ML17172A726

Section 12 - Final Administrative JPMs - North Anna Power Station

ML17172A726
Person / Time
Site:	North Anna
Issue date:	06/21/2017
From:	NRC/RGN-II
To:	Virginia Electric & Power Co (VEPCO)
References
Download: ML17172A726 (113)

Text

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Three Reactor Operators have the following history:

1. All three have off-shift assignments at the plant, are up to date in the License Operator Requalification Program (LORP), and have successfully completed their medical examination in the past year.

2. None of the 3 has worked on shift since April 1, 2016.

3. Time worked on shift since January 1, 2016 for each of the Reactor Operators is provided on the attached sheet.

INITIATING CUE You are to determine if each of the Reactor Operators is qualified to stand the Unit 1 RO watch for the remainder of the 0700 - 1900 shift on April 1, 2016. Record your answer in the blanks below (yes or no).

Operator A. _____________________

Operator B. _____________________

Operator C. _____________________

2016 NRC EXAM ADMIN CO 1 (RO)

Page: 2 of 8 Operator A License was active on January 1, 2016.

02/02/16 Worked 0700-1900 shift as Unit 1 OATC.

02/03/16 Worked 0700-1900 shift as Unit 1 OATC.

02/04/16 Worked 0700-1900 shift in the Tagging Office.

02/05/16 Worked 0700-1900 shift as Unit 1 BOP.

02/06/16 Worked 0700-1900 shift as Unit 1 BOP.

03/14/16 Worked 1900-0700 shift as Unit 1 OATC.

03/17/16 Worked 1900-0700 shift in the Tagging Office.

Operator B License was active on January 1, 2016.

02/01/16 Worked 0700-1900 shift as Unit 1 OATC.

02/02/16 Worked 0700-1900 shift in the Tagging Office.

02/03/16 Worked 0700-1900 shift offloading New Fuel.

02/05/16 Worked 0700-1900 shift as Unit 1 OATC.

02/14/16 Worked 1900-0700 shift as Unit 1 OATC.

03/02/16 Worked 0700-1900 shift as the Backboards.

03/03/16 Worked 0700-1900 shift as the U1 BOP.

Operator C License was active on January 1, 2016.

03/12/16 Worked 0700-1900 shift as Unit 1 OATC.

03/13/16 Worked 0700-1900 shift as Unit 1 OATC.

03/15/16 Scheduled 0700-1900 shift as Unit 1 BOP.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> into the shift, had to leave due to a family emergency.

03/16/16 Worked 1900-0700 shift as Unit 1 OATC.

03/21/16 Worked 1900-0700 shift as Unit 1 OATC.

2016 NRC EXAM ADMIN CO 1 (RO)

Page: 3 of 8 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine active/inactive license status in accordance with OP-AA-103, Operator Qualifications TASK STANDARDS Operator license status is determined K/A

REFERENCE:

GEN-2.1.4 (3.3/3.8)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time =

15 minutes Start Time = _______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating

[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS

2016 NRC EXAM ADMIN CO 1 (RO)

Page: 4 of 8 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 Three Reactor Operators have the following history:

1. All three have off-shift assignments at the plant, are up to date in the License Operator Requalification Program (LORP), and have successfully completed their medical examination in the past year.

2. None of the 3 has worked any shift since April 1, 2016.

2016 NRC EXAM ADMIN CO 1 (RO)

Page: 5 of 8

3. Time worked on shift since January 1, 2016 for each of the Reactor Operators is provided on the attached sheet.

INITIATING CUE You are to determine if each of the Reactor Operators is qualified to stand the Unit 1 RO watch for the remainder of the 0700 - 1900 shift on April 1, 2016. Record your answer in the blanks below (yes or no).

Operator A. _____________________

Operator B. _____________________

Operator C. _____________________

EVALUATION METHOD Classroom TOOLS AND EQUIPMENT Laptop with access to DocTop or copy of OP-AA-103, Operator Qualifications PERFORMANCE STEPS START TIME 1

OP-AA-103 - Operator Qualifications is referenced by the candidate Procedure Step 3.1 SAT [ ] UNSAT [ ]

Notes/Comments

2016 NRC EXAM ADMIN CO 1 (RO)

Page: 6 of 8 2

Determine the Active / Inactive status of Operator A license.

Procedure Step 3.1 Critical Step SAT [ ] UNSAT [ ]

Standards Applicant determines the license is Active because the operator worked the required 5 complete twelve hour shifts in a qualifying license position during the previous quarter.

Notes/Comments This step is critical to ensure that the individual is qualified to stand license duties in the control room.

3 Determine the Active / Inactive status of Operator B license.

Procedure Step 3.1 Critical Step SAT [ ] UNSAT [ ]

Standards Applicant determines the license is Inactive because the operator did not work the required 5 complete twelve hour shifts in a qualifying license position during the previous quarter.

The excess RO is the 4th Licensed Operator on the board as per Ops Management.

Backboard watch does NOT count because it is not the operator of record on the Unit.

Notes/Comments This step is critical to ensure that the individual is qualified to stand license duties in the control room.

2016 NRC EXAM ADMIN CO 1 (RO)

Page: 7 of 8 4

Determine the Active / Inactive status of Operator C license.

Procedure Step 3.1 Critical Step SAT [ ] UNSAT [ ]

Standards Applicant determines the license is Inactive because the operator did not work the required 5 complete twelve hour shifts in a qualifying license position during the previous quarter.

Notes/Comments This step is critical to ensure that the individual is qualified to stand license duties in the control room.

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

STOP TIME

2016 NRC EXAM ADMIN CO 1 (RO)

Page: 8 of 8 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS You are the Shift Manager on day shift (0700-1900) and are at minimum manning.

The Unit 1 OATC leaves due to a medical emergency at 1000.

Empcenter and VPPQS are not available.

Three Reactor Operators are available for call out and have the following history:

1. All three have off-shift assignments at the plant, are up to date in the License Operator Requalification Program (LORP), and have successfully completed their medical examination in the past year.

2. None of the 3 has worked on shift since April 1, 2016.

3. Time worked on shift since January 1, 2016 for each of the Reactor Operators is provided on the attached sheet.

INITIATING CUE You are to determine if each of the Reactor Operators is qualified to stand the Unit 1 RO watch for the remainder of the 0700 - 1900 shift on April 1, 2016. Record your answer in the blanks below (yes or no).

Operator A. _____________________

Operator B. _____________________

Operator C. _____________________

AND Determine any actions required by Tech Specs and any associated time limits.

2016 NRC EXAM ADMIN CO 1 (SRO)

Page: 2 of 10 Operator A License was active on January 1, 2016.

02/02/16 Worked 0700-1900 shift as Unit 1 OATC.

02/03/16 Worked 0700-1900 shift as Unit 1 OATC.

02/04/16 Worked 0700-1900 shift in the Tagging Office.

02/05/16 Worked 0700-1900 shift as Unit 1 BOP.

02/06/16 Worked 0700-1900 shift as Unit 1 BOP.

03/14/16 Worked 1900-0700 shift as Unit 1 OATC.

03/17/16 Worked 1900-0700 shift in the Tagging Office.

Operator B License was active on January 1, 2016.

02/01/16 Worked 0700-1900 shift as Unit 1 OATC.

02/02/16 Worked 0700-1900 shift in the Tagging Office.

02/03/16 Worked 0700-1900 shift offloading New Fuel.

02/05/16 Worked 0700-1900 shift as Unit 1 OATC.

02/14/16 Worked 1900-0700 shift as Unit 1 OATC.

03/02/16 Worked 0700-1900 shift as the Backboards.

03/03/16 Worked 0700-1900 shift as the U1 BOP.

Operator C License was active on January 1, 2016.

03/12/16 Worked 0700-1900 shift as Unit 1 OATC.

03/13/16 Worked 0700-1900 shift as Unit 1 OATC.

03/15/16 Scheduled 0700-1900 shift as Unit 1 BOP.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> into the shift, had to leave due to a family emergency.

03/16/16 Worked 1900-0700 shift as Unit 1 OATC.

03/21/16 Worked 1900-0700 shift as Unit 1 OATC.

2016 NRC EXAM ADMIN CO 1 (SRO)

Page: 3 of 10 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine active/inactive license status in accordance with OP-AA-103, Operator Qualifications and T.S. time limits for being below minimum manning requirements TASK STANDARDS Operator license status is determined for available personnel and T.S. time limits are determined K/A

REFERENCE:

GEN-2.1.4 (3.3/3.8)

GEN-2.1.5 (2.9/3.9)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time =

20 minutes Start Time = _______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating

[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS

2016 NRC EXAM ADMIN CO 1 (SRO)

Page: 4 of 10

2016 NRC EXAM ADMIN CO 1 (SRO)

Page: 5 of 10 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 Shift Manager on day shift (0700-1900) and are at minimum manning.

The Unit 1 OATC leaves due to a medical emergency at 1000.

Empcenter and VPPQS are unavailable.

2016 NRC EXAM ADMIN CO 1 (SRO)

Page: 6 of 10 Three Reactor Operators are available for call out and have the following history:

1. All three have off-shift assignments at the plant, are up to date in the License Operator Requalification Program (LORP), and have successfully completed their medical examination in the past year.

2. None of the 3 has worked on shift since April 1, 2016.

3. Time worked on shift since January 1, 2016 for each of the Reactor Operators is provided on the attached sheet.

INITIATING CUE You are to determine if each of the Reactor Operators is qualified to stand the Unit 1 RO watch for the remainder of the 0700 - 1900 shift on April 1, 2016. Record your answer in the blanks below (yes or no).

Operator A. _____________________

Operator B. _____________________

Operator C. _____________________

AND Determine any actions required by Tech Specs and any associated time limits.

EVALUATION METHOD Classroom TOOLS AND EQUIPMENT Laptop with access to DocTop OR Copies of the following:

Technical Specifications OP-AA-103, Operator Qualifications OP-AA-100, Conduct of Operations PERFORMANCE STEPS START TIME

2016 NRC EXAM ADMIN CO 1 (SRO)

Page: 7 of 10 1

OP-AA-103 - Operator Qualifications is referenced by the candidate Procedure Step 3.1 SAT [ ] UNSAT [ ]

Notes/Comments 2

Determine the Active / Inactive status of Operator A license.

Procedure Step 3.1 Critical Step SAT [ ] UNSAT [ ]

Standards Applicant determines the license is Active because the operator worked the required 5 complete twelve hour shifts in a qualifying license position during the previous quarter.

Notes/Comments This step is critical to ensure that the individual is qualified to stand license duties in the control room.

2016 NRC EXAM ADMIN CO 1 (SRO)

Page: 8 of 10 3

Determine the Active / Inactive status of Operator B license.

Procedure Step 3.1 Critical Step SAT [ ] UNSAT [ ]

Standards Applicant determines the license is Inactive because the operator did not work the required 5 complete twelve hour shifts in a qualifying license position during the previous quarter.

The excess RO is the 4th Licensed Operator on the board as per Ops Management.

Backboard watch does NOT count because it is not the operator of record on the Unit.

Notes/Comments This step is critical to ensure that the individual is qualified to stand license duties in the control room.

4 Determine the Active / Inactive status of Operator C license.

Procedure Step 3.1 Critical Step SAT [ ] UNSAT [ ]

Standards Applicant determines the license is Inactive because the operator did not work the required 5 complete twelve hour shifts in a qualifying license position during the previous quarter.

Notes/Comments This step is critical to ensure that the individual is qualified to stand license duties in the control room.

2016 NRC EXAM ADMIN CO 1 (SRO)

Page: 9 of 10 5

Determine manning requirements in accordance with Tech Specs.

Procedure Step T.S. 5.2.2.b Critical Step SAT [ ] UNSAT [ ]

Standards Applicant determines TS 5.2.2.b is applicable, and manning must be restored to minimum no later than 1200.

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

Notes/Comments

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

STOP TIME

2016 NRC EXAM ADMIN CO 1 (SRO)

Page: 10 of 10 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Plant computer is operable.

Unit is stable at 96% power All ex-core power-range channels are operable, and pictures of the current readings are attached A partially marked up copy of 1-PT-23 is provided for you.

The SRO desires that the current meters on the Power Range Drawers be used.

INITIATING CUE You are requested to perform a quadrant power tilt ratio determination by hand calculation in accordance with 1-PT-23. Inform the examiner of the results.

2016 NRC EXAM Admin JPM CO-2 Page: 2 of 10 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM R709 TASK Determine the quadrant power tilt ratio by hand calculation (1-PT-23).

TASK STANDARDS Power range current readings correctly recorded, normalized currents and QPTR calculated to the correct # of decimal places K/A

REFERENCE:

GEN 2.1.7 (4.4/4.7)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES RO Validation Time =

20 minutes Start Time = _______

Actual Time = _______ minutes Stop Time = _______

SRO Validation Time = 25 minutes Start Time = _______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating

[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date

2016 NRC EXAM Admin JPM CO-2 Page: 3 of 10 EVALUATOR'S COMMENTS

2016 NRC EXAM Admin JPM CO-2 Page: 4 of 10 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)

OPERATOR PROGRAM R709 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 Reactor Operator level.

INITIAL CONDITIONS Plant computer is operable.

Unit is stable at 96% power All ex-core power-range channels are operable, and pictures of the current readings are attached A partially marked up copy of 1-PT-23 is provided for you.

The SRO desires that the current meters on the Power Range Drawers be used.

2016 NRC EXAM Admin JPM CO-2 Page: 5 of 10 INITIATING CUE You are requested to perform a quadrant power tilt ratio determination by hand calculation in accordance with 1-PT-23. Inform the examiner of the results.

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 Calculator PERFORMANCE STEPS START TIME 1

Check Initial Conditions are satisfied and Review precautions and limitations.

Procedure Sections 3 and 4 SAT [ ] UNSAT [ ]

Standards Initial Conditions are verified and Precautions and limitations have been reviewed Notes/Comments Initial Conditions were previously signed off. Applicant may or may not review.

2016 NRC EXAM Admin JPM CO-2 Page: 6 of 10 2

Request the shift manager to direct an instrument technician to determine the channel current for each power-range detector, if desired.

Procedure Attachment 2 Step 1 SAT [ ] UNSAT [ ]

Simulation Cue(s) The shift manager has determined that the indications on the power range drawers are to be used Notes/Comments 3

Record the power-range detectors' current readings.

Procedure Attachment 2 Step 2 Critical Step SAT [ ] UNSAT [ ]

Standards Detectors' current readings ("A" and "B") for each power-range drawer are recorded to within 5 uamps of the actual current readings Notes/Comments

2016 NRC EXAM Admin JPM CO-2 Page: 7 of 10 4

Record the expected 100% power current readings from the Reactor Data Book.

Given data Critical Step SAT [ ] UNSAT [ ]

Standards Expected 100% power current readings from the Reactor Data Book should be transcribed correctly onto the PT.

Notes/Comments 5

Calculate the normalized detector currents.

Procedure Attachment 2 Page 3 Critical Step SAT [ ] UNSAT [ ]

Standards Normalized detector currents are calculated to four decimal places per the attached Answer Key.

Notes/Comments

2016 NRC EXAM Admin JPM CO-2 Page: 8 of 10 6

Calculate the quadrant power tilt ratios.

Procedure Attachment 2 Page 3 Critical Step SAT [ ] UNSAT [ ]

Standards Upper and lower quadrant power tilt ratios are calculated to four decimals per the attached Answer Key.

Notes/Comments 7

Record the value and location of the largest quadrant power tilt ratio.

Procedure Attachment 2 Page 3 Critical Step SAT [ ] UNSAT [ ]

Standards Operator determines that the largest QPTR is 1.0500 1% (1.0395 to 1.0605) on the N41 Lower quadrant.

Notes/Comments

2016 NRC EXAM Admin JPM CO-2 Page: 9 of 10 8

Verify that each measured value meets the acceptance criteria cited in the procedure.

Procedure Section 7.1 Critical Step SAT [ ] UNSAT [ ]

Standards Operator determines that the QPTR does NOT meet the acceptance criteria guidelines.

Notes/Comments 9

Notify the shift manager that the periodic test has been completed and of any out of specification conditions.

Procedure Section 7.2 SAT [ ] UNSAT [ ]

Notes/Comments Operator would enter Tech Specs to determine if any Actions are required.

2016 NRC EXAM Admin JPM CO-2 Page: 10 of 10 SRO ONLY PORTION 10 Determine any required actions in accordance with Technical Specifications T.S. 3.5.4.a Critical Step SAT [ ] UNSAT [ ]

Cue The Shift Manager directs you to determine any required actions in accordance with Technical Specifications.

Standards Tech Specs require that power is reduced 3% from rated thermal power for each 1% of QPTR > 1.00. The acceptable range for a final answer is 82.66% power to 87.31% power.

Notes/Comments When debriefing the SRO on results of QPTR, have a copy of Tech Specs available.

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

STOP TIME

UNIT ONE PROCEDURE NO:

1-PT-23 NORTH ANNA POWER STATION REVISION NO:

30 PROCEDURE TYPE:

UNIT NO:

OPERATIONS PERIODIC TEST 1

PROCEDURE TITLE:

QUADRANT POWER TILT RATIO DETERMINATION TEST FREQUENCY:

UNIT CONDITIONS REQUIRING TEST:

• 7 days when the QPTR alarm is OPERABLE

• 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady state operation when the QPTR alarm is Inoperable Mode 1 above 50-percent rated thermal power SPECIAL CONDITIONS: None SURV REQ REACT MGT REVISION

SUMMARY

FrameMaker Template Rev. 030.

Issued Administrative Correction to remove Reactor Engineer from the Cover Sheet. Changed Verify to Check through-out the procedure without Rev. Bars.

• Incorporated Plant Issue N-2005-4402-R5, Enhancements to Maintenance Steps in other Department Procedures, by adding PI to reference section step 2.4.1.

• Deleted Fluke Model 8840 with from Special Tools and Equipment table in section 5.

• Changed Shift Supervisor to SRO throughout procedure due to title change.

REASON FOR TEST (CHECK APPROPRIATE BOX):

Surveillance Post-Maintenance Work Order Number (Post-Maintenance Only): ____________________

TEST PERFORMED BY (SIGNATURE):

DATE STARTED:

DATE COMPLETED:

TEST RESULT (CHECK APPROPRIATE BOX):

Satisfactory Unsatisfactory Partial WORK REQUEST NUMBERS AND DATE:

THE FOLLOWING PROBLEM(S) WERE ENCOUNTERED AND CORRECTIVE ACTIONS TAKEN:

______________________________________________________________________________ (Use back for additional remarks.)

COGNIZANT SUPERVISOR or DESIGNEE:

DATE:

ADDITIONAL REVIEWS:

DATE:

CONTINUOUS USE KEY

TABLE OF CONTENTS Section Page DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 2 of 15 1.0 PURPOSE 3

2.0 REFERENCES

4 3.0 INITIAL CONDITIONS 6

4.0 PRECAUTIONS AND LIMITATIONS 6

5.0 SPECIAL TOOLS AND EQUIPMENT 8

6.0 INSTRUCTIONS 9

7.0 FOLLOW-ON 9

ATTACHMENTS 1

Unit 1 PCS QPTR Calculation 11 2

QPTR Hand Calculation 13 KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 3 of 15 1.0 PURPOSE To provide instructions for determining the core Quadrant Power Tilt Ratio (QPTR) by Computer Calculation or by hand calculation as required by Tech Spec SR 3.2.4.1.

The following Synopsis is designed as an aid to understanding the procedure, and is not intended to alter or take the place of the actual purpose, instructions, or text of the procedure itself.

The Quadrant Power Tilt Ratio (QPTR) is defined in the Technical Specifications as the ratio of the maximum upper excore detector output to the average upper excore detector outputs, or the maximum lower excore detector calibrated output to the average of the lower excore detector outputs, whichever is greater. With one excore detector inoperable and power below 75% RTP, the remaining three detectors are used for computing the average. With one excore detector inoperable and power above 75% RTP, QPTR is monitored using 1-PT-23.1 or 1-PT-21.1. As per Tech Spec 3.2.4, the maximum QPTR is 1.02 when reactor power is above 50% of Rated Thermal Power. The purpose for this limit is as follows:

• To ensure that the radial power distribution satisfies design limits.

• To provide DNB protection with radial (x-y) power tilts.

• To provide linear heat generation rate protection for radial (x-y) power tilts.

• To ensure that FQ(z) and remain within limits.

The QPTR is monitored to limit any gross changes in the radial power distribution between full core flux maps. The QPTR alarm setpoint is set as low as possible without causing spurious alarms.

DCP 95-161 installed test jacks in the front of the power range detector drawers.

Since the current meters on the front of the power range drawer are prone to meter drift and static charge effects, these jacks are the preferred way to perform the QPTR calculation by hand if the Unit 1 PCS is inoperable. These test jacks allow a DMM to be easily used to measure the voltage drop across the precision resistor which is in parallel to the face meter. A conversion of 1 millivolt = 1 amp is then used to obtain the detector current.

FN H

KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 4 of 15 It should be noted that the test jacks may only be used if no Power Range Channel has been placed in trip. This satisfies the single failure criteria assumed in the safety analysis which permits use of the test jacks. If one Power Range Channel is in trip and the Unit 1 PCS is inoperable, then currents read from the meters on front of the power range drawers will have to be used in the QPTR calculations.

There are multiple methods of monitoring QPTR available to the OATC. These methods include the following:

• BOTH Annunciator Panel A-C7, NIS PR UP DET DEV-DEF <50% and Annunciator Panel A-C8, NIS PR LWR DET DEV-DEF <50%

• Annunciator Panel A-D4, CMPTR ALARM PR TILT

• PCS point #U1170 With reactor power between 50% and 75% RTP, QPTR may be calculated with only three operable Power Range Channels, in accordance with Tech Spec SR 3.2.4.1, although as a good practice the first QPTR calculation should be compared with a symmetric or full incore flux map, to account for the loss of accuracy when one power range channel is removed from the average. With reactor power 75% RTP or greater, and only three Power Range Channels operable, then this procedure is not necessary, in accordance with Tech Spec SR 3.2.4.2, and the symmetric or full incore flux map is used to determine QPTR.

2.0 REFERENCES

2.1 Source Documents 2.1.1 UFSAR Section 4.3.2.2, Power Distribution 2.1.2 UFSAR Section 4.4.2.4, Flux Tilt Considerations 2.1.3 UFSAR Section 4.4.5.1, Incore Instrumentation 2.1.4 UFSAR Section 4.4.5.3, Instrumentation to Limit Maximum Power Output 2.1.5 UFSAR Section 7.7.1.3.1, Monitoring Functions Provided by the Nuclear Instrumentation System KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 5 of 15 2.2 Technical Specifications 2.2.1 Tech Spec 3.2.4 2.2.2 Tech Spec SR 3.2.4.1 2.2.3 Tech Spec SR 3.2.4.2 2.2.4 Tech Spec SR 3.3.1.1, Table 3.3.1-1, Items 2 and 3 2.3 Technical References 2.3.1 1-PT-23.1, Quadrant Power Tilt Ratio Determination Using the Incore Detector System 2.3.2 1-PT-21.1, Reactor Core Flux Mapping 2.3.3 Control Room Reactor Data Book (NASES 3.05) 2.3.4 Calculational Basis, approved 03-13-86 2.3.5 Westinghouse Position Statement on Core Tilt, VRA-92-034 (3/18/92) 2.3.6 DCP 95-161, Install NI Power Range Test Points for Unit 1 2.3.7 DCP 96-005, P-250 Upgrade 2.3.8 DCP 01-007, Phase 2 PCS Installation and P-250 Removal - Unit 1 2.4 Commitment Documents 2.4.1 Plant Issue N-2005-4402-R5, Enhancements to Maintenance Steps in other Department Procedures KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 6 of 15 Init Verif 3.0 INITIAL CONDITIONS NOTE: IF power level is 75% or greater AND any power range detector is inoperable, THEN do not perform this PT. 1-PT-23.1, Quadrant Power Tilt Ratio Determination Using the Incore Detector System, must be performed.

3.1 IF power level is 75% or greater, THEN all 4 power range detectors are OPERABLE.

3.2 Check at least three Excore Power Range Channels are operable.

3.3 Check the Reactor is at a stable power level.

3.4 Notify SRO of this test.

NOTE: For the purposes of this procedure, the Unit 1 PCS is considered inoperable if any of the Power Range Channel inputs to the Unit 1 PCS are bad or unreliable.

3.5 IF the Unit 1 PCS is inoperable AND all four Excore Power Range Channels are operable, THEN notify the Instrument Department to send a technician with the equipment listed in Section 5.0 to the control room to measure voltages from the NI Power Range Detector drawer test jacks.

4.0 PRECAUTIONS AND LIMITATIONS 4.1 Comply with the following guidelines when marking steps N/A:

• IF the conditional requirements of a step do not require the action to be performed, THEN mark the step N/A.

• IF any other step is marked N/A, THEN have the SRO or designee approve the N/A AND submit a Procedure Action Request (PAR).

KB KB KB KB KB N/A KB KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 7 of 15 4.2 With input from one Power Range Channel inoperable and reactor power is less than or equal to 75% RTP, the remaining three power range channels can be used for calculating QPTR, in accordance with Tech Spec SR 3.2.4.1.

4.3 Observe the following when using the test jacks on the front of the NI Power Range Detector drawers:

• Only qualified individuals may use M&TE to measure the voltage from the test jacks.

• In order to ensure proper channel separation, connect a single DMM to only one NI Power Range Detector channel at a time. Both the Upper and Lower Detector test jacks of one Power Range Detector channel may be connected to the DMM at the same time.

• To further enhance channel isolation, do NOT connect multiple DMMs to the test jacks of two or more Power Range Detector channels at one time.

• To reduce the possibility of adversely impacting the NI Power Range Detector channels, minimize the amount of time the DMM is connected to the test jacks.

• To avoid possible signal spikes due to static charge on the test leads, ground test leads to drawer case and short together prior to making connection to test jacks.

• The DMM shall NOT be left unattended while connected to the NI Power Range Detector drawer.

• ALL Power Range Detector channels shall be checked to ensure no Trip signal is locked in on ANY channel prior to connecting the DMM to ANY drawer.

• The DMM should not be connected to the test jacks of an inoperable NI Power Range Detector channel.

4.4 IF one Power Range Detector channel is in trip AND the Unit 1 PCS is inoperable, THEN QPTR MUST be determined by Hand Calculation using currents read from the analog current meters on the front of the operable Power Range Detector channels. It should be noted that due to possible static charge effects on the meters, this is the least accurate method to determine QPTR.

KB KB N/A KB KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 8 of 15 5.0 SPECIAL TOOLS AND EQUIPMENT IF the Unit 1 PCS is inoperable AND all four Power Range Channels are operable, THEN do the following:

INST

• Obtain the equipment listed below and check the equipment is calibrated to standards traceable to the National Institute of Standards and Technology INST

• Obtain test leads to connect the DMM above to a double banana jack (0.75 inch centers).

INST

• Record the following for the Digital Multimeter:

NQC No.: _______________________ Cal Due Date:

M & TE Type Accuracy Requirement DMM At least 5 1/2 digits and 1000 Megohm input resistance on 2 VDC range N/A KB KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 9 of 15 6.0 INSTRUCTIONS NOTE: Sections OR Attachments of this procedure NOT used may be discarded.

6.1 IF one Power Range Channel has become inoperable and Thermal Power is less than 75 percent RTP, THEN do ONE of the following:

6.1.1 The first performance of this test shall be done concurrently with one of the following Periodic Test procedures. Mark procedure not performed N/A.

• 1-PT-23.1, Quadrant Power Tilt Ratio Determination Using the Incore Detector System

• 1-PT-21.1, Reactor Core Flux Mapping RX ENG 6.1.2 Obtain Reactor Engineer concurrence that an incore flux map is not required for comparison to the first QPTR calculation after the Power Range Channel has become inoperable.

NOTE: For the purposes of this procedure, the Unit 1 PCS is considered inoperable if the Power Range Channel inputs to the Unit 1 PCS are bad or unreliable.

6.2 Do at least one of the following to determine QPTR: Mark methods not used N/A.

• IF desired to use the Unit 1 PCS to determine QPTR, THEN complete, Unit 1 PCS QPTR Calculation.

• IF desired to perform a hand calculation to determine QPTR, THEN complete, QPTR Hand Calculation.

7.0 FOLLOW-ON 7.1 Acceptance Criteria 7.1.1 A QPTR has been determined from at least 3 Operable Excore Power Range detectors.

N/A KB N/A KB KB KB KB KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 10 of 15 7.1.2 IF the Unit is at a power level above 50 percent, THEN the QPTR is 1.02 or less.

7.2 Follow-On Tasks NOTE: Sections OR Attachments of this procedure NOT used may be discarded.

7.2.1 IF any QPTR Report(s) were obtained, THEN attach them to this procedure.

7.2.2 IF the Unit is at a power level above 50 percent AND the QPTR is greater than 1.02, THEN do the following:

• Notify the SRO.

• Enter Action Statement of Tech Spec Action 3.2.4.A.

7.2.3 IF the QPTR is greater than 1.015, THEN notify the Reactor Engineer.

7.3 Completion Notification Notify the SRO that this test is complete.

Completed by: ___________________________________________ Date: _________

ATTACHMENTS 1

KB KB KB KB KB Today K Blev KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 11 of 15 (Page 1 of 2)

Unit 1 PCS QPTR Calculation 1.

Determine the appropriate value for Unit 1 PCS constant K0829 below, () check one:

IF all Power Range Detector channels are operable, THEN K0829 should be 0.

IF N41 is inoperable, THEN K0829 should be 1.

IF N42 is inoperable, THEN K0829 should be 2.

IF N43 is inoperable, THEN K0829 should be 3.

IF N44 is inoperable, THEN K0829 should be 4.

2.

Display addressable constant K0829.

SV 3.

IF the present value of K0829 is NOT equal to the value determined in Step 1, THEN enter the appropriate value by selecting the UPDATE A CONSTANT button from the System Menu screen.

4.

Request a QPTR Report by doing the following:

4.1 Select the NSSS AND BOP button from the Main Screen.

4.2 Select the QPTR button from the NSSS Menu Screen.

4.3 Select the F4=Report button from the NI: Quadrant Power Tilt Ratio screen.

4.4 IF using PCS, THEN select PRINT to print the QPTR Report.

5.

WHEN the QPTR Report is complete, THEN remove the report from the printer and examine the report as follows:

5.1 IF any data is indicated as NCAL on the QPTR Report, THEN notify the Reactor Engineer for resolution.

KB N/A KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 12 of 15 (Page 2 of 2)

Unit 1 PCS QPTR Calculation 5.2 IF any data indicated as NCAL cannot be resolved, THEN QPTR CANNOT be determined using the Unit 1 PCS. Mark the remainder of this attachment N/A AND complete Attachment 2, QPTR Hand Calculation.

5.3 IF no data is indicated as NCAL on the QPTR Report, THEN sign off the Current Verification section of the QPTR Report.

6.

Compare the Expected 100-percent currents from the Reactor Data Notebook to the NI Power Range Detector channel currents on the QPTR Report.

7.

IF the Reactor Data Book Expected 100-percent currents match the Expected 100-percent currents on the QPTR Report, THEN sign off the QPTR Report for the expected 100-percent currents.

8.

IF the Reactor Data Book Expected 100-percent currents do NOT match the Expected 100-percent currents on the QPTR Report, THEN do the following:

8.1 Notify the Reactor Engineer to resolve the discrepancy.

8.2 IF discrepancy cannot be resolved, THEN QPTR CANNOT be determined using the Unit 1 PCS. Complete Attachment 2, QPTR Hand Calculation.

CAUTION The Expected 100-percent currents from the Reactor Data Notebook should be used. IF new currents are being installed and a mixture of OLD and NEW Expected 100-percent currents are used, THEN the QPTR will be inaccurate.

N/A KB KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 13 of 15 (Page 1 of 3)

QPTR Hand Calculation 1.

IF no Power Range Detector Channel is in trip AND the Unit 1 SRO desires that the test jacks be used, THEN determine the NI Power Range Detector channel currents for each channel by doing the following:

1.1 Notify the Instrument Department to send a technician with the equipment listed in Section 5.0 to the control room to measure voltages from the NI Power Range Detector drawer test jacks.

INST 1.2 Have the Instrument Department technician place the DMM on the 2 VDC scale.

INST 1.3 Have the Instrument Department technician ground the test leads to the drawer case and short together prior to making each connection to reduce the possibility of adversely impacting the Power Range Detector channel.

INST INST SV 1.4 TM: Have the Instrument Department technician connect the DMM to the test jacks of each NI Power Range Detector channel one at a time and read the voltage indicated on the meter to the nearest millivolt.

1.5 Determine each NI Power Range Detector channel current by using the conversion 1 millivolt = 1 amp.

1.6 Record the measured currents on Page 3 of this attachment.

INST INST 1.7 TM: Have the Instrument Department technician disconnect the DMM from the test jacks.

CAUTION To ensure adequate channel separation, only one NI Power Range Detector channel may be monitored at a time by a single DMM using the test jacks on the front of the drawers (See Precaution & Limitation Step 4.3).

KB N/A KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 14 of 15 (Page 2 of 3)

QPTR Hand Calculation 2.

IF one Power Range Channel is in trip OR the Unit 1 SRO desires that the current meters on the Power Range drawers be used, THEN read the current meters on the front of each operable Power Range upper and lower Detector Channel AND record the measured currents on Page 3 of this attachment.

3.

IF the Unit 1 PCS is operable AND the Unit 1 SRO desires to use the Unit 1 PCS to obtain Current Readings, THEN do the following:

3.1 Request a QPTR Report by doing the following on the Unit 1 PCS:

a.

Select the NSSS AND BOP button from the Main Screen.

b.

Select the QPTR button from the NSSS Menu Screen.

c.

Select the F4=Report button from the NI: Quadrant Power Tilt Ratio screen.

d.

IF using PCS, THEN select PRINT to print the QPTR Report.

3.2 WHEN the QPTR Report is complete, THEN remove the report from the printer.

3.3 Using the QPTR Report, record the appropriate current readings in the Current Reading spaces provided on Page 3 of this attachment.

4.

Complete the calculations on Page 3 of this attachment.

5.

Have a qualified individual complete an independent verification of all calculations.

KB KB N/A KB KB KEY

DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 15 of 15 (Page 3 of 3)

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.

Description N-41 Upper N-42 Upper N-43 Upper N-44 Upper Avg. of Upper Normalized Currents Current Reading (record to nearest a)

Expected Current (record as shown in Reactor Data Book or 1-PT-22.4)

Normalized Current (Current Reading / Expected Current)

(4 decimal places)

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

(4 decimal places)

Description N-41 Lower N-42 Lower N-43 Lower N-44 Lower Avg. of Lower Normalized Currents Current Reading (record to nearest a)

Expected Current (record as shown in Reactor Data Book or 1-PT-22.4)

Normalized Current (Current Reading / Expected Current)

(4 decimal places)

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

(4 decimal places)

Maximum QPTR: _________________________________

(Record Maximum Upper or Lower QPTR Value from above)

Quadrant of Max QPTR: _________________________________

(N41 Upper, N41 Lower N42 Upper, N42 Lower, etc.)

Completed by: __________________________________________

Date: ________

Verified by:_____________________________________________

Date/Time Verification Completed: ________________________________ (Use this Time for recording when surveillance is completed) 170 175 165 200 172.1 200.9 168.8 201.9

.9878

.8711

.9775

.9906

.9567 1.0325.9105 1.0217 1.0354 210 190 210 215 203.8 213.4 208.1 216.0 1.0304.8903 1.0091.9954

.9813 1.0500.9073 1.0283 1.0143 1.0500 N-41 Lower 4/14/16 Today / Now K Blev Emmett Brown KEY 8

1.0324 1.0216 1.0353 1.0144 1.0500 0.9073 1.0283 0.9104

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Reactor power is 100%.

Control rods are fully withdrawn at 227 steps.

Core burnup is 15,500 MWD/MTU Reactor Coolant System boron concentration was determined 15 minutes ago to be 600 ppm.

No dilutions have occurred since the last Reactor Coolant System boron concentration was determined Two control rods on D bank are inoperable and unable to be tripped.

INITIATING CUE You are requested to perform 1-PT-10.1, SDM Determination at Power with Inoperable or Misaligned Control Rods, beginning at Step 6.0. Inform the examiner of your results.

2016 NRC EXAM Admin JPM EC (ALL)

Page: 2 of 9 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM R98 TASK Determine the shutdown margin at power with inoperable control rods (1-PT-10.1).

TASK STANDARDS Task was performed as directed by the procedure referenced in the task statement within parentheses (one of the underlined procedures if several are cited)

K/A

REFERENCE:

GEN 2.1.7 (4.4/4.7)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time =

30 minutes Start Time = _______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating

[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS

2016 NRC EXAM Admin JPM EC (ALL)

Page: 3 of 9 Dominion North Anna Power Station JOB PERFORMANCE MEASURE (Evaluation)

OPERATOR PROGRAM R98 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 Reactor Operator level.

2016 NRC EXAM Admin JPM EC (ALL)

Page: 4 of 9 INITIAL CONDITIONS Reactor power is 100%.

Control rods are fully withdrawn at 227 steps.

Reactor Coolant System boron concentration was determined 15 minutes ago to be 600 ppm.

No dilutions have occurred since the last Reactor Coolant System boron concentration was determined Two control rods on D bank are inoperable and unable to be tripped.

INITIATING CUE You are requested to perform 1-PT-10.1, SDM Determination at Power with Inoperable or Misaligned Control Rods, beginning at Step 6.0. Inform the examiner of your results.

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 Calculator Curve book or laptop with access to Doc Top PERFORMANCE STEPS START TIME

2016 NRC EXAM Admin JPM EC (ALL)

Page: 5 of 9 1

Verify that the initial conditions, precautions, and limitations are met.

Procedure Sections 3 and 4 SAT [ ] UNSAT [ ]

Notes/Comments 2

Record the current critical conditions.

Procedure Attachment 1 page 1 SAT [ ] UNSAT [ ]

Notes/Comments 3

Record the instantaneous shutdown conditions.

Procedure Attachment 1 page 2 SAT [ ] UNSAT [ ]

Notes/Comments

2016 NRC EXAM Admin JPM EC (ALL)

Page: 6 of 9 4

Record the sum of the current critical conditions.

Procedure Attachment 1 page 2 Critical Step SAT [ ] UNSAT [ ]

Standards Sum is determined to be -2650 pcm 100 pcm Notes/Comments 100 pcm delta is given due to graph interpolation.

5 Record the sum of the instantaneous shutdown conditions.

Procedure Attachment 1 Step 17 Critical Step SAT [ ] UNSAT [ ]

Standards Sum is determined to be -991 100 pcm Notes/Comments 100 pcm delta is given due to graph interpolation.

2016 NRC EXAM Admin JPM EC (ALL)

Page: 7 of 9 6

Record the difference between the current critical conditions and the instantaneous shutdown conditions.

Procedure Attachment 1 Step 17 Critical Step SAT [ ] UNSAT [ ]

Standards Difference is calculated to be 1659 200 pcm.

Notes/Comments Using values (including +/- 100 pcm interpolation error) from steps 4 and 5 7

If necessary, calculate the boron concentration required to achieve a shutdown margin of at least 1.77% K/K.

Procedure Attachment 1 Step 18 Critical Step SAT [ ] UNSAT [ ]

Standards Change in boron concentration required for the shutdown margin was determined to be 482 ppm 29 ppm Notes/Comments 29 ppm was determined using the interpolation criteria listed above, and substituting the min/max values into the equation.

8 Verify that the acceptance criteria cited in the procedure have been met.

Procedure Section 7 SAT [ ] UNSAT [ ]

Notes/Comments

2016 NRC EXAM Admin JPM EC (ALL)

Page: 8 of 9

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

STOP TIME

2016 NRC EXAM Admin JPM EC (ALL)

Page: 9 of 9 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)

UNIT ONE PROCEDURE NO:

1-PT-10.1 NORTH ANNA POWER STATION REVISION NO:

13 PROCEDURE TYPE:

UNIT NO:

OPERATIONS PERIODIC TEST 1

PROCEDURE TITLE:

SHUTDOWN MARGIN DETERMINATION AT POWER WITH INOPERABLE OR MISALIGNED CONTROL RODS TEST FREQUENCY:

UNIT CONDITIONS REQUIRING TEST:

• Within one hour after detection of an inoperable or misaligned control rod.

• At Least Once per 12 Hours while a rod is misaligned.

Modes 1 and 2 SPECIAL CONDITIONS: None SURV REQ EOP AP REACT MGT REVISION

SUMMARY

• Incorporated OP 08-0080 Shutdown Margin Calculation as follows:

• Added Step 7.3.1 Record results in the Narrative Log to include actual or projected shutdown margin PCM value.

REASON FOR TEST (CHECK APPROPRIATE BOX):

Surveillance Post-Maintenance Work Order Number (Post-Maintenance Only): ____________________

TEST PERFORMED BY (SIGNATURE):

DATE STARTED:

DATE COMPLETED:

TEST RESULT (CHECK APPROPRIATE BOX):

Satisfactory Unsatisfactory Partial WORK REQUEST NUMBERS AND DATE:

THE FOLLOWING PROBLEM(S) WERE ENCOUNTERED AND CORRECTIVE ACTIONS TAKEN:

______________________________________________________________________________ (Use back for additional remarks.)

COGNIZANT SUPERVISOR or DESIGNEE:

DATE:

ADDITIONAL REVIEWS:

Reactor Engineering:

DATE:

CONTINUOUS USE KEY KEY

TABLE OF CONTENTS Section Page DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 2 of 14 1.0 PURPOSE 3

2.0 REFERENCES

3 3.0 INITIAL CONDITIONS 4

4.0 PRECAUTIONS AND LIMITATIONS 5

5.0 SPECIAL TOOLS AND EQUIPMENT 6

6.0 INSTRUCTIONS 7

7.0 FOLLOW-ON 7

ATTACHMENTS 1

Shutdown Margin Determination 9

2 Detailed Description of Shutdown Margin Determination 12 KEY KEY

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 3 of 14 1.0 PURPOSE To provide instructions for verifying that the instantaneous Shutdown Margin is at least 1.77% k/k when operating in Modes 1 and 2 with one or more inoperable or dropped Control Rods, or with Control Rods of a single bank inserted out of sequence 18 steps from the Fully Withdrawn Position, per Tech Spec 3.1.4, 3.1.5, or 3.1.6.

This procedure may only be performed in Modes 1 or 2 to determine the instantaneous SDM that is available if the Unit tripped. If the Unit is in Modes 3, 4, or 5 with untrippable control rods, then 1-PT-10A, Shutdown Margin Determination - Hand Calculation, will have to be performed., Detailed Description of Shutdown Margin Determination, provides a detailed description of the methodology used in the Shutdown Margin determination.

2.0 REFERENCES

2.1 Source Documents 2.1.1 UFSAR Section 1.2.4, Control and Instrumentation 2.1.2 UFSAR Section 4.3.1.5, Shutdown Margin 2.1.3 UFSAR Section 4.3.2.4, Control Requirements 2.1.4 UFSAR Section 4.3.2.5.2, Rod Cluster Control Assemblies 2.1.5 UFSAR Section 4.3.2.6, Control Rod Patterns and Reactivity Worth 2.2 Technical Specifications 2.2.1 Tech Spec 3.1.1 2.2.2 Tech Spec 3.1.4 2.2.3 Tech Spec 3.1.5 2.2.4 Tech Spec 3.1.6 KEY KEY

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 4 of 14 2.3 Technical References 2.3.1 1-SC-3.4, Boron Coefficient vs Burnup For Zero Percent Power 2.3.2 1-SC-3.5, HZP Integral Worth Plot For Control Banks C and D In Overlap 2.3.3 1-SC-3.8, Power Defect 2.3.4 1-SC-8.1, PT-10 Rod Worth Data 2.3.5 1-SC-8.3, Shutdown Margin Data 2.3.6 1-SC-8.4, Reactivity Redistribution Factor vs Burnup 2.3.7 1-SC-8.5, N-1 Total Rod Worth vs Burnup 2.3.8 Calculational Basis, approved 10-14-87 and 4-17-89 (Revision 3) 2.3.9 Calculation SM-753 of 10-11-90, Re-evaluation of North Anna EOP Setpoint J4.

2.3.10 Engineering Transmittal NAF-980057, Rev. 0 Proposed Operator Response and Shutdown Margin Information For Incomplete Rod Insertion.

2.3.11 OE 13496, Excessive Boration For Dropped Rod, ANO Unit 2, 11/1/2001 (Revision 11) 2.4 Commitment Documents 2.4.1 CTS Assignment 02-94-1802, Commitment 003, Incorporate Unit 1 Tech Spec Amendment 179, Control Rod Urgent Failure Tech Spec Change.

Init Verif 3.0 INITIAL CONDITIONS 3.1 Verify the RCS boron concentration has been determined in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

KB KEY KEY

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 5 of 14 3.2 Verify no dilutions to the RCS have been performed since the most recently measured boron concentration.

3.3 Ensure the unit has not operated for more than four Effective Full Power Days since the last Cycle Burnup recorded in the Previous Critical Conditions data section of the Control Room Reactor Data Book OR contact the Reactor Engineer for the Cycle Burnup to use in the calculations.

3.4 Verify the unit is in Mode 1 or Mode 2 with one or more inoperable or dropped Control Rods, OR with Control Rods of a single bank inserted out of sequence (misaligned) up to 18 steps from the Fully Withdrawn Position.

3.5 Notify the SRO of this test.

4.0 PRECAUTIONS AND LIMITATIONS 4.1 Comply with the following guidelines when marking steps N/A:

• IF the conditional requirements of a step do not require the action to be performed, THEN mark the step N/A.

• IF any other step is marked N/A, THEN have the SRO or designee approve the N/A AND submit a Procedure Action Request (PAR).

4.2 Tech Specs require the Shutdown Margin to be at least 1.77% k/k. This corresponds to a shutdown core reactivity equal to or more negative than -1770 pcm with the highest worth control rod withdrawn.

4.3 Tech Spec 3.1.1 is not applicable in Mode 1 or in Mode 2 with Keff >1.0.

KB KB KB KB KB KB KB KB KB KEY KEY

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 6 of 14 4.4 Tech Spec 3.1.4 applies in Mode 1 or in Mode 2 during conditions of:

• One or more inoperable shutdown or control rod

• One or more misaligned shutdown or control rod 4.5 The following Tech Specs apply during conditions of one Shutdown Bank or one Control Bank being immovable below its insertion limit: (Reference 2.4.1)

• Tech Spec 3.1.5

• Tech Spec 3.1.6 4.6 WHEN recording values on Attachment 1, Shutdown Margin Determination, from Station Curves, THEN use plus (+) or minus (-) signs as indicated on the curves.

4.7 Reference 2.3.9 states that the second stuck control rod may be worth up to 1.55 times the worth of the single highest worth rod stuck. This is accounted for in Item 12 on Attachment 1 by increasing the value of Item 9 by 0.55 in the calculations.

5.0 SPECIAL TOOLS AND EQUIPMENT None KB KB KB KB KB KB KB KB KB KEY KEY

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 7 of 14 6.0 INSTRUCTIONS 6.1 Record the required values in Items 1 through 15 on Attachment 1, Shutdown Margin Determination.

6.2 Record the sum of Items 11 through 16 for each column, Instantaneous Shutdown Conditions and Current Critical Conditions, in Item 17 on Attachment 1.

6.3 Record the difference of the sums from Step 6.2 in Item 17 on Attachment 1. This final value is the amount of instantaneous reactivity by which the Reactor would be shut down if tripped with the highest Worth Rod Withdrawn and any inoperable or dropped rods in their present positions.

6.4 IF the value recorded in Step 6.3 is less negative than -1770 pcm, THEN calculate and record in Item 18 on Attachment 1 the change in boron concentration required to achieve a Shutdown Margin of at least 1.77% k/k.

7.0 FOLLOW-ON 7.1 Acceptance Criteria 7.1.1 The Shutdown Margin with Inoperable or Misaligned Control Rods was determined.

7.1.2 The final value recorded in Item 17 on Attachment 1 is equal to or more negative than -1770 pcm.

7.2 Follow-On Tasks 7.2.1 IF the final value recorded in Item 17 on Attachment 1 is less negative than

-1770 pcm, THEN do the following:

a.

IF the unit is in Mode 2 with Keff <1.0, THEN start a boration within 15 minutes and enter the Action Statement of Tech Spec 3.1.1.

b.

Start a boration in accordance with the applicable Action Statement of Tech Spec 3.1.4, 3.1.5, or 3.1.6.

KB KB KB KB KB KB 1

KB KB N/A KEY KEY

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 8 of 14 7.3 Completion Notification 7.3.1 Record results in the Narrative Log to include actual or projected shutdown margin PCM value.

7.3.2 Notify the SRO this test is complete.

Completed by: ___________________________________________ Date: _________

ATTACHMENTS KB KB 4/14/16 K. Chuck Bartowski KEY KEY

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 9 of 14 (Page 1 of 3)

Shutdown Margin Determination Current Critical Conditions 1.

Date:

2.

Time:

3.

Core Burnup (MWD/MTU):

4.

Power (%):

5.

C Bank Position (steps):

6.

D Bank Position (steps):

7.

Boron Concentration (ppm):

8.

Boron Worth Coefficient (pcm/ppm):

(1-SC-3.4)

NOTE: IF no rods are untrippable or dropped, THEN Items 9-10 should be marked N/A.

NOTE: A single dropped rod indicating 10 steps or less is NOT counted as an untrippable or dropped rod in Item 9. (Reference 2.3.11) 9.

Number of Untrippable or Dropped Rods:

10.

Stuck Rod Worth (pcm):

(1-SC-8.1 or 8.3)

Today Now 15,500 100 227 227 600

- 7.12 2

1634 KEY KEY

-7.12

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 10 of 14 (Page 2 of 3)

Shutdown Margin Determination Instantaneous Shutdown Conditions Current Critical Conditions 11.

Rod Worth (pcm).

(1-SC-8.5)

(1-SC-3.5, At -Power or HZP Worth as appropriate)

NOTE: IF no rods are untrippable or dropped, THEN Item 12 is 0.

12.

Untrippable or dropped Rod Worth (pcm):

0 NOTE: IF no control rods of a single bank are inserted out of sequence, THEN use 0 pcm for Current Critical Conditions in Step 13.

13.

Worth of Single Rod Bank inserted up to 18 steps from fully withdrawn position (pcm):

0 (1-SC-8.1) 14.

Reactivity Redistribution Factor (pcm):

(1-SC-8.4) 0 15.

Power Defect (pcm):

0 (1-SC-3.8) 16.

Reactivity Worth of up to 8 Rods stuck at 10 steps.

100 0

17.

Totals:

=

pcm Item 9 0.55

+

Item 10

x

=

-5588 0

2 1634 4167 0

330

-2650

-991

-2650 1659 KEY KEY

-5588

-2650

-891 to -1091

-2550 to -2750 1459 to 1859

-991 pcm +/-100 pcm for graph interpolation

-2650 pcm +/-100 pcm for graph interpolation

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 11 of 14 (Page 3 of 3)

Shutdown Margin Determination 18.

Determine Required Boron Concentration Change (CB) as Follows:

(-1770 pcm) pcm (Item 17)

CB

(

)

---

ppm

=

---

pcm/ppm (Item 8) 1659

-7.12 482 KEY KEY 1459 to 1859 453 to 511

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 12 of 14 (Page 1 of 3)

Detailed Description of Shutdown Margin Determination The following synopsis is designed as an aid to understanding the procedure, and is not intended to alter or take the place of the actual purpose, instructions or text of the procedure itself.

Tech Specs require the SDM to be within the limits specified in the COLR. The value of 1.77% k/k is deeply embedded in the Safety Analysis and is not likely to change, so the value of 1.77% k/k and related values are left in the procedure.

This procedure determines if the core can be instantaneously shutdown by 1.77%

k/k (1770 pcm) if all trippable control rods are inserted except the Most Reactive Control Rod (MRR) which remains fully withdrawn. This is done by using measured previous critical conditions and incorporating the reactivity effects of control rods insertion, and reactor power reduction. The factors that determine Shutdown Margin (SDM) are typically functions of several parameters and it is important that the various terms used in the SDM equation not omit or doubly account for any of these effects. SDM is calculated in this procedure by assuming the following sequence of events occurs while the core shuts down:

• The control rods are withdrawn fully while at the previous critical conditions power level. This is accounted for in the At-Power Control Banks D and C Worth in Normal Overlap (RW Prev Crit) and the Worth of a Single Rod Bank inserted out of sequence up to 18 steps from the Fully Withdrawn Position (RW Out of Seq).

Note that if the previous critical conditions were at zero power, then the HZP Control Banks D and C Worth in Normal Overlap would be used instead. This rod worth is unavailable for shutting down the reactor since the negative reactivity worth has already been compensated for by other means (reduced boron concentration, reduced power level, etc.)

KEY KEY

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 13 of 14 (Page 2 of 3)

Detailed Description of Shutdown Margin Determination

• The core power level was reduced from the previous critical conditions power level to zero power, 547° F conditions. This is accounted for in the Power Defect and Reactivity Redistribution Factor (RRF). Note that the change in worth of both the soluble boron and the xenon as the core power level is reduced to zero percent is included in the Power Defect. The RRF conservatively accounts for effects of possible extended operation with Control Bank D inserted and/or operating with the RCS temperature up to 2° F above program Tave which are not included in the Power Defect.

• While at zero power, 547° F, the control rods are inserted from the Fully Withdrawn Position with the most reactive rod (MRR) and any additional known stuck or otherwise untrippable rods (SRW) remaining out of the core. This is accounted for in the N-1 rod worth (RW ARI-MRR) and the MRR worth.

It is recognized that the events mentioned above actually occur simultaneously or in a different sequence than listed. However, the exact sequence of events of how the core went from the previous critical conditions to the shutdown conditions is not important, only that the correct starting and ending statepoint conditions are used.

Combining these terms mentioned above into an equation for SDM results in the following:

SDM = (RW ARI-MRR + SRW + RRF) - (RW Prev Crit + RW Out of Seq + Power Defect)

If sufficient SDM exists, then SDM will be calculated to be equal to or more negative than -1770 pcm.

KEY KEY

DOMINION 1-PT-10.1 North Anna Power Station Revision 13 Page 14 of 14 (Page 3 of 3)

Detailed Description of Shutdown Margin Determination It should be noted that several terms that are usually considered for SDM are absent from the above calculations. The reason for their omission is described below:

• No RCS boron concentration changes are assumed to occur due to the instantaneous nature of the SDM calculation. No values for Boron Worths are needed.

• No changes in isotopic concentrations are assumed to occur due to the instantaneous nature of the calculation. This means that there are no xenon concentration changes and the only xenon worth change (from At-Power to zero power) is already included in the Power Defect term.

• Based on the assumed lack of changes in isotopic concentrations, the Net Isotopic Decay Reactivity will be 0 pcm since it is used to account for plutonium decay, samarium increase, and changes in other isotopic concentrations.

• Since this is an instantaneous calculation, the RCS is assumed to remain at the no-load Tave of 547° F with no additional cooldown. Since the Temperature Defect is by definition 0 pcm at 547° F, it is not included in the calculations.

To account for the possibility that some control rods may not fully insert and actually be at 10 steps or less withdrawn, the available shutdown margin will be reduced by 100 pcm. This will account for a conservatively grouped set of 8 rods stuck at 10 steps.

A single dropped rod indicating 10 steps or less is also included in the 100 pcm penalty. Therefore, for shutdown margin calculations, only a dropped rod indicating greater than 10 steps requires an additional penalty above the 100 pcm. In this case, the dropped rod is counted as an equivalent stuck rod in the Shutdown Margin calculation.

If a dropped rod occurs while the Reactor is critical and Tref is matched to Tave with no RCS dilutions, then there is no change in Shutdown Margin.

KEY KEY

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 2 is shutdown. The A Cold Leg Loop Stop Valve MOV has stopped in mid-position and must be locally closed by the hand wheel.

The dose rates are shown on the attached Unit 2 Containment, 262 Elevation A Motor Cube.

It will take 15 minutes to locally close the valve; assume no dose is accumulated in transit to or from the work location.

Your accumulated dose this quarter is 300 mrem.

INITIATING CUE You are directed to determine the maximum stay time AND the correct RWP task number (16-2229-1 or 16-2229-2).

1.

The correct RWP is 2.

The maximum stay time is minutes.

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine the following:

Correct RWP and subtask Dose Alarm Dose Rate Alarm Stay Time (Maximum and Allowed by RWP)

TASK STANDARDS The operator determines the previously listed variables successfully.

KIA

REFERENCE:

GEN 2.3.7 (3.5/3.6)

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 I Date EVALUATORS COMMENTS 2016 NRC EXAM Page: 2 of 8 Admin JPM RadCon (ALL)

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 Unit 2 is shutdown. The A Cold Leg Loop Stop Valve MOV has stopped in mid-position and must be locally closed by the hand wheel.

The dose rates are shown on the attached Unit 2 Containment, 262 Elevation A Motor Cube.

It will take 15 minutes to locally close the valve; assume no dose is accumulated in transit to or from the work location.

Your accumulated dose this quarter is 300 mrem.

INITIATING CUE You are directed to determine the maximum stay time AND the correct RWP task number (16-2229-1 or 16-2229-2).

2016 NRC EXAM Page: 3 of 8 Admin JPM RadCon (ALL)

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 PERFORMANCE STEPS START TIME 1

From the RWPs provided determine which RWP is applicable for Procedure Step the job.

RWP 16-2229-2 critical Step SAT[]

UNSAT[J I Standards

[

RWP 10-2229-2 is seleotod from the two RWPo provided.

t(p-22 Ta.5K t c-CLec4e-4.

Noes RWP 16-2229-1 is not correct due to cc Id exceed the alarm setpoint.

RWP 16-2229-2 is the correct RWP and subtask.

?os-- Ey

%4wett

%U-t-J4A3Ot 2016 NRC EXAM Admin JPM RadCon (ALL)

Page: 4 of 8

2 Determine the maximum stay time Procedure Step:

RWP 16-2229-2 Critical Step SAT[J UNSAT[]

Standards If RWP Task I is selected then use the following calculation:

Operator uses RWP to determine dose alarm is set at 10 mRem.

Operator determines from the RWP (Worker Instruction #4) that the Operator must place the plant in a sate condition and leave the area once 80% of the dose alarm setpoint is reached.

Operator determines that they must leave the area after l6mRem of dose has been achieved. (80%

• 10 mRem 8 mRem)

Operator uses survey map to determine general area dose rate is 80 mR/hr.

Operator then divides 8 by 80 to obtain a stay time of 6 minutes

(.10 hrs).

If RWP Task 2 is selected then use the following calculation:

Operator uses RWP to determine dose alarm is set at 20 mRem.

Operator determines from the RWP (Worker Instruction #4) that the Operator must place the plant in a safe condition and leave the area once 80% of the dose alarm setpoint is reached.

Operator determines that they must leave the area after l6mRem of dose has been achieved. (80%

• 20 mRem = 16 mRem)

Operator uses survey map to determine general area dose rate is 80 mR/hr.

Operator then divides 16 by 80 to obtain a stay time of 12 minutes

(.20 hrs).

Notes/Comments:

END OF EVALUATION 2016 NRC EXAM Page: 5 of 8 Admin JPM RadCon (ALL)

STOP TIME 2016 NRC EXAM Page:6of8 Admin JPM RadCon (ALL)

Answer Key

?o Eyv Mkb41(-t ML tti4A3oI 1.

The correct RWP is 16 222-2 Ta-t b C 2

2.

The maximum stay time is RWP Task 1: 6 minutes (or the equivalent =.10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> or 1/10 hour), RWP Task 2:12 minutes (or the equivalent

.20 hour2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> or 1/5 hour).

2016 NRC EXAM Page: 7 of 8 Admin JPM RadCon (ALL)

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

ADMINISTRATIVE JOB PERFORMANCE MEASURE TASK Determine appropriate RWP and subtask, Limits, and Stay Times based on various RWP limits.

CHECKLIST Survey Map Selection of RWPs for the candidate to chose from Calculator 2016 NRC EXAM Page:8of8 Admin JPM RadCon (ALL)

Unit 2 Containment, 262 Elevation Verified Current By Date Newtron Count Today A Motor Cube Called North LDWA Low Dose Waiting Area HPA Hot Particle Area CAM Continuous Air Monitor LHRA Locked High Radiation Area CA Contaminated Area 0 Frisking Station HRA High Radiation Area ARA Airborne Radioactivity Area RCAB Radiological Control Area Boundary RA Radiation Area RM Radioactive Material(s)

NDCR Neutron Dose Calculation Required D

All gamma and/or neutron I X readings in mRem/hr unless Gen Area; Contact; LCK Locked Gate; Barrier noted.

RADIATION WORK PERMIT

SUMMARY

16-2229 RP-M-274 An. 2 PLANT CODE YEAR RWP NUMBER REV.

RWP START TYPE CATEGORY RWP EXPIRATION 2

16 16-2229 0

01-MAR-2016 00:00 S

RM 31-MAY-2016 23:59 RWP DESCRIPTION Routine duties, walkdowns and valve line-ups by Operations personnel.

TASK

SUMMARY

DOSE ALARM DOSE RATE ALARM TIME INTERVAL I

Dose rates <100 mremTht Routine duties, watkdowns and valve line-ups by OperatIons 10 50 personnel.

2 Dose rates >100 mreniThr Routine duties, walkdowns, and valve line-ups by Operations 20 150 personnel ALARA INFORMATION ALARA Review No.

Hours-Estimated Person-mrem 16-013 1999998 2845 SPECIAL INSTRUCTIONS:

Requirements for High Radiation Area Entry or Locked High Radiation Area:

-Notify HP Prior to entry

-Sign in on an RWP that ALLOWS entry into a High Radiation Area or Locked High Radiation Area.

-Understand the ED Alarm set points and your response to a dose or dose rate alarm.

-Understand the radiological conditions fog. dose rates) in the area

-Monitor Electronic Dosimetry frequently. (Approximately every 15 mInutes,)

-Notify RP upon exit.

Prepared By Robert MCNUU DATE:

020f 0( Approved By DATE:

I - -I c Revised By DATE:

Approved By DATE; Terminated By DATE:

Approved By DATE:

ORIGINAL Page 1

Task Number I

OF 2 RP-M-274 ATT. 2 VALID FROM 014iIAR2016 00:00 TO 31MAY2016 23:59 RWP 16-2229-1 REV. NO 0

DOSE RATE ALARM:

° mremlHr BUDGETED DOSE:

245 mrem DOSE LIMIT ALARM:

10 mrem ALARA EVALUATION NO: I603 JOB LOCATIONS:

Station Property cxduding Unit I Reactor Containment.

r 4

JOB DESCRIPTION:

Dose rates l0O mcerMu: Routine duties, waikdowns and valve line-ups by Operations personnel.

THE MAXIMUM POSTED AREA THAT CAN BE ENTERED:

Locked High Radiation Area

• 1 RADIOLOGICAL CONDITIONS: lndicates estimated value for RWP Preparation. See survey forms for details GENERAL AREA RADIATION LEVELS (mremlhr):

See Radiological Status Boards or specific survey form.

CONTACT/HOT SPOT RADIATION LEVELS (mrem/hr):

See Radiological Status Boards or sppdflc survey form.

CONTAMINATION LEVELS (UpmIlOOcrn2):

See Radiological Status Boards or specific survey form.

AIRBORNE RADIOACTIVITY (DAC):

<.30k REQUIRED JOB COVERAGE:

ROUTINE COVERAGE COMMENTS:

l.0)Continuous coverage required for:

. i.l)then loose surface levels are greater than l,000,000dpm/lOOcm2 or area has known DRPs greater than or equal to 100 mrem/hr on contact f open window).

1.2) When extremity dose rates are greater than 5,000 mrem/hr.

DOSIMETRY REQUIREMENTS:

EDISRD TLD I

p DOSIMETRY COMMENTS:

l.0)Caution: If PAM(ED) is utilized, ensure PANtED) is secured so that individual can feel the vibration if PAM(ED) alarms.

2.O)Notify HP prior to entry into a Neutron Exposure Area for additional dosimetry requirements.

ORIGINAL Page 2

Task Number I

OF 2 RP-M.274 ATT 2 PROTECTiVE CLOTHING REQUIREMENTS:

LAB COAT; SHOE COVERS GLOVES MAY BE WORN FOR ANY NON-PHYSICAL ACTIVITIES (I.E.

OBSERVATIONS OR EQUIPMENT CHECKS)

AND CONTAMINATION LEVELS ARE LESS THAN 10,000 DPM/lOOCM2.

l.0)Required Protective clothing:

1.1)Surgeons Hood 1.l.l)Full hoods required in cavity, accessing over head in loop

rooms, and when wearing communication devices/headsets.

1.2)One Pair Coveralls l.3)Rubber Boots l.4)High Top Shoe Covers 1.5)Cotton Inserts l.6)One Pair Rubber Gloves 2.0)?rotective Clothing requirements as stated are for entry into Contaminated Areas only.

3.0)Protective Clothing requireients for a Hot Particle Area fHPA)

(in additibn to those stated above]

are:

3.l)Hood

gloves, coveralls, high top shoe covers and rubber boots.

3.2)Workers interfacing with individuals/equipment in a EPA

- Gloves and face shield.

A RWP PRE-JOB BRIEFING IS REQUIRED:

HRA BRIEF BYAN HP TECHNICLAN AND SIGN ATTENDANCE SHEET.

WORKER INSTRUCTIONS:

NOTE:

ED dose rató alarm set-points are set conservatively at a low, yet feasible value for ALARA purposes.

It is expected that some ED dose rate alarms may be received when dose rate alarm oat-points are sat below 100 mR/hr.

I.0)ED A1arms l.1)If ED dose rate alarm occurs,reposition yourself such that the alarm clears.

1.1.1)11 ED dose rate alarm continues or three consecutive dose rate alarms

occur, then leave area immediately and report to the HP Office?

l.2)If ED dose alarm occurs, then leave area immediately and report to the HP Office.

2.0)flo not enter High Radiation Areas without HP coverage or a ED with knowledge of work area dose rates.

3.0) Workers shall read their ED approximately every 15 minutes.

4.0)Wlien 80% of the dose alarm set point is reached, leave work area in a safe condition and exit the RCA.

5.0) Workers are responsible for notifying the HP Supervisor prior to venting\\draining

systems, that may affect Radiological Conditions in an area, to ensure proper Health Physics Monitoring.

6.O)HPA exit instructions:

6.1)Use extreme care in removing PCs and frisking.

6.2)Workere are to be monitored by HP upon exiting the EPA.

6.3)Individuals exiting the HPA are to proceed directly to the RCA exit to perform whole body monitoring.

6.4)Workers are to be monitored by HPafter interfacing with workers/equipment in a HPA.

7.0)Do not remove any items f rom a posted Hot Particle Area until authorized by HP-Ops.

8.0)Remote telemetrics dosimetry shall be used for workers entering containment when available.

9.0)If telemetric ED is used then check in with HP after the telemetric ED has been issued to verify that it is transmitting properly.

10.0)Notify Health Physics prior to setting up any ladder.

ll.O)Notify HP prior to entry in overhead areas greater than 8 feet.

+/-2.0)Prior to returning Electronic DosinetryfED), all individuals shall process through the PDA for wl?ole body monitoring.

This is not requiredif returning ED solely for the purpose of changing RWPs.

HEALTH PHYSICS INSTRUCTiONS:

This RWP authorizes work in an ALPHA Level II area.

ORIGINAL Page 3

Task Number I

OF 2 RP-M-274 ATT. 2 I.0)Stop work and leave area if whole body dose rates exceed 100 mRemlhr.

1.l)if ED dose rate alarm equals the stop work dose rate, then DO NOT authorize worker to work through an alarm.

2.0)Hot Particle Are&

(HPA) monitoring requirements:

2.1) Workers exposed skin shall be monitored by HP-Ops every four hours (unless specified by the HP Supervisor) while the workers are, in the EPA.

2.2)Personnel monitoring for workers exiting the HPA will consist of a whole body scan witnin 1/2 inch using a RO-2 or eq4uivalent(open window)witli background less than 1.0 mremJhr.

2.3)Worker release criteria:

a net reading of less than 2.0 mrem/hr.

2.4)Instruct all individuals exiting the HRA to proceed directly to the RCA exit to perform whole body monitoring.

ORIGINAL Page 4

VALID FROM ROSE RATE ALARM:

DOSE LIMIT ALARM:

JOB LOCATIONS:

STATION PROPERTY. EXCLUDING U-I CONTAINMENT JOB DESCRIPTION:

Dose rates >100 mtenVhn Routine duties, walkdowns, and valve line-ups by Operations personnel THE MAXIMUM POSTED AREA THAT CAN BE ENTERED:

Locked High Radiation Area RADIOLOGICAL CONDITIONS:*Indlcates estimated value for RW.P Preparation. See survey forms for details GENERAL AREA RADIATION LEVELS (mremlhr):

See Radiological Status Boards or specific survey form CONTACTIHOT SPOT RADIATiON LEVELS (mrem/hr):

See Radiological Status Boards or specific survey form CONTAMINATION LEVELS (dprnIJOOcm2):

See Radiological Status Boards or specific survey form AIRBORNE RADIOACTIVITY (DAC):

.c30 REQUIRED JOB COVERAGE:

ROUTINE COVERAGE COMMENTS:

l.O)Continuous HP coverage required for:

l.l)When loose surface levels are greater than 1,000,000 dpm/lOOcm2 or area has known DRPs greater than or equal to 100 mrem/hr on contact (open window).

1.2) When extremity dose rates are greater than 5,000 tnrem/hr.

DOSIMETRY REQUIREMENTS:

EDISRD TLD DOSIMETRY COMMENTS:

l.O)Caution:

If PM(ED) is utilized, ensure PAM(ED) is secured so that individual can feel the vibration if PAM(ED) alarms.

2.0)Notify HP prior to entry into a Neutron Exposure Area for additional dosimetry requirements.

Task Number 2

0F2 01-MAR.2016 00:00 TO 31-MAY-2016 23:59 RWP 16-2229-2 REV. NO 0

mrem RP-M-274 AlT. 2

° mremlHr BUDGETED DOSE:

2800 20 mrem f

ALARA EVALUATION NO:

16013 ORIGIIJAL Page 5

Task Number 2

OF 2 RP-AA-274 AlT 2 PROTECTIVE CLOTHING REQUtREMENTS:

LAB

COAT, SHOE COVERS

& GLOVES MAY BE WORN FOR ANY NON-PHYSICAL ACTIVITIES (I.E.

OBSERVATIONS OR EQUIPMENT CHECKS)

AND CONTAMINATION LEVELS ARE LESS THAN 10,000 DPM/100CM2.

1.0)Required Prbtective clothing:

1.1)Surgeons Hood 1.1.1)Full hoods required in cavity, accessing over head in loop rooms, and when wearing communication devices/headsets.

1.2)One Pair Coveralls 1.3)Rubber BOOtS l.4)Higli Top Shoe Covers l.5)Cotton Inserts l.6)Qne Pair Rubber Gloves 2.0)Protective Clothing requirements as stated are for entry into Contaminated Areas only.

3.0)ProtectIve Clothing requirements for a Hot Particl Area (EPA)

(in addition to those stated above]

are:

3.1)Hood,

gloves, coveralls, high top shoe covers and rubber boots.

3.2)Workers interfacing with individuals/equipment in a EPA

- Gloves and face shield.

A RWP PRE-JOB BRJEIING IS REQUIRED:

HRA BRIEF BYAN HP TECHNICIAN AND SIGN ATTENDANCE SI-EET.

WORKER INSTRUCTIONS:

l.O)ED Alarms:

l.l)If ED dose rate alarm occurs, THEN leave area immediately and notify HP (unless authorized by HP Supervisor and have been briefed on proper responses)*.

1.2)If ED dose alarm occurs, THEN leave area immediately and report to the Health Physics office..

2.0)00 not enter High Radiation Areas without HP coverage or a ED with knowledge of work area dose rates.

3.0)Workers shall read their ED approximately every 15 minutes.

4.0)When 80% of the dose alarm set point is reached, leave work area in a safe condition and exit the RCA.

5.0)Workers are responsible for notifying the HP Supervisor prior to venting\\draining

systems, that may affect Radiological Conditions in an area, to ensure proper Health Physics Monitoring.

6.0)HPA exit instructions:

6.l)Use extreme care in removing PCs and frisking.

6.2)Workers are to be monitored by HP upon exiting the EPA.

6.3)Individuals exiting the EPA areto proceed directly to the RCA exit to perform whole body monitoring.

6.4)Workers are to be monitored by HP after interfacing with workers/equipment in a EPA.

7.O)Do not remove any items from a posted Hot Particle Area until autlioried by IIP-Ops.

8.0)Notify Health Phyéics prior to setting up any ladder.

9.0)Notify HP prior to entry in overhead areas greater than 8 feet.

lO.O)Remote telemetrics dosimetry shall be used for workers entering containment when available.

11.0)If telemetric ED is used then check in with HP after the telemetric ED has been issued to verify that it is transmitting properly.

12.0) Prior to returning Electronic DosimetryfEfl), all Individuals shall process through bhe PDA for whole body monitoring.

This is not required if returning ED solely for the purpose of changing RWPs.

HEALTH PHYSICS INSTRUCTIONS:

This RUP auth,orizes work in an ALPHA Level II area.

l.0)Stop work and leave area if whole body dose rates exceed 3000 mRem/hr.

2.0)When the ED dose rate alarm is set

>1000 mRem/lir then:

2.l)Stay times and continuous HP coverage is required.

ORIGINAL Page

Task Number 2

OF 2 RP-M-274 ATT. 2 3.0)Hot Particle Area (NPA) monitoring requirements:

3.l)Workers exposed skin shall be monitored by HP-Ops every four hours (unless specified by the H? Supervisor) while the worcers are in the HPA.

3.2)Personnel monitoring for workers exiting the HPA will consist of a whole body scan witnin 1/2 inch using a RO-2 or equivalent topen window) with background less tlin 1.0 mrem/hr.

3.3)Worker release criteria:

a net reading of less than 2.0 mrem/hr.

3.4)Instruct all individuals exiting the HPA to proceed directly to the RCA exit to perform whole body monitoring.

ORIGINAL Fage 7

• 1 I

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS At 1330, the SEM declared a General Emergency SG-1.1 for a Station Blackout At 1400, the SEM declared a General Emergency FG-1.1 Classification was declared on Unit 1 EPIP 1.06, Protective Action Recommendations, was entered and a PAR was issued. The previously completed EPIP-1.06 and PAR paperwork are provided for your review.

The time is now 1445 minutes and current conditions are:

Unit 1 : Conditions unchanged Unit 2 : Conditions unchanged TSC is still not operational Meteorological Data o

Wind Speed - 25 mph o

Wind Direction - 280° INITIATING CUE You are requested to perform EPIP-1.06, beginning at Step 11 Portions of this JPM are time critical.

2016 NRC EXAM EP JPM (SRO)

Page: 2 of 7 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM TASK Determine updated protective action recommendations (EPIP-1.06).

TASK STANDARDS Task was performed as directed by the procedure referenced in the task statement within parentheses (one of the underlined procedures if several are cited)

K/A

REFERENCE:

GEN-2.4.44 (2.1/4.0)

ALTERNATE PATH:

N/A TASK COMPLETION TIMES Validation Time =

15 minutes Start Time = _______

Actual Time = _______ minutes Stop Time = _______

PERFORMANCE EVALUATION Rating

[ ] SATISFACTORY [ ] UNSATISFACTORY Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date EVALUATOR'S COMMENTS

2016 NRC EXAM EP JPM (SRO)

Page: 3 of 7 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.

2016 NRC EXAM EP JPM (SRO)

Page: 4 of 7 INITIAL CONDITIONS At 1330, the SEM declared a General Emergency SG-1.1 for a Station Blackout At 1400, the SEM declared a General Emergency FG-1.1 Classification was declared on Unit 1 EPIP 1.06, Protective Action Recommendations, was entered and a PAR was issued. The previously completed EPIP-1.06 and PAR paperwork are provided for your review.

The time is now 1445 minutes and current conditions are:

Unit 1 : Conditions unchanged Unit 2 : Conditions unchanged TSC is still not operational Meteorological Data o

Wind Speed - 25 mph o

Wind Direction - 280° INITIATING CUE You are requested to perform EPIP-1.06, beginning at Step 11 Portions of this JPM are 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 None PERFORMANCE STEPS START TIME

2016 NRC EXAM EP JPM (SRO)

Page: 5 of 7 1

CHECK THE FOLLOWING:

Average wind direction shifts to any new area(s) (refer to ATTACHMENT 2, AFFECTED SECTOR(S) MAP)

Procedure Step 7 Critical Step SAT [ ] UNSAT [ ]

Standards SRO notes that wind direction has shifted and proceeds to step 17 Notes/Comments 2

UPDATE ATTACHMENT 2, AFFECTED SECTOR(S) MAP:

• Record time wind data acquired b)

• Record average wind direction from, in degrees c)

• Record average wind speed in mph d)

• Record affected sectors

• Mark new area(s) affected on map (use distinguishable markings from previous markings):

• Include all downwind sectors from previous PARs for this event AND

• All new downwind sectors for the PAR AND

• Any downwind sectors through which the wind shift occurred Procedure Step 17 Standards is updated (See KEY)

Notes/Comments

2016 NRC EXAM EP JPM (SRO)

Page: 6 of 7 3

COMPLETE PROTECTIVE ACTION RECOMMENDATION:

a) Complete ATTACHMENT 3, REPORT OF PROTECTIVE ACTION RECOMMENDATION

1) Mark appropriate PAR box(s)

2) Record Mile radius and Miles downwind

3) Record Downwind Sectors

4) Record Potassium Iodide (optional)

5) Record Remarks (optional)

6) Approve PAR (sign report)

7) Record date and time report approved Procedure Step 18.a SAT [ ] UNSAT [ ]

Critical Step SAT [ ] UNSAT [ ]

Standard is completed with updated data (See KEY)

Notes/Comments The new PAR has evacuated Sectors D and E to the 10 mile downwind (Sectors F, G, and H are still included from the original PAR.

4 DIRECT EMERGENCY COMMUNICATORS TO NOTIFY OFF-SITE AUTHORITIES OF PAR:

• Virginia Emergency Operations Center (VEOC) notified IAW:

EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS Procedure Step 19 Critical Step SAT [ ] UNSAT [ ]

Standards Completed within 15 minutes.

Notes/Comments

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

STOP TIME

2016 NRC EXAM EP JPM (SRO)

Page: 7 of 7 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)

1 of 11 COMMON PURPOSE Give guidance to the Station Emergency Manager or Recovery Manager regarding determination of Protective Action Recommendations.

ENTRY CONDITIONS Any one of the following:

1) Activation by EPIP-1.05, RESPONSE TO GENERAL EMERGENCY.

2) Activation by CPIP-3.1, CERC AND CEOF ACTIVATION.

3) Activation by CPIP-6.0, LEOF RECOVERY MANAGER GUIDANCE.

4) As directed by the Station Emergency Manager or Recovery Manager.

REFERENCE USE NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS (WITH 5 ATTACHMENTS)

REVISION 11 PAGE

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 2 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: ATTACHMENT 4, REFERENCE INFORMATION (NAPS) and ATTACHMENT 5, SECTOR MAP may be used as applicable for reference purposes.

____ 1 INITIATE PROCEDURE:

• By: ______________________________

Date: ____________________________

Time: ____________________________

____ 2 USE ATTACHMENT 1, PROTECTIVE ACTION RECOMMENDATION FLOWCHART NAPS, TO DETERMINE INITIAL PAR NOTE: ATTACHMENT 2, AFFECTED SECTOR(S) MAP, is to be used for all PAR developments from this procedure. ATTACHMENT 2, AFFECTED SECTOR(S) MAP is NOT to be used for PARs developed IAW EPIP-4.07, PROTECTIVE MEASURES.

____ 3 IMPLEMENT ATTACHMENT 2, AFFECTED SECTOR(S) MAP:

a) Record time wind data acquired a)

b) Record average wind direction from, in degrees b)

c) Record average wind speed in mph c)

d) Record affected sectors d)

e) Mark affected sectors on map (use any writing implement available, e.g., pen, pencil, highlighter, etc.)

e)

JS JS Joseph Supervisor Today 45 minutes ago JS 1300 1330

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 3 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____ 4 COMPLETE ATTACHMENT 3, REPORT OF PROTECTIVE ACTION RECOMMENDATION:

a) Protective Action Recommendation:

1) Mark appropriate PAR box(s)

2) Record Mile radius and Miles downwind

3) Record Downwind Sectors a) b) Thyroid CDE > 5 Rem at Site Boundary

Mark PAR box: POTASSIUM IODIDE b) GO TO Step 4.c.

c) Remarks/Approval Information:

1) Record Remarks (optional)

2) Approve PAR (sign report)

3) Record date and time report approved c)

____ 5 DIRECT EMERGENCY COMMUNICATORS TO NOTIFY OFF-SITE AUTHORITIES OF PAR:

• Virginia Emergency Operations Center (VEOC) notified IAW:

EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS OR

EPIP-4.07, PROTECTIVE MEASURES

• NRC notified IAW EPIP-2.02, NOTIFICATION OF NRC (notification made from Control Room or TSC, when activated)

• NRC notified IAW EPIP-4.33, HEALTH PHYSICS NETWORK COMMUNICATIONS (notifications made from TSC or LEOF/CEOF only after NRC requests HPN be established)

JS JS

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 4 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____ 6 HAVE RADIOLOGICAL ASSESSMENT DIRECTOR (RAD) IMPLEMENT EPIP-4.07, PROTECTIVE MEASURES [RADIOLOGICAL ASSESSMENT COORDINATOR (RAC) IF IN LEOF/CEOF]

CAUTION: Previously issued Protective Action Recommendations should not be reduced until the threat is fully under control and after consulting with Commonwealth of Virginia emergency response organization.

____ 7 CHECK THE FOLLOWING:

IF:

THEN do the following:

Severe Accident Conditions:

• CSFST Core Cooling RED AND

• Any Containment Loss Fission Product Barrier threshold met GO TO Step 8

Revised PAR provided by RAD/RAC IAW EPIP-4.07, PROTECTIVE MEASURES GO TO Step 13

Average wind direction shifts to any new area(s)

(refer to ATTACHMENT 2, AFFECTED SECTOR(S) MAP)

GO TO Step 17

PAR in effect - CONDITIONS UNCHANGED GO TO Step 20 JS

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 5 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____ 8 CHECK IF SEVERE ACCIDENT CONDITIONS EXIST:

• CSFST Core Cooling RED AND

• Any Containment Loss Fission Product Barrier threshold met

RETURN TO Step 7.

____ 9 COMPLETE ATTACHMENT 3, REPORT OF PROTECTIVE ACTION RECOMMENDATION:

a) Protective Action Recommendation:

1) Mark PAR box: EVACUATE

2) Record Mile radius 360°: 2

3) Record Miles downwind: 10

4) Record Downwind Sectors a) b) Thyroid CDE > 5 Rem at Site Boundary

Mark PAR box: POTASSIUM IODIDE b) GO TO Step 9.c.

c) Remarks/Approval Information:

1) Record Remarks (optional)

2) Approve PAR (sign report)

3) Record date and time report approved c)

JS JS

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 6 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____10 HAVE EMERGENCY COMMUNICATORS NOTIFY OFF-SITE AUTHORITIES OF PAR:

• Virginia Emergency Operations Center (VEOC) notified IAW:

EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS OR

EPIP-4.07, PROTECTIVE MEASURES

• NRC notified IAW EPIP-2.02, NOTIFICATION OF NRC (notification made from Control Room or TSC, when activated)

• NRC notified IAW EPIP-4.33, HEALTH PHYSICS NETWORK COMMUNICATIONS (notifications made from TSC or LEOF/CEOF only after NRC requests HPN be established)

____11 CHECK EMERGENCY - TERMINATED

RETURN TO Step 7.

____12 GO TO STEP 12

____13 CHECK IF REVISED PAR RECEIVED FROM RAD/RAC:

a) Evaluate PAR results with RAD/RAC b) Approve EPIP-4.07, Attachment 3, Radiological Protective Action Recommendation:

1) Record Remarks (optional)

2) Approve Radiological PAR (sign report)

3) Record date and time report approved

RETURN TO Step 7.

JS

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 7 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____14 DIRECT EMERGENCY COMMUNICATORS TO NOTIFY OFF-SITE AUTHORITIES OF PAR:

• Virginia Emergency Operations Center (VEOC) notified IAW:

EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS OR

EPIP-4.07, PROTECTIVE MEASURES

• NRC notified IAW EPIP-2.02, NOTIFICATION OF NRC (notification made from Control Room or TSC, when activated)

• NRC notified IAW EPIP-4.33, HEALTH PHYSICS NETWORK COMMUNICATIONS (notifications made from TSC or LEOF/CEOF only after NRC requests HPN be established)

____15 CHECK EMERGENCY - TERMINATED

RETURN TO Step 7.

____16 GO TO STEP 21

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 8 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: A new PAR is only issued for wind shifts, based on the conditions below, in new affected sectors that have NOT been included in a previous PAR.

____17 UPDATE ATTACHMENT 2, AFFECTED SECTOR(S) MAP:

a) Check if one of the following conditions exists:

• Dose Assessment or Field Monitoring readings indicates a projected dose of 1 Rem TEDE or 5 Rem Thyroid CDE in new area OR

• Potential for significant release as indicated by:

• CSFST Core Cooling RED AND

• Any Containment Loss Fission Product Barrier threshold met (from EALs) a) RETURN TO Step 7.

b) Record time wind data acquired b)

c) Record average wind direction from, in degrees c)

d) Record average wind speed in mph d)

e) Record affected sectors e)

(STEP 17 CONTINUED ON NEXT PAGE)

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 9 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 17.

UPDATE ATTACHMENT 2, AFFECTED SECTOR(S) MAP: (Continued) f)

Mark new area(s) affected on map (use distinguishable markings from previous markings):

• Include all downwind sectors from previous PARs for this event AND

• All new downwind sectors for the PAR AND

• Any downwind sectors through which the wind shift occurred

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 10 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____18 COMPLETE PROTECTIVE ACTION RECOMMENDATION:

a) Complete ATTACHMENT 3, REPORT OF PROTECTIVE ACTION RECOMMENDATION

1) Mark appropriate PAR box(s)

2) Record Mile radius and Miles downwind

3) Record Downwind Sectors

4) Record Potassium Iodide (optional)

5) Record Remarks (optional)

6) Approve PAR (sign report)

7) Record date and time report approved OR b) Approve EPIP-4.07, Attachment 3, RADIOLOGICAL PROTECTIVE ACTION RECOMMENDATION:

1) Record Remarks (optional)

2) Approve Radiological PAR (sign report)

3) Record date and time report approved

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 11 PAGE 11 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____19 DIRECT EMERGENCY COMMUNICATORS TO NOTIFY OFF-SITE AUTHORITIES OF PAR:

• Virginia Emergency Operations Center (VEOC) notified IAW:

EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS OR

EPIP-4.07, PROTECTIVE MEASURES

• NRC notified IAW EPIP-2.02, NOTIFICATION OF NRC (notification made from Control Room or TSC, when activated)

• NRC notified IAW EPIP-4.33, HEALTH PHYSICS NETWORK COMMUNICATIONS (notifications made from TSC or LEOF/CEOF only after NRC requests HPN be established)

____20 CHECK EMERGENCY - TERMINATED

RETURN TO Step 7.

____21 TERMINATE EPIP-1.06:

• Give completed EPIP-1.06, forms, and other applicable records to TSC Emergency Procedures Coordinator or LEOF Services Coordinator

• Completed by:___________________

Date:___________________________

Time:___________________________

- END -

1 of 1 General Emergency Declared Recommend implementation of Potassium Iodide (KI) strategies for the general public when the projected dose at site boundary PZ9LT;O`YVPK*+,

0ZZ\\L7YV[LJ[P]L(J[PVU9LJVTTLUKH[PVUMVYJ\\YYLU[*VUKP[PVUZ Note 1:

L]LYL(JJPKLU[*VUKP[PVUZ

*:-:;*VYL*VVSPUN9,+

AND

(U`*VU[HPUTLU[3VZZ-PZZPVU7YVK\\J[)HYYPLY[OYLZOVSKTL[

Yes No Yes Yes Yes Yes No Yes No Yes No Note 2:

EPA Protective Action Guidelines (PAG)

9LT;,+,

OR

9LT;O`YVPK*+,

No No No Yes Graphics No: MT2068 Evacuate 0-2 mile radius

TPSLZ

downwind Evacuate 0-10 mile radius all sectors Evacuate

TPSLYHKP\\Z

TPSLZ

downwind Evacuate 0-2 mile radius

TPSLZ

downwind Evacuate 0-2 mile radius

TPSLZ

downwind Shelter-In-Place 0-2 mile radius

TPSLZ

downwind Evacuate 0-2 mile radius 2-10 miles downwind PAG exceeded beyond 2 miles (Note 2)

PAG exceeded IL`VUKTPSLZ (Note 2)

Dose Assessment Available PAG exceeded H[:P[L)V\\UKHY`

(Note 2)

Dose Assessment directs evacuation Hostile Action Severe Accident (Note 1)

PAG 56; exceeded Yes NUMBER EPIP-1.06 ATTACHMENT TITLE PROTECTIVE ACTION RECOMMENDATION FLOWCHART NAPS ATTACHMENT 1

REVISION 11 PAGE

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE AFFECTED SECTOR(S) MAP ATTACHMENT 2

REVISION 11 PAGE NOTE: Rounding shall be used when determining affected sectors using wind direction.

For example: Wind Direction (degrees from) 11.5 to 11.9 would be rounded up to 12.0.

Wind Direction (degrees from) 11.1 to 11.4 would be rounded down to 11.0.

Average Wind Direction and Average Wind Speed Data:

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

AVERAGE WIND DIRECTION (Degrees) From AFFECTED SECTORS 349 - 11 H, J, K 12 - 33 J, K, L 34 - 56 K, L, M 57 - 78 L, M, N 79 - 101 M, N, P 102 - 123 N, P, Q 124 - 146 P, Q, R 147 - 168 Q, R, A 169 - 191 R, A, B 192 - 213 A, B, C 214 - 236 B, C, D 237 - 258 C, D, E 259 - 281 D, E, F 282 - 303 E, F, G 304 - 326 F, G, H 327 - 348 G, H, J A

B C

D E

F G

H J

K L

M N

P Q

78.75° 258.75° 33.75° 213.75° 236.25° 146.25° 303.75° R

10 5

2 281.25° 168.75° 123.75° 101.25° 56.25° 348.75° 11.25° 326.25° 191.25° Graphics No. SB1217E 45 min ago 310 12 F,G,H 1330 1400 310 15 F,G,H

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE REPORT OF PROTECTIVE ACTION RECOMMENDATION ATTACHMENT 3

REVISION 11 PAGE PAR MESSAGE # ________

NOTE:

• Transmit to Virginia EOC only using the VEOC ARD.

• IF VEOC ARD nonfunctional, THEN use VEOC autodial or direct dial (804) 674-2400 or (804) 310-8868.

• IF all means of communications with VEOC nonfunctional, THEN use Insta-Phone.

This is North Anna Power Station with a(n) Drill Message Emergency Message for Protective Action Recommendation. Use the Report of Protective Action Recommendation form to copy this message.

(READ SLOWLY)

PROTECTIVE ACTION RECOMMENDATION:

SHELTER-IN-PLACE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

EVACUATE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

BEYOND 10 MILE EPZ:

Evacuate Area: _____ Centerline in degrees; _____Distance in Miles; _____ Width in feet Shelter-in-place: ____ Centerline in degrees; _____Distance in Miles; _____ Width in feet POTASSIUM IODIDE:

Recommend implementation of Potassium Iodide (KI) strategies for the general public.

The projected dose at the site boundary is > 5 Rem Thyroid CDE.

The time is ______________ (24-hr time).

This is ________________________________________________________ / Emergency Communicator.

Message received by: Virginia EOC Watch Officer (name) ______________________________________.

This is North Anna Power Station out at _______________ (24-hr time) on ___________________ (date).

REMARKS (OPTIONAL) / APPROVAL INFORMATION [DO NOT READ]

NOTE: Shelter-in-Place may be recommended as a result of evacuation impediments (e.g., Hostile Action events) or other known conditions which make evacuation dangerous.

REMARKS: ________________________________________________________________________________

APPROVED BY: ___________________________________________ ______________ / _________

Station Emergency Manager or Recovery Manager Date Time 1

0-2 2-5 F,G,H Joe Supervisor Today 1340 1342 John Talker Bob Early 1345 Today

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE REPORT OF PROTECTIVE ACTION RECOMMENDATION ATTACHMENT 3

REVISION 11 PAGE PAR MESSAGE # ________

NOTE:

• Transmit to Virginia EOC only using the VEOC ARD.

• IF VEOC ARD nonfunctional, THEN use VEOC autodial or direct dial (804) 674-2400 or (804) 310-8868.

• IF all means of communications with VEOC nonfunctional, THEN use Insta-Phone.

This is North Anna Power Station with a(n) Drill Message Emergency Message for Protective Action Recommendation. Use the Report of Protective Action Recommendation form to copy this message.

(READ SLOWLY)

PROTECTIVE ACTION RECOMMENDATION:

SHELTER-IN-PLACE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

EVACUATE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

BEYOND 10 MILE EPZ:

Evacuate Area: _____ Centerline in degrees; _____Distance in Miles; _____ Width in feet Shelter-in-place: ____ Centerline in degrees; _____Distance in Miles; _____ Width in feet POTASSIUM IODIDE:

Recommend implementation of Potassium Iodide (KI) strategies for the general public.

The projected dose at the site boundary is > 5 Rem Thyroid CDE.

The time is ______________ (24-hr time).

This is ________________________________________________________ / Emergency Communicator.

Message received by: Virginia EOC Watch Officer (name) ______________________________________.

This is North Anna Power Station out at _______________ (24-hr time) on ___________________ (date).

REMARKS (OPTIONAL) / APPROVAL INFORMATION [DO NOT READ]

NOTE: Shelter-in-Place may be recommended as a result of evacuation impediments (e.g., Hostile Action events) or other known conditions which make evacuation dangerous.

REMARKS: ________________________________________________________________________________

APPROVED BY: ___________________________________________ ______________ / _________

Station Emergency Manager or Recovery Manager Date Time 1

2 10 F,G,H Today 1345 Joe Supervisor 2

1410 1412 John Talker Bob Early 1415 Today

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE REFERENCE INFORMATION (NAPS)

ATTACHMENT 4

REVISION 11 PAGE KNOWN EVACUATION IMPEDIMENTS:

As reflected in Attachment 1, PROTECTIVE ACTION RECOMMENDA-TION FLOWCHART NAPS, the only impediment North Anna Power Station will consider in the development of PARs will be Hostile Actions directed at the site.

PAR NOTIFICATION TIMES:

The initial PAR must be included with the initial notification of a General Emergency, which must be made to the State within 15 minutes following declaration of the General Emergency.

Notification of a revised PAR must be made to the State within 15 minutes of its development.

SECTORS/

WIND DIRECTION:

Downwind sectors may be determined from the table on Attachment 2, AFFECTED SECTOR(S) MAP.

Wind direction is always given in degrees from.

SHELTERING IN PLACE:

Sheltering-In-Place is recommended when a known condition or impediment exists which makes evacuation dangerous. A Hostile Action based event is the only know impediment to evacuation.

PREVIOUSLY ISSUED PAR:

Previously issued Protective Action Recommendations should not be reduced until the threat is fully under control and after consulting with Commonwealth of Virginia emergency response organization.

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE SECTOR MAP ATTACHMENT 5

REVISION 11 PAGE Graphics No. SV634A 522 522 208 208 208 208 208 651 687 629 629 669 651 612 612 612 612 612 612 606 606 680 606 648 649 Lake Anna State Park 691 656 656 614 738 647 648 601 601 601 601 653 652 652 652 652 651 613 613 613 669 651 651 625 625 628 628 669 669 624 623 623 623 522 700 700 North Anna Power Station 779 720 751 703 719 Lake Anna Lake Anna Lake Anna South Anna River 605 605 644 646 697 699 640 522 33 33 Louisa Mineral 665 605 618 618 681 208 208 22 208 33 22 689 689 700 522 772 779 656 656 716 774 657 614 689 601 602 721 643 653 659 606 703 608 608 613 648 606 738 738 678 647 605 658 605 605 670 738 738 604 605 622 605 622 658 658 666 738 738 738 614 614 669 669 622 701 715 715 601 601 775 618 618 618 601 704 712 7000 752 712 728 733 667 718 701 650 612 664 652 649 687 651 677 630 669 620 612 669 669 629 605 601 612 655 609 601 609 612 609 657 701 654 673 680 729 608 608 608 763 658 658 715 715 738 684 739 603 669 738 671 738 679 671 669 682 680 680 655 646 604 640 767 624 696 208 747 1726 1725 700 652 719 719 652 612 A

B C

D E

F G

H J

K L

M N

P Q

R 2 Miles 5 Miles 10 Miles 11.25° 348.75° 326.25° 303.75° 281.25° 258.75° 236.25° 213.75° 191.25° 168.75° 146.25° 123.75° 101.25° 78.75° 56.25° 33.75°

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE REPORT OF PROTECTIVE ACTION RECOMMENDATION ATTACHMENT 3

REVISION 11 PAGE PAR MESSAGE # ________

NOTE:

• Transmit to Virginia EOC only using the VEOC ARD.

• IF VEOC ARD nonfunctional, THEN use VEOC autodial or direct dial (804) 674-2400 or (804) 310-8868.

• IF all means of communications with VEOC nonfunctional, THEN use Insta-Phone.

This is North Anna Power Station with a(n) Drill Message Emergency Message for Protective Action Recommendation. Use the Report of Protective Action Recommendation form to copy this message.

(READ SLOWLY)

PROTECTIVE ACTION RECOMMENDATION:

SHELTER-IN-PLACE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

EVACUATE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

BEYOND 10 MILE EPZ:

Evacuate Area: _____ Centerline in degrees; _____Distance in Miles; _____ Width in feet Shelter-in-place: ____ Centerline in degrees; _____Distance in Miles; _____ Width in feet POTASSIUM IODIDE:

Recommend implementation of Potassium Iodide (KI) strategies for the general public.

The projected dose at the site boundary is > 5 Rem Thyroid CDE.

The time is ______________ (24-hr time).

This is ________________________________________________________ / Emergency Communicator.

Message received by: Virginia EOC Watch Officer (name) ______________________________________.

This is North Anna Power Station out at _______________ (24-hr time) on ___________________ (date).

REMARKS (OPTIONAL) / APPROVAL INFORMATION [DO NOT READ]

NOTE: Shelter-in-Place may be recommended as a result of evacuation impediments (e.g., Hostile Action events) or other known conditions which make evacuation dangerous.

REMARKS: ________________________________________________________________________________

APPROVED BY: ___________________________________________ ______________ / _________

Station Emergency Manager or Recovery Manager Date Time

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE AFFECTED SECTOR(S) MAP ATTACHMENT 2

REVISION 11 PAGE NOTE: Rounding shall be used when determining affected sectors using wind direction.

For example: Wind Direction (degrees from) 11.5 to 11.9 would be rounded up to 12.0.

Wind Direction (degrees from) 11.1 to 11.4 would be rounded down to 11.0.

Average Wind Direction and Average Wind Speed Data:

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

AVERAGE WIND DIRECTION (Degrees) From AFFECTED SECTORS 349 - 11 H, J, K 12 - 33 J, K, L 34 - 56 K, L, M 57 - 78 L, M, N 79 - 101 M, N, P 102 - 123 N, P, Q 124 - 146 P, Q, R 147 - 168 Q, R, A 169 - 191 R, A, B 192 - 213 A, B, C 214 - 236 B, C, D 237 - 258 C, D, E 259 - 281 D, E, F 282 - 303 E, F, G 304 - 326 F, G, H 327 - 348 G, H, J A

B C

D E

F G

H J

K L

M N

P Q

78.75° 258.75° 33.75° 213.75° 236.25° 146.25° 303.75° R

10 5

2 281.25° 168.75° 123.75° 101.25° 56.25° 348.75° 11.25° 326.25° 191.25° Graphics No. SB1217E























.75 146.25 10 5

2 146.25 10 8.75 3.75 101.25









146.25 10 5

123 101.25 101.25

.75 101.25 146.25 10 5

.75 123 101.25

.75 3.75 101.25





























KEY KEY 1445 280 25 D,E,F,G,H

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE REPORT OF PROTECTIVE ACTION RECOMMENDATION ATTACHMENT 3

REVISION 11 PAGE PAR MESSAGE # ________

NOTE:

• Transmit to Virginia EOC only using the VEOC ARD.

• IF VEOC ARD nonfunctional, THEN use VEOC autodial or direct dial (804) 674-2400 or (804) 310-8868.

• IF all means of communications with VEOC nonfunctional, THEN use Insta-Phone.

This is North Anna Power Station with a(n) Drill Message Emergency Message for Protective Action Recommendation. Use the Report of Protective Action Recommendation form to copy this message.

(READ SLOWLY)

PROTECTIVE ACTION RECOMMENDATION:

SHELTER-IN-PLACE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

EVACUATE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

BEYOND 10 MILE EPZ:

Evacuate Area: _____ Centerline in degrees; _____Distance in Miles; _____ Width in feet Shelter-in-place: ____ Centerline in degrees; _____Distance in Miles; _____ Width in feet POTASSIUM IODIDE:

Recommend implementation of Potassium Iodide (KI) strategies for the general public.

The projected dose at the site boundary is > 5 Rem Thyroid CDE.

The time is ______________ (24-hr time).

This is ________________________________________________________ / Emergency Communicator.

Message received by: Virginia EOC Watch Officer (name) ______________________________________.

This is North Anna Power Station out at _______________ (24-hr time) on ___________________ (date).

REMARKS (OPTIONAL) / APPROVAL INFORMATION [DO NOT READ]

NOTE: Shelter-in-Place may be recommended as a result of evacuation impediments (e.g., Hostile Action events) or other known conditions which make evacuation dangerous.

REMARKS: ________________________________________________________________________________

APPROVED BY: ___________________________________________ ______________ / _________

Station Emergency Manager or Recovery Manager Date Time KEY KEY 3

2 10 D,E,F,G,H Signature Today's Date Current CRITICAL STEP DATA Signature, Date and Time are CRITICAL STEP DATA. Time must be within 15 minutes of start time.