Revision as of 04:45, 2 May 2018

Text

Section 6 - Draft Administrative JPMs
	ML17172A714
Person / Time
Site:	North Anna
Issue date:	06/21/2017
From:	; Virginia Electric & Power Co (VEPCO)
To:	; NRC/RGN-II
References
	Download: ML17172A714 (133)
	v • d • e

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 eligible to work the Unit 1 OATC position on 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 Backboards. 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 = 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 eligible to work the Unit 1 OATC position on 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. 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)

KEY You are to determine if each of the Reactor Operators is eligible to work the Unit 1 OATC position on the 0700 - 1900 shift on April 1, 2016. Record your answer in the blanks below (yes or no). Operator A. YES Operator B. NO Operator C. NO

KEY 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. 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 eligible to work the Unit 1 OATC position on 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 Backboards. 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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.

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

2016 NRC EXAM ADMIN CO 1 (SRO) Page: 6 of 10 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 eligible to work the Unit 1 OATC position on 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.

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 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 (SRO) Page: 10 of 10 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)

KEY You are to determine if each of the Reactor Operators is eligible to work the Unit 1 OATC position on the 0700 - 1900 shift on April 1, 2016. Record your answer in the blanks below (yes or no). Operator A. YES Operator B. NO Operator C. NO AND Determine any actions required by Tech Specs and any associated time limits. Applicant determines TS 5.2.2.b is applicable, and manning must be restored to minimum no later than 1200 (within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

KEY Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Plant computer is operable. Unit is stable at 100% power All ex-core power-range channels are operable The SRO desires that a hand calculation of 1-PT-23 will be performed using the current meters on the Power Range drawers. INITIATING CUE You are requested to perform a quadrant power tilt ratio determination by hand calculation in accordance with 1-PT-23, and determine maximum power level, if applicable.

2016 NRC EXAM Admin JPM CO-2 Page: 2 of 9 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 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 JPM CO-2 Page: 3 of 9 2016 NRC EXAM Admin JPM CO-2 Page: 4 of 9 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 > 75% power All ex-core power-range channels are operable The SRO desires that a hand calculation of 1-PT-23 will be performed using the current meters on the Power Range drawers.

2016 NRC EXAM Admin JPM CO-2 Page: 5 of 9 INITIATING CUE You are requested to perform a quadrant power tilt ratio determination by hand calculation in accordance with 1-PT-23. 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 2016 NRC EXAM Admin JPM CO-2 Page: 6 of 9 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 1% of the actual current readings Notes/Comments 2016 NRC EXAM Admin JPM CO-2 Page: 7 of 9 4 Record the expected 100% power current readings from the Reactor Data Book. Given data SAT [ ] UNSAT [ ] 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 Notes/Comments 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 Notes/Comments 2016 NRC EXAM Admin JPM CO-2 Page: 8 of 9 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 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 2016 NRC EXAM Admin JPM CO-2 Page: 9 of 9 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.

10 Determine maximum power level in accordance with Tech Spec Action 3.2.4.A Tech Spec 3.4.2.A Critical Step SAT [ ] UNSAT [ ] Standards power for each 1% of QPTR > 1.00. Notes/Comments Using the 1% of the actual current readings given in Step 3 of the JPM, the drawer reading would be 210 2.1 µA - the acceptable range for a final answer is 82.66% power to 87.31% power. >>>>> END OF EVALUATION <<<<< STOP TIME __________

DOMINION1-PT-23North Anna Power Station Revision 30Page 6 of 15InitVerif3.0INITIAL CONDITIONSNOTE: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. _______3.1IF power level is 75% or greater, THEN all 4 power range detectors are OPERABLE. _______3.2Check at least three Excore Power Range Channels are operable. _______3.3Check the Reactor is at a stable power level._______3.4Notify 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._______3.5IF 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.4.0PRECAUTIONS AND LIMITATIONS_______4.1Comply 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).

DOMINION1-PT-23North Anna Power Station Revision 30Page 7 of 15_______4.2With 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._______4.3Observe 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._______4.4IF 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.

DOMINION1-PT-23North Anna Power Station Revision 30Page 8 of 155.0SPECIAL TOOLS AND EQUIPMENTIF 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 TypeAccuracy RequirementDMMAt least 51/2digits and 1000 Megohm input resistance on 2 VDC range DOMINION1-PT-23North Anna Power Station Revision 30Page 9 of 156.0INSTRUCTIONSNOTE:Sections OR Attachments of this procedure NOT used may be discarded. 6.1IF one Power Range Channel has become inoperable and Thermal Power is less than 75percent RTP, THEN do ONE of the following: 6.1.1The 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 ENG6.1.2Obtain 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. 6.2Do 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 Attachment1, Unit 1 PCS QPTR Calculation. _______*IF desired to perform a hand calculation to determine QPTR, THEN complete Attachment2, QPTR Hand Calculation. 7.0FOLLOW-ON7.1Acceptance Criteria_______7.1.1A QPTR has been determined from at least 3 Operable Excore Power Range detectors.

DOMINION1-PT-23North Anna Power Station Revision 30Page 10 of 15_______7.1.2IF the Unit is at a power level above 50 percent, THEN the QPTR is 1.02 or less. 7.2Follow-On TasksNOTE:Sections OR Attachments of this procedure NOT used may be discarded. _______7.2.1IF any QPTR Report(s) were obtained, THEN attach them to this procedure. 7.2.2IF the Unit is at a power level above 50 percent AND the QPTR is greater than1.02, THEN do the following:_______*Notify the SRO. _______*Enter Action Statement of Tech Spec Action 3.2.4.A. _______7.2.3IF the QPTR is greater than 1.015, THEN notify the Reactor Engineer.7.3Completion Notification_______Notify the SRO that this test is complete. Completed by: ___________________________________________ Date: _________ATTACHMENTS DOMINION1-PT-23North Anna Power Station Revision 30Page 11 of 15(Page 1 of 2)Attachment1Unit 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: _______4.1Select the NSSS AND BOP button from the Main Screen. _______4.2Select the QPTR button from the NSSS Menu Screen. _______4.3Select the F4=Report button from the NI: Quadrant Power Tilt Ratio screen. _______4.4IF 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: _______5.1IF any data is indicated as "NCAL" on the QPTR Report, THEN notify the Reactor Engineer for resolution.

DOMINION1-PT-23North Anna Power Station Revision 30Page 12 of 15(Page 2 of 2)Attachment1Unit 1 PCS QPTR Calculation_______5.2IF 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 Attachment2, QPTR Hand Calculation. _______5.3IF 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: _______8.1Notify the Reactor Engineer to resolve the discrepancy. _______8.2IF discrepancy cannot be resolved, THEN QPTR CANNOT be determined using the Unit 1 PCS. Complete Attachment2, QPTR Hand Calculation. CAUTIONThe 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.

DOMINION1-PT-23North Anna Power Station Revision 30Page 13 of 15(Page 1 of 3)Attachment2QPTR Hand Calculation1.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: _______1.1Notify 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._______INST1.2Have the Instrument Department technician place the DMM on the 2 VDC scale._______INST1.3Have 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.______________INSTINST SV1.4TM: 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. _______1.5Determine each NI Power Range Detector channel current by using the conversion 1 millivolt = 1 amp._______1.6Record the measured currents on Page 3 of this attachment.______________INSTINST1.7TM: Have the Instrument Department technician disconnect the DMM from the test jacks.CAUTIONTo 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).

DOMINION1-PT-23North Anna Power Station Revision 30Page 14 of 15(Page 2 of 3)Attachment2QPTR 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: 3.1Request 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. _______3.2WHEN the QPTR Report is complete, THEN remove the report from the printer. _______3.3Using 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.

DOMINION1-PT-23North Anna Power Station Revision 30Page 15 of 15(Page 3 of 3)Attachment2QPTR Hand CalculationNOTE: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 UpperAvg. of Upper Normalized CurrentsCurrent 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 LowerAvg. of Lower Normalized CurrentsCurrent Reading (record to nearest µa) 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 orLower QPTR Value from above)Quadrant of Max QPTR:_________________________________(N41 Upper, N41 LowerN42 Upper, N42 Lower, etc.)Completed by: __________________________________________ Date: ________Verified by:_____________________________________________Date/Time Verification Completed:________________________________(Use this Time for recordingwhen surveillance is completed)

Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS 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 Reactor power has been at 100% with "D" bank control rods at 227 steps for six months Two control rods on "D bank are inoperable and unable to be tripped. INITIATING CUE You are requested to determine the shutdown margin at power with inoperable control rods using 1-PT-10.1. If necessary, calculate the boron concentration required to achieve a shutdown margin of at least 1.77% K/K.

2016 NRC EXAM Admin JPM CO 2 (ALL) Page: 2 of 8 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 CO 2 (ALL) Page: 3 of 8 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 CO 2 (ALL) Page: 4 of 8 INITIAL CONDITIONS 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 Reactor power has been at 100% with "D" bank control rods at 227 steps for six months Two control rods on "D bank are inoperable and unable to be tripped. INITIATING CUE You are requested to determine the shutdown margin at power with inoperable control rods using 1-PT-10.1. If necessary, calculate the boron concentration required to achieve a shutdown margin of at least 1.77% K/K. 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 CO 2 (ALL) Page: 5 of 8 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 CO 2 (ALL) Page: 6 of 8 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 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 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 100 pcm.

Notes/Comments 2016 NRC EXAM Admin JPM CO 2 (ALL) Page: 7 of 8 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 15 ppm Notes/Comments 15 ppm was determined using the 100 pcm 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 >>>>> END OF EVALUATION <<<<< STOP TIME __________

2016 NRC EXAM Admin JPM CO 2 (ALL) Page: 8 of 8 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required)

UNIT ONE PROCEDURE NO:1-PT-10.1NORTH ANNA POWER STATIONREVISION NO:13PROCEDURE TYPE: UNIT NO:OPERATIONS PERIODIC TEST1 PROCEDURE TITLE: SHUTDOWN MARGIN DETERMINATION AT POWER WITH INOPERABLE OR MISALIGNED CONTROL RODSTEST 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 2SPECIAL CONDITIONS: NoneSURVREQEOPAPREACTMGTREVISION 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):SurveillancePost-MaintenanceWork Order Number (Post-Maintenance Only): ____________________TEST PERFORMED BY (SIGNATURE):DATE STARTED:DATE COMPLETED:TEST RESULT (CHECK APPROPRIATE BOX):SatisfactoryUnsatisfactoryPartialWORK 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 TABLE OF CONTENTSSectionPageDOMINION1-PT-10.1North Anna Power Station Revision 13Page 2 of 141.0PURPOSE

32.0REFERENCES

33.0INITIAL CONDITIONS4 4.0PRECAUTIONS AND LIMITATIONS5 5.0SPECIAL TOOLS AND EQUIPMENT6 6.0INSTRUCTIONS77.0FOLLOW-ON7ATTACHMENTS1Shutdown Margin Determination 9 2Detailed Description of Shutdown Margin Determination 12 DOMINION1-PT-10.1North Anna Power Station Revision 13Page 3 of 141.0PURPOSETo 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 Spec3.1.4, 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.Attachment2, Detailed Description of Shutdown Margin Determination, provides a detailed description of the methodology used in the Shutdown Margin determination.

2.0REFERENCES

2.1Source Documents2.1.1UFSAR Section 1.2.4, Control and Instrumentation 2.1.2UFSAR Section 4.3.1.5, Shutdown Margin 2.1.3UFSAR Section 4.3.2.4, Control Requirements 2.1.4UFSAR Section 4.3.2.5.2, Rod Cluster Control Assemblies 2.1.5UFSAR Section 4.3.2.6, Control Rod Patterns and Reactivity Worth2.2Technical Specifications2.2.1Tech Spec 3.1.1 2.2.2Tech Spec 3.1.4 2.2.3Tech Spec 3.1.5 2.2.4Tech Spec 3.1.6 DOMINION1-PT-10.1North Anna Power Station Revision 13Page 4 of 142.3Technical References2.3.11-SC-3.4, Boron Coefficient vs Burnup For Zero Percent Power 2.3.21-SC-3.5, HZP Integral Worth Plot For Control Banks C and D In Overlap 2.3.31-SC-3.8, Power Defect 2.3.41-SC-8.1, PT-10 Rod Worth Data 2.3.51-SC-8.3, Shutdown Margin Data 2.3.61-SC-8.4, Reactivity Redistribution Factor vs Burnup 2.3.71-SC-8.5, N-1 Total Rod Worth vs Burnup 2.3.8Calculational Basis, approved 10-14-87 and 4-17-89 (Revision 3)2.3.9Calculation SM-753 of 10-11-90, Re-evaluation of North Anna EOP Setpoint J4.2.3.10Engineering Transmittal NAF-980057, Rev. 0 Proposed Operator Response and Shutdown Margin Information For Incomplete Rod Insertion.2.3.11OE 13496, Excessive Boration For Dropped Rod, ANO Unit 2, 11/1/2001 (Revision 11)2.4Commitment Documents2.4.1CTS Assignment 02-94-1802, Commitment 003, Incorporate Unit 1 Tech Spec Amendment 179, Control Rod Urgent Failure Tech Spec Change.InitVerif3.0INITIAL CONDITIONS_______3.1Verify the RCS boron concentration has been determined in the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

DOMINION1-PT-10.1North Anna Power Station Revision 13Page 5 of 14_______3.2Verify no dilutions to the RCS have been performed since the most recently measured boron concentration. _______3.3Ensure 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. _______3.4Verify 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 18steps from the Fully Withdrawn Position._______3.5Notify the SRO of this test. 4.0PRECAUTIONS AND LIMITATIONS_______4.1Comply 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)._______4.2Tech 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._______4.3Tech Spec 3.1.1 is not applicable in Mode 1 or in Mode 2 with Keff >1.0.

DOMINION1-PT-10.1North Anna Power Station Revision 13Page 6 of 14_______4.4Tech 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 _______4.5The 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_______4.6WHEN recording values on Attachment1, Shutdown Margin Determination, from Station Curves, THEN use plus (+) or minus (-) signs as indicated on the curves. _______4.7Reference 2.3.9 states that the second stuck control rod may be worth up to 1.55times the worth of the single highest worth rod stuck. This is accounted for in Item12 on Attachment1 by increasing the value of Item9 by 0.55 in the calculations.5.0SPECIAL TOOLS AND EQUIPMENTNone DOMINION1-PT-10.1North Anna Power Station Revision 13Page 7 of 146.0INSTRUCTIONS______________6.1Record the required values in Items 1 through 15 on Attachment1, Shutdown Margin Determination. ______________6.2Record the sum of Items 11 through 16 for each column, Instantaneous Shutdown Conditions and Current Critical Conditions, in Item 17 on Attachment1. ______________6.3Record the difference of the sums from Step 6.2 in Item 17 on Attachment1. 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.______________6.4IF the value recorded in Step 6.3 is less negative than -1770 pcm, THEN calculate and record in Item 18 on Attachment1 the change in boron concentration required to achieve a Shutdown Margin of at least 1.77% k/k. 7.0FOLLOW-ON7.1Acceptance Criteria______________7.1.1The Shutdown Margin with Inoperable or Misaligned Control Rods was determined.______________7.1.2The final value recorded in Item 17 on Attachment1 is equal to or more negative than -1770 pcm. 7.2Follow-On Tasks7.2.1IF the final value recorded in Item 17 on Attachment1 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 15minutes and enter the Action Statement of Tech Spec3.1.1.______________b.Start a boration in accordance with the applicable Action Statement of Tech Spec 3.1.4, 3.1.5, or 3.1.6.

DOMINION1-PT-10.1North Anna Power Station Revision 13Page 8 of 147.3Completion Notification_______7.3.1Record results in the Narrative Log to include actual or projected shutdown margin PCM value._______7.3.2Notify the SRO this test is complete. Completed by: ___________________________________________ Date: _________ATTACHMENTS DOMINION1-PT-10.1North Anna Power Station Revision 13Page 9 of 14(Page 1 of 3)Attachment1Shutdown Margin Determination CurrentCriticalConditions1.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)

DOMINION1-PT-10.1North Anna Power Station Revision 13Page 10 of 14(Page 2 of 3)Attachment1Shutdown Margin DeterminationInstantaneousShutdownConditionsCurrentCriticalConditions11.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):___________0NOTE: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)015.Power Defect (pcm):0___________(1-SC-3.8)16.Reactivity Worth of up to 8 Rods stuck at 10 steps.100017.Totals:___________-___________=___________pcm Item 9---------------------0.55+ Item 10---------------------x=

DOMINION1-PT-10.1North Anna Power Station Revision 13Page 11 of 14(Page 3 of 3)Attachment1Shutdown Margin Determination18.Determine Required Boron Concentration Change (CB) as Follows:(-1770 pcm) -------------------------------pcm(Item 17)____________________ CB()----------------------------------------------ppm= ------------------------------------pcm/ppm(Item 8)

DOMINION1-PT-10.1North Anna Power Station Revision 13Page 12 of 14(Page 1 of 3)Attachment2Detailed Description of Shutdown Margin DeterminationThe 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.)

DOMINION1-PT-10.1North Anna Power Station Revision 13Page 13 of 14(Page 2 of 3)Attachment2Detailed Description of Shutdown Margin DeterminationThe 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.

DOMINION1-PT-10.1North Anna Power Station Revision 13Page 14 of 14(Page 3 of 3)Attachment2Detailed Description of Shutdown Margin DeterminationIt 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 10steps.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.

Dominion North Anna Power Station ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS Unit 2 is shutdown for leak repair on RCS. The "A" Cold Leg Loop Stop MOV has stopped mid-position and must be locally closed by the handwheel. The operator will be wearing a headset to communicate to the MCR during the evolution.

INITIATING CUE You are directed to perform the following: Select the appropriate RWP and subtask for operations personnel Determine the dose alarm setpoint AND the dose rate alarm setpoint in effect under the RWP. Determine the maximum stay time based on reaching the dosimeter alarm setpoint (assume that NO dose is accumulated in transit to or from the work location). Determine the maximum stay time based on the RWP requirements (assume that NO dose is accumulated in transit to or from the work location).

2016 NRC EXAM Admin JPM RadCon (ALL) Page: 2 of 9 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.

K/A

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 [ ] UNSATISFACTORY Candidate (Print) Evaluator (Print) Evaluator's Signature / Date EVALUATOR'S COMMENTS 2016 NRC EXAM Admin JPM RadCon (ALL) Page: 3 of 9 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 for leak repair on RCS. The "A" Cold Leg Loop Stop MOV has stopped mid-position and must be locally closed by the handwheel. The operator will be wearing a headset during to communicate to the MCR during the evolution. INITIATING CUE You are directed to determine the following: o Correct RWP and subtask o Dose Alarm o Dose Rate Alarm o Maximum stay time based on RWP dose limits (in minutes) o Maximum stay time based on RWP requirements (in minutes) 2016 NRC EXAM Admin JPM RadCon (ALL) Page: 4 of 9 Answer Sheet 1. The correct RWP is ___________________________ Task ______ 2. The dose limit alarm listed for this RWP is ___________________ mRem. 3. The dose rate alarm setpoint listed for this RWP is ___________________ mRem/hr. 4. The maximum stay time based on the RWP dose limit is _______________ minutes. 5. The maximum stay time based on the RWP requirements is ______________ minutes.

2016 NRC EXAM Admin JPM RadCon (ALL) Page: 5 of 9 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 the job. Procedure Step RWP 16-2229-2 Critical Step SAT [ ] UNSAT [ ]

Standards RWP 16-2229-2 is selected from the two RWPs provided.

Notes/Comments: RWP 16-2229-1 is not correct due to local dose rates would exceed the alarm setpoint. RWP 16-2229-2 is the correct RWP and subtask.

2016 NRC EXAM Admin JPM RadCon (ALL) Page: 6 of 9 2 From the RWPs provided, determine the dose alarm setpoint and dose rate alarm in effect under the RWP. Procedure Step: RWP 16-2229-2 Critical Step SAT [ ] UNSAT [ ]

Standards Operator correctly identifies that the dose alarm is 20 mRem and the dose rate alarm is 150 mRem/hr (RWP 16-2229-2).

Notes/Comments: Operator is required to identify from the survey map that task 2 setpoint must be used based on work location. 3 Determine the maximum stay time in minutes based on reaching the RWP dose alarm setpoint. Procedure Step: RWP 16-2229-2 Critical Step SAT [ ] UNSAT [ ]

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

Operator uses survey map to determine general area dose rate is 80 mR/hr. Operator then divides 20 mRem by 80 mRem/hr to obtain a maximum stay time of 15 minutes (.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months ) based on the RWP dose alarm setpoint. Notes/Comments:

2016 NRC EXAM Admin JPM RadCon (ALL) Page: 7 of 9 4 Determine the maximum stay time in minutes based on reaching the RWP requirements. Procedure Step: RWP 16-2229-2 Critical Step SAT [ ] UNSAT [ ] Standards 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 16mRem 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 after converting to minutes (.20 hrs x 60 minutes). Notes/Comments: END OF EVALUATION STOP TIME __________

2016 NRC EXAM Admin JPM RadCon (ALL) Page: 8 of 9 Answer Key 1. The correct RWP is _________16-2229____________ Task __2____ 2. The dose limit alarm listed for this RWP is _______20__________ mRem. 3. The dose rate alarm setpoint listed for this RWP is _______150_________ mRem/hr. 4. The maximum stay time based on the RWP dose limit is ______15 _____ minutes. 5. The maximum stay time based on the RWP requirements is _____12_______ minutes.

2016 NRC EXAM Admin JPM RadCon (ALL) Page: 9 of 9 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

LDWA - Low Dose Waiting Area HPA - Hot Particle Area CAM - Continuous Air Monitor LHRA - Locked High Radiation Area CA - Contaminated Area F 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 Gen Area; Contact; LCK Locked Gate; Barrier Unit 2 Containment, 262' Elevation "A" Motor Cube All gamma and/or neutron readings in mRem/hr unless noted. Verified Current By Date 2-RC-E-1A 2-RC-P-1A HRA 4 5 55 80 6 1 20 60 80 Called North 45 Dominion North Anna Power Station JOB PERFORMANCE MEASURE EVALUATION OPERATOR PROGRAM INITIAL CONDITIONS You are the Shift Manager during a General Emergency Classification that has occurred due to a LOCA with Core Cooling RED path on Unit 1 EPIP 1.06 was entered and a PAR was issued 45 minutes ago The TSC is not operational yet Current conditions are as follows:

Unit 1: Conditions are unchanged for General Emergency - FG-1.1 Unit 2: At power Meteorological: Wind speed 25 mph Wind direction 280° INITIATING CUE You are requested to assess the new information and perform the required actions in accordance with EPIP-1.06.

2016 NRC EXAM EP JPM (SRO) Page: 2 of 9 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 9 2016 NRC EXAM EP JPM (SRO) Page: 4 of 9 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 during a General Emergency Classification that has occurred due to a LOCA with Core Cooling RED path on Unit 1 EPIP 1.06 was entered and a PAR was issued 45 minutes ago The TSC is not operational yet Current conditions are as follows:

2016 NRC EXAM EP JPM (SRO) Page: 5 of 9 Unit 1: Conditions are unchanged for General Emergency - FG-1.1 Unit 2: At power Meteorological: Wind speed 25 mph Wind direction 280° INITIATING CUE You are requested to assess the new information and perform the required actions in accordance with EPIP-1.06. 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: 6 of 9 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): previous PARs for this event AND AND sectors through which the wind shift occurred Procedure Step 17 Standards Attachment 2 is updated (See KEY)

Notes/Comments 2016 NRC EXAM EP JPM (SRO) Page: 7 of 9 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 [ ] Simulation Cue(s) Attachment 3 is completed with updated data (See KEY) Notes/Comments 4 DIRECT EMERGENCY COMMUNICATORS TO NOTIFY OFF-SITE AUTHORITIES OF PAR: EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS Procedure Step 19 Critical Step SAT [ ] UNSAT [ ] Standards Notes/Comments >>>>> END OF EVALUATION <<<<<

2016 NRC EXAM EP JPM (SRO) Page: 8 of 9 STOP TIME __________

2016 NRC EXAM EP JPM (SRO) Page: 9 of 9 SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required) 1 of 1NUMBEREPIP-1.06ATTACHMENT TITLEREPORT OF PROTECTIVE ACTION RECOMMENDATIONATTACHMENT3REVISION11PAGEPAR 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 feetPOTASSIUM 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 1NUMBEREPIP-1.06ATTACHMENT TITLEAFFECTED SECTOR(S) MAPATTACHMENT2REVISION11PAGENOTE: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) FromAFFECTEDSECTORS349 - 11H, J, K 12 - 33 J, K, L 34 - 56K, L, M 57 - 78L, M, N 79 - 101 M, N, P 102 - 123 N, P, Q 124 - 146 P, Q, R 147 - 168Q, R, A 169 - 191R, A, B 192 - 213A, B, C 214 - 236B, C, D 237 - 258C, D, E 259 - 281D, E, F 282 - 303 E, F, G 304 - 326F, G, H 327 - 348G, H, JABCDEFGHJKLMNPQ78.75258.7533.75213.75236.25146.25303.75R1052281.25168.75123.75101.2556.25348.7511.25326.25191.25Graphics No. SB1217E146.251052.75123101.25146.25108.753.75101.25 1 of 11COMMONPURPOSEGive guidance to the Station Emergency Manager or Recovery Manager regarding determination of Protective Action Recommendations.ENTRY CONDITIONSAny 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 USENORTH ANNA POWER STATIONEMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONS(WITH 5 ATTACHMENTS)REVISION11PAGE NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE2 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINEDNOTE:ATTACHMENT4, REFERENCE INFORMATION (NAPS) and ATTACHMENT5, SECTOR MAP may be used as applicable for reference purposes. ____1INITIATE PROCEDURE:*By: ______________________________ Date: ____________________________ Time: ____________________________ ____2USE ATTACHMENT1, PROTECTIVE ACTION RECOMMENDATION FLOWCHART NAPS, TO DETERMINE INITIAL PARNOTE:ATTACHMENT2, AFFECTED SECTOR(S) MAP, is to be used for all PAR developments from this procedure. ATTACHMENT2, AFFECTED SECTOR(S) MAP is NOT to be used for PARs developed IAW EPIP-4.07, PROTECTIVE MEASURES. ____3IMPLEMENT ATTACHMENT2, AFFECTED SECTOR(S) MAP:a)Record time wind data acquireda)b)Record average wind direction from, in degreesb)c)Record average wind speed in mphc)d)Record affected sectorsd)e)Mark affected sectors on map (use any writing implement available, e.g., pen, pencil, highlighter, etc.)e)

NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE3 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINED ____4COMPLETE ATTACHMENT3, REPORT OF PROTECTIVE ACTION RECOMMENDATION:a)Protective Action Recommendation:1)Mark appropriate PAR box(s)2)Record Mile radius and Miles downwind3)Record Downwind Sectorsa)b)Thyroid CDE > 5 Rem at Site BoundaryMark PAR box: POTASSIUM IODIDEb)GOTO Step4.c.c)Remarks/Approval Information:1)Record Remarks (optional)2)Approve PAR (sign report)3)Record date and time report approvedc) ____5DIRECT EMERGENCY COMMUNICATORS TO NOTIFY OFF-SITE AUTHORITIES OF PAR:Virginia Emergency Operations Center (VEOC) notified IAW:EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONSOREPIP-4.07, PROTECTIVE MEASURESNRC 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)

NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE4 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINED ____6HAVE 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.* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

____7CHECK THE FOLLOWING:IF:THEN do the following:Severe Accident Conditions:CSFST Core Cooling REDANDAny Containment Loss Fission Product Barrier threshold metGOTO Step8Revised PAR provided by RAD/RAC IAW EPIP-4.07, PROTECTIVE MEASURESGOTO Step13Average wind direction shifts to any new area(s) (refer to ATTACHMENT2, AFFECTED SECTOR(S) MAP)GOTO Step17PAR in effect - CONDITIONS UNCHANGEDGOTO Step20 NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE5 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINED ____8CHECK IF SEVERE ACCIDENT CONDITIONS EXIST:CSFST Core Cooling REDANDAny Containment Loss Fission Product Barrier threshold metRETURNTO Step7. ____9COMPLETE ATTACHMENT3, REPORT OF PROTECTIVE ACTION RECOMMENDATION:a)Protective Action Recommendation:1)Mark PAR box: EVACUATE2)Record Mile radius 360°: 23)Record Miles downwind: 104)Record Downwind Sectorsa)b)Thyroid CDE > 5 Rem at Site BoundaryMark PAR box: POTASSIUM IODIDEb)GOTO Step9.c.c)Remarks/Approval Information:1)Record Remarks (optional)2)Approve PAR (sign report)3)Record date and time report approvedc)

NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE6 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINED ____10HAVE EMERGENCY COMMUNICATORS NOTIFY OFF-SITE AUTHORITIES OF PAR:Virginia Emergency Operations Center (VEOC) notified IAW:EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONSOREPIP-4.07, PROTECTIVE MEASURESNRC 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) ____11CHECK EMERGENCY - TERMINATEDRETURNTO Step7. ____12GOTO STEP12 ____13CHECK IF REVISED PAR RECEIVED FROM RAD/RAC:a)Evaluate PAR results with RAD/RACb)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 approvedRETURNTO Step7.

NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE7 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINED ____14DIRECT EMERGENCY COMMUNICATORS TO NOTIFY OFF-SITE AUTHORITIES OF PAR:Virginia Emergency Operations Center (VEOC) notified IAW:EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONSOREPIP-4.07, PROTECTIVE MEASURESNRC 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) ____15CHECK EMERGENCY - TERMINATEDRETURNTO Step7. ____16GOTO STEP21 NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE8 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINEDNOTE: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. ____17UPDATE ATTACHMENT2, 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 areaORPotential for significant release as indicated by:CSFST Core Cooling REDANDAny Containment Loss Fission Product Barrier threshold met (from EALs)a)RETURNTO Step7.b)Record time wind data acquiredb)c)Record average wind direction from, in degreesc)d)Record average wind speed in mphd)e)Record affected sectorse)(STEP 17 CONTINUED ON NEXT PAGE)

NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE9 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINED17.UPDATE ATTACHMENT2, 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 eventANDAll new downwind sectors for the PARANDAny downwind sectors through which the wind shift occurred NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE10 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINED ____18COMPLETE PROTECTIVE ACTION RECOMMENDATION:a)Complete ATTACHMENT3, REPORT OF PROTECTIVE ACTION RECOMMENDATION1)Mark appropriate PAR box(s)2)Record Mile radius and Miles downwind3)Record Downwind Sectors4)Record Potassium Iodide (optional)5)Record Remarks (optional)6)Approve PAR (sign report)7)Record date and time report approvedORb)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 NUMBEREPIP-1.06PROCEDURE TITLEPROTECTIVE ACTION RECOMMENDATIONSREVISION11PAGE11 of 11STEPACTION/EXPECTED RESPONSERESPONSE NOT OBTAINED ____19DIRECT EMERGENCY COMMUNICATORS TO NOTIFY OFF-SITE AUTHORITIES OF PAR:Virginia Emergency Operations Center (VEOC) notified IAW:EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONSOREPIP-4.07, PROTECTIVE MEASURESNRC 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) ____20CHECK EMERGENCY - TERMINATEDRETURNTO Step7. ____21TERMINATE EPIP-1.06:Give completed EPIP-1.06, forms, and other applicable records to TSC Emergency Procedures Coordinator or LEOF Services CoordinatorCompleted by:___________________Date:___________________________

Time:___________________________- END -

1 of 1GeneralEmergencyDeclaredRecommend implementation of Potassium Iodide (KI) strategiesfor the general public when the projected dose at site boundaryNote 1:

AND YesNoYesYesYesYesNoYesNoYesNoNote 2:EPA Protective Action Guidelines (PAG)

OR NoNoNoYesGraphics No: MT2068Evacuate 0-2 mile radiusdownwindEvacuate 0-10 mile radiusall sectorsEvacuate downwindEvacuate 0-2 mile radiusdownwindEvacuate 0-2 mile radiusdownwindShelter-In-Place 0-2 mile radiusdownwindEvacuate 0-2 mile radius2-10 miles downwindPAGexceededbeyond 2 miles(Note 2)PAGexceeded(Note 2)Dose AssessmentAvailablePAGexceeded(Note 2)DoseAssessmentdirectsevacuationHostileActionSevereAccident(Note 1)PAGexceededYesNUMBEREPIP-1.06ATTACHMENT TITLEPROTECTIVE ACTION RECOMMENDATION FLOWCHARTNAPSATTACHMENT1REVISION11PAGE 1 of 1NUMBEREPIP-1.06ATTACHMENT TITLEAFFECTED SECTOR(S) MAPATTACHMENT2REVISION11PAGENOTE: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) FromAFFECTEDSECTORS349 - 11H, J, K 12 - 33 J, K, L 34 - 56K, L, M 57 - 78L, M, N 79 - 101 M, N, P 102 - 123 N, P, Q 124 - 146 P, Q, R 147 - 168Q, R, A 169 - 191R, A, B 192 - 213A, B, C 214 - 236B, C, D 237 - 258C, D, E 259 - 281D, E, F 282 - 303 E, F, G 304 - 326F, G, H 327 - 348G, H, JABCDEFGHJKLMNPQ78.75°258.75°33.75°213.75°236.25°146.25°303.75°R1052281.25°168.75°123.75°101.25°56.25°348.75°11.25°326.25°191.25°Graphics No. SB1217E 1 of 1NUMBEREPIP-1.06ATTACHMENT TITLEREPORT OF PROTECTIVE ACTION RECOMMENDATIONATTACHMENT3REVISION11PAGEPAR 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 feetPOTASSIUM 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 1NUMBEREPIP-1.06ATTACHMENT TITLEREFERENCE INFORMATION(NAPS)ATTACHMENT4REVISION11PAGEKNOWN 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 15minutes 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.SHELTERINGINPLACE: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.PREVIOUSLYISSUED 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 1NUMBEREPIP-1.06ATTACHMENT TITLESECTOR MAPATTACHMENT5REVISION11PAGEGraphics No. SV634A522522208208208208208651687629629669651612612612612612612606606680606648649Lake AnnaState Park691656656614738647648601601601601653652652652652651613613613669651651625625628628669669624623623623522700700North AnnaPower Station779720751703719Lake AnnaLake AnnaLake AnnaSouth Anna River6056056446466976996405223333LouisaMineral665605618618681208208 2220833 22689689700522772779656656716774657614689601602721643653659606703608608613648606738738678647605658605605670738738604605622605622658658666738738738614614669669622701715715601601775618618618601704712700075271272873366771870165061266465264968765167763066962061266966962960560161265560960160961260965770165467368072960860860876365865871571573868473960366973867173867967166968268068065564660464076762469620874717261725700652719719652612ABCDEFGHJKLMNPQR2 Miles5 Miles10 Miles11.25°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 1NUMBEREPIP-1.06ATTACHMENT TITLEREPORT OF PROTECTIVE ACTION RECOMMENDATIONATTACHMENT3REVISION11PAGEPAR 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 feetPOTASSIUM 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

ML17172A714: Difference between revisions

Revision as of 04:45, 2 May 2018

Contents

Text

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

32.0REFERENCES

2.0REFERENCES

REFERENCE:

REFERENCE:

Navigation menu

ML17172A714: Difference between revisions

Revision as of 04:45, 2 May 2018

Text

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

32.0REFERENCES

2.0REFERENCES

REFERENCE:

REFERENCE:

Navigation menu

Search