ML100410114

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Initial Exam 2009-302 Draft Administrative JPMs
ML100410114
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 01/05/2010
From:
NRC/RGN-II
To:
References
IR-09-302
Download: ML100410114 (80)
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Appendix C Page 1 of 15 Form ES-C-1 Worksheet Facility: Shearon Harris Task No.: 301179H601 Task

Title:

Response to Voids In Reactor JPM No.: 2009B NRC Exam Vessel- Calculate Reactor Vessel Admin JPM RO A1-1 Maximum Vent Time KIA

Reference:

EPE E10 EK3.2 RO 3.2 SRO 3.7 Examinee: NRC Examiner:

Facility Evaluator: Date: _ __

Method of testing:

Simulated Performance: Actual Performance: x Classroom X Simulator Plant DRJ\fT 2009B NRC Exam Admin JPM RO A1-1 Rev 1

Appendix C Page 2 of 15 Form ES-C-1 Worksheet READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: The plant was at 100 percent power when a Small Break LOCA occurred.

  • All RCP have been secured.
  • SI has been terminated.
  • RVLlS Upper Range reading is 85 percent
  • Pressurizer level is 90 percent
  • RCS Pressure is 1560 psig
  • Containment Temperature is 195°F
  • Chemistry reports that Containment Hydrogen Concentration is 2.15 percent Based on the present conditions a void has formed in the Reactor Vessel. The CRS and STA have reviewed the CSFSTs. It was determined that FRP-1.3, Response To Voids In Reactor Vessel should be implemented.

Initiating Cue: The crew has completed preparing the Containment for Reactor Vessel venting. The CRS has directed you to calculate the maximum time the Reactor Vessel should be vented, using Attachment 1 of FRP-1.3 Your calculation should be determined to the second to allow timing using the MCR timer.

Task Standard: Determine maximum Reactor Vessel vent time within +/-5 seconds of calculation.

Required Materials: Calculator General

References:

FRP-1.3 Figure 2 and Attachment 1 (Rev. 16)

Handouts: FRP-1.3 Figure 2 and Attachment 1 (Rev. 16)

Time Critical Task: No Validation Time: 10 minutes 2009B NRC Exam Admin JPM RO A 1-1 Rev 1

Appendix C Page 3 of 15 Form ES-C-1 Worksheet Critical Step Justification Without the correct Containment volume you cannot determine the Step 2 maximum venting time Step 3 Without the correct hydrogen volume you cannot determine the maximum venting time Step 4 Without the correct hydrogen flow rate you cannot determine the maximum venting time Step 5 This is the maximum venting time calculation required by the CRS 2009B NRC Exam Admin JPM RD A1-1 Rev 1

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

FRP-I.3 Performance Step: 1 OBTAIN PROCEDURE (provided with handout)

Standard: Obtains FRP-1.3 and refers to Figure 2 and Attachment 1.

Comment:

FRP-I.3 Attachment 1 Step 1

./ Performance Step: 2 Calculate the maximum venting time using Attachment 1.

Calculate Containment Volume at STP 'A' in FT3 Standard: Using the provide Containment temperature of 195°F Containment Volume at STP 'A' = 1702094.66 FT3 Comment:

FRP-1.3 Attachment 1 Step 2

./ Performance Step: 3 Determine Maximum Hydrogen volume that can be vented 'B' in FT3 Standard: Using provided Containment Hydrogen Concentration of 2.15 percent determine maximum Hydrogen volume that can be vented 'B' = 14467.80 FT3 Comment:

./ - Denotes a Critical Step 2009B NRC Exam Admin JPM RO A1-1 Rev 1

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION FRP-I.3 Attachment 1 Step 3

../ Performance Step: 4 Determine Hydrogen flow rate as a function of RCS pressure 'C' in FT3/MIN.

Standard: Determines from Figure 2 that 1560 psig corresponds to 4850 FT3/MIN (Tolerance 4950 - 4750 FT3/MIN)

Comment:

FRP-1.3 Attachment 1 Step 4

../ Performance Step: 5 Calculate maximum venting time '0' in minutes.

Standard: Calculates 2.98 minutes (2 minutes and 59 seconds)

Tolerance +/- 5 seconds 3 min 4 seconds to 2 min 54 seconds Comment:

Terminating Cue: When calculation is returned ENDOFJPM STOP TIME:

../ - Denotes a Critical Step 2009B NRC Exam Admin JPM RO A1-1 Rev 1

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION KEY RESPONSE TO VOIDS IN WC'l'OR VESSEl.

6000

~

~

4000 3000 2000 1000 o 400 800 1200 11560~1oo 2000 2:4A}O ReS PRESSURE' {PStG)

I Rev. 16 I

./ - Denotes a Critical Step 20098 NRC Exam Admin JPM RO A1-1 Rev 1

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION KEY RESPONSE TO VOIDS IN REACTOR VESSEL Attachment 1 Sheet 1 of 1 INSTRUCTIONS roR DETBRHINING VENTING TIME

1. Detet'lline CNHT Volwa.e at STI.> A' ;

I A - (2.266 x 106 Fr3) x 492°R (CNtlT 'temperature OF + 460<"R) 1 195°F 1 A .11702094.66 (BT3) 2.

B _ 114467.80 1 (nl )

3. Deterllin.e Hydrogen flow rate as a funetion of ReS pressure 'C';
a. Cheek ReS pressure and mark on Figure 2.
b. Using Figure 2. read hydrogen flQW rate 'C',

1 4850 1 ITolerance 4750 - 4950 I c-(FT3/MIN)

4. Calculate 1I8X1:awa venting time 'D';

KaxiJnUll venting ti:ne - --

c 2 min and 59 seconds n- ____

D - ~-----o-Tolerance (MINUTES) 2 min 54 seconds 3 min 4 seconds EOP-FRP-I.3 Rev. 16 I Page 22 (If 23

./ - Denotes a Critical Step 2009B NRC Exam Admin JPM RO A1-1 Rev 1

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A 1 Response to Voids In Reactor Vessel - Calculate Reactor Vessel Maximum Vent Time Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009B NRC Exam Admin JPM RO A1-1 Rev 1

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET The plant was at 100 percent power when a Small Break LOCA Initial Conditions: occurred.

  • All RCP have been secured.
  • SI has been terminated.
  • RVLlS Upper Range reading is 85 percent
  • Pressurizer level is 90 percent
  • RCS Pressure is 1560 psig
  • Containment Temperature is 195°F
  • Chemistry reports that Containment Hydrogen Concentration is 2.15 percent Based on the present conditions a void has formed in the Reactor Vessel. The CRS and STA have reviewed the CSFSTs. It was determined that FRP-1.3, Response To Voids In Reactor Vessel should be implemented.

The crew has completed preparing the Containment for Reactor Initiating Cue:

Vessel venting. The CRS has directed you to calculate the maximum time the Reactor Vessel should be vented, using Attachment 1 of FRP-1.3 Your calculation should be determined to the second to allow timing using the MCR timer.

2009B NRC Exam Admin JPM RO A1-1 Rev 1

Appendix C Page 1 of 12 Form ES-C-1 Worksheet Facility: Shearon Harris Task No.: 001004H101 Task

Title:

Perform A Manual Shutdown JPM No.: 20098 NRC Exam Margin Calculation Admin JPM RO A 1-2 KIA

Reference:

G 2.1.25 RO 3.9 SRO 4.2 Examinee: NRC Examiner:

Facility Evaluator: Oate: _ __

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.

Initial Conditions: The plant has been operating at 52% power for 6 weeks while maintenance is replacing the motor on the 'A' Main Feedwater Pump

  • Core burnup is 140 EFPO
  • NO rods are believed to be immovable / untrippable
  • POWERTRAX is NOT available Initiating Cue: The CRS has directed you to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, "Manual SOM Calculation (Modes 1 and 2)" for current plant conditions.

NOTE: For this JPM assume independent verification has been performed.

20098 NRC Admin Exam RO A 1-2 Rev. 1

Appendix C Page 2 of 12 Form ES-C-1 Worksheet Task Standard: OST-1036, Attachment 3, Manual SOM Calculation (Modes 1 and 2),

completed with SOM of 5195 +/- 75 pcm (tolerance based on total of curves used and their division readability)

Required Materials: Calculator General

References:

OST-1036, Shutdown Margin Calculation Modes 1-5 (Rev. 40)

Curve Book (Cycle 16)

Handouts: OST-1036, Shutdown Margin Calculation Modes 1-5 (Rev. 40)

Time Critical Task: No Validation Time: 20 minutes Critical Step Justification Step 3 Must determine correct rod insertion limit based on curve value. The number of rod steps will be an input to the calculation.

Step 6 Must determine correct power defect based on curve value. The power defect will provide one of the inputs to the calculation.

Step 7 Must determine the correct rod worth based on curve value. The rod worth will provide one of the inputs to the calculation.

Step 9 The total shutdown margin was the task that the CRS directed applicant to perform.

2009B NRC Admin Exam RO A1-2 Rev. 1

Appendix C Page 3 of 12 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

OST-1036 Performance Step: 1 OBTAIN PROCEDURE (OST-1036 will be provided to allow candidates to write on, Curve Book will be included as a reference)

Standard: OST-1036, Section 7.3, Attachment 3, and Curve Book Comment:

OST-1036 Attachment 3 Step 1 Performance Step: 2 Enters Reactor Power Level Standard: Refers to given conditions and enters 52%

Comment:

CST-1036 Attachment 3 Step 2

./ Performance Step: 3 Determine Rod Insertion Limit for power level Standard: Refers to Curve F-16-1 and determines TS limit for RIL to be 96

+/- 2 steps (tolerance based on curve division readability)

Comment:

OST-1036 Attachment 3 Step 3 Performance Step: 4 Enters core Burn Up Standard: Refers to given conditions and enters 140 EFPD Comment:

./ - Denotes Critical Steps 2009B NRC Admin Exam RO A 1-2 Rev. 1

Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION OST-1036 Attachment 3 Step 4 Performance Step: 5 Enters RCS Boron Concentration Standard: Refers to initial conditions and enters 1140 ppm Comment:

Evaluator Note: ATT 3, STEP 5 NOT PERFORMED SINCE VALUE IS INCLUDED AS PART OF ATTACHMENT.

OST-1036 Attachment 3 Step 6

./ Performance Step: 6 Determines Power Defect for current power level Standard: Refers to Curve C-16-1 and determines power defect to be 1060 +/-50 pcm (tolerance based on curve division readability)

Comment:

OST-1036 Attachment 3 Step 7

./ Performance Step: 7 Determines Rod Worth for RIL position determined above Standard: Refers to Curve A-16-9 and determines rod worth to be 725 + 25 pcm (tolerance based on curve division readability)

Comment:

./ - Denotes Critical Steps 2009B NRC Admin Exam RO A 1-2 Rev. 1

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION OST-1036 Attachment 3 Step 8 Performance Step: 8 Enters worth of any additional immovable or untrippable rods Standard: Refers to given conditions and enters 0 Comment:

OST-1036 Attachment 3 Step 9 0/ Performance Step: 9 Determines Total Shutdown Margin Standard: Determines Total Shutdown Margin to be 5195 +/- 75 pcm (tolerance based on total of all curves used and their division readability)

Comment:

OST-1036 Section 7.3 Performance Step: 10 Signs off Section 7.3 steps Standard: Signs off steps as complete Comment:

Terminating Cue: When OST-1036, Attachment 3, Manual SOM Calculation is completed.

ENOOFJPM STOP TIME:

0/ - Denotes Critical Steps 2009B NRC Admin Exam RD A 1-2 Rev. 1

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 CRITICAL BORON CONCENTRATION ¥s. CYCLE EXPOSURE AT HFP. MO. EQU1UBR1UM XENON CONDmoNS 1900 1800 1100 1600 1500 400 300 200 100 51!FPDlDIV eYe I.E EXPOSURE (EFPD)

IDetermination of Boron concentration for 140 EFPD CURVE NO. .-':--'I"II'--!~FRinr----

.-';--'I'1':~~~inr---- ~~""'!'-

REV NO. ~~-:-

ORIGINATOR ~~~K:J.;5>>f""=--

u;J~~~~~~:-::: DATE SUPERVISOR Il~~~

.... __~"..,..~.......

.l4-.::~~~~E:o'-''o"'F-- DATE SUPSRINTENDENT ~

SHIFT OPERATIONS DATE

./ - Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION HARRIS UNIT 1 CYCLE 16 ROD INSERTION LIMITS 240 8,.2: ~

(46 8,.2 t5) (l 2.2 22!

(l2.2 221i~

, r 220 1// V /

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201) 180 '"

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0 V/ (0, (0,( ~G) lOG) 0 1Q 20 30 40 !E~ GO 70 30 90 1 PERCENT OF RATED THERMAL POWER CURVE NO, REYNO ~

ORIGINATOR ORIGINATOR SUPERVISOR

'r~~~~~;:u::;-:-

'foi:~~~=~~- DATE

.\

~TETE'",

DATE I->;M.

SUPERINTENDEIU

'i ~ ...- :1 r

SHIFT OPERATIONS DATE

./ - Denotes Critical Steps 2009B NRC Admin Exam RO A 1-2 Rev. 1

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 POWER DEFECT vs. POWER LEVEL for VARIOUS BORON CONCENTRATIONS BOL (0 :I EFPD ~ 160) 2D P<:MiD1\f 20 40 80 POWER LEVEL (peRCENT)

CURVE NO, REV NO 0 ORIGINATOR SUPERVISOR

~~fMiz..L~~~~!:!",- DATE DATE

.~.

SUPERJNTENIENT -

SHIFT OPERATIONS DATE

./ - Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 DIFFERENTIAL AND INTEGRAL ROD WORTH CONTROL BANKS D and C MOVING WITH 103 STEP OVERLAP SOL (0 ~ EfPD S 160). HFP, SQUIUBRIUM XENON

-1800 *18

~1700 *17

~1GOO

-1500 *15

,-1400 *14

&1300

.... -1200

§ e --1100

~

0

-1000

~ -900 0

~ .aoo

..J r2 -725 m

I-ie -600

.000

-400

-300

-zoo

  • 100
UPCtM)N 0

96 0 20 40 60 80 120 140 160 180 200 220 240

$ STePlilDIV I) tt3 :a~1

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

II BANKO 129

  • ~----~~~K~C---------*

CURVE CURVE NO.

NO.

ORIGINATOR ~~~~~~_ _ _

REV NO.

DATE SQ ..

SUPERVISOR ~~~:l:t:~::;;Clrel:~_ DATE SUPERlmEMDENT -

SHIFT OPERAilONS OPERA.lIONS DA lE Cr

./ - Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1

Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION (SHADED AREA BELOW INDICATES DATA ALREADY PROVIDED)

Manual SDM Calculation (Modes 1 and 2)

1. Reactor power level. 52  %
2. Rod insertion limit for the above power level 96 +/- 2 96+/-2 steps on bank D
3. Burn up (POWERTRAXIMCR Status Board). 140 EFPD
4. Present RCS Boron Concentration 1140 ppm NOTE: Use absolute values of numbers obtained from curves.
5. Total worth of all control and shutdown banks, minus the worth of the most reactive rod for Fuel Cycle 16.

pcm (a )

6. Cycle 16 Power defect for the power level recorded in Step 1.

(Refer to Curves C-X-1 to C-X-3).

Curve used C-16-1 1060 +/-50 pcm (b)

NOTE: HFP curves are used for power levels of 10% or greater.

7. Inserted control rod worth at the rod insertion limit recorded in Step 2.

(Refer to Curves A-X-6 to A-X-11)

Curve used A-16-9 725 +/-25 pcm (c )

8. Worth of any additional immovable or untrippable rods (for each stuck rod, use the most reactive single rod worth (1129 pcm) or obtain individual withdrawn rod worth from the reactor engineer).

o pcm (d)

9. Determine the Total Shutdown Margin using the following formula:

Total SDM C B = 6980 - 1060 +/ 725 +/ 0 (e ) (a ) (b) (c) (d) 5195 +/- 75 pcm

( e)

./ - Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009B NRC EXAM Admin JPM RO A 1 Perform A Manual Shutdown Margin Calculation Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009B NRC Admin Exam RO A 1-2 Rev. 1

Appendix C Page 12 of 12 Form ES-C-1 JPM CUE SHEET The plant has been operating at 52% power for 6 weeks while Initial Conditions: maintenance is replacing the motor on the 'A' Main Feedwater Pump

  • Core burnup is 140 EFPD
  • NO rods are believed to be immovable / untrippable POWERTRAX is NOT available Initiating Cue:

The CRS has directed you to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, "Manual SDM Calculation (Modes 1 and 2)" for current plant conditions.

NOTE: For this JPM assume independent verification has been performed.

2009B NRC Admin Exam RO A1-2 Rev. 1

Appendix C Page 1 of 12 Form ES-C-1 Worksheet Facility: Shearon Harris Task No.: 005016H101 Task

Title:

Perform OP-111 , Attachment 3 - JPM No.: 2009B NRC Exam Low Head SI Standby Lineup Admin JPM RO A2 Checklist KIA

Reference:

G2.2.15 RO 3.9 SRO 4.3 Examinee: NRC Examiner:

Facility Evaluator: Date: _ __

Method of testing:

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

Initial Conditions: A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

Initiating Cue: You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 - Low Head SI Standby Lineup Checklist, for the control room operated valves. An AO is checking the local equipment.

2009B NRC RO Admin Exam JPM RO A2 Rev. 1

Appendix C Page 2 of 12 Form ES-C-1 Worksheet Task Standard: All errors identified.

Required Materials: OP-111, Attachment 3, with CHECK column initialed except for the local valves.

General

References:

OP-111 (Rev. 44)

Time Critical Task: No Validation Time: 10 minutes Critical Step Justification Step 2 Must identify all out of alignment equipment for Independent Verification Step 3 Must identify all out of alignment equipment for Independent Verification Step 4 Must identify all out of alignment equipment for Independent Verification Step 5 Must identify all out of alignment equipment for Independent Verification Step 6 Must identify all out of alignment equipment for Independent Verification 2009B NRC RO Admin Exam JPM RO A2 Rev. 1

Appendix C Page 3 of 12 Form ES-C-1 Worksheet 20098 NRC Exam - SIMULATOR SETUP Simulator Operator

  • Reset to IC-170 (Password 9newguys)

Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

To recreate the conditions of this JPM:

  • Initial Simulator IC-16 (Mode 4 with RHR aligned for ECCS)
  • Place 1RH-30, RHR HEAT XCHG A OUT FLOW CONT to "0%" open on controller
  • Leave control power ON for 1SI-341 S8
  • Freeze and Snap these conditions for future use 20098 NRC RO Admin Exam JPM RO A2 Rev. 1

Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

OP-111 Attachment 3 Performance Step: 1 Obtain procedure.

Standard: Fills out applicable sections of Sheet 1 of 4 and reviews Attachment.

Evaluator Cue: Provide OP-111, Attachment 3.

Evaluator Note: The Attachment can be performed in any order. The following valves/controls are out of position. All others are correctly positioned.

Comment:

OP-111 Attachment 3 continued

" Performance Step: 2 Locates and compares actual position to required position lAW Attachment 3.

Standard: Determines 1RH-30 is SHUT (0% demand) and notes out-of-position condition in REMARKS section.

Evaluator Cue: As CRS: Throughout the JPM, acknowledge any verbal communications. Instruct them to document mis-positioned controls/valves but continue performing the Attachment without re-aligning any equipment.

Comment:

./ - Denotes Critical Steps 2009B NRC Admin Exam JPM RO A2 Rev. 1

Appendix C Page 5 ot 12 Form ES-C-1 PERFORMANCE INFORMATION OP-111 Attachment 3 continued

,j Performance Step: 3 Locates and compares actual position to required position lAW Attachment 3.

Standard: Determines 1SI-341 SB is not OFF and notes out-ot-position condition in REMARKS section.

Comment:

OP-111 Attachment 3 continued

,j Performance Step: 4 Locates and compares actual position to required position lAW Attachment 3.

Standard: Determines 1SI-322 SA is not OPEN and notes out-ot-position condition in REMARKS section.

Comment:

OP-111 Attachment 3 continued

,j Performance Step: 5 Locates and compares actual position to required position lAW Attachment 3.

  • 1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA Standard: Determines 1CC-147 is not SHUT and notes out-ot-position condition in REMARKS section.

Comment:

./ - Denotes Critical Steps 2009B NRC Admin Exam JPM RO A2 Rev. 1

Appendix C Page 60t 12 Form ES-C-1 PERFORMANCE INFORMATION OP-111 Attachment 3 continued

--J Performance Step: 6 Locates and compares actual position to required position lAW Attachment 3.

  • 1CC-167, CCW FROM RHR HEAT EXCHANGER B-SB Standard: Determines 1CC-167 is not SHUT and notes out-ot-position condition in REMARKS section.

Comment:

OP-111 Attachment 3 continued Performance Step: 7 Provide Attachment to CRS.

Standard: Completes Att. 3, Sheet 1 ot 4 and provides Attachment to CRS.

Evaluator Cue: Acknowledge any verbal report.

Comment:

Terminating Cue: When the applicable section of the Attachment has been returned to the CRS.

ENDOFJPM STOP TIME:

./ - Denotes Critical Steps 2009B NRC Admin Exam JPM RO A2 Rev. 1

Appendix C Page 7 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A2 - Perform OP-111, Attachment 3 - Low Head SI Standby Lineup Checklist Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009B NRC Admin Exam JPM RO A2 Rev. 1

Appendix C Page 8 of 12 Form ES-C-1 JPM CUE SHEET Initial Conditions: A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

Initiating Cue: You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 - Low Head SI Standby Lineup Checklist, for the control room operated valves.

An AO is checking the local equipment.

2009B NRC Exam Admin JPM RO A2 Rev. 1

Appendix C Page 9 of 12 Form ES-C-1 JPM CUE SHEET Attachment 3 - Low Head Safety Injection Standby Lineup Checklist Sheet 1 of4 Person(s) Performing Checklist Initials Name (Print) Initials Name (Print)

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

TR Terry Right Remarks - Indicate any component not in the prescribed position.

Checklist Started Time 0(;00 Date TODAY Checklist Completed Time Date ______

Approved by Date Date _ _ __

UnitSCQ ----

After receiving the final review signature, this OP Attachment becomes a QA RECORD.

IOP-111 Rev. 44 Page 142 of 1531 2009B NRC Exam Admin JPM RO A2 Rev. 1

Appendix C Page 10 of 12 Form ES-C-1 JPM CUE SHEET Attachment 3 -low Head Safety Injection Standby Uneup Checklist Sheet2of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSmON CHECK VERIFY 1RH-1 RCS lOOP A TO RHR PUMP A-SA Shut TR 1RH-2 RCS lOOP A TO RHR PUMP A-SA Shut TR 1RH-39 RCS lOOP C TO RHR PUMP B-SB Shut TR 1RH-40 RCSlOOPCTO RHRPUMP B-SB Shut TR 1RH-30 RHR HEAT XCHG A OUT flOW CONT Open TR 1RH-66 RHR HEAT XCHG B OUT FLOW CONT TR (HC-603B1) Open 1RH-20 RHR HEAT XCHG A BVP FLOW CaNT Manual &

Shut TR 1RH-58 RHR HEAT XCHG B BVP FLOW CaNT Manual &

Shut TR 1RH-26 '"' RHR Header A to eves letdown lsol locked Shut TR Vlv 1RH-64 '"' RHR Header B to eves Letdown lsol locked Shut TR Vlv 1RH-31 RHR PUMP A-SA MINI FLOW Opeo TR 1RH-69 RHR PUMP B-SB MINI FLOW Opeo TR 1CS-28 RHR LETDOWN (HC-1421) Shut TR 1CC-146 ** RHR HX A OuOet Throttle Valve Locked TR Throttled 1CC-147 CCW FROM RHR HEAT EXCHANGER TR Shut A-SA

    • Throttled =

This is a local valve operated in the body of the procedure.

should be as recorded in the last OST-1216. This ensures the required flow for E CSfunction.

IOP-111 Rev. 44 Page 143 of 1531 2009B NRC Exam Admin JPM RO A2 Rev. 1

Appendix C Page 11 of 12 Form ES-C-1 JPM CUE SHEET Attachment 3 - Low Head Safety Injection Standby Uneup Checklist Sheet3of4 COMPONENT NUMBER COMPONENT DESCRIPTION POsmON CHECK VERIFY 1CC-166- RHR HX B Oullet Throttle Vatve Locked TR Throttled 1CC-167 CCW FROM RHR HEAT EXCHANGER TR Shut B-SB 1SI-340SA LOW HEAD 51lRAlN A TO COLD LEG Open & Pull to Lock TR 1SI-340SA LOW HEAD SI TRAIN A TO COLD LEG Off TR CONT PWR & VlV POS 1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG ~&Pull to Lock TR 1SI-341 SB LOW HEAD 51 TRAIN B TO COLD LEG Off TR CONT PWR & VlV pas 1SI-326SA LOW HEAD SI TRAIN A TO HOT LEG Open TR CROSSOVER 1SI-327SB LOW HEAD 51 TRAIN B TO HOT LEG Open TR CROSSOVER 1SI-322SA RWST TO RHR PUMP A-SA Open TR 1SI-323SB RWST TO RHR PUMP B-SB Open TR

- Throttled position should be as recorded in the last 05T-1216. This ensures the required flow for ECCS function.

IOP-111 Rev. 44 Page 144 of 153 I 2009B NRC Exam Admin JPM RO A2 Rev. 1

Appendix C Page 12 of 12 Form ES-C-1 JPM CUE SHEET Attachment 3 - Low Head Safety Injection Standby Uneup Checklist Sheet4of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSmON CHECK VERIFY 480V MCC-1A21-SA 1A21-SA-7B RCS L~A to RHR Pump 1A-SA Locked Off TR (1RH-2) oth Bkrs)

Locked Off TR 1A21-SA-8A RCS L~ C to RHR PUfll> 1B-SB Locked Off TR (1 RH4O) (Both Bkrs)

Locked Off TR 4tlUV MGG-1tl21-S1:i 1B21-SB-5B RCS ~ RHR Pump 1A-SA (1RH-1) Bkrs) Locked Off TR Locked Off TR 1B21-SB-11A RCS ~ C to RHR PUrIll1B-SB Locked Off TR (1RH-39J (Both Bkrs)

Locked Off TR 1 OP-111 Rev. 44 Page 145 of 1531 2009B NRC Exam Admin JPM RO A2 Rev. 1

Appendix C Page 1 of 8 Form ES-C-1 Worksheet Facility: Shearon Harris Task No.:

Task

Title:

Using survey maps determine stay JPM No.: 20098 NRC Exam times Admin JPM RD A-3 KIA

Reference:

G.2.3.4 RO 3.2 SRO 3.7 Examinee: NRC Examiner:

Facility Evaluator: Date: _ __

Method of testing:

Simulated Performance: Actual Performance: x Classroom X Simulator Plant 20098 NRC Exam Admin JPM ROA3 Rev. 1

Appendix C Page 2 of 8 Form ES-C-1 Worksheet READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

  • 1ED-18 Initiating Cue: 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 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem.

The clearance and work activity is for the 'A' ED Tank Transfer Pump.

Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits. Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent - Radiation Protection approval.

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.

2009B NRC Exam Admin JPM ROA3 Rev. 1

Appendix C Page 3 of 8 Form ES-C-1 Worksheet Task Standard: Calculation of stay times based on survey maps, two hours for Operator 1, five hours for Operator 2.

Required Materials: Survey map A4 RAB 190' North Valve MAP 2 SFD-5-S-0684 General

References:

DOS-NGGC-0004 (Rev. 10)

DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non- Progress Energy dose for the current year has been determined.

Time Critical Task: No Validation Time: 12 minutes Critical Task Justification Step 1 Must determine dose rates in order to calculate stay time Step 2 Must determine available dose to determine stay time.

Step 3 Calculation of stay time.

2009B NRC Exam Admin JPM ROA3 Rev. 1

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Evaluator Note: The order of performance does not matter IF THE APPLICANT ASKS FOR IT: Provide a copy of OOS-NGGC-0004, Rev. 10

./ Performance Step: 1 Using Radiological Survey Record Map A4 and RAB 190' North map, determines dose rates in the area where the clearance will be applied Standard: Identifies that General Area Dose Rates are 120 mrem/hr Comment:

./ Performance Step: 2 Determine the remaining dose for the year for each individual Standard: Operator 1: 240 mrem (2000 mrem - 1760 mrem =240 mrem Operator 2: 600 mrem 4000 mrem - 700 mrem (PE) - 2700 mrem (SL) =600 mrem Comment:

./ - Denotes Critical Steps 2009B NRC Exam Admin JPM RO A3 Rev. 1

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION

./ Performance Step: 3 Determine stay time for each operator (based on 1st Operator reaching 2 mrem and the 2nd Operator reaching 4 mrem - for the year)

Standard: Operator 1: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 240 mrem + 120mrem/hr =2 hrs Operator 2: 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 600 mrem + 120 mrem/hr =5 hours Comment:

Terminating Cue: After the stay time has been calculated, this JPM is complete ENDOFJPM STOP TIME:

../ - Denotes Critical Steps 2009B NRC Exam Admin JPM RO A3 Rev. 1

Appendix C Page 6 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A Using survey maps determine stay times. (DOS-NGGC-0004 Rev. 10)

DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT =2 rem Progress Energy dose not to exceed 4 rem total dose if non- Progress Energy dose for the current year has been determined.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009B NRC Exam Admin JPM RO A3 Rev. 1

Appendix C Page 7 of 8 Form ES-C-1 JPM CUE SHEET Initial Conditions: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

  • 1ED-18 INITIATING CUE: 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 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem.

The clearance and work activity is for the 'A' ED Tank Transfer Pump.

Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits. Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent - Radiation Protection approval.

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.

Name _____________________________________

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

Operator 1: ____________________

_____________________ Operator 2:

2009B NRC Exam Admin JPM RO A3 Rev. 1

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Appendix C Page 1 of 6 Form ES-C-1 Worksheet Facility: Shearon Harris Task No.:

Task

Title:

During a Loss of Shutdown Cooling. JPM No.: 2009B NRC Exam determine the time that the RCS will Admin JPM SRO A1-1 reach Core Boiling and Boil-Off KIA

Reference:

G2.1.20 RD 4.6 SRO 4.6 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.

Initial Conditions: On 9/05/09 at 0000 the plant was shutdown for a refueling outage.

  • While the Reactor cavity was being filled the 'B' RHR pump tripped.

Motor repairs are not expected to be completed until 9/25/09.

  • The Reactor cavity fill was completed to the normal refueling levels with the 'A' RHR pump.
  • No fuel has been moved due to problems with the Manipulator Crane and the Source Range audible count rate.
  • On 9/22/09 at 1400 the 'A' RHR pump tripped.
  • The crew is implementing AOP-020, Loss of RCS Inventory or RHR While Shutdown.
  • Core exit thermocouples are rising; they are currently reading 135°F.

Initiating Cue: lAW AOP-020 you are directed to refer to curves H-X-8 through H-X-11 and determine the time to reach core boiling and core boil-off time. Mark up your curves to indicate where you are determining these times. Return the curves to the examiner with this page. Write your estimates of time to boil" and time to boil-off' on the lines at the bottom of this page (below).

2009B NRC Exam Admin JPM SRO A 1-1 Rev. 1

Appendix C Page 2 of 6 Form ES-C-1 Worksheet Task Standard: Candidate obtains curves and correctly identifies the time to reach core boiling and core boil-off time Required Materials: Curves H-X-8 through H-X-11 (All Rev. 2)

General

References:

AOP-020 (Rev. 31) Curve Book curves H-X-8, 9,10 and 11 (All Rev. 2)

Time Critical Task: No Validation Time: 10 minutes Critical Step Justification Step 3 Step required in order to accurately determine time to boil" using the appropriate curve.

Step 4 Step required in order to accurately determine time to boil-off" using the appropriate curve.

2009B NRC Exam Admin JPM SRO A1-1 Rev. 1

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Performance Step: 1 OBTAIN CURVES NEEDED FOR CALCULATION (Curves will be provided to the candidate)

Standard: Refers to curves H-X-8 through H-X-11 Comment:

Performance Step: 2 Refers to provided data and determines that curve H-X-9 is required to calculate time to boil" and curve H-X-11 is required to calculate "boil-off' time Standard: Reviews curves and determines which ones are appropriate to determine the time to boil" and "boil-off time" Comment:

./ Performance Step: 3 Based on time since shutdown (9/5/09 - 9/22109) 17 days 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> since shutdown and current RCS temperature of 135°F using curve H-X-9 determine time to boil" Standard: Reviews curve H-X-9 Determines that time to boil" is 22 minutes (+/- 1 minute)

Comment:

./ - Denotes Critical Steps 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION

./ Performance Step: 4 Based on time since shutdown (9/5/09 - 9/22/09) 17 days 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> since shutdown and current RCS temperature of 135°F using curve H-X-11 determine time to boil-oft" Standard: Reviews curve H-X-11 Determines that time to boil-off' is 4 hrs and 45 minutes

<+/- 15 minutes) or (4.5 to 5.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />)

Comment:

Terminating Cue: After completing the "time to boil" and "time to boil-off" calculation, the evaluation on this JPM is complete.

ENDOFJPM STOP TIME:

./ - Denotes Critical Steps 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A1 During a Loss of Shutdown Cooling, determine the time that the RCS will reach Core Boiling and Boil-Off Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009B NRC Exam Admin JPM SRO A1-1 Rev. 1

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET Initial Conditions: On 9/05/09 at 0000 the plant was shutdown for a refueling outage.

  • While the Reactor cavity was being filled the '8' RHR pump tripped. Motor repairs are not expected to be completed until 9/25/09.
  • The Reactor cavity fill was completed to the normal refueling levels with the 'A' RHR pump.
  • No fuel has been moved due to problems with the Manipulator Crane and the Source Range audible count rate.
  • On 9/22/09 at 1400 the 'A' RHR pump tripped.
  • The crew is implementing AOP-020, Loss of RCS Inventory or RHR While Shutdown.
  • Core exit thermocouples are rising; they are currently reading 135°F.

INITIATING CUE: lAW AOP-020 you are directed to refer to curves H-X-8 through H-X-11 and determine the time to reach core boiling and core boil-off time. Mark up your curves to indicate where you are determining these times. Return the curves to the examiner with this page. Write your estimates of time to boil" and time to boil-off' on the lines at the bottom of this page (below).

Name _______________________________________________

Record your calculations here and return your curves to the examiner:

TIME TO BOIL _ _ _ _ _ _ _ __

TIME TO BOIL-OFF _ ____ __ __ _ __ __ ___

2009B NRC Exam Admin JPM SRO A1-1 Rev. 1

Appendix C Page 1 of 7 Form ES-C-1

.... ii Worksheet Facility: Shearon Harris Task No.: 301013H401 Task

Title:

Determine Boric Acid Addition JPM No.: 2009B NRC Exam Following CR Evacuation Admin JPM SRO A1-2 KIA

Reference:

G2.1.25 RO 3.9 SRO 4.2 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.

Initial Conditions: The Control Room has been evacuated and the MCB transfer to the ACP has been completed. Plant management has directed a plant cooldown to mode 5 utilizing AOP-004. BAT level is 83% with a concentration of 7205 ppm. The RCS is currently 915 ppm.

Initiating Cue: You are the CRS. Perform a calculation of the required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST-1036 cold shutdown boron requirement of 1740 ppm.

DRAFT 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1

Appendix C Page 2 of 7 Form ES-C-1 Worksheet Task Standard: Utilizes Curve E-X-2 to determine required boric acid addition to achieve cold shutdown and Curve D-2 to obtain a change of 27 to 29 percent in BAT level (or a final level of 54 to 56 percent).

Actual is 28% change (or 55% final).

Required Materials: Curve Book Calculator General

References:

AOP-004 (Rev. 46)

Curve Book nomograph E-X-2 (Rev. 4) and Curve D-2 (Rev. 0)

Time Critical Task: No Validation Time: 15 minutes Critical Step Justification Step 3 Step is critical in order to correctly identify the amount of boric acid required boric acid concentration.

Step 4 Step is critical in order to determine the change in tank level.

2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1

Appendix C Page 3 of 7 Form ES-C-1 VERIFICATION OF COMPLETION START TIME:

Performance Step: 1 OBTAIN PROCEDURE Standard: Obtains AOP-004 and refers to Section 3.2 Step 25 (Copy of step will be provided to the candidate)

Comment:

Performance Step: 2 Obtain cold shutdown boron concentration using copy of latest OST-1036 in back of book.

Standard:

Evaluator Cue: (If candidate asks: This information is provided in the initiating cue.)

Required shutdown boron concentration is 1740 ppm Comment:

./ Performance Step: 3 Determine required gallons of boric acid to achieve required RCS boron concentration using the formula on the boron addition nomograph E-2 Standard: Utilizes formula on Nomograph E-2 and calculates between 9130 to 9030 gallons of boric acid to be added. Actual is 9080 gallons Boron Addition (ReS @ 350 D F)

Vi =. -M 1n(7000-Cf) 8.33 7000 - Ci M =538,000

./- Denotes Critical Steps 2009B NRC Exam Admin JPMSRO A1-2 Rev. 1

Appendix C Page 4 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Examiners NOTE: The Nomograph formula found on Curve E-X-2 assumes that the BAT boron concentration is 7000 ppm. In this JPM the given information is BAT concentration is 7205 ppm. The candidate MUST use the given concentration of 7205 ppm to come to the correct boron addition.

CORRECT CALCULATION

-538000 InlZ205 -1740).

VB = 8. 33 \-7205 - 915 . =9080 If candidate uses 7000 ppm for BAT BA concentration (from the nomograph) instead of changing to 7205 ppm the result will be 9409 gallons INCORRECT CALCULATION (using wrong BAT concentration)

-538000 I (!OOO -1740)

VB = 8.. 33 n\7000 - 915 . =9409 If candidate uses correct BAT BA concentration but uses the wrong Curve (E-X-1 verses E-X-2) the result will be 7443 gallons INCORRECT CALCULATION (using wrong RCS Mass - wrong curve)

-441000 l (Z205 -1740)

VB = 8.33 n\720S - 915 ; =7443 Comment:

./- Denotes Critical Steps 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1

Appendix C Page 5 of 7 Form ES-C-1 VERIFICATION OF COMPLETION 0/ Performance Step: 4 Determine the change in boric acid tank level equivalent to the required gallons of boric acid using the boric acid tank curve 0-2 Standard: Utilizes Curve 0-2 and obtains a change of 27 to 29 percent (or a final level of 54 to 56 percent).

Actual is 28% change (or 55% final).

-:':51)00 1IIIIIIIIIIIIIIltill IIllllL1l1ll1ll1t II lt60rle n60r1e Add Tonk Volume in ~n(lrt

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.+

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III 1111/11 IU'II 10 fO 30 40 5O~50 70 80[!!] 90 100 120000 - 9080 = 10020 f}

It Incnceted * \83-55=28\

~ONTROL ROOM COpy . I Comment:

STOP TIME:

Terminating Cue: When candidate completes the calculations the JPM is completed.

ENDOFJPM 0/- Denotes Critical Steps 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 20098 NRC Exam Admin JPM SRO A 1 Determine boric acid addition following control room evacuation Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

../- Denotes Critical Steps 20098 NRC Exam Admin JPMSRO A 1-2 Rev. 1

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET The Control Room has been evacuated and the MCB transfer to Initial Conditions:

the ACP has been completed. Plant management has directed a plant cooldown to mode 5 utilizing AOP-004. BAT level is 83%

with a concentration of 7205 ppm. The RCS is currently 915 ppm.

Initiating Cue: You are the CRS. Perform a calculation of the required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST-1036 cold shutdown boron requirement of 1740 ppm.

2009B NRC Exam Admin JPMSRO A1-2 Rev. 1

Appendix C DRAFT Page 1 of 12 Worksheet Form ES-C-1 Facility: Shearon Harris Task No.: 005016H101 Task

Title:

Perform OP-111, Attachment 3 -. JPM No.: 2009B NRC Exam Low Head SI Standby Lineup Admin JPM SRO A2 Checklist KIA

Reference:

G2.2.15 RO 3.9 SRO 4.3 Examinee: NRC Examiner:

Facility Evaluator: Date: _ __

Method of testing:

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

Initial Conditions: A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

Initiating Cue: You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 - Low Head SI Standby Lineup Checklist, for the control room operated valves. An AD is checking the local equipment.

2009B NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 2 of 12 Form ES-C-1 Worksheet Task Standard: All errors identified.

Required Materials: OP-111, Attachment 3, with CHECK column initialed except for the local valves.

General

References:

OP-111 (Rev. 44)

Time Critical Task: No Validation Time: 10 minutes Critical Step Justification:

Step 2 Must identify all out of alignment equipment for Independent Verification Step 3 Must identify all out of alignment equipment for Independent Verification Step 4 Must identify all out of alignment equipment for Independent Verification Step 5 Must identify all out of alignment equipment for Independent Verification Step 6 Must identify all out of alignment equipment for Independent Verification 2009B NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 3 of 12 Form ES-C-1 Worksheet 20098 NRC Exam - SIMULATOR SETUP Simulator Operator

  • Reset to IC-170 (Password 9newguys)

Silence and Acknowledge annunciators GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.)

To recreate the conditions of this JPM:

  • Initial Simulator IC-16 (Mode 4 with RHR aligned for ECCS)
  • Place 1RH-30, RHR HEAT XCHG A OUT FLOW CO NT to "0%" open on controller
  • Leave control power ON for 1SI-341 S8
  • Freeze and Snap these conditions for future use 20098 NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

OP-111 Attachment 3 Performance Step: 1 Obtain procedure.

Standard: Fills out applicable sections of Sheet 1 of 4 and reviews Attachment.

Evaluator Cue: Provide OP-111, Attachment 3.

Evaluator Note: The Attachment can be performed in any order. The following valves/controls are out of position. All others are correctly positioned.

Comment:

OP-111 Attachment 3 continued

~ Performance Step: 2 Locates and compares actual position to required position lAW Attachment 3.

Standard: Determines 1RH-30 is SHUT (0% demand) and notes out-of-position condition in REMARKS section.

Evaluator Cue: As CRS: Throughout the JPM, acknowledge any verbal communications. Instruct them to document mis-positioned controls/valves but continue performing the Attachment without re-aligning any equipment.

Comment:

../ - Denotes Critical Steps 2009B NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 5 ot 12 Form ES-C-1 PERFORMANCE INFORMATION OP-111 Attachment 3 continued

" Performance Step: 3 Locates and compares actual position to required position lAW Attachment 3.

Standard: Determines 1SI-341 SB is not OFF and notes out-ot-position condition in REMARKS section.

Comment:

OP-111 Attachment 3 continued '

" Performance Step: 4 Locates and compares actual position to required position lAW Attachment 3.

Standard: Determines 1SI-322 SA is not OPEN and notes out-ot-position condition in REMARKS section.

Comment:

OP-111 Attachment 3 continued

" Performance Step: 5 Locates and compares actual position to required position lAW Attachment 3.

  • 1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA Standard: Determines 1CC-147 is not SHUT and notes out-ot-position condition in REMARKS section.

Comment:

./ - Denotes Critical Steps 2009B NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 60t 12 Form ES-C-1 PERFORMANCE INFORMATION OP-111 Attachment 3 continued

" Performance Step: 6 Locates and compares actual position to required position lAW Attachment 3.

  • 1CC-167, CCW FROM RHR HEAT EXCHANGER 8-S8 Standard: Determines 1CC-167 is not SHUT and notes out-ot-position condition in REMARKS section.

Comment:

OP-111 Attachment 3 continued Performance Step: 7 Provide Attachment to CRS.

Standard: Completes Att. 3, Sheet 1 ot 4 and provides Attachment to CRS.

Evaluator Cue: Acknowledge any verbal report.

Comment:

Terminating Cue: When the applicable section of the Attachment has been returned to the CRS:

ENDOFJPM STOP TIME:

./ - Denotes Critical Steps 20098 NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 7 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A2 - Perform OP-111, Attachment 3 - Low Head SI Standby Lineup Checklist Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009B NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 8 of 12 Form ES-C-1 JPM CUE SHEET Initial Conditions: A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

Initiating Cue: You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 - Low Head SI Standby Lineup Checklist, for the control room operated valves.

An AO is checking the local equipment.

2009B NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 9 of 12 Form ES-C-1 JPM CUE SHEET Attacmnent 3 - Low Head Safety Injection Standby Lineup Checklist Sheet1of4 Person(s) Perfonning Cheddisf Initials Name (Print) Initials Name (Print)

TR Terry Ilight Remarks - Indicate any component not in the prescribed positiorL Checklist Started Date TODAY' Checklist Completed Time Date _ _ __

Approved by Date UnitSCO After receiving the final review signature. this OP Attadvnent becomes a QA RECORD.

IOP-111 Rev. 44 Page 142 of 1531 2009B NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 10 of 12 Form ES-C-1 JPM CUE SHEET Attachment 3 - Low Head Safety Injection Standby Uneup Checklist Sheet2of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSITION CHECK VERIFY 1RH-1 RCS LOOP A TO RHR PUMP A-SA Shut TR 1RH-2 RCS LOOP A TO RHR PUMP A-SA Shut TR 1RH-39 RCS LOOP C TO RHR PUMP B-SB Shut TR 1RH-40 RCSLOOPCTORHRPUMPB-SB Shut TR 1RH-30 RHR HEAT XCHG A OUT FLOW CONT Open TR 1RH-66 RHR HEAT XCHG B OUT FLOW CONT TR (HCr03B1) Open 1RH-20 RHR HEAT XCHG A BVP FLOW CONT Manual &

Shut TR 1RH-58 RHR HEAT XCHG B BVP FLOW CONT Manual &

Shut TR 1RH-26 ,. RHR Header A to eves Letdown 1501 Vlv Locked Shut TR 1RH-64

... This is a local valve operated in the body of the procedure.

- Throttled ~0I1 should be as recorded in the last OST-1216. This ensures the required flow for E CS function.

IOP-111 Rev. 44 Page 143 of 1531 2009B NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 11 of 12 Form ES-C-1 JPM CUE SHEET Attachment 3 - Low Head Safety Injection Standby lineup Checklist Sheet 3 of4 COMPONENT NUMBER COMPONENT DESCRIPTION POsmON CHECK VERIFY 1CC-166- RHR HX B Outlet Throttle Valve Locked TR Throttled 1CC-167 CCW FROM RHR HEAT EXCHANGER TR B-SB Shut 1SI-340SA LOW HEAD SI TRAIN A TO COLD LEG Open & Pull to Lock TR 1SI-340SA LOW HEAD SI TRAIN A TO COLD LEG Off TR CONT PWR & VLV POS 1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG ~&Pull to Lock TR 1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG Off TR CONT PWR & VLV POS 1SI-326 SA LOW HEAD SI TRAIN A TO HOT LEG Open TR CROSSOVER 1SI-327SB LOW HEAD SI TRAIN B TO HOT LEG Open TR CROSSOVER 1SI-322 SA RWST TO RHR PUMP A-SA Open TR 1SI-323SB RWST TO RHR PUMP B-SB Open TR

- Throttled position should be as recorded in the last OST-1216. This ensures the required flow for ECCS function.

1 OP-111 Rev. 44 Page 144 of 1531 20098 NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 12 of 12 Form ES-C-1 JPM CUE SHEET Attachment 3 - Low Head Safety Injection Standby Uneup Checklist Sheet4of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSmON CHECK VERIFY 480V MCC-1A21-SA 1A21-SA-7B RCS Lg(B A to RHR Puflll1A-SA Locked Off TR (1RH-2) oth 8krs)

Locked Off TR 1A21-SA-8A RCS L~ C to RHR PlIfIl> 1B-SB Locked Off TIt (1RH-40) (Both Bkrs)

Locked Off TIt 4tlUV MCG-1tl21-!::)H 1B21-SB-5B RCS ~ RHR Puflll1A-SA (1RH-1) 8krs) Locked Off TIt Locked Off TIt 1B21-SB-11A RCS ~ C to RHR PUf1ll1E~-SB Locked Off TR (1RH-39)(Both Bkrs)

Locked Off TIt 1 OP-111 Rev. 44 Page 145 of 1531 2009B NRC Exam Admin JPM SRO A2 Rev. 1

Appendix C Page 1 of 8 Form ES-C-1 Worksheet Facility: Task No.:

Task

Title:

Using survey maps determine stay JPM No.: 2009B NRC Exam times Admin JPM SRO A-3 KIA

Reference:

G.2.3.4 RO 3.2 SRO 3.7 Examinee: NRC Examiner:

Facility Evaluator: Date: _ __

Method of testing:

Simulated Performance:

Actual Performance: x Classroom X Simulator Plant 2009B NRC Exam Admin JPM SRO A3 Rev. 1

Appendix C Page 2 of 8 Form ES-C-1 Worksheet READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

  • 1ED-18 Initiating Cue: 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 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem.

The clearance and work activity is for the 'A' ED Tank Transfer Pump.

Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits. Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent - Radiation Protection approval.

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.

2009B NRC Exam Admin JPM SRO A3 Rev. 1

Appendix C Page 3 of 8 Form ES-C-1 Worksheet Task Standard: Calculation of stay times based on survey maps, two hours for Operator 1, five hours for Operator 2.

Required Materials: Survey map A4 RAB 190' North Valve MAP 2 SFD-5-S-0684 General

References:

DOS-NGGC-0004 (Rev. 10)

DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non- Progress Energy dose for the current year has been determined.

Time Critical Task: No Validation Time: 12 minutes Critical Task Justification Step 1 Must determine dose rates in order to calculate stay time Step 2 Must determine available dose to determine stay time.

Step 3 Calculation of stay time.

2009B NRC Exam Admin JPM SRO A3 Rev. 1

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION START TIME:

Evaluator Note: The order of performance does not matter IF THE APPLICANT ASKS FOR IT: Provide a copy of DOS-NGGC-0004, Rev. 10

.;' Performance Step: 1 Using Radiological Survey Record Map A4 and RAB 190' North map, determines dose rates in the area where the clearance will be applied Standard: Identifies that General Area Dose Rates are 120 mrem/hr Comment:

.;' Performance Step: 2 Determine the remaining dose for the year for each individual Standard: Operator 1: 240 mrem (2000 mrem - 1760 mrem = 240 mrem Operator 2: 600 mrem 4000 mrem -700 mrem (PE) - 2700 mrem (SL) =600 mrem Comment:

./ - Denotes Critical Steps 2009B NRC Exam Admin JPM SRO A3 Rev. 1

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION

./ Performance Step: 3 Determine stay time for each operator (based on 1st Operator reaching 2 mrem and the 2nd Operator reaching 4 mrem - for the year)

Standard: Operator 1: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 240 mrem + 120mremihr =2 hrs Operator 2: 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 600 mrem + 120 mrem/hr = 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Comment:

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

ENDOFJPM STOP TIME:

./ - Denotes Critical Steps 20098 NRC Exam Admin JPM SRO A3 Rev. 1

Appendix C Page 6 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A Using survey maps determine stay times. (DOS-NGGC-0004 Rev. 10)

DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non- Progress Energy dose for the current year has been determined.

Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

2009B NRC Exam Admin JPM SRO A3 Rev. 1

Appendix C Page 7 of 8 Form ES-C-1 JPM CUE SHEET Initial Conditions: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

  • 1ED-18 Initiating Cue: 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 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem.

The clearance and work activity is for the 'A' ED Tank Transfer Pump.

Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits: Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent - Radiation Protection approval.

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.

Name _____________________________________

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

Operator 1: _____________________ Operator 2:

2009B NRC Exam Admin JPM SRO A3 Rev. 1

Appendix C Job Performance Measure Form ES-C-1 F~, ["'). F.\ Fe:, r:~"'-'I Worksheet f~F ~i{:, l'~~~~" fl Facility: Shearon Harris Task No.: 345001 H602 Task

Title:

Classify an event JPM No.: 2009B NRC Exam Admin JPM SRO A4 KIA

Reference:

G2.4.41 RO 2.9 SRO 4.6 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.

Initial Conditions: A refueling outage has just been completed and a plant heat up is being performed lAW GP-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3.

Initiating Cue: Using the attached information sheet and the EAL Flow Path, classify the event. Mark the EAL Flow Path appropriately.

THIS IS A TIME CRITICAL JPM.

2009B NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Event classified as an Site Area Emergency (2-4-3)

Required Materials: None General

References:

PEP-110 EAL Flowpath EP-EAL (allowed reference)

Handouts: JPM Cue Sheets Pages 4 and 5 PEP-110 EAL Flowpath EP-EAL (allowed reference)

Time Critical Task: Yes Validation Time: 15 minutes Critical Step Justification Step 2 Classification of the event.

2009B NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION Evaluator Note: Start Time for this JPM begins when the individual has been briefed START TIME:

Performance Step: 1 OBTAIN EAL FLOW PATH.

Standard: Obtains EAL Flow Path. (EP-EAL is an allowed reference)

Comment:

./ - Denotes a Critical Step 2009B NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

-/ Performance Step: 2 CLASSIFY EVENT Standard: Identifies an Site Area Emergency (2-4-3),

DAMAGE TO SPENT FUEL with ANY SPENT FUEL POOL AREA RAD MON > 700 mRlHR Basis:

Damage to spent fuel in the Fuel Handling Building is assessed to determine if a single or multiple assemblies are affected.

Trigger points for the FHB area radiation monitors were calculated to provide a symptomatic indication of damage the affected assembly(s). The 700 mRlHR criteria is the dose rate expected at the monitor nearest the damaged assembly(s) based on the expected dose rate from damaging more than 1 spent fuel assembly that had recently been removed from the reactor.

CLASSIFICATION GUIDANCE:

Fuel handling accidents are analyzed as part of the HNP Licensing Basis. These accidents (as demonstrated through evaluation) are not expected to exceed Part 100 limits.

Emergency filtration units are available to mitigate the consequences of these accidents.

Comment:

STOP TIME:

Terminating Cue: Event classification stated to evaluator.

ENDOFJPM

-/ - Denotes a Critical Step 2009B NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 5 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 20098 NRC Exam Admin JPM SRO A4 - Classify an event Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

20098 NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 6 of 7 Form ES-C-1 JPM CUE SHEET Initial Conditions: A refueling outage has just been completed and a plant heat up is being performed lAW GP-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3.

Initiating Cue: Using the attached information sheet and the EAL Flow Path, classify the event. Mark the EAL Flow Path appropriately.

THIS IS A TIME CRITICAL JPM 2009B NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET CLASSIFICATION INFORMATION SHEET A refueling outage has just been completed and a plant heat up is being performed lAW GP-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3.

Current plant conditions are:

  • RCS Temp 180°F
  • RCS Pressure 345 psig
  • 'A' RHR pump is in operation Fuel handlers are performing a fuel shuffle and moving assemblies from the 'A' Fuel Pool to 'B' Fuel Pool.

An emergency landing was being attempted by an aircraft returning to RDU. The pilot has lost control and the aircraft has impacted on the west side of the Fuel Handling Building. The side of the building has suffered external damage and a fire is burning at the impact site.

The impact was so severe that a fuel assembly being moved has dropped from the Fuel Bridge Crane and ruptured. The highest Fuel Building Radiation monitor is reading 825 mr/hr.

Classify the event Name __________________________________________________

Record your classification here and return to the examiner.

EAL Classification: _________________________

2009B NRC Exam Admin JPM SRO A4 Rev. 1

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