Step 2: BOP checks A & D SG pressure boundaries are intact.

Step 3: BOP identifies B & C SGs are faulted.

Step 4: BOP checks B & C SGs are not isolated and isolates steam flow to the EFW pump by closing MS-V 394. CCT*2 Step 5: BOP checks CST level> 250,000 gals.

Step 6: BOP checks secondary radiation is normal.

Step 7: PSO checks if ECCS flow can be reduced:

Subcooling > 40 deg.

Secondary heat sink> 65 % SG wide range level

RCS pressure stable or increasing

PZR level> 7%

US transitions to ES- 1.1 SI Termination, Step 1 or E-1 if the steam generators have not yet completely blown down.

During the post-scenario JPM, the US will evaluate the correct Emergency Response classification based on SUS, RCS leak Terminate Terminate the examination when the crew transitions to ES-1.1 Anticipated AOP/EOP flow-path: OS1235.05, Exam SI Termination, or E-1, loss of Reactor or Secondary Coolant, OS1201.07, OS1201.02, E-O, E-2, ES 1.1 or E-1 or at the Chief Examiner's discretion. Possible brief transition may be from E-O to ES-0.1 and back to E-O, based upon timing.

Page 19 of 21

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DEIVIONSTRATIVE EXAM # 01 Rev. 2 CREW CRITICAL TASKS

1. MANUALLY actuate main steamline isolation or close IVISIVs before a severe (Orange Path) challenge develops to either the subcriticality or the integrity CSF or before transition to ECA-2.1, whichever happens first,(CCT E-O,O)

2. Isolate the faulted Steam Generators before transition out of E-2, Faulted Steam Generator Isolation, or ECA-2.1, Uncontrolled Depressurization of All Steam Generators.(CCT E-2,A)

Page 21 of 21

'Appendix D Scenario Outline Form ES-D-1 Seabrook Station 2010 NRC Exam-Simulator Scenarios Facility: ,Seabrook Scenario No.: ~ Op-Test No.:

Examiners: Dave Silk Operators:

Initial Conditions: MOL, 100% Power.

Turnover:

The plant is at 100% power.

Decrease plant power at 1O%/hr to 45% power to allow for repairs of FW-P-32A oil leak. Currently at Step 1.3 of OS1 000.06, Figure 6

Main Steam Atmospheric Steam Dump ("A" ASDV). MS-PV-3001 is Danger Tagged closed due to excessive seat leakage. MS-V-5 is closed and tagged. Tech. Spec. 3.7.1.6 and 3.6.3 were entered 4 days ago.

I

SW-P-41 C tagged out for motor replacement.

Event Malf. No. Event Event No. Type* Description 1 PSOR Decrease plant power @ 10%/hr.

BOPN USN 2 ttRCTT411 PSOI RCS Loop 1 T cold will fail high causing inward control rod US I,TS motion.

3 ptMSPK3004 BOPC "D" ASDV controlling pressure channel will fail high causing USTS "D" ASDVto open.

4 mfCS012 PSOC Letdown line leak requiring letdown isolation.

US C, TS 5 mfED038 PSOM loss of Offsite Power, complicated by "A" EDG failure to start, mfED031 BOPM "B" EDG starts then trips on low oil pressure and Steam Driven EFW pump trips on overspeed.

mfED034 USM avMSVSV2 6 mfSW013 BOPC On Bus 6 power restoration from SEPs no Service Water mfSWD15 Pump will start.

mfSW017 The Motor Driven EFW Pump Trips on Overcurrent.

mfFW055 7 rmvMSV129 BOPC Crew directs reset and restart of FW-P37A (terry turbine) to USC establish EFW flow to the Steam Generators.

(N)ormal. (R)eactivity. (I)nstrument, (C)omponent. (M)ajor Note: Anticipated AOP/EOP flow-path: OS 1201.08, OS 1201.02, E-O. ECA-D.D, E-D. ES-D.1 1

SEABROOK 2009*2010 LOIT NRC SIMULATOR EXAMINATION # 03 Rev. 2 OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL THAT FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 NRC INITIAL EXAM SECURITY AGREEMENT.

PREPARED BY: DATE: _ _ __

- - - - -INSTRUCTOR REVIEWED BY: DATE: _ _ __

SME (Optional)

APPROVED BY: DATE: _ _ __

TRAINING SUPERVISOR

2010 LOIT 03 Rev. 2 SCENARIO The simulator is initialized at 100% power. SW-P-4'1 C is danger tagged out for motor replacement. 'A" ASDV is tagged out of service due to seat leakage.

The A Main Feed Pump has a small control system oil leak that cannot be repaired with the pump operating. The crew will start a 10% per hour downpower to 45% power.

The Loop 1 Tcold instrument (TE-411) will fail high. The crew responds with OS1201.08, "Tave/Delta T Instrument Failure".

The "D" ASDV controlling pressure channel will fail high causing "D" ASDV to open. The BOP operator should recognize the "D" ASDV opening is due to a failed pressure channel. The ASDV controller is placed in MANUAL and the valve is closed to prevent an uncontrolled power/reactivity increase.

A leak in the letdown line at the inlet to the Reactor Coolant Filter will be initiated.

Letdown flow will be reduced approximately 50%, causing VCT level to decrease. The crew responds using OS1201.02, "RCS Leak".

A Loss of Offsite Power will occur. The 'B' EDG will start and then trip on low lube oil pressure caused by a lube oil leak. The 'A' EDG fails to start. The crew will recover power to Bus E6 via the Supplemental Emergency Power System (SEPS).

The EFW Turbine Trip Throttle valve will close for unknown reasons. Recovery of the EFW turbine will be delayed until later in the scenario.

Upon restoration of power to Bus E6, the "B' train SW pump will not Auto restart and action must be taken to start a pump to restore SW flow. The crew will enter E-O and ECA-O.O for these events.

During the recovery of Bus E6, the Motor Driven EFVV Pump will trip on Overcurrent requiring the use of the Turbine driven EFW pump to restore EFW flow to the SGs.

Anticipated AOP/EOP flow-path: OS1201.08, OS1201.02, E-O, ECA-O.O, E-O, ES-0.1 Page 2 of 22

2010 LOIT 03 Rev. 2 SIMULATOR SETUP

1. Reset the simulator to a 100%, Middle of Core Life condition. This setup has been snapped to password protected IC92. Alternately, any other 100% IC (IC-30) can be used, and conditions established using Scenario Sim test EV3 or manually input as described below.

2. D Set Protected Train as "8" on MPCS and MC8

3. If EV3 is to be used, establish the exam setup by running the following scenario:

D Select: Scenario D Select: Len D Select: Sim test EV3 D Select Run

4. D Verify the following conditions were entered:

5. Insert the following Malfunction and Overrides to fail the Auto Start of "A" EDG; Electrical Distribution:

D IMF mfED031, DG-1A Auto Start Failure D Override the DG-1A Emergency Start pushbutton to RELEASE.

D On Panel Graphic PHF09, Override the "A" EDG Emergency Stop Push buttons to STOP

6. Insert the following Malfunction to Trip the "8" EDG on Low Lube Oil Pressure, Electrical Malfunctions:

D I IMF mfED034, DG-18 Low Lube Oil Press Trip

7. Set up the ASDV "A" Closure and Isolation with MS-V5:

~

D On Sim Diagram MS1, for MS-V5 Select the Remote Function, rfMS009, and Set Final value to 0 D On MS-PK-3001, place the controller to Manual and Minimum Output On Sim Diagram MS1, MS-PV-3001, Component Malfunction D SELECT: FAIL CLOSED D . SELECT: INSERT D PLACE MC8 jog switch to CLOSED for MS-PV-3001 and place a Control 80ard Continued on next page.

Page 3 of 22

2010 LOIT 03 Rev. 2

8. Using Malfunctions, Service Water, Insert the following malfunctions to prevent Auto Start of SW-P-41 B, 410 and P-110B o IMF mfSW013, SW-P-41 B Fails to Auto Start o IMF mfSW015, SW-P-41D Fails to Auto Start o IMF mfSW017, SW-P-110B Fails to Auto Start

9. Activate trigger for FW-P-37A Overspeed.

I LOIT, L30591, Loss of FW-P-37A on Overspeed

10. Setup the Malfunction for FW-P-37B to Trip on Overcurrent after starting in ECA-O.O.

o Malfunctions, Feedwater o SELECT: mfFW055, FW-P-37B Overcurrent Trip o SELECT: INSERT

11. Tag out SW-P-41 C by inserting the following:

o Override cSWP41 C, SW-P-41 C breaker racked out o Remote Function cSWV22, SW-V-22 breaker open o Tag the Control Switch for SW -P-41 C Page 4 of 22

2010 LOIT 03 Rev. 2 SHIFT TURNOVER

The plant is at 100% power.

Decrease plant power at 10%/hr to 45% power to allow for repairs of FW-P-32A oil leak.

Currently at Step 1.3 of OS1000.06, Figure 6

Main Steam Atmospheric Steam Dump ("An ASDV), MS-PV-3001 is Danger Tagged closed due to excessive seat leakage. MS-V-5 is closed and tagged. Tech. Spec.

3.7.1.6 and 3.6.3 were entered 4 days ago.

SW-P-41 C tagged out for motor replacement.

Page 5 of 22

2010 LOIT 03 Rev. 2 SCENARIO OUTLINE EVENT INSTRUCTION COMMENTS Shift Turnover Shift turnover information as stated. Operators should review alarms and indications Event 1: PSO (R) BOP (N) US (N)

Decrease plant The crew should prepare for and initiate a plant shutdown at power @ 10%/hr. 10%/hr. The US should use OS1000.06, Power Decrease procedure and reference Figure 6, Rapid Power Decrease Guidelines.

Unit Supervisor: A brief reactivity review will take place discussing the temperature limits for Tave to be used in the power decrease. The temperature band will normally be -3°F to +3°F. Boration will be used for temperature control during the power decrease. Control rods will be used for AFD and temperature control.

Turbine Operations: The BOP will decrease turbine load using automatic DEHC operations. Using the laminated sheets, Figure 12 of OS1000.06, The basic steps are:

Insert the desired loading Rate.

Insert the desired Power Level.

Monitor turbine loading using "Load Status" is Unloading and "Load Actual" decreases.

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

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

Reactor Power change: The crew will use control rods in automatic to control temperature during the turbine load decrease. Using 001-56, a boration value will be determined to change the boron concentration and decrease power/temperature. If control rods are used in manual the operator will verify rod speed. place the Rod Motion Selector Page 6 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS (in-Hold-Out) switch to the "IN" direction and insert the rods a maximum of three steps. He will monitor temperature and power as confirmation of his actions.

Using the laminated sheets for Figure 3 of OS1 008.01, Boration Check List, the RO will set up the controllers for the required boration volume and rate.

The high level steps are:

Verify the pumps in AUTO

Verify the makeup valves are in AUTO

Place Blender Mode Start Switch to STOP

Place the Mode Selector Switch to Borate

Set the quantity on CIS-FIQ-111 and CIS-FIQ-110 controllers

Set the Mode Start Switch to START

Verify the pumps and valves respond

Verify Plant Response.

Restore System to Automatic control.

Allow the crew to commence the downpower or at Chief Examiners discretion prior to entering the next Event.

Page 7 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS Event 2: PSO (I) US (I,TS)

RCS Loop 1 Tcold RCS Loop 1 Tcold will fail high causing inward control rod fails high motion.

Initiate the instrument failure as follows: Control Rods step in based on TavglTref deviation.

o I SELECT Malfunction: Reactor Coolant The crew should diagnose that rods are stepping in due to an i instrument failure. The PSO should recommend and/or the Unit (Component)

Supervisor should direct the PSO to place rods in manual using o I SELECT Component: ttRCTT411 "skill of the operator."

SELECT: FAIL HIGH o I SELECT: INSERT Alarms:

F5298, OTOT Chan Trip 04422, Average Tavg High 04421, Tavg-Tref Deviation 87457, Rod Motion Detected UL-6, A3, RC Loop 1, T8-411 C OTOT, momentarily lit, transient condition The crew responds using OS1201.08, TavglDelta T Instrument Failure:

Step 1: The PSO should identify that Loop 1 Tave instrument has failed.

Step 2: The US should direct the PSO to place rods in MANUAL. This action may already have taken place prior to the procedure step as a "skill of the operator" task.

Page 8 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS

BOP checks condenser steam dumps closed.

PSO adjusts charging and letdown flow as necessary to restore PZR level.

Step 3: The PSO defeats the Loop 1 ~T input, Loop 1 Tavg input, and selects a non-affected loop for the ~T,OT,OP recorder.

The following Alarms Reset:

F5298, OTDT Chan Trip 04422, Average Tavg High The following alarms will have occurred and will remain in alarm:

VAS F8115, RC Loop 1 Tavg Deviation VAS F8119, RC Loop 1 Delta T Deviation Step 4: The PSO verifies that Tavg is within 1°F of Tref.

If not, the US directs PSO to manually withdraw rods or the BOP to reduce turbine load to restore temperature.

PSO places rods back in automatic.

PSO checks PZR level at program, and restores level control to automatic

BOP checks steam dumps in NA RESET NOTE; As a power decrease is planned rods may remain in MANUAL.

Step 5: The RO should verify that there are no redundant bi stable lights lit for the following:

UL-1, T Avg Lo Loop To FW Iso

UL-1, T Avg Lo-Lo Loop Stm Dmp Iso

UL-6, RCS Loop OT~T

UL-6, RCS Loop OP~T

UL-12, Tavg Lo Loop To FW Iso Page 9 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS Step 6: The Unit Supervisor should identify Tech. Spec. 3.3.1, Reactor Trip System Instrumentation, Item 7, Over Temperature ~T and Item 8, Over Power ~T are applicable.

Requires affected bistables to be placed in the trip condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

T.R 19, Feedwater Isolation On Low Tavg Coincident With Reactor Trip is not applicable due to 3 other channels available.

If I&C is directed to bypass the failed instrument, RCS The Unit Supervisor may coordinate with I&C to place the Loop 1 Tcold, RC-TI-411, perform the following: affected bistables to bypass, using BTl, for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D I SELECT:CP1Bypass Cabinet SELECT: Door Open SELECT: Enable SELECT: Panel Overview SELECT: BTl CP1 Position the following switches to bypass:

D I TB411G D I TB411C TB412G TB412C SELECT: CP1 Bypass Cabinet SELECT: Door Closed I SELECT: Enable Allow the crew to complete the abnormal procedure or at Chief Examiners discretion prior to entering the next Event.

Page 10 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS Event 3: o I SELECT: MALFS BOP (C), US (TS)

ASDV Failure D I SELECT: Main Steam (Component) "D" ASDV controlling pressure channel will fail high causing "D" ASDV to open.

SELECT: ptMSPK3004 SELECT: Fail to Specified Value Alarms:

D5217, ASDV D Not Full Closed INSERT FINAL VALUE: 1500 D INPUT RAMP TIME: 45 BOP operator recognizes "D" ASDV opening due to a failed pressure channel.

D SELECT: INSERT Using "Skill of the Operator" the US will direct taking manual control of the ASDV and closing the valve.

The BOP will place the ASDV controller in MANUAL and close the valve to stop uncontrolled power/reactivity excursion.

The BOP/Crew should also refer to the Alarm Response Procedure for D5217 to verify response.

Verify S/G pressure and compare to ASDV controllers setpoint. (instrument failure)

Adjust ASDV controller setpoint and/or transfer steam load the condenser as required. (Not required)

If an ASDV has failed open:

o PlacesNerifies ASDV control switch in close o Locally isolates ASDV as necessary by closing MS-V-49. (Not necessary) o PlacesNerifies controller for the ASDV in manual minimum Page 11 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS

The US evaluates Tech. Specs:

o TS 3.7.1.6, Atmospheric Relief Valves. The crew is already in Action A due to the "AI! ASOV being tagged out. The US should determine that the "0" ASOV is operable, based upon the availability to control the valve using the "Jog" switch. No additional actions are required.

o TS 3.6.3, Containment Isolation Valves. The valve remains operable as a containment isolation valve, no additional actions are required.

Following US review of Tech. Specs. or at Chief Examiners discretion continue with the next Event.

Page 12 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS Event 4: D SELECT: Malfunctions PSO (C), US (C,TS)

Alarms:

Initiation of a D SELECT: Chemical and Volume Control:

RDMS High Alarm, RM6541, PAB 7 ft North letdown line B7399, RCS Unidentified Leak Rate High SELECT: mfCS012, Letdown Line Leak At Filter leak.

B8266, RCS Unidentified Leak Rate Warning Inlet To Reactor Coolant RDMS High Alarm, RM6508-2, High Range PAB North EI-7 INPUT Value: 0.5 D I SELECT: INSERT

RO should identify decrease in VCT level.

NOTE: The crew could initially enter OS1252.03 Area High Radiation abnormal.

~

I The crew responds with OS1201.02, RCS Leak:

The Unit Supervisor should alert the crew to the Caution Statement prior to step 1:

If the plant is in Mode 1,2,or 3 with SI accumulators aligned for injection and pressurizer level can not be maintained greater than 7% using normal charging lineup, then perform the following:

1) Trip reactor

2) When the reactor trip is verified, then actuate SI

3) Go to E-O, REACTOR TRIP OR SAFETY INJECTION.

Step 1: The PSO will control charging and letdown flow as necessary to maintain pressurizer level, and verify that pressurizer level is stable or increasing.

This is a continuous action step. The RNO response for this step reflects the information contained in the procedure caution as described above.

Step 2: The US may refer to ER-1.1, Classification of Emergencies for potential E-Plan classification.

Step 3: The crew should identify that a eves leak is suspected. The US should proceed to Step 6.

Step 6: The Unit Supervisor will direct the PSO to isolate letdown.

Page 13 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS

The PSO will close the following valves:

o CS-HCV-189 o CS-HCV-190 o CS-V-145 o RC-V-81

PSO isolates charging to the loops:

o Closes CS-HCV-182 o Maintains seal inj. flow 6-13 gpm utilizing CS FCV-121 in manual.

o Closes Charging Line isolation valves CS-V-142 and CS-V-143.

Alarms:

When letdown flow is isolated the following alarms will occur:

VAS B8166, Pzr Stm/Chg Line AT Approach When the charging line isolation valves are closed the following alarms will occur:

VAS D7853, Chg Pmp Disch Combined Hdr Flow Low VAS D7872. Chg Header Contm Iso VLV-142 Closed VAS D7873, Cng Header Contm Iso VLV-143 Closed When a VCT auto makeup occurs at 30% level the following alarm will occur" VAS D4660, BA Makeup VLV-110B to Chg Pmp Open Step 7: The crew should identify that the leak is isolated by verifying the following parameters:

Instructor CUE: After completion of Step 7, have the NSO

Pressurizer level-Increasing at a rate equal to the report that the leak appears to be from the inlet to the difference between seal injection and seal return.

reactor coolant filter, CS-F-1.

Containment air particulate and gas monitor. Stable or Decreasing. Since the leak was in the PAB, the US may also reference PAB monitors.

Containment temperature and pressure. Stable or Page 14 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS Decreasing

Containment sump A and B levels. Normal or Decreasing Step 8: The crew will be checking charging and letdown system integrity based on:

VCT level decrease-Equal to the difference between seal injection and seal return.

PAB radiation levels-Stable or decreasing.

NOTE: The outcome of these verifications is time dependent. The RNO step directs dispatching HP/NSO's to determine the source of the leak. If the source cannot be identified the step directs entering OS1202.02, Charging System Failure. The crew could also enter procedure OS1252.03, Area High Radiation abnormal.

Step 9: The Unit Supervisor should direct the PSO to establish excess letdown. Excess letdown is necessary to remove the inventory being added to the ReS via seal injection flow.

NOTE: Do not exceed Excess Letdown Heat Exchanger outlet temperature of 175°F. Do not exceed Excess Letdown Heat Exchanger outlet pressure of 150 psig.

The PSO establishes excess letdown as follows:

Opens CC-V-434, Excess Letdown Heat Exchanger Cooling Water isolation valve

Checks open CS-V-167 and 168, Excess Letdown Containment Isolation valves

Checks closed CS-HCV-123, Excess Letdown flow control valve.

Opens CS-V-175 and 176, Excess Letdown Containment Isolation valves.

Flushes Excess Letdown to RCDT, Aligns CS-V-170 to RCDT, Slowly opens CS-HCV-123 to flush for greater Page 15 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS than 5 minutes, then closes CS-HCV-123.

Aligns CS-V-170 to Seal Return Header.

Establish Excess Letdown flow via CS-HCV-123. The RO should limit flow such that excess letdown heat exchanger outlet temp is <175°F and outlet pressure is

<150 psig.

Using the MPCS, the PSO will remove data point A0620, Letdown Outlet Flow, from the plant calorimetric calculation.

Step 10: PSO confirms RCS Leakage has stopped by verifying:

VCT level stable

Containment radiation particulate & gas stable or decreasing

Containment temperature and pressure stable or decreasing

Containment sump A & B level trends decreasing or normal Step 11: US Minimizes effect of loss of Normal letdown:

Contacts Chemistry & HP regarding loss of demin. flow and RCS hydrogen maintenance,

Verify Tech. Spec. Compliance: These T.S. 's are not currently applicable however, follow up will be needed if RCS chemistry samples indicate limits exceeded.

o T.S. 3.4.7, Chemistry o T.S. 3.4.8, Specific Activity US goes to step 18 Step 18: US verifies Tech. Spec. Compliance:

T.S. 3.4.6.2, Reactor Coolant System Leakage

T.S. 3.4.10, Structural Integrity Since the leak was on the letdown System, this is not considered RCS leakage and T.S. does not apply.

Following US review of Tech. Specs. at step 18 or at Chief Examiners discretion continue with the next series of Events.

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2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS Event 5: Initiate the loss of power as follows: PSO (M), BOP (M), US (M)

~~~~------------------------~

The plant D SELECT: Malfunctions The Cr~w enters E-O and performs the Immediate Actions steps has .a loss of D SELECT: EI ect' rica I D'ISt rI'b U t'Ion and eXits at step 3 to ECA-O.O.

offsite . ECA-O.O, LOSS OF ALL AC POWER power. D SELECT: mfED038, Loss of OffsIte Power. Step 1: The RO verifies that the reactor is tripped:

D SELECT: INSERT

Checks reactor trip and bypass breakers open.

Checks neutron flux decreasing.

Trip the Turbine Driven EFW urn as follows:

D SELECT: 5im Diagram: FW3 Step 2: The BOP verifies that the turbine is tripped:

Checks all stop valves closed.

D LEFT Click on MS-V129

Checks generator breaker open.

D SELECT: MANUAL ADJUST SELECT: Final Position =0 NOTE: The 'A' DG fails to start and no actions will recover the

'A' DG. The 'B' EDG will trip on Low Lube Oil Pressure.

D I SELECT: INSERT Step 3: The PSO checks the RCS Isolated, NOTE: This pump wiii not be restored until after the

.Pressurizer PORVs closed power restoration in ECA-O.O. Provide delay statements

.Letdown isolation valves closed to control room if asked about status, i.e., can not reset CS-V-14S valve, having difficulty with washer and need Or maintenance assistance. RC-LCV-4S9 Or NOTE: If the crew request the B EDG placed in RC-LCV-460 Maintenance: .Closes Excess Letdown valves CS-V-17S and 176 I SELECT: Local Panels D I SELECT: DG System -RCS Sample Valves closed D SELECT: DG B SELECT: 55-9710 to Maintenance Page 17 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS Instructor CUE: Step 4: The BOP should identify that there is no EFW flow.

MS-V-129 is tripped closed but no indication due to LOP.

NSO will find a large quantity of oil on the "B" The crew should utilize Step 4 RNO, and direct an NSO to EDG skid. Finds oil line to engine oil pressure locally start the steam driven EFW pump per OS1036.03, switches ruptured. RESETTING THE STEAM DRIVEN EFW PUMP TRIP VALVE.

Step 5: The crew should continue efforts to restore power.

NSO finds nothing obviously wrong with "Au SEP's is available EDG. If directed by crew to prevent

BOP place UAT and RAT breaker switches in Pull-To uncontrolled start, use DG Local Panels to set Lock.

LOCAL on the LOCAL/REMOTE switch.

BOP should attempt an emergency start of EDG 'A'.

Instructor Cue; A Slave relay start at K603 test

If previously directed by the crew, as time switch S909 is unsuccessful.

allows, report as HP that steam lines show no Neither EDG will be able to function. The RNO for this step is to change in radiation levels. use the SEP's diesel generator. SEP's is available.

Event 6 Instructor CUE: Upon Bus 6 power restoration from SEPs no Service SW pump does Delay restoration of EFW flow from the turbine water pump will start. The Motor Driven EFW Pump Trips not auto-start driven pump until Bus E6 is re-energized and B on Overcurrent.

EFW pump trips on Overcurrent.

This satisfies aCCT.

CCT2 US directs Step 5 RNO: B: BOP performs the following:

!E...SEPS bus feeder breaker is aligned to Bus 6, THEN:

1) Places the following equipment control switches in PULL TO LOCK position:

DG 1B output breaker

CBS-P-9B

SI-P-6B

2) Manually closes SEPS Bus 6 breaker.

3) US goes to Step 5f.

Page 18 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS Step 5f: Verifies EPS - ACTUATED AND SEQUENCING When the crew dispatches an NSO to the field to Step5g: Crew checks equipment loaded:

reset the EFW pump, perform the following

Charging pump

Thermal barrier cooling pump (around step 5Q of ECA-O.O):

PCCW pump o IUSing Panel Graphic FW3: Open FW-V-346

EFW pump o SELECT: Component Remote Functions BOP (C): The EFW Pump will trip on Overcurrent when the Bus is re-energized, requiring the Turbine Driven EFW Event 7 Summary Pump to be restored to recover feedwater flow and SG EFW pump trip o !SELECT: rmvMSV129 level.

o SELECT: Manual Adjust

SW or cooling tower pump NOT running, BOP must Reset RMO and manually start SW-P-41D.

o SELECT: 1.0 BOP (C), CCT 1: Sub step g. has the operator verify one o ISELECT INSERT I ocean SW pu.mp o.r cooling t?wer pump running. The crew should Identify that Tram 'B' has no pumps Event 6 running. The RNO for the step directs manually starting a (Continued) SW pump. The RMO relay needs to be reset to restart the Restoration of SW SWpump.

BOP Checks AC emergency busses - AT LEAST ONE ENERGIZED

BOP Checks AC emergency busses - ALL ENERGIZED

BOP Checks emergency bus - NOT POWERED BY EMERGENCY DIESEL. US refers to Step 5j. RNO: If Emergency Bus is powered by SEPS, then maintain SEPS load limit per ATTACHMENT A while performing actions in other procedures in effect.

Page 19 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS

US returns to procedure and step in effect. FRPs shall now be implemented as required.

If a RED path exists at this time for Heat Sink, the crew will transition to FR-H.1, Response to Loss of Secondary Heat Sink, and verify actions to recover the turbine driven EFW pump are successful to restore >500 gpm EFWflow.

Crew Returns to E-O Step 3 as the procedure and step in effect:

Step 3A: BOP verifies AC emergency busses - AT LEAST ONE ENERGIZED Step 3B: BOP responds AC emergency busses - BOTH NOT ENERGIZED. US refers to 3B RNa: Try to restore power to other train from emergency diesel generator or offsite source as time permits. Do NOT use SEPS.

SEPS is supplying Bus E6.

Step 4: PSO Checks If SI Is Actuated:

Checks SI annunciators NOT lit for train A and B US Refers to RNa to Check if SI is required:

RCS pressure - LESS THAN 1800 PSIG

Pressurizer level - LESS THAN 7%

Containment pressure - GREATER THAN 4 PSIG

RCS subcooling - LESS THAN 40°F

Any SG pressure - LESS THAN 585 PSIG If SI was actuated, the crew will continue with SI should NOT be required:

E-O step 5. IF SI is required, THEN manually actuate.

Page 20 of 22

2010 LOIT 03 Rev. 2 EVENT INSTRUCTION COMMENTS SI should not be required and crew IF SI is NOT required, THEN go to ES-0.1, REACTOR TRIP transitions to ES~0.1, Reactor Trip Response. RESPONSE, Step 1 Anticipated AOP/EOP flow-path: OS1201.08, OS1201.02, E-O, ECA-O.O, E-O, ES-0.1 Terminate examination when the crew transitions to ES-0.1 and stabilizes RCS temperature with the ASOVs, or processes past step 5 of E-O or at Chief Examiner direction.

Instructor NOTE: restore A-Point A0620, Letdown Outlet Flow, to scan at the end of the scenario.

Emergency Plan:

The charging system leak does not qualify as an RCS leak, so no e-plan call is made based on this event.

Post scenario JPM- Alert E-plan classification on:

Alert based upon EAL SA4, Unplanned Loss of most or all safety system annunciation or indication in Control Room (ROMS) with a significant transient in progress.

Alert based upon EAL SA5, Power to AC emergency buses reduced to a single power source for >15 minutes such that any additional single failure would result in station blackout. (as validated)

IF 15 minutes had elapsed from the start of Event 5 (LOP Event) until the SEPS breaker was closed at ECA 0.0 step 5.b RNO, then SAE on EAL SS1,Both AC buses E5 and E6 de-energized for> 15 minutes Page 21 of 22

2010 LOIT 03 REV. 2 CREW CRITICAL TASKS

1. Manually start an ocean Service Water Pump or a Cooling Tower Pump.

2. Energize at least one AC Emergency bus before transition out of E-O, Reactor trip or Safety Injection, unless the transition is to ECA 0.0, in which case the critical task must be performed before placing safeguards equipment in the pull to lock position as directed by Step 6 of ECA-O.O.

Paqe 22 of 22

v t e Letter Sequence Other
TAC:U01694, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML103490597, ML103490620, ML103490635, ML103490648, ML103490663
MONTHYEAR2010-12-10 [Table View]

ML103490648

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