ML17172A714
| 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) | |
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 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. _____________________
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 <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 Page: 2 of 8 ADMIN CO 1 (RO)
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 Page: 3 of 8 ADMIN CO 1 (RO)
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 Page: 4 of 8 ADMIN CO 1 (RO)
- 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 Procedure Step 3.1 candidate SAT [ ] UNSAT [ ]
Notes/Comments 2016 NRC EXAM Page: 5 of 8 ADMIN CO 1 (RO)
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 Page: 6 of 8 ADMIN CO 1 (RO)
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 Page: 7 of 8 ADMIN CO 1 (RO)
SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required) 2016 NRC EXAM Page: 8 of 8 ADMIN CO 1 (RO)
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.
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 <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 Page: 2 of 10 ADMIN CO 1 (SRO)
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 Page: 3 of 10 ADMIN CO 1 (SRO)
2016 NRC EXAM Page: 4 of 10 ADMIN CO 1 (SRO)
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 Page: 5 of 10 ADMIN CO 1 (SRO)
- 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 Page: 6 of 10 ADMIN CO 1 (SRO)
1 OP-AA-103 - Operator Qualifications is referenced by the Procedure Step 3.1 candidate 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 Page: 7 of 10 ADMIN CO 1 (SRO)
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 Page: 8 of 10 ADMIN CO 1 (SRO)
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 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 Page: 9 of 10 ADMIN CO 1 (SRO)
SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required) 2016 NRC EXAM Page: 10 of 10 ADMIN CO 1 (SRO)
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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).
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.
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 Page: 2 of 9 Admin JPM CO-2
2016 NRC EXAM Page: 3 of 9 Admin JPM CO-2
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 Page: 4 of 9 Admin JPM CO-2
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 Procedure Sections 3 limitations. and 4 SAT [ ] UNSAT [ ]
Standards Initial Conditions are verified and Precautions and limitations have been reviewed Notes/Comments 2016 NRC EXAM Page: 5 of 9 Admin JPM CO-2
2 Request the shift manager to direct an instrument technician to Procedure Attachment determine the channel current for each power-range detector, if 2 Step 1 desired.
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 Page: 6 of 9 Admin JPM CO-2
4 Record the expected 100% power current readings from the Given data Reactor Data Book.
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 Page: 7 of 9 Admin JPM CO-2
7 Record the value and location of the largest quadrant power tilt Procedure Attachment ratio. 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 Procedure Section 7.1 cited in the procedure.
Critical Step SAT [ ] UNSAT [ ]
Standards Operator determines that the QPTR does NOT meet the acceptance criteria guidelines.
Notes/Comments 2016 NRC EXAM Page: 8 of 9 Admin JPM CO-2
9 Notify the shift manager that the periodic test has been completed Procedure Section 7.2 and of any out of specification conditions.
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 Tech Spec 3.4.2.A Action 3.2.4.A Critical Step SAT [ ] UNSAT [ ]
Standards Tech Specs require that power is reduced 3% from rated thermal 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 __________
2016 NRC EXAM Page: 9 of 9 Admin JPM CO-2
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.
KB
_______ 3.1 IF power level is 75% or greater, THEN all 4 power range detectors are OPERABLE.
KB
_______ 3.2 Check at least three Excore Power Range Channels are operable.
KB
_______ 3.3 Check the Reactor is at a stable power level.
KB
_______ 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.
N/A KB
_______ 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 KB
_______ 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).
DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 7 of 15 KB
_______ 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.
KB
_______ 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.
N/A KB
_______ 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.
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:
N/A KB
_______
- Obtain the equipment listed below and check the equipment is calibrated to INST standards traceable to the National Institute of Standards and Technology M & TE Type Accuracy Requirement DMM At least 5 1/2 digits and 1000 Megohm input resistance on 2 VDC range
_______
- Obtain test leads to connect the DMM above to a double banana jack (0.75 inch INST centers).
_______
- Record the following for the Digital Multimeter:
INST NQC No.: _______________________ Cal Due Date: ________________________
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.
N/A KB
_______
- 1-PT-23.1, Quadrant Power Tilt Ratio Determination Using the Incore Detector System
_______
- 1-PT-21.1, Reactor Core Flux Mapping
_______ 6.1.2 Obtain Reactor Engineer concurrence that an incore flux map is not required RX ENG 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.
N/A KB
_______
- IF desired to use the Unit 1 PCS to determine QPTR, THEN complete Attachment 1, Unit 1 PCS QPTR Calculation.
KB
_______
- IF desired to perform a hand calculation to determine QPTR, THEN complete Attachment 2, QPTR Hand Calculation.
7.0 FOLLOW-ON 7.1 Acceptance Criteria KBKB
_______ 7.1.1 A QPTR has been determined from at least 3 Operable Excore Power Range detectors.
DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 10 of 15 1
_______ 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.
KB
_______ 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:
KB
_______
- Notify the SRO.
KB
_______
- Enter Action Statement of Tech Spec Action 3.2.4.A.
KB
_______ 7.2.3 IF the QPTR is greater than 1.015, THEN notify the Reactor Engineer.
7.3 Completion Notification KB
_______ Notify the SRO that this test is complete.
K Blev Completed by: ___________________________________________ Date: _________ Today ATTACHMENTS
DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 11 of 15 (Page 1 of 2)
Attachment 1 Unit 1 PCS QPTR Calculation N/A KB
_______ 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.
_______ _______ 3. IF the present value of K0829 is NOT equal to the value determined in Step 1, THEN SV 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.
DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 12 of 15 (Page 2 of 2)
Attachment 1 Unit 1 PCS QPTR Calculation N/A KB
_______ 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.
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.
_______ 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.
DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 13 of 15 (Page 1 of 3)
Attachment 2 QPTR Hand Calculation 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).
- 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:
N/A KB
_______ 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.
_______ 1.2 Have the Instrument Department technician place the DMM on the 2 VDC INST scale.
_______ 1.3 Have the Instrument Department technician ground the test leads to the drawer INST case and short together prior to making each connection to reduce the possibility of adversely impacting the Power Range Detector channel.
_______ _______ 1.4 TM: Have the Instrument Department technician connect the DMM to the test INST INST SV 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.
_______ _______ 1.7 TM: Have the Instrument Department technician disconnect the DMM from INST INST the test jacks.
DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 14 of 15 (Page 2 of 3)
Attachment 2 QPTR Hand Calculation KB
_______ 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.
N/A KB
_______ 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.
KB
_______ 4. Complete the calculations on Page 3 of this attachment.
KB
_______ 5. Have a qualified individual complete an independent verification of all calculations.
DOMINION 1-PT-23 North Anna Power Station Revision 30 Page 15 of 15 (Page 3 of 3)
Attachment 2 QPTR Hand Calculation NOTE: Current Readings may be obtained from the face meters of the Power Range B Drawer OR from the test jacks OR from the Unit 1 PCS, if operable.
Avg. of Upper N-41 N-42 N-43 N-44 Normalized Description Upper Upper Upper Upper Currents Current Reading (record to nearest a) 170 175 165 200 Expected Current (record as shown in Reactor Data Book or 1-PT-22.4) 172.1 200.9 168.8 201.9 Normalized Current (Current Reading / Expected Current)
(4 decimal places) .9878 .8711 .9775 .9906 .9567 QPTR (Normalized Current / Avg. of Norm. Currents)
(4 decimal places) 1.0325 .9105 1.0217 1.0354 Avg. of Lower N-41 N-42 N-43 N-44 Normalized Description Lower Lower Lower Lower Currents Current Reading (record to nearest a) 210 190 210 215 Expected Current (record as shown in Reactor Data Book or 1-PT-22.4) 203.8 213.4 208.1 216.0 Normalized Current (Current Reading / Expected Current)
(4 decimal places) 1.0304 .8903 1.0091 .9954 .9813 QPTR (Normalized Current / Avg. of Norm. Currents)
(4 decimal places) 1.0500 .9073 1.0283 1.0143 1.0500 (Record Maximum Upper or Maximum QPTR: _________________________________
Lower QPTR Value from above)
N-41 Lower (N41 Upper, N41 Lower Quadrant of Max QPTR: _________________________________
N42 Upper, N42 Lower, etc.)
K Blev Completed by: __________________________________________ Date: ________
4/14/16 Emmett Brown Verified by:_____________________________________________
Today / Now (Use this Time for recording Date/Time Verification Completed: ________________________________
when 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.
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 Page: 2 of 8 Admin JPM CO 2 (ALL)
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 Page: 3 of 8 Admin JPM CO 2 (ALL)
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 Page: 4 of 8 Admin JPM CO 2 (ALL)
1 Verify that the initial conditions, precautions, and limitations are Procedure Sections 3 met. 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 Page: 5 of 8 Admin JPM CO 2 (ALL)
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 Procedure Attachment the instantaneous shutdown conditions. 1 Step 17 Critical Step SAT [ ] UNSAT [ ]
Standards Difference is calculated to be 1659 +/- 100 pcm.
Notes/Comments 2016 NRC EXAM Page: 6 of 8 Admin JPM CO 2 (ALL)
7 If necessary, calculate the boron concentration required to achieve Procedure Attachment a shutdown margin of at least 1.77% K/K. 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 Procedure Section 7 met.
SAT [ ] UNSAT [ ]
Notes/Comments
>>>>> END OF EVALUATION <<<<<
STOP TIME __________
2016 NRC EXAM Page: 7 of 8 Admin JPM CO 2 (ALL)
SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required) 2016 NRC EXAM Page: 8 of 8 Admin JPM CO 2 (ALL)
PROCEDURE NO:
1-PT-10.1 KEY REVISION NO:
NORTH ANNA POWER STATION 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. Modes 1 and 2
- At Least Once per 12 Hours while a rod is misaligned.
SPECIAL CONDITIONS: None SURV EOP REACT REQ AP 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): WORK REQUEST NUMBERS AND DATE:
Satisfactory Unsatisfactory Partial THE FOLLOWING PROBLEM(S) WERE ENCOUNTERED AND CORRECTIVE ACTIONS TAKEN:
UNIT ONE
______________________________________________________________________________ (Use back for additional remarks.)
COGNIZANT SUPERVISOR or DESIGNEE: DATE:
ADDITIONAL REVIEWS: DATE:
Reactor Engineering:
CONTINUOUS USE KEY
DOMINION 1-PT-10.1 North Anna Power Station KEY Revision 13 Page 2 of 14 TABLE OF CONTENTS Section Page 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
DOMINION North Anna Power Station KEY 1-PT-10.1 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.
Attachment 2, 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
DOMINION North Anna Power Station KEY 1-PT-10.1 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 KB
_______ 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 />.
KEY
DOMINION 1-PT-10.1 North Anna Power Station KEY Revision 13 Page 5 of 14 KB
_______ 3.2 Verify no dilutions to the RCS have been performed since the most recently measured boron concentration.
KB
_______ 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.
KB
_______ 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.
KB
_______ 3.5 Notify the SRO of this test.
4.0 PRECAUTIONS AND LIMITATIONS KB
_______ 4.1 Comply with the following guidelines when marking steps N/A:
KB
_______
- IF the conditional requirements of a step do not require the action to be performed, THEN mark the step N/A.
KB
_______
- 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
_______ 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.
KB
_______ 4.3 Tech Spec 3.1.1 is not applicable in Mode 1 or in Mode 2 with Keff >1.0.
KEY
DOMINION North Anna Power Station KEY 1-PT-10.1 Revision 13 Page 6 of 14 KB
_______ 4.4 Tech Spec 3.1.4 applies in Mode 1 or in Mode 2 during conditions of:
KB
_______
- One or more inoperable shutdown or control rod KB
_______
- One or more misaligned shutdown or control rod KB
_______ 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)
KB
_______
_______
_______ 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.
KBKB
_______ 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 KEY
DOMINION North Anna Power Station KEY 1-PT-10.1 Revision 13 Page 7 of 14 6.0 INSTRUCTIONS KB KB
_______ _______ 6.1 Record the required values in Items 1 through 15 on Attachment 1, Shutdown Margin Determination.
KB
_______ _______ 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.
KB
_______ _______ 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.
KB
_______ _______ 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 KB
_______ _______ 7.1.1 The Shutdown Margin with Inoperable or Misaligned Control Rods was determined.
1
_______ _______ 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:
N/A KB _______
_______ 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.
KB
_______ _______ b. Start a boration in accordance with the applicable Action Statement of Tech Spec 3.1.4, 3.1.5, or 3.1.6.
KEY
DOMINION 1-PT-10.1 North Anna Power Station KEY Revision 13 Page 8 of 14 7.3 Completion Notification KB
_______ 7.3.1 Record results in the Narrative Log to include actual or projected shutdown margin PCM value.
KB
_______ 7.3.2 Notify the SRO this test is complete.
K. Chuck Bartowski Completed by: ___________________________________________ Date: _________ 4/14/16 ATTACHMENTS KEY
DOMINION North Anna Power Station KEY 1-PT-10.1 Revision 13 Page 9 of 14 (Page 1 of 3)
Attachment 1 Shutdown Margin Determination Current Critical Conditions
- 1. Date: Today
- 2. Time: Now
- 3. Core Burnup (MWD/MTU): 15,500
- 4. Power (%): 100
- 5. C Bank Position (steps): 227
- 6. D Bank Position (steps): 227
- 7. Boron Concentration (ppm): 600
- 8. Boron Worth Coefficient (pcm/ppm): -7.11- 7.12 to -7.13 (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 2 Rods:
- 10. Stuck Rod Worth (pcm): 1634 (1-SC-8.1 or 8.3)
KEY
DOMINION North Anna Power Station KEY 1-PT-10.1 Revision 13 Page 10 of 14 (Page 2 of 3)
Attachment 1 Shutdown Margin Determination Instantaneous Current Shutdown Critical Conditions Conditions
-5587 to -5589
-5588 0
- 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):
1634 -
2 - + 0.55 x -------------------- 4167
___________ 0 Item 9 Item 10 =
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 0 0 position (pcm): (1-SC-8.1)
- 14. Reactivity Redistribution Factor 330 to 332
___________ 0 (pcm): (1-SC-8.4)
- 15. Power Defect (pcm): 0 -2650
-2647 to -2653 (1-SC-3.8)
- 16. Reactivity Worth of up to 8 Rods stuck 100 0 at 10 steps.
-988-991 to -992
___________ -2647-2650 to -2653
___________ 1659 1659 to 1661
- 17. Totals: - =
pcm KEY
DOMINION North Anna Power Station KEY 1-PT-10.1 Revision 13 Page 11 of 14 (Page 3 of 3)
Attachment 1 Shutdown Margin Determination
- 18. Determine Required Boron Concentration Change (CB) as Follows:
1659 to1661
(-1770 pcm) - ----------------------------- - pcm (Item 17) 482
____________________ = ---------------------------------------------- ppm
( C B )
-7.12
- pcm/ppm (Item 8)
KEY
DOMINION 1-PT-10.1 North Anna Power Station KEY Revision 13 Page 12 of 14 (Page 1 of 3)
Attachment 2 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
DOMINION North Anna Power Station KEY 1-PT-10.1 Revision 13 Page 13 of 14 (Page 2 of 3)
Attachment 2 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
DOMINION North Anna Power Station KEY 1-PT-10.1 Revision 13 Page 14 of 14 (Page 3 of 3)
Attachment 2 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
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).
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 Page: 2 of 9 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 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 Page: 3 of 9 Admin JPM RadCon (ALL)
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 Page: 4 of 9 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 [ ]
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 Page: 5 of 9 Admin JPM RadCon (ALL)
2 From the RWPs provided, determine the dose alarm setpoint and Procedure Step:
dose rate alarm in effect under the RWP. 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 Procedure Step:
the RWP dose alarm setpoint. 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 <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />) based on the RWP dose alarm setpoint.
Notes/Comments:
2016 NRC EXAM Page: 6 of 9 Admin JPM RadCon (ALL)
4 Determine the maximum stay time in minutes based on reaching Procedure Step:
the RWP requirements. 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 Page: 7 of 9 Admin JPM RadCon (ALL)
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 Page: 8 of 9 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: 9 of 9 Admin JPM RadCon (ALL)
Unit 2 Containment, 262 Elevation Verified Current By Date A Motor Cube 60 80 55 20 80 45 2-RC-E-1A 6
2-RC-P-1A 1
5 4 HRA Called North 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 All gamma and/or neutron readings in mRem/hr unless Gen Area; Contact; LCK Locked Gate; Barrier noted.
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.
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 Page: 2 of 9 EP JPM (SRO)
2016 NRC EXAM Page: 3 of 9 EP JPM (SRO)
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 Page: 4 of 9 EP JPM (SRO)
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 Page: 5 of 9 EP JPM (SRO)
1 CHECK THE FOLLOWING: Procedure Step 7 Average wind direction shifts to any new area(s) (refer to ATTACHMENT 2, AFFECTED SECTOR(S) MAP)
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: Procedure Step 17
- 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 Standards Attachment 2 is updated (See KEY)
Notes/Comments 2016 NRC EXAM Page: 6 of 9 EP JPM (SRO)
3 COMPLETE PROTECTIVE ACTION RECOMMENDATION: Procedure Step 18.a 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 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- Procedure Step 19 SITE AUTHORITIES OF PAR:
- Virginia Emergency Operations Center (VEOC) notified IAW:
EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS Critical Step SAT [ ] UNSAT [ ]
Standards Notes/Comments
>>>>> END OF EVALUATION <<<<<
2016 NRC EXAM Page: 7 of 9 EP JPM (SRO)
STOP TIME __________
2016 NRC EXAM Page: 8 of 9 EP JPM (SRO)
SIMULATOR, LABORATORY, IN--PLANT SETUP (If Required) 2016 NRC EXAM Page: 9 of 9 EP JPM (SRO)
KEY NUMBER ATTACHMENT TITLE ATTACHMENT EPIP-1.06 3 REPORT OF PROTECTIVE ACTION RECOMMENDATION REVISION PAGE 11 1 of 1 PAR MESSAGE # ________ 2 NOTE:
- 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: ____ 2 Mile radius 360° and ____10 Miles downwind in the following sectors:
D,E,F,G,H 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: ________________________________________________________________________________
Signature APPROVED BY: ___________________________________________ Today's Date / _________
______________ Current Station Emergency Manager or Recovery Manager Date Time KEY
KEY NUMBER ATTACHMENT TITLE ATTACHMENT EPIP-1.06 2 AFFECTED SECTOR(S) MAP REVISION PAGE 11 1 of 1 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)
Current At ____________, Wind Direction From ___________, 280 25 Wind Speed ____________, D,E,F,G,H 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 AFFECTED DIRECTION A SECTORS R 348.75° 11.25° B (Degrees) From 326.25° 33.75° 349 - 11 H, J, K Q C 12 - 33 J, K, L 56.25° 303.75° 34 - 56 K, L, M D
P 57 - 78 L, M, N 78.75° 79 - 101 M, N, P 281.25° 102 - 123 N, P, Q N E 124 - 146 P, Q, R 2
101.25° 101.25 147 - 168 Q, R, A 258.75° 169 - 191 R, A, B 5
M F 192 - 213 A, B, C 123.75° 1233.75 236.25° 214 - 236 B, C, D L 10 G 237 - 258 C, D, E 213.75° 146.25° 146.25 259 - 281 D, E, F K 191.25° 168.75° 8.75
.75 H J Graphics No. SB1217E 282 - 303 E, F, G 304 - 326 F, G, H 327 - 348 G, H, J KEY
NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS (WITH 5 ATTACHMENTS) PAGE 1 of 11 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.
COMMON REFERENCE USE
NUMBER PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS 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.
JS
____ 1 INITIATE PROCEDURE:
Joseph Supervisor
- By: ______________________________
Today Date: ____________________________
45 minutes ago Time: ____________________________
JS
____ 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.
JS
____ 3 IMPLEMENT ATTACHMENT 2, AFFECTED SECTOR(S) MAP:
a) Record time wind data acquired a) b) Record average wind direction from, in b) degrees c) Record average wind speed in mph c) d) Record affected sectors d) e) Mark affected sectors on map (use any writing e) implement available, e.g., pen, pencil, highlighter, etc.)
NUMBER PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS PAGE 3 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED JS
____ 4 COMPLETE ATTACHMENT 3, REPORT OF a)
PROTECTIVE ACTION RECOMMENDATION:
a) Protective Action Recommendation:
- 1) Mark appropriate PAR box(s)
- 2) Record Mile radius and Miles downwind
Mark PAR box: POTASSIUM IODIDE c) Remarks/Approval Information: c)
- 1) Record Remarks (optional)
- 2) Approve PAR (sign report)
- 3) Record date and time report approved JS
____ 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)
NUMBER PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS 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: GO TO Step 8
- CSFST Core Cooling RED AND
- Any Containment Loss Fission Product Barrier threshold met Revised PAR provided by RAD/RAC IAW GO TO Step 13 EPIP-4.07, PROTECTIVE MEASURES Average wind direction shifts to any new area(s)
(refer to ATTACHMENT 2, AFFECTED GO TO Step 17 SECTOR(S) MAP)
PAR in effect - CONDITIONS UNCHANGED GO TO Step 20
NUMBER PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS PAGE 5 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED JS
____ 8 CHECK IF SEVERE ACCIDENT CONDITIONS RETURN TO Step 7.
EXIST:
- CSFST Core Cooling RED AND
- Any Containment Loss Fission Product Barrier threshold met JS
____ 9 COMPLETE ATTACHMENT 3, REPORT OF a)
PROTECTIVE ACTION RECOMMENDATION:
a) Protective Action Recommendation:
- 1) Mark PAR box: EVACUATE
- 2) Record Mile radius 360°: 2
- 3) Record Miles downwind: 10
Mark PAR box: POTASSIUM IODIDE c) Remarks/Approval Information: c)
- 1) Record Remarks (optional)
- 2) Approve PAR (sign report)
- 3) Record date and time report approved
NUMBER PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS PAGE 6 of 11 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED JS
____ 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 RETURN TO Step 7.
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
NUMBER PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS 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 PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS 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: a) RETURN TO Step 7.
- 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) 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 PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS 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 PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS 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 PROCEDURE TITLE REVISION 11 EPIP-1.06 PROTECTIVE ACTION RECOMMENDATIONS 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 -
NUMBER ATTACHMENT TITLE ATTACHMENT EPIP-1.06 1 PROTECTIVE ACTION RECOMMENDATION FLOWCHART REVISION PAGE NAPS 11 1 of 1 General Emergency Declared Yes Evacuate Severe 0-2 mile radius Accident 2-10 miles (Note 1) Yes downwind No Dose Hostile Assessment Shelter-In-Place Action directs 0-2 mile radius Yes No evacuation TPSLZ
downwind No Yes PAG PAG PAG PAG Dose exceeded exceeded exceeded 56; Assessment IL`VUK TPSLZ beyond 2 miles H[:P[L)V\UKHY` exceeded Available Yes No No No (Note 2) (Note 2) (Note 2)
No Yes Yes Yes Yes Evacuate Evacuate Evacuate Evacuate Evacuate 0-2 mile radius TPSLYHKP\Z 0-2 mile radius 0-2 mile radius 0-10 mile radius
TPSLZ TPSLZ TPSLZ TPSLZ
all sectors downwind downwind downwind downwind Recommend implementation of Potassium Iodide (KI) strategies for the general public when the projected dose at site boundary PZ 9LT;O`YVPK*+,
0ZZ\L7YV[LJ[P]L(J[PVU9LJVTTLUKH[PVUMVYJ\YYLU[*VUKP[PVUZ Note 1: Note 2:
*:-:;*VYL*VVSPUN9,+ 9LT;,+,
AND OR
(U`*VU[HPUTLU[3VZZ-PZZPVU7YVK\J[)HYYPLY[OYLZOVSKTL[ 9LT;O`YVPK*+,
Graphics No: MT2068
NUMBER ATTACHMENT TITLE ATTACHMENT EPIP-1.06 2 AFFECTED SECTOR(S) MAP REVISION PAGE 11 1 of 1 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:
45 min ago Wind Direction From ___________,
At ____________, 310 12 Wind Speed ____________, F,G,H 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 AFFECTED DIRECTION A SECTORS R 348.75° 11.25° B (Degrees) From 326.25° 33.75° 349 - 11 H, J, K Q C 12 - 33 J, K, L 56.25° 303.75° 34 - 56 K, L, M D
P 57 - 78 L, M, N 78.75° 79 - 101 M, N, P 281.25° 102 - 123 N, P, Q N E 124 - 146 P, Q, R 2
101.25° 147 - 168 Q, R, A 258.75° 169 - 191 R, A, B 5
M F 192 - 213 A, B, C 123.75° 236.25° 214 - 236 B, C, D L 10 G 237 - 258 C, D, E 213.75° 146.25° 259 - 281 D, E, F K 191.25° 168.75° H J Graphics No. SB1217E 282 - 303 E, F, G 304 - 326 F, G, H 327 - 348 G, H, J
NUMBER ATTACHMENT TITLE ATTACHMENT EPIP-1.06 3 REPORT OF PROTECTIVE ACTION RECOMMENDATION REVISION PAGE 11 1 of 1 PAR MESSAGE # ________ 1 NOTE:
- 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: ____ 2 Mile radius 360° and ____
10 Miles downwind in the following sectors:
F,G,H 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.
45 min ago (24-hr time).
The time is ______________
John Talker This is ________________________________________________________ / Emergency Communicator.
Bob Early Message received by: Virginia EOC Watch Officer (name) ______________________________________.
This is North Anna Power Station out at _______________ Today 45 min ago (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: ________________________________________________________________________________
Joseph Supervisor APPROVED BY: ___________________________________________ Today
______________ 45 min ago
/ _________
Station Emergency Manager or Recovery Manager Date Time
NUMBER ATTACHMENT TITLE ATTACHMENT EPIP-1.06 4 REFERENCE INFORMATION REVISION PAGE (NAPS) 11 1 of 1 As reflected in Attachment 1, PROTECTIVE ACTION RECOMMENDA-KNOWN TION FLOWCHART NAPS, the only impediment North Anna Power EVACUATION Station will consider in the development of PARs will be Hostile Actions IMPEDIMENTS: directed at the site.
The initial PAR must be included with the initial notification of a General Emergency, which must be made to the State within 15 minutes PAR NOTIFICATION following declaration of the General Emergency.
TIMES:
Notification of a revised PAR must be made to the State within 15 minutes of its development.
Downwind sectors may be determined from the table on Attachment 2, SECTORS/ AFFECTED SECTOR(S) MAP.
WIND DIRECTION:
Wind direction is always given in degrees from.
SHELTERING Sheltering-In-Place is recommended when a known condition or IN impediment exists which makes evacuation dangerous. A Hostile PLACE: Action based event is the only know impediment to evacuation.
Previously issued Protective Action Recommendations should not be PREVIOUSLY reduced until the threat is fully under control and after consulting with ISSUED PAR: Commonwealth of Virginia emergency response organization.
NUMBER ATTACHMENT TITLE ATTACHMENT EPIP-1.06 5 SECTOR MAP REVISION PAGE 11 1 of 1 669 624 651 608 613 629 348.75° 11.25° 648 629 687 680 608 1726 629 651 664 696 A
606 612 10 Miles 703 649 677 630 669 649 687 326.25° R 612 B 33.75° 1725 747 651 601 208 652 606 606 648 669 522 653 612 606 612 652 653 651 669 612 Q
719 719 721 650 C
208 208 728 606 612 659 691 643 733 701 656 651 303.75° 612 718 56.25° 7000 738 620 651 612 601 5 Miles 602 Lake Anna 667 648 612 State Park 712 208 752 669 652 Lake Anna 656 613 P D 738 647 522 208 601 719 Lake Anna 614 614 613 738 647 669 281.25° 613 2 Miles 208 689 78.75° 628 657 623 614 738 678 625 652 605 779 605 605 669 N 624 623 North Anna Power Station 614 601 605 738 605 E 604 522 720 700 628 208 670 625 622 622 658 22 700 652 33 751 738 258.75° 623 605 208 738101.25° 22 658 712 622 669 703 601 700 669 671 Louisa Lake Anna 208 666 679 M
767 Mineral 700 618 618 652 F 671 738 646 738 669 33 665 775 601 689 681 658 669 522 701 123.75° 738 236.25° 605 652 604 689 656 682 618 603 715 644 779 618 601 601 772 646 L 656 704 G
715 605 609 716 658 601 739 684 715 213.75° 612 618 146.25° 697 699 K 612 609 655 701 H673 680 729 South Anna River 680 658 640 605 522 609 J 654 680 763 738 33 191.25° 168.75°608 715 774 640 657 655 608 608 601 Graphics No. SV634A
NUMBER ATTACHMENT TITLE ATTACHMENT EPIP-1.06 3 REPORT OF PROTECTIVE ACTION RECOMMENDATION REVISION PAGE 11 1 of 1 PAR MESSAGE # ________
NOTE:
- 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