Text

Initial Exam 2008-301 Draft Administrative JPMs
	ML101970328
Person / Time
Site:	Robinson
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)
	v • d • e

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

Facility:

HB ROBINSON Date of Examination:

2008 NRC Examination Level (circle one): I SRO Operating Test Number:

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

Code*

N G2.2.1 (3.9);

001 A4.l0 (3.5)

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

M 015 Al.04 (3.5)

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

N 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-l 14, Primary Water Flow Auto Mode.

N 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:

(C)ontrol room

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

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

(P)revious 2 exams ( 1; randomly selected)

(S)imulator NUREG-l 021, Revision 9 ES-301 Administrative Topics Outline Form ES-301-1 Z>t-afl.

Facility:

HB ROBINSON Date of Examination:

200BNRC Examination Level (circle one):

[@/SRO Operating Test Number:

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

Code*

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

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

M 015 A 1.04 (3.5)

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

N G2.2.12 (3.7)

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

N 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:

(C)ontrol room (D)irect from bank (:::; 3 for ROs; :::; for SROs & RO retakes)

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

(P)revious 2 exams (:::; 1; randomly selected)

(S)imulator NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301 -1 LD-L Facility:

HB ROBINSON Date of Examination:

2008 NRC Examination Level (circle one):

RO 4 SRO Operating Test Number:

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

Code*

N G2.2.1 (4.2);

001 A4.10 (3.9)

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

M 015A1.04(3.7)

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

N 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-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 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 Codes & Criteria:

(C)ontrol room (D)irect from bank ( 3 for ROs; for SROs & RO retakes)

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

(P)revious 2 exams ( 1; randomly selected)

(S)imulator NUREG-1 021, Revision 9 ES-301 Administrative Topics Outline Form ES-301-1 J] ;r- ~ !-./:::

Facility:

HB ROBINSON Date of Examination:

200BNRC Examination Level (circle one):

RO~SROI Operating Test Number:

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

Code*

N G2.2.1 (4.2); 001 A4.10 (3.9)

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

M 015 A1.04 (3.7)

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

N G2.2.12 (4.1)

Equipment Control Given a set of conditions, perform the Administrative Daily Checks to determine potentiometer settings for FCV-113A, Boric Acid Flow and HFC-114, 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 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 Codes & Criteria:

(C)ontrol room (D)irect from bank (~ 3 for ROs; ~ for SROs & RO retakes)

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

(P)revious 2 exams (~ 1; randomly selected)

(S)imulator NUREG-1 021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301 -2 LVra)t Facility:

HB ROBINSON Date of Examination:

2008 NRC Exam Level (circle one):

RO / SRO(l) I SRO (U)

Operating Test No.:

Control Room Systems@ (8 for RO; 7 for SRO-l; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function a.

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

per OST-Ol 1. (SB) b.

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

Level Alarm. (51) c.

(RCSIOO2): Start a RCP per OP-i 01. (S4)

D, L, S 4P d.

(CSS/026): Reactor Trip/Safety Injection response with Failure of A, N, 5 5

Containment Spray to Actuate. (S5) e.

(AC DIST/062): Restore Control Power to ECCS Valves. (S2).

A, D, 5 6

f.

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

g.

(RMS/072): Respond to a Loss of Circulating Water Pump. (S7)

A, D, 5, 8

h.

(SW/076): Limit Radiation Exposure in response to a Radiation D, 5 9

alarm. (S3) (SRO-I do not perform).

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

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

D, E, R 1

j.

(PZR Pressure/OlO): Energize PZR Heaters from Emergency D, E 3

busses using EPP-21. (1P3) k.

(EDGIO64): Manually start EDG using Air Start Solenoids. (IPi)

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 / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant

> 1 /

1 I 1

(L)ow-Power I Shutdown 1 /

1 /

1 (N)ew or (M)odified from bank including 1(A) 2 /

2 /

1 (P)revious 2 exams i < 3 I 2 (randomly selected)

(R)CA 1I1/1 (S)imulator NUREG-1021, Revision 9 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

HB ROBINSON Date of Examination:

200BNRC Exam Level (circle one):

RO 1 SRO(I) 1 SRO (U)

Operating Test No.:

Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System 1 JPM Title Type Code*

Safety Function

a.

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

per OST -011. (S8)

b.

(ECCS/006): Fill a Safety Injection Accumulator to clear the Low D,S 2

Level Alarm. (S1)

c.

(RCS/002): Start a RCP per OP-101. (S4)

D,L,S 4P

d.

(CSS/026): Reactor Trip/Safety Injection response with Failure of A,N,S 5

Containment Spray to Actuate. (S5)

e.

(AC DIST/062): Restore Control Power to ECCS Valves. (S2).

A,D,S 6

f.

(NIS/015): Remove N-44 from service. (S6)

D,S 7

g.

(RMS/072): Respond to a Loss of Circulating Water Pump. (S7)

A, D, S, 8

h.

(SW/076): Limit Radiation Exposure in response to a Radiation D,S 9

alarm. (S3) (SRO-I do not perform).

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

i.

(Rod ControI/001): Trip the Reactor as Inside AO. (IP2)

D, E, R 1

j.

(PZR Pressure/010): Energize PZR Heaters from Emergency D,E 3

busses using EPP-21. (IP3)

k.

(EDG/064): Manually start EDG using Air Start Solenoids. (IP1)

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 (C)ontrol room (D)irect from bank 5:9/5:8/5:4 (E)mergency or abnormal in-plant

?1/;?1/~: :1 (L)ow-Power 1 Shutdown

?1/;?1/;?1 (N)ew or (M)odified from bank including 1 (A)

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

(R)CA

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

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

HB ROBINSON Task No.:

01006100101 Task

Title:

Manually Calculate an Estimated JPM No.:

2008 NRC JPM Al Critical Condition K/A

Reference:

G2.l.25 (3.9/4.2)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant 2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

HB ROBINSON Task No.:

01006100101 Task

Title:

Manually Calculate an Estimated Critical Condition JPM No.:

2008 NRC JPM A1 KIA

Reference:

G2.1.25 (3.9/4.2)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

x Classroom X

Simulator Plant 2008 NRC JPM A1 NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-i 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 is in Mode 3 with TAVG at 547 degrees F following a unit trip.

The trip occurred from equilibrium conditions following a 78 day run at full power conditions.

Critical Data Stamp initiated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to trip lists the following conditions at time of trip:

o 602 ppm Boron o

Control rods at 218 steps on CB D o

Poweratl00%RTP o

Burnup is at 333.01 EFPD (11668.5 MWD/MTU)

Projected return to criticality is 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months 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.

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 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 is in Mode 3 with TAVG at 547 degrees F following a unit trip.

The trip occurred from equilibrium conditions following a 78 day run at full power conditions.

Critical Data Stamp initiated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to trip lists the following conditions at time of trip:

o 602 ppm Boron o

Control rods at 218 steps on CB "0" o

Power at 100% RTP o

Burnup is at 333.01 EFPO (11668.5 MWO/MTU)

Projected return to criticality is 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months 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.

2008 NRC JPM A 1 NUREG 1021, Revision 9, Supplement 1

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

Calculate Estimated Critical Condition within +1-250 PCM of Reactor Engineering validated condition.

Required Materials:

Calculator GP-003, Attachment 10.1 Applicable Plant Curve Book curves: Section 1, Section 2 General

References:

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

GP-003, Attachment 10.1 Applicable Plant Curve Book curves: Section 1, Section 2 Initiating Cue:

Perform a Manual Estimated Critical Condition Calculation lAW GP-003, 0.1 for a projected Critical condition time of 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months from trip.

Time Critical Task:

NO Validation Time:

75 minutes 2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 Task Standard:

Calculate Estimated Critical Condition within +/- 250 PCM of Reactor Engineering validated condition.

Required Materials:

Calculator GP-003, Attachment 10.1 Applicable Plant Curve Book curves: Section 1, Section 2 General

References:

GP- 003, NORMAL PLANT STARTUP FROM HOT SHUTDOWN TO CRITICAL Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

2008 NRC JPM A1 Station Curve Book GP-003, Attachment 10.1 Applicable Plant Curve Book curves: Section 1, Section 2 Perform a Manual Estimated Critical Condition Calculation lAW GP-003, 0.1 for a projected Critical condition time of 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months from trip.

NO 75 minutes NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 15 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Start Time:

Performance Step: 1 Enter Attachment 10.1 pre-trip data (Steps 1.1, 1.2, 1.3)

Standard:

Enters Criticality number as 501.

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

Power Level at 100% (Step 1.2)

Boron Concentration at 602 (Step 1.3.1)

Number of days since last Critical Data Stamp and shutdown as

0. (Step 1.3.2)

Examiners Note:

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.

Examiners Note:

Comment:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Page 4 of 15 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Note:

Comment:

Performance Step: 2 Standard:

Examiner's Note:

Comment:

2008 NRC JPM A1 Start Time: ___

Enter Attachment 10.1 pre-trip data (Steps 1.1, 1.2, 1.3)

Enters Criticality number as 501.

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

Power Level at 100% (Step 1.2)

Boron Concentration at 602 (Step 1.3.1)

Number of days since last Critical Data Stamp and shutdown as O. (Step 1.3.2)

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

Enters 602 ppm in Step 1.3.6.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 15 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 Using Integral Boron Worth Curve 1.13, enter Integral Boron Worth.

Standard:

Using Integral Boron Worth Curve 1.13, enters Integral Boron Worth as 5166 pcm in Step 1.4.

Examiners Note:

Interpolated data: BOL Value = 5500, EOL value 4500,.66%

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

Standard:

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

Examiners Note:

Interpolated data: BOL value = 2560, EOL value = 2800.

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

Comment:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 3 Standard:

Examiner's Note:

Comment:

Performance Step: 4 Standard:

Examiner's Note:

Comment:

2008 NRC JPM A1 Page 5 of 15 PERFORMANCE INFORMATION Form ES-C-1 Using Integral Boron Worth Curve 1.13, enter Integral Boron Worth.

Using Integral Boron Worth Curve 1.13, enters Integral Boron Worth as 5166 pcm in Step 1.4.

Interpolated data: BOl Value = 5500, EOl value 4500,.66%

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

5166.

Acceptable ranges/tolerances for curves are NOT given for this JPM. Final PCM change has an acceptable range of +/-

250 pcm, which includes all individual curve and math tolerances.

USing Xenon Worth Curve 2.1, enter Xenon Worth at time of trip.

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

Interpolated data: BOl value = 2560, EOl value = 2800.

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

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 15 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 5 Using Power Defect Curve 1.3, enter Power Defect at time of trip.

Standard:

Using Power Defect Curve 1.3, enters Power Defect at time of trip as 2115 pcm, in Step 1.6.

Examiners Note:

Power Defect Curves 1.3B (MOL) and 1.3C (EOL) should be used to interpolate power defect for 100% power, Boron concentration of 602 ppm. Interpolated data: MOL = 1950 pcm, EOL = 2450 pcm. Interpolate EOL MOL = 500 pcm x

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

Comment:

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

Standard:

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

Examiners Note:

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

Interpolated data: BOL from Curve 2.4A = 790, EOL from Curve 2.4B = 980. EOL BOL = 190 x.66 =125. 790 + 125 =

915.

Comment:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 5 Standard:

Examiner's Note:

Comment:

Performance Step: 6 Standard:

Examiner's Note:

Comment:

2008 NRC JPM A 1 Page 6 of 15 PERFORMANCE INFORMATION Form ES-C-1 Using Power Defect CUNe 1.3, enter Power Defect at time of trip.

Using Power Defect CUNe 1.3, enters Power Defect at time of trip as 2115 pcm, in Step 1.6.

Power Defect Curves 1.3B (MOL) and 1.3C (EOl) should be used to interpolate power defect for 100% power, Boron concentration of 602 ppm. Interpolated data: MOL = 1950 pcm, EOl = 2450 pcm. Interpolate EOl - MOL = 500 pcm x

.33 = 165 (MOl-EOl delta). 1950 + 165 = 2115 pcm.

Using Samarium Worth Curves 2.4A, 2.48, 2.5, enter Samarium Worth at time of trip.

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

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

Interpolated data: BOl from Curve 2.4A = 790, EOl from Curve 2.4B = 980. EOl - BOl = 190 x.66 =125. 790 + 125 =

915.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 15 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 7 Using Inserted Rod Worth curve 1.6, 1.8 enter Inserted Rod Worth at time of trip.

Standard:

Using Inserted Rod Worth curve 1.6, i.8 enters Inserted Rod Worth at time of trip as 0 pcm in Step 1.8.

Examiners Note:

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 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months in Steps 2.1, 2.2, 2.3.

Examiners Note:

Comment:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 7 Standard:

Examiner's Note:

Comment:

Performance Step: 8 Standard:

Examiner's Note:

Comment:

2008 NRC JPM A1 Page 7 of 15 PERFORMANCE INFORMATION Form ES-C-1 Using Inserted Rod Worth curve 1.6, 1.8 enter Inserted Rod Worth at time of trip.

Using Inserted Rod Worth curve 1.6, 1.8 enters Inserted Rod Worth at time of trip as 0 pcm in Step 1.8.

Should use Curve 1.6 per Note #3.

Enter Projected Boron Concentration, temperature, and time since shutdown.

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

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 15 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 9 Enter Integral Boron Worth.

Standard:

Enters Integral Boron Worth as 5166 pcm in Step 2.4.

Examiners Note:

Should enter same value as Step 1.4, above.

Comment:

Performance Step: 10 Enter Projected Xenon Worth at Startup.

Standard:

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

Examiners Note:

Interpolated data from BOL Curve 2.3A (3400 pcm @ 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months ) and EOL Curve 2.3B (4200 pcm @ 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months ).

Interpolating 4200 3400 = 800 x.66 = 528.

3400 + 528 =

3928 pcm.

Comment:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 9 Standard:

Examiner's Note:

Comment:

Page 8 of 15 PERFORMANCE INFORMATION Enter Integral Boron Worth.

Enters Integral Boron Worth as 5166 pcm in Step 2.4.

Should enter same value as Step 1.4, above.

Form ES-C-1 Performance Step: 10 Enter Projected Xenon Worth at Startup.

Standard:

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

Examiner's Note:

Interpolated data from 80l Curve 2.3A (3400 pcm @ 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months ) and EOl Curve 2.38 (4200 pcm @ 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months ).

Comment:

2008 NRC JPM A1 Interpolating 4200 - 3400 = 800 x.66 = 528. 3400 + 528 =

3928 pcm.

NUREG 1021, Revision 9, Supplement 1

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

Standard:

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

Examiners Note:

Interpolated data: BOL Curve 2.4A = 865, EOL Curve 2.4.B =

1070.

205 x £6 = 135 + 865 = 1000 pcm.

Comment:

Performance Step: 12 Enter Samarium change before equilibrium.

Standard:

Enters Samarium change before equilibrium as 0 pcm.

Examiner Cue:

Comment:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Page 9 of 15 PERFORMANCE INFORMATION Performance Step: 11 Enter Samarium Worth at Startup.

Form ES-C-1 Standard:

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

Examiner's Note:

Interpolated data: BOl Curve 2.4A = 865, EOl Curve 2.4.B =

1070.

205 x.66 = 135 + 865 = 1000 pcm.

Comment:

Performance Step: 12 Enter Samarium change before equilibrium.

Standard:

Enters Samarium change before equilibrium as a pcm.

Examiner Cue:

Comment:

2008 NRC JPM A1 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 15 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 13 Enter determined values, perform calculation per Step 3.2 to determine calculated change in Reactivity.

Standard:

Enter determined values, perform calculation per Step 3.2 to determine calculated change in Reactivity. Calculate Change in Reactivity = 822 pcm +1-250 pcm (572-i 072 pcm).

Examiners Note:

Comment:

performance Step: 14 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)

Examiners Note:

AT Step 4.2, inform candidate: Reactor Engineers calculation is the same as yours.

Comment:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Page 10 of 15 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 13 Enter determined values, perform calculation per Step 3.2 to determine calculated change in Reactivity.

Standard:

Enter determined values, perform calculation per Step 3.2 to determine calculated change in Reactivity. Calculate Change in Reactivity = 822 pcm +/- 250 pcm (572-1072 pcm).

Examiner's Note:

Comment:

Performance Step: 14 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 Note:

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

Comment:

2008 NRC JPM A1 NUREG 1021, Revision 9, Supplement 1

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

performance Step: 15 Determine new Critical Rod Position associated with the integral worth in Step 4.1 using Curve 1.8.

Standard:

Determines new Critical Rod Position associated with the integral worth in Step 4.1 usina Curve 1.8. as listed in the table below.

Candidate value from step 4.2.

Allowable Tolerance Band.

> 572 672 pcm 95 steps 168 steps

> 672 772 pcm 80 steps 155 steps

> 772 872 pcm 70 steps 128 steps 872 972 pcm 58 steps 90 steps

> 972 1072 pcm 50 steps 82 steps Examiners Note:

Tolerance Bands vary by pcm calculated and are calculated based on +/- /2 of the range between the 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.

Standard:

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

Examiners Note:

Comment:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C

Performance Step: 15 Standard:

Examiner's Note:

Comment:

Page 11 of 15 PERFORMANCE INFORMATION Form ES-C-1 Determine new Critical Rod Position associated with the integral worth in Step 4.1 using Curve 1.8.

Determines new Critical Rod Position associated with the integral wort h' C

In Step 4.1 using urve 1.8. as listed in the table below.

Candidate value from step 4.2.

Allowable Tolerance Band.

2=. 572 - 672 pcm 95 steps 168 steps 2=. 672 - 772 pcm 80 steps 155 steps 2=. 772 - 872 pcm 70 steps 128 steps 2=. 872 - 972 pcm 58 steps 90 steps 2=. 972 - 1072 pcm 50 steps 82 steps Tolerance Bands vary by pcm calculated and are calculated based on +/- % of the range between the EOl and MOL curves on Curve 1.8 for the pcm band.

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

Standard:

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

Examiner's Note:

Comment:

2008 NRC JPM A1 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 15 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 17 Answers questions in Steps 5.2 and 5.3.

Standard:

Answers questions in Steps 5.2 and 5.3 as YES.

Examiners Note:

Comment:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Page 12 of 15 PERFORMANCE INFORMATION Performance Step: 17 Answers questions in Steps 5.2 and 5.3.

Standard:

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

Examiner's Note:

Comment:

Form ES-C-1 2008 NRC JPM A1 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 13 of 15 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 18 Calculate the tolerance band of plus OR minus 500 pcm from the ECP in Steps 6.1.1 and 6.1.2.

Standard:

Calculates the tolerance band of plus OR minus 500 pcm from the ECP as 5 steps to 200 steps on Bank D.

Examiners Note:

Comment:

Performance Step: 19 Record ECP completion time.

Standard:

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

Examiners Note:

To allow use of this ECP, criticality must be achieved within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the completion time recorded. This will ensure compliance with ITS SR 3.1.6.1.

Comment:

END OFTASK Terminating Cue:

GP-003, Attachment 10.1 completed.

STOP TIME:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 18 Standard:

Examiner's Note:

Comment:

Page 13 of 15 PERFORMANCE INFORMATION Form ES-C-1 Calculate the tolerance band of plus OR minus 500 pcm from the ECP in Steps 6.1.1 and 6.1.2.

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

Performance Step: 19 Record ECP completion time.

Standard:

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

Examiner's Note:

To allow use of this ECP, criticality must be achieved within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the completion time recorded. This will ensure compliance with ITS SR 3.1.6.1.

Comment:

END OF TASK Terminating Cue:

GP-003, Attachment 10.1 completed.

STOP TIME:

2008 NRC JPM A1 NUREG 1021, Revision 9, Supplement 1

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

2008 NRC JPM Al Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Page 14 of 15 VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC JPM A 1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

Form ES-C-1 2008 NRC JPM A1 NUREG 1021, Revision 9, Supplement 1

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

The plant is in Mode 3 with TAVG at 547 degrees F following a unit trip.

The trip occurred from equilibrium conditions following a 78 day run at full power conditions.

Critical Data Stamp initiated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to trip lists the following conditions at time of trip:

o 602 ppm Boron o

Control rods at 218 steps on CB D o

Poweratio0%RTP o

Burnup is at 333.01 EFPD (11668.5 MWD/MTU)

Projected return to criticality is 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months 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, 0.1 for a projected Critical Condition time of 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months from trip.

2008 NRC JPM Al NUREG 1021, Revision 9, Supplement 1 Appendix C Initial Conditions:

Initiating Cue:

2008 NRC JPM A1 Page 15 of 15 JPM CUE SHEET Form ES-C-1 The plant is in Mode 3 with TAVG at 547 degrees F following a unit trip.

The trip occurred from equilibrium conditions following a 78 day run at full power conditions.

Critical Data Stamp initiated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to trip lists the following conditions at time of trip:

o 602 ppm Boron o

Control rods at 218 steps on CB "0" 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 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months 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.

Perform a Manual Estimated Critical Condition Calculation lAW GP-03, 0.1 for a projected Critical Condition time of 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months from trip.

NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form 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:

015 Al.04 (3.5/3.7)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAM INEE 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 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.

ERFIS is inoperable.

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 45 Normalizing 99 o

N44: Upper 48 Normalizing 97 o

N44: Lower 45 Normalizing 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 Appendix C Facility:

Task

Title:

KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing:

HB ROBINSON Job Performance Measure Worksheet Task No.:

Perform a Manual QPTR Calculation JPM No.:

015 A 1.04 (3.5/3.7)

NRC Examiner:

Date:

Form ES-C-1 01015100402 2008 NRC JPM A2 Simulated Performance:

Actual Performance:

x Classroom Plant X

Simulator

-~-

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:

Task Standard:

Required Materials:

2008 NRC JPM A2 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.

ERFIS is inoperable.

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 - 45 Normalizing - 99 o

N44: Upper - 48 Normalizing - 97 o

N44: Lower - 45 Normalizing - 95 Perform a MANUAL QPTR calculation lAW FMP-007, QUADRANT POWER TILT with an accuracy of +/- 0.5%.

Calculator FMP-007, QUADRANT POWER TILT NUREG 1021, Revision 9, Supplement 1

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

References:

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

FMP-007 Attachment 10.2, MANUAL QPTR CALCULATIONS.

Handouts:

FMP-007, QUADRANT POWER TILT.

Initiating Cue:

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

Time Critical Task:

NO Validation Time:

15 minutes 2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1 Appendix C General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

2008 NRC JPM A2 Job Performance Measure Worksheet Form ES-C-1 FMP-007, QUADRANT POWER TILT, Section 8.2.4, Manual QPTR Calculations.

FMP-007 Attachment 10.2, MANUAL QPTR CALCULATIONS.

FMP-007, QUADRANT POWER TILT.

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

NO 15 minutes NUREG 1021, Revision 9, Supplement 1

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

The plant is at 60% RTP.

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

APP-005-F4, PR LOWER CH HI FLUX DEV/AUTO DEFEAT is illuminated.

ERFIS is inoperable FMP-007, Attachment 10.2 Manual QPTR Calculations has been initiated, with Indicated Detector Currents and Normalizing Detector Currents recorded.

INITIATING CUE:

Complete Attachment iO.2 lAW FMP-007, QUADRANT POWER T LT.

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1 Appendix C INITIAL CONDITIONS:

Job Performance Measure Worksheet The plant is at 60% RTP.

Form ES-C-1 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.

ERFIS is inoperable FMP-007, Attachment 10.2 Manual QPTR Calculations has been initiated, with Indicated Detector Currents and Normalizing Detector Currents recorded.

INITIATING CUE:

Complete Attachment 10.2 lAW FMP-007, QUADRANT POWER TILT.

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 10 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Start Time:

Performance Step: 1 Enter each Indicated and Normalizing Detector Current in 0.2 Standard:

Enters detector currents as given in initiating cue in correct boxes of Attachment 10.2.

Examiners Note:

Comment:

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1 Appendix C Page 4 of 10 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner's Note:

Comment:

2008 NRC JPM A2 Start Time: ___ _

Enter each Indicated and Normalizing Detector Current in 0.2 Enters detector currents as given in initiating cue in correct boxes of Attachment 10.2.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 10 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 2 Divide each Indicated Detector Current by its corresponding Normalizing Detector Current and record the result as the Normalized Detector Ratio on Attachment 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 Lower N41 = 0.4583 Upper N42 = 0 Lower N42 = 0 Upper N43 = 0.4808 Lower N43 = 0.4545 Upper N44 0.4948 Lower N44 = 0.4737 Examiners Note:

Calculated values rounded to 4th decimal place.

Cornment:

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 Examiners Note:

Calculated values rounded to 4 th decimal place.

Candidate should NOT include data from the failed NI Channel.

Comment:

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 2 Standard:

Examiner's Note:

Comment:

Performance Step: 3 Standard:

Examiner's Note:

Comment:

2008 NRC JPM A2 Page 5 of 10 PERFORMANCE INFORMATION Form ES-C-1 Divide each Indicated Detector Current by its corresponding Normalizing Detector Current and record the result as the Normalized Detector Ratio on Attachment 10.2.

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 = 0.5122 Upper N42 = 0 Upper N43 = 0.4808 Upper N44'= 0.4948 Lower N41 = 0.4583 Lower N42 = 0 Lower N43 = 0.4545 Lower N44 = 0.4737 Calculated values rounded to 4th decimal place.

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.

Upper Average Normalized Detector Ratio = 0.4959 Lower Average Normalized Detector Ratio = 0.4621 Calculated values rounded to 4th decimal place.

Candidate should NOT include data from the failed NI Channel.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 10 Form ES-C-i PERFORMANCE INFORMATION

performance Step: 4 Determine the maximum Upper Normalized Detector Ratio and divide it by the Average Upper Normalized Detector Ratio from Performance Step 2 and record the resulting Upper QPTR on 02.

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 0.2.

Upper QPTR = 0.5122 / 0.4959 = 1.0329 Examiners Note:

Calculated values rounded to 4 th decimal place.

Comment:

performance Step: 5 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.

Lower QPTR = 0.4737/0.4621 = 1.0251 Examiners Note:

Calculated values rounded to 4 th decimal place.

Comment:

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1 Appendix C Page 6 of 10 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 4 Determine the maximum Upper Normalized Detector Ratio and divide it by the Average Upper Normalized Detector Ratio from Performance Step 2 and record the resulting Upper QPTR on 0.2.

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 0.2.

Upper QPTR = 0.5122/0.4959 = 1.0329 Examiner's Note:

Calculated values rounded to 4th decimal place.

Comment:

Performance Step: 5 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.

Lower QPTR = 0.4737 /0.4621 = 1.0251 Examiner's Note:

Calculated values rounded to 4th decimal place.

Comment:

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1

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

pel.formance Step: 6 Record 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.

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:

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.

Standard:

Enters comment that the Calculated Maximum QPTR exceeds allowable Tech Spec limit of < 1.02 or enters 90.4% as Reactor Power limit.

Examiners Note:

Calculated values rounded to 4k decimal place.

Comment:

END OF TASK Terminating Cue:

Manual QPTR has been completed.

STOP TIME:

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1 Appendix C Page 7 of 10 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 6 Record 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.

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.

Examiner's Note:

Comment:

Performance Step: 7 Standard:

Examiner's Note:

Comment:

Terminating Cue:

STOP TIME:

2008 NRC JPM A2 Records the Maximum QPTR as 1.0329, Power Level as 60%.

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

Enter appropriate comments regarding the Manual QPTR Calcu lation.

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

Calculated values rounded to 4th decimal place.

END OF TASK Manual QPTR has been completed.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 10 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC JPM A2 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1 Appendix C Page 8 of 10 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.:

2008 NRC JPM A2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

2008 NRC JPM A2 NUREG 1021, Revision 9, Supplement 1

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

HB ROBINSON Task No.:

Task

Title:

Determine If Required Shift Manning Is JPM No.:

2008 NRC ADM SRO b Met.

K/A

Reference:

2.1.4 Examinee

NRC Examiner:

Facility Evaluator:

Date:

Method of testincj:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAM INEE 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:

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 SRO STA Auten q

Bailes Blair Brown Ellis G rant Harbin Hinds Horton 1

Hunt Task Standard:

Determine that proper shift manning is NOT met.

Required Materials:

OMM-001-2, SHIFT ROUTINES AND OPERATING PRACTICES.

2008 NRC ADM SRO b NUREG 1021, Revision 9, Supplement 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

HB ROBINSON Task No.:

Task

Title:

Determine If Required Shift Manning Is JPM No.:

2008 NRC ADM SRO b Met.

KIA

Reference:

2.1.4 Examinee

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

x Classroom Plant X

Simulator 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:

Task Standard:

Required Materials:

You are the CRSS.

Unit 2 is operating at 100% RTP.

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

(~ = PRESENT)

Qualifications and/or License held Name SSO CRSS RO AO FPAO WCCSRO Auten

~

Bailes

~

Blair

~

Brown

~

Ellis

~

Grant Harbin Hinds

~

Horton

~

Hunt Determine that proper shift manning is NOT met.

OMM-001-2, SHIFT ROUTINES AND OPERATING PRACTICES.

STA

~

2008 NRC ADM SRO b NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C1 Worksheet General

References:

OMM-O01-2, SHIFT ROUTINES AND OPERATING PRACTICES.

Initiating Cue:

Determine whether the shift complement requirements are met.

Time Critical Task:

NO Validation Time:

10 minutes 2008 NRC ADM SRO b NUREG 1021, Revision 9, Supplement 1 Appendix C General

References:

Initiating Cue:

Time Critical Task:

Validation Time:

Job Performance Measure Worksheet Form ES-C-1 OMM-001-2, SHIFT ROUTINES AND OPERATING PRACTICES.

Determine whether the shift complement requirements are met.

NO 10 minutes 2008 NRC ADM SRO b NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 6 Form ES-C-i PERFORMANCE INFORMATION Examiner Note: The required reference for this JPM is OMM-OO1-2, Section 8.1.3.

Performance Step: 1 Determine whether the MIMIMUM shift complement is met Standard:

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

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 -2, Section 81.3.4.a.

Examiners Note:

Examiners Cue:

Comment:

2008 NRC ADM SRO b NUREG 1021, Revision 9, Supplement 1 Appendix C Page 3 of 6 PERFORMANCE INFORMATION Form ES-C-1 Examiner Note: The required reference for this JPM is OMM-001-2, Section 8.1.3.

Performance Step: 1 Standard:

Examiner Note:

Comment:

Performance Step: 2 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

2008 NRC ADM SRO b Determine whether the MIMIMUM shift complement is met Candidate determines that the shift complement is one individual less than required.

Determine what additional resources, by qualification, are required.

Candidate determines that the additional individual needed can be an SCO, CO or AO as specified in OMM-001-2, Section 8.1.3.4.a.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 6 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 Candidate Question What allowances are provided for the shift to be one less than the minimum requirement?

Standard:

The shift complement may be one less than the minimum requirement for a period NOT to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift members provided immediate action is taken to restore the shift complement to within the minimum requirements.

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

Examiners Note:

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

Examiners Cue:

Comment:

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

STOP TIME:

2008 NRC ADM SRO b NUREG 1021, Revision 9, Supplement 1 Appendix C

Performance Step: 3 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

Page 4 of 6 PERFORMANCE INFORMATION Form ES-C-1 Candidate Question - What allowances are provided for the shift to be one less than the minimum requirement?

The shift complement may be one less than the minimum requirement for a period NOT to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift members provided immediate action is taken to restore the shift complement to within the minimum requirements.

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

OMM-001-2, Section 8.1.2.1 is reference to the question.

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

STOP TIME:

2008 NRC ADM SRO b NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 6 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC ADM SRO b Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2008 NRC ADM SROb NUREG 1021, Revision 9, Supplement i Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC ADM SRO b Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

Form ES-C-1 2008 NRC ADM SRO b NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 6 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

You are the CRSS.

Unit 2 is operating at 100% RTP.

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

(J = PRESENT)

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

Bailes q

Blair q

Brown Ellis q

Grant Harbin Hinds q

Horton q

Hunt INITIATING CUE:

Determine whether the shift complement requirements are met.

2008 NRC ADM SRO b NUREG 1021, Revision 9, Supplement 1 Appendix C Page 6 of 6 JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS:

You are the CRSS.

INITIATING CUE:

2008 NRC ADM SRO b Unit 2 is operating at 100% RTP.

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

(..j = PRESENT)

Qualifications and/or License held Name SSO CRSS RO AO FPAO WCCSRO Auten

..j Bailes

..j Blair

..j Brown

..j Ellis

..j Grant Harbin Hinds

..j Horton

..j Hunt Determine whether the shift complement requirements are met.

STA

..j NUREG 1021, Revision 9, Supplement 1

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

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:

2.3.12 (3.2/3.7)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testinci:

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):

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 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 extension of up to the Repair and Re-entry 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 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?

2008 NRC JPM A3 NUREG 1021, Revision 9, Supplement 1 Appendix C Facility:

Task

Title:

HB ROBINSON Job Performance Measure Worksheet Task No.:

Form ES-C-1 Evaluate the Radiological conditions JPM No.:

2008 NRC JPM A3 for two situations below, and answer Questions #1 and #2 KIA

Reference:

2.3.12 (3.2/3.7)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

x Classroom Plant X

Simulator 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):

2008 NRC JPM A3 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-position two manual valves in a 17 Rlhr field to ensure continued operation of available ECCS components.

The Radiological Control Director has authorized an annual dose extension of up to the "Repair and Re-entry 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 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?

NUREG 1021, Revision 9, Supplement 1

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

A manual isolation valve in the Excess Letdown HX discharge line was closed for maintenance.

The valve was re-opened by an AD who received 22 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 mm.

2008 NRC JPM A3 NUREG 1021, Revision 9, Supplement 1 Appendix C Initial Conditions (8):

Job Performance Measure Worksheet Form ES-C-1 A manual isolation valve in the Excess Letdown HX discharge line was closed for maintenance.

The valve was re-opened by an AO who received 22 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.

2008 NRC JPM A3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 5 Form ES-C-i VERIFICATION OF COMPLETION Start Time:

Performance Step: 1 Answer Condition A:

Repair and re-entry Limit is 10 REM.

Most limiting person is Operator B Operator B: 10,000 mRem 203 mRem = 9797 mRem left for the year.

(9797 mRem)(i 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 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-1 303, 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 Terminating Cue:

Questions for conditions A and B have been answered.

Stop time:

2008 NRC JPM A3 NUREG 1021, Revision 9, Supplement 1 Appendix C Start Time: __ _

Performance Step: 1 Standard:

Examiner Note:

Comment:

Performance Step: 2 Standard:

Examiner Note:

Comment:

Terminating Cue:

Stop time: __

2008 NRC JPM A3 Page 3 of 5 Form ES-C-1 VERI FICATION OF COMPLETION Answer Condition "A":

Repair and re-entry Limit is 10 REM.

Most limiting person is Operator "8" Operator "8": 10,000 mRem - 203 mRem = 9797 mRem left for the year.

(9797 mRem)(1 hour/17,000 mRem) = (.576 hrs.)(60 mins/hour) = 34.577 minutes.

Calculates a stay time of 33.0 -34.6 minutes.

Answer Condition "8":

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.)

Per OPS-NGGC-1303, 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.

END OF TASK Questions for conditions "A" and "8" have been answered.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 5 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC JPM A3 Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2008 NRC JPM A3 NUREG 1021, Revision 9, Supplement 1 Appendix C Page 4 of 5 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.:

2008 NRC JPM A3 Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

2008 NRC JPM A3 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 5 Form ES-C-i JPM CUE SHEET 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 crewfTSC has determined it is necessary to 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 extension of up to the Repair and Re-entry 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 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?

Initial Conditions (B):

A manual isolation valve in the excess Letdown HX discharge line was closed for maintenance.

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

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

2008 NRC JPM A3 NUREG 1021, Revision 9, Supplement 1 Appendix C Initial Conditions (A):

Initial Conditions (8):

2008 NRC JPM A3 Page 5 of 5 JPM CUE SHEET Form ES-C-1 An accident has resulted in the declaration of a Site Area Emergency (SA 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-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 extension of up to the "Repair and Re-entry 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 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?

A manual isolation valve in the excess Letdown HX discharge line was closed for maintenance.

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

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

NUREG 1021, Revision 9, Supplement 1

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

HB ROBINSON Task No.:

02344100403 Task

Title:

Declare an Emergency Event JPM No.:

2008 NRC JPM A5 K/A

Reference:

G2.4.41 (2.9/4.6)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAM INEE 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 operating at 100% RTP with a CV Pressure Relief in progress when a Large Break LOCA occurred.

The crew is progressing through PATH-i.

R-32A, CV High Range Monitor, is reading 6.4 Rem/hr.

CV Pressure Relief Valves Vi 2-10 and V12-ii 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 is reading 44% and is stable.

Weather conditions: Wind direction from 100 degrees, Wind Speed is 3 MPH, Stability Class is D, Precipitation is Zero.

You are the SSO.

Task Standard:

Identifies event as a SITE AREA EMERGENCY, per ES 1.1.

Required Materials:

EPCLA-Oi, EMERGENCY CONTROL, Revision 23 EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices 2008 NRC JPM A5 NUREG 1021, Revision 9, Supplement 1 Appendix C Facility:

Task

Title:

KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing:

HB ROBINSON Job Performance Measure Worksheet Task No.:

Declare an Emergency Event JPM No.:

G2.4.41 (2.9/4.6)

NRC Examiner:

Date:

Form ES-C-1 02344100403 2008 NRC JPM A5 Simulated Performance:

Actual Performance:

___ Plant x

Classroom X

Simulator

-~-

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.

I nitial Conditions:

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

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 and 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 RVLlS is reading 44% and is stable.

Weather conditions: Wind direction from 100 degrees, Wind Speed is 3 MPH, Stability Class is 0, Precipitation is Zero.

You are the SSO.

Task Standard:

Identifies event as a SITE AREA EMERGENCY, per FS 1.1.

Required Materials:

EPCLA-01, EMERGENCY CONTROL, Revision 23 2008 NRC JPM AS EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices NUREG 1021, Revision 9, Supplement 1

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

References:

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

EPCLA-Oi, EMERGENCY CONTROL, Revision 23 EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices 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 minutes.

Time Critical Task:

YES (Emergency classification is a 15 minute time critical task)

Validation Time:

12 minutes 2008 NRC JPM A5 NUREG 1021, Revision 9, Supplement 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 General

References:

EPCLA-01, EMERGENCY CONTROL, Revision 23 Handouts:

EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices EPCLA-01, EMERGENCY CONTROL, Revision 23 EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices 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 minutes.

Time Critical Task:

YES (Emergency classification is a 15 minute time critical task)

Validation Time:

12 minutes 2008 NRC JPM A5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 7 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

START TIME:

CRITICAL TASK START TIME:

Performance Step: 1 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:

Provide the candidate with a copy of the EAL matrices.

Comment:

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

Standard:

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

Examiners Note:

Provide the candidate with a copy of EPCLA-Oi.

Comment:

2008 NRC JPM A5 NUREG 102i, Revision 9, Supplement i Appendix C Page 3 of 7 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

START TIME: ___ _

Performance Step: 1 Standard:

Examiner's Note:

Comment:

Performance Step: 2 Standard:

Examiner's Note:

Comment:

2008 NRC JPM AS CRITICAL TASK START TIME: ___

Confirms that an off-normal condition exists.

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

Provide the candidate with a copy of the EAL matrices.

Refers to EPCLA-01, EMERGENCY CONTROL.

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

Provide the candidate with a copy of EPCLA-01.

NUREG 1021, Revision 9, Supplement 1

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

Performance Step: 3 Evaluate ALL CONDITIONS Matrix per EPCLA-Oi (Step 8.3.1).

Standard:

Candidate reviews and evaluates ALL CONDITIONS Matrix.

Examiners Note:

Comment:

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

Standard:

Candidate reviews and evaluates HOT CONDITIONS Matrix.

Examiners Note:

Comment:

2008 NRC JPM A5 NUREG 1021, Revision 9, Supplement i Appendix C Page 4 of 7 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 3 Evaluate ALL CONDITIONS Matrix per EPCLA-01 (Step 8.3.1).

Standard:

Candidate reviews and evaluates ALL CONDITIONS Matrix.

Examiner's Note:

Comment:

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

Standard:

Candidate reviews and evaluates HOT CONDITIONS Matrix.

Examiner's Note:

Comment:

2008 NRC JPM AS NUREG 1021, Revision 9, Supplement 1

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

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

Standard:

Candidate selects SITE AREA EMERGENCY.

Examiners Note:

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-i)

Reactor Coolant System Barrier Loss 1 (Containment High Range Radiation Monitor R-32A or R-32B > 5 Remlhr).

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

Comment:

ENDOFTASK Terminating Cue:

EAL classification has been determined.

STOP TIME:

CRITICAL TASK STOP TIME:

2008 NRC JPM A5 NUREG 1021, Revision 9, Supplement 1 Appendix C Page 5 of 7 PERFORMANCE INFORMATION Form ES-C-1

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

Standard:

Candidate selects SITE AREA EMERGENCY.

Examiner's Note:

Site Area Emergency based on the following:

Comment:

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)

Reactor Coolant System Barrier - Loss 1 (Containment High Range Radiation Monitor R-32A or R-32B > 5 Rem/hr).

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

END OF TASK Terminating Cue:

EAL classification has been determined.

STOP TIME: ____ _

CRITICAL TASK STOP TIME: ___

2008 NRC JPM A5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 7 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC JPM A5 Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2008 NRC JPM A5 NUREG 1021, Revision 9, Supplement 1 Appendix C Page 6 of 7 VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC JPM AS Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

Form ES-C-1 2008 NRC JPM AS NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 7 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

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

The crew is progressing through PATH-i.

R-32A, CV High Range Monitor, is reading 6.4 Rem/hr.

CV Pressure Relief Valves Vi 2-10 and 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.

Full Range RVLIS is reading 44% and is stable.

Weather conditions: Wind direction from i 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 iS minutes.

2008 NRC JPM A5 NUREG i 02i, Revision 9, Supplement 1 Appendix C INITIAL CONDITIONS:

INITIATING CUE:

2008 NRC JPM A5 Page 7 of 7 JPM CUE SHEET Form ES-C-1 The plant was operating at 100% RTP with a CV Pressure Relief in progress when a Large Break LOCA occurred.

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 and 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 RVLlS is reading 44% and is stable.

Weather conditions: Wind direction from 100 degrees, Wind Speed is 3 MPH, Stability Class is D, and Precipitation is Zero.

You are the SSO.

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 minutes.

NUREG 1021, Revision 9, Supplement 1

ML101970328

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