Text

Initial Exam 2008-301 Final Administrative JPMs
	ML101970298
Person / Time
Site:	Robinson
Issue date:	06/28/2010
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	50-261/08-301
	Download: ML101970298 (90)
	v • d • e

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 ADM Critical Condition.

RO/SRO a K/A

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 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 °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 the time of the trip:

o 760 ppm Boron o

Control rods at 218 steps on CB D o

Poweratl00%RTP o

Burnup is at 251.57 EFPD (9056.5 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 760 ppm.

The next Criticality number is 501.

You have been directed to perform a Manual Estimated Critical Conditions calculation for the given conditions.

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 2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Facility:

Task

Title:

Job Performance Measure Worksheet Form ES-C-1 HB ROBINSON Manually Calculate an Estimated Critical Condition.

Task No.:

01006100101 JPM No.:

2008 NRC ADM RO/SRO a 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 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:

o The plant is in Mode 3 with TAVG at 547 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 the time of the trip:

o 760 ppm Boron o

Control rods at 218 steps on CB "D" o

Power at 1 00% RTP o

Burnup is at 251.57 EFPD (9056.5 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 760 ppm.

The next Criticality number is 501.

You have been directed to perform a Manual Estimated Critical Conditions calculation for the given conditions.

Task Standard:

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

Required Materials:

Calculator G P-003, Attachment 10.1 Applicable Plant Curve Book curves: Section 1, Section 2 2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1

Appendix C Job Performance Measure Form ES-C-i Worksheet 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 ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 General

References:

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

Initiating Cue:

Time Critical Task:

Validation Time:

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 2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 14 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.

Enters CB D at 218 steps. (Step 1.1)

Power Level at 100%. (Step 1.2)

Boron Concentration at 760 ppm. (Step 1.3.1)

Number of days since last Critical Data Stamp and S/D 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 760 ppm in Step 1.3.6.

Examiners Note:

Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Page 3 of 14 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 ADM RO/SRO a Start Time: ___

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

Enters Criticality number as 501.

Enters CB "D" at 218 steps. (Step 1.1)

Power Level at 1 00%. (Step 1.2)

Boron Concentration at 760 ppm. (Step 1.3.1 )

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

(Step 1.3.2)

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

Enters 760 ppm in Step 1.3.6.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 14 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, the candidate enters Integral Boron Worth as 6312.5 +/- 125 pcm in Step 1.4.

Examiners Note:

Interpolated data: BOL Value = 5750, EOL value 6875.

50% interpolation EOL-BOL, 5750 + 50% of delta (1125) 5750 + 562.5 = 6312.5 Acceptable tolerance is +/- 125 pcm.

6312.5 + 125 = 6437.5 6312.5125 = 6187.5 Comment:

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

Standard:

Using Xenon Worth Curve 2.1, candidate enters Xenon Worth at time of trip as 2687.5 +/- 25 pcm, in Step 1.5.

Examiners Note:

Interpolated data: BOL value = 2575, EOL value = 2800.

50 % interpolating EOL-BOL, = 2575 + 50% of delta (225) 2575 + 112.5 = 2687.5 2687.5 + 25 = 2712.5 2687.525 = 2662.5 Comment:

2008 NRC ADM RO/SRO a 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 ADM RO/SRO a Page 4 of 14 PERFORMANCE INFORMATION Form ES-C-1 Using Integral Boron Worth Curve 1.13, enter Integral Boron Worth.

Using Integral Boron Worth Curve 1.13, the candidate enters Integral Boron Worth as 6312.5 +/- 125 pcm in Step 1.4.

Interpolated data: BOl Value = 5750, EOl value 6875.

50% interpolation EOl-BOl, 5750 + 50% of delta (1125) 5750 + 562.5 = 6312.5 Acceptable tolerance is +/- 125 pcm.

6312.5 + 125 = 6437.5 6312.5 -125 = 6187.5 Using Xenon Worth Curve 2.1, enter Xenon Worth at time of trip.

Using Xenon Worth Curve 2.1, candidate enters Xenon Worth at time of trip as 2687.5 +/- 25 pcm, in Step 1.5.

Interpolated data: BOl value = 2575, EOl value = 2800.

50 % interpolating EOl-BOl, = 2575 + 50% of delta (225) 2575 + 112.5 = 2687.5 2687.5 + 25 = 2712.5 2687.5 - 25 = 2662.5 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 14 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 1886 +/- 25 pcm, in Step 1.6.

Examiners Note:

Power Defect Curve 1.3B (MOL) should be used to interpolate power defect for 100% power, Boron concentration of 760 ppm.

Interpolated data:

600 ppm curve = 1950 pcm, 800 ppm curve = 1870 pcm.

1950-1 870 = 80 pcm, 80/200 x160 = 64 pcm 1950-64 = 1886 pcm 1886+25= 1911 pcm 188625=1861 porn Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C

Performance Step: 5 Standard:

Examiner's Note:

Comment:

2008 NRC ADM RO/SRO a Page 5 of 14 PERFORMANCE INFORMATION Form ES-C-1 Using Power Defect Curve 1.3, enter Power Defect at time of trip.

Using Power Defect Curve 1.3, enters Power Defect at time of trip as 1886 +/- 25 pcm, in Step 1.6.

Power Defect Curve 1.3B (MOL) should be used to interpolate power defect for 100% power, Boron concentration of 760 ppm.

Interpolated data:

600 ppm curve = 1950 pcm, 800 ppm curve = 1870 pcm.

1950-1870 = 80 pcm, 80/200 x160 = 64 pcm 1950 - 64 = 1886 pcm 1886 + 25 = 1911 pcm 1886 - 25 = 1861 pcm NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 14 Form ES-C-i PERFORMANCE INFORMATION 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, 2.48, 2.5, enters Samarium Worth at time of trip as 890 +/- 5 porn in Step 1.7.

Examiners Note:

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 = 800, EOL from Curve 2.4B = 980. EOL BOL = 180 x 50% = 90.

800 + 90 = 890 890 + 5 = 895 8905 = 885 Comment:

Performance Step: 7 Using Inserted Rod Worth curves 1.6 and 1.8, enter Inserted Rod Worth at time of trip.

Standard:

Using Inserted Rod Worth curve 1.6 and 1.8, enters Inserted Rod Worth at time of trip as 5 +/- 5 pcrn in Step 1.8.

Examiners Note:

Should use Curve 1.6 per Note #3.

Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C

Performance Step: 6 Standard:

Examiner's Note:

Comment:

Performance Step: 7 Standard:

Examiner's Note:

Comment:

2008 NRC ADM RO/SRO a Page 6 of 14 PERFORMANCE INFORMATION Form ES-C-1 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 890 +/- 5 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 = 800, EOl from Curve 2.4B = 980. EOl - BOl = 180 x 50% = 90.

800 + 90 = 890 890 + 5 = 895 890 - 5 = 885 Using Inserted Rod Worth curves 1.6 and 1.8, enter Inserted Rod Worth at time of trip.

Using Inserted Rod Worth curve 1.6 and 1.8, enters Inserted Rod Worth at time of trip as 5 +/- 5 pcm in Step 1.8.

Should use Curve 1.6 per Note #3.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 8 Enter Projected Boron Concentration, temperature, and time since shutdown.

Standard:

Enters Projected Boron Concentration and temperature as 760 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:

Performance Step: 9 Enter Integral Boron Worth.

Standard:

Enters Integral Boron Worth as 6312.5 +/- 125 pcm in Step 2.4.

Examiners Note:

Should enter same value as Step 1.4, above.

Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 8 Standard:

Examiner's Note:

Comment:

Performance Step: 9 Standard:

Examiner's Note:

Comment:

2008 NRC ADM RO/SRO a Page 7 of 14 PERFORMANCE INFORMATION Form ES-C-1 Enter Projected Boron Concentration, temperature, and time since shutdown.

Enters Projected Boron Concentration and temperature as 760 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.

Enter Integral Boron Worth.

Enters Integral Boron Worth as 6312.5 +/- 125 pcm in Step 2.4.

Should enter same value as Step 1.4, above.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 10 Enter Projected Xenon Worth at Startup.

Standard:

Enters Projected Xenon Worth at Startup as 3825 +/- 50 pcm in Step 2.5.

Examiners Note:

Interpolated data from BOL Curve 2.3A (3450 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 3450 = 750 x 50% = 375.

3450 ÷ 375 = 3825 pcm.

3825 + 50 = 3875 pcm 382550 = 3775 pcm Comment:

Performance Step: 11 Enter Samarium Worth at Startup.

Standard:

Enters Samarium Worth at Startup as 965+/-5 pcm in Step 2.6.

Examiners Note:

Interpolated data: BOL from Curve 2.4A = 860, EOL from Curve 2.4B = 1070. EOL BOL = 210 x 50% = 105.

860 + 105 = 965 965 + 5 = 970 9655 = 960 Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Page 8 of 14 PERFORMANCE INFORMATION

Performance Step: 10 Enter Projected Xenon Worth at Startup.

Form ES-C-1 Standard:

Enters Projected Xenon Worth at Startup as 3825 +/- 50 pcm in Step 2.5.

Examiner's Note:

Interpolated data from BOl Curve 2.3A (3450 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 - 3450 = 750 x 50% = 375.

3450 + 375 = 3825 pcm.

3825 + 50 = 3875 pcm 3825 - 50 = 3775 pcm Comment:

Performance Step: 11 Enter Samarium Worth at Startup.

Standard:

Enters Samarium Worth at Startup as 965 +/- 5 pcm in Step 2.6.

Examiner's Note:

Interpolated data: BOl from Curve 2.4A = 860, EOl from Curve 2.4B = 1070. EOl - BOl = 210 x 50% = 105.

860 + 105 = 965 965 + 5 = 970 965 - 5 = 960 Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1

Appendix C Page 9 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 12 Enter Samarium change before equilibrium.

Standard:

Enters Samarium change before equilibrium as 0 pcm or NAs Step 2.7.

Examiners Note:

Comment:

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 673.5 pcm +1-250 pcm (423.5 to 923.5 pcm).

Examiners Note:

Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Page 9 of 14 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 12 Enter Samarium change before equilibrium.

Standard:

Enters Samarium change before equilibrium as 0 pcm or NAs Step 2.7.

Examiner's Note:

Comment:

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 = 673.5 pcm +/- 250 pcm (423.5 to 923.5 pcm).

Examiner's Note:

Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 14 Calculate and enter New Controlling Rod Worth per Step 4.1.

Standard:

Step 4.1: 5 pcm (from Step 1.8) + 673.5 pcm (from Step 3.2.5) =

678.5 pcm.

(acceptable range = 428.5 to 928.5 pcm)

Examiners Note:

Examiners Cue:

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

Comment:

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 using Curve 1.8. as listed in the table below.

Candidate value from Step Allowable Tolerance Band.

4.2.

> 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:

Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Page 10 of 14 PERFORMANCE INFORMATION Form ES-C-1

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

Standard:

Step 4.1: 5 pcm (from Step 1.8) + 673.5 pcm (from Step 3.2.5) =

678.5 pcm. (acceptable range = 428.5 to 928.5 pcm)

Examiner's Note:

Examiner's Cue:

Comment:

Performance Step: 15 Standard:

Examiner's Note:

Comment:

2008 NRC ADM RO/SRO a At Step 4.2, inform candidate: "Reactor Engineer's calculation is the same as yours."

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 worth in Step 4.1 using Curve 1.8. as listed in the table below.

Candidate value from Step Allowable Tolerance Band.

4.2.

~ 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 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 11 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 16 Enter Estimated Critical Condition data in Step 5.1.

Standard:

Enters Estimated Critical Condition data in Step 5.1 (92 steps on CB D, 760 ppm boron, 547 °F TAVG).

Examiners Note:

Comment:

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:

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 38 steps to 185 steps on Bank D.

Examiners Note:

Comment:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Page 11 of 14 PERFORMANCE INFORMATION Form ES-C-1 Performance Step: 16 Enter Estimated Critical Condition data in Step 5.1.

Standard:

Enters Estimated Critical Condition data in Step 5.1 (92 steps on CB "0",760 ppm boron, 547 OF TAVG).

Examiner's Note:

Comment:

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:

Performance Step: 18 Standard:

Examiner's Note:

Comment:

2008 NRC ADM RO/SRO a 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 38 steps to 185 steps on Bank "0".

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 12 of 14 Form ES-C-i PERFORMANCE INFORMATION 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 ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Page 12 of 14 PERFORMANCE INFORMATION Form ES-C-1 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 ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1

Appendix C Page 13 of 14 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC ADM RO/SRO a Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2008 NRC ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Page 13 of 14 VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC ADM RO/SRO a 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 ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1

Appendix C Page 14 of 14 Form ES-C-i JPM CUE SHEET Initial Conditions:

The plant is in Mode 3 with TAVG at 547 °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 the time of the trip:

o 760 ppm Boron o

Control rods at 218 steps on CB D o

Poweratl00%RTP o

Burnup is at 251.57 EFPD (9056.5 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 760 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 003, Attachment 10.1 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 ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1 Appendix C Initial Conditions:

Initiating Cue:

Page 14 of 14 JPM CUE SHEET Form ES-C-1 o

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

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

Critical Oata 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 the time of the trip:

o 760 ppm Boron o

Control rods at 218 steps on CB "0" o

Power at 100% RTP o

Burnup is at 251.57 EFPO (9056.5 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 760 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-003, Attachment 10.1 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 ADM RO/SRO a NUREG 1021, Revision 9, Supplement 1

ATTACHMENT 10.1 Page 1 of 4 ESTIMATED CRITICAL CONDITION FORM Criticality #

/

Control Operator cZ1 N &

Date 7cL44)

SSO 1.0 PREVIOuS CRITICAL CONDITION forCOt (hrs.)on 77%rSy (Date)

NOTE:

Critical data from initial Startup Physics Testing should be used when calculating the ECP if this startup is to be performed during the first 5 EFPD of the fuel cycle.

Siemens methodology accounts for the reactivity contribution associated with the difference in temperature on the integral boron worth by including the reactivity contribution into the Power Defect Curve and POWERTRAX. Therefore, integral boron worth is calculated based upon no load temperature of 547°F and Hot Zero Power (HZP) condition.

CAUTION Previous Critical Data should be from Equilibrium Conditions (i.e., Steady State Power for a minimum of 72 hrs). The use of Critical Data from non-equilibrium conditions must be adjusted or it can provide inaccurate ECP results.

An ECP following an extended mid-cycle shutdown (greater than 30 days) should consider Plutonium build in effects. Reactor Engineering should provide input for the ECP.

1.1.

Rod Position on Controlling Bank________ was 21 Steps (Critical Data Stamp) 1.2.

Power Level (Critical Data Stamp)

/1) ( %

1.3.

Boron Concentration:

1.3.1. RECORD Boron Concentration (Critical Data Stamp) 1.3.2. RECORD number of days between date of last Critical Data Stamp and start of shutdown:

0 days NOTE:

If the time between last Critical Data Stamp and shutdown is less than or equal to one day, then calculating an adjusted current boron concentration is NOT necessary.

1.3.3. IF shutdown less than or equal to one day after last Critical Data Stamp, THEN GO TO Step 1.3.6 AND RECORD Critical Data Stamp Boron Concentration as the Current Critical Boron Concentration.

GP-003 Rev. 80 Page 34 of 41 4//15LVeitr jce~

ATTACHMENT 10.1 Page 1 of 4 ESTIMATED CRITICAL CONDITION FORM Criticality # >CJ (

Control Operator ------"';;;rr--==:'---:------

Date 1f; c1~

SSO -~-'Ir-"

0=-/"'-:;;-, ~-+-~=--_

1.0 PREVIOJS CRITICAL CONDITION for 0,106 (hrs.) on --F-"----=---'-+

NOTE:

Critical data from initial Startup Physics Testing should be used when calculating the ECP if this startup is to be performed during the first 5 EFPD of the fuel cycle.

Siemens' methodology accounts for the reactivity contribution associated with the difference in temperature on the integral boron worth by including the reactivity contribution into the Power Defect Curve and POWERTRAX. Therefore, integral boron worth is calculated based upon no load temperature of 547°F and Hot Zero Power (HZP) condition.

CAUTION Previous Critical Data should be from Equilibrium Conditions (i.e., Steady State Power for a minimum of 72 hrs). The use of Critical Data from non-equilibrium conditions must be adjusted or it can provide inaccurate ECP results.

An ECP following an extended mid-cycle shutdown (greater than 30 days) should consider Plutonium build in effects. Reactor Engineering should provide input for the ECP.

NOTE:

1.1.

Rod Position on Controlling Bank'!)

(Critical Data Stamp) 1.2.

Power Level (Critical Data Stamp) was 21 g' Steps

/oc> %

1.3.

Boron Concentration:

1.3.1. RECORD Boron Concentration (Critical Data Stamp) 1.3.2. RECORD number of days between date of last Critical Data Stamp and start of shutdown:

1te; ppm o days If the time between last Critical Data Stamp and shutdown is less than or equal to one day, then calculating an adjusted current boron concentration is NOT necessary.

1.3.3. IF shutdown less than or equal to one day after last Critical Data Stamp, THEN GO TO Step 1.3.6 AND RECORD Critical Data Stamp Boron Concentration as the Current Critical Boron Concentration.

I GP-003 Rev. 80 Page 34 of 41 I

ATTACHMENT 10.1 Page 2 of 4 ESTIMATED CRITICAL CONDITION FORM 1.3.4. RECORD the observed change in RCS boron concentration per day for the last week prior to the last Critical Data Stamp (positive if increasing,

/ IA negative if decreasing).

( ),AJ (/1 ppm/day 1.3.5. CALCULATE Boron Concentration Change since last Critical Data Stamp (Multiply days in Step 1.3.2 by

/

change ppm/day in Step 1.3.4).

( ) \\) (A ppm 1.3.6. RECORD Current Critical Boron Concentration (Step 1.3.1 plus Step 1.3.5, if applicable) 1.4.

Integral Boron Worth (Curve 1.13 or POWERTRAX using

/

Current Critical Boron Concentration)

>pcm (Use curves or data based upon 547°F, HZP) 1.5.

Xenon Worth (Curve 2.1 or POWERTRAX) 1 z%g% )cm 1.6.

Power Defect Worth (Curve 1.3 or POWERTRAX)

/pcm 1.7.

Samarium Worth (Curve 2.4A, 2.4B, 2.5 or POWERTRAX) 2 pcm 1.8.

Inserted Rod Worth at Power (Curve 1.6, 1.8 or POWERTRAX) 3 f

pcm 1

IF previous critical data is NOT from equilibrium conditions, THEN contact the Reactor Engineer for Xenon Worth.

2 At the Beginning of Life (BOL) prior to reaching the equilibrium Samarium Value use Curve 2.5 or POWERTRAX data. After equilibrium Samarium concentration is reached, use Curve 2.4A (BOL) or Curve 2.4B (EOL), interpolating as necessary, or use POWERTRAX data.

IF previous rod position was greater than 128 steps on Bank D, THEN use the Full Power Rod Worth curve 1.6. For rod positions less than 128 steps on Bank D, Curve 1.8 should be used.

2.0 PROJECTED CRITICAL CONDITIONS fort(hrs.) on 2.1 Boron Concentration (Actual) ppm

/

2.2 Average Temperature (Actual) (Achieve Criticality 547°F) 2.3 Hours Since Shutdown

/...5 Hrs 2.4 Integral Boron Worth (Curve 1.13 or POWERTRAX)

(Use curves or data based upon 547°F, HZP) 2.5 Xenon Worth (Curve 2.3 or POWERTRAX)

GP-003 Rev. 80 Page 35 of 41 1.4.

1.5.

1.6.

1.7.

1.S.

2 3

ATTACHMENT 10.1 Page 2 of 4 ESTIMATED CRITICAL CONDITION FORM 1.3.4. RECORD the observed change in RCS boron concentration per day for the last week prior to the last Critical Data Stamp (positive if increasing,

/ fAA negative if decreasing).

( L,L~,LL~Lppm/day 1.3.5. CALCULATE Boron Concentration Change since last Critical Data Stamp (Multiply days in Step 1.3.2 bYA fiAI change ppm/day in Step 1.3.4).

( ) &.~ ppm 1.3.6. RECORD Current Critical Boron Concentration (Step 1.3.1 plus Step 1.3.5, if applicable)

Integral Boron Worth (Curve 1.13 or POWERTRAX using Current Critical Boron Concentration)

(Use curves or data based upon 547°F, HlP)

Xenon Worth (Curve 2.1 or POWERTRAX) 1 Power Defect Worth (Curve 1.3 or POWERTRAX)

Samarium Worth (Curve 2.4A, 2.48, 2.5 or POWERTRAX)2 Inserted Rod Worth at Power (Curve 1.6, 1.S or POWERTRAX)3 ppm 03/2-1 >pcm 4gZ~pcm

/rg?jpcm

<29 0 pcm 5

pcm IF previous critical data is NOT from equilibrium conditions, THEN contact the Reactor Engineer for Xenon Worth.

At the Beginning of Life (BOL) prior to reaching the equilibrium Samarium Value use Curve 2.5 or POWERTRAX data. After equilibrium Samarium concentration is reached, use Curve 2.4A (BOL) or Curve 2.4B (EOL), interpolating as necessary, or use POWERTRAX data.

IF previous rod position was greater than 128 steps on Bank "0", THEN use the Full Power Rod Worth Curve 1.6. For rod positions less than 128 steps on Bank "0", Curve 1.8 should be used.

2.0 PROJECTED CRITICAL CONDITIONS for~(hrs.) on 1iJ/rt1 (Date) 2.1 Boron Concentration (Actual) 7.6~ ppm 7

2.2 Average Temperature (Actual) (Achieve Criticality 547°F)

"":;;'17 OF 2.3 Hours Since Shutdown

/5 Hrs 2.4 Integral Boron Worth (Curve 1.13 or POWERTRAX)

I3lt~./:: pcm (Use curves or data based upon 547°F, HlP) 2.5 Xenon Worth (Curve 2.3 or POWERTRAX)

I GP-003 Rev. SO Page 35 of 41 I

ATTACHMENT 10.1 Page 3 of 4 ESTIMATED CRITICAL CONDITION FORM 2.6 IF Samarium Worth is at equilibrium, THEN determine Samarium worth using one of the following.

/ /

Curve 2.4A (BOL) interpolating as necessary.

(A pcm

Curve 2.4B (EOL) interpolating as necessary.

9-pcm POWERTRAX data.

pcm 2.7 IF the startup is due to a trip before equilibrium Samarium is reached, THEN add the change as determined from Curve 2.4A to 3he previous Samarium worth of Step 1,.7.

Step 1.7 nJ(A pcm + Change (Curve 2.4A) iii44 pcm pcm 3.0 REACTIVITY CHANGES FROM PREVIOUS CRITICAL TO PROJECTED CRITICAL Complete the following table as follows:

3.1 Enter the required information. Each value entered into the PREVIOUS and PROJECTED fields should be entered as POSITIVE NUMBERS.

3.2 Perform the designated calculations to determine the change in each parameter and the total change in reactivity.

Previous Action Projected Result

1. Integral Boron Worth L3fz.

Subtract g

pcm

2. Xenon Worth

?4?1Z Subtract

=..-// 37 pcm

3. Samarium Worth Subtract

=

7 pcm

4. Power Defect

/

Subtract 0

pcm

5. Change in Reactivity pcm 4.0 REACTIVITY BALANCE 4.1 New Controlling Rod Worth =

+

t 73.

Inserted Rod Worth Change in Reactivity (Step 1.8)

(Step 3.2.5)

=

PCM 4.2 Record the New Controlling Rod Wo calculated on the ECP provided by the Reactor Engineer.

PCM GP-003 Rev. 80 Page 36 of 41 ATTACHMENT 10.1 Page 3 of 4 ESTIMATED CRITICAL CONDITION FORM 2.6 IF Samarium Worth is at equilibrium, THEN determine Samarium worth using one of the following.

Curve 2.4A (BOl) interpolating as necessary.

Curve 2.4B (EOl) interpolating as necessary.

POWERTRAX data.

2.7 IF the startup is due to a trip before equilibrium Samarium is reached, THEN add the change as determined from tllA pem Jli....pcm

!VIA pcm Curve 2.4AJre previous Samarium worth of Step 1,.?

Step 1.7 A pcm + Change (Curve 2.4A) IJIA pcm = ~

pcm 3.0 REACTIVITY CHANGES FROM PREVIOUS CRITICAL TO PROJECTED CRITICAL Complete the following table as follows:

3.1 Enter the required information. Each value entered into the PREVIOUS and PROJECTED fields should be entered as POSITIVE NUMBERS.

3.2 Perform the designated calculations to determine the change in each parameter and the total change in reactivity.

Previous Action Projected Result

1. Integral Boron Worth Subtract

2. Xenon Worth Subtract

3. Samarium Worth Subtract

4. Power Defect Subtract

5. Change in Reactivity 4.0 REACTIVITY BALANCE pcm pcm pcm pcm pcm 4.1 New Controlling Rod Worth =

~

+

t 7.3. ~

Inserted Rod Worth Change in Reactivity (Step 1.8)

(Step 3.2.5)

=

b 7g~~ PCM 4.2 Record the New Controlling Rod w~calcu.lated on the ECP provided by the Reactor Engineer.

III e___

PCM I GP-003 Rev. 80 Page 36 of 41 I

ATTACHMENT 10.1 Page 4 of 4 ESTIMATED CRITICAL CONDITION FORM 4.3 IF the results of the two ECPs are not within 250 pcm of each other, THEN contact the Reactor Engineer for further actions.

4.4 New critical rod position associateduith the integral worth in Step 4.1 as determined from Curve 1.8.

7 2n Steps on Bank

.-/)

5.0 ESTIMATED CRITICAL CONDITION 5.1 Shutdown A 225 Steps*

Shutdown B 225 Steps*

Control A 225 Steps*

Control B 225 Steps*

Control C Z. c7 Steps Control D qi.- Steps Boron T-AVG

These banks shall be at 225 steps except for physics tests.

5.2 Is the position above the minimum insertion limits?

(ITS SR 3.1.6.1)

(circle one) 5.3 Is the position less than or equal to 225 steps on Bank D?

YES NO circe one) 6.0 Calculate the tolerance band of plus OR minus 500 pcm from the ECP.

6.1.1 Maximum rod position (ECP -500 pcm):/9-Steps on Bank 6.1.2 Minimum rod position (ECP + 500 pcm):,

A 2

Stepson Bank JJ 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 below. This will ensure compliance with ITS SR 3.1.6.1.

6.1.3 Record ECP completion time.

Time i1u)

Pertormed by:

i /L Approved by:

CRSS or SSO Signa ure j GP-003 Rev. 80 Page 37 of 41 4.3 4.4 ATTACHMENT 10.1 Page 4 of 4 ESTIMATED CRITICAL CONDITION FORM IF the results of the two ECPs are not within 250 pcm of each other, THEN contact the Reactor Engineer for further actions.

New critical rod position associated ~ith the integral worth in Step 4.1 as determined from Curve 1.8.

b-r Steps on Bank J) 5.0 ESTIMATED CRITICAL CONDITION 5.1 Shutdown "A" Steps*

5.2 5.3 Shutdown "B" Steps*

Control "A" Steps*

Control liB" Steps*

Control "C" Z.

Steps Control "0" G z,. Steps Boron ppm T-AVG of

These banks shall be at 225 steps except for physics tests.

Is the position above the minimum insertion limits?

(ITS SR 3.1.6.1)

Is the position less than or equal to 225 steps on Bank "D"?

@NO (circle one)

~NO

¥a'one) 6.0 Calculate the tolerance band of plus OR minus 500 pcm from the ECP.

6.1.1 Maximum rod position (ECP - 500 pcm)j<? /

j)

--+f--.s..<2i.....:>::::...--Steps on Bank _'_

6.1.2 Minimum rod position (ECP + 500 pcm): :;( (')

1\\

J Steps on Bank ~

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 below. This will ensure compliance with ITS SR 3.1.6.1.

6.1.3 Record ECP completion time.

Performed by: h, l' ~

Approved by: __

<"","",,~~~*/lJ=--..., :d)~":::--=-:fo'-j)--tif"~-=----

CRSS or SSO Sig~Ure I GP-003 Rev. 80 Time rJ(!W Page 37 of 41 I

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

HB ROBINSON Task No.:

Task

Title:

Overtime Extension Determination JPM No.:

2008 NRC ADM RO b K/A

Reference:

2.1.5 Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

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

Initial Conditions:

You are the RO.

Unit 2 is operating at 100% RTP.

Severe winter storm in the region has limited the mobility of numerous Operations personnel from traveling to the plant site.

All shifts are manned at minimum staffing levels.

Situation 1:

After multiple attempts to provide you with a relief, an RO has been located that can relieve you halfway through the 1900-0700 shift.

This is Day 4 of your working the 0700-i 900 shift (Friday).

You have been requested to stay over to cover the first 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the 19-0700 shift.

Situation 2:

The oncoming STA has notified the CRSS that he is at the Emergency Room with kidney stones and will not be available to cover the 19-07 shift tonight.

The CRSS has been successful in contacting the STA that just completed working the last 6 night shifts (19-07) and he has agreed to cover the shift.

The CRSS has asked you to evaluate this against the PLP-Oi 5 procedure requirements.

Task Standard:

Determines work hour limits that will be exceeded and notify supervision.

Required Materials:

PLP-01 5, PROGRAM FOR NUCLEAR POWER PLANT STAFF WORKING HOURS, Revision 13.

2008 NRC ADM RO b 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.:

Overtime Extension Determination JPM No.:

2.1.5 NRC Examiner:

Date:

Form ES-C-1 2008 NRC ADM RO b 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:

You are the RO.

Unit 2 is operating at 100% RTP.

Severe winter storm in the region has limited the mobility of numerous Operations personnel from traveling to the plant site.

All shifts are manned at minimum staffing levels.

Situation 1:

After multiple attempts to provide you with a relief, an RO has been located that can relieve you halfway through the 1900-0700 shift.

This is Day 4 of your working the 0700-1900 shift (Friday).

You have been requested to stay over to cover the first 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the 19-0700 shift.

Situation 2:

The oncoming ST A has notified the CRSS that he is at the Emergency Room with kidney stones and will not be available to cover the 19-07 shift tonight.

The CRSS has been successful in contacting the ST A that just completed working the last 6 night shifts (19-07) and he has agreed to cover the shift.

The CRSS has asked you to evaluate this against the PLP-015 procedure requirements.

Task Standard:

Determines work hour limits that will be exceeded and notify supervision.

Required Materials:

PLP-015, PROGRAM FOR NUCLEAR POWER PLANT STAFF WORKING HOURS, Revision 13.

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

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

References:

PLP-015, PROGRAM FOR NUCLEAR POWER PLANT STAFF WORKING HOURS Initiating Cue:

Determine any work hour limits that may be exceeded and notify supervision.

Time Critical Task:

NO Validation Time:

15 minutes 2008 NRC ADM RO b NUREG 1021, Revision 9, Supplement 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 General

References:

PLP-015, PROGRAM FOR NUCLEAR POWER PLANT STAFF WORKING HOURS Initiating Cue:

Determine any work hour limits that may be exceeded and notify supervision.

Time Critical Task:

NO Validation Time:

15 minutes 2008 NRC ADM RO b NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 6 Form ES-C-i VERIFICATION OF COMPLETION Performance Step: 1 Locates PLP-015, PROGRAM FOR NUCLEAR POWER PLANT STAFF WORKING HOURS.

Standard:

Copy of procedure obtained.

Examiner Note:

Comment:

Performance Step: 2 Using procedure, determine the limits that will be exceeded for Situation 1.

Standard:

Situation 1:

Candidate determines that Criteria 2 More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, Criteria 3 More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, and Criteria 4 More than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period will be exceeded.

Examiners Note:

Examiners Cue:

Comment:

2008 NRC ADM RO b NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 1 Standard:

Examiner Note:

Comment:

Performance Step: 2 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

2008 NRC ADM RO b Page 3 of 6 VERIFICATION OF COMPLETION Form ES-C-1 Locates PLP-015, PROGRAM FOR NUCLEAR POWER PLANT STAFF WORKING HOURS.

Copy of procedure obtained.

Using procedure, determine the limits that will be exceeded for Situation 1.

Situation 1:

Candidate determines that Criteria 2 - More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, Criteria 3 - More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, and Criteria 4 - More than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period will be exceeded.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 6 Form ES-C-i VERIFICATION OF COMPLETION Performance Step: 3 Using procedure, determine the limits that will be exceeded for Situation 2.

Standard:

Situation 2:

Candidate determines that Criteria 5 More than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in seven consecutive days.

Examiners Note:

Examiners Cue:

Comment:

Performance Step: 4 Provide the CRSS or SSO with information obtained from the procedure.

Standard:

Provides CRSS or SSO with information obtained from the procedure.

Examiners Note:

Examiners Cue:

Comment:

Termination: When the determination has been made that overtime limits will be exceeded and supervision notified.

STOP TIME:

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

Performance Step: 3 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

Performance Step: 4 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

Page 4 of 6 VERIFICATION OF COMPLETION Form ES-C-1 Using procedure, determine the limits that will be exceeded for Situation 2.

Situation 2:

Candidate determines that Criteria 5 - More than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in seven consecutive days.

Provide the CRSS or SSO with information obtained from the procedure.

Provides CRSS or SSO with information obtained from the procedure.

Termination: When the determination has been made that overtime limits will be exceeded and supervision notified.

STOP TIME:

2008 NRC ADM RO 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 RO 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 RO b NUREG 1021, Revision 9, Supplement 1 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC ADM RO 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 RO 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 RO.

Unit 2 is operating at 100% RTP.

Severe winter storm in the region has limited the mobility of numerous Operations personnel from traveling to the plant site.

All shifts are manned at minimum staffing levels.

Situation 1:

After multiple attempts to provide you with a relief, an RO has been located that can relieve you halfway through the 1900-0700 shift.

This is Day 4 of your working the 0700-1900 shift (Friday).

You have been requested to stay over to cover the first 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the 19-0700 shift.

Situation 2:

The oncoming STA has notified the CRSS that he is at the Emergency Room with kidney stones and will not be available to cover the 19-07 shift tonight.

The CRSS has been successful in contacting the STA that just completed working the last 6 night shifts (19-07) and he has agreed to cover the shift.

The CRSS has asked you to evaluate this against the PLP-01 5 procedure requirements.

INITIATING CUE:

Determine any work hour limits that may be exceeded and notify supervision.

2008 NRC ADM RO 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 RO.

INITIATING CUE:

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

Severe winter storm in the region has limited the mobility of numerous Operations personnel from traveling to the plant site.

All shifts are manned at minimum staffing levels.

Situation 1:

After multiple attempts to provide you with a relief, an RO has been located that can relieve you halfway through the 1900-0700 shift.

This is Day 4 of your working the 0700-1900 shift (Friday).

You have been requested to stay over to cover the first 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the 19-0700 shift.

Situation 2:

The oncoming ST A has notified the CRSS that he is at the Emergency Room with kidney stones and will not be available to cover the 19-07 shift tonight.

The CRSS has been successful in contacting the ST A that just completed working the last 6 night shifts (19-07) and he has agreed to cover the shift.

The CRSS has asked you to evaluate this against the PLP-015 procedure requirements.

Determine any work hour limits that may be exceeded and notify supervision.

NUREG 1021, Revision 9, Supplement 1

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

HB ROBINSON Task No.:

Task

Title:

Review EMP-022 GASEOUS WASTE JPM No.:

2008 NRC ADM SRO bi RELEASE PERMITS for completeness prior to CV pressure relief.

K/A

Reference:

2.1.4 (3.8)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

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

Initial Conditions:

You are the CRSS.

The plant is operating at 100% RTP.

Current CV pressure is 0.75 PS 1G.

Last CV pressure relief was performed 3 days ago.

Task Standard:

Determine that EMP-022, Attachment 10.2 is complete and corrected prior to CV pressure relief.

Required Materials:

EMP-022, GASEOUS WASTE RELEASE PERMITS General

References:

EMP-022 GASEOUS WASTE RELEASE PERMITS OP-921 CONTAINMENT AIR HANDLING ITS LCO 3.3.6 ODCM Table 3.10-1 item 2.a Initiating Cue:

You have been asked to review and approve a CV pressure relief permit lAW EMP-022, and to take necessary actions to conduct the release.

Time Critical Task:

NO Validation Time:

10 minutes 2008 NRC ADM SRO bi NUREG 1021, Revision 9, Supplement 1 Appendix C Facility:

Task

Title:

KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing:

Job Performance Measure Worksheet HB ROBINSON Task No.:

Review EMP-022 GASEOUS WASTE JPM No.:

RELEASE PERMITS for completeness prior to CV pressure relief.

2.1.4 (3.8)

NRC Examiner:

Date:

Form ES-C-1 2008 NRC ADM SRO b1 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:

Task Standard:

Required Materials:

General

References:

Initiating Cue:

Time Critical Task:

Validation Time:

You are the CRSS.

The plant is operating at 100% RTP.

Current CV pressure is 0.75 PSIG.

Last CV pressure relief was performed 3 days ago.

Determine that EMP-022, Attachment 10.2 is complete and corrected prior to CV pressure relief.

EMP-022, GASEOUS WASTE RELEASE PERMITS EMP-022 GASEOUS WASTE RELEASE PERMITS OP-921 CONTAINMENT AIR HANDLING ITS LCO 3.3.6 ODCM Table 3.10-1 item 2.a You have been asked to review and approve a CV pressure relief permit lAW EMP-022, and to take necessary actions to conduct the release.

NO 10 minutes 2008 NRC ADM SRO b1 NUREG 1021, Revision 9, Supplement 1

Appendix C Page 2 of 7 Form ES-C-i PERFORMANCE INFORMATION Examiners Note:

The steps in this JPM may be performed in any order.

Start Time:

Performance Step: 1 Candidate reviews EMP-022, Attachment 10.2 for completeness and setpoint data.

Standard:

Candidate identifies initials are missing for Part II SOURCE CHECK for R-i2 and refers to Note (5).

Examiners Note:

EMP-022, ATTACHMENT 10.2, PART II SOURCE CHECK IS BLANK FOR R-12.

Examiners Cue:

The RO notifies you that R-12 would not respond to the Source Check.

Comment:

Performance Step: 2 Candidate reviews Note (5) of EMP-022, Attachment 10.2.

Source check for R-i 2 required prior to each C.V. Release (ODCM Table 3.11-i item 2.b).

If R-12 fails source check, refer to Section 7.3.3 OR 7.3.4. (ITS LCO 3.3.6)

Standard:

Candidate refers to LCO 3.3.6 and applies LCO 3.3.6.A.

Candidate refers to ODCM Table 3.10-1 item 2.a and determines that the release can continue.

Candidate refers to section 7.3.3 of EMP-022 and determines that the release can continue. (This is the only portion of this step that is Critical)

Examiners Note:

Examiners Cue:

Comment:

2008 NRC ADM SRO bi NUREG 1021, Revision 9, Supplement 1 Appendix C Examiner's Note:

Page 2 of 7 PERFORMANCE INFORMATION Form ES-C-1 The steps in this JPM may be performed in any order.

Start Time: ______ _

Performance Step: 1 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

Performance Step: 2 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

2008 NRC ADM SRO b1 Candidate reviews EMP-022, Attachment 10.2 for completeness and setpoint data.

Candidate identifies initials are missing for Part II SOURCE CHECK for R-12 and refers to Note (5).

EMP-022, ATTACHMENT 10.2, PART II SOURCE CHECK IS BLANK FOR R-12.

The RO notifies you that R-12 would not respond to the Source Check.

Candidate reviews Note (5) of EMP-022, Attachment 10.2.

Source check for R-12 required prior to each C.V. Release (ODCM Table 3.11-1 item 2.b). If R-12 fails source check, refer to Section 7.3.3 OR 7.3.4. (ITS LCO 3.3.6)

Candidate refers to LCO 3.3.6 and applies LCO 3.3.6.A.

Candidate refers to ODCM Table 3.10-1 item 2.a and determines that the release can continue.

Candidate refers to section 7.3.3 of EMP-022 and determines that the release can continue. (This is the only portion of this step that is Critical)

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 7 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 Candidate enters START block of EMP-022, Section 7.3.3 logic and continues to first logic block.

Are R-l 1 and R-l 2 operable? NO Standard:

Candidate answers NO to first logic block of EMP-022, Section 7.3.3.

Examiners Note:

Examiners Cue:

Comment:

Performance Step: 4 Candidate enters second logic block of EMP-022, Section 7.3.3.

ODCM Table 3.10-i: > 30 days inoperable, report in next annual report.

Standard:

Candidate determines that R-12 has been inoperable for < 30 days based on initial conditions and continues to next logic block.

Examiners Note:

Determination is based on last CV pressure relief 3 days ago.

Examiners Cue:

Comment:

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

Performance Step: 3 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

Performance Step: 4 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

2008 NRC ADM SRO b1 Page 3 of 7 PERFORMANCE INFORMATION Form ES-C-1 Candidate enters START block of EMP-022, Section 7.3.3 logic and continues to first logic block.

Are R-11 and R-12 operable? NO Candidate answers NO to first logic block of EMP-022, Section 7.3.3.

Candidate enters second logic block of EMP-022, Section 7.3.3.

ODCM Table 3.10-1: > 30 days inoperable, report in next annual report.

Candidate determines that R-12 has been inoperable for < 30 days based on initial conditions and continues to next logic block.

Determination is based on last CV pressure relief 3 days ago.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 7 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 5 Candidate enters next logic block.

Is R-14C operable? YES.

Standard:

Candidate answers YES and determines that R-14C is operable from EMP-022, Attachment 10.2.

Examiners Note:

Examiners Cue:

Comment:

Performance Step: 6 Candidate enters next logic block.

Is sampler flow rate monitor (R-i 1) OPERABLE? YES.

Standard:

Candidate answers YES and determines that sampler flow rate monitor (R-i 1) is operable from EMP-022, Attachment 10.2.

Examiners Note:

Examiners Cue:

R-1 1 indicates as you see it.

Comment:

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

Performance Step: 5 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

Performance Step: 6 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

2008 NRC ADM SRO b1 Page 4 of 7 PERFORMANCE INFORMATION Candidate enters next logic block.

Is R-14C operable? YES.

Form ES-C-1 Candidate answers YES and determines that R-14C is operable from EMP-022, Attachment 10.2.

Candidate enters next logic block.

Is sampler flow rate monitor (R-11) OPERABLE? YES.

Candidate answers YES and determines that sampler flow rate monitor (R-11) is operable from EMP-022, Attachment 10.2.

R-11 indicates as you see it.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 7 Form ES-C.1 PERFORMANCE INFORMATION Performance Step: 7 Candidate enters next logic block.

Continue with release.

Standard:

Candidate answers YES to Continue with release and returns to EMP-022, Attachment 10.2.

Examiners Note:

Examiners Cue:

Comment:

Performance Step: 8 Candidate reviews EMP-022, Attachment 10.2 for completeness and setpoint data.

Standard:

Candidate determines R-1 2 setpoint is set more conservative.

Examiners Note:

Examiners Cue:

R-12 setpoint has been verified to be correct lAW OMM-014, 0.1.

Comment:

Termination: Terminate JPM when EMP-022 is corrected and candidate determines CV pressure relief can continue.

STOP TIME:

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

Performance Step: 7 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

Performance Step: 8 Standard:

Examiner's Note:

Examiner's Cue:

Comment:

Page 5 of 7 PERFORMANCE INFORMATION Candidate enters next logic block.

Continue with release.

Form ES-C-1 Candidate answers YES to Continue with release and returns to EMP-022, Attachment 10.2.

Candidate reviews EMP-022, Attachment 10.2 for completeness and setpoint data.

Candidate determines R-12 setpoint is set more conservative.

R-12 setpoint has been verified to be correct lAW OMM-014, 0.1.

Termination: Terminate JPM when EMP-022 is corrected and candidate determines CV pressure relief can continue.

STOP TIME:

2008 NRC ADM SRO b1 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 ADM SRO bi 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 SRO bi NUREG 1021, Revision 9, Supplement 1 Appendix C Page 6 of 7 VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC ADM SRO b1 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 b1 NUREG 1021, Revision 9, Supplement 1

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

You are the CRSS.

The plant is operating at 100% RTP.

Current CV pressure is 0.75 psig Last CV pressure relief was performed 3 days ago.

INITIATING CUE:

You have been asked to review and approve a CV pressure relief permit lAW EMP-022, and to take necessary actions to conduct the release.

2008 NRC ADM SRO bi NUREG 1021, Revision 9, Supplement 1 Appendix C Page 7 of 7 JPM CUE SHEET INITIAL CONDITIONS:

You are the CRSS.

The plant is operating at 100% RTP.

Current CV pressure is 0.75 psig Last CV pressure relief was performed 3 days ago.

Form ES-C-1 INITIATING CUE:

You have been asked to review and approve a CV pressure relief permit lAW EMP-022, and to take necessary actions to conduct the release.

2008 NRC ADM SRO b1 NUREG 1021, Revision 9, Supplement 1

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

HB ROBINSON Task No.:

01004101901 Task

Title:

Determine CVCS Blender Controls JPM No.:

2008 NRC ADM RO c Potentiometer Settings.

K/A

Reference:

G2.2.12 (3.7/4.1)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

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

Initial Conditions:

Scheduled maintenance of Boric Acid Transfer Pump A has made it necessary to swap the BAST on BLEND to BAST B.

Current RCS boron concentration is 480 ppm.

BAST B boron concentration is 21984 ppm.

Task Standard:

Calculate the proper blender setting for new BAST boron concentration.

Required Materials:

OST-021, Daily Surveillances, Revision 22 Station Curve 4.1 with Calculator and Straight Edge General

References:

OST-021, Daily Surveillances, Revision 22 Station Curve 4.1 Handouts:

OST-02i, Daily Surveillances, Revision 22 Station Curve 4.1 Initiating Cue:

The CRSS has directed you to calculate the blender settings for using BAST B on BLEND using OST-021, Section 8.6.

Time Critical Task:

NO Validation Time:

10 minutes 2008 NRC ADM RO c NUREG 1021, Revision 9, Supplement 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

HB ROBINSON Task No.:

01004101901 Task

Title:

Determine CVCS Blender Controls Potentiometer Settings.

JPM No.:

2008 NRC ADM RO c KIA

Reference:

G2.2.12 (3.7/4.1)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

x Classroom X

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

Initial Conditions:

Scheduled maintenance of Boric Acid Transfer Pump "A" has made it necessary to swap the BAST on BLEND to BAST "B".

Current RCS boron concentration is 480 ppm.

BAST "B" boron concentration is 21984 ppm.

Task Standard:

Calculate the proper blender setting for new BAST boron concentration.

Required Materials:

OST-021, Daily Surveillances, Revision 22 Station Curve 4.1 with Calculator and Straight Edge General

References:

OST-021, Daily Surveillances, Revision 22 Station Curve 4.1 Handouts:

OST-021, Daily Surveillances, Revision 22 Station Curve 4.1 Initiating Cue:

The CRSS has directed you to calculate the blender settings for using BAST "B" on BLEND using OST-021, Section 8.6.

Time Critical Task:

NO Validation Time:

10 minutes 2008 NRC ADM RO c NUREG 1021, Revision 9, Supplement 1

Appendix C Page 2 of 6 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

START TIME:

NOTE: Potentiometer settings are validated on Monday, Wednesday, and Friday OR if the BAST aligned to BLEND is changed.

The Primary Water flow rate is normally set at 100 gpm (pot setting 6.5).

Performance Step: 1 IF daily checks on FCV-i i 3A, BORIC ACID FLOW AND HFC 114, Primary WTR FLOW AUTO MODE, are required, THEN perform the following:

1.

Calculate the boric acid flow rate required for the current plant conditions:

x =

az x = boric acid flow required (gpm) y = dilution water flow (gpm) z = current RCS boron (ppm) a = current boron of the BAST aligned to Blend (ppm)

BAST aligned to Blend (A I B)

Standard:

Candidate determines the following information:

y

= 100 gpm that was given in the note.

z = 480 ppm given in the initial conditions.

a = 21984 ppm given in the initial conditions.

BAST aligned to Blend = BAST B as given in the initial conditions.

x = 2.23 gpm if calculated correctly.

Examiners Note:

All required data was given in the initial conditions or provided in the notes within the procedure.

Comment:

2008 NRC ADM RO c NUREG 1021, Revision 9, Supplement 1 Appendix C Page 2 of 6 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

STARTTIME: ___ _

NOTE: Potentiometer settings are validated on Monday, Wednesday, and Friday OR if the BAST aligned to BLEND is changed.

The Primary Water flow rate is normally set at 100 gpm (pot setting 6.5).

Performance Step: 1 Standard:

Examiner's Note:

Comment:

2008 NRC ADM RO c IF daily checks on FCV-113A, BORIC ACID FLOW AND HFC-114, Primary WTR FLOW AUTO MODE, are required, THEN perform the following:

1. Calculate the boric acid flow rate required for the current plant conditions:

x=~

a-z x = boric acid flow required (gpm) y = dilution water flow (gpm) z = current RCS boron (ppm) a = current boron of the BAST aligned to Blend (ppm)

BAST aligned to Blend (A / B)

Candidate determines the following information:

y = 100 gpm that was given in the note.

z = 480 ppm given in the initial conditions.

a = 21984 ppm given in the initial conditions.

BAST aligned to Blend = BAST "B" as given in the initial conditions.

x = 2.23 gpm if calculated correctly.

All required data was given in the initial conditions or provided in the notes within the procedure.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 6 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 2 Perform peer check of boric acid flow rate.

Standard:

Candidate will request peer check for the calculation performed.

Examiners Cue:

Inform candidate that the peer check was completed satisfactory.

Comment:

Performance Step: 3 Using Plant Curve 4.1, Determine the allowable FCV-i 1 3A potentiometer setting range by subtracting AND adding 0.5 gpm to the calculated boric acid flow rate in the previous step and RECORD.

Pot. Setting range to Standard:

2.23 gpm (Pot setting of 2.7 on FCV-i 1 3A).

2.2 gpm + 0.5 gpm = 2.7 gpm (Pot setting of 3.2 on FCV-i 1 3A).

2.2 gpm 0.5 gpm = 1.7 gpm (Pot setting of 2.1 on FCV-1 1 3A).

Pot setting range should be noted as 2.1 to 3.2.

Examiners Note:

Comment:

2008 NRC ADM RO c NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 2 Standard:

Examiner's Cue:

Comment:

Performance Step: 3 Standard:

Examiner's Note:

Comment:

2008 NRC ADM RO c Page 3 of 6 PERFORMANCE INFORMATION Perform peer check of boric acid flow rate.

Form ES-C-1 Candidate will request peer check for the calculation performed.

Inform candidate that the peer check was completed satisfactory.

Using Plant Curve 4.1, Determine the allowable FCV-113A potentiometer setting range by subtracting AND adding 0.5 gpm to the calculated boric acid flow rate in the previous step and RECORD.

Pot. Setting range to __ _

2.23 gpm (Pot setting of 2.7 on FCV-113A).

2.2 gpm + 0.5 gpm = 2.7 gpm (Pot setting of 3.2 on FCV-113A).

2.2 gpm - 0.5 gpm = 1.7 gpm (Pot setting of 2.1 on FCV-113A).

Pot setting range should be noted as 2.1 to 3.2.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 6 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 4 Perform Peer Check of the allowable FCV-i 1 3A potentiometer setting range calculation.

Standard:

Candidate will request peer check for the potentiometer readings that was obtained from Plant Curve 4.1.

Examiners Cue:

Inform candidate peer check was completed satisfactory.

Comment:

Performance Step: 5 Using the information above, verify the POTs are correctly adjusted to the most recent RCS Boron concentration.

Record Pot. Setting FCV-i 1 3A Record Pot. Setting HFC-i 14 Standard:

Candidate will not be required to adjust the potentiometers but should determine that the pot settings are as follows:

FCV-113A2.7 HFC-1 146.5 Examiners Note:

Scope of the JPM was to determine the FCV-113A setting.

Pot setting should be within the range of 2.1 to 3.2.

HFC-114 pot setting was given in the procedure note as 6.5.

Comment:

Terminating Cue:

Blender controls have been properly set for current RCS boron concentration.

STOP TIME:

2008 NRC ADM RO c NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 4 Standard:

Examiner's Cue:

Comment:

Performance Step: 5 Standard:

Examiner's Note:

Comment:

Terminating Cue:

STOP TIME: ____ _

2008 NRC ADM RO c Page 4 of 6 PERFORMANCE INFORMATION Form ES-C-1 Perform Peer Check of the allowable FCV-113A potentiometer setting range calculation.

Candidate will request peer check for the potentiometer readings that was obtained from Plant Curve 4.1.

Inform candidate peer check was completed satisfactory.

Using the information above, verify the POTs are correctly adjusted to the most recent RCS Boron concentration.

Record Pot. Setting FCV -113A Record Pot. Setting __ _

HFC-114 Candidate will not be required to adjust the potentiometers but should determine that the pot settings are as follows:

FCV-113A-2.7 HFC-114 - 6.5 Scope of the JPM was to determine the FCV-113A setting.

Pot setting should be within the range of 2.1 to 3.2.

HFC-114 pot setting was given in the procedure note as 6.5.

Blender controls have been properly set for current RCS boron concentration.

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 RO c Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2008 NRC ADM RO c NUREG 1021, Revision 9, Supplement 1 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC ADM RO c 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 ADM RO c NUREG 1021, Revision 9, Supplement 1

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

Scheduled maintenance of Boric Acid Transfer Pump A has made it necessary to swap the BAST on BLEND to BAST B.

Current RCS boron concentration is 480 ppm.

BAST B boron concentration is 21984 ppm.

INITIATING CUE:

The CRSS has directed you to calculate the blender settings for using BAST B on BLEND using OST-02i, Section 8.6.

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

Scheduled maintenance of Boric Acid Transfer Pump "A" has made it necessary to swap the BAST on BLEND to BAST "B".

Current RCS boron concentration is 480 ppm.

BAST "B" boron concentration is 21984 ppm.

INITIATING CUE:

The CRSS has directed you to calculate the blender settings for using BAST "B" on BLEND using OST-021, Section 8.6.

2008 NRC ADM RO c NUREG 1021, Revision 9, Supplement 1

8.6 Administrative Daily Checks Section 8.6 Page 1 of 2 INIT 8.6.1 IF daily checks on FCV-1 13A, BORIC ACID FLOW AND HFC-1 14, PRIMARY WTR FLOW AUTO MODE, are required, THEN PERFORM the following:

1.

CALCULATE the boric acid flow rate required for the current plant conditions:

x=jy a-z x

Where:

x = boric acid flow required (gpm) y = dilution water flow z = current RCS boron a = current boron of the BAST aligned to Blend BAST aligned to Blend 2.

PERFORM Peer Check of boric acid flow rate.

gpm /QO ppm ppm OST-021 Rev. 22 Page 23 of 26 NOTE:

Potentiometer Settings are validated on Monday, Wednesday, and Friday OR if the BAST aligned to Blend is changed. (NCR 152674)

The Primary Water flow rate is normally set for 100 gpm (Pot setting 6.5).

These checks are for administrative purposes only AND do not apply to any acceptance criteria OR Tech Specs. (NCR 77439)

NBA 8.6 Administrative Daily Checks Section 8.6 Page 1 of 2 INIT NOTE:

Potentiometer Settings are validated on Monday, Wednesday, and Friday OR if the BAST aligned to Blend is changed. (NCR 152674)

The Primary Water flow rate is normally set for 100 gpm (Pot setting 6.5).

These checks are for administrative purposes only AND do not apply to any acceptance criteria OR Tech Specs. (NCR 77439) 8.6.1 IF daily checks on FCV-113A, BORIC ACID FLOW AND HFC-114, PRIMARY WTR FLOW AUTO MODE, are required, IOST-021 THEN PERFORM the following:

1.

2.

CALCULATE the boric acid flow rate required for the current plant conditions:

Where:

x=~

a-z x =2-__ Z-3gpm x = boric acid flow required (gpm) y = dilution water flow gpm z = current RCS boron ppm a = current boron of the BAST aligned to Blend BAST aligned to Blend ppm~

AfB-Lt ~

PERFORM Peer Check of boric acid flow rate.

~

Rev. 22 Page 23 of 261

Section 8.6 Page 2 of 2 8.6.1 (Continued)

INIT 3.

Using Plant Curve 4.1, DETERMINE the allowable FCV-1 1 3A potentiometer setting range by subtracting AND adding 0.5 gpm to the calculated boric acid flow rate in the previous step AND RECORD.

Pot. setting range Z 0( toc2.-

4.

PERFORM Peer Check of the allowable FCV-1 1 3A potentiometer setting range calculation.

5.

Using the information above, VERIFY the POTs are correctly adjusted to the most recent RCS Boron concentration.

Record Pot. setting 7

FCV-113 Record Pot. setting HFC-1 1 OST-021 Rev. 22 Page 24 of 26 8.6.1 (Continued)

Section 8.6 Page 2 of 2 INIT

3.

4.

5.

IOST-021 Using Plant Curve 4.1, DETERMINE the allowable FCV-113A potentiometer setting range by subtracting AND adding 0.5 gpm to the calculated boric acid flow rate in the previous step AND RECORD..

~

Pot. setting range Z p (

to L.Jg z" PERFORM Peer Check of the allowable FCV-113A potentiometer setting range calculation.

Using the information above, VERIFY the POTs are correctly adjusted to the most recent RCS Boron concentration.

'2-", 7 Record Pot. setting ___

w __

Record Pot. setting __

6",--, _:;

FCV-113k~a HFC-11'a Rev. 22 Page 24 of 26/

9.0 RECORDS 9.1 Completed procedure, including completed partials.

10.0 ATTACHMENTS 10.1 Surveillance Test Procedure Certification and Review Form OST-021 I

Rev. 22 Page 25 of 2J 9.0 RECORDS 9.1 Completed procedure, including completed partials.

10.0 ATTACHMENTS 10.1 Surveillance Test Procedure Certification and Review Form IOST-021 Rev. 22 Page 25 of 261

ATTACHMENT 10.1 Page 1 of 1 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM Scheduled I Unscheduled (Circle one)

(If unscheduled, state reason for test and the page numbers included in partial test)

Test Performed by Test Complete:

Date__________

Time___________

Test Satisfactory: Yes / No (Circle one)

Reviewed by:

Date Shift Technical Advisor Comments: (Required if results were unsatisfactory)

Approved by:

Date Superintendent Shift Operations OST-021 Rev. 22 Page 26 of 26 ATTACHMENT 10.1 Page 1 of 1 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM Scheduled I Unscheduled (Circle one)

(If unscheduled, state reason for test and the page numbers included in partial test)

~I Test Performed by ~

Test Complete:

Date ____ _

Test Satisfactory: Yes I No (Circle one)

Reviewed by:

Time Shift Technical Advisor Comments: (Required if results were unsatisfactory)

Approved by:

Superintendent Shift Operations IOST-021 Rev. 22 Date ----

Date ----

Page 26 of 261

20 X 2OTOTHE INCH 46 1240 h

7 X

10 ircs

,.or, u. s.

KEUFFEL Lr ES5ZR Co.

)

]

T]Inrr+:Ir*+ppi TfHEfl1T

! rrnT H !ffli 1

l t

I

L1 1t1 f1 L

[

fr J

iHjIH LHJHH uHli

{Jj.i..

i l

i I

I Fli

.11

)1 I

H li t HH IH jj ij

[)

HI 1

j IiII I

ilu i!I.jIiI I

Ij It I

I (I!IiII)TiI T

iJ H1ff 1

i i1 iJ J

1LI LLI IIlHH Iji1 iIj ijj I

j 1

[L 1

11HH H

II II iH 1i1j U

1!

1ii H

I I

I L

HI 1i tHL

tII:IlIHH LHI r ii L

r 11 II tI H

Hh i I! H iI

I I

1 i 1 jIiiz il I jIi II

iTII*

II})

I I

l 1

I) l i1 il 1i{f iI j11 I

1i.j liii i1 J I I

1H1 Wi!

I Ii i iI 1

{W H

IH 1

H L

H i

L jHj 1hhI!li 1

11 IHL iLL 4

H rH Ht tI LH H

j H

jH 1

HI H

L i!

J tt tjI

iI ii i

1 J

H

itHId I

1 lj H

L H

1 iIiiH Ii 1t 1

jji j

I III iLLllI L

I Ii i

l L

Hh H 11 1 i; il:IwWLH jj;:l.j::::.

i1 1i

!i

i

!! i; i

.t.

i! ii;

!;1 :j j

jIl !;

Ii

_I

i L

b Hi L11z. Z 1. E ZL.i.z:z i

.L.

Z..E E J LTZJZ[JL 7 l

I

[

1_L_1 I :

---7 7

1 1.

-. T..

IL ri

.. w :te I

~::~ I::;:~:::'~::::r:::=~ '~::J-= ~£~~~ :~l?::lf:--;ir~~ :~:=::C:==~,=::?:~~:::, ~::::~t:~j~ :~~+=::: ~~ =\\ ~.::::: i I:** J-

~k::-' :~~:~:l::~::::::':-:~:V~~--::=~:~:::l~ :;::l.~~: __ ::-::t~f~~I~::~ :>~-i:~~ ::=i~:== *~=-:=H<.:>::\\

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

HB ROBINSON Task No.:

02351100501 Task

Title:

Review and Approve Technical JPM No.:

2008 NRC ADM SRO c Specification Surveillance.

K/A

Reference:

G2.2.12 (4.1)

G2.2.40 (4.7)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

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

Initial Conditions:

The plant is operating at 100% RTP.

OST-020, SHIFTLY SURVEILLANCES, Sections 4 and 8.4 have been completed by the Reactor Operator.

Task Standard:

Review and approve completed surveillance test.

Required Materials:

Completed OST-020, SHIFTLY SURVEILLANCES, Revision 29 General

References:

OST-020, SHIFTLY SURVEILLANCES.

Initiating Cue:

The SSO directs you to review and approve OST-020, SHIFTLY SURVEILLANCES.

Time Critical Task:

NO Validation Time:

7 minutes 2008 NRC ADM SRO c NUREG 1021, Revision 9, Supplement i Appendix C Facility:

Task

Title:

KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing:

Job Performance Measure Worksheet HB ROBINSON Review and Approve Technical Specification Surveillance.

G2.2.12 (4.1)

G2.2.40 (4.7)

Task No.:

JPM No.:

NRC Examiner:

Date:

Form ES-C-1 02351100501 2008 NRC ADM SRO c Simulated Performance:

Actual Performance:

x Classroom X

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

Initial Conditions:

The plant is operating at 100% RTP.

OST-020, SHIFTLY SURVEILLANCES, Sections 4 and 8.4 have been completed by the Reactor Operator.

Task Standard:

Review and approve completed surveillance test.

Required Materials:

Completed OST-020, SHIFTLY SURVEILLANCES, Revision 29 General

References:

OST-020, SHIFTLY SURVEILLANCES.

Initiating Cue:

The SSO directs you to review and approve OST-020, SHIFTL Y SURVEILLANCES.

Time Critical Task:

NO Validation Time:

7 minutes 2008 NRC ADM SRO c NUREG 1021, Revision 9, Supplement 1

Appendix C Page 2 of 8 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Start Time:

Performance Step: 1 Obtain completed OST-020, SHIFTLY SURVEILLANCES.

Standard:

Candidate will be given a completed copy of OST-020 with Section 4 and Section 8.4 completed.

Examiner Note:

Comment:

Performance Step: 2 Ensure that Section 4, PREREQUISITES, Steps 4.1, 4.2 and 4.3 have been signed off with the appropriate mode noted in Step

4.3. Standard

Steps are signed off with MODE 1 specified for the 07-19 and 19-07 shifts.

Examiner Note:

Comment:

2008 NRC ADM SRO c NUREG 1021, Revision 9, Supplement 1 Appendix C Page 2 of 8 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Examiner Note:

Comment:

Performance Step: 2 Standard:

Examiner Note:

Comment:

2008 NRC ADM SRO c Start Time: ___

Obtain completed OST-020, SHIFTL Y SURVEILLANCES.

Candidate will be given a completed copy of OST-020 with Section 4 and Section 8.4 completed.

Ensure that Section 4, PREREQUISITES, Steps 4.1,4.2 and 4.3 have been signed off with the appropriate mode noted in Step 4.3.

Steps are signed off with MODE 1 specified for the 07-19 and 19-07 shifts.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 8 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 Review Step 8.4.1.1.a, comparing SI Accumulator levels against the minimum and maximum levels to ensure compliance with ITS SR 3.5.1.2.

Standard:

Candidate determines that SI Accumulator A on the 19-07 Shift reading is below the minimum level allowed to meet the minimum level for ITS SR 3.5.1.2 (61% vs 61.5% minimum).

Examiners Note:

SI Accumulator A level LOW is entry into ITS LCO 3.5.1 Condition C (Restore accumulator to OPERABLE status in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ).

Comment:

Performance Step: 4 Review Step 8.4.1.1.b, comparing SI Accumulator nitrogen cover pressures against the minimum and maximum pressures to ensure compliance with ITS SR 3.5.1.3.

Standard:

Candidate determines that SI Accumulator C on the 19-07 Shift reading is above the maximum pressure allowed to meet the maximum pressure for ITS SR 3.5.1.3 (665 PSIG vs 660 PSIG maximum).

With SI Accumulator A level LOW and SI Accumulator C pressure HIGH, entry is required into ITS LCO 3.5.1 Condition E (Two or more accumulators inoperable, Enter LCO 3.0.3 immediately).

Examiners Note:

Comment:

2008 NRC ADM SRO c 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 ADM SRO c Page 3 of 8 PERFORMANCE INFORMATION Form ES-C-1 Review Step 8.4.1.1.a, comparing SI Accumulator levels against the minimum and maximum levels to ensure compliance with ITS SR 3.5.1.2.

Candidate determines that SI Accumulator "A" on the 19-07 Shift reading is below the minimum level allowed to meet the minimum level for ITS SR 3.5.1.2 (61 % vs 61.5% minimum).

SI Accumulator "A" level LOW is entry into ITS LCO 3.5.1 Condition C (Restore accumulator to OPERABLE status in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ).

Review Step 8.4.1.1.b, comparing SI Accumulator nitrogen cover pressures against the minimum and maximum pressures to ensure compliance with ITS SR 3.5.1.3.

Candidate determines that SI Accumulator "C" on the 19-07 Shift reading is above the maximum pressure allowed to meet the maximum pressure for ITS SR 3.5.1.3 (665 PSIG vs 660 PSIG maximum).

With SI Accumulator "A" level LOW and SI Accumulator "C" pressure HIGH, entry is required into ITS LCO 3.5.1 Condition E (Two or more accumulators inoperable, Enter LCO 3.0.3 immediately).

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 8 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 5 Review Step 8.4.1.2, verifying that the valves listed are in their proper safeguards position and have their control power removed to comply with ITS SR 3.5.2.1.

Standard:

All valves listed in Step 8.4.1.2 have been initialed to signify that they are in their proper position with control power removed.

Examiners Note:

Comment:

Performance Step: 6 Candidate will review Attachment 10.1, SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM and ensure that the following data is noted:

Test is SCHEDULED.

Test performed by has: INITIALS, PRINTED NAME AND DATE.

Test complete has: DATE AND TIME Standard:

Candidate will verify that all of the above information has been completed on the form.

Examiners Note:

Comment:

2008 NRC ADM SRO c 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 ADM SRO c Page 4 of 8 PERFORMANCE INFORMATION Form ES-C-1 Review Step 8.4.1.2, verifying that the valves listed are in their proper safeguards position and have their control power removed to comply with ITS SR 3.5.2.1.

All valves listed in Step 8.4.1.2 have been initialed to signify that they are in their proper position with control power removed.

Candidate will review Attachment 10.1, SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM and ensure that the following data is noted:

Test is SCHEDULED.

Test performed by has: INITIALS, PRINTED NAME AND DATE.

Test complete has: DATE AND TIME Candidate will verify that all of the above information has been completed on the form.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 8 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 7 Candidate will complete Attachment 10.1, SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM.

Test Satisfactory: YES Reviewed By: SIGNED AND DATED.

Standard:

Candidate will verify that the information above is completed.

Examiners Note:

Comment:

Performance Step: 8 Candidate will review Attachment 10.2, SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM and ensure that the following data is noted:

Test is SCHEDULED.

Test performed by has: INITIALS, PRINTED NAME AND DATE.

Test complete has: DATE AND TIME Standard:

Candidate will verify that all of the above information has been completed on the form.

Examiners Note:

Comment:

2008 NRC ADM SRO c 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 ADM SRO c Page 5 of 8 PERFORMANCE INFORMATION Form ES-C-1 Candidate will complete Attachment 10.1, SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM.

Test Satisfactory: YES Reviewed By: SIGNED AND DATED.

Candidate will verify that the information above is completed.

Candidate will review Attachment 10.2, SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM and ensure that the following data is noted:

Test is SCHEDULED.

Test performed by has: INITIALS, PRINTED NAME AND DATE.

Test complete has: DATE AND TIME Candidate will verify that all of the above information has been completed on the form.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 8 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 9 Candidate will complete Attachment iO.2, SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM.

Test Satisfactory: NO Reviewed By: SIGNED AND DATED.

Comments: COMMENTS WILL BE ANNOTATED THAT SI ACCUMULATOR A LEVEL IS LOW AND SI ACCUMULATOR C PRESSURE IS HIGH.

Standard:

Candidate will verify that the information above is completed.

Examiners Note:

Comment:

Termination: Surveillance has been reviewed and ITS LCO action statement has been entered.

STOP TIME:

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

Performance Step: 9 Standard:

Examiner's Note:

Comment:

Page 6 of 8 PERFORMANCE INFORMATION Form ES-C-1 Candidate will complete Attachment 10.2, SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM.

Test Satisfactory: NO Reviewed By: SIGNED AND DATED.

Comments: COMMENTS WILL BE ANNOTATED THAT SI ACCUMULATOR A LEVEL IS LOW AND SI ACCUMULATOR C PRESSURE IS HIGH.

Candidate will verify that the information above is completed.

Termination: Surveillance has been reviewed and ITS LCO action statement has been entered.

STOP TIME:

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

Appendix C Page 7 of 8 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC ADM SRO c 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 SRO c NUREG 1021, Revision 9, Supplement 1 Appendix C Page 7 of 8 VERIFICATION OF COMPLETION Job Performance Measure No.:

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

Appendix C Page 8 of 8 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

The plant is operating at 100% RTP.

OST-020, SHIFTLY SURVEILLANCES, Sections 4 and 8.4 have been completed by the Reactor Operator.

INITIATING CUE The SSO directs you to review and approve OST-020, SHIFTLY SURVEILLANCES.

2008 NRC ADM SRO c NUREG 1021, Revision 9, Supplement 1 Appendix C Page 8 of 8 JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS:

The plant is operating at 100% RTP.

OST-020, SHIFTL Y SURVEILLANCES, Sections 4 and 8.4 have been completed by the Reactor Operator.

INITIATING CUE The SSO directs you to review and approve OST-020, SHIFTL Y SURVEILLANCES.

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

j Pmress Energy Continuous Use H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 3 PART 9 OST-020 SHIFTLV SURVEILLANCES REVISION 29 rOST-020 Rev. 29 Page 1 of 42 IOST-020 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 PLANT OPERATING MANUAL VOLUME 3 PART 9 OST-020 SHIFTL Y SURVEILLANCES REVISION 29 Rev. 29 c

Continuous Use Page 1 of 421

SUMMARY

OF CHANGES PRR 00272479 OST-020, Rev. 29 STEP REVISION COMMENTS 882 Added a new step for the FPAO to verify aN rack mounted SCBAs are in proper physical condition to enforce the interim measure directed by Ops Directive 08-02 until NCR 00269428 determines the long term permanent resolution.

OST-020 Rev. 29 Page 2 of 42 STEP 8.8.2 IOST-020

SUMMARY

OF CHANGES PRR 00272479 OST-020, Rev. 29 REVISION COMMENTS Added a new step for the FPAO to verify all rack mounted SCBAs are in proper physical condition to enforce the interim measure directed by Ops Directive 08-02 until NCR 00269428 determines the long term permanent resolution.

Rev. 29 Page 2 of 421

TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 4

2.0 REFERENCES

4 3.0 RESPONSIBILITES 5

4.0 PREREQUISITES 5

5.0 PRECAUTIONS AND LIMITATIONS 5

6.0 SPECIAL TOOLS AND EQUIPMENT 7

7.0 ACCEPTANCE CRITERIA 7

8.0 PROCEDURE 8

8.1 Reactivity Control Systems 8

8.2 Instrumentation 10 8.3 Reactor Coolant System 21 8.4 Emergency Core Cooling Systems 32 8.5 Containment Systems 36 8.6 Plant Systems 37 8.7 Refueling Operations 38 8.8 Other 39 9.0 RECORDS 40 10.0 ATTACHMENTS 40 10.1 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM (Shift 07-19) 41 10.2 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM (Shift 19-07) 42 OST-020 I

Rev. 29 Page 3 of 42 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE............................................................................................................ 4

2.0 REFERENCES

...................................................................................................... 4 3.0 RESPONSIBILITES.............................................................................................. 5 4.0 PREREQUISITES................................................................................................. 5 5.0 PRECAUTIONS AND LIMITATIONS.................................................................... 5 6.0 SPECIAL TOOLS AND EQUIPMENT.................................................................. 7 7.0 ACCEPTANCE CRITERIA.................................................................................... 7 8.0 PROCEDURE....................................................................................................... 8 8.1 Reactivity Control Systems.............................................................................. 8 8.2 Instrumentation.............................................................................................. 10 8.3 Reactor Coolant System................................................................................ 21 8.4 Emergency Core Cooling Systems................................................................ 32 8.5 Containment Systems.................................................................................... 36 8.6 Plant Systems................................................................................................ 37 8.7 Refueling Operations..................................................................................... 38 8.8 Other.............................................................................................................. 39 9.0 RECORDS.......................................................................................................... 40 10.0 ATTACHMENTS................................................................................................. 40 10.1 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM (Shift 07-19)...................................................................................... 41 10.2 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM (Shift 19-07)...................................................................................... 42 IOST-020 Rev. 29 Page 3 of 421

1.0 PURPOSE 1.1 To provide instructions for performing ITS, TRM or ODCM required shiftly surveillances during all phases of plant operation regardless of plant mode.

2.0 REFERENCES

2.1 Improved Technical Specifications (ITS) 2.2 OMM-015, Operations Surveillance Testing 2.3 OMM-001-11, Logkeeping 2.4 OP-006, Pressurizer PORV Pneumatic System/LTOPP 2.5 OMM-024, Rod Position Channel Check 2.6 PLP-100, Technical Requirements Manual (TRM) 2.7 ODCM, Offsite Dose Calculation Manual 2.8 EST-047, Reactor Coolant Flow Test 2.9 ESR 97-00601, Channel Check Tolerances for Steam Flow at Low Power Levels.

2.10 ESR 97-00611, Rod Position Indication Drift 2.11 RNP-l/INST-1040, Revision 1, Main Steam Accuracy and Scaling Calculation 2.12 RNP-l/INST-1 128, Revision 0, FT-424 Error/Uncertainty Calculation 2.13 8S19-P-101, Station Blackout Coping Analysis Report 2.14 CR 97-02328, SR 3.1.6.2 Documentation 2.15 GP-010, Refueling 2.16 ESR 99-00220, Alternate method of determining Seal Injection flow 2.17 EC 47162, Set-Points, Uncertainty Calc change for Appendix K Uprate 2.18 LDCR 03-0002, Proposed change to LCO 3.1.7, Required Action A.1 2.19 NCR 188409, New Containment Analysis from Westinghouse OST-020 Rev. 29 Page 4 of 42 1.0 PURPOSE 1.1 To provide instructions for performing ITS, TRM or ODCM required shiftly surveillances during all phases of plant operation regardless of plant mode.

2.0 REFERENCES

2.1 Improved Technical Specifications (ITS) 2.2 OMM-015, Operations Surveillance Testing 2.3 OMM-001-11, Logkeeping 2.4 OP-006, Pressurizer PORV Pneumatic System/L TOPP 2.5 OMM-024, Rod Position Channel Check 2.6 PLP-100, Technical Requirements Manual (TRM) 2.7 ODCM, Offsite Dose Calculation Manual 2.8 EST-047, Reactor Coolant Flow Test 2.9 ESR 97-00601, Channel Check Tolerances for Steam Flow at Low Power Levels.

2.10 ESR 97-00611, Rod Position Indication Drift 2.11 RNP-IIINST-1040, Revision 1, Main Steam Accuracy and Scaling Calculation 2.12 RNP-IIINST-1128, Revision 0, FT-424 Error/Uncertainty Calculation 2.13 8S 19-P-1 01, Station Blackout Coping Analysis Report 2.14 CR 97-02328, SR 3.1.6.2 Documentation 2.15 GP-010, Refueling 2.16 ESR 99-00220, Alternate method of determining Seal Injection flow 2.17 EC 47162, Set-Points, Uncertainty Calc change for Appendix K Uprate 2.18 LDCR 03-0002, Proposed change to LCO 3.1.7, Required Action A.1 2.19 NCR 188409, New Containment Analysis from Westinghouse IOST-020 Rev. 29 Page 4 of 421

RESPONSIBILITES Operations personnel are responsible for the performance, review and approval of this test.

PREREQUISITES This revision has been verified to be the latest revision available.

The Superintendent Shift Operations has given permission to conduct this test.

RECORD plant mode which shiftly checks are being performed.

(07-1 9)MODE (19-07)MODE /

PRECAUTIONS AND LIMITATIONS Any steps not applicable shall be marked N/A and the reason(s) noted in the COMMENTS section of Attachment 10.1 or 10.2.

This procedure has been screened lAW PLP-037 criteria and determined not applicable to PLP-037.

Steps within this procedure may be performed in any sequence, unless specified.

Steps may be done concurrently between watchstations.

OST-020 Rev. 29 Page 5 of 42 3.0 3.1 4.0 4.1 4.2 4.3 5.0 5.1 5.2 5.3 5.4 INIT lid/UI dz 7

Date (

3.0 RESPONSIBILITES 3.1 Operations personnel are responsible for the performance, review and approval of this test.

4.0 PREREQUISITES 4.1 4.2 4.3 5.0 5.1 5.2 5.3 5.4 This revision has been verified to be the latest revision available.

The Superintendent Shift Operations has given permission to conduct this test.

RECORD plant mode which shiftly checks are being performed. I (07 -19)MODE _

(19-07)MODE L PRECAUTIONS AND LIMITATIONS Any steps not applicable shall be marked N/A and the reason(s) noted in the COMMENTS section of Attachment 10.1 or 10.2.

This procedure has been screened lAW PLP-037 criteria and determined not applicable to PLP-037.

Steps within this procedure may be performed in any sequence, unless specified.

Steps may be done concurrently between watchstations.

IOST-020 Rev. 29 Page 5 of 421

5.5 The foNowing guidance does NOT apply to Steam Flow instruments when turbine load is less than 20% AND only applies to RTGB instrumentation. It is NOT intended to apply to instrumentation of different types sensing the same parameter (i.e., direct reading local pressure gauge shall NOT be compared against a pressure transmitter driving a remote meter): (CR 95-02700) 5.5.1 A deviation greater than 5% of full scale is used as the OOS limit. The instrument shall be declared OOS.

5.6 Steam Flow loops are pressure compensated to account for density changes in the steam that occur from low-load to full-load operation. The calibration of the loops are set up for optimum performance at 100% of rated flow. As a result, the performance of the loops at low flows is not as accurate, and can be operable but may not meet the 5% tolerance. Based on this information, the following should be used for channel check of the redundant Steam Flow instruments: (CR 95-02700) 5.6.1 IF Turbine load is less than or equal to 20%, THEN

Steam Flow should be greater than 90% of indicated Feed Flow.

AND

The tolerance between redundant Steam Flows should be within 0.4xlO 6

pph. (ESR 97-00601) 5.6.2 IF Turbine load is greater than 20%, THEN the tolerance between redundant Steam Flow instruments should be within 5%.

5.6.3 If it appears that the 5% tolerance will not be met prior to exceeding 20%

Turbine load, THEN Engineering should be contacted to evaluate the specific situation.

QST-020 Rev. 29 Page 6 of 42 5.5 The following guidance does NOT apply to Steam Flow instruments when turbine load is less than 20% AND only applies to RTGB instrumentation. It is NOT intended to apply to instrumentation of different types sensing the same parameter (Le., direct reading local pressure gauge shall NOT be compared against a pressure transmitter driving a remote meter): (CR 95-02700) 5.5.1 A deviation greater than 5% of full scale is used as the OOS limit. The instrument shall be declared OOS.

5.6 Steam Flow loops are pressure compensated to account for density changes in the steam that occur from low-load to full-load operation. The calibration of the loops are set up for optimum performance at 100% of rated flow. As a result, the performance of the loops at low flows is not as accurate, and can be operable but may not meet the 5% tolerance. Based on this information, the following should be used for channel check of the redundant Steam Flow instruments: (CR 95-02700) 5.6.1 IF Turbine load is less than or equal to 20%, THEN Steam Flow should be greater than 90% of indicated Feed Flow.

AND The tolerance between redundant Steam Flows should be within OAx106pph. (ESR 97-00601) 5.6.2 IF Turbine load is greater than 20%, THEN the tolerance between redundant Steam Flow instruments should be within 5%.

5.6.3 If it appears that the 5% tolerance will not be met prior to exceeding 20%

Turbine load, THEN Engineering should be contacted to evaluate the specific situation.

IOST-020 Rev. 29 Page 6 of 421

6.0 SPECIAL TOOLS AND EQUIPMENT 6.1 None 7.0 ACCEPTANCE CRITERIA 7.1 All steps for the applicable Mode have been completed.

7.2 Performance of the surveillance satisfies the ITS, TRM and ODCM requirements and the OST should be considered SAT. IF the stated condition(s) is not met, THEN the applicable Action Statement is required to be entered.

7.3 The reviewing and approving authorities may accept this test lAW provisions set forth in OMM-015.

OST-020 Rev. 29 Page 7 of 42 6.0 SPECIAL TOOLS AND EQUIPMENT 6.1 None 7.0 ACCEPTANCE CRITERIA 7.1 All steps for the applicable Mode have been completed.

7.2 Performance of the surveillance satisfies the ITS, TRM and ODeM requirements and the OST should be considered SAT. IF the stated condition(s) is not met, THEN the applicable Action Statement is required to be entered.

7.3 The reviewing and approving authorities may accept this test lAW provisions set forth in OMM-015.

IOST-020 Rev. 29 Page 7 of 421

Section 8.4 Page 1 of 4 INIT INIT 07-19 19-07 8.4 Emergency Core Cooling Systems 8.4.1 IF MODE 1, 2 OR 3 shiftly checks are required, THEN PERFORM the following:

IF RCS pressure is greater than 1000 psig, THEN PERFORM the following:

a.

VERIFY Borated Water Volume in each SI Accumulator is greater than or equal to 825 ft3 (61.5%) and less than or equal to 841 ft3 (80.4%). (ITS SR 3.5.1.2)

SI Accumulator A (07-19)

SlAccumulatorB (07-19)

SlAccumulatorC (07-19) 9,çju1_

SlAccumulatorA (19-07)

(

SI Accumulator B (19-07) 7 %

SI Accumulator C (19-07)

OST-020 Rev. 29 Page 32 of 42 Section 8.4 Page 1 of 4 INIT INIT 07-19 19-07 8.4 Emergency Core Cooling Systems 8.4.1 IF MODE 1, 2 OR 3 shiftly checks are required, THEN PERFORM the following:

I OST-020

1.

IF RCS pressure is greater than 1000 psig, THEN PERFORM the following:

a.

VERIFY Borated Water Volume in each SI Accumulator is greater than or equal to 825 ft3 (61.5%) and less than or equal to 841 ft3 (80.4%). (ITS SR 3.5.1.2)

~

SIAccumulator"A" (07-19)H ~G SI Accumulator "B" SI Accumulator "C" SI Accumulator "A" SI Accumulator "B" SI Accumulator "C" Rev. 29 (07-19)~ ~ft, (07-19)M~

(19-07) K

% a,L-,

(19-07) 61 % ~

(19-07)-'4- % d~

Page 32 of 42/

b.

VERIFY Nitrogen Cover pressure in each SI Accumulator is greater than or equal to 600 psig and less than or equal to 660 psig.

SI Accumulator Afl

SI Accumulator C OST-020 Rev. 29 Page 33 of 42 8.4.1.1 (Continued)

Section 8.4 Page 2 of 4 INIT INIT 07-19 19-07 (07-19);

(07-19) psigL (07-19)/s (19-07) psig (19-07) psig (19-07) Lpsig Section 8.4 Page 2 of 4 8.4.1.1 (Continued)

INIT INIT IOST-020 07-19 19-07

b.

VERIFY Nitrogen Cover pressure in each SI Accumulator is greater than or equal to 600 psig and less than or equal to 660 psig.

(ITS SR 3.5.1.3)

SI Accumulator "A" SI Accumulator "8" SI Accumulator "c" SI Accumulator "A" SI Accumulator "8" SI Accumulator "C" Rev. 29 (07-19) 6~p~

(07-19) 6 i¥> ps~

(07-19) 65~ pSid}k (19-07) ~

psig (19-07) ~

psig

~

(2L~

Page 33 of 421

8.4.1 (Continued)

SI-862B,

SI-863A,

Sl-863B,

Sl-864A,

SI-864B,

Sl-866A,

Sl-866B,

Sl-878A,

S[-878B, RWSTto RHR RHR LOOP RECIRC RHR LOOP RECIRC RWST DISCH RWST DISCH LOOP 3 HOT LEG INJ LOOP 2 HOT LEG INJ SI DISCH CROSS CONN SI DISCH CROSS CONN Section 8.4 Page 3 of 4 INIT INIT 07-19 19-07 OST-020 Rev. 29 Page 34 of 42 2.

VERIFY the following valves are in the listed positions with Control Power to the valve operator removed.

(ITS SR 3.5.2.1)

SI-862A, RWST to RHR

Sl-862A AC Control Power Defeat Switch

Sl-862B AC Control Power Defeat Switch DefeatarLJ/LA DefeatL,cA.

Section 8.4 Page 3 of 4 8.4.1 (Continued)

INIT INIT 07-19 19-07 IOST-020

2.

VERIFY the following valves are in the listed positions with Control Power to the valve operator removed.

(ITS SR 3.5.2.1)

SI-862A, RWST to RHR SI-8628, RWST to RHR OP~~-=-

~---..40r.41 SI-863A, RHR LOOP RECIRC CLOS -----t:t:o--

SI-8638, RHR LOOP RECIRC SI-864A, RWST DISCH SI-8648, RWST DISCH SI-866A, LOOP 3 HOT LEG INJ CLOS SI-8668, LOOP 2 HOT LEG INJ SI-878A, SI DISCH CROSS CONN SI-8788, SI DISCH CROSS CONN SI-862A AC Control Power Defeat Switch SI-8628 AC Control Power Defeat Switch Rev. 29

'--="---

Defeat~

Defeat~,A-Page 34 of 421

Section 8.4 Page 4 of 4 8.4.1.2 (Continued)

INIT INIT 07-19 19-07

Sl-863A AC Control Power Defeat Switch Defe

Sl-863B AC Control Power Defeat Switch Defea

SI-864A AC Control Power Defeat Switch Defeat

SI-864B AC Control Power Defeat Switch Defeat

Sl-866A AC Control Power Defeat Switch Defeat

Sl-866B AC Control Power Defeat Switch

Sl-878A breaker on MCC-5 in CMPT No. 2C OPE 4 E-

Sl-878B breaker on MCC-6 in CMPT NO. 15C OST-020 Rev. 29 Page 35 of 42 8.4.1.2 (Continued)

IOST-020 SI-863A AC Control Power Defeat Switch SI-8638 AC Control Power Defeat Switch SI-864A AC Control Power Defeat Switch SI-8648 AC Control Power Defeat Switch SI-866A AC Control Power Defeat Switch SI-8668 AC Control Power Defeat Switch SI-878A breaker on MCC-5 in CMPT No. 2C SI-8788 breaker on MCC-6 in CMPT NO. 15C Rev. 29 Section 8.4 Page 4 of 4 INIT INIT 07-19 19-07 Defe~~

Defea~&~

Defeat4~

Defeatd~

Defeat4t:~

Defea~a opd~

OP~~

Page 35 of 421

9.0 RECORDS 9.1 The completed procedure and any partials are forwarded to Plant Records.

10.0 ATTACHMENTS 10.1 Surveillance Test Procedure Certification and Review Form (Shift 07-19) 10.2 Surveillance Test Procedure Certification and Review Form (Shift 19-07)

OST-020 Rev. 29 Page 40 of 42 9.0 RECORDS 9.1 The completed procedure and any partials are forwarded to Plant Records.

10.0 ATTACHMENTS 10.1 Surveillance Test Procedure Certification and Review Form (Shift 07-19) 10.2 Surveillance Test Procedure Certification and Review Form (Shift 19-07)

IOST-020 Rev. 29 Page 40 of 421

ATTACHMENT 10.1 Page 1 of 1 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM SHIFT 07-19 (Circle one)

(If unscheduled, state reason for test and the page numbers included in partial test) ki4als Name (Pri,çt)

.1) t Test Performed By:<4Li

/

7? L4y TestComplete:

Date:7(ii?

7 Time:_________

Test Satisfactory: Yes I No (Circle one)

Reviewed by:

Shift Technical Advisor Date Comments: (Required if results were unsatisfactory)

Approved by:

Superintendent Shift Operations Date OST-020 Rev. 29 Page 41 of 42 ATTACHMENT 10.1 Page 1 of 1 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM SHIFT 07-19 6d;;dule~nscheduled (Circle one)

(If unscheduled, state reason for test and the page numbers included in partial test)

I~

Test Performed By:..c.

Test Complete:

Date:Jr;JAy Time:----L;i--=--.!(J~_1A_V_

Test Satisfactory: Yes / No (Circle one)

Reviewed by:

Shift Technical Advisor Date Comments: (Required if results were unsatisfactory)

Approved by:

Superintendent Shift Operations Date IOST-020 Rev. 29 Page 41 of 421

ATTACHMENT 10.2 Page 1 of 1 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM SHIFT 19-07 Unscheduled (Circle one)

(If unscheduled, state reason for test and the page numbers included in partial test)

InIs Nan (Print) at Test Peormed By:

Test Complete:

Date:__________

Time: fJ j1)

Test Satisfactory: Yes / No (Circle ne)

Reviewed by:

Shift Technical Advisor Date Comments: (Required if results were unsatisfactory)

Approved by:

Superintendent Shift Operations Date OST-020 Rev. 29 Page 42 of 42 ATTACHMENT 10.2 Page 1 of 1 SURVEILLANCE TEST PROCEDURE CERTIFICATION AND REVIEW FORM SHIFT 19-07

~

Unscheduled (Circle one)

(If unscheduled, state reason for test and the page numbers included in partial test)

In~

Test Performed By: ~

Test Complete:

Test Satisfactory:

Reviewed by:

Date:~

Yes / No (Circle one)

Time:

Shift Technical Advisor Comments: (Required if results were unsatisfactory)

Approved by:

Date Superintendent Shift Operations Date IOST-020 Rev. 29

~Jrtj

~

Page 42 of 421

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

HB ROBINSON Task No.:

Task

Title:

Determine ALARA dose.

JPM No.:

2008 NRC ADM RO/SRO d K/A

Reference:

G2.3.4 (3.2/3.7)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

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

Initial Conditions:

The plant is operating at 100% RTP.

HVE-6A fan dampers have failed and must be adjusted to support continued plant operation.

A team has been assembled to determine options for successful job performance while maintaining overall dose ALARA.

SELECTION PATH-A PATH-B Pathway Dose Rate 430 mR/hr 210 mR/hr Pathway Transit Time 1 person 6

1 person 15 to Job Site (minutes) 2 people 2

2 people 5

Job Site Dose Rate 100 mR/hr Job Site Work Duration 1 person 40 (minutes) 2 people 15 Pathway Transit Time 1 person 6

1 person 15 from Job Site (minutes) 2 people 2

2 people 5

Task Standard:

Determine ALARA dose for the stated job is to use 2 workers transiting via Path A. Determine that each worker will receive 53.7 +/- 5 mRem.

Required Materials:

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

HB ROBINSON Task

Title:

Determine ALARA dose.

KIA

Reference:

G2.3.4 (3.2/3.7)

Task No.:

JPM No.:

2008 NRC ADM RO/SRO d Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

x Classroom X

Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

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

Initial Conditions:

The plant is operating at 100% RTP.

HVE-6A fan dampers have failed and must be adjusted to support continued plant operation.

A team has been assembled to determine options for successful job performance while maintaining overall dose ALARA.

SELECTION PATH-A PATH-B Pathway Dose Rate 430 mRlhr 210 mRlhr Pathway Transit Time 1 person - 6 1 person - 15 to Job Site (minutes) 2 people - 2 2 people - 5 Job Site Dose Rate 100 mRlhr Job Site Work Duration 1 person - 40 (minutes) 2 people -15 Pathway Transit Time 1 person - 6 1 person - 15 from Job Site (minutes) 2 people - 2 2 people - 5 Task Standard:

Determine ALARA dose for the stated job is to use 2 workers transiting via Path A. Determine that each worker will receive 53.7 +/- 5 mRem.

Required Materials:

Calculator 2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1

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

References:

Handouts:

Initiating Cue:

Using the data given, determine the recommended path to the job site, the number of workers necessary to effectively complete the job and keep radiation dose ALARA, and the dose each worker will receive.

Time Critical Task:

NO Validation Time:

30 minutes 2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1 Appendix C General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

Job Performance Measure Worksheet Form ES-C-1 Using the data given, determine the recommended path to the job site, the number of workers necessary to effectively complete the job and keep radiation dose ALARA, and the dose each worker will receive.

NO 30 minutes 2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 10 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Start Time:

Performance Steps may be performed in any order.

Performance Step: 1 Determine Transit dose to the job site for 1 worker via PATH A.

Standard:

Determines that 1 worker transiting via PATH A will receive 43 +/-

2.2 mRem entering the job site.

(430 mR/hr) x (1 hr/60 mm.) x 6 mm. = 43 mRem Tolerance band is 40.8 to 45.2 mRem Examiners Note:

Comment:

Performance Step: 2 Determine Transit dose to the job site for 2 workers via PATH A.

Standard:

Determines that 2 workers transiting via PATH A will receive 28.7

+/- 1.5 mRem entering the job site.

(430 mR/hr) x (1 hr/60 mm.) x 2 mm. x 2 = 28.7 mRem Tolerance band is 27.2 to 30.2 mRem Examiners Note:

Comment:

2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1 Appendix C Page 3 of 10 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 ADM RO/SRO d Start Time: ___ _

Performance Steps may be performed in any order.

Determine Transit dose to the job site for 1 worker via PATH A.

Determines that 1 worker transiting via PATH A will receive 43 +/-

2.2 mRem entering the job site.

(430 mR/hr) x (1 hr/60 min.) x 6 min. = 43 mRem Tolerance band is 40.8 to 45.2 mRem Determine Transit dose to the job site for 2 workers via PATH A.

Determines that 2 workers transiting via PATH A will receive 28.7

+/- 1.5 mRem entering the job site.

(430 mR/hr) x (1 hr/60 min.) x 2 min. x 2 = 28.7 mRem Tolerance band is 27.2 to 30.2 mRem NUREG 1021, Revision 9, Supplement 1

Appendix C Page 4 of 10 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 Determine work site dose for 1 worker.

Standard:

Determines that 1 worker periorming job will receive 66.7 +/- 3.3 mRem.

(100 mR/hr) x (1 hr!60 mm.) x 40 mm. = 66.7 mRem Tolerance band is 63.4 to 70 mRem Examiners Note:

Comment:

Performance Step: 4 Determine work site dose for 2 workers.

Standard:

Determines that 2 workers performing job will receive 50.0 +/- 2.5 mRem.

(100 mR/hr) x (1 hr/60 mm.) x 15 mi x 2 = 50.0 mRem Tolerance band is 47.5 to 52.5 mRem Examiners Note:

Comment:

2008 NRC ADM ROISRO d 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 ADM RO/SRO d Page 4 of 10 PERFORMANCE INFORMATION Determine work site dose for 1 worker.

Form ES-C-1 Determines that 1 worker performing job will receive 66.7 +/- 3.3 mRem.

(100 mR/hr) x (1 hr/60 min.) x 40 min. = 66.7 mRem Tolerance band is 63.4 to 70 mRem Determine work site dose for 2 workers.

Determines that 2 workers performing job will receive 50.0 +/- 2.5 mRem.

(100 mR/hr) x (1 hr/60 min.) x 15 min. x 2 = 50.0 mRem Tolerance band is 47.5 to 52.5 mRem NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 10 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 5 Determines dose received to exit work site via PATH A.

Standard:

Determines that 1 worker transiting via PATH A will receive 43 +/-

2.2 mRem to exit the job site.

(430 mR/hr) x (1 hrI6O mm.) x 6 mm. = 43 mRem Tolerance band is 40.8 to 45.2 mRem Determines that 2 workers transiting via PATH A will receive 28.7

+/- 1.5 mRem to exit the job site.

(430 mR/hr) x (1 hr!60 mm.) x 2 mm. x 2 = 28.7 mRem Tolerance band is 27.2 to 30.2 mRem Examiners Note:

Comment:

Performance Step: 6 Determine dose received for entire job if PATH A is used.

Standard:

Determines that to perform job using PATH A will result in 152.7 mRem for 1 worker and 107.4 mRem for 2 workers.

1 worker: (43) + (66.7) + (43) = 152.7 mRem dose.

Tolerance band is 145 to 160.4 mRem 2 workers: (28.7) + (50) + (28.7) = 107.4 mRem dose.

Tolerance band is 101.9 to 112.9 mRem (50.95 to 56.45 mRem to each worker)

Examiners Note:

Comment:

2008 NRC ADM RO/SRO d 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 ADM RO/SRO d Page 5 of 10 PERFORMANCE INFORMATION Form ES-C-1 Determines dose received to exit work site via PATH A.

Determines that 1 worker transiting via PATH A will receive 43 +/-

2.2 mRem to exit the job site.

(430 mR/hr) x (1 hr/60 min.) x 6 min. = 43 mRem Tolerance band is 40.8 to 45.2 mRem Determines that 2 workers transiting via PATH A will receive 28.7

+/- 1.5 mRem to exit the job site.

(430 mR/hr) x (1 hr/60 min.) x 2 min. x 2 = 28.7 mRem Tolerance band is 27.2 to 30.2 mRem Determine dose received for entire job if PATH A is used.

Determines that to perform job using PATH A will result in 152.7 mRem for 1 worker and 107.4 mRem for 2 workers.

1 worker: (43) + (66.7) + (43) = 152.7 mRem dose.

Tolerance band is 145 to 160.4 mRem 2 workers: (28.7) + (50) + (28.7) = 107.4 mRem dose.

Tolerance band is 101.9 to 112.9 mRem (50.95 to 56.45 mRem to each worker)

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 6 of 10 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 7 Determine Transit dose to the job site for 1 worker via PATH B.

Standard:

Determines that 1 worker transiting via PATH B will receive 52.5

+/- 2.6 mRem entering the job site.

(210 mR/hr) x (1 hr/60 mm.) x 15 mi

= 52.5 mRem Tolerance band is 49.9 to 55.1 mRem Examiners Note:

Comment:

Performance Step: 8 Determine Transit dose to the job site for 2 workers via PATH 8.

Standard:

Determines that 2 workers transiting via PATH B will receive 35.0

+/- 1.8 mRem entering the job site.

(210 mR/hr) x (1 hr/60 mm.) x 5 mm. x 2 = 35 mRem Tolerance band is 33.2 to 36.8 mflem Examiners Note:

Comment:

2008 NRC ADM RO/SRO d 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 ADM RO/SRO d Page 6 of 10 PERFORMANCE INFORMATION Form ES-C-1 Determine Transit dose to the job site for 1 worker via PATH B.

Determines that 1 worker transiting via PATH B will receive 52.5

+/- 2.6 mRem entering the job site.

(210 mR/hr) x (1 hr/60 min.) x 15 min. = 52.5 mRem Tolerance band is 49.9 to 55.1 mRem Determine Transit dose to the job site for 2 workers via PATH B.

Determines that 2 workers transiting via PATH B will receive 35.0

+/- 1.8 mRem entering the job site.

(210 mR/hr) x (1 hr/60 min.) x 5 min. x 2 = 35 mRem Tolerance band is 33.2 to 36.8 mRem NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 10 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 9 Determines dose received to exit work site via PATH B.

Standard:

Determines that 1 worker transiting via PATH B will receive 52.5

+/- 2.6 mRem exiting the job site.

(210 mR/hr) x (ihrI6O mm.) x 15 mm. = 52.5 mRem Tolerance band is 49.9 to 55.1 mRem Determines that 2 workers transiting via PATH B will receive 35.0

+/- 1.8 mRem exiting the job site.

(210 mR/hr) x (1 hr/60 mm.) x 5 mm. x 2 = 35 mRem Tolerance band is 33.2 to 36.8 mRem Examiners Note:

Comment:

Performance Step: 10 Determine dose received for entire job if PATH B is used.

Standard:

Determines that to perform job using PATH B will result in 171.7 mRem for 1 worker and 120 mRem for 2 workers.

1 worker: (52.5) + (66.7) + (52.5) = 171.7 mRem dose.

2 workers: (35) + (50) + (35) = 120 mRem dose. (60 mRem to each worker)

Examiners Note:

Comment:

2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1 Appendix C Performance Step: 9 Standard:

Examiner's Note:

Comment:

Page 7 of 10 PERFORMANCE INFORMATION Form ES-C-1 Determines dose received to exit work site via PATH B.

Determines that 1 worker transiting via PATH B will receive 52.5

+/- 2.6 mRem exiting the job site.

(210 mR/hr) x (1 hr/60 min.) x 15 min. = 52.5 mRem Tolerance band is 49.9 to 55.1 mRem Determines that 2 workers transiting via PATH B will receive 35.0

+/- 1.8 mRem exiting the job site.

(210 mR/hr) x (1 hr/60 min.) x 5 min. x 2 = 35 mRem Tolerance band is 33.2 to 36.8 mRem

Performance Step: 10 Determine dose received for entire job if PATH B is used.

Standard:

Determines that to perform job using PATH B will result in 171.7 mRem for 1 worker and 120 mRem for 2 workers.

Examiner's Note:

Comment:

2008 NRC ADM RO/SRO d 1 worker: (52.5) + (66.7) + (52.5) = 171.7 mRem dose.

2 workers: (35) + (50) + (35) = 120 mRem dose. (60 mRem to each worker)

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 10 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 11 Determine lowest possible ALARA dose for job and PATH taken.

Standard:

Candidate determines that the lowest dose received is to perform the job with 2 workers transiting to and from the job using PATH A.

Examiners Note:

Comment:

Terminating Cue:

Candidate determines lowest dose received and PATH used.

STOP TIME:

2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1 Appendix C Page 8 of 10 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 11 Determine lowest possible ALARA dose for job and PATH taken.

Standard:

Candidate determines that the lowest dose received is to perform the job with 2 workers transiting to and from the job using PATH A.

Examiner's Note:

Comment:

Terminating Cue:

Candidate determines lowest dose received and PATH used.

STOP TIME:

2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1

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

2008 NRC ADM RO/SRO d Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1 Appendix C Page 9 of 10 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.:

2008 NRC ADM RO/SRO d 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 ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 10 Form ES-C-i JPM CUE SHEET Initial Conditions:

The plant is operating at 100% RTP.

HVE-6A fan dampers have failed and must be adjusted to support continued plant operation.

A team has been assembled to determine options for successful job performance while maintaining overall dose ALARA.

SELECTION PATH-A PATH-B Pathway Dose Rate 430 mR/hr 210 mR/hr Pathway Transit Time 1 person 6

1 person 15 to Job Site (minutes) 2 people 2

2 people 5

Job Site Dose Rate 100 mR/hr Job Site Work Duration 1 person 40 (minutes) 2 people 15 Pathway Transit Time 1 person 6

1 person 15 from Job Site (minutes) 2 people 2

2 people 5

Recommended PATH Number of Workers Dose Received by each worker Initiating Cue:

Using the data given, determine the recommended path to the job site, the number of workers necessary to effectively complete the job and keep radiation dose ALARA, and the dose each worker will receive.

2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1 Appendix C Initial Conditions:

Initiating Cue:

Page 10 of 10 JPM CUE SHEET The plant is operating at 100% RTP.

Form ES-C-1 HVE-6A fan dampers have failed and must be adjusted to support continued plant operation.

A team has been assembled to determine options for successful job performance while maintaining overall dose ALARA.

SELECTION PATH-A PATH-B Pathway Dose Rate 430 mRlhr 210 mRlhr Pathway Transit Time 1 person - 6 1 person -15 to Job Site (minutes) 2 people - 2 2 people - 5 Job Site Dose Rate 100 mRlhr Job Site Work Duration 1 person - 40 (minutes) 2 people -15 Pathway Transit Time 1 person - 6 1 person -15 from Job Site (minutes) 2 people - 2 2 people - 5 Recommended PATH Number of Workers Dose Received by each worker Using the data given, determine the recommended path to the job site, the number of workers necessary to effectively complete the job and keep radiation dose ALARA, and the dose each worker will receive.

2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1

Appendix C Page 10 of 10 Form ES-C-i JPM CUE SHEET Initial Conditions:

The plant is operating at 100% RP.

HVE-6A fan dampers have failed and must be adjusted to support continued plant operation.

A team has been assembled to determine options for successful job performance while maintaining overall dose ALARA.

SELECTION PATH-A PATH-B Pathway Dose Rate 430 mR/hr 210 mR/hr Pathway Transit Time 1 person 6

1 person 15 to Job Site (minutes) 2 people 2

2 people 5

Job Site Dose Rate 100 mRlhr Job Site Work Duration 1 person 40 (minutes) 2 people 15 Pathway Transit Time 1 person 6

1 person 15 from Job Site (minutes) 2 people 2

2 people 5

Recommended PATH PATH A Number of Workers 2 Workers Dose Received by 53.7 mR per worker each worker (50.95 to 56.45 mR per worker)

Initiating Cue:

Using the data given, determine the recommended path to the job site, the number of workers necessary to effectively complete the job and keep radiation dose ALARA, and the dose each worker will receive.

2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1 Appendix C Initial Conditions:

Initiating Cue:

Page 10 of 10 JPM CUE SHEET Form ES-C-1 HP15 e

ke~

The plant is operating at 1 00% ~P.

HVE-6A fan dampers have failed and must be adjusted to support continued plant operation.

A team has been assembled to determine options for successful job performance while maintaining overall dose ALARA.

SELECTION PATH-A PATH-B Pathway Dose Rate 430 mR/hr 210 mRlhr Pathway Transit Time 1 person - 6 1 person -15 to Job Site (minutes) 2 people - 2 2 people - 5 Job Site Dose Rate 100 mRlhr Job Site Work Duration 1 person - 40 (minutes) 2 people -15 Pathway Transit Time 1 person - 6 1 person -15 from Job Site (minutes) 2 people - 2 2 people - 5 Recommended PATH PATH A Number of Workers 2 Workers Dose Received by 53.7 mR per worker each worker (50.95 to 56.45 mR per worker)

Using the data given, determine the recommended path to the job site, the number of workers necessary to effectively complete the job and keep radiation dose ALARA, and the dose each worker will receive.

2008 NRC ADM RO/SRO d NUREG 1021, Revision 9, Supplement 1

elf Selection PATH-A Dose PATH-B Dose Pathway Dose 430 mR/hr 210 mR/hr Rate Pathway 1 person 6

1 person 43 1 person 15 1 person

Transit Time /

minutes mR minutes 52.5 mR Dose to Job 2 people 2 2 people

2 people 5

2 people 35 Site minutes 28.7 mR minutes mR Job Site Dose 100 mR/hr Rate Job Work Site 1 person 40 1 person 66.7 mR minutes 2 people 15 2 people 50 mR minutes Pathway 1 person 6

1 person 43 1 person 15 1 person

Transit Time /

minutes mR minutes 52.5 mR Dose from Job 2 people 2 2 people

2 people 5

2 people 35 Site minutes 28.7 mR minutes mR Total Dose 1 person 152 7 mR 1 person 171.7 mR 2 people 107.4 mR 2 people 120 mR ALARA Dose PATH-A using 2 people 107.4 mR

V'\\5l;J ~

.v Selection PATH-A Dose PATH-B Dose Pathway Dose 430 mR/hr 210 mR/hr Rate Pathway 1 person - 6 1 person - 43 1 person -15 1 person-Transit Time I minutes mR minutes 52.5 mR Dose to Job 2 people - 2 2 people-2 people - 5 2 people - 35 Site minutes 28.7 mR minutes mR Job Site Dose 100 mR/hr Rate Job Work Site 1 person - 40 1 person - 66.7 mR minutes 2 people -15 2 people - 50 mR minutes Pathway 1 person - 6 1 person - 43 1 person -15 1 person-Transit Time I minutes mR minutes 52.5 mR Dose from Job 2 people - 2 2 people-2 people - 5 2 people - 35 Site minutes 28.7 mR minutes mR Total Dose 1 person -1527 mR 1 person - 171.7 mR 2 people - 107.4 mR 2 people - 120 mR ALARA Dose PATH-A using 2 people - 107.4 mR

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 ADM SRO e K/A

Reference:

G2.4.41 (2.9/4.6)

Exam inee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Actual Performance:

X Classroom X

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

Initial Conditions:

The plant was operating at 100% RTP with a CV Pressure Relief in progress when a grid transient caused a Turbine Generator lockout.

During the grid transient, the Startup Transformer was lost.

The Reactor did NOT trip on interlock and could NOT be tripped from the Control Room.

Operators were dispatched and successfully opened the Reactor Trip Breakers from the Rod Drive MG Set Room at 1425 today.

The Reactor is now tripped and the crew is progressing through FRP-S.1.

480V Bus E-i is deenergized and EDG A CANNOT be started.

480V Bus E-2 is powered from EDG B.

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 the event as a SITE AREA EMERGENCY, per SS 2.1.

Required Materials:

EPCLA-01, EMERGENCY CONTROL, Revision 25 EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices EPNOT-0i, CR/EOF EMERGENCY COMMUNICATOR, Revision 28 2008 NRC ADM SRO e 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 ADM SRO e 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:

The plant was operating at 100% RTP with a CV Pressure Relief in progress when a grid transient caused a Turbine Generator lockout.

During the grid transient, the Startup Transformer was lost.

The Reactor did NOT trip on interlock and could NOT be tripped from the Control Room.

Operators were dispatched and successfully opened the Reactor Trip Breakers from the Rod Drive MG Set Room at 1425 today.

The Reactor is now tripped and the crew is progressing through FRP-S.1.

480V Bus E-1 is deenergized and EDG "A" CANNOT be started.

480V Bus E-2 is powered from EDG "B".

Weather conditions: Wind direction from 1 00 degrees, Wind Speed is 3 MPH, Stability Class is D, Precipitation is Zero.

You are the SSO.

Task Standard:

Identifies the event as a SITE AREA EMERGENCY, per SS 2.1.

Required Materials:

EPCLA-01, EMERGENCY CONTROL, Revision 25 EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices EPNOT-01, CR/EOF EMERGENCY COMMUNICATOR, Revision 28 2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1

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

References:

EPCLA-0i, EMERGENCY CONTROL, Revision 25 EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices EPNOT-0i, CRIEOF EMERGENCY COMMUNICATOR, Revision 28 Handouts:

EPCLA-0i, EMERGENCY CONTROL, Revision 25 EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices EPNOT-O1, CR/EOF EMERGENCY COMMUNICATOR, Revision 28 Initiating Cue:

Classify the event lAW the EAL matrices. Upon completion of event classification, inform the Examiner.

Time Critical Task:

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

Validation Time:

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

References:

EPCLA-01, EMERGENCY CONTROL, Revision 25 Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices EPNOT-01, CRlEOF EMERGENCY COMMUNICATOR, Revision 28 EPCLA-01, EMERGENCY CONTROL, Revision 25 EPCLA-04, EMERGENCY ACTION LEVEL TECHNICAL BASES DOCUMENT EAL Matrices EPNOT-01, CR/EOF EMERGENCY COMMUNICATOR, Revision 28 Classify the event lAW the EAL matrices. Upon completion of event classification, inform the Examiner.

YES (Emergency classification is a 15 minute time critical task) 12 minutes 2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1

Appendix C Page 3 of 14 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

START TIME:

CRITICAL TASK START TIME FOR EAL CLASSIFICATION:

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-O1.

Comment:

2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1 Appendix C Page 3 of 14 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with an asterisk)

STARTTIME: ___ _

CRITICAL TASK START TIME FOR EAL CLASSIFICATION: ___

Performance Step: 1 Standard:

Examiner's Note:

Comment:

Performance Step: 2 Standard:

Examiner's Note:

Comment:

2008 NRC ADM SRO e 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 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 3 Evaluate ALL CONDITIONS Matrix per EPCLA-O1 (Step 8.3.1).

Standard:

Candidate reviews and evaluates ALL CONDITIONS Matrix.

Examiners Note:

Comment:

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

Standard:

Candidate reviews and evaluates HOT CONDITIONS Matrix.

Examiners Note:

Comment:

2008 NRC ADM SRO e 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 ADM SRO e Page 4 of 14 PERFORMANCE INFORMATION Form ES-C-1 Evaluate ALL CONDITIONS Matrix per EPCLA-01 (Step 8.3.1).

Candidate reviews and evaluates ALL CONDITIONS Matrix.

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

Candidate reviews and evaluates HOT CONDITIONS Matrix.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 5 of 14 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)

Category 2, RPS Failure:

Failure of Reactor Protection System instrumentation to complete or initiate an automatic reactor trip once a Reactor Protection System setpoint has been exceeded and manual trip was not successful.

SS2.1:

Indication(s) exist that automatic and manual trip (initiated from the RTGB) failed to generate a negative SUR and prompt decrease in reactor power <5% after any RPS setpoint is exceeded.

Comment:

CRITICAL TASK STOP TIME FOR EAL CLASSIFICATION:

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

Performance Step: 5 Standard:

Examiner's Note:

Comment:

Page 5 of 14 PERFORMANCE INFORMATION Form ES-C-1 Select EAL condition conforming to the available information.

Candidate selects SITE AREA EMERGENCY.

Site Area Emergency based on the following:

HOT CONDITIONS - EAL Matrix (Sheet 2 of 3)

Category 2, RPS Failure:

Failure of Reactor Protection System instrumentation to complete or initiate an automatic reactor trip once a Reactor Protection System setpoint has been exceeded and manual trip was not successful.

SS2.1:

Indication(s) exist that automatic and manual trip (initiated from the RTGB) failed to generate a negative SUR and prompt decrease in reactor power < 5% after any RPS setpoint is exceeded.

CRITICAL TASK STOP TIME FOR EAL CLASSIFICATION: ___

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

Appendix C Page 6 of 14 Form ES-C-i PERFORMANCE INFORMATION CRITICAL TASK START TIME FOR NOTIFICATION:

Performance Step: 6 Candidate completes the EAL classification and informs the Examiner.

Standard:

Candidate informs the examiner that he has completed the event classification.

Examiners Cue:

When candidate is complete with the EAL classification cue the candidate to manually complete an Emergency Notification Form and submit it to the SEC.

The clock starts when you have completed the classification.

Comment:

2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1 Appendix C Page 6 of 14 PERFORMANCE INFORMATION Form ES-C-1 CRITICAL TASK START TIME FOR NOTIFICATION: ___

Performance Step: 6 Standard:

Examiner's Cue:

Comment:

2008 NRC ADM SRO e Candidate completes the EAL classification and informs the Examiner.

Candidate informs the examiner that he has completed the event classification.

When candidate is complete with the EAL classification cue the candidate to manually complete an Emergency Notification Form and submit it to the SEC.

The clock starts when you have completed the classification.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 7 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 7 Obtain EPNOT-0i, Attachment 10.8.

Standard:

Copies Attachment from procedure or pulls it from a file.

Examiners Note:

The Evaluator may provide Attachment 10.8 after the candidate demonstrates that they know how to locate procedures.

Comment:

Performance Step: 8 Enter Line 1 information.

Standard:

Marks DRILL and Message # 1.

Examiners Note:

Comment:

Performance Step: 9 Enter Line 2 information.

Standard:

Marks INITIAL.

Examiners Note:

Comment:

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

Performance Step: 7 Standard:

Examiner's Note:

Comment:

Performance Step: 8 Standard:

Examiner's Note:

Comment:

Performance Step: 9 Standard:

Examiner's Note:

Comment:

2008 NRC ADM SRO e Page 7 of 14 PERFORMANCE INFORMATION Obtain EPNOT -01, Attachment 10.8.

Form ES-C-1 Copies Attachment from procedure or pulls it from a file.

The Evaluator may provide Attachment 10.8 after the candidate demonstrates that they know how to locate procedures.

Enter Line 1 information.

Marks DRILL and Message # 1.

Enter Line 2 information.

Marks INITIAL.

NUREG 1021, Revision 9, Supplement 1

Appendix C Page 8 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 10 Enter Line 3 information.

Standard:

Enters H.B. Robinson as the Site and enters CONFIRMATION PHONE NUMBER.

Examiners Cue:

When candidate requests the ERO phone list, tell him the number is 843-383-3685.

Comment:

Performance Step: 11 Enter Line 4 information.

Standard:

Marks SITE AREA EMERGENCY, and lists SS2.1 as determined in Performance Step 5 and a description of the event classification as listed on the EAL matrices.

Examiners Note:

Comment:

Performance Step: 12 Enter Line 5, Protective Action Recommendation information.

Standard:

Marks NONE.

Examiners Note:

Comment:

2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1 Appendix C Page 8 of 14 PERFORMANCE INFORMATION

Performance Step: 10 Enter Line 3 information.

Form ES-C-1 Standard:

Enters H.B. Robinson as the Site and enters CONFIRMATION PHONE NUMBER.

Examiner's Cue:

When candidate requests the ERO phone list, tell him the number is 843-383-3685.

Comment:

Performance Step: 11 Enter Line 4 information.

Standard:

Marks "SITE AREA EMERGENCY", and lists SS2.1 as determined in Performance Step 5 and a description of the event classification as listed on the EAL matrices.

Examiner's Note:

Comment:

Performance Step: 12 Enter Line 5, Protective Action Recommendation information.

Standard:

Marks NONE.

Examiner's Note:

Comment:

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

Appendix C Page 9 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 13 Enter Line 6, EMERGENCY RELEASE, information.

Standard:

Marks NONE.

Examiners Note:

Comment:

Performance Step: 14 Enter Line 7, RELEASE SIGNIFICANCE, information.

Standard:

Marks NA.

Examiners Note:

Comment:

Performance Step: 15 Enter Line 8, EVENT PROGNOSIS, information.

Standard:

Marks STABLE.

Examiners Note:

Comment:

2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1 Appendix C Page 9 of 14 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 13 Enter Line 6, EMERGENCY RELEASE, information.

Standard:

Marks NONE.

Examiner's Note:

Comment:

Performance Step: 14 Enter Line 7, RELEASE SIGNIFICANCE, information.

Standard:

Marks NA.

Examiner's Note:

Comment:

Performance Step: 15 Enter Line 8, EVENT PROGNOSIS, information.

Standard:

Marks STABLE.

Examiner's Note:

Comment:

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

Appendix C Page 10 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 16 Enter Line 9, METEROLOGICAL DATA, information.

Standard:

Enters 100 degrees, 3 mph, 0 Precipitation, Marks Stability Class Examiners Note:

Comment:

Performance Step: 17 Enter Line 10 INFORMATION.

Standard:

Marks Block A, DECLARATION: Enters applicable date and time.

Examiners Note:

Comment:

Performance Step: 18 Enter Line ii information, AFFECTED UNITS.

Standard:

Marks Unit 2.

Examiners Note:

Comment:

2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1 Appendix C Page 10 of 14 PERFORMANCE INFORMATION Form ES-C-1

Performance Step: 16 Enter Line 9, METEROLOGICAL DATA, information.

Standard:

Enters 100 degrees, 3 mph, 0 Precipitation, Marks Stability Class "D".

Examiner's Note:

Comment:

Performance Step: 17 Enter Line 10 INFORMATION.

Standard:

Marks Block A, DECLARATION: Enters applicable date and time.

Examiner's Note:

Comment:

Performance Step: 18 Enter Line 11 information, AFFECTED UNITS.

Standard:

Marks Unit 2.

Examiner's Note:

Comment:

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

Appendix C Page 11 of 14 Form ES-C-i PERFORMANCE INFORMATION Performance Step: 19 Enter Line 12 information UNIT STATUS.

Standard:

Enters Shutdown Time as 1425, todays date.

Examiners Note:

Comment:

Performance Step: 20 Enter Line 13 Remarks information.

Standard:

Enters information describing accident from EAL matrix.

Examiners Note:

May leave LINE 13, Remarks blank or enter EAL information.

Comment:

Performance Step: 21 Submits for APPROVAL by SEC.

Standard:

Submits completed form within 15 minutes of classification time.

Examiners Note:

Comment:

2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1 Appendix C Page 11 of 14 PERFORMANCE INFORMATION

Performance Step: 19 Enter Line 12 information UNIT STATUS.

Standard:

Enters Shutdown Time as 1425, today's date.

Examiner's Note:

Comment:

Performance Step: 20 Enter Line 13 Remarks information.

Form ES-C-1 Standard:

Enters information describing accident from EAL matrix.

Examiner's Note:

May leave LINE 13, Remarks blank or enter EAL information.

Comment:

Performance Step: 21 Submits for APPROVAL by SEC.

Standard:

Submits completed form within 15 minutes of classification time.

Examiner's Note:

Comment:

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

Appendix C Page 12 of 14 Form ES-C-i PERFORMANCE INFORMATION Terminating Cue:

EAL classification has been determined and notification has been made.

STOP TIME:

CRITICAL TASK STOP TIME FOR NOTIFICATION:

2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1 Appendix C Terminating Cue:

STOP TIME: ___

Page 12 of 14 PERFORMANCE INFORMATION Form ES-C-1 EAL classification has been determined and notification has been made.

CRITICAL TASK STOP TIME FOR NOTIFICATION: ___

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

Appendix C Page 13 of 14 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.:

2008 NRC ADM SRO e Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiners Signature:

Date:

2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1 Appendix C Page 13 of 14 VERIFICATION OF COMPLETION Job Performance Measure No.:

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

Appendix C Page 14 of 14 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 grid transient caused a Turbine Generator lockout.

During the grid transient, the Startup Transformer was lost.

The Reactor did NOT trip on interlock and could NOT be tripped from the Control Room.

Operators were dispatched and successfully opened the Reactor Trip Breakers from the Rod Drive MG Set Room at 1425 today.

The Reactor is now tripped and the crew is progressing through FRP-S.i.

480V Bus E-1 is deenergized and EDG A CANNOT be started.

480V Bus E-2 is powered from EDG B.

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

You are the SSO.

INITIATING CUE:

Classify the event lAW the EAL matrices. Upon completion of event classification, inform the Examiner.

2008 NRC ADM SRO e NUREG 1021, Revision 9, Supplement 1 Appendix C Initial Conditions:

INITIATING CUE:

2008 NRC ADM SRO e Page 14 of 14 JPM CUE SHEET Form ES-C-1 The plant was operating at 100% RTP with a CV Pressure Relief in progress when a grid transient caused a Turbine Generator lockout.

During the grid transient, the Startup Transformer was lost.

The Reactor did NOT trip on interlock and could NOT be tripped from the Control Room.

Operators were dispatched and successfully opened the Reactor Trip Breakers from the Rod Drive MG Set Room at 1425 today.

The Reactor is now tripped and the crew is progressing through FRP-S.1.

480V Bus E-1 is deenergized and EDG "A" CANNOT be started.

480V Bus E-2 is powered from EDG "B".

Weather conditions: Wind direction from 1 00 degrees, Wind Speed is 3 MPH, Stability Class is D, Precipitation is Zero.

You are the SSO.

Classify the event lAW the EAL matrices. Upon completion of event classification, inform the Examiner.

NUREG 1021, Revision 9, Supplement 1

ML101970298

Text

Title:

Reference:

Title:

Reference:

References:

References:

Response

Response

Title:

Reference:

Title:

Reference:

References:

References:

Response

Response

Title:

Reference:

References:

Title:

Reference:

References:

Response

Response

Title:

Reference:

References:

Title:

Reference:

References:

Response

Response

Title:

Reference:

References:

Title:

Reference:

References:

4.3. Standard

Response

Response

SUMMARY

SUMMARY

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

2.0 REFERENCES

Title:

Reference:

Title:

Reference:

References:

References:

Response

Response

Title:

Reference:

Title:

Reference:

References:

References:

Response

Response

Navigation menu

Search