ML101970328

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Initial Exam 2008-301 Draft Administrative JPMs
ML101970328
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 06/28/2010
From:
NRC/RGN-II
To:
Progress Energy Carolinas
References
50-261/08-301, ES-301, ES-301-1 50-261/08-301
Download: ML101970328 (44)
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Text

ES-301 Administrative Topics Outline ES-301 -1 Form ES-301-1 Draf/

Z>t-afl.

Facility: HB ROBINSON Date of Examination: 2008 NRC 200BNRC Examination Level (circle one): I SRO

[@/SRO Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note) Code*

Code*

N N G2.2.1 (3.9); 001 A4.l0 A4.10 (3.5)

Conduct of Operations Given a set of conditions and applicable references, perform a Manual Estimated Critical Condition Calculation.

M 015 AAl1.04

.04 (3.5)

Conduct of Operations Given a set of conditions, perform a Manual Quadrant Power Tilt Calculation.

. N N G2.2.12(3.7)

G2.2.12 (3.7)

Equipment Control Given a set of conditions, perform the Administrative Daily Checks to determine potentiometer settings for FCV-l 13A, Boric Acid Flow and HFC-114, FCV-113A, HFC-l 14, Primary Water Flow Auto Mode.

N G2.3.7(3.5)

G2.3.7 (3.5)

Radiation Control Given an RWP and a Survey Map, fill out a Radiation Worker RCA Card (ALARA Card).

Not selected for RO.

Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria:
  • Type (C)ontrol room

.(D)irect ( 3 for ROs; :::; for SROs & RO retakes)

(D)irect from bank (:::;

(M)odifled from bank (>

(N)ew or (M)odified (> 1)

( 1; randomly selected)

(P)revious 2 exams (:::;

(S)imulator NUREG-l 021, Revision 9 NUREG-1

ES-301 ES-301 Administrative Topics Administrative Topics Outline Outline Form Form ES-301-1 ES-301 -1 LD-L J] ;r- ~ !-./:::

Facility:

Facility: HB ROBINSON HB ROBINSON Date of Date of Examination:

Examination: 200BNRC 2008 NRC Examination Level Examination Level (circle (circle one):

one): RO~SROI RO 4 SRO Operating Test Operating Test Number:

Number:

Administrative Topic Administrative Topic Type Type Describe activity Describe to be activity to be performed performed (see Note)

(see Note) Code*

Code*

N N G2.2.1 (4.2);

G2.2.1 (4.2); 001001 A4.10 A4.10 (3.9)

(3.9)

Conduct of Operations applicable references, Given a set of conditions and applicable Manual Estimated Critical Condition perform a Manual Calculation.

Calculation.

M 015A1.04(3.7) 015 A1.04 (3.7)

Conduct of Operations Given a set of conditions, performperform a Manual Quadrant Power Tilt Calculation.

N G2.2.12(4.1)

G2.2.12 (4.1)

Equipment Control Given a set of conditions, perform the Administrative Daily Checks to determine potentiometer settings for FCV-1 1 3A, Boric Acid Flow and HFC-114, FCV-113A, HFC-1 14, Primary Water Flow Auto Mode.

N G2.3.7 (3.6)

Radiation Control Given an RWP and a Survey Map, fill out a Radiation Worker RCA Card (ALARA Card).

N N G2.4.41 (4.6); G2.4.44 (4.4)

Emergency Plan Given a set of conditions, classify the event lAW the Emergency Action Level Matrices.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type
  • Type Codes & Criteria: (C)ontrol room (D)irect from bank ( (~ 3 3 for ROs; ~ for SROs & RO retakes)

(N)ew or (M)odified from bank (> (> 1) 1)

(P)revious 22 exams exams ( (~ 1; 1; randomly selected) selected)

(S) imulator (S)imulator NUREG-1 NUREG-1 021, 021, Revision Revision 99

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301 -2 LVra)t Facility: HB ROBINSON Date of Examination: 2008 NRC 200BNRC Exam Level (circle one): RO 1 SRO(l) 1

/ SRO(I) I SRO (U) Operating Test No.:

Systems@ (8 for RO; 7 for SRO-I; Control Room Systems@ SRO-l; 2 or 3 for SRO-U, including 11 ESF)

Code*

Type Code* Safety System 1 / JPM Title Function

a. (IRPI/014): Perform Rod Control Exercise and IRPI Surveillance A, M, 5 A,M,S 1 1

OST-Ol per OST 1. (S8)

-011. (SB)

b. (ECCS/006):

(ECCSIOO6): Fill a Safety Injection Accumulator to clear the Low D, S D,S 2 Level Alarm. (S1)

(51)

c. (RCS/002): OP-i 01. (S4)

(RCSIOO2): Start a RCP per OP-101. D, L, S D,L,S 4P

d. (CSS/026): Reactor Trip/Safety Injection response with Failure of A, N, 5 A,N,S 5 Containment Spray to Actuate. (S5)
e. (AC DIST/062): Restore Control Power to ECCS Valves. (S2). A, D, 5 A,D,S 6
f. (NIS/015):

(NISIO15): Remove N-44 from service. (S6) 0, 5 D,S 7

g. (RMS/072): Respond to a Loss of Circulating Water Pump. (S7) 5, A, D, S, 8
h. (SW/076): Limit Radiation Exposure in response to a Radiation D, 5 D,S 9 alarm. (S3) (SRO-I do not perform).

Systems@ (3 for RO; 3 for SRO-I; In-Plant Systems@ SRO-l; 3 or 2 for SRO-U)

i. Control/OO1): Trip the Reactor as Inside AO. (IP2)

(Rod ControI/001): D, E, R 1 1

j. Pressure/OlO): Energize PZR Heaters from Emergency (PZR Pressure/010): D, E D,E 3 busses using EPP-21. (IP3) (1P3)
k. (EDGIO64): Manually start EDG using Air Start Solenoids. (IP1)

(EDG/064): (IPi) A, E, N, R A,E,N,R 6

@@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

    • Type Codes Criteria for RO 1 / SRO-I 1/ SRO-U (A)lternate path 4-6 / 4-6 / 2-3 4-6/4-6/2-3 (C)ontrol room (D)irectfrombank (D)irect from bank 5:9/5:8/5:4 (E)mergency or abnormal in-plant  ;?1/;?1/~::1

> 1 / 1 I 1 (L)ow-Power 1 I Shutdown  ;?1/;?1/;?1 1 / 1 / 1 (N)ew or (M)odified from bank including 1 1(A)

(A) 2/ 2/ 1

?2/?..2/?:..1 (P)revious 2 exams 5: 3/:::; 3 I 2 (randomly selected) i < 3/:::;

(R)CA ;o.:1/;,:1/;?1 1I1/1 (S)imulator NUREG-1021, Revision 9

Appendix CC Appendix Job Performance Measure Job Performance Measure Form ES-C-1 Form ES-C-i Worksheet Worksheet Facility:

Facility: HB ROBINSON HB ROBINSON Task No.:

Task No.: 01006100101 01006100101 Task

Title:

Task

Title:

Manually Calculate Manually Calculate an Estimated an Estimated JPM No.:

JPM No.: 2008 2008 NRC NRC JPMJPM A1 Al Critical Condition Critical Condition K/A

Reference:

KIA

Reference:

G2.l .25 (3.9/4.2)

G2.1.25 (3.9/4.2)

Examinee:

Examinee: NRC Examiner:

NRC Examiner:

Facility Evaluator:

Facility Evaluator: Date:

Date:

Method of testing:

Simulated Performance:

Performance: Actual Performance:

Performance: xX Classroom X Simulator ---

Plant 2008 2008 NRC NRC JPM JPM AlA1 NUREG NUREG 1021, 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Appendix C Job Performance Measure Job Performance Measure Form ES-C-1 Form ES-C-i Worksheet Worksheet READ TO READ TO THE EXAMINEE THE EXAMINEE II will will explain explain the initial conditions, the initial conditions, which which steps steps to simulate or to simulate or discuss, discuss, and and provide provide initiating initiating cues.

cues.

When you When complete the you complete the task task successfully, successfully, the objective for the objective this Job for this Performance Measure Job Performance Measure will be will be satisfied.

satisfied.

Initial Conditions:

Initial ** The plant is in Mode Mode 3 with TTAVG AVG at 547 degrees F F following a unit unit trip.

    • The trip occurred from equilibrium conditions following a 78 78 day day run run at full power conditions.
  • Critical Data Stamp initiated 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> prior to trip lists the following conditions at time of trip:

o 602 ppm Boron o Control rods at 218 steps on CB "0" D o Poweratl00%

Power at 100%RTPRTP o Burnup is at 333.01 EFPO EFPD (11668.5 MWO/MTU)

MWD/MTU)

  • Projected return to criticality is 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> from the trip, at Boron Concentration of 602 ppm.

Concentration

  • The next Criticality number is 501.
  • You have been directed to perform a Manual Estimated Critical Conditions calculation for the given conditions.

2008 2008 NRCNRC JPM JPM Al A1 NUREG NUREG 1021,1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix CC Appendix Job Performance Job Performance Measure Measure Form Form ES-C-1 ES-C-i Worksheet Worksheet Task Standard:

Task Standard: Calculate Estimated Calculate Estimated Critical Critical Condition Condition within within +/-

+1- 250 250 PCM PCM of of Reactor Reactor Engineering validated Engineering validated condition.

condition.

Required Materials:

Required Materials: Calculator Calculator GP-003, Attachment GP-003, Attachment 10.1 10.1 Applicable Plant Applicable Plant Curve Curve Book Book curves:

curves: Section Section 11,, Section Section 22 General

References:

General

References:

GP- 003, GP- NORMAL PLANT 003, NORMAL PLANT STARTUP STARTUP FROM FROM HOTHOT SHUTDOWN SHUTDOWN TO TO CRITICAL CRITICAL Station Curve Station Curve Book Book Handouts:

Handouts: Attachment 10.1 GP-003, Attachment 10.1 Applicable Plant Plant Curve Book Book curves: Section 1, 1, Section Section 22 Initiating Cue:

Initiating Perform a Manual Estimated Critical Condition Calculation lAW GP-003, Attachment 10.1 for a projected Critical condition time of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> from trip.

Time Critical Task:

Time NO Validation Time:

Validation 75 minutes 2008 2008 NRCNRCJPM JPM Al A1 NUREG NUREG 1021, 1021, Revision Revision 9,9, Supplement Supplement 11

Appendix C Appendix C Page 44 of Page of 15 15 Form Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION (Denote Critical (Denote Critical Steps Steps with with an asterisk) an asterisk)

Start Start Time:

Time: _ _ __

Performance Step:

Performance Step: 11 Enter Attachment Enter Attachment 10.1 pre-trip data 10.1 pre-trip data (Steps (Steps 1.1, 1.1, 1.2, 1.2, 1.3) 1.3)

Standard:

Standard: Enters Criticality Enters Criticality number number as as 501.

501.

Correctly enters CB "0" D at 218 steps (Step 1.1).1 .1).

Power Level at 100% (Step 1.2)

Power 1 .2)

Boron Concentration Boron Concentration at at 602 602 (Step (Step 1.3.1) 1 .3.1)

Number of days since last Critical Data Stamp and shutdown as O.

0. (Step 1.3.2)

Examiners Note:

Examiner's Comment:

Performance Step: 2 Transitions to Step 1.3.6 lAW Step 1.3.3, Records Current Critical Boron Concentration.

Standard: Enters 602 ppm in Step 1.3.6.1 .3.6.

Examiners Examiner's Note:

Comment:

2008 2008 NRC NRC JPM JPM AlA1 NUREG 1021, NUREG 1021, Revision Revision 9,9, Supplement Supplement 11

Appendix C Appendix C Page 55 of Page of 15 15 Form Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION Performance Step:

Performance Step: 33 Using Integral Using Integral Boron Boron Worth Worth Curve Curve 1.13, 1.13, enter enter Integral Integral Boron Boron Worth.

Worth.

Standard:

Standard: Using Integral Using Integral Boron Boron Worth Worth Curve Curve 1.13, 1 .13, enters enters Integral Integral Boron Boron Worth asas 5166 5166 pcm in Step 1.4.

pcm in Step 1.4.

Examiners Note:

Examiner's Interpolated data: BOl Interpolated =

BOL Value = 5500, EOl EOL value 4500, .66%

interpolation BOl-EOl, interpolation BOL-EOL, 4500 ++ .66%.66% of delta = = 4500 + 666 =

+ 666 =

5166.

Acceptable ranges/tolerances for curves are NOT given for this JPM. Final PCM change has an acceptable range of +/- +1-250 pcm, which includes all individual curve and math tolerances.

Comment:

Performance Step: 4 Using Xenon Worth Curve 2.1, enter Xenon Worth at time of trip.

USing Standard: Using Xenon Worth Curve 2.1, enters Xenon Worth at time of trip as 2720 pcm, in Step 1.5.

Examiners Examiner's Note: Interpolated data: BOL =

BOl value = 2560, EOL EOl value =2800.

=

EOl-BOl, == 240 x .66 == 160 Interpolating EOL-BOL, 160 ++ 2560 == 2720.

Comment:

2008 NRC 2008 NRC JPM JPM Al A1 NUREG 1021, Revision NUREG 1021, Revision 9,9, Supplement Supplement 11

Appendix C Appendix C Page 66 of Page of 15 15 Form Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION Performance Step:

Performance Step: 55 Using Power Using Power Defect Defect CUNe Curve 1.3, 1.3, enter enter Power Power Defect Defect atat time time of of trip.

trip.

Standard: Using Power Using Power Defect Defect CUNe Curve 1.3, 1 .3, enters Power Power Defect Defect at time of pcm, in trip as 2115 pcm, in Step Step 1.6.

1 .6.

Examiners Note:

Examiner's Note: Power Defect Curves 1.3B (MOL) and 1.3C (EOl)

Power (EOL) should be used to interpolate power defect for 100% power, Boron concentration of 602 ppm. Interpolated data: MOL = = 1950 pcm, EOlEOL == 2450 pcm. Interpolate EOl EOL - MOL == 500 pcm x

.33 = (MOL-EOL delta). 1950 + 165 == 2115 pcm.

= 165 (MOl-EOl Comment:

Performance Step: 6 Using Samarium Worth Curves 2.4A, 2.48, 2.4B, 2.5, enter Samarium Worth at time of trip.

Standard: Using Samarium Worth Curves 2.4A, 2.4B, 2.48, 2.5, enters Samarium Worth at time of trip as 915 pcm in Step 1.7.

Examiners Note:

Examiner's Per Note #2, should use Curves 2.4A and 2.48 2.4B for Equilibrium Samarium conditions at time of trip.

Interpolated data: BOL BOl from Curve 2.4A == 790, EOL EOl from Curve 2.4B == 980. EOL EOl - BOL BOl == 190190 x .66 =125. 790 ++ 125125 ==

915.

Comment:

2008 2008 NRC NRC JPM JPM Al A1 NUREG NUREG 1021, 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Appendix C Page 77 of Page of 15 15 Form Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION Performance Step:

Performance Step: 77 Using Inserted Using Inserted Rod Rod Worth Worth curve curve 1.6, 1 .6, 1.8 enter Inserted 1.8 enter Inserted Rod Rod Worth at Worth at time of trip.

time of trip.

Standard: Using Inserted Using Inserted Rod Rod Worth curve 1.6, 1.6, 1.8 enters Inserted i .8 enters Inserted Rod Rod Worth at Worth at time time of of trip trip as as 00 pcm in Step pcm in Step 1.8.

1.8.

Examiners Note:

Examiner's Should use Curve 1.6 per Note #3.

Comment:

Performance Step: 8 Enter Projected Boron Concentration, temperature, and time since shutdown.

Standard: Enters Projected Boron Concentration and temperature as 602 ppm, 547 deg. F., 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> in Steps 2.1, 2.2, 2.3.

Examiners Note:

Examiner's Comment:

2008 NRC 2008 NRC JPM JPM Al A1 NUREG NUREG 1021,1021, Revision Revision 9,9, Supplement Supplement 11

Appendix CC Appendix Page 88 of Page of 15 15 Form Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION Performance Step:

Performance Step: 99 Enter Integral Enter Integral Boron Boron Worth.

Worth.

Standard:

Standard: Enters Integral Enters Integral Boron Boron Worth Worth as 5166 pcm as 5166 pcm inin Step Step 2.4.

2.4.

Examiners Note:

Examiner's Note: Should enter Should enter same same value value as as Step Step 1.4, 1.4, above.

above.

Comment:

Comment:

Performance Step: 10 Enter Projected Xenon Worth at Startup.

Standard:

Standard: Enters Projected Xenon Worth at Startup as 3928 pcm in Step 2.5.

Examiners Note:

Examiner's Interpolated data from 80l BOL Curve 2.3A (3400 pcm @ 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />) and EOlEOL Curve 2.3B 2.38 (4200 pcm @ 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />).

Interpolating 4200 - 3400 == 800 x .66 == 528. 3400 ++ 528 ==

3928 pcm.

Comment:

2008 2008 NRC NRC JPM JPM Al A1 NUREG NUREG 1021, 1021, Revision Revision 9,9, Supplement Supplement 11

Appendix C Page 9 of 15 Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION 11 Performance Step: 11 Enter Samarium Worth at Startup.

Standard: Enters Samarium Worth at Startup as 1000 pcm in Step 2.6.

Examiners Note:

Examiner's Interpolated data: BOl =

BOL Curve 2.4A = 865, EOl EOL Curve 2.4.B =

=

=

£6 = 135 +

1070. 205 x .66 =

+ 865 = 1000 pcm.

Comment:

Performance Step: 12 Enter Samarium change before equilibrium.

Standard: Enters Samarium change before equilibrium as a 0 pcm.

Examiner Cue:

Comment:

2008 NRC JPM Al A1 NUREG 1021, 1021, Revision 9, Supplement 11

Appendix C Appendix C Page 10 Page 10 of of 15 15 Form Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION Performance Step:

Performance Step: 13 13 Enter determined values, Enter determined values, perform perform calculation calculation per per Step Step 3.2 3.2 to to determine calculated determine calculated change change inin Reactivity.

Reactivity.

Standard:

Standard: Enter determined Enter determined values, values, perform perform calculation calculation per per Step Step 3.2 3.2 to to determine calculated determine calculated change change inin Reactivity.

Reactivity. Calculate Calculate Change Change inin Reactivity == 822 pcm +/-

Reactivity +1- 250 pcm (572-1072 (572-i 072 pcm).

Examiners Note:

Examiner's Note:

Comment:

  • performance Step: 14
  • Performance Calculate and enter New Controlling Rod Worth per Step 4.1.

Standard: Step 4.1: 0 pcm (from Step 1.8) + + 822 pcm (from Step 3.2.5) =

=

822 pcm. (acceptable range = = 572 - 1072 pcm)

Examiner's Examiners Note: Reactor Engineer's AT Step 4.2, inform candidate: "Reactor Engineers calculation is the same as yours.

yours."

Comment:

2008 NRC JPM 2008 NRC JPM Al A1 NUREG 1021, NUREG 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Appendix C Page 11 Page 1 1 of of 15 15 Form ES-C-1 Form ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION

  • performance Step:
  • Performance Step: 15 15 Determine new Determine new Critical Critical Rod Rod Position Position associated associated withwith the the integral integral worth in worth Step 4.1 in Step 4.1 using using Curve Curve 11 .8..8.

Standard:

Standard: Determines new Determines new Critical Critical Rod Rod Position Position associated associated with with the the integral integral worth wort h'In Step 4.1 in Step usina C 4.1 using Curve urve 1.8.

1 .8. as as listed listed in in the the table table below.

below.

Candidate value Candidate value from stepstep 4.2.

4.2. Allowable Allowable Tolerance Tolerance Band.Band.

572 - 672 pcm

> 572 2=. 95 steps 168 168 steps 2=. 772 pcm

> 672 - 772 pcm 80 80 steps 155 155 steps

> 772 - 872 pcm 2=. 70 70 steps 128 128 steps 2=. 872 - 972 pcm 58 steps 90 steps

> 972 - 1072 pcm 2=. 50 steps 82 steps Examiners Note:

Examiner's Tolerance Bands vary by pcm calculated and are calculated Tolerance based on +/- /2 of the range between the EOl

+/-% EOL and MOL curves on Curve 1.8 for the pcm band.

Comment:

Performance Step: 16 Enter Estimated Critical Condition data in Step 5.1 5.1..

Standard: Enters Estimated Critical Condition data in Step 5.1 (77 steps on CB D, "0", 602 ppm boron, 547 °F OF TAVG).

TAVG ).

Examiners Examiner's Note:

Comment:

2008 2008 NRC NRC JPM JPM Al A1 NUREG 1021, NUREG 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Appendix C Page 12 Page 12 of of 15 15 Form Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION Performance Performance Step:

Step: 17 17 Answers questions Answers questions in in Steps Steps 5.2 5.2 and and 5.3.

5.3. Standard

in Steps Answers questions in Steps 5.2 and and 5.3 YES.

5.3 as "YES".

Examiners Note:

Examiner's Comment:

2008 NRC 2008 NRC JPM JPM Al A1 NUREG 1021, Revision NUREG 1021, Revision 9, 9, Supplement Supplement 11

Appendix C Page 13 of 15 ES-C-i Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 18 Calculate the tolerance band of plus OR minus 500 pcm from the 6.1 .2.

6.1 .1 and 6.1.2.

ECP in Steps 6.1.1 Standard: Calculates the tolerance band of plus OR minus 500 pcm from the ECP as 5 steps to 200 steps on Bank "D".D.

Examiners Note:

Examiner's Comment:

Performance Step: 19 Record ECP completion time.

Standard: Candidate records the present time that the ECP calculation was completed.

Examiner's Examiners Note: To allow use of this ECP, criticality must be achieved within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the completion time recorded. This will ensure compliance with ITS SR 3.1.6.1.

Comment:

END OF OFTASK TASK Terminating Cue: GP-003, Attachment 10.1 completed.

STOP TIME:

2008 NRC NRC JPM Al A1 NUREG 1021, Revision 9, Supplement 11 NUREG 1021,

Appendix C Appendix C Page 14 Page of 15 14 of 15 Form Form ES-C-1 ES-C-i VERIFICATION OF VERIFICATION OF COMPLETION COMPLETION Job Performance Job Performance Measure Measure No.:

No.: NRC JPM 2008 NRC 2008 JPM AAl1 Examinees Name:

Examinee's Name:

Date Performed:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature:

Examiners Date:

2008 2008 NRC JPM Al NRC JPM A1 NUREG NUREG 1021, 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Appendix C Page 15 Page 15 of of 15 15 Form ES-C-1 Form ES-C-i JPM CUE JPM CUE SHEET SHEET Initial Conditions:

Initial Conditions: ** plant is The plant is in in Mode Mode 33 with TTAVG AVG at 547 degrees at 547 degrees FF following following aa unit unit trip.

  • The trip occurred from equilibrium conditions following a 78 day run at full power conditions.
  • Critical Data Stamp initiated 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> prior to trip lists the following conditions at time of trip:

o 602 ppm Boron o Control rods at 218 steps on CB "0" D Poweratio0%RTP o Power at 100% RTP o Burnup is at 333.01 EFPD (11668.5 MWD/MTU)

  • Projected return to criticality is 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> from the trip, at Boron Concentration of 602 ppm.
  • The next Criticality number is 501.
  • You have been directed to perform a Manual Estimated Critical Conditions calculation for the given conditions.

Initiating Cue: Perform a Manual Estimated Critical Condition Calculation lAW GP-03, Attachment 10.1 for a projected Critical Condition time of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> from trip.

2008 2008 NRCNRC JPM JPM Al A1 NUREG NUREG 1021,1021, Revision 9, 9, Supplement Supplement 11

Appendix C Job Performance Measure Form ES-C-1 ESC-1 Worksheet Facility: HB ROBINSON Task No.: 01015100402 Task

Title:

Perform a Manual QPTR Calculation JPM No.: 2008 NRC JPM A2 K/A

Reference:

KIA 015 Al .04 (3.5/3.7)

A 1.04 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x X

Classroom -~-

X Simulator - - - Plant READ TO THE EXAMINEE EXAM INEE II 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 is at 60% RTP.
  • Power Range Nuclear Instrument PRNI-42 is inoperable due to a failed power supply.
  • APP-005-F4, PR LOWER CH HI FLUX DEV/AUTO DEFEAT is illuminated.
  • Detector Currents are as follows:

o N41: Upper - 63 Normalizing - 123 o N41: Lower - 55 Normalizing - 120 o N43: Upper - 50 Normalizing - 104 o N43: Lower -4545 Normalizing - 99 o N44: Upper - 48 Normalizing - 97 o N44: Lower -4545 Normalizing -95 95 Task Standard: Perform a MANUAL QPTR calculation lAW FMP-007, QUADRANT POWER TILT with an accuracy of +/- +1- 0.5%.

Required Materials: Calculator FMP-007, QUADRANT POWER TILT 2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1 1

Appendix C Appendix C Job Job Performance Performance Measure Measure Form Form ES-C-1 ES-C-i Worksheet Worksheet General

References:

General

References:

FMP-007, QUADRANT FMP-007, QUADRANT POWER POWER TILT, TILT, Section Section 8.2.4, 8.2.4, Manual Manual QPTR QPTR Calculations.

Calculations.

FMP-007 Attachment FMP-007 Attachment 10.2, 10.2, MANUAL MANUAL QPTR QPTR CALCULATIONS.

CALCULATIONS.

Handouts:

Handouts: FMP-007, QUADRANT FMP-007, QUADRANT POWER POWER TILT.

Initiating Cue:

Initiating Cue: Perform a MANUAL Perform MANUAL QPTR calculation lAW lAW FMP-007, FMP-007, QUADRANT POWER TILT, section 8.2.4.

POWER Critical Task:

Time Critical NO NO Validation Time: 15 minutes 2008 2008 NRCNRC JPM JPM A2 A2 NUREG 1021, NUREG 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Appendix C Performance Measure Job Performance Job Measure Form Form ES-C-i ES-C-1 Worksheet Worksheet INITIAL CONDITIONS:

INITIAL CONDITIONS: ** The The plant is at plant is 60% RTP.

at 60% RTP.

  • Power Range Nuclear Instrument PRNI-42 Nuclear Instrument PRNI-42 is due to aa is inoperable due tailed power supply.

failed power supply.

  • APP-005-F4, PR LOWER CH HI FLUX DEV/AUTO DEV/AUTO DEFEAT is is illuminated.
  • FMP-007, Attachment 10.2 Manual QPTR Calculations has been 10.2 Manual Normalizing Detector initiated, with Indicated Detector Currents and Normalizing Detector Currents recorded.

INITIATING CUE: Complete Attachment iO.2 10.2 lAW FMP-007, QUADRANT POWER TILT.

T LT.

2008 2008 NRC JPM A2 NRC JPM NUREG 1021, Revision NUREG 1021, Revision 9, Supplement 11 9, Supplement

Appendix C Appendix C Page 44 of Page of 10 10 Form ES-C-1 Form ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION (Denote Critical (Denote Critical Steps Steps with an asterisk)

Start Time: _ _ __

Performance Step: 11 Enter each Indicated and Normalizing Detector Current in Attachment 10.2 Standard: Enters detector currents as given in initiating cue in correct boxes of Attachment 10.2.

Examiners Note:

Examiner's Comment:

2008 2008 NRC NRC JPM JPM A2 A2 NUREG NUREG 1021, 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C 10 Page 5 of 10 ES-C-i Form ES-C-1 PERFORMANCE INFORMATION PERFORMANCE INFORMATION Performance Step: 2 Divide each Indicated Detector Current by its Indicated Detector its corresponding Current and record the result as the Normalizing Detector Current Normalized Detector Ratio on Attachment 10.2. 10.2.

Standard: Divides each Indicated Detector Current by its corresponding Normalizing Detector Current and records the result as the Normalized Detector Ratio on Attachment 10.2:

Upper N41 = 0.51 22

= 0.5122 Lower N41 == 0.4583 Upper N42 == 0 Lower N42 = = 0 Upper N43 = = 0.4808 Lower N43 = = 0.4545 N44 0.4948 Upper N44'= Lower N44 = = 0.4737 Examiners Note:

Examiner's Calculated values rounded to 4th decimal place.

Cornment:

Comment:

Performance Step: 3 Average the Upper Normalized Detector Ratios and record the result as the Average Normalized Detector Ratio in the Upper column on Attachment 10.2.

Average the Lower Normalized Detector Ratios and records the result as the Average Normalized Detector Ratio in the Lower column on Attachment 10.2.

Standard: Upper Average Normalized Detector Ratio = = 0.4959 Lower Average Normalized Detector Ratio = = 0.4621 th 4

Examiners Note:

Examiner's Calculated values rounded to 4th decimal place.

Candidate should NOT include data from the failed NI Channel.

Comment:

2008 NRC JPM A2 NUREG 1021, 1021, Revision 9, Supplement 11

Appendix CC Page 66 of Page of 10 10 Form ES-C-1 Form ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION

  • performance Step:
  • Performance Step: 44 Determine the maximum Determine maximum Upper Upper Normalized Normalized Detector Detector Ratio Ratio and and divide itit by divide by the Average Upper Normalized Detector Ratio from Performance Step 2 and record the resulting Upper QPTR on Attachment 10.2.102.

Standard: Determines the maximum Upper Normalized Detector Ratio and divides it by the Average Upper Normalized Detector Ratio from Performance Step 2 and records the resulting Upper QPTR on Attachment 10.2.

Upper QPTR = 0.5122 / 0.4959 =

= 0.5122/0.4959 = 1.0329 th 4

Examiners Note:

Examiner's Calculated values rounded to 4th decimal place.

Comment:

  • performance Step: 5
  • Performance Determine the maximum Lower Normalized Detector Ratio and divide it by the Average Lower Normalized Detector Ratio and record the resulting Lower QPTR on Attachment 10.2.

Standard: Determines the maximum Lower Normalized Detector Ratio and divides it by the Average Lower Normalized Detector Ratio and records the resulting Lower QPTR on Attachment 10.2. 10.2.

Lower QPTR == 0.4737/0.4621 = 1.0251 0.4737 /0.4621 = 1.0251 Examiners Examiner's Note: Calculated values rounded to 4 th 4th decimal place.

Comment:

2008 2008 NRC NRC JPM JPM A2 A2 NUREG NUREG 1021, 1021, Revision 9, Supplement Revision 9, Supplement 11

Appendix C Page 7 of 10 ES-C-i Form ES-C-1 PERFORMANCE INFORMATION

  • pel.formance Step: 6
  • Performance Record the larger of the Upper QPTR or the Lower QPTR as the Maximum QPTR on Attachment 10.2 10.2 along with the reactor power and any comments.

Standard: Records the larger of the Upper QPTR or the Lower QPTR as the Maximum QPTR on Attachment 10.2 along with the reactor power and any comments.

Records the Maximum QPTR as 1.0329, Power Level as 60%.

Examiners Note:

Examiner's Correct Calculated Maximum QPTR is 1.0329 Acceptable range is +/-+1- 0.5% (1.0277 to 1.0380)

Comment:

Performance Step: 7 Enter appropriate comments regarding the Manual QPTR Calculation.

Calcu lation.

Standard: Enters comment that the Calculated Maximum QPTR exceeds allowable Tech Spec limit of S 1.02 or enters 90.4% as Reactor

< 1.02 Power limit.

Examiner's Note:

Examiners Calculated values rounded to 4k 4th decimal place.

Comment:

END OF TASK Terminating Cue: Manual QPTR has been completed.

STOP TIME:

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 11 NUREG 1021,

Appendix C Page 8 of 10 Form ES-C-1 ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2008 NRC JPM A2 Examinees Name:

Examinee's Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Examiner's Signature: Date:

2008 NRC NRC JPM JPM A2 NUREG NUREG 1021, 1021, Revision 9, 9, Supplement Supplement 11

Appendix Appendix C C Job Job Performance Performance Measure Measure Form Form ES-C-1 ES-C..1 Worksheet Worksheet Facility:

Facility: HB ROBINSON HB ROBINSON Task Task No.:

No.:

Task

Title:

Task

Title:

Determine IfIf Required Determine Required Shift Shift Manning Manning Is Is JPM JPM No.:

No.: 2008 2008 NRC NRC ADM SROSRO bb Met.

K/A

Reference:

KIA 2.1.4 Examinee: NRC Examiner:

Facility Evaluator: Date:

testincj:

Method of testing:

Simulated Performance: Actual Performance: xX Classroom X Simulator - - - Plant READ TO THE EXAMINEE EXAM INEE II 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: You are the CRSS.

Unit 2 is operating at 100% RTP.

The following operators are available at the beginning of the shift:

(q

(~ =

= PRESENT)

Qualifications and/or License held Name SSO CRSS RO AO FPAO WCC WCCSRO SRO STA Auten q~

Bailes ~

Blair ~

Brown ~

Ellis ~

G rant Grant Harbin Harbin ~

Hinds ~

Horton Horton 1~

Hunt Hunt Task Task Standard:

Standard: Determine that that proper proper shift shift manning manning is is NOT NOT met.

met.

Required Materials:

Materials: OMM-001-2, SHIFTSHIFT ROUTINES AND AND OPERATING OPERATING PRACTICES.

PRACTICES.

2008 2008 NRC NRC ADM ADM SRO SRO bb NUREG NUREG 1021, 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Appendix C Job Job Performance Performance Measure Measure Form Form ES-C-1 ES-C1 Worksheet Worksheet General

References:

General

References:

OMM-O01-2, SHIFT OMM-001-2, SHIFT ROUTINES ROUTINES ANDAND OPERATING OPERATING PRACTICES.

PRACTICES.

Initiating Cue:

Initiating Cue: Determine whether Determine whether the the shift shift complement complement requirements requirements are are met.

met.

Time Critical Time Critical Task:

Task: NO NO Validation Time:

Validation 10 minutes 10 minutes 2008 2008 NRC NRC ADM ADM SROSRO bb NUREG 1021, NUREG 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Appendix C Page of 66 Page 33 of Form Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION Examiner Note:

Examiner Note: The The required required reference reference for for this this JPM JPM is is OMM-001-2, OMM-OO1-2, Section Section 8.1.3.

8.1.3.

    • Performance Step: 11 Performance Determine whether the MIMIMUM Determine MIMIMUM shift shift complement is is met met Standard:

Standard: Candidate determines Candidate determines that that the the shift complement is is one individual individual less than required.

Examiner Note:

Examiner Note:

Comment:

    • Performance Step: 2 Determine what additional resources, by qualification, are required.

Standard: Candidate determines that the additional individual needed can be an SCO, CO or AO as specified in OMM-00i OMM-001-2,-2, Section 81 .3.4.a.

8.1.3.4.a.

Examiners Examiner's Note:

Examiners Examiner's Cue:

Comment:

2008 NRC 2008 NRC ADM ADM SRO SRO bb NUREG NUREG 1021,1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Appendix C Page 44 of Page of 66 Form Form ES-C-1 ES-C-i PERFORMANCE INFORMATION PERFORMANCE INFORMATION

    • Performance Step:

Performance Step: 33 Candidate Question Candidate Question - What What allowances allowances areare provided provided for for the the shift shift to be to be one one less less than than the the minimum minimum requirement?

requirement?

Standard:

Standard: The shift The shift complement complement may may be be one one less less than than the the minimum minimum requirement for requirement for aa period period NOT NOT to to exceed exceed 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> hours in in order order toto accommodate unexpected absence of on-duty on-duty shift members provided immediate action is taken to to restore the shift complement to within the minimum requirements.

provision does NOT This provision NOT permit permit any member position any shift member position to be be unmanned upon unmanned upon shift change change due due to an oncoming oncoming shift member member being late or absent.

Examiners Note:

Examiner's OMM-OO1-2, Section 8.1.2.1 is reference to the question.

OMM-001-2, Examiners Cue:

Examiner's Comment:

Termination: When the minimum shift manning has been determined and the question responded to.

STOP TIME:

2008 2008 NRC NRC ADM ADM SRO SRO bb NUREG NUREG 1021, 1021, Revision 9, Supplement Revision 9, Supplement 11

Appendix C Appendix C Page 55 of Page of 66 Form Form ES-C-1 ES-C-i VERIFICATION OF VERIFICATION OF COMPLETION COMPLETION Job Performance Job Performance Measure Measure No.:

No.: 2008 NRC 2008 NRC ADM ADM SRO SRO bb Examinees Name:

Examinee's Name:

Examiners Name:

Examiner's Name:

Date Performed:

Date Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Examiner's Signature: Date:

2008 2008 NRC NRC ADM ADM SROb SRO b NUREG NUREG 1021, 1021, Revision 9, Supplement Revision 9, Supplement i1

Appendix C Appendix C Page 66 of Page of 66 Form Form ES-C-1 ES-C-i JPM CUE JPM CUE SHEET SHEET INITIAL CONDITIONS:

INITIAL CONDITIONS: You are You are the the CRSS.

CRSS.

Unit 22 isis operating Unit operating at at 100%

100% RTP.RTP.

The following The following operators operators areare available available at at the the beginning beginning ofof the the shift:

shift:

(J == PRESENT)

(..j PRESENT)

Qualifications License held Qualifications and/or License held Name Name SSO SSO CRSS RO RO AO FPAO FPAO WCCSRO WCC SRO STA STA Auten ..jq Bailes ..jq Blair ..jq Brown ..j Ellis ..jq Grant Harbin ..j Hinds ..jq Horton q

..j Hunt INITIATING CUE: Determine whether the shift complement requirements are met.

2008 2008 NRC NRC ADM ADM SRO SRO bb NUREG 1021, NUREG 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Job Performance Measure ES-C-i Form ES-C-1 Worksheet Facility:

Facility: ROBINSON HB ROBINSON Task No.:

Task

Title:

Evaluate the Radiological conditions JPM No.: 2008 NRC JPM A3 for two situations below, and answer Questions #1 and #2 K/A

Reference:

KIA 2.3.12 (3.2/3.7)

Examinee: NRC Examiner:

Facility Evaluator: Date:

testinci:

Method of testing:

Simulated Performance: Actual Performance: xX Classroom X Simulator ---

Plant READ TO THE EXAMINEE II 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):

  • An accident has resulted in the declaration of a Site Area Emergency (SAE).
  • There is no release in progress, but fuel damage has resulted in increased radiation levels in the RCA.
  • The operating crew/TSC has determined it is necessary to re- re position two manual valves in a 17 Rlhr R/hr field to ensure continued operation of available ECCS components.
  • The Radiological Control Director has authorized an annual dose extension of up to the Repair "Repair and Re-entry Limit Limit" for each of the two operators who will operate the valves.
  • The work plan specifies that both operators must enter, work, and leave the area at the same time.
  • Operator A has 31 mRem this quarter and 174 mRem for the year.
  • Operator BB has 75 mRem this quarter and 203 mRem for the year.

Considering only the radiation levels in the area of work, what is the maximum stay time?

2008 NRC JPM A3 NUREG 1021, Revision 9, Supplement 11 NUREG 1021,

Appendix C Job Performance Measure Form ES-C-1 ES-C-i Worksheet Initial Conditions (8):

Initial (B): ** A manual isolation valve in the Excess Letdown HX discharge Excess Letdown line was closed for maintenance.

    • The valve was re-opened by an an AO received 22 mRem AD who received mRem while doing so.

What is the acceptable method for performing verification of position on this valve?

Task Standard: Correctly answer the questions associated with the two situations.

Required Materials: Calculator General

References:

None Initiating Cue: Answer the questions associated with the two situations.

Time Critical Task: NO Validation Time: 12 min.

mm.

2008 NRC JPM A3 NUREG 1021, 1021, Revision 9, Supplement 11

Appendix C Page 3 of 5 ES-C-i Form ES-C-1 VERIFICATION VERI COMPLETION FICATION OF COMPLETION Start Time: _ __

  • Performance Step: 11 Answer Condition "A": A:
    • Repair and re-entry Limit is 10 10 REM.
  • Most limiting person is Operator "8" B
  • Operator "8":

B: 10,000 mRem - 203 mRem == 9797 mRem left for the year.

mRem)(i hour/17,000

  • (9797 mRem)(1 hour/i 7,000 mRem) = = (.576 hrs.)(60 mins/hour) == 34.577 minutes.

Standard: Calculates a stay time of 33.0 -34.6 minutes.

Examiner Note:

Comment:

    • Performance Step: 2 Answer Condition "8": B:

Answers that FUNCTIONAL VERIFICATION is the acceptable method for verifying position. (Also acceptable; concludes that verifying position via flow verification, temperature monitor, or tank level change.)

Standard:

Examiner Note:

Comment: Per OPS-NGGC-1 OPS-NGGC-1303, 303, 10 10 mRem is considered to be excessive for INDEPENDENT/CONCURRENT VERIFICATION.

FUNCTIONAL VERIFICATION is the acceptable alternative. In this case it would involve verifying flow in the line via a flow meter, temperature monitor, tank level change or a combination thereof.

ENDOFTASK END OF TASK Terminating Cue: Questions for conditions A "8" have been answered.

"A" and B Stop time: _ __

2008 NRC JPM JPM A3 NUREG NUREG 1021, 1021, Revision 9, 9, Supplement Supplement 11

Appendix C C Page 4 of Page of 55 Form ES-C-1 Form ES-C-i VERIFICATION OF VERIFICATION OF COMPLETION COMPLETION Performance Measure Job Performance Measure No.:

No.: 2008 NRC NRC JPM JPM A3 Examinees Name:

Examinee's Examiners Name:

Examiner's Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Examiner's Signature: Date:

2008 2008 NRC NRC JPM JPM A3 A3 NUREG NUREG 1021, 1021, Revision Revision 9, 9, Supplement Supplement 11

Appendix C Page 5 of 5 ES-C-i Form ES-C-1 JPM CUE SHEET Initial Conditions (A):

Initial (A): ** An accident has resulted in the declaration of a Site Area Emergency (SA(SAE)

E)

  • There is no release in progress, but fuel damage has resulted in increased radiation levels in the RCA.
  • The operating crewfTSC has determined it is necessary to re- re position two manual valves in a 17 R/hr field to ensure continued operation of available ECCS components.
  • The Radiological Control Director has authorized an annual dose Repair and Re-entry Limit" extension of up to the "Repair Limit for each of the two operators who will operate the valves.
  • The work plan specifies that both operators must enter, work, and leave the area at the same time.
  • Operator A has 31 mRem this quarter and 174 mRem for the year.
  • Operator 8 B has 75 mRem this quarter and 203 mRem for the year.

Considering only the radiation levels in the area of work, what is the maximum stay time?

(B):

Initial Conditions (8): ** A manual isolation valve in the excess Letdown HX discharge line was closed for maintenance.

  • The valve was re-opened by an AD AO who received 22m 22mRem Rem while doing so.

What is the acceptable method for performing verification of position on this valve?

2008 NRC JPMJPM A3 NUREG 1021, Revision 9, Supplement 11 NUREG 1021,

Appendix C Job Performance Measure Form ES-C-1 ES-C-i Worksheet Facility:

Facility: HB ROBINSON Task No.: 02344100403 Task

Title:

Declare an Emergency Event Declare No.:

JPM No.: 2008 NRC JPM A5 K/A

Reference:

KIA G2.4.41 (2.9/4.6)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: xX Classroom -~-

X Simulator _ _ _ Plant EXAM INEE READ TO THE EXAMINEE II 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.

IInitial nitial Conditions:

  • The plant was operating at 100% RTP with a CV Pressure Relief in progress when a Large Break LOCA occurred.
  • PATH-i.

The crew is progressing through PATH-1.

  • R-32A, CV High Range Monitor, is reading 6.4 Rem/hr.
  • Vi 2-10 and V12-ii CV Pressure Relief Valves V12-10 V12-11 did not close.
  • Core Exit thermocouples currently read 685 degrees F and are slowly trending down.
  • Reactor Engineering has reported that NO substantial core damage has occurred.
  • Full Range RVLIS RVLlS is reading 44% and is stable.
  • Weather conditions: Wind direction from 100 100 degrees, Wind Speed is 3 MPH, Stability Class is D, 0, Precipitation is Zero.
  • You are the SSO.

Task Standard: Identifies event as a SITE AREA EMERGENCY, per FS ES 1.1.

1.1.

Required Materials: EPCLA-Oi, EPCLA-01, EMERGENCY CONTROL, Revision 23 EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices 2008 NRC NRC JPM JPM A5 AS NUREG NUREG 1021, 1021, Revision 9, 9, Supplement 11

Appendix C Appendix C Job Performance Job Performance Measure Measure Form Form ES-C-1 ES-C-i Worksheet Worksheet General

References:

General

References:

EPCLA-O1, EMERGENCY EPCLA-01, EMERGENCY CONTROL, CONTROL, Revision Revision 23 23 EPCLA-04, EMERGENCY EPCLA-04, EMERGENCY ACTION ACTION LEVEL LEVEL TECHNICAL TECHNICAL BASES BASES DOCUMENT DOCUMENT EAL Matrices EAL Matrices Handouts:

Handouts: EPCLA-Oi, EMERGENCY EPCLA-01, EMERGENCY CONTROL, CONTROL, Revision Revision 23 23 EPCLA-04, EMERGENCY EPCLA-04, EMERGENCY ACTION LEVEL LEVEL TECHNICAL TECHNICAL BASES BASES DOCUMENT DOCUMENT EAL Matrices Initiating Cue:

Initiating Classify the event lAW the EAL Classify EAL matrices.

matrices. Refer Refer to EPCLA-01 EPCLA-01 for guidance on the EAL classification. Provide the selected classification to the Examiner within 15 minutes.

Time Critical Task: 15 minute time critical task)

YES (Emergency classification is a 15 Validation Time: 12 minutes 2008 NRC 2008 NRC JPM JPM A5 A5 NUREG 1021, Revision NUREG 1021, Revision 9,9, Supplement Supplement 11

Appendix C Page 3 of 7 Page Form ES-C-1 Form ES-C-i PERFORMANCE INFORMATION an asterisk)

(Denote Critical Steps with an START TIME: _ _ __ CRITICAL TASK START TIME: _ _ __

Performance Step: 11 Confirms that an off-normal condition exists.

Standard: Candidate concludes that an off-normal condition is observed and obtains a copy of the EAL matrices.

Examiners Note:

Examiner's Provide the candidate with a copy of the EAL matrices.

Comment:

Performance Step: 2 Refers to EPCLA-01, EPCLA-O1, EMERGENCY CONTROL.

Standard: Candidate obtains a copy of EPCLA-01, EPCLA-Oi, EMERGENCY CONTROL.

Examiners Note:

Examiner's EPCLA-Oi.

Provide the candidate with a copy of EPCLA-01.

Comment:

2008 NRC JPM A5 AS NUREG 1021, Revision 9, Supplement i1 NUREG 102i,

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

    • Performance Step: 3 EPCLA-Oi (Step 8.3.1).

Evaluate ALL CONDITIONS Matrix per EPCLA-01 Standard: Candidate reviews and evaluates ALL CONDITIONS Matrix.

Examiners Note:

Examiner's Comment:

    • Performance Step: 4 Evaluate HOT CONDITIONS Matrix per EPCLA-01 EPCLA-Oi (Step 8.3.2).

Standard: Candidate reviews and evaluates HOT CONDITIONS Matrix.

Examiners Note:

Examiner's Comment:

2008 NRC NRC JPM JPM A5 AS NUREG NUREG 1021, 1021, Revision 9, Supplement i1

Appendix C Page 5 of 7 Form Form ES-C-1 ES-C-i INFORMATION PERFORMANCE INFORMATION

    • Performance Step: 5 EAL condition conforming to the available information.

Select EAL Standard: Candidate selects SITE AREA EMERGENCY.

Examiners Note:

Examiner's Site Area Emergency based on the following:

HOT CONDITIONS - EAL Matrix (Sheet 2 of 3)

F, Fission Product Barriers; Applicable in Modes 1, 2, 3 & & 4.

FS1 .1, Loss or Potential Loss of any two barriers. (Table F-1)

FS1.1, F-i)

> 5 Rem/hr).

  • Containment Barrier - Loss 5 (Containment isolation valve(s) not closed after Containment isolation AND Downstream pathway to the environment exists.

Comment:

ENDOFTASK END OF TASK Terminating Cue: EAL classification has been determined.

STOP TIME: _ _ _ __ CRITICAL TASK STOP TIME: _ _ __

2008 NRC JPM JPM A5 NUREG NUREG 1021, 1021, Revision 9,9, Supplement 11

Appendix C Page 6 of 7 Form ES-C-1 ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: A5 2008 NRC JPM AS Examinees Name:

Examinee's Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiners Signature:

Examiner's Date:

2008 NRC JPM A5 AS NUREG NUREG 1021, 1021, Revision 9, Supplement 11

Appendix C Appendix C Page 77 of Page of 77 Form ES-C-1 Form ES-C-i JPM CUE JPM CUE SHEET SHEET INITIAL CONDITIONS:

  • 100% RTP with a CV Pressure Relief The plant was operating at 100%

in progress when a Large Break LOCA occurred.

  • PATH-i.

The crew is progressing through PATH-1.

  • R-32A, CV High Range Monitor, is reading 6.4 Rem/hr.
  • CV Pressure Relief Valves V12-10 Vi 2-10 and V12-11 Vi 2-i i did not close.
  • Core Exit thermocouples currently read 685 degrees F and are slowly trending down.
  • Reactor Engineering has reported that NO substantial core damage has occurred.
  • RVLIS is reading 44% and is stable.

Full Range RVLlS

  • Weather conditions: Wind direction from 100i 00 degrees, Wind Speed is 3 MPH, Stability Class is D, and Precipitation is Zero.
  • You are the SSO.

INITIATING CUE: Classify the event lAW the EAL matrices. Refer to EPCLA-01 for guidance on the EAL classification. Provide the selected classification to the Examiner within 15 iS minutes.

2008 2008 NRC NRC JPM JPM A5 A5 NUREG NUREG i1021, 02i, Revision 9, 9, Supplement Supplement 11

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