Text

301 Initial Exam Final Administrative JPMs
	ML13325A960
Person / Time
Site:	Harris
Issue date:	11/18/2013
From:	; NRC/RGN-II
To:	; Duke Energy Progress
References
	50-400/13-301
	Download: ML13325A960 (74)
	v • d • e

Appendix C Job Performance Measure Form ES-C-i Worksheet Facility:

Shearon Harris Task No.:

119015H301 Task

Title:

Determine Active I Inactive Status JPM No.:

2013 NRC Admin Of Off Shift License Personnel JPM RO SRO Al-i K/A

Reference:

G2.l.l 3.8 /4.2 Alternate Path: No Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The plant was at 100% power, when the OAC has a medical emergency Initial Conditions and will not be able to work his next scheduled shift.

The Operations Resource Scheduler has contacted four off shift individuals to replace the OAC on the following day.

Initiatin Cue You are to determine if each of the Licensed Operators is eligible to g

work the OAC position on the 0700

- 1900 shift on September 13, 2013.

2013 NRC Admin Exam RO SRO Al-i Rev. Final

Appendix C Job Performance Measure Form ES-C-I Worksheet Task Standard:

Determines the Training Department Rotation of Assignment and Work Control Operator license are Active and eligible to stand the 0700

- 1900 shift on September 13, 2013 Required Materials:

Calculator General

References:

OMM-00l, rev 98 Handouts:

JPM Cue Sheets Pages 7 - 8 Time Critical Task:

No Validation Time:

15 minutes Critical Step Justification Must determine the Active I Inactive status of Operator license correctly Step 2 or an ineligible Operator may stand watch Ste 3

Must determine the Active I Inactive status of Operator license correctly or an ineligible Operator may stand watch Must determine the Active / Inactive status of Operator license correctly Step or an ineligible Operator may stand watch Ste 5

Must determine the Active I Inactive status of Operator license correctly or an ineligible Operator may stand watch 2013 NRC Admin Exam RO SRO Al-i Rev. Final

Appendix C Page 3 of 9 Form ES-C-I PERFORMANCE INFORMATION Start Time:

Performance Step: I OBTAIN PROCEDURE Standard:

Obtains OMM-OO1 and refers to Section 5.5 Maintenance of NRC Operator Licenses.

Comment:

V Performance Step: 2 Determine if the Active I Inactive status of FIN Team Operator license Standard:

Candidate determines the license is Inactive and NOT ELIGIBLE because the operator did not work the required 5 twelve hour shifts in a license position during the previous quarter.

Comment:

V Performance Step: 3 Determine if the Active I Inactive status of Training Department Rotation of Assignment Operator license Standard:

Candidate determines the license is Active and ELIGIBLE because the license was reactivated in the previous quarter.

There is not a requirement to complete the normally required 5 twelve hour shifts in a license position during the quarter.

(i.e. could complete the reactivation during the last week of a quarter, thus the opportunity would not be available to work the 5 shifts)

Comment:

V

- Denotes a Critical Step 2013 NRC Admin Exam RO SRO Al-i Rev. Final

Appendix C Page 4 of 9 Form ES-C-i PERFORMANCE INFORMATION V

Performance Step: 4 Determine if the Active I Inactive status of Work Control Operator license Standard:

Candidate determines the license is Active and ELIGIBLE because the operator worked the required 5 twelve hour shifts in a license position during the previous quarter.

Comment:

V Performance Step: 5 Determine if the Active I Inactive status of Procedure Writers Group Operator license Standard:

Candidate determines the license is Inactive and NOT ELIGIBLE because a required license position was NOT reactivated in the previous quarter AND the individual did not work the required 5 twelve hour shifts in a license position during the quarter. (te.

STA position is not an on shift position that is credited for a license operator watch)

Comment:

Performance Step: 6 Determines the licensed operators eligible to stand the 0700 1900 shift on September 13, 2013 Standard:

Determines the Training Department Rotation of Assignment and Work Control Operator license are Active and eligible to stand the 0700- 1900 shift on September 13, 2013 Evaluator Cue:

CRS acknowledges determination of eligible watch standers END OF JPM Comment:

Stop Time:

V

- Denotes a Critical Step 2013 NRC Admin Exam RO SRO Al-I Rev. Final

Appendix C Page 5 of 9 Form ES-C-I PERFORMANCE INFORMATION KEY Four Reactor Operators have the following history:

All four are current in License Operator Requalification Training and have had a medical examination in the past 2 years.

None of the 4 have worked any shift since 06/30/13.

None of the 4 would exceed 10 CFR Part 26 (fatigue hours) requirements by standing this shift Active/Inactive status and time on shift since April 1, 2013 is as follows for each Reactor Operators:

FIN Team Operator License was active on April I 2013 4/02/13

- worked 0700-1900 shift as OAC 4/03/13

- worked 0700-1900 shift as BOP 5/04/13

- worked 0700-1900 shift as CRS 6/14/13

- worked 0700-1 900 shift as STA 6/17/13

- worked 1900-0700 shift as CRS Training Department Rotation of Assignment Operator License was inactive on April 1, 2013 5/02/13 thru 5/06/13 worked 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months under the direction of the OAC and completed all requirements for reactivation.

5/10/13

- worked 0700-1900 shift as BOP 5/12/13

- worked 0700-1 900 shift as OAC 5/1 4/13

- worked 1900-0700 shift as QAC 5/31/13

- worked 1900-0700 shift as BOP Work Control Operator License was active on April 1, 2013 4/23/13 - worked 0700-1900 shift as OAC 4/25/13 - worked 0700-1900 shift as BOP 5/05/13 - worked 0700-1900 shift as OAC 5/14/13 - worked 1900-0700 shift as BOP 6/17/13 - worked 1900-0700 shift as OAC Procedure Writers Group Operator License was active on April 1, 2013 4/12/13 thru 4/16/13 worked 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months under the direction of the STA and completed all requirements for reactivation.

4/14/13

- worked 1900-0700 shift as STA 4/18/13

- worked 0700-1900 shift as STA 5/12/13

- worked 0700-1 900 shift as OAC 5/14/13

- worked 1900-0700 shift as BOP 5/31/13

- worked 1900-0700 shift as CRS To maintain active status, licensed individuals shall actively perform the functions of an operator or senior operator on a minimum of five 12-hour shifts per calendar quarter.

OR A minimum of 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions under the direction of an operator or senior operator as appropriate and in the position to which the individual will be assigned. The 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months must have included a complete review of all required shift turnover procedures.

V

- Denotes a Critical Step 2013 NRC Admin Exam RO SRO Al-I Rev. Final

Appendix C Page 6 of 9 Form ES-C-i PERFORMANCE INFORMATION KEY 1.

FIN Team Operator ELIGIBLE GIBLE 2.

Training Department Rotation of Assignment Operator....BLE NOT ELIGIBLE 3.

Work Control Operator BLE CT ELIGIBLE 4.

Procedure Writers Group Operator ELIGIBLE IGIBLE

- Denotes a Critical Step 2013 NRC Admin Exam RO SRO Al-i Rev. Final

Appendix C Page 7 of 9 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2013 NRC JPM RO SRO Al-i Determine Active I Inactive Status Of Off Shift License Personnel OMM-00i Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

20i3 NRC Admin Exam RO SRO Al-i Rev. Final

Appendix C Page 8 of 9 Form ES-C-I JPM CUE SHEET Name:

Date:

The plant was at 100% power, when the QAC has a medical emergency and will not be able to work his next scheduled shift.

The Operations nitia Ofl itions.

Resource Scheduler has contacted four off shift individuals to replace the OAC on the following day.

You are to determine if each of the Licensed Operators is eligible to Initiating Cue:

work the CAC position on the 0700 - 1900 shift on September 13, 2013.

After making the determination of License Operator eligibility circle their status below:

1.

FIN Team Operator ELIGIBLE / NOT ELIGIBLE 2.

Training Department Rotation of Assignment Operator ELIGIBLE / NOT ELIGIBLE 3.

Work Control Operator ELIGIBLE / NOT ELIGIBLE 4.

Procedure Writers Group Operator ELIGIBLE / NOT ELIGIBLE 2013 NRC Admin Exam RO SRO Al-i Rev. Final

Appendix C Page 9 of 9 Form ES-C-i JPM CUE SHEET Four Reactor Operators have the following history:

All four are current in License Operator Requalification Training and have had a medical examination in the past 2 years.

None of the 4 have worked any shift since 06/30/13.

None of the 4 would exceed 10 CFR Part 26 (fatigue hours) requirements by standing this shift Active/Inactive status and time on shift since April 1, 2013 is as follows for each Reactor Operators:

FIN Team Operator License was active on April 1, 2013 4/02/13

- worked 0700-1900 shift as OAC 4/03/13

- worked 0700-1 900 shift as BOP 5/04/13

- worked 0700-1900 shift as CRS 6/14/13

- worked 0700-1 900 shift as STA 6/17/13

- worked 1900-0700 shift as CRS Training Department Rotation of Assignment Operator License was inactive on April 1, 2013 5/02/13 thru 5/06/13 worked 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months under the direction of the QAC and completed all requirements for reactivation.

5/10/13

- worked 0700-1900 shift as BOP 5/12/13

- worked 0700-1900 shift as QAC 5/14/13

- worked 1900-0700 shift as QAC 5/31/13

- worked 1900-0700 shift as BOP Work Control Operator License was active on April 1, 2013 4/23/13

- worked 0700-1900 shift as OAC 4/25/13

- worked 0700-1900 shift as BOP 5/05/13

- worked 0700-1900 shift as QAC 5/14/13

- worked 1900-0700 shift as BOP 6/17/13

- worked 1900-0700 shift as QAC Procedure Writers Group Operator License was active on April 1, 2013 4/12/13 thru 4/16/13 worked 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months under the direction of the STA and completed all requirements for reactivation.

4/14/13

- worked 1900-0700 shift as STA 4/18/13 - worked 0700-1900 shift as STA 5/12/13

- worked 0700-1900 shift as OAC 5/14/13

- worked 1900-0700 shift as BOP 5/31/13

- worked 1900-0700 shift as CRS 2013 NRC Admin Exam RO SRO Al-I Rev. Final

Appendix C Job Performance Measure Form ES-C-i Worksheet Facility:

HARRIS Task No.:

301 i79H601 Task

Title:

Determine Average RCS Boron JPM No.:

2013 NRC Admin Concentration JPM RO SRO Ai-2 K/A

Reference:

004 A4.04 3.2 / 3.6 Alternate Path: No Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Following a loss of offsite power, recovery actions are being taken in accordance with EOP-ECA-0. 1, Loss of All AC Power Recovery Without SI Required Plant conditions are as follows:

PRZ pressure 2230 psig RCS Hot Leg temperatures 555°F Core Exit thermocouples 560°F PRZ Liquid space temperature 650°F Initial Conditions:

PRZ Steam space temperature 650°F PRZ level 45 %

Charging and letdown are in service, with letdown flow at 45 gpm.

Chemistry has just taken RCS boron samples and reports the following results:

Loop B Hot Leg 930 ppm Loop C Hot Leg 940 ppm PRZ Liquid Space 961 ppm The CRS requires that you calculate the average RCS boron Initiating Cue:

concentration for these conditions per EOP-ECA-0.1, Attachment 1 to TVVO decimal places.

2013 NRC Exam Admin JPM RO SRO A1-2 Rev. Final

Appendix C Job Performance Measure Form ES-C-i Worksheet Task Standard:

Average RCS boron calculation determined to be 937.42 +/- 0.50 ppm.

Required Materials:

Calculator Curve Book General

References:

EOP-ECA-0.1, Loss of All AC Power Recovery Without SI Required, Rev. 0 Curve D-X-40, Pressurizer Volume Handouts:

JPM Cue Sheets EOP-ECA-0. 1, Loss of All AC Power Recovery Without SI Required, Rev. 0 Attachment I Curve Book (preferred) or at a minimum Curve D-X-40 Time Critical Task:

No Validation Time:

1 1 minutes Critical Step Justification Must correctly determine PRZ volume based on PRZ level and curve Step 3 D-X-40 to obtain correct final values of calculation for average RCS boron concentration.

Must correctly determine CVCS volume (Vcvcs) based on letdown status Step 4 to obtain correct final values of calculation for average RCS boron concentration.

Must correctly calculate average RCS boron concentration (CAVG) using Step 8 the formula to obtain correct final values of calculation for average RCS boron concentration.

2013 NRC Exam Admin JPM RO SRO Ai-2 Rev. Final

Appendix C Page 3 of 9 Form ES-C-i PERFORMANCE INFORMATION Start Time:

Performance Step: I Locate ECA-O.1, Attachment i, and Curve Book (Attachment i provided with handout)

Standard:

Obtains ECA-O.1, Attachment i, and Curve Book Comment:

ECA-O.i, Att. 1, Step I Performance Step: 2 Record PRZ level at the time of PRZ sample Standard:

Records PRZ level as 45%

Comment:

ECA-O.1, Att. 1, Step 2 V

Performance Step: 3 Determine PRZ volume (VPRz) based on PRZ level and curve D-X-40 Standard:

References curve D-X-40 Determines intersection of 653°F PRZ LIQUID SPACE TEMP LINE and 45% on INDICATED PRESSURIZER LEVEL axis (X) to correspond to 2900 +/- 100 gallons on VOLUME axis (Y)

Comment:

V - Denotes a Critical Step 2013 NRC Exam Admin JPM RO SRO A1-2 Rev.Final

Appendix C Page 4 of 9 Form ES-C-i PERFORMANCE INFORMATION ECA-0.1, Aft. 1, Step 3 V

Performance Step: 4 Determine CVCS volume (Vcvc) based on letdown status:

If letdown in service = 2136 gal ÷ 2 = 1068 gal If letdown isolated = 0 Standard:

Determines letdown volume of 1068 gallons due to letdown being in service Comment:

ECA-0.1, Att. 1, Step 4 Performance Step: 5 Record RCS loop B boron concentration C2 Standard:

Records RCS loop B boron concentration as 930 ppm Comment:

ECA-0.1, AU. 1, Step 5 Performance Step: 6 Record RCS loop C boron concentration C3 Standard:

Records RCS loop C boron concentration as 940 ppm Comment:

ECA-0.1,Att. 1, Step 6 Performance Step: 7 Record PRZ liquid space boron concentration CPRZ Standard:

Records PRZ liquid space boron concentration as 961 ppm Comment:

V

- Denotes a Critical Step 2013 NRC Exam Admin JPM RO SRO A1-2 Rev.Final

Appendix C Page 5 of 9 Form ES-C-i PERFORMANCE INFORMATION ECA-0.i,Att. 1, Step 7 v

Performance Step: 8 Calculate average RCS boron concentration (CAVG) using the following formula (formula on Att. I, Step 7)

Standard:

Calculates average RCS boron concentration to be 937.42 +/- 0.5 ppm. (Range 936.92

- 937.92 ppm)

Evaluator Note:

NOTE: ALLOWED TOLERANCE BORDERS TOLERANCE FOR ALLOWED ERROR IN READING CURVE D-X-40, BUT WILL NOT BE MET IF APPLICANT FAILS TO ACCOUNT FOR CVCS LETDOWN OR OTHER SIMILAR ERRORS.

Comment:

Evaluator Cue:

When boration calculation is completed END OF JPM Stop Time:

Terminating Cue:

Calculation of average boration concentration completed.

V - Denotes a Critical Step 2013 NRC Exam Admin JPM RO SRO Ai-2 Rev.Final

Appendix C Page 6 of 9 Form ES-C-i PERFORMANCE INFORMATION KEY LOSS OF ALL AC POWER RECOVERY WIThOUT SI REQULRED Sheet I of 1 CALCULATION FOR AVERAGE RCS BORON CONCENTRATION 1.

Record PRZ level at the time of PRZ sample:

45 Z

Determine PRZ volume (VPRZ ) based on PRZ level and curve D-X-40: 2900 +/- 100 GAL 3.

Determine CVCS volume (Vcvcs) based on letdown status:

1068 GAL If letdown in serice = 213 GAL+ 2 = 1058 GAL If letdown isolated

=

0 GAL 4.

Record RCS loop B boron concentration 02:

PPM 5.

Record RCS loop C boron concentration 03:

940 PPM 6.

Record PRZ liquid space boron concentration Cz:

PPM 7

Calculate average RCS boron concentration (Cv 9

) using the Following formula:

[(930 + 940) x (31218 + 1068)] + [961 x (2900 + 3700)]

[(02

-- C) x (31218 + Vcvcs)] + [Cpftz x (Vez

+ 3700)1 937 42

=

PPM (Vpz ÷ 2 x (Vcvcs) 66135)

(2900 + 2 x (1068) + 66135)

NOTE 1: RCS Volume not including PRZ, Upper Head, Surge Line or CVCS = 62,435 GAL.

(Value halved in calculation to account for averaging the boron concentration for LoopsBand C =31,218 GAL)

NOTE 2: PCS Volume not including PRZ or CVCS = 661 35 GAL.

NOTE 3: Combined Upper Head and Surge Line Volume = 3700 GAL.

(Upper Head Volume = 3365 GAL and Surge Line Volume = 335 GAL.)

NOTE 4: CVCS Volume = 2136 GAL (Value halved in Step 3 to account for averaging the boron concentration for RCS loop B and C = 1068 GAL.)

NOTE 5: The boron concentration of the Upper Head and Surge Line is assumed to be that of the PRZ since these volumes also stagnate when RCPs are lost. CVCS boron concentration is assumed to be that of the RCS.

EOP-ECA-0. 1 I

Rev. 0 I

Page 49 of 54

- Denotes a Critical Step 2013 NRC Exam Admin JPM RO SRO Ai-2 Rev.Final

Appendix C Fge 7 of 9 Form ES-C-I PERFORMANCE INFORMATION KEY PRESSURIZER VOLUME (LT-459, LT-460, AND LT-461) 10000*

95O0-PRZ LiQUID SPACE TEMP JVJJ_

f V

8500 1

--653DEGF

8000

7500-550DEGF 7O0O

J 65OO--

6 o

00 T

1 V

V 5500

35ODEGF

.1 5000---

L,...,

_V_VVVV

ii-

--70DEGF V

V V

V

.T 4O0O_

°°29OO1OO

i 3000

V V

2500

--- s 2000 VVVV CRNO NOO 1500 7-9Z 1000

-- J..

- SHIFT OPERTIQNS DATE 500----

._-V.-.

VVVVVV 01 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 INDICA TED PRESSURIZER LEVEL (%)

V

- Denotes a Critical Step 2013 NRC Exam Admin JPM RO SRO AI-2 Rev.Final

Appendix C Page 8 of 9 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2013 NRC Exam Admin JPM RO SRO A1-2 Determine Average RCS Boron Concentration Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2013 NRC Exam Admin JPM RO SRO A1-2 Rev. Final

Appendix C Page 9 of 9 Form ES-C-I JPM CUE SHEET Following a loss of offsite power, recovery actions are being taken in accordance with EOP-ECA-0. 1, Loss of All AC Power Recovery Without SI Required Plant conditions are as follows:

PRZ pressure 2230 psig RCS Hot Leg temperatures 555° F Core Exit thermocouples 560° F PRZ Liquid space temperature 650°F Initial Conditions:

PRZ Steam space temperature 650°F PRZ level 45 %

Charging and letdown are in service, with letdown flow at 45 gpm.

Chemistry has just taken RCS boron samples and reports the following results:

Loop B Hot Leg 930 ppm Loop C Hot Leg 940 ppm PRZ Liquid Space 961 ppm The CRS requires that you calculate the average RCS boron Initiating Cue:

concentration for these conditions per EOP-ECA-0.1, Affachment 1 to TWO decimal places.

2013 NRC Exam Admin JPM RO SRO A1-2 Rev. Final

Appendix C Job Performance Measure Form ES-C-i Worksheet Facility:

Shearon Harris Task No.:

015004H201 Task

Title:

Perform the Quadrant Power Tilt JPM No.:

2013 NRC Exam Ratio Surveillance Admin JPM RO A2 K/A

Reference:

G2.2.i2 RO 3.7 SRO 4.1 Alternate Path: No Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The plant is operating at 90% power when a rod in Control Bank A (P-b) dropped.

The crew is performing AOP-001, MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM.

Initial Conditions:

There are NO deficiency tags on PR NIs.

ERFIS points ANM9II2U and ANM9113L have a BAD quality code. HNP IT has been notified and they are evaluating the ERFIS points.

The CRS has directed you to perform a manual QPTR lAW OST-b039, CALCULATION OF QPTR. The Power Range NIS indications are provided.

Initiating Cue:

For the purposes of the examination, there will be no independent verification. Show values of your work.

2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Job Performance Measure Form ES-C-i Worksheet Task Standard:

Calculations within required band.

Correct Tech Spec actions are identified.

Required Materials:

Calculator General

References:

OST-i 039, CALCULATION OF QPTR, Revision 16 Technical Specifications Handouts:

OST-1 039 Power Range NI Current and Voltage Set point Table Technical Specifications Time Critical Task:

No Validation Time:

10 minutes Critical Step Justification Must accurately determine the correct calculation based on collecting Step 9 and inputting either provided data or visual inspection data. The calculation will yield an unsatisfactory QPTR.

Must accurately determine the correct calculation based on collecting Step 10 and inputting either provided data or visual inspection data. The calculation will yield an unsatisfactory QPTR.

Must accurately determine the correct calculation based on collecting Step 11 and inputting either provided data or visual inspection data. The calculation will yield an unsatisfactory QPTR.

Ste 14 Must identify that the QPTR upper is outside the band which will make I

this overall results unsatisfactory.

Ste 15 Must determine that QPTR is greater than 1.02 (which is a Tech Spec p

limit) and that the QPTR is unsatisfactory.

Step 19 Must correctly identify through documentation that the QPTR limits are exceeded.

2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Page 3 of 16 Form ES-C-i PERFORMANCE INFORMATION Start Time:

Performance Step: I Obtain procedure.

Standard:

Reviews procedure.

Evaluator Cue:

Provide OST-1 039.

Evaluator Note:

A KEY is provided for your use on JPM prior to candidate pages.

Comment:

NOTE: The NI curve numbers provided in this JPM are Evaluator Note:

numbers from the 2013 NRC Exam Frozen Procedures Curve Book folder.

Precaution and Limitation 4.0.1 has guidance if performing this Procedure Note:

OST with one Power Range Channel inoperable.

Performance Step: 2 Completes Prerequisites section:

Verify instrumentation needed for the performance of this test is free of deficiencies that affect instrument indication.

Verify the most recent Curve F-X-8 is used in the performance of this procedure. (Reference 2.1.1 and 2.1.2)

OBTAIN CRS permission to perform this OST.

Standard:

Logs F-18-8 revision number: 6 Initials/signs all blocks Comment:

V

- Denotes Critical Steps 2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Page 4 of 16 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 IF Quadrant Power Tilt Ratio Calculation Computer Program is used, THEN PERFORM the following:

MARK Step 7.0.2 N/A.

MARK Section 7.2 N/A.

PERFORM Section 7.1.

IF manual calculation of the Quadrant Power Tilt Ratio is used, THEN PERFORM the following:

MARK Section 7.1 N/A.

PERFORM Section 7.2.

Standard:

Marks Section 7.1 N/A Proceeds to Section 7.2 Comment:

OST-1 039 Section 72 Note prior to step I Performance Step: 4 NOTE: The detector current meters on each power range channel drawer are designated as left-upper, right-lower.

Standard:

Reads and circle slashes note Comment:

OST-1 039 Section 7.2, Step I Performance Step: 5 Prior to reading the value of detector current, VERIFY the meter range/rate switch is in the 4001 iAJSLOW position.

Standard:

Prior to reading the value of detector current, VERIFIES the Meter Range/Rate switch is in the 400 pA/SLOW position.

Evaluator Note:

This information is on the JPM Cue Sheet Comment:

V

- Denotes Critical Steps 2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Page 5 of 16 Form ES-C-i PERFORMANCE INFORMATION OST-1 039 Section 7.2, Step 2 Performance Step: 6 RECORD on Attachment 2, in column A, the upper and lower detector currents from all operable power range channels as read on the Nuclear Instrumentation Cabinet.

Standard:

Transposes readings from PRNIS Readings Table onto.

Comment:

OST-1 039 Section 7.2, Step 3 Performance Step: 7 RECORD on Attachment 2, in column B, the 100% power normalized current for each channel from Curve F-x-8.

Standard:

Transposes TOP and BOTTOM 100% current values from the Curve Book provided.

Comment:

OST-1 039 Section 7.2, Note prior to Step 4 Performance Step: 8 NOTE: When recording all fractions and ratios, record to four decimal places, dropping the fifth and subsequent decimal places.

Standard:

Reads and circle slashes note Comment:

OST-1 039 Section 7.2, Step 4 q

Performance Step: 9 Divide values in Column A by the respective normalized current in Column B and record the result in Column C as the Normalized Fraction.

Standard:

Divides each Upper and Lower reading by the respective 100%

normalized current value and records in Column C.

Comment:

V

- Denotes Critical Steps 2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Page 6 of 16 Form ES-C-i PERFORMANCE INFORMATION OST-1 039 Section 7.2, Step 5 J

Performance Step: 10 CALCULATE the average value for the upper and the lower Normalized Fractions as follows:

ADD the Normalized Fraction in each section of column C, recording the sum in the space provided.

DIVIDE the sum obtained in Step 7.2.5.a by the number of operable NI channels, recording the result in column D of Attachment 2.

Standard:

Adds all Normalized Fractions for the same plane and records the sum in the space provided.

Divides by the sum by four and records result in Column D.

Comment:

OST-1 039 Section 72, Step 6 q

Performance Step: 11 Using the formula and values from Attachment 2, CALCULATE the Upper and Lower Ratios.

Standard:

Divides the Maximum Normalized Fraction by the Average Normalized Fraction on each plane.

Determines the UPPER ratio is 1.02 The applicant may inform the CRS as soon as any Evaluator Note:

calculation is> 1.02. If so, acknowledge and direct applicant to complete Attachment 2.

Comment:

OST-1 039 Section 7.2, Step 7 Performance Step: 12 PERFORM independent verification of all calculations made on.

Standard:

Requests Independent Verifier.

Evaluator Cue:

If necessary, repeat Initiating Cue: For the purpose of this examination, there will be no independent verification of your work.

Comment:

Candidate may choose to check calculations.

V

- Denotes Critical Steps 2013 NRC Exam Admin JPM ROA2 Rev. Final

Appendix C Page 7 of 16 Form ES-C-i PERFORMANCE INFORMATION OST-1 039 Section 7.2, Note prior to Step 8 Performance Step: 13 NOTE: The upper ratio or the lower ratio, whichever is greater, is the quadrant power tilt ratio (QPTR).

Standard:

Reads and circle slashes note Comment:

OST-1 039 Section 7.2, Step 8 q

Performance Step: 14 RECORD QPTR Standard:

Records QPTR value as 1.0902 to 1.0912 (N43 UPPER)

Identifies Upper as outside the band Comment:

Acceptable band is +1-5% (rounded to.0005).

UPPER calculated band is 1.0902 to 1.0912 LOWER calculated band is 1.0665 to 1.0675 OST-1 039 Section 7.2, Step 9 J

Performance Step: 15 CHECK QPTR is less than or equal to 1.02.

Standard:

Identifies Upper QPTR as greater than 1.02 and QPTR is unacceptable Comment:

OST-1 039 Section 7.2, Note prior to Step 10 Performance Step: 16 NOTE: ERFIS turn on codes used to obtain ERFIS QPTR values include QPTR and GD QPTR.

Standard:

Reads and circle slashes note Comment:

V

- Denotes Critical Steps 2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Page 8 of 16 Form ES-C-I PERFORMANCE INFORMATION OST-1 039 Section 7.2, Step 10 Performance Step: 17 IF the ERFIS calculated QPTR value is available, THEN COMPARE OST-1 039 results to the ERFIS QPTR calculated output as a quality check.

Standard:

Request status of ERFIS calculated QPTR value, and N/As step 7.2.10 when notified ERFIS QPTR is not available.

[

Evaluator Note:

This information is on the JPM Cue Sheet Evaluator Cue:

Comment:

OST-1 039 Section 7.2, Step 11 Performance Step: 18 IF any ERFIS QPTR quality codes do not have a good quality code or the higher of ANM9112U orANM9113L do not approximate the value for QPTR determined above, THEN CONTACT HNP IT to investigate.

Standard:

Request if notification of the status of the ERFIS calculated QPTR value to HNP IT has been completed.

Evaluator Note:

This information is on the JPM Cue Sheet Evaluator Cue:

Comment:

- Denotes Critical Steps 2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Page 9 of 16 Form ES-C-i PERFORMANCE INFORMATION OST-1 039 Section 7.3, Test Completion Step I Performance Step: 19 IF this test was performed due to an inoperable QPTR alarm, THEN DOCUMENT completion of PMID 22125 RQ 01.

COMPLETE applicable sections of Attachment 3, Certifications and Reviews.

IN FORM the CRS this test is completed.

Standard:

Check marks Periodic Surveillance or notes AOP-001 in Comments section Plant Condition: 90% Power (may note dropped rod)

. Mode 1

Todays Date

Current Time

OST Completed By: Applicants name Initials/Name q

Indicate in General Comments Section and/or informs CRS that the limit is exceeded Evaluator Cue:

Acknowledge any report.

Comment:

After the CRS has been notified:

Terminating Cue:

Evaluation on this JPM is complete.

STOP Time:

V

- Denotes Critical Steps 2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Page 10 of 16 Form ES-C-I PERFORMANCE INFORMATION KEY Record QPTR = 1.0907 Acceptable band is +/-5% (rounded to.0005) 1.0902 to 1.0912 CHECK QPTR is less than or equal to 1.02 (circle) YES A

B C

D UPPER UPPER AVERAGE UPPER 100% POWER NORMALIZED UPPER UPPER DETECTOR NORMALIZED FRACTION NORMALIZED DETECTOR CURRENT CURRENT (NOTE 1)

FRACTION N-41 145.6 164.1 0.8872 N-42 162.5 187.6 0.8662 0.8840 N-43 199.8 207.2 0.9642 N-44 138.4 169.1 0.8184 SUM 3.5360 Maximum Upper Normalized Fraction 0.9642 Upper Ratio =

=

1.0907*

Average Upper Normalized Fraction 0.8840

Standard for this calculation is 1.0902 to 1.0912 A

B C

D LOWER LOWER AVERAGE LOWER 100% POWER NORMALIZED LOWER LOWER DETECTOR NORMALIZED FRACTION NORMALIZED DETECTOR CURRENT CURRENT (NOTE 1i FRACTION N-41 159.6 183.0 0.8721 N-42 172.1 209.9 0.8199 0.8632 N-43 209.3 224.7 0.9314 N-44 165.2 199.1 0.8297 SUM 3.4531 Maximum Lower Normalized Fraction 0.9314 Lower Ratio =

=

1.0790**

Average Lower Normalized Fraction 0.8632

- Standard for this calculation is 1.0785 to 1.0795

- Denotes Critical Steps 2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Page ii of 16 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2013 NRC Exam Admin JPM RO A2 Perform a Quadrant Power Tilt Ratio Surveillance Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Form ES-C-i JPM CUE SHEET Name:

Date:

The plant is operating at 90% power when a rod in Control Bank A (P-iO) dropped.

The crew is performing AOP-001, MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM.

Initial Conditions:

There are NO deficiency tags on PR Nls.

ERFIS points ANM91 12U and ANM9I 13L have a BAD quality code. HNP IT has been notified and they are evaluating the ERFIS points.

The CRS has directed you to perform a manual QPTR lAW OST-1039, CALCULATION OF QPTR. The Power Range NIS indications are Initiating Cue:

provided.

For the purposes of the examination, there will be no independent verification. Show values of your work.

2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix Form ES-C-I JPM CUE SHEET r CU*U4 145 6 MI4tRl 0

TECT ?

IZr i! LL I*

I I

a ItX7%r!

4

. !! E%

400pA!SLOW.r 4OOiNSLOW

+

DPERATLEC:KR I

fl,.

1___ I

1 2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix JPM CUE SHEET Form ES-C-i NL.U 2013 NRC Exam Admin JPM RO A2 Rev. Final DE3ET i

J 3,

400pA!SLOW 400pNSLOW L

J I

Appendix JPM CUE SHEET Form ES-C-I

£ 400 pNSLOW LLL1M rixT 1!J L.k I

\\iT c

k I

r_1 L

400 iAiSLOW z..

r

qq

_t_

q !

2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix JPM CUE SHEET Form ES-C-I 2013 NRC Exam Admin JPM RO A2 Rev. Final

Appendix C Job Performance Measure Form ES-C-i Worksheet Facility:

Shearon Harris Task No.:

0i5004H201 Task

Title:

Perform the Quadrant Power Tilt JPM No.:

2013 NRC Exam Ratio Surveillance Admin JPM SRO A2 K/A

Reference:

G2.2.12 RO 3.7 SRO 4.1 Alternate Path: No Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

The plant is operating at 90% power when a rod in Control Bank A (P-b) dropped.

The crew is performing AOP-001, MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM.

Initial Conditions:

There are NO deficiency tags on PR Nis.

ERFIS points ANM91I2U and ANM9113L have a BAD quality code. HNP IT has been notified and they are evaluating the ERFIS points.

The CRS has directed you to perform a manual QPTR lAW OST-1 039, CALCULATION OF QPTR, AND evaluate the actions, if any, of the applicable Technical Specification. The Power Range NIS indications Initiating Cue:

are provided.

For the purposes of the examination, there will be no independent verification. Show values of your work.

2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Job Performance Measure Form ES-C-i Worksheet Task Standard:

Calculations within required band.

Correct Tech Spec actions are identified.

Required Materials:

Calculator General

References:

OST-1039, CALCULATION OF QPTR, Revision 16 Technical Specifications Handouts:

OST-1 039 Power Range NI Current and Voltage Set point Table Technical Specifications Time Critical Task:

No Validation Time:

15 minutes Critical Step Justification Must accurately determine the correct calculation based on collecting Step 9 and inputting either provided data or visual inspection data. The calculation will yield an unsatisfactory QPTR.

Must accurately determine the correct calculation based on collecting Step 10 and inputting either provided data or visual inspection data. The calculation will yield an unsatisfactory QPTR.

Must accurately determine the correct calculation based on collecting Step 11 and inputting either provided data or visual inspection data. The calculation will yield an unsatisfactory QPTR.

Ste 14 Must identify that the QPTR upper is outside the band which will make p

this overall results unsatisfactory.

Ste 15 Must determine that QPTR is greater than 1.02 (which is a Tech Spec I

limit) and that the QPTR is unsatisfactory.

Step 19 Must correctly identify through documentation that the QPTR limits are exceeded.

Must accurately identify associated Technical Specifications with a Step 20 QPTR that has exceeded the limits specified in HNP Technical Specifications.

2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 3 of 18 Form ES-C-I PERFORMANCE INFORMATION Start Time:

Performance Step: I Obtain procedure.

Standard:

Reviews procedure.

Evaluator Cue:

Provide OST-1039.

Evaluator Note:

A KEY is provided for your use on JPM prior to candidate pages.

Comment:

NOTE: The NI curve numbers provided in this JPM are Evaluator Note:

numbers from the 2013 NRC Exam Frozen Procedures Curve Book folder.

Precaution and Limitation 4.0.1 has guidance if performing this Procedure Note:

OST with one Power Range Channel inoperable.

Performance Step: 2 Completes Prerequisites section:

Verify instrumentation needed for the performance of this test is free of deficiencies that affect instrument indication.

Verify the most recent Curve F-X-8 is used in the performance of this procedure. (Reference 2.1.1 and 2.1.2)

OBTAIN CRS permission to perform this OST.

Standard:

Logs F-18-8 revision number: 6 Initials/signs all blocks Comment:

- Denotes Critical Steps 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 4 of 18 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 IF Quadrant Power Tilt Ratio Calculation Computer Program is used, THEN PERFORM the following:

MARK Step 7.0.2 N/A.

MARK Section 7.2 N/A.

PERFORM Section 7.1.

IF manual calculation of the Quadrant Power Tilt Ratio is used, THEN PERFORM the following:

MARK Section 7.1 N/A.

PERFORM Section 7.2.

Standard:

Marks Section 7.1 N/A Proceeds to Section 7.2 Comment:

OST-1 039 Section 7.2 Note prior to step I Performance Step: 4 NOTE: The detector current meters on each power range channel drawer are designated as left-upper, right-lower.

Standard:

Reads and circle slashes note Comment:

OST-I 039 Section 7.2, Step I Performance Step: 5 Prior to reading the value of detector current, VERIFY the meter range/rate switch is in the 400 jiA/SLOW position.

Standard:

Prior to reading the value of detector current, VERIFIES the Meter Range/Rate switch is in the 400 pA/SLOW position.

Evaluator Note:

This information is on the JPM Cue Sheet Comment:

if

- Denotes Critical Steps 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 5 of 18 Form ES-C-i PERFORMANCE INFORMATION OST-1 039 Section 7.2, Step 2 Performance Step: 6 RECORD on Attachment 2, in column A, the upper and lower detector currents from all operable power range channels as read on the Nuclear Instrumentation Cabinet.

Standard:

Transposes readings from PRNIS Readings Table onto.

Comment:

OST-1 039 Section 7.2, Step 3 J

Performance Step: 7 RECORD on Attachment 2, in column B, the 100% power normalized current for each channel from Curve F-x-8.

Standard:

Transposes TOP and BOTTOM 100% current values from the Curve Book provided.

Comment:

OST-1 039 Section 7.2, Note prior to Step 4 Performance Step: 8 NOTE: When recording all fractions and ratios, record to four decimal places, dropping the fifth and subsequent decimal places.

Standard:

Reads and circle slashes note Comment:

OST-1 039 Section 7.2, Step 4 J

Performance Step: 9 Divide values in Column A by the respective normalized current in Column B and record the result in Column C as the Normalized Fraction.

Standard:

Divides each Upper and Lower reading by the respective 100%

normalized current value and records in Column C.

Comment:

7

- Denotes Critical Steps 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 6 of 18 Form ES-C-I PERFORMANCE INFORMATION OST-1 039 Section 7.2, Step 5 q

Performance Step: 10 CALCULATE the average value for the upper and the lower Normalized Fractions as follows:

ADD the Normalized Fraction in each section of column C, recording the sum in the space provided.

DIVIDE the sum obtained in Step 7.2.5.a by the number of operable NI channels, recording the result in column D of Attachment 2.

Standard:

Adds all Normalized Fractions for the same plane and records the sum in the space provided.

Divides by the sum by four and records result in Column D.

Comment:

OST-1039 Section 7.2, Step 6 q

Performance Step: 11 Using the formula and values from Attachment 2, CALCULATE the Upper and Lower Ratios.

Standard:

Divides the Maximum Normalized Fraction by the Average Normalized Fraction on each plane.

Determines the UPPER ratio is 1.02 The applicant may inform the CRS as soon as any Evaluator Note:

calculation is> 1.02. If so, acknowledge and direct applicant to complete Attachment 2.

Comment:

OST-1 039 Section 7.2, Step 7 Performance Step: 12 PERFORM independent verification of all calculations made on.

Standard:

Requests Independent Verifier.

Evaluator Cue:

If necessary, repeat Initiating Cue: For the purpose of this examination, there will be no independent verification of your work.

Comment:

Candidate may choose to check calculations.

- Denotes Critical Steps 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 7 of 18 Form ES-C-I PERFORMANCE INFORMATION OST-1 039 Section 7.2, Note prior to Step 8 Performance Step: 13 NOTE: The upper ratio or the lower ratio, whichever is greater, is the quadrant power tilt ratio (QPTR).

Standard:

Reads and circle slashes note Comment:

OST-1 039 Section 7.2, Step 8 J

Performance Step: 14 RECORD QPTR:

Standard:

Records QPTR value as 1.0902 to 1.0912 (N43 UPPER)

Identifies Upper as outside the band O.Q5 Comment:

Acceptable band is +1-5% (rounded to.0005).

UPPER calculated band is 1.0902 to 1.0912 LOWER calculated band is 1.0665 to 1.0675 OST-1 039 Section 7.2, Step 9 J

Performance Step: 15 CHECK QPTR is less than or equal to 1.02.

Standard:

Identifies Upper QPTR as greater than 1.02 and QPTR is unacceptable Comment:

OST-1 039 Section 7.2, Note prior to Step 10 Performance Step: 16 NOTE: ERFIS turn on codes used to obtain ERFIS QPTR values include QPTR and GD QPTR.

Standard:

Reads and circle slashes note Comment:

- Denotes Critical Steps 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 8 of 18 Form ES-C-i PERFORMANCE INFORMATION OST-1 039 Section 7.2, Step 10 Performance Step: 17 IF the ERFIS calculated QPTR value is available, THEN COMPARE OST-1039 results to the ERFIS QPTR calculated output as a quality check.

Standard:

Request status of ERRS calculated QPTR value, and N/As step 7.2.10 when notified ERFIS QPTR is not available.

Evaluator Note:

This information is on the JPM Cue Sheet Evaluator Cue:

Comment:

OST-1 039 Section 7.2, Step 11 Performance Step: 18 IF any ERFIS QPTR quality codes do not have a good quality code or the higher of ANM91 1 2U or ANM91 1 3L do not approximate the value for QPTR determined above, THEN CONTACT HNP IT to investigate.

Standard:

Request if notification of the status of the ERFIS calculated QPTR value to HNP IT has been completed.

[

Evaluator Note:

This information is on the JPM Cue Sheet Evaluator Cue:

Comment:

- Denotes Critical Steps 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 9 of 18 Form ES-C-i PERFORMANCE INFORMATION OST-1 039 Section 7.3, Test Completion Step I Performance Step: 19 IF this test was performed due to an inoperable QPTR alarm, THEN DOCUMENT completion of PMID 22125 RQ 01.

COMPLETE applicable sections of Attachment 3, Certifications and Reviews.

INFORM the CRS this test is completed.

Standard:

Check marks Periodic Surveillance or notes AOP-001 in Comments section

Plant Condition: 90% Power (may note dropped rod)

Mode 1

Todays Date

Current Time

OST Completed By: Applicants name Initials/Name 1

Indicate in General Comments Section and/or informs CRS that the limit is exceeded Evaluator Cue:

Acknowledge any report.

Comment:

V - Denotes Critical Steps 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 10 of 18 Form ES-C-I PERFORMANCE INFORMATION

,J Performance Step: 20 Identify the Technical Specification LCOs that would be in effect.

Standard:

Identifies that Technical Specification 3.2.4, Quadrant Power Tilt Ratio has been exceeded Identifies the following ACTION statements to be implemented and the required time limitation (see page 12) o 3.2.4.b.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months b.

With Ea QUORAI1T PWER TtLT RATIO datariined to ace* t;Q9 du. to of at.r a shuow or contro ro4:

1.

Calciflata ta UARANT PW TZLT ria at 1*at once pir hour Ufti1 *lthet a)

Th MORANt POWIR TILT RAna 1 reded to wWifn ft 11aft or b)

TWERHAL PO4 fa r*duce to T. an S0 of RATED ThEP14A.

PCWER.

o 3.2.4.b.2 30 minutes, reduce thermal power to < 73%

(9%x3%=27%

100%-27%=73%)

2.

Rodue ThERJAL PGWE at Iaast fr RATED T RMA1. PW LOT

% f IrWicred qUADRANT POWER TtT aAIO

.xc.s* ol LGO dithln 30 mfnutae; o

3.2.4.b.3 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.

Vnfy that the QUADRANT POWER tILT RATO 1 w1tHi IZ.5 1 iml wf thin Z hours after xcedtnq the 1Ilt or rtduca ThERI4AI.

POU to cii than 5 of RATED ThER(AL POWER within tn* next Z hours and educi the Pwer Ranqe Neutron FTix*th Trip S4t4olnts to less than or eauaT to S of RATED 1HEF4AL POW!

within the next 4 wurs; an Technical Specification 3.2.4.b.4 is not required to be identified Evaluator Note:

since no direction is provided in the cue for raising thermal power.

Comment:

After the CRS has been notified:

Terminating Cue:

Evaluation on this JPM is complete.

STOP Time:

- Denotes Critical Steps 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Lower Ratio =

Average Lower Normalized Fraction

- Standard for this calculation is 1.0785 to 1.0795

- Denotes Critical Steps Appendix C Page 1 1 of 18 Form ES-C-i PERFORMANCE INFORMATION KEY Record QPTR 1.0907 Acceptable band is +1-5% (rounded to.0005) 1.0902 to 1.0912 CHECK QPTR is less than or equal to 1.02 (circle) YES A

B C

D UPPER UPPER AVERAGE UPPER 100% POWER NORMALIZED UPPER UPPER DETECTOR NORMALIZED FRACTION NORMALIZED DETECTOR CURRENT CURRENT (NOTE 1)

FRACTION N-41 145.6 164.1 0.8872 N-42 162.5 187.6 0.8662 0.8840 N-43 199.8 207.2 0.9642 N-44 138.4 169.1 0.8184 SUM 3.5360 Maximum Upper Normalized Fraction 0.9642 Upper Ratio =

=

1.0907*

Average Upper Normalized Fraction 0.8840

Standard for this calculation is 1.0902 to 1.0912 A

B C

D LOWER LOWER AVERAGE LOWER 100% POWER NORMALIZED LOWER LOWER DETECTOR NORMALIZED FRACTION NORMALIZED DETECTOR CURRENT CURRENT (NOTE 1)

FRACTION N-4 1 159.6 183.0 N-44 0.8721 N-42 172.1 209.9 0.8199 N-43 209.3 224.7 0.9314 165.2 199.1 0.8632 0.8297 SUM Maximum Lower Normalized Fraction 3.4531 0.9314 0.8632

=

1.0790**

2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 12 of 18 Form ES-C-i PERFORMANCE INFORMATION KEY WER GIrRraUtWN tirrs ll$I4G CONQLTtQN FALR,ppfi*rON AaIaN (Ccnt!nue4):

S With tile AORANT POWER TILT RATIO detarilned t5 extnd 1. 09 due to zisaligiwent of either a shutdown or control rod:

t C41;Ctllata the QUADRANT POWER TILT RATIO at least once er hour urati I either:

a)

The QUADRANT POWER TILT RATIO is reduced to within its iiitt or a

)

THERMAL POWER f jj to less than iS of RATED THERMAL POWER.

2.

Raduce ThERMAL POWER at least from RATED ThERMAL POWER far nch 1% of Indicated QUADRANT POWER TILT RATIO In excess of LOO wjtitin 3D ainuta; 3.

Verify tiiat the QUADRANT POWER TILT RATIO is ithin its lisit within Z noun after exceeding the limit or reduct ThERMAL fl to less than 3 f RATED THERMAL POWER within the next 2 houre jnd reduce the Power Rariçe Neutron Flux-High trip Setoints to less than or equal to S5X of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; ad 4..

Identify and correct the cause of the out-of-halt condition prior to Increasing ThERMAL POWER; subsequent POWER OPERATION save 5( of RATED THERML POWER may proceed prov 14.4 that the QUADRANT POWER TILT RATIO Is verified within its liiit at least once per hour for 12 houn or uttil verified acceptable at 9 or greeter RATED Th: L POWER.

With the QUAOaANT POWER TILT RATIO detereined to exceed 1.09 due to causes other tnan the mfsatiçnent of either a shutdown or control rod:

1.

Calculate the QUADRANT POWER TILT RATIO a Ittit 041CC per hour untIl either:

a)

Th.QUACRANTPOWERT!LTRATTO is reduced to within its limit, or b)

THERMAL POWER is reduced to less than 5 of RATED THERMAL POWEL SNEARON HARRIS - UNIT 1 3/4 212 V

- Denotes Critical Steps 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 13 of 18 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2013 NRC Exam Admin JPM RO A2 Perform a Quadrant Power Tilt Ratio Surveillance Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2013 NRC Exam Admin JPM SRO A2 Rev. Final

Caballero, Bruno From:

Simon Schwindt Sent:

Tuesday, October 01, 2013 10:23 AM To:

Caballero, Bruno

Subject:

Re:

Bruno I have discussed with JR and the standard in the JPM should have been + or

- 0.5% (i.e. 0.0005).

The value band given in the JPM for the QPTR (as we discussed) should be used as the standard.

Thanks Simon From: Caballero, Bruno <Bruno.Caballero(nrc.gov>

To:

...k.

I.

F

Sent: Tuesday, October 1, 2013 10:02 AM

Subject:

FW:

From: Caballero, Bruno Sent: Tuesday, October 01, 2013 8:38 AM To: Laska, Gerard

Subject:

Bruno Caballero USNRC Region II, Sr Operations Engineer 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 404-997-4608 1

Appendix C Form ES-C-i JPM CUE SHEET Name:

Date:

The plant is operating at 90% power when a rod in Control Bank A (P-ic) dropped.

The crew is performing AOP-OOi, MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM.

Initial Conditions:

There are NO deficiency tags on PR NIs.

ERFIS points ANM91 i2U and ANM91 13L have a BAD quality code. HNP IT has been notified and they are evaluating the ERFIS points.

The CRS has directed you to perform a manual QPTR lAW OST-1 039, CALCULATION OF QPTR, AND evaluate the actions, if any, of the applicable Technical Specification. The Power Range NIS indications Initiating Cue:

are provided.

For the purposes of the examination, there will be no independent verification. Show values of your work.

2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix JPM CUE SHEET Form ES-C-i 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix JPM CUE SHEET Form ES-C-I 162 5 172.1 rE2TG): A

.w

-V 400 iA/SLOW

\\

400 hA/SLOW

- ?

4

-flLi rr i

ii

4 bi I

2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix JPM CUE SHEET Form ES-C-i I

DCTICPDfl A 9N

4yt wM W Ih Fs;L4I 43fl W%%

400 iNSLOW L

S tt&S Ai%thI tfl SkWa*

p*%%wt4N nF&fl 400 pAISLOW Th-4 V7o!%

Hqu 4t C1)LIIAM £LaIU U4L9 Y fl1 M4 I.

F I

Eli TtCtYLl Ill S

b Wi Ii.

t:u u a

fl

I S

2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix JPM CUE SHEET Form ES-C-i røE-ni ftflorMftr 4S4AXI

/....+ 1 400pAISLOW nt a4a.1 GETCTOfi A 11t% W4Z!(

irr xvn OEPA1flN !3ELECTOF aMI MflP[flJ4sOVfl 4çe 400 pNSLOW

+c&

JWfl QEVECTOR &

Ct L

A ft 2013 NRC Exam Admin JPM SRO A2 Rev. Final

Appendix C Page 1 of ii Form ES-C-i Worksheet Facility:

Shearon Harris Task No.:

Task

Title:

Using survey maps determine stay JPM No.:

2013 NRC Exam Admin times JPMROSROA-3 K/A

Reference:

G.2.3.4 RD 3.2 SRO 3.7 Alternate Path: No Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Two individuals are tasked to hang a clearance on 1CS-38, Letdown PCV Isol Vlv. The clearance includes the following valves:

1CS-35, Inlet Isol Vlv to LTDN PCV 1CS-36, Inlet Isol Vlv to LTDN PCV Drain Vlv Initial Conditions:

1CS-37, Inlet Isol to LTDN PCV Drain Vlv 1CS-38, Letdown PCV Isol Vlv.

1 CS-39, Outlet Isol Vlv to LTDN PCV Drain Vlv 1CS-40, Outlet Isol to LTDN PCV Drain Isol Vlv 1 CS-43,_Outlet_Isol_Vlv to_LTDN_PCV Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1750 mrem (Duke Energy Progress). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Duke Energy Progress) and worked at Nine Mile Point earlier this year where he received an additional accumulated dose of 2550 mrem.

The clearance and work activity is for 1CS-38, Letdown PCV Isol Vlv. The ALARA group has determined that additional shielding is not warranted for this Initiating Cue:

work.

Using the supplied survey map, determine the maximum allowable individual stay times for each Operator that would prevent exceeding the Duke Energy Progress Annual Administrative dose limit while performing these activities.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

2013 NRC Exam Admin JPM RD SRO A3 Rev. Final

Appendix C Page 2 of 1 1 Form ES-C-i Worksheet Task Standard:

Calculation of stay times based on survey maps, two hours for Operator 1, six hours for Operator 2.

Required Materials:

Survey map A45 RAB 236 LETDOWN & LETDOWN REHEAT HX &VG Map 21 SFD-5-S-1 304 General

References:

DOS-NGGC-0004, Administrative Dose Limits Section 9.3, Duke Energy Progress Annual Administrative Dose Limits (Rev.12)

LIMIT 2 REM Duke Energy Progress dose not to exceed 4 REM total dose if Non-Duke Energy Progress dose for the current year has been determined.

Time Critical Task:

No Validation Time:

14 minutes Critical Step Justification Ste 3

IF incorrect calculation of stay time is made the individuals could exceed p

their dose limits.

Step 1 Step 2 Must determine dose rates in order to calculate stay time Must determine available dose to determine stay time.

2013 NRC Exam Admin JPM RO SRO A3 Rev. Final

Appendix C Page 3 of ii Form ES-C-i PERFORMANCE INFORMATION START TIME:

The order of performance does not matter Evaluator Note IF THE APPLICANT ASKS FOR IT: DOS-NGGC-0004, Rev. 12 is one of the documents in the 2013 NRC Exam Frozen Procedures folder.

v Performance Step: I Using Radiological Survey Record Map A45 and RAB 236 LETDOWN & LETDOWN REHEAT HX &VG Map 21, determines dose rates in the area where the clearance will be applied Standard:

Identifies that General Area Dose Rates are 125 mrem/hr Comment:

v Performance Step: 2 Determine the remaining dose for the year for each individual Standard:

Operator 1: 250 mrem 2000 mrem

- 1750 mrem = 250 mrem Operator 2: 750 mrem 4000 mrem

- 700 mrem (PE)

- 2550 mrem (NMP) = 750 mrem Comment:

V

- Denotes Critical Steps 2013 NRC Exam Admin JPM RO SRO A3 Rev. Final

Appendix C Page 4 of 1 1 Form ES-C-i PERFORMANCE INFORMATION

Performance Step: 3 Determine stay time for each operator (based on 1 St Operator reaching 2 Rem and the 2nd Operator reaching 4 Rem

- for the year)

Standard:

Operator 1: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 250 mrem ÷ 125 mrem/hr = 2 hrs Operator2: 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 750 mrem ÷ 125 mrem/hr = 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Comment:

Terminating Cue:

After the stay time has been calculated, this JPM is complete.

END OF JPM STOP TIME:

V

- Denotes Critical Steps 2013 NRC Exam Admin JPM RO SRO A3 Rev. Final

Appendix C Page 5 of 1 1 Form ES-C-I VERIFICATION OF COMPLETION Job Performance Measure No.:

2013 NRC Exam Admin JPM RO SRO A Using survey maps determine stay times. (DOS-NGGC-0004 Rev. 12)

DOS-NGGC-0004, Administrative Dose Limits, Section 9.3, Duke Energy Progress Annual Administrative Dose Limits.

LIMIT = 2 REM Progress Energy dose not to exceed 4 REM total dose if Non-Duke Energy Progress dose for the current year has been determined.

Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2013 NRC Exam Admin JPM RO SRO A3 Rev. Final

Appendix C Form ES-C-i JPM CUE SHEET Name:

Date:

Two individuals are tasked to hang a clearance on 1 CS-38, Letdown PCV Isol Vlv. The clearance includes the following valves:

1CS-35, Inlet Isol Vlv to LTDN PCV 1CS-36, Inlet Isol Vlv to LTDN PCV Drain Vlv Initial Conditions:

1CS-37, Inlet Isol to LTDN PCV Drain Vlv 1 CS-38, Letdown PCV Isol Vlv.

1CS-39, Outlet Isol Vlv to LTDN PCV Drain Vlv 1CS-40, Outlet Isol to LTDN PCV Drain lsol Vlv 1 CS-43,_Outlet_Isol_Vlv_to_LTDN_PCV Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1750 mrem (Duke Energy Progress). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Duke Energy Progress) and worked at Nine Mile Point earlier this year where he received an additional accumulated dose of 2550 mrem.

The clearance and work activity is for 1 CS-38, Letdown PCV Isol Vlv. The ALARA group has determined that additional shielding is not warranted for this Initiating Cue:

work.

Using the supplied survey map, determine the maximum allowable individual stay times for each Operator that would prevent exceeding the Duke Energy Progress Annual Administrative dose limit while performing these activities.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

Record the maximum allowable stay time calculations below to the nearest hour and minute.

Operator 1:

Operator2:

2013 NRC Exam Admin JPM RO SRO A3 Rev. Final

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Appendix C Form ES-C-i JPM CUE SHEET 4

H GALLERY Ii 0

RAB 236 LETDOWN & LETDOWN REHEAT HEAT EXCHANGERS/VALVE S

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<PHOTOGRAPHS I

SURVEYS j I

LETDOWNHX V

ii N

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AREA HAD MONITOR IARMI 2013 NRC Exam Admin JPM RO SRO A3 Rev. Fina

ppendix C Form ES-C-i JPM CUE SHEET Radiation Area Beta Dose Rate HRA HitiottArca LHRA Locked HiabRadiation Area I

Rem/how VNRA Very Hifladiation Area

)CXXX Bøundtuy ARA Airborne Radhation Area 0 smear Location CA Ca.majnationAzea Mr Sampe LOclLtiort R14A Radioactive MateriaIsAra IO)

Dose Ratesin mrerniir unIs othetise noted QA Rtcotd 2013 NRC Exam Admin JPM RO SRO A3 Rev. Final

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Appendix C Job Performance Measure Form ES-C-I Worksheet Facility:

Task

Title:

Shearon-Harris Classify an EAL Task No.:

345001 H602 JPM No.:

2013 NRC Exam AdminJPM SROA4 K/A

Reference:

G2.4.41 RO 2.9 SRO 4.6 Alternate Path: No Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing: This JPM can be performed in any setting with the required references available.

Simulated Performance:

Classroom X

Simulator Actual Performance:

Plant x

Part 1: Evaluate the EAL Matrix and determine the highest classification required for these plant conditions. NOTE: Do not use SEC judgment.

NOTE: Write out EAL classification in blank provided then raise Initiating Cue:

your hand and return your page to the Evaluator.

Part 2: Based on your EAL classification complete the Nuclear Power Plant Emergency Notification form. WEB EOC is NOT available.

READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

This is a two (2) part TIME CRITICAL JPM where each part will be timed separately.

Initial Conditions:

Given the following plant conditions:

The plant is in Mode 1 Wind speed is 10 mph and wind direction is 265 degrees A-SA Safety train is in service AOP-016 is being performed due to a 12 gpm leak in C SG The following occurs at 1115:

Offsite Power is lost Reactor trips on undervoltage for all 3 RCPs SG A Pressure 598 psig SG B Pressure 595 psig SG C Pressure 603 psig Containment pressure stabilizes at 3.6 psig At 1120:

BOP reports IBD-39, Stm Gen C Inside Bldn Isol. and 1 BD-49, Stm Gen C Outside Bldn Isol failed to close automatically or manually Sanford Substation Maintenance reports that their truck brakes failed and it has crashed into Breaker 52-13 damaging the breaker and the connecting transmission lines The time is now 1125 2013 NRC Exam Admin JPM SRO A4 Rev. Final

Appendix C Job Performance Measure Form ES-C-i Worksheet Task Standard:

Classify the highest EAL as an Alert HAl.6 and ENF correctly filled out.

Required Materials:

None General

References:

PEP-i 10 EAL Matrix PEP-hO EP-EAL (allowed reference)

PEP-310 Attachment 9 ENF Form Handouts:

Attached Initial Conditions PEP-lb PEP-i 10 EAL Matrix EP-EAL Time Critical Task:

YES 15 minutes for classification.

YES 15 minutes to complete ENF Validation Time:

15 minutes for classification 15 minutes to complete ENF CRITICAL STEP JUSTIFICATION Classification of the event is critical for determining State and County Step 2 notifications, public information notices, site information notices, and event reportability to the Nuclear Regulatory Commission.

Step 4 has been completed correctly.

Form must be filled out correctly. The critical lines are identified on Page ENF 7 of this JPM. Each line must be filled out correctly and are critical based on HNP EP and NEI 99-02 Rev. 6 Standards.

2013 NRC Exam Admin JPM SRO A4 Rev. Final

Appendix C Page 3 of 10 Form ES-C-i PERFORMANCE INFORMATION Start Time for this portion of JPM begins when the Evaluator Cue:

individual has been briefed.

START TIME:

Performance Step: I OBTAINS EP-EAL and EAL Matrix.

Standard:

Obtains EP-EAL and EAL Matrix Comments:

if Performance Step: 2 Identify EAL Classification for events in progress.

Standard :

The correct EAL is: Alert HAt6 Vehicle crash resulting in EITHER:

Visible damage (Note 4) to any Table H-i structure containing systems or components required for safe shutdown of the plant OR Control Room indication of degraded performance of systems required for the safe shutdown of the plant (Table H-i)

Comments:

Terminating Cue:

Event classification sheet provided to evaluator.

STOP TIME:

After the candidate returns this JPM classification page state:

Examiners Cue:

Now based on your EAL classification complete the Nuclear Power Plant Emergency Notification form.

WEB EOC is not available.

2013 NRC Exam Admin JPM SRO A4 Rev. Final

Appendix C Page 4 of 10 Form ES-C-i PERFORMANCE INFORMATION Emergency Action LeveLs Emergency Aticn LeveL Technical Bases Citegoy; i-I Kazarda Subcatjory 1

Nural of Dstnjcve Phnomna Initiating COflCiitiOfl Natural or destrucUve phenomena affecting Vital Areas EAI:

HAt6 Alert Vehicle crash resulting in EITHER:

VisIbI dimge (Nate 4)to any Thbi H1 structur continin tm& or cornponnts requrecl for safe shutcown of the plant OR Control Room imdicationof degraded performance of systems required for me sae shiitcon of the plant (Table 1I-I :

Nt 4 is&

cr sruzure : is. rdIy wchzui n*asrir.snIs, estng r r1yis s ficntc cse ccncsrn reshg e orird cper tycrIithyfaftecsc fety ctncI. sytern orcnpnnt Enpe rnae indudes: def due to ieat i!1pL denting, penetration, ptwe, raEkn, P1flt bsenrg sbl Dnge nctc blcrnih (ag., paint citippig. crrJ1e;)

Tbl H-I Strueturs Continirg Safe Shutd n Eqiiprnnt 1QrA ar Iin

FuI Har1ng uithg ftccs.-h Eiidiri Thrbir 8u1dnj inc udir Traiisfornr.ra)

mpry Dil Gt idiri Oies.1 Fu& Oi 9toree i1dix (DFO)

WLt:ake truzbire 4

uxiliary R ser..oi thtaice Sr.cture NSW S1ructre

zhyrtI Yard 2 1 Ot Enk underur rmevajs entain Si py,, n1ro 3nd c3bIeE: senirg anyi the areas I P-EAL Rev. I Page 152 of 26 I 2013 NRC Exam Admin JPM SROA4 Rev. Final

Appendix C Page 5 of 10 Form ES-C-i PERFORMANCE INFORMATION Emergency Action LeveLs Al eflmerit I merency ActIcn Level [ecrInicaI bases Mode Applicability:

All Generic The occurrence of St5LE DAMAGE andc degrades sytern repcnse s intended to diciimnate acianst esser eents The inta report should not be nterpfeted a rnandaflnçj a lençthy damage assessment prior to cIassiticatin. tJQ5ft1pt is made in this EAL to asses the acftl magnitude of the damage. The signmcance here is not that a particular system or structure wdujd. bul

[k:1 th vri wait ufu1fliit niui1u lu tii dei1L1iJ1L E&aton of th er Ie& i epç oprte, vo.Id he raed on Sjtern Malfunction EAL.

This EAL ackiree:es vehice crashes th the PROTECTED AREA that results in VISIBLE DAMAGE to VITL AREAS or indication of damage to safety structures, systems, D compcnents iiiiriiy fuitkii uid iuit R. if huhkwri uiti ptnL Plant-Spcltic The Table i-li strucres were obtained from the HNP Sf shLItdc?fl aflalysis. EQuipment witlin the Tui1ie &iildinci that 15 important for safe shutdown of the plant includes the:

components required to brng oftsite pDwer into the plant 69 KY buses, and the ability of the 50 VDC cyotom to oupply the 60 KJA invortor. Equipmcnt in the Yad 261 Duel Banke incbdes components fleeced to bring otfsite power into the i1ant 6:.9 KY buses and underground cables and piping for the ESW, EDO and NSW systems. (ret. 1, 2, 3)

This EL is intended to adress crashes of vehicle types large enough to cause significant daniage to piart struct res containing functions ad systems required for safe ahutdow of the Diant. Vehicle types include autcniobiles, aircraft, trucks, cranes, foiNiffs, wateitorne crag, etc.

HNP Basis Re 1

erence(s)::

1 3.3.1.1

2. AP-300 Severe Weather Response

3. DBD-31 Meteorological and Environmental Monitoring, Stem

4. AQP036. Safe Shutdo,w FoiIowir A Fire 5:

FSAR74 I EP-EAL Rev. 10 Pacje* 153of 296 I 2013 NRC Exam Admin JPM SRO A4 Rev. Final

Appendix C Page 6 of 10 Form ES-C-I PERFORMANCE INFORMATION Start Time for this portion of JPM begins when the individual has been provided the ENF form.

Evaluator Cue:

After the candidate returns the EAL classification page then provide them with a blank copy of PEP-310 Attachment 9, Nuclear Power Plant ENF to fill out manually. The clock starts when the candidate has the form.

START TIME:

Performance Step: 3 Determines that PEP-310 attachment 9, Nuclear Power Plant ENF is required.

Standard:

Locates PEP-310 attachment 9 on computer. Then when provided a blank ENF form by Evaluator completes the form manually.

Comments:

V Performance Step: 4 Completes PEP-310 Attachment 9 (see key for critical steps)

Standard:

PEP-310 Attachment 9 filled out correctly. Returns form to Evaluator.

Comments:

Terminating Cue:

ENF form completed and provided to evaluator.

STOP TIME:

Examiners Cue:

After the candidate returns the ENF form record the stop time and then announce END of JPM.

2013 NRC Exam Admin JPM SRO A4 Rev. Final

Appendix C Page 7 of 10 Form ES-C-I PERFORMANCE INFORMATION Justification for critical steps of the ENF notification form can be found in the LOCT Performance Evaluation grading guidance. This guidance has been approved by EP and the latest revision is dated 7/4/10.

The standards for timely and accurate Emergency Action level (EAL) Classification development, Protective Action Recommendations (PARs) development and EAL and PARs Notifications are set forth in NEI 99-02 (Revision 6), Regulatory Assessment Performance Indicator Guideline.

NOTE: The following (line numbers) are applicable to the Emergency Notification Form (ENF)

(For the 2013 NRC Exam Admin JPM SRO A4 the following ENF lines must be correctly filled out and are therefore critical)

Initial Emergency Notification Form (ENF) completed apropriate to the event to include:

(Line 1)

Whether the event is a drill or actual event (Line 4)

Class of emerency (Line 4)

EAL number (Line 4)

Description of emergency (EAL description)

(Line 5)

Whether offsite protective measures (PARs) are necessary (Line 5)

Potentially affected population and areaas (Correct EPZ subzone information)

(Line 6)

Whether a release is taking place (Line 9)

Wind direction and speed (Line 10)

Date and time of declartion of emergency (Line 11 or Line 3)

Plant and/or unit as applicable 2013 NRC Exam Admin JPM SRO A4 Rev. Final

Appendix C Page 8 of 10 Form ES-C-i PERFORMANCE INFORMATION Line 10

- Maximum classification declaration time is 1140 Examiners NOTE:

I Line 17

- Maximum Event notification time is 1155 Attachmcnt 9 Nuckar Power Pbnt Ernergcrny NoUfktitioi Fom ACTVAL EVEFif FES3E; 1

NO1FICAT1ON: T1 DTEF

?tY2NTATCN CcdrriIcn

N FP1ae 1l oeurq AX Im-ctrg SiabI Drig WiiidC OT dree Wnt Speed 1C rnh recpitakn

_XXXX Trday a a e

7. RELEASE S3NFE:

8. EVNTPPCGNO&

0. METECROLO3ICL IYJA:

NotteqJrE inai ticior 1O. DECLR.TIc*J TIMINT1a4 1i.FFECTEDUNSc W

ID LHT TAJS N

t FJtEd LNS StJ5 No RUr r CUC49 t1i_________ CC U3

%Pce itTm

13. FEWRKS:

FOLLOW-UP INFORMA1ION (Lines 1$ through 16 Not Required for InitiI Notifictions EMROENcY RELEASE DATA. UOTRECIUIRED W LIF{E4 A L SELECTED.

TPE:EIejatd MxI 3ind UHTS:G

.t3tUC tb4 c:__________ Iodir:___________

Chc FCM: irtom Etart Flite Date _J.

__S1op 11m_______ C _..._J_

Lku start Tiire Date _i J_Sop fln________ De

16. PROJEC]ICN PRMETRS:

PojeIvn ariod Esiirae ReaseCuricn

_______HcurE cjex pertmect Tme______

Date /

16. PROJECIED COSE TECE re Mutt Thyrtd cDE rn tariday 5

17.9RCVED NOIIFIED RECEIVED

- XXIX Taday Data Re. 28 Pace 28 of 56

1. DRLL

2. JNITLL.

3. Sfl2:

HIW

4. EVERGENCY UNJSUAL C/ENT

. ?LERT j SITE tREk EMERNCY GRL ER3Er4C(

CUSflCATON:

BSEDCN EAL_f E_ DESRIPTD ALEF the to ahiDle crasi-rasuit ing rr,l Pr>.

rn rf d,rr1r1 p frnrn,c r,F

!-f-m vpi vl fm safa siutlown of the plant Tab1e H-1

5. PROTECTIVE ACTION RECOMNENEATICINS:

NONE

. tELTR II K

TAL :cc:

kflH SrvrE PAASO OTFER

6. EMERGENC REA$E Noe I Ocjirtn Ha Cxtirre Jr1er hatcri Tk MCR-SEC 2013 NRC Exam Admin JPM SRO A4 Rev. Final

Appendix C Page 9 of 10 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2013 NRC Exam Admin JPM SRO A4 Classify an Event and Complete the ENF.

Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2013 NRC Exam Admin JPM SRO A4 Rev. Final

Appendix C Form ES-C-I JPM CUE SHEET Name:

Date:

This is a two (2) part TIME CRITICAL JPM where each part will be timed separately.

Given the following plant conditions:

The plant is in Mode 1 Wind speed is 10 mph and wind direction is 265 degrees A-SA Safety train is in service AOP-016 is being performed due to a 12 gpm leak in C SG The following occurs at 1115:

Offsite Power is lost Reactor trips on undervoltage for all 3 RCPs Initial Conditions:

SG A Pressure 598 psig SG B Pressure 595 psig SG C Pressure 603 psig Containment pressure stabilizes at 3.6 psig At 1120:

BOP reports 1 BD-39, Stm Gen C Inside Bldn lsol. and 1BD-49, Stm Gen C Outside Bldn Isol failed to close automatically or manually Sanford Substation Maintenance reports that their truck brakes failed and it has crashed into Breaker 52-13 damaging the breaker and the connecting transmission lines The time is now 1125 Part 1: Evaluate the EAL Matrix and determine the highest classification required for these plant conditions. NOTE: Do not use SEC judgment.

NOTE: Write out EAL classification in blank provided then raise Initiating Cue:

your hand and return your page to the Evaluator.

Part 2: Based on your EAL classification complete the Nuclear Power Plant Emergency Notification form. WEB EOC is NOT available.

EAL Classification:

EAL:

2013 NRC Exam Admin JPM SRO A4 Rev. Final

ML13325A960

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