ML103050214

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Initial Exam 2010-301 Final Administrative JPMs
ML103050214
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 07/16/2010
From:
Division of Nuclear Materials Safety II
To:
References
50-338/10-301, 50-339/10-301
Download: ML103050214 (51)
v • d • e


Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: North Anna Power Station Date of Examination: 6/21/2010 Examination Level: Combined (See Below) Operating Test Number: I (FINAL)

Administrative Topic Type Describe activity to be performed (KA)

(see Note) Code*

M, R Determine the Quadrant Power Tilt Ratio by hand calculation 1 a) Conduct of Operations G2. 1.7 (1 -PT-23) and determine maximum allowable power level based on the calculation.

(ALL) (G2.1 .7, RO 4.4 I SRO 4.7)

D, R Determine time to boil (1-GOP-i 3.1, Att. 1).

ib) Conduct of Operations G2.1 .25 (ALL) (2.1.25, RO 3.9/ SRO 4.2)

M, R Evaluate and apply Tech Specs and procedure requirements

2) Equipment Control G2.2.37 based on UNSAT condition of a plant component.

(SRO) (2.2.37, RO 3.6 / SRO 4.6)

M, R Given an attached survey, determine entry requirements and

3) Radiation Control G2.3.7 stay times associated with a given work activity.

(All) (2.3.7, RO 3.5 / SRO 3.6)

M, R Classify an emergency event (EPIP-i .01) 4)(SRO) Emergency Plan G2.4.41 (SRO ONLY) (2.4.41, RO 2.9/SRO4.6)

M, S, P Transmit report of emergency to State and local governments.

4) (RO) Emergency Plan G2.4.43 (RO only) (2.4.43, RO 3.2 / SRO 3.8)

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

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (<3 for RO5; 4 for SROs & RO retakes)

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

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

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit was at 100% power when a control rod dropped into the core The Unit has been stabilized at 99% power with Tavg and Tref matched.

Unit 1 PCS is unavailable.

All ex-core power-range channels are operable.

The Instrument Shop has obtained power range detector current readings.

A copy of 1-PT-22.4, Attachment 4, Unit 1 Power Range Calibration Data is available.

INITIATING CUE You are requested to perform a Quadrant Power Tilt Ratio determination by hand calculation in accordance with 1-PT-23, Quadrant Power Tilt Ratio Determination.

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM R709(M)

TASK Determine the Quadrant Power Tilt Ratio by hand calculation (1-PT-23) and determine maximum allowed power level based on the calculation.

TASK STANDARDS Maximum QPTR correctly calculated and maximum power level allowed by TS 3.2.4 correctly determined.

KIA

REFERENCE:

G2.1.7 (4.4/4.7)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 24 minutes Start Time =

Actual Time = minutes Stop Time =

PERFORMANCE EVALUATION Rating [

]SATISFACTORY [

]UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluators Signature /

Date EVALUATORS COMMENTS NAPS 2010 NRC EXAM Page 2 of 7 Admin JPM Ia FINAL REVISION 5/21/2010

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE (Evaluation).

OPERATOR PROGRAM R709 INITIAL CONDITIONS Unit was at 100% power when a control rod dropped into the core The Unit has been stabilized at 99% power with Tavg and Tref matched.

Unit 1 PCS is unavailable.

All ex-core power-range channels are operable.

The Instrument Shop has obtained power range detector current readings.

A copy of 1-PT-22.4, Attachment 4, Unit 1 Power Range Calibration Data is available.

INITIATING CUE You are requested to perform a Quadrant Power Tilt Ratio determination by hand calculation in accordance with 1-PT-23, Quadrant Power Tilt Ratio Determination.

EVALUATION METHOD Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT Calculator Copy of 1-PT-22.4, Attachment 4, Unit I Power Range Calibration Data.

Evaluator will need a copy of Technical Specifications and Bases for performance of elements 5 and 6 of this evaluation.

NAPS 2010 NRC EXAM Page3of7 Admrn JPM la FINAL REVISION 5/21/2010

PERFORMANCE STEPS START TIME 1 Record the expected 100% power current readings in attachment 2. I Procedure Step ISAT[1 UNSAT[] I Standards I Data correctly transcribed from the copy of 1-PT-22.4 provided.

Notes/Comments 2 I Calculate the normalized detector currents and averages. Procedure Step I ISAT[] UNSATI]

I Standards I Normalized detector currents and averages are calculated.

Notes/Comments NAPS 2010 NRC EXAM Page 4 of 7 Admin JPM Ia FINAL REVISION 5/21/2010

3 I Calculate the quadrant power tilt ratios. I Procedure Step Critical Step SAT[] UNSAT[]

Standards Upper and lower quadrant power tilt ratios are calculated.

- Individual QPTRs determined per the acceptance criteria of the attached answer key AND

- Maximum QPTR determined to be 1.0396 acceptance criteria: 1.0386 to 1.0406 (+1- 0.001)

Notes/Comments 4 Record the value and location of the largest quadrant power tilt Procedure Step ratio.

I SAT[] UNSAT[]

Standards Value transcribed from previous step.

Location recorded is N41 L.

Notes/Comments The following elements take place one-on-one with the evaluator, after the candidate has completed the QPTR calculation in the classroom.

NAPS 2010 NRC EXAM Page 5 of 7 Admin JPM Ia FINAL REVISION 5/21/2010

EVALUATORS NOTE IF QPTR calculations are correct, THEN continue the JPM, otherwise JPM should be terminated at this point.

I5 I Identifies QPTR exceeds maximum permissible value of 1.02. Procedure Step I ISATFI UNSAT[]

Evaluators Note Provide candidate with Technical Specifications and Bases for use in completing this element and element 6.

Demonstration Ask the applicant to identify whether the acceptance criteria of 1-PT-23 Cues are met.

Standards Technical Specification 3.2.4 is identified and QPTR determined to exceed the LCO 3.2.4 based on given conditions (thermal power of

>50% RTP provided in the IC, so TS 3.2.4 Applicability is met).

Notes/Comments NAPS 2010 NRC EXAM Page6of7 Admin JPM la FINAL REVISION 5/21/2010

6 I Determine maximum allowable power level per TS 3.2.4. I Procedure Step I Critical Step SAT[] UNSAT[]

Evaluators Note IF the candidate calculated a QPTR of < 1.02 and determined that the LCO was met in element 5, THEN end the evaluation at this point.

IF the candidate calculated a QPTR of> 1.02 and determined that the LCD was NOT met in element 5, THEN provide the following cue.

Demonstration Ask the applicant to calculate the maximum power level allowed by Cues Technical Specification 3.2.4, based on the QPTR.

Standards Maximum power level determined to be 88.12%

(from TS 3.2.4 power must be reduced > 3% from RTP for each 1% of QPTR> 1.00. Therefore 3.96% X 3 = 11.88).

For conservatism power may be rounded down to 88% +/- 1%

Notes/Comments

>>>>> END OF EVALUATION <<<<<

STOP TIME NAPS 2010 NRC EXAM Page 7 of 7 Admin JPM la FINAL REVISION 5/21/2010

DOMINION 1-PT-23 North Anna Power Station Revision 29 Page 15 of 15 (Page 3 of 3)

Attachment 2 QPTR Hand Calculation NOTE: Current Readings may be obtained from the face meters of the Power Range B Drawer OR from the test jacks OR from the Unit 1 PCS, if operable.

Avg. of Upper N-41 N-42 N-43 N-44 Normalized Description Upper Upper Upper Upper Currents Current Reading (record to nearest j.ta) /5 1 itj4 I t7 LX) 0 Expected Current (record as shown in Reactor Data Book or 1 PT-22 4) 1 o Zob Normalized Current (Current Reading I Expected Current)

C//(Lç, .%1))

(4 decimal places) ç If QPTR (Normalized Current / Avg of Norm Currents)

(4 decimal places) ( i o c Avg. of Lower N-41 N-42 N-43 N-44 Normalized Description Lower Lower Lower Lower Currents Current Reading (record to nearest j.w) 3 1 Ze {

Expected Current (record as shown in Reactor Data Book or 1 PT-224) fl7 RL lcL Z.2 I.

Normalized Current (Current Reading / Expected Current)

(4 decimal places) . 9o c-c 7c_

QPTR (Normalized Current / Avg. of Norm. Currents)

(4 decimal places) I 9 12) I.Cft I )JJ 32 Maximum QPTR: U (Record Maximum Upper or Lower QPTR Value from above)

Quadrant of Max QPTR: (N4l Upper, N4l Lower N42 Upper, N42 Lower, etc.)

Completed by: Date:

Verified by:______________________________________________

(Use this Time for recording Date/Time Verification Completed:

when surveillance is completed)

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS The unit entered Mode 3 on 4/01/2010 at 0600 for a scheduled refueling outage.

The core has been reloaded and the cavity drain-down is complete.

Current conditions are as follows:

  • The Date and time is 4/20/2010, 2000
  • RCS level is 74 inches above Mid Loop
  • RHR pump discharge temperature is 97°F
  • 55 fuel assemblies were exchanged during on-load INITIATING CUE The Shift Manager has directed you to determine the estimated time to boil in accordance with 1-GOP-13.1, using the current conditions.

(Record your results in the space provided)

Corrected Time to Boil estimate:

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine estimated time to boil.

TASK STANDARDS Given a copy of 1-GOP-i 3.1, determine the estimated time to boil KIA

REFERENCE:

G2.i.25 (3.9)4.2)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 10 minutes Start Time =

Actual Time = minutes Stop Time =

PERFORMANCE EVALUATION Rating [

]SATISFACTORY [ I UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluators Signature /

Date EVALUATORS COMMENTS NAPS 2010 NRC EXAM Page: 2 of 7 Admin JPM lb FINAL REVISION 5/21/2010

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE (Evaluation)

OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS The unit entered Mode 3 on 4/01/2010 at 0600 for a scheduled refueling outage.

The core has been reloaded and the cavity drain-down is complete.

Current conditions are as follows:

  • The Date and time is 4/20/2010, 2000
  • RCS level is 74 inches above Mid Loop
  • RHR pump discharge temperature is 97°F
  • 55 fuel assemblies were exchanged during on-load NAPS 2010 NRC EXAM Page: 3 of 7 Admin JPM lb FINAL REVISION 5/21/2010

INITIATING CUE The Shift Manager has directed you to determine the estimated time to boil in accordance with 1-GOP-13.1, using the current conditions.

EVALUATION METHOD Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT Calculator Copy of 1-GOP-13.1.

PERFORMANCE STEPS START TIME 1 Determine time after shutdown for use on attachment 1 or 2. Procedure Step N/A SAT[] UNSAT[]

Standards Operator determines time after shutdown for use on attachment 1 or 2 is 19 days and 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> (470 hours0.00544 days <br />0.131 hours <br />7.771164e-4 weeks <br />1.78835e-4 months <br />).

Notes/Corn rnents:

NAPS 2010 NRC EXAM Page:4of7 Admin JPM lb FINAL REVISION 5/21/2010

2 Enter Time to Boil from midloop and 100°F from attachment 1 or 2. Procedure Step:

5.6.1 Critical Step SAT[] UNSAT[]

Standards Operator determines 19.25 minutes (based on time of 470 hours0.00544 days <br />0.131 hours <br />7.771164e-4 weeks <br />1.78835e-4 months <br /> from entry into Mode 3).

Acceptance criteria of 19.0 19.5 (based on half-increment L readability).

Notes/Corn ments:

3 Enter correction factor for RCS water level from attachment 3. Procedure Step:

5.6.2 CriticaiStep SAT[] UNSAT[]

Standards Operator determines 1.61 (based on initial condition of 74 inches above midloop).

Acceptance criteria of 1.60 1.62 (based on half-increment readability).

Notes/Comments:

NAPS 2010 NRC EXAM Page: 5 of 7 Admin JPM lb FINAL REVISION 5/21/2010

4 Enter correction factor for initial RCS temperature from Procedure Step:

attachment 4. 5.6.3 ICritical Step SAT[] UNSAT[]

Standards Operator determines 1.025 (based on initial condition of 97°F RHR pump discharge temperature).

Acceptance criteria of 1.00 1.05 (based on half-increment readability).

Notes/Comments:

5 Enter correction factor for number of fuel assemblies exchanged Procedure Step:

this fuel cycle on-load attachment 5. 5.6.4 Critical Step SAT[] UNSAT[]

Standards Operator determines 1.1175 (based on initial condition of 55 fuel assemblies were exchanged during on-load).

Acceptance criteria of 1.1150 1.1200 (based on half-increment readability).

Notes/Comments:

NAPS 2010 NRC EXAM Page: 6 of 7 Admin JPM lb FINAL REVISION 5/21/2010

6 Determine corrected time to boil estimate. Procedure Step:

5.6.5 Critical Step SAT[] UNSAT[]

Standards Operator determines corrected Time to Boil 35.5 minutes based on above elements.

(19.25 x 1.61 x 1.025 x 1.1175)

Acceptance criteria:

Low calc 33.9 minutes** (19.0 x 1.60 x 1.00 x 1.1150)

High caic 37.1 minutes (19.5 x 1.62 x 1.05 x 1.1200) for conservatism a lower limit of acceptance criteria of 33 minutes is acceptable based on rounding down times.

Notes/Comments:

>>>>> END OF EVALUATION <<<<<

STOP TIME NAPS 2010 NRC EXAM Page: 7 of 7 Admin JPM lb FINAL REVISION 5/21/2010

DOMNI0N 1-GOP-13.1 North Anna Power Station Revision 18 Page 13 of 18 NOTE: An individual correction factor that does not apply should be entered as 1.0.

5.6 IF in Mode 5 (with RCS vented or soon to be vented) OR in Mode 6 (with Cavity level less than 23 ft above the Reactor pressure vessel flange), THEN calculate estimated time to boiling in the RCS for loss of cooling by doing the following: (Reference 2.4.1) 5.6.1 Enter Time to Boil from midloop and 100°F, for desired time after Shutdown, Attachment I or Attachment2: Ct5 -a

.c)

NOTE: For water levels above 78, a factor of 1.64 should be used.

5.6.2 Enter desired correction factor for RCS water level, K, from Attachment 3:

NOTE: RHR pump discharge is the preferred location to obtain RCS temperature when RHR is in service.

5.6.3 Enter desired correction factor for initial RCS temperature, K, from Attachment 4:

5.6.4 Enter desired correction factor for number of fuel assemblies exchanged this fuel cycle on-load (assemblies NOT used in the just-completed cycle), Kf, from Attachment 5: 1

5) Ck NOTE: Times should be rounded down for conservatism.

5.6.5 Multiply values of Steps 5.6.1

  • 5.6.2
  • 5.6.3

5.6.6 Enter the corrected Time to Boil estimate on l-GOP-13.0.

K

\O \ jO

(..cO x

DOMINION 1-GOP-i 3.1 North Anna Power Station Revision 18 Page 14 of 18 (Page 1 of 1)

Attachment I Time to Boil Based on Hours After Shutdown z

1 C\

Time to Boil, Midloop and 100°F 20 l4 I

18

/

/

16 -

d 14 -- --

--- - --i -----

12 --

C) 1 C

0 10 0

a)

E I

8 6

4 2

0 0 100 200 300 400 500 Time After Shutdown (Hours)

SM-1565-0-A, Figure A-3

DOMINION 1-GOP-i 3.1 North Anna Power Station Revision 18 Page 15 of 18 (Page 1 of 1)

Attachment 2 Time to Boil Based on Days After Shutdown Time to Boil, Midloop and 100°F 50 45 40 35 30 U,

0 4-0 25 0

0)

E I-20 15 10 5

0 0 10 20 30 40 50 60 70 80 90 100 Time After Shutdown (Days) SM-1565-0-A, Figure A-4

DOMINION 1-GOP-i 3.1 North Anna Power Station Revision 18 Page 16 of 18 (Page 1 of 1)

Attachment 3 RCS Water Level Correction Factor 1.7 1.6 o

P 1.5

.J .4 1.3 1.2 1.1 I

Inches Above Mid Loop Graphics No. CS4922

DOMINION 1-GOP-i 3.1 North Anna Power Station Revision 18 Page 17 of 18 (Page 1 of 1)

Attachment 4 Correction Factor For Initial RCS Temperature 70 90 110 130 150 170 190 210 Initial Temperature (°F)

Graphics No. CS4923

DOMINION 1 -GOP-13.1 North Anna Power Station Revision 18 Page 18 of 18 age 1 of 1)

Attachment 5 Correction Factor For Number of Refueled Assemblies

. 1.10 ci çk-Number of Refuel Assemblies Graphics No. CS4924 u_i

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 1 is operating at 100% when Nuclear Oversight reports that an inspection has identified calculation errors during the previous main steam safety valve (MSSV) testing.

The data was recalculated, and the following lists for the actual setpoints for the affected SG MSSVs:

1-MS-SV-1O1A-- 1125 psig 1-MS-SV-103B 1070 psig 1-MS-SV-103C 1150 psig 1-MS-SV-i 02A 1090 psig 1 -MS-SV-i 04B 1103 psig 1 -MS-SV-1 04A - 1158 psig INITIATING CUE Based on the revised setpoint data provided, you are requested to perform the following:

1. Identify inoperable MSSVs, if any.
2. Evaluate compliance with Technical Specification requirements and determine actions required, if any.

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM S35 TASK Evaluate compliance with technical requirements (Technical Requirements) for Main Steam Safety Valves.

TASK STANDARDS LCO 3.7.1 was entered KIA

REFERENCE:

GEN-2.2.37 (3.6/4.6)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 20 minutes Start Time =

Actual Time = minutes Stop Time =

PERFORMANCE EVALUATION Rating [ ] SATISFACTORY [1 UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluators Signature /

Date EVALUATORS COMMENTS NAPS 2010 NRC EXAM Page: 2 of 6 Admin JPM 2 FINAL REVISION 5/21/2010

Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)

OPERATOR PROGRAM S35 READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

PREREQUISITES The trainee has completed the applicable course knowledge training at the senior reactor operator level.

NAPS 2010 NRC EXAM Page:3of6 Admin JPM 2 FINAL REVISION 5/21/2010

INITIAL CONDITIONS Unit 1 is operating at 100% when Nuclear Oversight reports that an inspection has identified calculation errors during the previous main steam safety valve setpoint.

The data was recalculated, and the following lists for the actual setpoints for the affected SG MSSVs:

1-MS-SV-1O1A 1125 psig 1-MS-SV-103B 1070 psig 1-MS-SV-103C 1150 psig 1 -MS-SV-1 02A 1090 psig I -MS-SV-1 04B 1103 psig 1-MS-SV-104A- 1158 psig INITIATING CUE Based on the revised setpoint data provided, you are requested to perform the following:

1 Identify inoperable MSSVs, if any.

2. Evaluate compliance with Technical Specification requirements and determine actions required, if any.

EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))

Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))

TOOLS AND EQUIPMENT Technical Specifications, Technical Requirements Manual, and Bases Documents.

Calculator NAPS 2010 NRC EXAM Page:4of6 Admin JPM 2 FINAL REVISION 5/21/2010

PERFORMANCE STEPS START TIME I1 Identify the applicable technical specification LCO requirement. I Procedure Step I CriticalStep ISAT[] UNSAT[]

I Standards Tech Spec 3.7.1 is identified as the applicable LCO Notes/Comments

[2 I Determine operability of affected components using Table 3.7.1-2. I Procedure Step LCritical Step SAT[] UNSAT[J Standards Candidate identifies only lOlA, 104A, 103B, and 103C, are inoperable I (see table below, valves outside acceptance criteria shown in bold type).

Valve Number Lift setpoint Tech Spec lift Tech Spec provided by JPM setting acceptable range (Table 3.7.1-2) (+1- 3%)

1-MS-SV-IOIA 1125 psig 1085 psig 1053 1117 psig 1-MS-SV-102A 1090 psig 1095 psig 1063- 1127 psig 1-MS-SV-104A 1158 psig 1120 psig 1087 1153 psig 1-MS-SV-103B 1070 psig 1110 psig 1077 1143 psig 1 -MS-SV-i 04B 1103 psig 1120 psig 1087 1153 psig 1-MS-SV-103C 1150 psig 1110 psig 1077 1143 psig Notes/Comments This results in two (2) MSSVs on A SG inoperable, one (1) MSSV on B SG inoperable, and one (1) MSSV on C SG inoperable.

NAPS 2010 NRC EXAM Page: 5 of 6 Admin JPM 2 FINAL REVISION 5/21/2010

3 Determine the REQUIRED ACTION and COMPLETION TIME for Procedure Step the applicable limiting condition for operation (LCO).

ICritical Step SAT[] UNSAT[]

Standards Using Table 3.7.1-1 and the data from element 2 candidate determines the following actions and completion times apply (required power level shown in bold type):

Action Completion time B.1, Reduce THERMAL POWER to less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or equal to the Maximum Allowable % RTP (37%) specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

B.2, Reduce the Power Range Neutron Flux- 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> High reactor trip setpoint to less than or equal to the Maximum Allowable % RTP (37%) specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

Notes/Comments Based on A SG having only 3 operable MSSVs. If candidate misreads table 3.7.1-1 they may erroneously select 21% power (table is based on operable number per SG, NOT inoperable number per SG.

END OF EVALUATION STOP TIME NAPS 2010 NRC EXAM Page:6of6 Admin JPM 2 FINAL REVISION 5/21/2010

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Both Units are operating at 100% power with no abnormal conditions. A drain valve on the west side at the bottom of the fluid waste treating tank (1-DC-TK-2) needs to be cycled several times.

All radiation workers involved in the task have worked at the North Anna site and no other locations.

INITIATING CUE You are directed to perform the following:

  • Select the appropriate RWP for operations personnel
  • Determine the required protective clothing for the job.
  • Determine the required dosimetry for the job.
  • Determine the dose alarm setpoint AND the dose rate alarm setpoint in effect under the RWP.
  • Determine the maximum stay time based on reaching the dosimeter alarm setpoint (assume that NO dose is accumulated in transit to or from the work location).

. State the action(s) required if a dosimeter alarm setpoint is reached.

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine Correct RWP, Stay Time, Dosimetry, and Dressout Requirements For A Given Task.

TASK STANDARDS Correct RWP is selected, protective clothing and dosimetry are selected for the given RWP, dose alarm and dose rate setpoints identified from the RWP, and the maximum stay time calculated based on the alarm setpoints.

KIA

REFERENCE:

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 20 minutes Start Time =

Actual Time = minutes Stop Time =

PERFORMANCE EVALUATION Rating [1 SATISFACTORY [1 UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluators Signature /

Date EVALUATORS COMMENTS NAPS 2010 NRC EXAM Page: 2 of 7 Admin JPM 3FINAL REVISION 5/21/2010

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE (Evaluation)

OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS Both Units are operating at 100% power with no abnormal conditions. A drain valve on the west side at the bottom of the fluid waste treating tank (1-DC-TK-2) needs to be cycled several times.

All radiation workers involved in the task have worked at the North Anna site and no other locations.

INITIATING CUE You are directed to perform the following:

. Select the appropriate RWP for operations personnel

  • Determine the required protective clothing for the job.
  • Determine the required dosimetry for the job.
  • Determine the dose alarm setpoint AND the dose rate alarm setpoint in effect under the RWP.
  • Determine the maximum stay time based on reaching the dosimeter alarm setpoint (assume that NO dose is accumulated in transit to or from the work location).
  • State the action(s) required if a dosimeter alarm setpoint is reached.

NAPS 2010 NRC EXAM Page: 3 of 7 Admin JPM 3 FINAL REVISION 5/21/2010

EVALUATION METHOD Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT RWPs, Survey Map, Calculator Ensure survey map is color copy PERFORMANCE STEPS START TIME 1 From the RWPs provided determine which RWP is applicable for Procedure Step the job. RWP 10-2229 Critical Step SAT[] UNSAT[]

I Standards I RWP 10-2229 is selected from the four RWPs provided.

Notes/Comments:

RWP 1 0-0001 is not correct since no HRA entries are allowed under this RWP.

RWP 10-1007 is not correct since it is for maintenance activities.

RWP 10-1203 is not correct since it is for emergency situations RWP 10-2229 is the correct RWP.

NAPS 2010 NRC EXAM Page:4of7 Admin JPM 3 FINAL REVISION 5/21/2010

2 From the RWPs provided, determine the protective clothing Procedure Step:

requirements. RWP 10-2229 Critical Step SAT[] UNSAT{]

Standards Operator determines that the area is in a contaminated area (CA) and the protective clothing requirements are those listed on the RWP (page 4) for contaminated areas.

Protective Clothing Requirements:

1.0) Required Protective Clothing One Hood One Pair Coveralls Rubber Boots High Top Shoe Covers Cotton Inserts One Pair Rubber Gloves Notes/Comments: Operator is required to identify from the survey map that the area is a contaminated area (CA).

3 From the RWPs provided, determine the dosimetry required. Procedure Step:

RWP 10-2229 Critical Step SAT[J UNSAT[}

Standards Operator identifies that DAD/SRD & TLD are required (page 4 of RWP).

Notes/Comments: Operator is required to identify from the survey map that the area is a high rad area.

NAPS 2010 NRC EXAM Page: 5 of 7 Admin JPM 3FINAL REVISION 5/21/2010

4 From the RWPs provided, determine the dose alarm setpoint and Procedure Step:

dose rate alarm in effect under the RWP. RWP 10-2229 Critical Step SAT[] UNSAT[J Standards Operator correctly identifies that the dose alarm is 50 mRem and the dose rate alarm is 500 mRem/hr (RWP page 1 or page 4).

Notes/Comments: Operator is required to identify from the survey map that task 2 setpoint must be used based on work location.

5 Determine the maximum stay time in minutes based on reaching Procedure Step:

the RWP dose alarm setpoint. RWP 10-2229 Critical Step SAT[] UNSAT[]

Standards Operator uses RWP to determine dose alarm is set at 50 mRem.

Operator uses survey map to determine general area dose rate is 125 mr/hr.

Operator then divides 50 by 125 to obtain a stay time of 24 minutes after converting to minutes (.4 hrs x 60 minutes).

Notes/Comments:

NAPS 2010 NRC EXAM Page: 6 of 7 Admin JPM 3 FINAL REVISION 5/21/2010

6 State the action(s) required if a dosimeter alarm setpoint is Procedure Step:

reached. RWP 10-2229 Lcritical Step SAT[] UNSAT[]

Standards Operator correctly identifies leave area immediately and report to (notify) the health physics office (RWP page 5, worker instructions 1.1 and 1.2.

Notes/Comments:

END OF EVALUATION STOP TIME NAPS 2010 NRC EXAM Page: 7 of 7 Admin JPM 3FINAL REVISION 5/21/2010

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 1 is shutdown with RCS temperature at 420°F.

Unit 2 is at 100% power.

/1 1-VG-RM-179 has had a valid reading of 4.22 E + 7 Ci/sec. for 18 minutes.

Dose assessment is available and indicates that doses at or beyond the site boundary are 40 mR TEDE and 120 mR CDE thyroid.

INITIATING CUE You are requested to classify an emergency event in accordance with EPIP-1.01.

This is a time critical JPM.

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Classify an emergency event.

TASK STANDARDS Event was identified as RA1 .2 within 15 minutes.

KIA

REFERENCE:

GEN-2.4.41 (2.9/4.6)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 10 minutes Start Time Actual Time = minutes Stop Time PERFORMANCE EVALUATION Rating [1 SATISFACTORY [1 UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluators Signature /

Date EVALUATORS COMMENTS NAPS 2010 NRC EXAM Page:2of5 Admin JPM 4 (SRO ONLY) FINAL REVISION 5/21/2010

Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)

OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

PREREQUISITES The trainee has completed the applicable course knowledge training at the Senior Reactor Operator level.

INITIAL CONDITIONS Unit 1 is shutdown with RCS temperature at 420°F.

Unit 2 is at 100% power.

VG-RM-179 has had a valid reading of 4.22 E + 7 Ci/sec. for 18 minutes.

Dose assessment is available and indicates that doses at or beyond the site boundary are 40 mR TEDE and 120 mR CDE thyroid.

NAPS 2010 NRC EXAM Page: 3 of 5 Admin JPM 4 (SRO ONLY) FINAL REVISION 5/21/2010

INITIATING CUE You are requested to classify an emergency event in accordance with EPIP-1.O1. This is a time critical JPM.

EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))

Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))

TOOLS AND EQU!PMENT Copy of EAL tables and EAL technical basis document PERFORMANCE STEPS START TIME (15 minute clock begins once candidate acknowledges that they understand their task)

Note: Candidate should use HOT CONDITIONS (RCS> 200°F) based on initial conditions provided by JPM.

1 Determine the EAL identifier using the emergency action level Procedure Step matrix.

Critical Step SAT[] UNSAT[]

Standards Event is evaluated and identified as Abnormal Rad Release I Rad Effluent (RA1.2).

Notes/Corn ments Since dose assessment available, candidate must apply Note 1 of the EAL matrix to make the correct classification (if rad monitor reading are used it will result in an inappropriate classification level, RS1.1)

NAPS 2010 NRC EXAM Page: 4 of 5 Admin JPM 4 (SRO ONLY) FINAL REVISION 5/21/2010

2 I Event declaration made within 15 minutes. I Procedure Step Critical Step SAT[] UNSAT[}

I Standards I Event is declared as RA1 .2 within 15 minutes.

Notes/Comments start time - stop time = minutes Acceptance criteria: (time is less than or equal to 15 minutes)

>>>>> END OF EVALUATION <<<<<

STOP TIME (15 minute clock ends once candidate makes classification)

NAPS 2010 NRC EXAM Page: 5 of 5 Admin JPM 4 (SRO ONLY) FINAL REVISION 5/21/2010

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS You are the Emergency Communicator.

Unit 2 has experienced a loss of offsite power and the Station Emergency Manager (SEM), the evaluator, has declared an NOUE, EAL identifier SU1.1.

NO release of radioactive material is presently occurring.

There are NO known impediments to site access.

INITIATING CUE You are requested to make the initial state and local notification in accordance with EPIP 2.01, Notification of State and Local Governments.

This is the initial emergency declaration and the Station Emergency Manager has directed items 5 through 9 of the form be excluded from the message.

The time of the declaration is now.

This JPM is time critical.

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Make state and local notifications in accordance with EPIP-2.O1.

TASK STANDARDS Make notification of event (SU1.1).

KIA

REFERENCE:

GEN-2.443 (3.2/3.8)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time = 10 minutes Start Time =

Actual Time minutes Stop Time =

PERFORMANCE EVALUATION Rating [

]SATISFACTORY [

jUNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluators Signature /

Date EVALUATORS COMMENTS NAPS 2010 NRC EXAM Page: 2 of 9 Admin JPM 4 (RO ONLY) FINAL REVISION 5/21/2010

Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)

OPERATOR PROGRAM READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE Instructions for Simulator JPMs I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

Instructions for In-Plant JPMs I will explain the initial conditions, and state the task to be performed. All steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

PREREQUISITES The trainee has completed the applicable course knowledge training at the senior reactor operator level.

INITIAL CONDITIONS You are the Emergency Communicator.

Unit 2 has experienced a loss of offsite power and the Station Emergency Manager (SEM), the evaluator, has declared an NOUE, EAL identifier SU1.1.

NO release of radioactive material is presently occurring.

There are NO known impediments to site access.

NAPS 2010 NRC EXAM Page: 3 of 9 Admin JPM 4 (RO ONLY) FINAL REVISION 5/21/2010

INITIATING CUE You are requested to make the initial state and local notification in accordance with EPIP 2.01, Notification of State and Local Governments.

This is the initial emergency declaration and the Station Emergency Manager has directed items 5 through 9 of the form be excluded from the message.

The time of the declaration is now.

This JPM is time critical.

EVALUATION METHOD Perform if conducted in the simulator or in a laboratory (use Performance Cue(s))

Simulate if conducted in the station or on a dead simulator (use Simulation Cue(s))

TOOLS AND EQUIPMENT Emergency Communicator Notebook (Located in Simulator).

NAPS 2010 NRC EXAM Page: 4 of 9 Admin JPM 4 (RO ONLY) FINAL REVISION 5/21/2010

PERFORMANCE STEPS START TIME (15 minute clock begins once candidate acknowledges that they understand their task) 1 Obtain Notification form Procedure Step EPIP-2.O1 ISATF1 UNSATI1 I Standards Operator obtains form from Emergency Communicator Notebook.

Notes/Comments Note: Average wind speed and direction will vary slightly with simulator run time and IC, evaluator should observe that candidate uses the correct indicator (as discussed below in the Notes section) when completing the form.

2 Record information on Report of Emergency to State and Local Procedure Step Governments. EPIP-2.O1 ICriticaiStep SAT[] UNSAT[]

Standards Information on Report of Emergency to State and Local Governments is filled in as shown on attached key.

. Candidate enters Emergency Classification as NOUE, SU1.1 (provided by initial conditions of JPM)

. Candidate obtains Wind Speed from Main Tower lower Level

. Candidate obtains Wind Direction from Main Tower lower Level

  • Candidate uses EPIP-2.O1, Attachment 1, page 5 of 9, and determines the Compass Point to, wind direction to, and Compass Point from, based on wind direction from which they obtained_from_PCS_or_recorders.

Notes/Comments Main Tower lower Level is required to be used for obtaining wind direction and Wind Speed as this is the FIRST priority given by EPIP-2.O1 (see Attachment 1 page 4 of 9).

NAPS 2010 NRC EXAM Page: 5 of 9 Admin JPM 4 (RO ONLY) FINAL REVISION 5/21/2010

3 Have SEM/RM approve report. Procedure Step E P1 P-2. 01 I LCritical Step ISAT[i UNSAT[] 1 I Standards I SEM/RM approves and signs the approval block.

Performance Inform operator I am the SEM and I will approve the report. (sign Cue(s approval line on top right hand corner of form)

Notes/Comments 4 Establish communications. Procedure Step EPIP-2.01 ISAT[1 UNSAT[]

I Standards I Operator uses VEOC ARD to establish contact.

Notes/Comments Booth operator will respond as Virginia EOC and local governments during ring down.

NAPS 2010 NRC EXAM Page: 6 of 9 Admin JPM 4 (RO ONLY) FINAL REVISION 5/21/2010

NOTE: Time critical portion of JPM stops when operator makes contact.

5 Operator makes contact with State and local Emergency Operation Procedure Step Centers (EOCs). EPIP-2.O1 Critical Step SAT[] UNSAT[]

Standards Time contact made:

Start Time - Time contact made = mins.

Acceptance Criteria:

Operator establishes contact in less than or equal to 15 minutes.

Notes/Comments Booth operator will respond as Virginia EOC 6 Perform initial roll call. Procedure Step 6.c of EPIP-2.O1 Critical Step SAT[] UNSAT[]

Standards I Operator checks boxes as EOCs answer.

Notes/Corn ments Booth operator will respond to roll call as follows: Louisa County is on the line, Spotsylvania County is on the line, Hanover County is on the line, Orange County is on the line, Caroline County is on the line.

NAPS 2010 NRC EXAM Page: 7 of 9 Admin JPM 4 (RO ONLY) FINAL REVISION 5/21/20 10

7 Record time initial notification was made on form. Procedure Step EPIP-2.O1 ISAT[1 UNSAT[]

Standards I Operator enters time. I Performance Inform operator JPM is complete.

Cue(s)

Notes/Comments END OF EVALUATION STOP TIME NAPS 2010 NRC EXAM Page: 8 of 9 Admin JPM 4 (RO ONLY) FINAL REVISION 5/21/2010

SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)

Reset to IC #2, 100% power.

DO simspray and check recorders.

- - Change PCS screens if required such that MET data screen is NOT displayed.

Do phone check from on simulator floor (VEOC ARD line) (only for first JPM of day)

- Booth operator respond as Virginia EOC when rung and for roll call as follows:

- Louisa County is on the line, Spotsylvania County is on the line, Hanover County is on the line, Orange County is on the line, Caroline County is on the line.

NAPS 2010 NRC EXAM Page:9of9 Admin JPM 4 (RO ONLY) FINAL REVISION 5/21/2010

cO(

REPORT OF EMERGENCY TO STATE AND LOCAL GOVERNMENTS MESSAGE #_____ ,POVAL c4r Ot $A Pe (Station Emergency Manager or Recovery Manager)

This is North Anna Power Station ntrol Room C TSC C LEOF C CEOF. Standby for roll-call and following emergency message. Use a Report of Emergency form to copy message. (Conduct a roll-call and check boxes as each party answers.)

f!Pirgiruia EC C Louisa Coury ED8potsylvania Couty Ci-1anoier CoujNy I1Orare CounW IJIroIine County hetfris I. The emergency message is as follows: (READ SLOWLY)

(24-hr time) -

cor4- fr , E Item 1. STATUS: ctual Event C Actual Event terminated at on Drill C Drill terminated (24-hr time) (date)

Item 2. EMERGENCY CLASSIFICATION: NOUE C Alert C Site Area Emergency C General Emergency Category Classification (--E Jt fl. o =

C R S j:ri:j C S i. 1 Declared at on C H C F C A C G (24-hr time) (date)

C E C C Fission Product Barriers affected: C N/A C Fuel Clad C Reactor Coolant C Containment Item 3. RELEASE OF RADIOACTIVE MATERIAL: Routine releases ongoing due to plant operations.

Additional radiological releases associated with the event:

C A. No radiological release. Will NOT transmit Report of Radiological Conditions to Virginia EOC.

C B. Radiological release in progress. Will transmit Report of Radiological Conditions to Virginia EOC.

C C. Radiological release now terminated. Will transmit Report of Radiological Conditions to Virginia EOC.

C D. Radiological release projected to occur. Will transmit Report of Radiological Conditions to Virginia EOC.

Item 4. METEOROLOGICAL DATA: Based on: WOn-site Measurements C Off-site Measurements C Not Available Time: AVE Wind Direction from I b] degrees (00 to 360°), Compass Point s vvE (24-hr time) 7 to Z..SZC degrees (0° to 360°), Compass Point VVN VV AVE Wind Speed ZE mph NOTE: Items 5 9 optional for message reporting initial Emergency Plan entry or emergency classification change and Excluded from message may be checked. Items 5 9 are excluded from message may be read in lieu of reading each item.

Item 5. ASSISTANCE REQUESTED OR BEING PROVIDED: EExcluded from message C None

(#) Fire Units from (#) Police Units from

(#) Rescue Units from (#) Other Item 6. EMERGENCY RESPONSE ACTIONS UNDERWAY: Excluded from message C None C Station emergency personnel called in C Station monitoring teams dispatched off-site C Other Item 7. EVACUATION OR COMPANY DISMISSAL OF SITE PERSONNEL: FExcluded from message CN0 C Evacuation to Primary Remote Assembly Area: C Planned C In progress C Completed C Released from RAA C Evacuation to Secondary Remote Assembly Area: C Planned C In progress C Completed C Released from RAA C Company Dismissal: C Planned C In progress C Completed C Other Item 8. PROGNOSIS OF SITUATION SINCE LAST REPORT: LExcluded from message C Stable C Worsening C Improving C Other Item 9. ADDITIONAL INFORMATION (Do not use abbreviations, mark numbers or acronyms.): Excluded from message This is (name) Communicator Please acknowledge receipt of this message. (Conduct roll-call and check boxes as each party answers.)

C Virginia EOC C Louisa County C Spotsylvania County C Hanover County C Orange County C Caroline County This is North Anna Power Station C Control Room C TSC C LEOF C CEOF out at on (24-hr time) (date)

CONTINUED ON REVERSE FOR STATE Form No. 730861(Sept 2009)

Admin JPM 4 (RO only), Additional remarks Items show in GREEN highlight are completed PRIOR to obtaining approval Items shown in ORANGE highlight are completed when Emergency Communicator has completed form and obtains approval from SEM to transmit AND Makes contact For item 1: typically Drill is checked for anything other than a bona fide ACTUAL emergency. The candidate may check Actual Event since this is an NRC evaluated JPM. Either is acceptable for the JPM, evaluator may discuss with candidate after completion of jpm if desired.

For item 4: data shown is for illustration purposes only, actual values may vary slightly with simulator IC and run time. See JPM for explanation of where data should be obtained from and how compass points are determined.

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