ML15259A396
| ML15259A396 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 09/16/2015 |
| From: | Division of Reactor Safety II |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML15259A396 (137) | |
Text
2015 301NRCEXAMAdministrativeJPM1 R WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-R 2015-301 NRC EXAM Page 2 of 13 EVALUATION SHEET Task: DETERMINE LICENSE STATUS ACTIVE OR INACTIVE.
Alternate Path:
n/a Facility JPM #:
Modified.
Safety Function:
N/A Title: Conduct of Operations.
K/A 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
Rating(s):
3.3/3.8 CFR: 41.10/43.2 Evaluation Method:
Simulator In-Plant Classroom X References
- OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions , Rev. 8.
Task Number:
RO-119-PAI-2.07-001 Title: Maintain active NRC License Task Standard:
Applicant reviews data provided and determines: 1. RO A is INACTIVE. 2. RO B is ACTIVE. 3. RO C is ACTIVE.
Validation Time:
15 minutes Time Critical:
Yes No X ========================================================================================= Applicant: ___________________________ _________________
Time Start: ________
NAME Docket No.
Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________ NAME SIGNATURE DATE ==========================================================================================
COMMENTS WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-R 2015-301 NRC EXAM Page 3 of 13 Tools/Equipment/Procedures Needed:
Laptop Computer. NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the appli cant via a laptop computer loaded with the NRC REFERENCE DISK.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-R 2015-301 NRC EXAM Page 4 of 13 DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
Three (3) Reactor Operators (R Os) have the following history: Reactor Operators A and C obtained their NRC License in 2012. Reactor Operator B was issued a license on January 15, 2015 All perform off-shift a ssignments at the plant. All are current in License O perator Requalific ation Training. LMS demonstrates associated medical r equirements of OPDP-10 have been met for each RO. None of the three (3) has worked any shift since March 15, 2015.
The ACTIVE/INACTIVE status and time on shift since January 1, 2015 is as follows for each of the ROs: REACTOR OPERATOR - A License was ACTIVE on January 1, 2015 01/02/15 Worked 0700-1530 shift as Unit 1 OAC. 01/03/15 Worked 0700-1700 shift as Unit 1 OAC. 01/04/15 Worked 0700-1900 shift as Unit 1 OAC. 01/05/15 Worked 0700-1900 shift as Unit 1 OAC. 02/26/15 Worked 0700-1900 shift as Unit 1 OAC.
REACTOR OPERATOR - B License was ISSUED on January 15, 2015 02/01/15 Worked 0700-1530 shift as Unit 1 CRO. 02/02/15 Worked 0700-1530 shift as Unit 1 OAC. 02/14/15 Worked 1900-0700 shift as Unit 1 OAC. 03/02/15 Worked 0700-1900 shift in the Tagging Office.
REACTOR OPERATOR - C License was ACTIVE on January 1, 2015 01/07/15 Worked 0700-1900 shift as Unit 1 OAC. 01/08/15 Worked 0700-1900 shift as Unit 1 OAC. 01/09/15 Worked 0700-1900 shift as Unit 1 OAC. 01/10/15 Worked 0700-1900 shift as Unit 1 OAC. 02/28/15 Worked 0700-1900 shift as Unit 1 CRO.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-R 2015-301 NRC EXAM Page 5 of 13 INITIATING CUES:
You are to determine if each of the RO's Licenses is ACTI VE or INACTIVE as of 0700 on April 1, 2015.
Circle your answer in the statements provided below: RO A's License is ACTIVE / INACTIVE.
RO B's License is ACTIVE / INACTIVE. RO C's License is ACTIVE / INACTIVE.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 6 of 13 START TIME: _______
STEP 1.: Determine the ACTIVE / INACTI VE status of RO A's license STANDARD: The Applicant determines the license is INACTIVE due to the following reasons: (Critical)
The RO DID NOT work the required qualified 5 twelve hour shifts in a license position during the previous quarter.
OPDP-10, 3.2.2.B. To be granted credit for a shift, the individual shall be present from shift turnover though shi ft turnover. The shift period is defined by the schedule worked by the rotati ng shift crews. Either 12-hour or 8-hour shifts is the normal.
Step is critical to ensure an RO with an inactive license does not perform license duties COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 7 of 13 STEP 2.: Determine the ACTIVE / INACTIVE status of RO B's license STANDARD: The Applicant determines the license is ACTIVE due to the following reasons: (Critical)
In accordance with OPDP-10, 3.2.1. F, When a licensee is issued a new NRC License number, the licensee is immediately active. The licensee is not required to perform 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Under Instruction that calendar quarter and is not required to stand five 12-hour sh ifts or seven 8-hour shifts in the calendar quarter that the new license number was issued. The licensee must stand the required shifts in the next calendar quarter to maintain an
active license.
Step is critical to ensure an RO with an inactive license does not perform license duties COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 8 of 13 STEP 3.: Determine the ACTIVE / INACTIVE status of RO C's license STANDARD: The Applicant determines the license is ACTIVE due to the following reasons: (Critical)
On 01/08/15, the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time to attend the pre-job brief COUNTS as actively performing the functions of an operator, so all of the hours for the shift are courted.
Assisting an AUO in the perform ance of a surveillance procedure DOES count as licensed duties. Credit towards license maintenance would be given for this period.
Step is critical to ensure an RO with an inactive license does not perform license duties.
COMMENTS:
END OF TASK CRITICAL STEP ___ SAT
___ UNSAT
STOP TIME ________
1-R Key
DO NOT HAND TO APPLICANT
You are to determine if each of the RO's Licenses is ACTI VE or INACTIVE as of 0700 on April 1, 2015.
Circle your answer in the statements provided below.
RO A's License is ACTIVE / INACTIVE.
RO B's License is ACTIVE / INACTIVE.
RO C's License is ACTIVE / INACTIVE.
1-R
Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 1-R INITIAL CONDITIONS:
Three (3) Reactor Operators (R Os) have the following history: Reactor Operators A and C obtained their NRC License in 2012. Reactor Operator B was issued a license on January 15, 2015 All perform off-shift a ssignments at the plant. All are current in License O perator Requalific ation Training. LMS demonstrates associated medical r equirements of OPDP-10 have been met for each RO. None of the three (3) has worked any shift since March 15, 2015.
The ACTIVE/INACTIVE status and time on shift since January 1, 2015 is as follows for each of the ROs: REACTOR OPERATOR - A License was ACTIVE on January 1, 2015 01/02/15 Worked 0700-1530 shift as Unit 1 OAC. 01/03/15 Worked 0700-1700 shift as Unit 1 OAC. 01/04/15 Worked 0700-1900 shift as Unit 1 OAC. 01/05/15 Worked 0700-1900 shift as Unit 1 OAC. 02/26/15 Worked 0700-1900 shift as Unit 1 OAC.
REACTOR OPERATOR - B License was ISSUED on January 15, 2015 02/01/15 Worked 0700-1530 shift as Unit 1 CRO. 02/02/15 Worked 0700-1530 shift as Unit 1 OAC. 02/14/15 Worked 1900-0700 shift as Unit 1 OAC. 03/02/15 Worked 0700-1900 shift in the Tagging Office.
REACTOR OPERATOR - C License was ACTIVE on January 1, 2015 01/07/15 Worked 0700-1900 shift as Unit 1 OAC. 01/08/15 Worked 0700-1900 shift as Unit 1 OAC. 01/09/15 Worked 0700-1900 shift as Unit 1 OAC. 01/10/15 Worked 0700-1900 shift as Unit 1 OAC. 02/28/15 Worked 0700-1900 shift as Unit 1 CRO.
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 1-R INITIATING CUES:
You are to determine if each of the RO's Licenses is ACTI VE or INACTIVE as of 0700 on April 1, 2015.
Circle your answer in the statements provided below: RO A's License is ACTIVE / INACTIVE.
RO B's License is ACTIVE / INACTIVE. RO C's License is ACTIVE / INACTIVE.
2015 301NRCEXAMAdministrativeJPM1 S WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-S 2015-301 NRC EXAM Page 2 of 13 EVALUATION SHEET Task: DETERMINE LICENSE STATUS ACTIVE OR INACTIVE.
Alternate Path:
n/a Facility JPM #:
Modified Safety Function:
N/A Title: Conduct of Operations.
K/A 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.
Rating(s):
3.3/3.8 CFR: 41.10/43.2 Evaluation Method:
Simulator In-Plant Classroom X References
- OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions , Rev. 8.
Task Number:
SRO-119-PAI-2.07-001 Title: Maintain active NRC License.
Task Standard:
Applicant reviews data provided and determines: 1. RO A is INACTIVE 2. RO B is ACTIVE 3. SRO C is ACTIVE Validation Time:
15 minutes Time Critical:
Yes No X ========================================================================================= Applicant: ___________________________ _________________
Time Start: ________
NAME Docket No.
Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________ NAME SIGNATURE DATE ==========================================================================================
COMMENTS WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-S 2015-301 NRC EXAM Page 3 of 13 Tools/Equipment/Procedures Needed:
Laptop Computer. NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the appli cant via a laptop computer loaded with the NRC REFERENCE DISK.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-S 2015-301 NRC EXAM Page 4 of 13 DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
Three (3) Reactor Operators (R Os) have the following history: Reactor Operator A an NRC License in 2012. Reactor Operator B was issued an NRC License on January 15, 2015. SRO C obtained their NRC License in 2011. All perform off-shift a ssignments at the plant. All are current in License Operator Requalification Training. LMS demonstrates associated medical r equirements of OPDP-10 have been met for each operator.
The ACTIVE/INACTIVE status and time on shift since January 1, 2015 is as follows for each of the ROs: REACTOR OPERATOR - A License was ACTIVE on January 1, 2015 01/02/15 Worked 0700-1530 shift as Unit 1 OAC. 01/03/15 Worked 0700-1700 shift as Unit 1 OAC. 01/04/15 Worked 0700-1900 shift as Unit 1 OAC. 01/05/15 Worked 0700-1900 shift as Unit 1 OAC. 02/26/15 Worked 0700-1900 shift as Unit 1 OAC.
REACTOR OPERATOR - B License was ISSUED on January 15, 2015 02/01/15 Worked 0700-1530 shift as Unit 1 CRO. 02/02/15 Worked 0700-1530 shift as Unit 1 OAC. 02/14/15 Worked 1900-0700 shift as Unit 1 OAC. 03/02/15 Worked 0700-1900 shift in the Tagging Office.
SENIOR REACTOR OPERATOR - C License was ACTIVE on January 1, 2015 01/01/15 Worked 0700-1900 shift as Unit 1 US. 01/02/15 Worked 0700-1900 shift as Unit 1 OAC. 01/03/15 Worked 0700-1900 shift as Unit 1 OAC. 01/05/15 Worked 0700-1900 shift as Unit 1 OAC. 01/14/15 Worked 1900-0700 shift as Refueling SRO. 02/02/15 Worked 0700-1900 shift as Unit 1 OAC.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-S 2015-301 NRC EXAM Page 5 of 13 INITIATING CUES:
You are to determine if each of the operators is ACTIVE or INAC TIVE as of 0700 on April 1, 2015. Circle your answer in the statements provided below: RO A's License is ACTIVE / INACTIVE.
RO B's License is ACTIVE / INACTIVE. RO C's License is ACTIVE / INACTIVE.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-S 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 6 of 13 START TIME: _______
STEP 1.: Determine the ACTIVE / INACTIVE status of RO A's license STANDARD: The Applicant determines the license is INACTIVE due to the following reasons: (Critical)
Per OPDP-10, Section 3.2.2, Nuclear Plant Requirements for Maintaining Active License Status, Item B.
B. To be granted credit for a shift, the individual shall be present from shift turnover though shift turnover. The sh ift period is defined by the schedule worked by the rotating shift crews. Eit her 12-hour or 8-hour shifts is the normal. The operator DID NOT work the required qu alified 5 twelve hour shifts in a license position during the previous quarter.
On 1/08/15, the RO was not present on shift from shift turnover to shift turnover.
On 1/07/15, the RO worked in the Tagging Office for which credit was not received. Step is critical to ensure an RO with an inactive license does not perform license duties.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-S 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 7 of 13 STEP 2.: Determine the ACTIVE / INACTIVE status of RO B's license STANDARD: The Applicant determines the license is ACTIVE due to the following reasons: (Critical)
Per OPDP-10, Section 3.2.1, ACTIVE LICENSE STATUS MAINTENANCE, Item C. When a licensee is issued a new NRC License number, the licensee is immediately active. The licensee is not required to perform 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Under Instruction that calendar quarter and is not required to stand five (5) 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts (or seven (7) ei ght hour shifts) in the calendar quarter that the new license number was iss ued. The licensee must stand five (5) 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts (or seven (7) eight hour sh ifts) in the next calendar quarter to maintain an active license.
Step is critical to ensure an RO with an inactive license does not perform license duties.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1-S 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 8 of 13 STEP 3.: Determine the ACTIVE / INACTIVE status of SRO C's license STANDARD: The Applicant determines the license is ACTIVE due to the following reasons: (Critical)
Per OPDP-10, Section 3.1 ACTIVE LICENSE STATUS MAINTENANCE, Item A: A. To maintain an active status, the licensee shall actively perform the functions of an operator or senior operator for a minimum of seven 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shifts a calendar quarter or five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts a calendar quarter in a position credited for watch-standing proficiency. To maintain the supervisory portion of a SRO license active, a SRO must stand at least one complete watch (8 or 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift) per calendar quarter in a shift crew position credited for SRO-only supervi sory licensed duties. It is the licensee's responsibility to maintain cognizance of his/her license status. The remainder of complete watches (to meet the required minimum of seven 8-hour or five 12-hour shifts per calendar quarter) may be performed in either a credited SRO or RO position.
SRO C stood one 12-hour shift in the cr edited Unit Supervisor position, thus maintaining the supervisory portion of the license. SRO C stood an additional 4 12-hour shifts in the RO position of OAC. SRO C stood one 12-hour shift as the Refueling SRO position, thus for which credit was not given. Step is critical to ensure an SRO with an inactive license does not perform license duties.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT
STOP TIME ________
1-S Key
DO NOT HAND TO APPLICANT
You are to determine if each of the Operator's Licenses is ACTIVE or INACTIVE as of 0700 on April 1, 2015.
Circle your answer in the statements provided below:
RO A's License is ACTIVE / INACTIVE
RO B's License is ACTIVE / INACTIVE
SRO C's License is ACTIVE / INACTIVE
1-S
Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 1-S INITIAL CONDITIONS:
Three (3) Reactor Operators (R Os) have the following history: Reactor Operator A an NRC License in 2012. Reactor Operator B was issued an NRC License on January 15, 2015. SRO C obtained their NRC License in 2011. All perform off-shift a ssignments at the plant. All are current in License Operator Requalification Training. LMS demonstrates associated medical r equirements of OPDP-10 have been met for each operator.
The ACTIVE/INACTIVE status and time on shift since January 1, 2015 is as follows for each of the ROs: REACTOR OPERATOR - A License was ACTIVE on January 1, 2015 01/02/15 Worked 0700-1530 shift as Unit 1 OAC. 01/03/15 Worked 0700-1700 shift as Unit 1 OAC. 01/04/15 Worked 0700-1900 shift as Unit 1 OAC. 01/05/15 Worked 0700-1900 shift as Unit 1 OAC. 02/26/15 Worked 0700-1900 shift as Unit 1 OAC.
REACTOR OPERATOR - B License was ISSUED on January 15, 2015 02/01/15 Worked 0700-1530 shift as Unit 1 CRO. 02/02/15 Worked 0700-1530 shift as Unit 1 OAC. 02/14/15 Worked 1900-0700 shift as Unit 1 OAC. 03/02/15 Worked 0700-1900 shift in the Tagging Office.
SENIOR REACTOR OPERATOR - C License was ACTIVE on January 1, 2015 01/01/15 Worked 0700-1900 shift as Unit 1 US. 01/02/15 Worked 0700-1900 shift as Unit 1 OAC. 01/03/15 Worked 0700-1900 shift as Unit 1 OAC. 01/05/15 Worked 0700-1900 shift as Unit 1 OAC. 01/14/15 Worked 1900-0700 shift as Refueling SRO. 02/02/15 Worked 0700-1900 shift as Unit 1 OAC.
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 1-S INITIATING CUES:
You are to determine if each of the operators is ACTIVE or INAC TIVE as of 0700 on April 1, 2015. Circle your answer in the statements provided below: RO A's License is ACTIVE / INACTIVE.
RO B's License is ACTIVE / INACTIVE. RO C's License is ACTIVE / INACTIVE.
2015 301NRCEXAMAdministrativeJPM2 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 2015-301 NRC EXAM EVALUATION SHEET Task: PERFORM RCS DEBORATION CALCULATION.
Alternate Path:
n/a Facility JPM #:
New Safety Function:
N/A Title: Equipment Control.
K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. Rating(s):
3.9/4.2 CFR: 41.10/45.13 Evaluation Method:
Simulator In-Plant Classroom X References
RO-062-TI-59-001 Title: Perform boron concentration change calculations.
Task Standard:
Applicant calculates it will take 96 minutes (acceptable range 92 to 100 minutes) to reduce RCS boron concentration from 40 ppm to 35 ppm based on 1-SOI-62.04, CVCS Purification System, Appendix B, RCS Deboration Calculation and TI-59, Boron Tables.
Validation Time:
15 minutes Time Critical:
Yes No X =========================================================================================
Applicant: ___________________________
_________________
Time Start: ________
NAME Docket No.
Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE ==========================================================================================
COMMENTS Page 2 of 10
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 2015-301 NRC EXAM Page 3 of 10 Tools/Equipment/Procedures Needed:
Laptop Computer. NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the appli cant via a laptop computer loaded with the NRC REFERENCE DISK.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 2015-301 NRC EXAM Page 4 of 10 DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 2 is performing pre-operational testing. 2. Unit 1 is in Mode 1 coasting down prior to refueling. 3. Current RCS C B is 40 ppm. 4. Current RCS temp erature is 565 °F. 5. Mixed Bed A contains fresh, unborated resin.
- 6. Maximum letdown flow will be used duri ng this evolution. 7. You are an extra operator.
INITIATING CUES:
The Unit SRO has directed you to perform 1-SOI-62.04, CVCS Purification System, Appendix B RCS Deboration Calculation, to determine the time that CVCS Mixed Bed Demineralizer 'A' must be in service in order to reduce RCS boron concentration to 35 ppm.
Enter the results of your calculation here:
TIME =________
__________________
______.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 5 of 10 START TIME: _______
STEP 1: [1] INDICATE Mixed Bed for which this calculation is being performed (CHECK ONLY ONE.)
Mixed Bed A __________
OR Mixed Bed B __________
STANDARD: From INITIAL CONDITIONS, the applicant checks Mixed Bed A.
COMMENTS:
___ SAT
___ UNSAT
NOTE This calculation is based on the Mixed B ed being a fresh unborated bed, all letdown flow being directed through the mixed bed bei ng placed in servic e, and the following:
STEP 2: [2] RECORD current RCS Temperature:
STANDARD:
From INITIAL CONDITIONS, applicant records 565 °F as the current RCS temperature.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 6 of 10 STEP 3: [3] RECORD RCS Volume (V) based on current RCS Temp using TI-59 (first page of App D through App N, as appropriate.)
STANDARD:
Applicant locates 1-TI-59, and selects Appendix K, and records 86212.4 as the RCS volume.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT
STEP 4: [4] PERFORM the following calculation to estimate time in service:
STANDARD:
Applicant enters letdown flow of 120 gpm, since the INITIAL CONDITIONS requires letdown flow to be at maximum, and RCS volume of 86212.4 gallons. Applicant calculates time of 96 minutes (Acceptable Range 92 to 100 minutes.)
Applicant documents time on Handout Sheet.
COMMENTS:
END OF TASK CRITICAL STEP ___ SAT
___ UNSAT
STOP TIME ________
2 Key DO NOT HAND TO APPLICANT
WBN Unit 1 CVCS Purification System 1-SOI-62.04 Rev. 0001 Page 93 of 99 Appendix B (Page 1 of 1)
RCS Deboration Calculation
[1] INDICATE Mixed Bed for which this Calculation is being performed (CHECK ONLY ONE.)
Mixed Bed A ________
OR Mixed Bed B ________
NOTE This calculation is based on the Mixed Bed being a fresh unborated bed, all letdown flow being directed through the mixed bed being placed in service, and the following:
Q T Cf = Co e
-V Where: Cf = Final Boron Concentration Co = Initial Boron Concentration Q = Mixed Bed Flow Rate (Letdown Flow in gpm) V = RCS Volume at operating temperature (gals)
T = Time (minutes)
[2] RECORD current RCS Temperature: ________RCS Temp
[3] RECORD RCS Volume (V) based on current RCS Temp using TI-59 (first page of App D thr ough App N, as appropriate.) ________RCS Volume
[4] PERFORM the following calculation to estimate time in service: Time = -ln (C f/C o) V =-ln (________ppm/________ppm) ________gals Q ____________gpm Time = ______________ minutes [5] RECORD Mixed Bed Run times for which this Calculation is being performed (Times can be obtained from Attachment 1 for the associated demin). 1 2 3 4 5 6 7 8 Run time Total time Initials
WBN Unit 1 Boron Tables 1-TI-59 Rev. 0000 Page 80 of 104 Appendix K (Page 1 of 8)
°F 2
Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 2 INITIAL CONDITIONS:
- 1. Unit 2 is performing pre-operational testing. 2. Unit 1 is in Mode 1 coasting down prior to refueling. 3. Current RCS C B is 40 ppm. 4. Current RCS temp erature is 565 °F. 5. Mixed Bed A contains fresh, unborated resin.
- 6. Maximum letdown flow will be used duri ng this evolution. 7. You are an extra operator.
INITIATING CUES:
The Unit SRO has directed you to perform 1-SOI-62.04, CVCS Purification System, Appendix B RCS Deboration Calculation, to determine the time that CVCS Mixed Bed Demineralizer 'A' must be in service in order to reduce RCS boron concentration to 35 ppm.
Enter the results of your calculation here:
TIME =________
__________________
______.
WBN Unit 1 CVCS Purification System 1-SOI-62.04 Rev. 0001 Page 93 of 99 Appendix B (Page 1 of 1)
RCS Deboration Calculation
[1] INDICATE Mixed Bed for which this Calculation is being performed (CHECK ONLY ONE.)
Mixed Bed A ________
OR Mixed Bed B ________
NOTE This calculation is based on the Mixed Bed being a fresh unborated bed, all letdown flow being directed through the mixed bed being placed in service, and the following:
Q T Cf = Co e
-V Where: Cf = Final Boron Concentration Co = Initial Boron Concentration Q = Mixed Bed Flow Rate (Letdown Flow in gpm) V = RCS Volume at operating temperature (gals)
T = Time (minutes)
[2] RECORD current RCS Temperature: ________RCS Temp
[3] RECORD RCS Volume (V) based on current RCS Temp using TI-59 (first page of App D thr ough App N, as appropriate.) ________RCS Volume
[4] PERFORM the following calculation to estimate time in service: Time = -ln (C f/C o) V =-ln (________ppm/________ppm) ________gals Q ____________gpm Time = ______________ minutes [5] RECORD Mixed Bed Run times for which this Calculation is being performed (Times can be obtained from Attachment 1 for the associated demin). 1 2 3 4 5 6 7 8 Run time Total time Initials
2015 301NRCEXAMAdministrativeJPM3R
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM Page 2 of 17 Task: CALCULATE QPTR AND EVALUATE RESULTS TO DETERMINE IF ACCEPTANCE CRITERIA ARE MET.
Alternate Path:
n/a Facility JPM #:
Modified from 3-OT-JPMADA.2-1 Safety Function:
N/A Title: Equipment Control.
K/A 2.2.12 Knowledge of surveillance procedures.
Rating(s):
3.7/4.1 CFR: 41.10 / 45.13 Evaluation Method:
Simulator In-Plant Classroom X References
- 1-SI-0-21,Excore QPTR & Axial Flux Difference, Rev. 19; Nuclear Operating Book (NOB). A-2 Sheet 1 Rev. 129, Sheet 2 Rev. 128, Sheet 3 Rev. 129, Sheet 4 Rev 127.
Task Number:
RO-092-SI-2-001 Title: Perform a QPTR calculation.
Task Standard:
The applicant:
- 1. Calculates Quadrant Power Tilt Ratio using 1-SI-0-21, Excore QPTR & Axial Flux Difference, Attachment 1, QPTR Determination Using Detector Currents. 2. Evaluates results and concludes that the acceptance criterion for 1-SI-0-21, Shutdown Margin, Section 6.2, Conservative SDM Hand Calculation is
NOT met for N-42 Upper Detector.
Validation Time:
15 minutes Time Critical:
Yes No X ==============================================================================================
Applicant: ___________________________
_________________
Time Start: ________
NAME Docket No.
Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE ==============================================================================================
COMMENTS WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM Page 3 of 17 T ools/Equipment/Procedures Needed:
Laptop Computer. NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM Page 4 of 17 READ TO OPERATOR DIRECTION TO APPLICANT:
I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
IN ITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational testing.
- 2. Unit 1 is operating at 100% power.
- 3. AFD Monitor Alarm and QPTR alarms are out of service due to a card problem in the annunciator system. 4. 1-SI-0-21 Excore QPTR & Axial Flux Difference is required to be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> since both QPTR alarms are inoperable.
- 5. Plant computer is not available.
- 6. M&TE will NOT be utiliz ed for data measurements. 7. You are a support CRO.
INITIATING CUES:
NOTE: Perform calculations to a sufficient number of decimal places to allow for evaluation of acceptance criteria.
PART 1 Given the data that was just obtained from each power range channel upper and lower detector currents, the Unit Supervisor directs you to perform 1-SI-0
-21, Excore QPTR &
Axial Flux Difference, Att achment 1, QPTR Determinati on Using Detector Currents.
PART 2
Has ACCEPTANCE CRITERIA been MET? (Circle your answer)
YES NO
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 5 of 17 START TIME: _______ NOTE TO EVALUATOR: The following steps are from Attachment 1 of 1-SI-0-21.
NOTES 1) Determining detector curr ents by measuring the voltage across the detector's meter test points, using a DVM, is the most accurate method for measuring QPTR and for determining the validity of a QPTR alarm. 2) Using the detector current meter readings is another method to quickly check that QPTR is within limits. These meters are NOT as accurate as the DVM readings and may produce unacceptable results because: 1) the meters on the 'B' drawer may be scaled too high or (2) the meter may be unstable due to drift or no ise. When unacceptable re sults are obtained, DVM readings should be obtained; otherwise, Step 1.0[1] and 1.0[2] may be marked N/A if DVM NOT used. 3) Up to one inoperable excore channel can be marked N/A if THERMAL POWER is < 75% RTP. STEP 1: [1.] RECORD DVM information: A. TVA M&TE ID: ________________
B. Cal Due Date: ________________
STANDARD: Applicant refers to the INITIATING CUES and determines this step will not be used and per NOTE 3 marks Step 1.0[1] N/A.
COMMENTS:
___ SAT
___ UNSAT STEP 3: [2.] ENSURE require M&TE is within its current calibration.
STANDARD: Applicant refers to the INITIATING CUES and determines this step will not be used and per NOTE 3 marks Step 1.0[2] N/A.
COMMENTS:
___ SAT
___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 6 of 17 CAUTION An inadvertent reactor trip may be prevented by ensuring that no power range neutron high flux rate or power range high flux bist ables are in the tripped condition prior to taking EACH measurement in the NIS Power Range Drawer B.
NOTES 1) The following determination may be made by measuring the voltage across the 1000 ohm precision resistor in NIS power range drawer B. When using this method the Ohm's Law conversion from a millivolt m easurement to a microamp measurement only requires changing the unit designator (e.g., 280 millivol ts converts to 280 microamps). 2) Detector A is the TOP or UPPER Detector and Detector B is the BOTTOM or LOWER detector on the NIS drawer B STEP 3: [3] DETERMINE the microamps for each upper and lower excore detector on each NIS power range drawer B, AND RECORD below. STANDARD: Applicant obtains the detector cu rrent microamp readings from the handout given during task assignment and enters the appropriate data into Attachment 1 Step 3.
COMMENTS:
___ SAT
___ UNSAT NOTE: R t and R b (detector calibration data) changes periodically throughout the cycle. Current values are on NOB Sheet A-2, NIS Calibration Data.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 7 of 17 EVALUATOR: The NOB Sheets attached to this JPM are to be given to the applicant when the applicant refers to the NOB. Th e data sheets attached are the basis for the calculations in the JPM.
STEP 4: [4] OBTAIN and RECORD values of Rt and Rb (volts/ microamps).
STANDARD: Applicant obtains the detector curr ent values from NOB Sheets A-2 for the respective NIS Power Ran ge Detectors and records them in appropriate blocks on Attachment 1 Step 4. This step is critical since an incorrect entry may cause the resultant calculation to indicate that Acceptance Criteria are met, when in fact QPTR limit has been exceeded.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 8 of 17 STEP 5: [5] CALCULATE calibrated output voltages by multiplying the uncalibrated detector output cu rrents by Rt or Rb (as applicable). A. Vt = It x Rt B. Vb = Ib x Rb STANDARD: Applicant calculates the calibrated output voltages
[Step 3] by multiplying the respective detecto r's current reading by resistance values [Step 4] and records the results in appropriate blocks on Step 5.
Step is critical since the values calculated will be used to calculate the average detector voltages.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 9 of 17 STEP 6: [6] CALCULATE average calibrated output voltage for the upper and lower detectors.
STANDARD: Applicant calculates the average output voltages for the upper detector by adding the respective upper detector's calibrated output voltage readings
[from Step 5]
and dividing the result by the number of channels in service.
This process is repeated for the lower detector using the lower detector calibrated voltages. The results recorded in appropriate bl ocks on Attachment 1, Step 6.
Step is critical since the values calculated will be used to determine the QPTR for individual upper and lower detectors, and then compared to the Tech Spec limit to ensure compliance.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 10 of 17 STE P 7: [7] CALCULATE QPTR values by dividing each detector's (upper or lower) Calibration Output Voltage by the average (upper or lower) Calibrated Output Voltage.
A. Q PTR t = V t Avg V t B. QPTR b = V b x Avg V b STANDARD: Applicant calculates QPTR values by dividing the respective Calibrated Output Voltage
[Step 5] by the Average Calibrated Output Voltage for each NIS channel detector [Step 6]. The results recorded in appropriate blocks on Attachment 1.
Step is critical since the values calculated will be used to determine whether the individual QPTR for each detector is within the Tech Spec lim it to ensure compliance.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 11 of 17 STEP 8: [8] OBTAIN a review of calculations, results and Tech Spec Acceptance Criteria by task qualified individual.
STANDARD: Applicant requests a review of the calculation by a Task Qualified individual (STA, SRO)
COMMENTS:
___ SAT
___ UNSAT STEP 10: Informs the Unit Supervisor that Attachment 1 of 1-SI-0-21 has been completed and provides the results of the QPTR calculation.
STANDARD: Applicant informs the Unit Supervisor of the completion of Attachment 1 and Section 6.1 of 1-SI-0-21 and r eports that acc eptance criteria have not been satisfied. QPTR N-42 Upper Detector is
1.0 2783931
, exceeding the QPTR limit of 1.02.
Step is critical since the value for N42T does not meet Acceptance Criteria of 1.02 (LCO 3.2.4).
EXAMINER CUE: Acknowledge report as Unit Supervisor.
COMMENTS:
END OF TASK CRITICAL STEP ___ SAT
___ UNSAT TIME STOP: ________
3 R Key DO NOT HAND TO APPLICANT
3R Calculations performed using Excel:
Upper Lower I to p R to p V to p I bottom R bottom V bottom N41 373 0.03493 13.02889 370 0.03537 13.0869 N42 363 0.03688 13.38744 391 0.03343 13.07113 N43 369 0.03474 12.81906 399 0.0331 13.2069 N44 326 0.03946 12.86396 372 0.03442 12.80424 Average 13.0248375 Average 13.0422925 QPTR N41 1.000311136 1.003420219 N42 1.027839311 1.002211076 N42 0.984201146 1.012621056 N44 0.987648406 0.981747649
` 3R
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 18 of 25 Attachment 1 (Page 2 of 4)
QPTR Determination Using Detector Currents Data Package: Page ____
Date ________
1.0 QPTR DETERMINATION USING DETECTOR CURRENTS (continued)
CAUTION An inadvertent reactor trip may be prevented by ensuring that no power range channel's neutron high flux rate or power range high flux bistables are in the tripped condition prior to taking EACH measurement in the NIS Power Range Drawer B.
NOTES 1) The following determination may be made by measuring the voltage across the 1000 ohm precision resistor in NIS power range drawer B.
When using this method the Ohm's Law conversion from a millivolt m easurement to a microam p measurement only requires changing the unit designator (e.g., 280 millivolts converts to 280 microamps). 2) Detector A is the TOP or UPPER Detector and Detector B is the BOTTOM or LOWER detector on the NIS drawer B
[3] DETERMINE the microamps for each upper and lower excore detector on each NIS power range drawer B, AND RECORD below. UPPER DETECTOR LOWER DETECTOR NIS Channel I t Detector Current (microamps)
I b Detector Current (microamps) N-41A N-42A N-43A N-44A ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 19 of 25 Attachment 1 (Page 3 of 4)
QPTR Determination Using Detector Currents Data Package: Page ____
Date ________
1.0 QPTR DETERMINATION USING DETECTOR CURRENTS (continued)
NOTE R t and R b (detector calibration data) changes periodi cally throughout the cycle. Current values are on Unit 1 NOB Sheet A-2, NIS Calibration Data.
[4] OBTAIN and RECORD values of R t and R b(volts/ microamps).
UPPER DETECTOR LOWER DETECTOR NIS Channel R t (volts/ microamps) R b (volts/ microamps) N-41A N-42A N-43A N-44A ________
[5] CALCULATE calibrated output voltages by multiplying the uncalibrated detector output currents by R t or R b (as applicable).
A. V t = I t x R t B. V b = I b x R b UPPER DETECTOR LOWER DETECTOR NIS Channel V t Calib. Output Voltage V b Calib. Output Voltage N-41A N-42A N-43A N-44A ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 20 of 25 Attachment 1 (Page 4 of 4)
QPTR Determination Using Detector Currents Data Package: Page ____
Date ________
1.0 QPTR DETERMINATION USING DETECTOR CURRENTS (continued)
[6] CALCULATE average calibrated output voltage for the upper and lower detectors.
UPPER V t LOWER V b AVERAGE
________
[7] CALCULATE QPTR values by dividi ng each detector's (upper or lower) Calibration Output Voltage by the average (upper or
lower) Calibration Output Voltage.
A. QPTR t = V t ÷ Avg V t B. QPTR b = V b ÷ Avg V b UPPER DETECTOR LOWER DETECTOR NIS Channel QPTR t Value QPTR b Value N-41A N-42A N-43A N-44A ________
[8] OBTAIN a review of calculations, results and Tech Spec Acceptance Criteria by task qualified individual. ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 11 of 25 Data Package: Page ____
Date ________
5.0 ACCEPTANCE
CRITERIA NOTE When one Excore detector is inoperable and Thermal Power is < 75 % RTP, the three remaining detectors may be used to calculate the average. If one Excore detector is inoperable and Thermal Power is 75 % RTP, REFER TO 1-SI-0-22.
A. Calculated QPTR is 1.02. NOTE The AFD limits specified in Technical Specifications, Unit 1 Core Operating Limit Report (COLR) may be less restrictive than those resulting from compliance with other Surveillance Requirements that would be published in Unit 1 NOB Sheet A-1.
1 B. AFD is within Limits of Unit 1 NOB S heet A-1, Target Band vs. Power Level for OPERABLE excore channels, which will en sure requirements of the COLR are met per the following conditions 1 1. At least 2-out-of-3 channels with in Limits, when 3 AFD channels are OPERABLE.
OR 2. At least 3-out-of-4 channels with in Limits, when 4 AFD channels are OPERABLE.
3R Applicant compares results of calculation to the Tech Spec limit of <1.02, and determines that N-41B Top exceeds the ACCEPTANCE CRITE RIA of 1-SI-0-21, Excore QPTR & Axial Flux Difference. Applicant circles NO on the sheet.
3 R
Handout Package for Applicant
3 R IN ITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational testing.
- 2. Unit 1 is operating at 100% power.
- 3. AFD Monitor Alarm and QPTR alarms are out of service due to a card problem in the annunciator system. 4. 1-SI-0-21 Excore QPTR & Axial Flux Difference is required to be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> since both QPTR alarms are inoperable.
- 5. Plant computer is not available.
- 6. M&TE will NOT be utiliz ed for data measurements. 7. You are a support CRO.
INITIATING CUES:
NOTE: Perform calculations to a sufficient number of decimal places to allow for evaluation of acceptance criteria.
PART 1 Given the data that was just obtained from each power range channel upper and lower detector currents, the Unit Supervisor directs you to perform 1-SI-0
-21, Excore QPTR &
Axial Flux Difference, Att achment 1, QPTR Determinati on Using Detector Currents.
PART 2
Has ACCEPTANCE CRITERIA been MET? (Circle your answer)
YES NO
3 R Data obtained from each power range channel upper and lower detector currents UPPER DETECTOR LOWER DETECTOR NIS CHANNEL I t Detector Current (microamps)
I b Detector Current (microamps)
N-41A 373 370 N-42A 363 391 N-43A 369 399 N-44A 326 372 Watts Bar Nuclear Plant Unit 1 Surveillance Instruction 1-SI-0-21 Excore QPTR
& Axial Flux Difference Revision 0019 Quality Related Level of Use: Continuous Use Effective Date: 08-19-2013 Responsible Organization: RXE, Reactor Engineering Prepared By: Kevin S. Elam Approved By: Lukus S. Barnes
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 2 of 25 Revision Log Revision or Change Number Effective Date Affected Page Numbers Description of Revision/Change 13 07/18/2002 2, 5, 8, 10, 11, 16 & 18 NON-INTENT Revision. Clarified when to use hand calculation using Attachment 1. Clarified Detector A is the upper and Detector B is the lower detector. Clarified when three detectors are acceptable. 14 10/19/2004 2, 11, 19 NON-INTENT Revision. Revised for PER 67703. Added step to perform hand calculation
in Attachment 1 during NIS calibrations. Added steps to perform a technical review of
calculations performed in Attachment 1. 15 03/17/08 All This procedure has been converted from Word 95 to Word XP using Rev. 14 by the Conversion Team. NON-INTENT Revision to clarify the conditions which the QPTR and AFD Monitor
Alarms are operable during Power Range calibrations. 16 12/28/2009 2 & 21 NON-INTENT change to clarify the qualification and requirements of post-performance reviewer (PER 169445). Removed "rev" from Revision Log. 17 02/09/2010 2, 9, 13 NON-INTENT change to clarify use of the C1 coefficients and the fact that the AFD points are available below 50% RTP. 18 03/16/12 All NON-INTENT change to alter administrative actions. Add guidance to perform RCS Loop
Delta T and Tave trending IAW PER 492835.
Other administrative enhancements, such as Unit 1 or 2 nomenclature. 19 08/19/13 2, 22, 24 Minor Editor ial change to change the "2nd Party" verifications to "C oncurrent Verifications".
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 3 of 25 Table of Contents
1.0 INTRODUCTION
.......................................................................................................... 5 1.1 Pur pose ...................................................................................................................
..... 5 1.2 Scope
............................................................................................................................ 5 1.2.1 Activities to be Performed ............................................................................... 5 1.2.2 Surveillance Requirement s Fulfilled and Unit Modes ...................................... 5 1.3 Frequency and Conditions ............................................................................................ 6
1.4 Background
................................................................................................................... 7
2.0 REFERENCES
............................................................................................................. 8
2.1 Performance
References .............................................................................................. 8 2.2 Developmental References
........................................................................................... 8 2.2.1 TVA Procedures
.............................................................................................. 8
2.2.2 Other
............................................................................................................... 8 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 9
4.0 PREREQUISI
TE ACTIONS ........................................................................................ 10
4.1 Preliminar
y Actions ..................................................................................................... 1 0 4.2 Special Tools, M&TE , Parts, and Supplies ................................................................. 10 4.3 Approvals and No tifications ........................................................................................ 10
5.0 ACCEPTANCE
CRITERIA ......................................................................................... 11
6.0 PERFORMANCE
........................................................................................................ 12 6.1 Excore QPTR Determination ...................................................................................... 12 6.2 Axial Flux Difference AFD Determination
.................................................................... 13 7.0 POST PERFORM ANCE ACTIVITY ............................................................................ 15 8.0 RECO RDS ..................................................................................................................
16 8.1 QA Re cords ................................................................................................................ 16 8.2 Non-QA Records ........................................................................................................ 16 Attachment 1: QPTR Determination Using Detect or Currents ...................................... 17 Attachment 2: Maintenance of QPTR Constants On the ICS ......................................... 21 Attachment 3: Maintenance of AFD And Target Band Constants On The ICS .............................................................................................................. 23 WBN Unit 1 Excore QPTR
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 4 of 25 Table of Contents (continued) Source Notes
............................................................................................. 25
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 5 of 25
1.0 INTRODUCTION
1.1 Purpose
This Instruction provides detailed steps fo r determination of the Quadrant Power Tilt Ratio (QPTR) and Axial Flux Difference (AFD).
2 1.2 Scope 1.2.1 Activities to be Performed A. Determination that QP TR is within limits. B. Determination that AFD is within limits.
C. Maintenance of QPTR Constants on the plant Integrated Computer System (ICS). D. Maintenance of AFD and Target Band Constants on the ICS. 1.2.2 Surveillance Requirements Fulfilled and Unit Modes Performance of this instruction satisfies the following Surveillance Requirements (SRs): SURVEILLANCE REQUIREMENT APPLICABLE MODES PERFORMANCE MODES SR 3.2.4.1 1 (1) 1 SR p 3.2.3.1 (3) 1 (2) 1 LCO 3.2.4
Action A.2 1 (1) 1 (1) Above 50% RATED THERMAL POWER (RTP). (2) Greater than or equal to 50% RTP.
(3) This instruction is used for the 7 day frequency only. 1-SI-92-5 is used for the hourly frequency.
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 6 of 25
1.3 Frequency
and Conditions NOTE The ICS serves as the AFD Monitor Alarm and alternate to the QPTR alarm. The alarms are considered operable provided the computer is NOT failed and the calculated values are NOT flagged as NCAL.
A. Sections 6.1 and 6.2 are to be perfo rmed every 7 days if the QPTR & AFD alarms are OPERABLE and THERMAL POWER is 50% RTP. B. Section 6.1 is to be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if both of the QPTR alarms are INOPERABLE and THERMAL POWER is greater than 50% RTP. C. Section 6.1 is to be performed following each NIS calibration when new calibration data is being entered to reset the clock associated with the inoperable QPTR alarm. D. Section 6.1 and Attachment 1 may be performed after alarm indication of a Quadrant Power Tilt to verify validit y and to more accurately determine the extent of the Quadrant Power Tilt. E. QPTR and AFD determinations are required to be current before power escalation above 50% RTP. F. Performance of Section 6.1 is NOT appropriate with one excore channel inoperable and THERMAL POWER 75% RTP. Under these conditions, SR 3.2.4.2 applies and 1-SI-0-22 will need to be performed. G. Performance of Section 6.2 is NOT appropriate when the AFD monitor is INOPERABLE (e.g. the ICS or other software problems). Under this condition, 1-SI-92-5 must be performed. H. ICS constants are required to be maintained current. Constants should be verified prior to the initial performance of this instruction after refueling and can be verified in any mode and at any time. I. This SI or portions of this instru ction may be performed at times other than those specified at the discretion of the Reactor Engineering Manager or SM/Unit SRO.
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 7 of 25
1.4 Background
QPTR is the ratio of the maximum upper ex core detector calibrated output to the average of the upper excore detector calibra ted outputs or the ra tio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. If one excore detector is inoperable and THERMAL POWER is < 75% RTP, the remaining three detectors shall be used for computing the average.
The primary QPTR alarms are 1-XA-55-4B-83B, POWER RANGE UPR DETECTOR FLUX DEVN [1-M-4] and 1-XA-55-4B-83C, POWER RANGE LWR DETECTOR FLUX DEVN [1-M-4]. The secondary or alternate QPTR alarm is from the ICS and triggers the RONAN annunciation on [1-M
-4] 1-XA-55-4B-83D, PLANT COMPUTER GENERATED ALARM (SEE ICS). During normal surveillance of QPTR, the ICS calculation of QPTR is the preferred method to meet the surveillance. The most accurate method of calculating QPTR is by measuring the excore detector voltage ac ross the detector's current meter test points in NIS power range drawer B. This is the preferred method for determining if the QPTR alarm indication is valid and to determine the extent of the Quadrant Power Tilt.
The ICS serves as the AFD Monitor Ala rm and is considered operable provided that the computer is NOT failed and the calculated values are NOT flagged by NCAL. If the computer AFD data points differ significa ntly from MCR values, contact the plant computer Software Engineer for evaluation. Axial Flux Difference is the difference in the normalized flux si gnals between the top and bottom halves of a two section excore neutron detector. The DELTA FLUX program on the ICS monitors the AFD of each of the operable excore channels once each minute and provides an alarm if the AFD for two or more operable excore channels are outside specified limits and triggers the RONAN annunciation on [1-M-4] 1-XA-55-4B-83D, PLANT COMPUTER GENERATED ALARM (SEE ICS). If the ICS is inoperable, the indications on 1-M-4 are acceptable by themselves to monitor AFD. REFER TO instruction 1-SI-92-5 when the AFD alarm function is inoperable.
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 8 of 25
2.0 REFERENCES
2.1 Performance
References A. Unit 1 Nuclear Operating Book (NOB), Sheet A-1, Target Band vs. Power Level B. Unit 1 Nuclear Operating Book (NOB), Sheet A-2, NIS Calibration Data C. 1-SI-0-22, INCORE QPTR D. WBN Integrated Computer S ystem, System User's Guide E. TI-68.011, Acquisi tion of T', T, T o , And RCS Streaming Factors for Periodic Update 2.2 Developmental References 2.2.1 TVA Procedures A. ARI-81-87, NIS & ROD CONTROLS B. 0-SI-0-3, Weekly Log C. 1-SI-92-2, NIS Mont hly Recalibration Data D. 1-SI-92-5, Hourly Axia l Flux Difference Inspection E. NPG-SPP-10.4, Reacti vity Management Program
2.2.2 Other
A. Unit 1 Technical Specifications, Section 3.2.3 B. Unit 1 Technical Specifications, Section 3.2.4 C. Westinghouse Letter 97TV-G-0066, WESTINGHOUSE POSITION ON CORE TILT, August 27, 1997 D. TVA Letter T41920727938, T/S Al arms For QPTR, July 27, 1992 E. Unit 1 CORE OPERATING LIMITS REPORT (COLR) [current cycle]
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 9 of 25
3.0 PRECAUTIONS
AND LIMITATIONS A. The meter test points in NIS Power Range drawer B are NOT isolated signals and improper measurement of the detector voltage wh ile in the NIS drawer could cause a channel trip. B. An inadvertent reactor trip may be prevented by ensuring that no power range neutron high flux rate or power range high flux channels are in the tripped condition prior to taking a detector vo ltage measurement in each power range drawer B. C. AFD should be maintained within the limits specified in the Unit 1 Nuclear Operating Book (NOB) which will ensur e requirements of the Unit 1 CORE OPERATING LIMITS REPO RT (COLR) are met. D. The ICS AFD data points should NOT differ significantly from MCR values when both the ICS and Power Range channels are calibrated. E. When performing this instruction fo llowing an NIS calibration (on all 4 channels), this surveillance instruction must be performed between calibrations.
If Reactor Engineering used 1-SI-92-3, Incore-Excore Cross Calibration Data, to calibrate the ICS calculations for AFD and QPTR via non 1.00000 values for the power range computer point C1 coefficients, then the ICS QPTR calculation is OPERABLE (even though the 1-XA-55-4B-83B and 1-XA-55-4B-83C alarms are not yet calibrated).
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 10 of 25 Data Package: Page ____ Date ________
4.0 PREREQUISITE
ACTIONS 4.1 Preliminary Actions
[1] RECORD the start date and time on Surveillance Task Sheet. ________
[2] IF the Integrated Computer Syst em (ICS) constants associated with QPTR require updating, THEN PERFORM Attachment 2. ________
[3] IF the ICS constants associat ed with AFD or Target Band require updating, THEN PERFORM Attachment 3. ________ 4.2 Special Tools, M&TE, Parts, and Supplies
[1] IF QPTR is to be determined by measurement across meter test points, THEN ENSURE the following M&TE is available: DESCRIPTION MINIMUM RANGE REQUIRED ACCURACY Keithley Model 197 or equivalent 0.1 to 0.5 Vdc
+/- 0.1% ________ 4.3 Approvals and Notifications
[1] NOTIFY SM/Unit SRO of intent to perform this Instruction ________
[2] IF QPTR is to be determined by measurement across meter test points, THEN NOTIFY Instrument Maintenance t hat support is required for Instruction performance. ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 11 of 25 Data Package: Page ____ Date ________
5.0 ACCEPTANCE
CRITERIA NOTE When one Excore detector is inoperable and Thermal Power is < 75 % RTP, the three remaining detectors may be used to calculate the average. If one Excore detector is inoperable and Thermal Power is 75 % RTP, REFER TO 1-SI-0-22.
A. Calculated QPTR is 1.02. NOTE The AFD limits specified in Technical Specifications, Unit 1 Core Operating Limit Report (COLR) may be less restrictive than those resulting from compliance with other Surveillance Requirements that would be published in Unit 1 NOB Sheet A-1.
1 B. AFD is within Limits of Unit 1 NOB S heet A-1, Target Band vs. Power Level for OPERABLE excore channels, which will en sure requirements of the COLR are met per the following conditions 1 1. At least 2-out-of-3 channels with in Limits, when 3 AFD channels are OPERABLE.
OR 2. At least 3-out-of-4 channels with in Limits, when 4 AFD channels are OPERABLE.
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 12 of 25 Data Package: Page ____ Date ________
6.0 PERFORMANCE
6.1 Excore QPTR Determination NOTES 1) Obtaining QPTR calculated values from th e ICS is the preferred method to check that the QPTR is within Technical Specification limits. QPTR values are obtained from ICS calculated computer points for upper and lo wer radial flux tilt. These points are available on the "Tilting Fact ors" display. The report ma y be printed with Turn On code TFREP. 2) Up to one inoperable excore channel c an be marked N/A if THERMAL POWER is
< 75% RTP.
[1] IF performing this instruction during an NIS calibration (when all four channels are NOT complete), THEN REFER to Precautions and Limitations 3.0E. ________
[2] IF the ICS is available, THEN PRINT the Tilting Factors Report AND/OR PERFORM the QPTR calculations using Attachment 1. ________
[3] REVIEW the Upper (A) and Lower (B) QPTR values. ________
[4] CHECK () Acceptance Criteria.
ACCEPTANCE CRITERIA
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 13 of 25 Data Package: Page ____ Date ________
6.2 Axial
Flux Difference AFD Determination NOTES 1) Up to one inoperable excore channel can be marked N/A.
- 2) IF the C1 Coefficients are not set to 1.00000, THEN there may a difference between the I Meter and Computer Point AFD values.
[1] RECORD the AFD from [1-M-4] for each operable excore channel. NIS Channel INSTRUMENT NUMBER QUADRANT # Flux % (i.e. AFD) N-41A 1-NI-41C Quadrant 4 % N-42A 1-NI-42C Quadrant 2 % N-43A 1-NI-43C Quadrant 1 % N-44A 1-NI-44C Quadrant 3 % ________
NOTES 1) AFD values are available on the "Primary Mimics, Doghouse Display" and on the "Tilting Factors" display. The report ma y be printed with turn on code TFREP, if not previously printed. 2) Below 50% RTP, AFD limits do not apply, but the ICS AFD Limit points will be linear extensions to the line segments from 50% to 100% RTP; therefor e, Steps 6.2[4] and 6.2[5] may be N/A. 3) AFD Limits on Unit 1 NOB Sheet A-1 and the ICS may be more co nservative than the Unit 1 COLR values.
[2] REVIEW the Dynamic AFD Display and the Unit 1 NOB Sheet A-1, AND RECORD the more conservative AFD Low and High Limit values. AFD Low Limit (Negative)
%AFD High Limit (Positive)
% ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 14 of 25 Data Package: Page ____ Date ________
6.2 Axial
Flux Difference AF D Determination (continued)
[3] VERIFY () Acceptance Criteria.
Acceptance Criteria: AFD is within Limi ts of Unit 1 NOB Sheet A-1, Target Band vs.
Power Level for OPERABLE excore channels, which will ensur e requirements of the Unit 1 COLR are met per the following conditions:
1
- At least 2-out-of-3 channels within Limits, when 3 AFD channels are OPERABLE.
- At least 3-out-of-4 channels within Limits, when 4 AFD channels are OPERABLE. YES NO ________
[4] VERIFY the AFD limits on Unit 1 NOB Sheet A-1 are representative of those displa yed on the Dynamic AFD Display on the ICS. ________
[5] IF Steps 6.2[3] or 6.2[4] criteria was NOT met, THEN NOTIFY SM/SRO and Reactor Engineering for evaluation of the AFD Monitor/Alarm operability, AND PERFORM 1-SI-92-5, Hourly Axial Flux Difference Inspection, as required. ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 15 of 25 Data Package: Page ____ Date ________
7.0 POST PERFORMANCE ACTIVITY NOTE To be considered a complete weekly performanc e, the Tech Spec Acceptance Criteria must be satisfied by performance of both Sections 6.1 and 6.2.
[1] RECORD completion date and time on Surveillance Task Sheet. ________
[2] NOTIFY SM/Unit SRO that this Instruction is complete. ________
NOTES 1) The independent review performed on t he STS sheet may be performed by either Operations or Reac tor Engineering. 2) The remaining steps in this section may be completed after SRO acceptance criteria review, but before the WO is closed.
[3] IF the performance of this instruct ion is for the weekly routine performance,
THEN CONTINUE with Step 7.0[4].
OTHERWISE , MARK the remainder of this instruction N/A. ________
[4] EVALUATE the need to update the Reactivity Briefing Binder. ________
[5] IF the Reactivity Briefing Binder needs updating, THEN INITIATE an update. ________
[6] TREND the indications for the RCS Loop T and Tavg.
3 ________
[7] IF the trends indicate that an RCS Loop T is approximately 0.7% deviant from THERMAL POWER, THEN PERFORM the following:
A. NOTIFY the applicable Engineer that TI-68.011 needs to be performed to update the applicable Delta T o.3 ________
[8] IF the trends indicate that an RCS Loop Tavg is approximately 0.7°F deviant from Tavg o at nominal full power, THEN PERFORM the following:
A. NOTIFY the applicable Engineer that TI-68.011 needs to be performed to update the applicable Tavg o.3 ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 16 of 25
8.0 RECORDS
8.1 QA Records The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:
Completed parts of Sections 4.0, 5.0, 6.0, and 7.0 Completed Attachments Surveillance Task Sheet
Other sheets added during the performance 8.2 Non-QA Records No non-QA records are created by this Instruction.
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 17 of 25 Attachment 1 (Page 1 of 4)
QPTR Determination Using Detector Currents Data Package: Page ____ Date ________ 1.0 QPTR DETERMINATION USING DETECTOR CURRENTS NOTES 1) Determining detector currents by measur ing the voltage across the detector's meter test points, using a DVM, is the most accurate method for measuring QPTR and for determining the validity of a QPTR alarm. 2) Using the detector current meter reading s is another method to quickly check that QPTR is within limits. These meters are NOT as accurate as the DVM readings and may produce unacceptable results because: 1) the meters on the 'B' drawer may be scaled too high or (2) the meter may be unstable due to drift or noise. When unacceptable results are obtained, DVM re adings should be obt ained; otherwise, Step 1.0[1] and 1.
0[2] may be marked N/A if DVM NOT used. 3) Up to one inoperable excore channel c an be marked N/A if THERMAL POWER is
< 75% RTP.
[1] RECORD DVM information:
TVA M&TE ID: _____________________
Cal Due Date: _____/
_____/___________ ________
[2] ENSURE required M&TE is within its current calibration. ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 18 of 25 Attachment 1 (Page 2 of 4)
QPTR Determination Using Detector Currents Data Package: Page ____ Date ________
1.0 QPTR DETERMINATION USING DETECTOR CURRENTS (continued)
CAUTION An inadvertent reactor trip may be prevented by ensuring that no power range channel's neutron high flux rate or power range high flux bistables are in the tripped condition prior to taking EACH measurement in the NIS Power Range Drawer B.
NOTES 1) The following determination may be made by measuring the voltage across the 1000 ohm precision resistor in NIS power range drawer B.
When using this method the Ohm's Law conversion from a millivolt m easurement to a microam p measurement only requires changing the unit designator (e.g., 280 millivolts converts to 280 microamps). 2) Detector A is the TOP or UPPER Detector and Detector B is the BOTTOM or LOWER detector on the NIS drawer B
[3] DETERMINE the microamps for each upper and lower excore detector on each NIS power range drawer B, AND RECORD below. UPPER DETECTOR LOWER DETECTOR NIS Channel I t Detector Current (microamps)
I b Detector Current (microamps) N-41A N-42A N-43A N-44A ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 19 of 25 Attachment 1 (Page 3 of 4)
QPTR Determination Using Detector Currents Data Package: Page ____ Date ________
1.0 QPTR DETERMINATION USING DETECTOR CURRENTS (continued)
NOTE R t and R b (detector calibration data) changes periodi cally throughout the cycle. Current values are on Unit 1 NOB Sheet A-2, NIS Calibration Data.
[4] OBTAIN and RECORD values of R t and R b(volts/ microamps). UPPER DETECTOR LOWER DETECTOR NIS Channel R t (volts/ microamps) R b (volts/ microamps) N-41A N-42A N-43A N-44A ________
[5] CALCULATE calibrated output voltages by multiplying the uncalibrated detector output currents by R t or R b (as applicable). A. V t = I t x R t B. V b = I b x R b UPPER DETECTOR LOWER DETECTOR NIS Channel V t Calib. Output Voltage V b Calib. Output Voltage N-41A N-42A N-43A N-44A ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 20 of 25 Attachment 1 (Page 4 of 4)
QPTR Determination Using Detector Currents Data Package: Page ____ Date ________
1.0 QPTR DETERMINATION USING DETECTOR CURRENTS (continued)
[6] CALCULATE average calibrated output voltage for the upper and lower detectors. UPPER V t LOWER V b AVERAGE ________
[7] CALCULATE QPTR values by dividi ng each detector's (upper or lower) Calibration Output Voltage by the average (upper or
lower) Calibration Output Voltage. A. QPTR t = V t ÷ Avg V t B. QPTR b = V b ÷ Avg V b UPPER DETECTOR LOWER DETECTOR NIS Channel QPTR t Value QPTR b Value N-41A N-42A N-43A N-44A ________
[8] OBTAIN a review of calculations, results and Tech Spec Acceptance Criteria by task qualified individual. ________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 21 of 25 Attachment 2 (Page 1 of 2)
Maintenance of QPTR Constants On the ICS Data Package: Page ____ Date ________ 1.0 CONSTANTS APPLICABLE TO THE ICS TILT REVIEW PROGRAM Pt Mnemonic Point Description Point ID Units Source Q1UTILTF UPPER Q1 NIS TILT NORM FACTOR (CH 43) K0600 NONE XR-RCON Q2UTILTF UPPER Q2 NIS TILT NORM FACTOR (CH 42) K0601 NONE XR-RCON Q3UTILTF UPPER Q3 NIS TILT NORM FACTOR (CH 44) K0602 NONE XR-RCON Q4UTILTF UPPER Q4 NIS TILT NORM FACTOR (CH 41) K0603 NONE XR-RCON Q1LTILTF LOWER Q1 NIS TILT NORM FACTOR (CH 43) K0604 NONE XR-RCON Q2LTILTF LOWER Q2 NIS TILT NORM FACTOR (CH 42) K0605 NONE XR-RCON Q3LTILTF LOWER Q3 NIS TILT NORM FACTOR (CH 44) K0606 NONE XR-RCON Q4LTILTF LOWER Q4 NIS TILT NORM FACTOR (CH 41) K0607 NONE XR-RCON UPQPTLIM UPPER NIS TILT ALARM LIMIT K0608 NONE XR-RCON LOQPTLIM LOWER NIS TILT ALARM LIMIT K0609 NONE XR-RCON PRQPTLIM POWER RANGE NIS TILT ALARM LIMIT K0610 NONE XR-RCON WBN Unit 1 Excore QPTR
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 22 of 25 Attachment 2 (Page 2 of 2)
Maintenance of QPTR Constants On the ICS Data Package: Page ____ Date ________
1.0 CONSTANTS
APPLICABLE TO THE ICS TILT REVIEW PROGRAM (continued)
[1] OBTAIN the latest source doc ument for the applicable constant to be updated. This may be the Unit 1 Core Operating Limit Report or a performance package from a Surveillance Instruction or other applicable approved document. ________
[2] RECORD the Point ID and current as found value of the applicable constant(s) to be updated on the STS sheet. ________
[3] RECORD the Point ID and new value of the applicable constant(s) to be updat ed on the STS sheet OR ATTACH a copy of the applic able source document (applicable pages) to the data package. ________
[4] UPDATE the ICS as applicable. ________
[5] VERIFY the constants that have been updated on the ICS match the proposed new constant s provided in Step 1.0[3] above. ________
________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 23 of 25 Attachment 3 (Page 1 of 2)
Maintenance of AFD And Target Band Constants On The ICS Data Package: Page ____ Date ________ 1.0 CONSTANTS APPLICABLE TO THE ICS OF AFD AND TARGET BAND PROGRAM.
NOTE Most of these constants may be updated using the ICS UPDATE CONSTANTS function on the AXIAL FLUX DIFFERENCE MAIN MENU.
Pt Mnemonic Point Description Point ID Units Source MAXCTP REAC TOTAL THERMAL AT 100 PC Q K0029 MW KAFD1 INC/EXC OFFSET RATIO QUAD 1 (CH 3) K0551 %/Volt XR-RCON KAFD2 INC/EXC OFFSET RATIO QUAD 2 (CH 2) K0552 %/Volt XR-RCON KAFD3 INC/EXC OFFSET RATIO QUAD 3 (CH 4) K0553 %/Volt XR-RCON KAFD4 INC/EXC OFFSET RATIO QUAD 4 (CH 1) K0554 %/Volt XR-RCON LOOFFSET RAOC NEG AFD WARNING BAND TO LIMIT K2022 % XR-RCON HIOFFSET RAOC POS AFD WARNING BAND TO LIMIT K2023 PCT XR-RCON AFLLX RAOC NEGATIVE AFD LIMIT AT 50% POWER K2024X PCT XR-RCON AFLLY RAOC NEGATIVE AFD LO PWR SETPT (50%) K2024Y PCT XR-RCON AFLUX RAOC NEGATIVE AFD LIMIT AT FULL POWER K2025X PCT XR-RCON AFLUY RAOC NEGATIVE AFD BRKPT POWER (100%) K2025Y PCT XR-RCON AFHUX RAOC POSITIVE AFD LIMIT AT FULL POWER K2026X PCT XR-RCON AFHUY RAOC POSITIVE AFD BRKPT POWER (100%) K2026Y PCT XR-RCON AFHLX RAOC POSITIVE AFD LIMIT AT 50% PWR K2027X PCT XR-RCON AFHLY RAOC POSITIVE AFD LOW PWR STPT (50%) K2027Y PCT XR-RCON AFDTARG AFD TARGET VALUE AT FULL POWER K2028 PCT XR-RCON OFFSTL AFD NEGATIVE BANDWITH FROM TARGET K2029 PCT XR-RCON OFFSTH AFD POSITIVE BANDWITH FROM TARGET K2030 PCT XR-RCON TIME OUT OF BAND LIMIT - AFD K2031 MIN WBN Unit 1 Excore QPTR
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 24 of 25 Attachment 3 (Page 2 of 2)
Maintenance of AFD And Target Band Constants On The ICS Data Package: Page ____ Date ________
1.0 CONSTANTS
APPLICABLE TO THE ICS OF AFD AND TARGET BAND PROGRAM. (continued)
[1] OBTAIN the latest source doc ument for the applicable constant to be updated. This may be the Unit 1 Core Operating Limit Report or a performance package from a Surveillance Instruction or other applicable approved document. ________
[2] RECORD the Point ID and current as found value of the applicable constant(s) to be updated on the STS sheet. ________
[3] RECORD the Point ID and new value of the applicable constant(s) to be updat ed on the STS sheet OR ATTACH a copy of the applic able source document (applicable pages) to the data package. ________
[4] UPDATE the ICS as applicable. ________
[5] VERIFY the constants that had been updated on the ICS match the proposed new constant s provided in Step 1.0[3] above. ________
________
& Axial Flux Difference 1-SI-0-21 Rev. 0019 Page 25 of 25 Source Notes (Page 1 of 1)
Requirements Statement Source Document Implementing Statement Referenced more conservative limits of Unit 1 NOB Sheet A-1 instead of the
Unit 1 COLR Limits. WBPER960655 1 Corrective action to prevent missing surveillance requirements. WBPER970101 2 Trend RCS Delta T and T' values for potential update and notify the applicable Engineer, as necessary. WBN PER 492835 3
2015 301NRCEXAMAdministrativeJPM3S WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S 2015-301 NRC EXAM Page 2 of 10 EVALUATION SHEET Task: EVALUATE CONDITIONS AND APPLY TECHNICAL SPECIFICATIONS Alternate Path:
n/a Facility JPM #:
Modified.
Safety Function:
N/A Title: Equipment Control.
K/A 2.2.37 Ability to determine operability and/or availability of safety related equipment.
Rating(s):
3.6/4.6 CFR: 41.7 / 43.5 / 45.12 Evaluation Method:
Simulator In-Plant Classroom X References
- WBN Technical Specifications, Amendment 98. 1-PI-OPS-1-PE, Protected Equipment, Rev 15.
Task Number:
RO-119-SSP-12 -007 Title: Monitor plant conditions to ensure compliance with Technical Specification Limited Conditions for Operation (LCO)
requirements.
Task Standard:
PART 1: The applicant determines that entry into LCO 3.7.5, Auxiliary Feedwater (AFW) System, Condition B is required, and TD AFW pump must be returned to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. PART 2 The applicant determines equipment which needs to be protected using 1-PI-OPS-1-PE, Protected Equipment, Rev 15 Page 32 of 68 Table TD AFWP.
Validation Time:
15 minutes Time Critical:
Yes No X ========================================================================================= Applicant: ___________________________ _________________
Time Start: ________
NAME Docket No.
Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________ NAME SIGNATURE DATE ==========================================================================================
COMMENTS WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S 2015-301 NRC EXAM Page 3 of 10 Tools/Equipment/Procedures Needed:
Laptop Computer. NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the appli cant via a laptop computer loaded with the NRC REFERENCE DISK.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S 2015-301 NRC EXAM Page 4 of 10 DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is in MODE 1, 100% power.
- 2. A steam leak downstream of 1-FCV-1-17, MAIN STEA M AUX FWP HDR SUPPLY ISOL has developed and was subsequently isolated.
INITIATING CUES:
PART 1 Based on the INITIAL CONDITIONS given, determine what, if any Te chnical Specification LCO(s) must be entered and required actions.
LCO (s):___________
__________________
_________
ACTION: ________________
______________________
PART 2 Determine and then list what, if any equipment must be protected based on the conditions given.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 5 of 10 START TIME: _______
STEP 1: Applicant locates and evaluates information contained in INITIAL CONDITIONS and determines that LCO 3.7.5, Condition A is NOT applicable.
STANDARD: Applicant determines that 1-FC V-1-15, SG 1 ST EAM SUPPLY TO T-D AFW PMP and 1-FCV-1-16, SG 4 STEAM SUPPLY TO T-D AFW PMP remain OPERABLE.
COMMENTS:
___ SAT
___ UNSAT
STEP 2: Applicant evaluates information contained in INITIAL CONDITIONS and determines that LCO 3.7.5, Condition B IS applicable STANDARD: Applicant determines that the isolation of the leak downstream of 1-FCV-1-17, MAIN STEAM AUX FWP HDR SUPPLY ISOL renders the TD AFW pump INOPERABLE, requiring entry into Condition B.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 6 of 10 EXAMINER: The CRITICAL TASK associated with Step 3 may be satisfied by the applicant indicating the information is contained on 1-PI-OPS-1-PE, PROTECTED EQUIPMENT, Page 32 of 68, TDAFW PUMP.
STEP 3: Applicant locates 1-PI-O PS-1-PE, Protect ed Equipment, and locates table pertaining to TD AFW PUMP.
STANDARD: Applicant determines the followi ng equipment is required to be protected: 1-HS-3-118A, AFW PMP A-A on 1-M-4 1-HS-2-128A,AFW PMP B-B on 1-M-4 MDAFW PUMP 1A on AB Elev. 713; 6.9kV SD Bd 1A-A COMP 10 MD AFW PUMP 1B on AB Elev. 713; 6.9kV SD Bd 1B-B COMP 10
1-BKR-3-128 AFW PUMP 1B-B 1A EDG 1B EDG 480V Diesel Aux Bd 1A1-A 480V Diesel Aux Bd 1A2-A 480V Diesel Aux Bd 1B1-B 480V Diesel Aux Bd 1B2-B COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT
STOP TIME ________
3 S Key DO NOT HAND TO APPLICANT
3-S KEY PART 1 Based on the INITIAL CONDITIONS given, determine what, if any Technical Specification LCOs must be entered. LCO: 3.7.5, Auxiliary Fe edwater (AFW) System CONDITION: B. One AFW train inoperable in MODE 1, 2, or 3 for reasons other than Condition A, restore AFW train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 10 days from discovery of failure to meet LCO.
NOTE: The steam supplies addressed in CONDITION A are 1-FCV-1-15 and 1-FCV-1-16, which are the automatic valves from SG 1 and SG 4 respectively. The initial conditions state that the leak is downstream of 1-FCV-1-17, a steam isolation valve. Entry into CONDITION A is incorrect.
PART 2 Determine and then list what, if any equipment must be protected based on the conditions given. The applicant determines equipment needing to be protected using 1-PI-OPS-1-PE, Protected Equipment, Rev 15 Page 32 of 68, Table TD AFWP.
AFW System 3.7.5 Watts Bar-Unit 1 3.7-11 Amendment 55 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE. ----------------------------------------------NOTE--------------------------------------------------- Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4. --------------------------------------------------------------------------------------------------------- APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal. ACTIONS ---------------------------------------------------------------NOTE---------------------------------------------------------------- LCO 3.0.4.b is not applicable when entering MODE 1. ---------------------------------------------------------------------------------------------------------------------------------------- CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to turbine driven AFW pump inoperable. A.1 Restore steam supply to OPERABLE status. 7 days AND 10 days from discovery of failure to meet the LCO B. One AFW train inoperable in MODE 1, 2 or 3 for reasons other than Condition A. B.1 Restore AFW train to OPERABLE status. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 10 days from discovery of failure to meet the LCO (continued)
WBN Unit 1 Protected Equipment 1-PI-OPS-1-PE Rev. 0015 Page 32 of 68 Attachment 2 (Page 19 of 25)
Protected Equipment Log (Modes 1 through 4)
Degraded/ OOS Component TDAFW PUMP Protected Component Location Date Installed Date Removed Comments 1-HS-3-118A AFW PMP A-A 1-M-4 1-HS-3-128A AFW PMP B-B 1-M-4 MDAFW PUMP 1A AUX BLDG ELEV 713 MDAFW PUMP 1B AUX BLDG ELEV 713 1-BKR-3-118 AFW PUMP 1A-A 6.9kV SD Bd 1A-A COMP 10 1-BKR-3-128 AFW PUMP 1B-B 6.9kV SD Bd 1B-B COMP 10 1A EDG Per Attachment 2 1B EDG Per Attachment 2 480V Diesel Aux Bd 1A1-A DGB ELEV 760 480V Diesel Aux Bd 1A2-A DGB ELEV 760 480V Diesel Aux Bd 1B1-B DGB ELEV 760 480V Diesel Aux Bd 1B2-B DGB ELEV 760
3 S Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 3 S INITIAL CONDITIONS:
- 3. Unit 1 is in MODE 1, 100% power.
- 4. A steam leak downstream of 1-FCV-1-17, MAIN STEA M AUX FWP HDR SUPPLY ISOL has developed and was subsequently isolated.
INITIATING CUES:
PART 1 Based on the INITIAL CONDITIONS given, determine what, if any Te chnical Specification LCO(s) must be entered and required actions.
LCO (s):___________
___________________________
ACTION: ________________
______________________
PART 2 Determine and then list what, if any equipment must be protected based on the conditions given.
2015 301NRCEXAMAdministrativeJPM4 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 2015-301 NRC EXAM Page 2 of 12 EVALUATION SHEET Task: CALCULATE THE MAXIMUM PERMISSIBLE STAY TIME WITHIN EMERGENCY DOSE LIMITS Alternate Path:
n/a Facility JPM #:
New Safety Function:
N/A Title: Radiation Control K/A 2.3.4 Knowledge of limiting conditions for operations and safety limits.
Rating(s):
3.2/3.7 CFR: 41.12/43.4/45.10 Evaluation Method:
Simulator In-Plant Classroom X References
- EPIP-15, Emergency Exposure Guidelines, Rev. 16.
Task Number:
AUO-119-SSP-5.01-001 Title: Control personnel radiation exposure.
Task Standard:
The applicant: 1. Calculates the dose expected for Task #1 through Task #3. 2. Determines that Tasks #1 through #3 can be performed without exceeding equipment protection emergency dose limits. 3. Calculates the maximum allowable stay time for Task #4 to be 18 minutes.
Validation Time:
18 minutes Time Critical:
Yes No X ========================================================================================= Applicant: ___________________________ _________________
Time Start: ________
NAME Docket No.
Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________ NAME SIGNATURE DATE ==========================================================================================
COMMENTS WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 2015-301 NRC EXAM Page 3 of 12 Tools/Equipment/Procedures Needed:
Laptop Computer. NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the appli cant via a laptop computer loaded with the NRC REFERENCE DISK.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 2015-301 NRC EXAM Page 4 of 12 DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. A GENERAL EMERGENCY has b een declared on Unit 1.
- 2. 1A RHR Pump is air bound and must be vented per 1-AOI-14, Loss of RHR Shutdown Cooling.
- 3. The TSC has requested that 1B-B RHR Pump motor bearing oil levels be checked and filled as required afte r restoring 1A-A RHR Pump, suggests usi ng the same Repair Team.
- 4. The tasks are listed in the table below, and estimated times (including transit to and from location) and dose rates have been provided.
- 5. Each Task must be performed in the order listed.
- 6. The equipment protection emergency dose limit is 10 REM.
- 7. You have been selected to perform the task. (Continued on next page)
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 2015-301 NRC EXAM Page 5 of 12 INITIATING CUES:
The Site Emergency Director (SED) directs you to perform the following with the information provided: 1. Calculate the expected dose for tasks 1 through 3 and document the results in the TABLE. Task # Location/Task Description Time allowed/req'd (minutes) Dose Rate (R/hr) Expected Dose 1 Elevation 676' 1A-A RHR Pump Room /Close RHR pump discharge isolation valve 1-ISV-74-520 10 3 2 #4 Accumulator Room / Vent common suction piping 1-TV-74-543, 1-TV-74-504 20 18 3 Elevation 676' 1A-A RHR Pump Room /Vent 1A-A RHR Pump discharge piping and pump casing and open RHR pump discharge isolation valve 1-ISV-74-520 40 3 4 Elevation 676' 1B-B RHR Pump Room / Inspect 1B-B RHR pump motor bearing oil levels and fill as required. 5 2. Answer the following: Can you perform Tasks #1 through #3 without exceeding the equipment protection emergency dose limit? (Circle one)
YES / NO IF YES, then enter the permitted stay time for Task #4.
IF NO, then state the highest sequential task # that can be performed, if any.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 6 of 12 START TIME: _______
STEP 1: Applicant calculates the EXPECTED DOSE for Tasks #1 through #3.
STANDARD: Applicant determines the following:
EXPECTED DOSE for TASK # 1 (10 minutes/60 minutes/hour) x 3 R/hr =
0.5 R EXPECTED DOSE for TASK #2 (20 minutes/60 minutes/hr) x 18 R/hr =
6.0 R EXPECTED DOSE for TASK #3 (40 minutes/60 minutes/hr) x 3 R/hr =
2.0 R TOTAL EXPECTED DOSE for TASKS #1, #2 and #3 is 8.5 R.
COMMENTS:
CRITICAL STEP ___ SAT ___ UNSAT
STEP 2: Applicant answers the question "Can you perform Tasks #1 through #3 without exceeding th e equipment protection emergency dose limit?"
STANDARD: Applicant circles YES on the APPLICANT CUE SHEET.
COMMENTS:
CRITICAL STEP ___ SAT ___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 2015-301 NRC EXAM STEP/STANDARD SAT/UNSAT Page 7 of 12 STEP 3: Applicant determines stay ti me limit for Task #4 must be less than or equal to 18 minutes.
STANDARD: Applicant subtracts 8.5 R from th e limit of 10 R and determines the remaining dose to be 1.5 R. Applicant divides 1.5 R by 5 R/hr (the expected dose for Task #4) and determines the stay time to be 0.3 hrs. Applicant multiplies 0.3 hr x 60 minutes/hr and determines a maximum stay time of 18 minutes for Task
- 4. Applicant enters 18 minutes for permitted stay time for Task #4.
COMMENTS:
CRITICAL STEP ___ SAT
___ UNSAT
STOP TIME ________
3 S Key
DO NOT HAND TO APPLICANT
2 2 0 0 1 1 5 5--3 3 0 0 1 1 N N R R C C E E X X A A M M J J P P M M 4 4 K K E E Y Y 1. Calculate the expected dose for tasks 1 through 3 and document the results in the TABLE. Task # Location/Task Description Time allowed/req'd (minutes) Dose Rate (R/hr) Expected Dose 1 Elevation 676' 1A-A RHR Pump Room /Close RHR pump discharge isolation valve 1-ISV-74-520 10 3 0.5 2 #4 Accumulator Room / Vent common suction piping 1-TV-74-543, 1-TV-74-504 20 18 6 3 Elevation 676' 1A-A RHR Pump Room /Vent 1A-A RHR Pump discharge piping and pump casing and open RHR pump discharge isolation valve 1-ISV-74-520 40 3 2.5 4 Elevation 676' 1B-B RHR Pump Room / Inspect 1B-B RHR pump motor bearing oil levels and fill as required. 18 5 1.5 2. Answer the following: Can you perform Tasks #1 through #3 without exceeding the equipment protection emergency dose limit? (Circle one)
YES / NO IF YES, then enter the permitted stay time for Task
- 4.
18 MINUTES
. IF NO, then state the highest sequential task # that can be performed, if any.
N/A .
4
Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 4 INITIAL CONDITIONS:
- 1. A GENERAL EMERGENCY has b een declared on Unit 1.
- 2. 1A RHR Pump is air bound and must be vented per 1-AOI-14, Loss of RHR Shutdown Cooling. 3. The TSC has requested that 1B-B RHR Pump motor bearing oil levels be checked and filled as required afte r restoring 1A-A RHR Pump, suggests usi ng the same Repair Team.
- 4. The tasks are listed in the table below, and estimated times (including transit to and from location) and dose rates have been provided.
- 5. Each Task must be performed in the order listed.
- 6. The equipment protection emergency dose limit is 10 REM.
- 7. You have been selected to perform the task. (Continued on next page)
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 4 INITIATING CUES:
The Site Emergency Director (SED) directs you to perform the following with the information provided: 1. Calculate the expected dose for tasks 1 through 3 and document the results in the TABLE. Task # Location/Task Description Time allowed/req'd (minutes) Dose Rate (R/hr) Expected Dose 1 Elevation 676' 1A-A RHR Pump Room /Close RHR pump discharge isolation valve 1-ISV-74-520 10 3 2 #4 Accumulator Room / Vent common suction piping 1-TV-74-543, 1-TV-74-504 20 18 3 Elevation 676' 1A-A RHR Pump Room /Vent 1A-A RHR Pump discharge piping and pump casing and open RHR pump discharge isolation valve 1-ISV-74-520 40 3 4 Elevation 676' 1B-B RHR Pump Room / Inspect 1B-B RHR pump motor bearing oil levels and fill as required. 5 2. Answer the following: Can you perform Tasks #1 through #4 without exceeding the equipment protection emergency dose limit? (Circle one)
YES / NO IF YES, then enter the permitted stay time for Task #4.
IF NO, then state the highest sequential task # that can be performed, if any.
NRCEXAM2015 301AdministrativeJPM5
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2015-301 Page 2 of 10 EVALUATION SHEET Task: CLASSIFY THE EVENT - SITE AREA EMERGENCY Alternate Path:
n/a Facility JPM #:
Modified Safety Function:
N/A Title: Emergency Procedures / Plan K/A 2.4.39 Knowledge of the emergency action level thresholds and classifications.
Rating(s):
2.9/4.6 CFR: 41.10 / 43.5 / 45.11 Evaluation Method:
Simulator In-Plant Classroom X* References
- EPIP-1, Emergency Plan Classification Flowpath, Rev. 42. EPIP-2, Notification of Unusual Event, Rev.34. EPIP-3, Alert, Rev. 40. EPIP-4, Site Area Emergency, Rev. 38.
EPIP-5, General Emergency, Rev. 44.
Task Number:
SRO-113-EPIP-001 Title: Classify emergency events requiring Emergency Plan implementation.
Task Standard:
The applicant:
- 1. Classifies the event as a SITE AREA EMERGENCY within 15 minutes of the Start Time.
- 2. EPIP-4, Site Area Emergency, Appendix A, Site Area Emergency Initial Notification Form is marked correctly per the supplied KEY.
Validation Time:
20 minutes Time Critical:
Yes X No ==============================================================================================
EVALUATION SHEET Applicant: ___________________________
_________________
Time Start: ________
NAME Docket No.
Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE ============================================================================================== COMMENTS WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2015-301 Page 3 of 10 Tools/Equipment/Procedures Needed:
NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.
EXAMINER: Multiple copies of each of the following forms will be available for use by the applicants:
EPIP-2, Notification of Unusual Even, Appendix A, Notification of Unusual Event Initial Notification Form, and Appendix B, State of Tennessee Notification.
EPIP-3, Alert, Appendix A, Alert Notification Form, and Appendix B, State of Tennessee Notification. EPIP-4, Site Area Emergency, Appendix A, Site Area Emergency Initial Notification Form, and A ppendix B, State of Tennessee Notification. EPIP-5, General Emergency, Appendix A, General Emergency Initial Notification Form, Appendix B, State of Tennessee
Notification, and Appendix H, Initial - Protective Action
Recommendations.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2015-301 Page 4 of 10 READ TO THE APPLICANT:
DIRECTION TO APPLICANT:
I will explain the initial conditions and state the task to be performed. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is at 100% power. 2. You are the Shift Manager.
- 3. Windows 166-E, SEISM IC RECORDER INITIATED and 166-D, OBE SPECTRA EXCEEDED are LIT. 4. Reports from Site Security confi rm that an earthquake was felt on site. 5. The Auxiliary Building AUO reports that Gas Decay tank H was full and has suddenly depressurized. 6. An initial dose assessment has been performed using the ICS computer and the following results are predicted at the exclusion area boundary (EAB): TEDE: 115 mrem/hr Thyroid CDE: 440 mrem/hr
INITIATING CUES:
- 1. You are to evaluate conditions provid ed, and then determine the proper event classification(s), if any. 2. If needed, after you have classified the even t(s), fill out the appropriate form(s) which are used to make the initial notification to the Operations Duty Specialist (ODS). 3. This JPM contains ti me critical elements.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 5 of 10 START TIME: _______
STEP 1: Classifies the event as a SITE AREA EMERGENCY within 15 minutes of the Start Time.
STANDARD: Applicant refers to EPIP-1, Secti on 5, Destructive Phenomenon, 5.1, Earthquake.
Applicant determines that t he following conditions exist: Both Window 166-D, OBE SPECTRA EXCEEDED and Window 166-E, SEISMIC RECORDING INITIATED are LIT, AND Reports from personnel internal and external to the main control room have been received that gr ound motion has been sensed.
Based on Emergency Class Criteria, t he applicant determines this event is an ALERT. Applicant refers to EPIP-1, Section 7, RADIOLOGICAL, 7.1, Gaseous Effluent.
Applicant determines that the following exist under 7.1 Gaseous Effluents: Condition 1 has NOT been exceeded.
Condition 2 has NOT been exceeded.
The initial dose assessment indica tes that the >100 mrem/hr TEDE value HAS been exceeded.
Based on Emergency Class Criteria, the applicant determines the need to declare an SITE AREA EMERGENCY.
Criteria to meet the critical step is for the EALs to be correctly identified and the declaration made within 15 minutes.
NOTE TO EXAMINER
- Time Declarati on Made: ________________
COMMENTS: CRITICAL STEP ___ SAT
___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 6 of 10 STEP 2: Completes EPIP-4, Site Area Emergency, Appendix A, Site Area Emergency Initial Notification Form.
STANDARD: Applicant completes EPIP-4, SITE AREA EMERGENCY, Appendix A, Site Area Emergency Initial Notification Form.
Step is critical to ensure the correct information is communicated to outside agencies.
COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT STEP 3: EPIP-4, Site Area Emergen cy, Appendix A, Site Area Emergency Initial Notification Form, is marked correctly.
STANDARD: Applicant completes EPIP-4, SITE AREA EMERGENCY, Appendix A, Site Area Emergency Initial Notification Form, per the attached key.
Critical elements that must appear on Appendix A form:
Item 1 - Marked as a Drill or Actual Item 3 - EAL Designator -
7.1 (Gaseous Effluent)
Item 5. - Time and Date that applicant declared the event.
Completed by (SED): Block signed by applicant.
COMMENTS:
CRITICAL STEP ___ SAT ___ UNSAT STOP TIME ________
Page 7 of 10 5 S KEY DO NOT HAND TO APPLICANT
WBN Unit 0 Emergency Plan Classification Logic EPIP-1 Rev. 0042 Page 38 of 54 Attachment 5 (Page 3 of 7)
5.1 Earthquake
5.2 Tornado
Mode Initiating/Condition Mode Initiating/Condition G E N E R A L Refer to "Fission Product Barrier Matrix" Refer to "Fission Product Barrier Matrix" S I T E Refer to "Fission Product Barrier Matrix" Refer to "Fission Product Barrier Matrix" A L E R T All Earthquake detected by site seismic instrumentation (1 and 2)
- 1. (a and b)
- a. Ann.166 D indicates "OBE Spectra Exceeded" b. Ann.166 E indicates "Seismic Recording Initiated"
- 2. (a or b) a. Ground motion sensed by Plant personnel b. National Earthquake Information Center at 1-(303) 273-8500 can confirm the event.
All Tornado or High Winds strikes any structure listed in Table 5-1 and results in VISIBLE DAMAGE (1 and 2) 1. Tornado or High Winds (Sustained >80 mph > one minute) strikes any structure listed in Table 5-1
- 2. (a or b) a. Confirmed report of any VISIBLE DAMAGE b. Control Room indications of degraded Safety System or component response due to event Note: Site Met Data Instrumentation fails to 0 at >100 mph. National Weather Service Morristown 1-(423) 586-8400 can provide additional information if needed.
U N U S U A L E V E N T All Earthquake detected by site seismic instrumentation (1 and 2) 1. Ann. 166 E indicator "Seismic Recording Initiated"
- 2. (a or b) a. Ground motion sensed by Plant personnel b. National Earthquake Information Center at 1-(303) 273-8500 can confirm the event.
All Tornado within the SITE PERIMETER
- 1. Plant personnel report a Tornado has been sighted within the SITE PERIMETER (Refer to Figure 5-A)
WBN Unit 0 Emergency Plan Classification Logic EPIP-1 Rev. 0042 Page 49 of 54 Attachment 7 (Page 3 of 8)
7.1 Gaseous
Effluents
7.2 Liquid
Effluents Mode Initiating/Condition Mode Initiating/Condition G E N E R A L All EAB dose resulting from an actual or imminent release of Gaseous Radioactivity that exceeds 1000 mrem TEDE or 5000 mrem Thyroid CDE for the actual or projected duration of the release (1 or 2 or 3)
- 1. A VALID Rad monitor reading exceeds the values under General in Table 7-1 for >15 minutes, unless assessment within this time period confirms that the Criterion is Not exceeded. 2. Field survey results indicate >1000 mrem/hr gamma or an I-131 concentration of 3.9E-6
µ Ci/cc at SP 3. EP dose assessment results indicate EAB dose >1000 mrem TEDE or >5000 mrem Thyroid CDE for the actual or projected duration of the release (Figure 7-A)
Not Applicable S I T E All EAB dose resulting from an actual or imminent release of Gaseous Radioactivity that exceeds 100 mrem TEDE or 500 mrem Thyroid CDE for the actual or projected duration of the release (1 or 2 or 3)
- 1. A VALID Rad monitor reading exceeds the values under Site in Table 7-1 for >15 minutes, unless assessment within this time period confirms that the Criterion is Not exceeded 2. Field survey results indicate >100 mrem/hr gamma or an I-131 concentration of 3.9E-7
µ Ci/cc at SP 3. EP dose assessment results indicate EAB dose >100 mrem TEDE or >500 mrem Thyroid CDE for the actual or projected duration of the release (Figure 7-A) Not Applicable A L E R T All Any UNPLANNED release of Gaseous Radioactivity that exceeds 200 times the ODCM Limit for >15 minutes (1 or 2 or 3)
- 1. A VALID Rad monitor reading exceeds the values under Alert in Table 7-1 for >15 minutes, unless assessment within this time period confirms that the Criterion is Not exceeded 2. Field survey results indicate >10 mrem/hr gamma at SP >15 minutes 3. EP dose assessment results indicate EAB dose >10 mrem TEDE for the duration of the release (Figure 7-A)
All Any UNPLANNED release of Liquid Radioactivity that exceeds 200 times the ODCM Limit for >15 minutes (1 or 2) 1. A VALID Rad monitor reading exceeds the values under Alert in Table 7-1 for >15 minutes, unless assessment within this time period confirms that the Criterion is Not exceeded. 2. Sample results exceed 200 times the ODCM limit value for an unmonitored release of liquid radioactivity >15 minutes in duration U N U S U A L E V E N T All Any UNPLANNED release of Gaseous Radioactivity that exceeds 2 times the ODCM Limit for >60 minutes (1 or 2 or 3)
- 1. A VALID Rad monitor reading exceeds the values under UE in Table 7-1 for >60 minutes, unless assessment within this time period confirms that the Criterion is Not exceeded 2. Field survey results indicate >0.1 mrem/hr gamma at SP for >60 minutes 3. EP dose assessment results indicate EAB dose >0.1 mrem TEDE for the duration of the release (Figure 7-A)
All Any UNPLANNED release of Liquid Radioactivity to the Environment that exceeds 2 times the ODCM Limit for >60 minutes (1 or 2) 1. A VALID Rad monitor reading exceeds the values under UE in Table 7-1 for >60 minutes, unless assessment within this time period confirms that the Criterion is Not exceeded. 2. Sample results exceed 2 times the ODCM limit value for an unmonitored release of liquid radioactivity >60 minutes in duration
WBN Unit 0 Site Area Emergency EPIP-4 Rev. 0038 Page 15 of 28 Appendix A (Page 1 of 1) Site Area Emergency Initial Notification Form
- 1. This is a Drill This is an Actual Event - Repeat - This is an Actual Event
- 2. The SED at Watts Bar has declared a Site Area Emergency
- 3. EAL Designator: ________________________________
- 4. Radiological Conditions: (Check one under both Airborne and Liquid column.)
Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits 1 Minor releases within federally approved limits 1 Releases above federally approved limits 1 Releases above federally approved limits 1 Release information not known (1Tech Specs/ODCM)
Release information not known (1Tech Specs/ODCM)
- 5. Event Declared:
Time:________________
Eastern Time Date:__________________
- 6. Provide Protective Action Recommendation:
None Completed By (SED)
________________________
_______________ Peer Checked By:
________________________
_______________
Page 8 of 10 5 S BLANK FORMS
WBN Unit 0 Notification of Unusual Event EPIP-2 Rev. 0034 Page 14 of 24 Appendix A (Page 1 of 1)
Notification of Unusual Event Initial Notification Form
- 1. This is a Drill This is an Actual Event - Repeat - This is an Actual Event
- 2. The SED at Watts Bar has declared a NOTIFICATION OF UNUSUAL EVENT.
- 4. Radiological Conditions: (Check one under both Airborne and Liquid column.) Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits 1 Minor releases within federally approved limits 1 Releases above federally approved limits 1 Releases above federally approved limits 1 Release information not known (1Tech Specs/ODCM) Release information not known (1Tech Specs/ODCM)
- 5. Event Declared: Time:________________ Eastern Time Date:__________________
- 6. Protective Action Recommendation:
None Completed By (SED) ________________________________________ Peer Checked By: ________________________________________
WBN Unit 0 Alert EPIP-3 Rev. 0040 Page 15 of 30 Appendix A (Page 1 of 1) Alert Initial Notification Form
- 1. This is a Drill This is an Actual Event - Repeat - This is an Actual Event
- 2. The SED at Watts Bar has declared an ALERT 3. EAL Designator: ________________________________
- 4. Radiological Conditions: (Check one under both Airborne and Liquid column.) Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits 1 Minor releases within federally approved limits 1 Releases above federally approved limits 1 Releases above federally approved limits 1 Release information not known (1Tech Specs/ODCM)
Release information not known (1Tech Specs/ODCM)
- 5. Event Declared: Time:________________ Eastern Time Date:__________________
- 6. Protective Action Recommendation:
None Completed by (SED):
__________________
__________________
________ Peer checked by: ______
__________________
____________________
WBN Unit 0 Site Area Emergency EPIP-4 Rev. 0038 Page 15 of 28 Appendix A (Page 1 of 1) Site Area Emergency Initial Notification Form
- 1. This is a Drill This is an Actual Event - Repeat - This is an Actual Event
- 2. The SED at Watts Bar has declared a Site Area Emergency
- 3. EAL Designator: ________________________________
- 4. Radiological Conditions: (Check one under both Airborne and Liquid column.)
Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits 1 Minor releases within federally approved limits 1 Releases above federally approved limits 1 Releases above federally approved limits 1 Release information not known (1Tech Specs/ODCM)
Release information not known (1Tech Specs/ODCM)
- 5. Event Declared: Time:________________
Eastern Time Date:__________________
- 6. Provide Protective Action Recommendation:
None Completed By (SED)
________________________
_______________ Peer Checked By:
________________________
_______________
WBN Unit 0 General Emergency EPIP-5 Rev. 0044 Page 15 of 37 Appendix A (Page 1 of 2) General Emergency Initial Notification Form Protective Action Recommendation Worksheet 1. Determine the correct PAR using the PAR diagram (Appendix H) Recommendation 1
- Shelter 2 mile radius
- Shelter 5 miles downwind Recommendation 2
- Shelter 5 mile radius Recommendation 3
- Evacuate 2 mile radius
- Shelter 5 miles downwind Recommendation 4
- Evacuate 2 mile radius
- Evacuate 5 miles downwind
- Shelter 10 miles downwind Recommendation 5
- Evacuate 2 mile radius and all sectors greater than Protective Action Guidelines (PAG) Recommendation 6
- Evacuate 2 mile radius
- Evacuate 5 miles downwind 2. Identify the affected sectors using the table below Wind direction From (46 meters): ___________________ degrees 2 Mile Radius Sectors 5 Mile Radius Sectors 5 Mile Downwind Sectors Wind Direction From 10 Mile Downwind Sectors A1, B1, C1, D1 A1, B1, C1, D1, A2, B2, C2, D2, A3, B4, C4, C5, C7, C8, D4, D5 C7, D2, D4, D5 26°- 68° C9, D6, D7, D8, D9 A3, D2, D4, D5 69°- 110° A4, D3,D6, D7, D8, D9 A2, A3, D2, D5 111°- 170° A4, A5, A6, A7, D3, D6 A2, A3, B2, B4, C2 171°- 230° A5, A6, A7, B3, B5 B2, B4, C2 231°- 270° B5, C3 B2, C2, C4, C5 271°- 325° B3,C3, C6, C11 C2, C4, C5, C7, C8, D4 326°- 25° C6, C9, C10, C11, D9 3. Use the above information to complete page 2 of this appendix.
WBN Unit 0 General Emergency EPIP-5 Rev. 0044 Page 16 of 37 Appendix A (Page 2 of 2) General Emergency Initial Notification Form
- 1. This is a Drill This is an Actual Event - Repeat - This is an Actual Event
- 2. The SED at Watts Bar has declared a GENERAL EMERGENCY
- 4. Radiological Conditions: (Check one under both Airborne and Liquid column.) Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits 1 Releases above federally approved limits 1 Release information not known (1Tech Specs/ODCM) Minor releases within federally approved limits 1 Releases above federally approved limits 1 Release information not known (1Tech Specs/ODCM)
- 5. Event Declared: Time:__________________ Date:_____________________
- 6. The Meteorological Conditions are: (Use 46 meter data from the Met Tower. IF data is NOT available from the MET tower, contact the National Weather Service by dialing 9-1-423-586-8400. The National Weather Service will provide wind direction and wind speed.) Wind Direction is FROM:_____________ degrees (15 minute average) Wind Speed: ______________ mph (15 minute average)
- 7. Provide Protective Action Recommendation utilizing Appendix H: (Check all Sectors as appropriate) A) AFFECTED SECTORS Evacuate 2 Mile A1 B1 C1 D1 5 Mile A2 A3 B2 B4 C2 C4 C5 C7 C8 D2 D4 D5 10 Mile A4 A5 A6 A7 B3 B5 C3 C6 C9 C10 C11 D3 D6 D7 D8 D9 Shelter (do not check sectors evacuated above) 2 Mile A1 B1 C1 D1 5 Mile A2 A3 B2 B4 C2 C4 C5 C7 C8 D2 D4 D5 10 Mile A4 A5 A6 A7 B3 B5 C3 C6 C9 C10 C11 D3 D6 D7 D8 D9 B) ALL OTHER SECTORS MONITOR AND PREPARE. C) CONSIDER ISSUANCE OF KI IN ACCORDANCE WITH THE STATE PLAN. Completed by (SED)______________ Peer Checked by ________________
WBN Unit 0 General Emergency EPIP-5 Rev. 0044 Page 31 of 37 Appendix H (Page 1 of 2)
Protective Action Recomme ndation Flow Chart
WBN Unit 0 General Emergency EPIP-5 Rev. 0044 Page 32 of 37 Appendix H (Page 2 of 2)
Protective Action Recomme ndation Flow Chart
5 S
Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 5 INITIAL CONDITIONS:
- 1. Unit 1 is at 100% power. 2. You are the Shift Manager.
- 3. Windows 166-E, SEISM IC RECORDER INITIATED and 166-D, OBE SPECTRA EXCEEDED are LIT. 4. Reports from Site Security confi rm that an earthquake was felt on site. 5. The Auxiliary Building AUO reports that Gas Decay tank H was full and has suddenly depressurized. 6. An initial dose assessment has been performed using the ICS computer and the following results are predicted at the exclusion area boundary (EAB): TEDE: 115 mrem/hr Thyroid CDE: 440 mrem/hr
INITIATING CUES:
- 1. You are to evaluate conditions provid ed, and then determine the proper event classification(s), if any. 2. If needed, after you have classified the even t(s), fill out the appropriate form(s) which are used to make the initial notification to the Operations Duty Specialist (ODS). 3. This JPM contains ti me critical elements.