ML15245A309
| ML15245A309 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/31/2015 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| 50-413/15-301, 50-414/15-301 | |
| Download: ML15245A309 (47) | |
Text
Catawba Nuclear Station Admin. JPM A.1-1 May 2015 NRC Exam PAGE 1 OF 9 JPM A.1-1 RO / SRO
Catawba Nuclear Station Admin. JPM A.1-1 May 2015 NRC Exam PAGE 2 OF 9 EVALUATION SHEET Task:
Calculate Reactor Vessel Head Venting Time Alternate Path:
N/A Facility JPM #:
CSF-003 Safety Function:
N/A K/A G 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
Importance:
3.9 / 4.2 CFR:
41.10 / 43.5 / 45.12 Preferred Evaluation Location:
Preferred Evaluation Method:
Simulator Classroom X
Perform X
Simulate
References:
EP/1/A/5000/FR-I.3 Response to Voids in Reactor Vessel, Enclosure 5 (rev 17) and images of control room gauges needed to perform head vent calculation.
Task Standard:
Reactor vessel head maximum allowable vent time calculated as between 3.4 minutes and 5.2 minutes.
Validation Time:
15 minutes Time Critical:
Yes No X
Applicant:
Time Start: __________
NAME___________________________
Docket #_______________
Time Finish: __________
Performance Rating:
SAT ____ UNSAT ____
Performance Time _____
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS
Catawba Nuclear Station Admin. JPM A.1-1 May 2015 NRC Exam PAGE 3 OF 9 SIMULATOR OPERATOR INSTRUCTIONS:
- 1.
ENSURE NRC Examination Security has been established.
- 2.
Insert the following malfunctions:
Instructor Action Final Delay Ramp Delete In Event XMT-VV010 (TVV_5090 LOWER CNT AIR TEMP A MTR) 140 XMT-VV011 (TVV_5110 LOWER CNT AIR TEMP B MTR) 140 XMT-VV014 (TVV_5170 LOWER CNT AIR TEMP C MTR) 140 XMT-VV015 (TVV_5190 LOWER CNT AIR TEMP D MTR) 140 XMT-VX003 (XMI_5320 CNT TRN A H2 ANAL MTR) 1.5 XMT-VX004 (XMI_5330 CNT TRN B H2 ANAL MTR) 1.5 XMT-CNT009 (PNS_5090 CNT PRESS MTR (PI-937))
3.0 XMT-CNT008 (PNS_5060 CNT PRESS MTR (PI-936))
3.0 XMT-CNT007 (PNS_5050 CNT PRESS MTR (PI-935))
3.0 XMT-CNT006 (PNS_5040 CNT PRESS MTR (PI-934))
3.0 XMT-CNT011 (PNS_5380 CNT TRN B PRESS MTR) 3.0 XMT-CNT010 (PNS_5370 CNT TRN A PRESS MTR) 3.0 IND-NC023 (PNC_5120 LOOP B HOT LEG W/R PRESS MTR (PI-405))
1000 IND-NC024 (PNC_5140 LOOP C HOT LEG W/R PRESS MTR (PI-403))
1000
- 3.
Take digital photographs of the gauges listed above or provide control board mimics from the instructor station.
NOTE TO EVALUATOR: These have been provided as part of the JPM package for each applicant.
PAGE 4 0F 9 Catawba Nuclear Station Admin. JPM A.1-1 May 2015 NRC Exam PAGE 4 OF 9 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
A LOCA is in progress on Unit 1.
INITIATING CUES:
The CRS directs you to calculate and record the maximum reactor vessel head venting time per EP/1/A/5000/FR-I.3 (Response to Voids in Reactor Vessel) (Allowable Hydrogen Venting Time).
EXAMINER NOTE: Each applicant should receive a copy of FR-I.3 Enclosure 5 as well as 4 pictures of control room gauges for:
H2 Analyzers Containment Pressure Lower Containment Air Temperatures Loop B and C Hot Leg W/R Pressure
Catawba Nuclear Station Admin. JPM A.1-1 May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 9 START TIME: _______
STEP 1: Step 1 Calculate A where A = 9500 X (P + 14.7) X 492 14.7 (T+460)
Where: P = Containment pressure (PSIG)
T = Lower Containment temperature (°F)
STANDARD:
Calculate A:
Determine containment pressure as 2.9 psig to 3.1 psig.
Determine Lower Containment Temperature as 135°F - 145°F.
Using 2.9, 135 A = 9500 X (2.9 + 14.7) X 492 = 9405.18 14.7 (135+460)
Using 2.9, 145 A = 9500 X (2.9 + 14.7) X 492 = 9249.68 14.7 (145+460)
Using 3.1, 135 A = 9500 X (3.1 + 14.7) X 492 = 9513.07 14.7 (135+460)
Using 3.1, 145 A = 9500 X (3.1 + 14.7) X 492 = 9354.76 14.7 (145+460)
NOTE TO EXAMINER: Acceptable band for value of A is 9249 - 9513.
This step is critical to properly perform this task and to meet the JPM standard to calculate the maximum head vent time for the conditions given.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.1-1 May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 9 STEP 2: Step 2 Calculate B where B = (3 - H) X A Where H = Containment Hydrogen Concentration (%)
STANDARD:
Determine H2 concentration as between 1.25% and 1.75%.
Using bounding values of A (9249 to 9513):
B = (3 - 1.25) X 9249 = 16185.8 B = (3 - 1.25) X 9513 = 16647.8 B = (3 - 1.75) X 9249 = 11561.3 B = (3 - 1.75) X 9513 = 11891.3 NOTE TO EXAMINER: Acceptable range for value of B is 11561 -
16648.
This step is critical to properly perform this task and to meet the JPM standard to calculate the maximum head vent time for the conditions given.
COMMENTS:
CRITICAL STEP
___ SAT
___UNSAT
Catawba Nuclear Station Admin. JPM A.1-1 May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 0F 9 STEP 3: Step 3 Determine C from the curve for the current NC system pressure.
STANDARD:
Determines NC pressure from pictures as 975 psig to 1025 psig.
Determines C (hydrogen flow rate) as between 3,200 - 3400 SCFM.
This step is critical to properly perform this task and to meet the JPM standard to calculate the maximum head vent time for the conditions given.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.1-1 May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 0F 9 STEP 4 Step 4 Calculate T:
T= B / C = Venting time in minutes STANDARD:
Using bounding values for B and C:
T = 11561 / 3200 = 3.61 minutes T = 11561 / 3400 = 3.40 minutes T = 16648 / 3200 = 5.20 minutes T = 16648 / 3400 = 4.90 minutes NOTE TO EXAMINER: Maximum allowable venting time acceptable band is 3.4 - 5.2 minutes (3 minutes 24 seconds to 5 minutes 12 seconds).
This step is critical to properly perform this task and to meet the JPM standard to calculate the maximum head vent time for the conditions given.
COMMENTS:
END OF TASK CRITICAL STEP
___ SAT
___ UNSAT STOP TIME ________
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Catawba 2015 NRC Exam - Admin. JPM A.1-1 INITIAL CONDITIONS:
A LOCA is in progress on Unit 1.
INITIATING CUES:
The CRS directs you to calculate and record the maximum reactor vessel head venting time per EP/1/A/5000/FR-I.3 (Response to Voids in Reactor Vessel) (Allowable Hydrogen Venting Time).
Catawba Nuclear Station Admin. JPM A.1-2R May 2015 NRC Exam PAGE 1 OF 9 JPM A.1-2R RO
Catawba Nuclear Station Admin. JPM A.1-2R May 2015 NRC Exam PAGE 2 OF 9 EVALUATION SHEET Task:
Perform a Manual NC System Leakage Calculation Alternate Path:
N/A Facility JPM #:
NC-094 Modified Safety Function:
N/A K/A G 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
Importance:
4.4 / 4.7 CFR:
41.5 / 43.5 / 45.12 / 45.13 Preferred Evaluation Location:
Preferred Evaluation Method:
Simulator Classroom X
Perform X
Simulate
References:
PT/1/A/4150/001 D (NC System Leakage Calculation) rev 81 Task Standard:
A manual NC System Leakage Calculation is performed per PT/1/A/4150/001 D (NC System Leakage Calculation) and the following results reported:
Unidentified Leakage 10.6 - 10.7 gpm, Identified Leakage 0.2 - 0.3 gpm, Total Accumulated Leakage 21.8 - 21.9 gpm. Box is checked for > 20 gpm total leakage on Enclosure 13.3.2.
Validation Time:
30 minutes Time Critical:
Yes No X
Applicant:
Time Start: __________
NAME___________________________
Docket #_______________
Time Finish: __________
Performance Rating:
SAT ____ UNSAT ____
Performance Time _____
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS
PAGE 3 0F 9 Catawba Nuclear Station Admin. JPM A.1-2R May 2015 NRC Exam PAGE 3 OF 9 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 1 is in Mode 1 at 100% power.
The OAC is out of service due to emergent system failures and will not be returned to service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Other operators are performing PT/1/A/4600/009 (Loss of Operator Aid Computer) and OP/1/A/6700/003 (Operation With the Operator Aid Computer Out of Service).
INITIATING CUES:
The CRS directs you to perform an NC System Leakage Calculation per PT/1/A/4150/001 D (NC System Leakage Calculation).
Steps are complete through 12.11.
You are to perform step 12.12.
The Open Item Summary has been updated. The background leakage is.077 gpm (Orbisphere flow reported by Primary Chemistry).
Using the attached Data Sheet and PT/1/A/4150/001 D, calculate and report the following information back to the CRS:
____________ gpm Identified Leakage
____________ gpm Total Accumulated Leakage
____________ gpm EXAMINER NOTE: Each applicant should receive a copy of attached Data Sheets and a copy of PT/1/A/4150/001 D rev 81 body signed off through step 12.11 and Enclosure 13.3.
Catawba Nuclear Station Admin. JPM A.1-2R May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 0F 9 START TIME: _______
STEP 1 12.12 IF the OAC is partially or wholly unavailable OR Unit 1 is NOT at or near normal operating temperature and pressure (i.e. Tavg < 550°F and W/R pressure < 2200 psig), perform Enclosure 13.3 (Manual Leakage Calculation).
STANDARD:
Applicant determines that this step is applicable and goes to Enclosure 13.3 for a manual leakage calculation.
COMMENTS:
___ SAT
___UNSAT STEP 2 Enclosure 13.3 step 1.1 Verify the following valves are closed:
- 1NC-56B (RMW Pump Disch Cont Isol)
- 1NV-236B (Boric Acid to NV Pumps Suct)
- 1NV-252A (NV Pumps Suct From FWST)
- 1NV-253B (NV Pumps Suct From FWST)
- 1NI-9A (NV Pump C/L Inj Isol)
- 1NI-10B (NV Pump C/L Inj Isol)
STANDARD:
Applicant determines from the data sheet provided that all of the listed valves are closed.
COMMENTS:
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.1-2R May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 9 STEP 3 1.2 Record Initial Data on Enclosure 13.3.1 (Manual Leakage Data) using Control Room indications or OAC (if available).
STANDARD:
Applicant records initial data on Enclosure 13.3.1 using the provided data sheet.
COMMENTS:
___ SAT
___ UNSAT NOTE: Calculation accuracy improves as the time between initial and final data increases.
STEP 4 1.3 Wait at least 60 minutes prior to obtaining final data.
STANDARD:
Applicant is given data for 61 minutes after initial data.
COMMENTS:
___ SAT
___ UNSAT STEP 5 1.4 Record Final Data on Enclosure 13.3.1 (Manual Leakage Data) using Control Room indications or OAC (if available).
STANDARD:
Applicant records final data on Enclosure 13.3.1 using the provided data sheet.
COMMENTS:
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.1-2R May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 9 STEP 6 1.5 Using data from Enclosure 13.3.1 (Manual Leakage Data),
calculate change in T-Avg:
____________ - _____________ = _________ °F NC Average temp initial NC Average temp final STANDARD:
Applicant calculates change in T-Avg to be.2°F.
COMMENTS:
___ SAT
___ UNSAT NOTE: Procedure may continue while performing the following step.
If change in T-Avg is greater than 0.25°F (0.1°F if using OAC), calculation is invalid and must be repeated.
STEP 7 1.6 IF change in T-Avg is less than or equal to 0.25°F (0.1°F if using OAC), perform all calculations on Enclosure 13.3.2 (Manual Calculation).
STANDARD:
Applicant determines from previous step that T-Avg is 0.2°F and performs calculations from Enclosure 13.3.2.
COMMENTS:
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.1-2R May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 0F 9 STEP 8 Enclosure 13.3.2 (Manual Calculation)
STANDARD:
Applicant performs the required calculations and comes up with the following results:
VCT Leakage Rate = 10.96 gpm (Allowable range 10.9 - 11.0 gpm)
PZR Leakage Rate = 0 gpm Total Leakage = 10.96 gpm (Allowable range 10.9 - 11.0 gpm)
NCDT Leakage Rate =.184 gpm (Allowable range 0.1 - 0.2 gpm)
PRT Leakage Rate = 0 gpm Identified Leakage =.261 gpm (Allowable range 0.2 - 0.3 gpm)
Unidentified Leakage = 10.699 gpm (Allowable range 10.6 - 10.7 gpm)
Total Accumulated Leakage = 21.89 gpm (Allowable range 21.8 - 21.9 gpm)
These steps are critical to ensure accurate leakage values will be used to determine compliance with Technical Specifications/Selected License Commitments for NC system leakage.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 9 Ensure box is checked on Enclosure 13.3.2 for > 20 gpm.
STANDARD:
Applicant determines that total accumulated leakage is > 20 gpm, and check the box indicating this on Enclosure 13.3.2.
This step is critical to meet the task and JPM standard.
COMMENTS:
END OF TASK CRITICAL STEP
___ SAT
___ UNSAT STOP TIME ________
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Catawba 2015 NRC Exam - Admin. JPM A.1-2R INITIAL CONDITIONS:
Unit 1 is in Mode 1 at 100% power.
The OAC is out of service due to emergent system failures and will not be returned to service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Other operators are performing PT/1/A/4600/009 (Loss of Operator Aid Computer) and OP/1/A/6700/003 (Operation With the Operator Aid Computer Out of Service).
INITIATING CUES:
The CRS directs you to perform an NC System Leakage Calculation per PT/1/A/4150/001 D (NC System Leakage Calculation).
Steps are complete through 12.11.
You are to perform step 12.12.
The Open Item Summary has been updated. The background leakage is.077 gpm (Orbisphere flow reported by Primary Chemistry).
Using the attached Data Sheet and PT/1/A/4150/001 D, calculate and report the following information back to the CRS:
____________ gpm Identified Leakage
____________ gpm Total Accumulated Leakage
____________ gpm
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Catawba 2015 NRC Exam - Admin. JPM A.1-2R DATA SHEET The following valves are closed:
- 1NC-56B (RMW Pump Disch Cont Isol)
- 1NV-236B (Boric Acid to NV Pumps Suct)
- 1NV-252A (NV Pumps Suct From FWST)
- 1NV-253B (NV Pumps Suct From FWST)
- 1NI-9A (NV Pump C/L Inj Isol)
- 1NI-10B (NV Pump C/L Inj Isol)
Parameter Instrument 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> Data 2101 hours0.0243 days <br />0.584 hours <br />0.00347 weeks <br />7.994305e-4 months <br /> Data NC Avg. Temp.
1NCCR5421 584.5 °F 584.3 °F VCT Level 1NVP5761 65%
30%
PZR Level 1NCP5164 55%
55%
NCDT Level 1WLP5630 48%
51%
PRT Level 1NCP5131 68%
68%
1A NC Pump #1 Seal Leakoff Flow 2.50 GPM 1B NC Pump #1 Seal Leakoff Flow 2.87 GPM 1C NC Pump #1 Seal Leakoff Flow 2.77 GPM 1D NC Pump #1 Seal Leakoff Flow 2.79 GPM 1EMF-71 Leakage 75 GPD 1EMF-72 Leakage 80 GPD 1EMF-73 Leakage 1 GPD 1EMF-74 Leakage 1 GPD Background leakage -.077 gpm (Orbisphere flow)
Catawba Nuclear Station Admin. JPM A.1-2S May 2015 NRC Exam PAGE 1 OF 10 JPM A.1-2S SRO
Catawba Nuclear Station Admin. JPM A.1-2S May 2015 NRC Exam PAGE 2 OF 10 EVALUATION SHEET Task:
Perform a Manual NC System Leakage Calculation Alternate Path:
N/A Facility JPM #:
NC-094 Modified Safety Function:
N/A K/A G 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
Importance:
4.4 / 4.7 CFR:
41.5 / 43.5 / 45.12 / 45.13 Preferred Evaluation Location:
Preferred Evaluation Method:
Simulator Classroom X
Perform X
Simulate
References:
PT/1/A/4150/001 D (NC System Leakage Calculation) rev 81 Task Standard:
A manual NC System Leakage Calculation is performed per PT/1/A/4150/001 D (NC System Leakage Calculation) and the following results reported:
Unidentified Leakage 10.6 - 10.7 gpm, Identified Leakage 0.2 - 0.3 gpm, Total Accumulated Leakage 21.8 - 21.9 gpm. Determines that T.S. 3.4.13 Condition A and SLC 16.7-9 Condition B are applicable.
Validation Time:
30 minutes Time Critical:
Yes No X
Applicant:
Time Start: __________
NAME___________________________
Docket #_______________
Time Finish: __________
Performance Rating:
SAT ____ UNSAT ____
Performance Time _____
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE COMMENTS
PAGE 3 0F 10 Catawba Nuclear Station Admin. JPM A.1-2S May 2015 NRC Exam PAGE 3 OF 10 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 1 is in Mode 1 at 100% power.
The OAC is out of service due to emergent system failures and will not be returned to service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Other operators are performing PT/1/A/4600/009 (Loss of Operator Aid Computer) and OP/1/A/6700/003 (Operation With the Operator Aid Computer Out of Service).
INITIATING CUES:
The CRS directs you to perform an NC System Leakage Calculation per PT/1/A/4150/001 D (NC System Leakage Calculation).
Steps are complete through 12.11.
You are to perform step 12.12.
The Open Item Summary has been updated. The background leakage is.077 gpm (Orbisphere flow reported by Primary Chemistry).
Using the attached Data Sheet and PT/1/A/4150/001 D, calculate and report the following information back to the CRS:
____________ gpm Identified Leakage
____________ gpm Total Accumulated Leakage
____________ gpm Applicable Tech Specs or SLCs:
EXAMINER NOTE: Each applicant should receive a copy of attached Data Sheets and a copy of PT/1/A/4150/001 D rev 81 body signed off through step 12.11 and Enclosure 13.3.
Catawba Nuclear Station Admin. JPM A.1-2S May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 0F 10 START TIME: _______
STEP 1 12.12 IF the OAC is partially or wholly unavailable OR Unit 1 is NOT at or near normal operating temperature and pressure (i.e. Tavg < 550°F and W/R pressure < 2200 psig), perform Enclosure 13.3 (Manual Leakage Calculation).
STANDARD:
Applicant determines that this step is applicable and goes to Enclosure 13.3 for a manual leakage calculation.
COMMENTS:
___ SAT
___UNSAT STEP 2 Enclosure 13.3 step 1.1 Verify the following valves are closed:
- 1NC-56B (RMW Pump Disch Cont Isol)
- 1NV-236B (Boric Acid to NV Pumps Suct)
- 1NV-252A (NV Pumps Suct From FWST)
- 1NV-253B (NV Pumps Suct From FWST)
- 1NI-9A (NV Pump C/L Inj Isol)
- 1NI-10B (NV Pump C/L Inj Isol)
STANDARD:
Applicant determines from the data sheet provided that all of the listed valves are closed.
COMMENTS:
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.1-2S May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 10 STEP 3 1.2 Record Initial Data on Enclosure 13.3.1 (Manual Leakage Data) using Control Room indications or OAC (if available).
STANDARD:
Applicant records initial data on Enclosure 13.3.1 using the provided data sheet.
COMMENTS:
___ SAT
___ UNSAT NOTE: Calculation accuracy improves as the time between initial and final data increases.
STEP 4 1.3 Wait at least 60 minutes prior to obtaining final data.
STANDARD:
Applicant is given data for 61 minutes after initial data.
COMMENTS:
___ SAT
___ UNSAT STEP 5 1.4 Record Final Data on Enclosure 13.3.1 (Manual Leakage Data) using Control Room indications or OAC (if available).
STANDARD:
Applicant records final data on Enclosure 13.3.1 using the provided data sheet.
COMMENTS:
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.1-2S May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 10 STEP 6 1.5 Using data from Enclosure 13.3.1 (Manual Leakage Data),
calculate change in T-Avg:
____________ - _____________ = _________ °F NC Average temp initial NC Average temp final STANDARD:
Applicant calculates change in T-Avg to be.2°F.
COMMENTS:
___ SAT
___ UNSAT NOTE: Procedure may continue while performing the following step.
If change in T-Avg is greater than 0.25°F (0.1°F if using OAC), calculation is invalid and must be repeated.
STEP 7 1.6 IF change in T-Avg is less than or equal to 0.25°F (0.1°F if using OAC), perform all calculations on Enclosure 13.3.2 (Manual Calculation).
STANDARD:
Applicant determines from previous step that T-Avg is 0.2°F and performs calculations from Enclosure 13.3.2.
COMMENTS:
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.1-2S May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 0F 10 STEP 8 Enclosure 13.3.2 (Manual Calculation)
STANDARD:
Applicant performs the required calculations and comes up with the following results:
VCT Leakage Rate = 10.96 gpm (Allowable range 10.9 - 11.0 gpm)
PZR Leakage Rate = 0 gpm Total Leakage = 10.96 gpm (Allowable range 10.9 - 11.0 gpm)
NCDT Leakage Rate =.184 gpm (Allowable range 0.1 - 0.2 gpm)
PRT Leakage Rate = 0 gpm Identified Leakage =.261 gpm (Allowable range 0.2 - 0.3 gpm)
Unidentified Leakage = 10.699 gpm (Allowable range 10.6 - 10.7 gpm)
Total Accumulated Leakage = 21.89 gpm (Allowable range 21.8 - 21.9 gpm)
These steps are critical to ensure accurate leakage values will be used to determine compliance with Technical Specifications/Selected License Commitments for NC system leakage.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.1-2S May 2015 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 0F 10 STEP 9 Determine applicable Tech Specs/SLCs.
STANDARD:
Applicant determines that T.S. LCO 3.4.13 is not met for unidentified leakage being > 1 gpm and that Condition A needs to be entered. Even though total primary to secondary leakage is > 150 gpd, the T.S.
requirement is for primary to secondary leakage to any 1 S/G > 150 gpd, so Condition B is not applicable. Due to total accumulated leakage being >
20 gpm, SLC 16.7-9 Condition B should also be entered. SLC 16.7-9 condition B will have the applicants enter Condition A immediately.
This step is critical to meet the task and standard of this JPM.
COMMENTS:
END OF TASK CRITICAL STEP
___ SAT
___ UNSAT STOP TIME ________
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Catawba 2015 NRC Exam - Admin. JPM A.1-2S READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 1 is in Mode 1 at 100% power.
The OAC is out of service due to emergent system failures and will not be returned to service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Other operators are performing PT/1/A/4600/009 (Loss of Operator Aid Computer) and OP/1/A/6700/003 (Operation With the Operator Aid Computer Out of Service).
INITIATING CUES:
The CRS directs you to perform an NC System Leakage Calculation per PT/1/A/4150/001 D (NC System Leakage Calculation).
Steps are complete through 12.11.
You are to perform step 12.12.
The Open Item Summary has been updated. The background leakage is.077 gpm (Orbisphere flow reported by Primary Chemistry).
Using the attached Data Sheet and PT/1/A/4150/001 D, calculate and report the following information back to the CRS:
____________ gpm Identified Leakage
____________ gpm Total Accumulated Leakage
____________ gpm Applicable Tech Specs or SLCs:
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Catawba 2015 NRC Exam - Admin. JPM A.1-2S DATA SHEET The following valves are closed:
- 1NC-56B (RMW Pump Disch Cont Isol)
- 1NV-236B (Boric Acid to NV Pumps Suct)
- 1NV-252A (NV Pumps Suct From FWST)
- 1NV-253B (NV Pumps Suct From FWST)
- 1NI-9A (NV Pump C/L Inj Isol)
- 1NI-10B (NV Pump C/L Inj Isol)
Parameter Instrument 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> Data 2101 hours0.0243 days <br />0.584 hours <br />0.00347 weeks <br />7.994305e-4 months <br /> Data NC Avg. Temp.
1NCCR5421 584.5 °F 584.3 °F VCT Level 1NVP5761 65%
30%
PZR Level 1NCP5164 55%
55%
NCDT Level 1WLP5630 48%
51%
PRT Level 1NCP5131 68%
68%
1A NC Pump #1 Seal Leakoff Flow 2.50 GPM 1B NC Pump #1 Seal Leakoff Flow 2.87 GPM 1C NC Pump #1 Seal Leakoff Flow 2.77 GPM 1D NC Pump #1 Seal Leakoff Flow 2.79 GPM 1EMF-71 Leakage 75 GPD 1EMF-72 Leakage 80 GPD 1EMF-73 Leakage 1 GPD 1EMF-74 Leakage 1 GPD Background leakage -.077 gpm (Orbisphere flow)
Catawba Nuclear Station Admin. JPM A.2 May 2015 NRC Exam PAGE 1 OF 7 JPM A.2 RO / SRO
Catawba Nuclear Station Admin. JPM A.2 May 2015 NRC Exam PAGE 2 OF 7 EVALUATION SHEET Task:
Calculate RL System Heat Rise Alternate Path:
N/A Facility JPM #:
New Safety Function:
N/A K/A G 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
Importance:
4.2 / 4.4 CFR:
41.5 / 43.5 / 45.12 Preferred Evaluation Location:
Preferred Evaluation Method:
Simulator Classroom X
Perform X
Simulate
References:
PT/0/A/4250/011 (RL Temperature And Discharge Flow Determination)
Task Standard:
RL Heat Rise T calculated to be between 11°F and 12°F. Applicant determines that a plant heat load reduction is required.
Validation Time:
20 minutes Time Critical:
Yes No X
Applicant:
Time Start: __________
NAME___________________________
Docket #_______________
Time Finish: __________
Performance Rating:
SAT ____ UNSAT ____
Performance Time _____
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS
Catawba Nuclear Station Admin. JPM A.2 May 2015 NRC Exam PAGE 3 OF 7 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
A loss of both Unit 1 and Unit 2 OACs occurred 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.
INITIATING CUES:
The CRS directs you to perform PT/0/A/4250/011 (RL Temperature And Discharge Flow Determination) Enclosure 13.6 (RL System Heat Rise (T) Calculation).
RL discharge flows from Enclosure 13.2 were determined to be the following:
- A train RL discharge flow (RLAF) = 21,355 gpm
- B train RL discharge flow (RLBF) = 24,560 gpm Record below the RL Heat Rise T and whether NPDES permit requirements are met for todays date.
RL Heat Rise T ___________
A Plant heat load reduction is / is NOT required. Circle the correct answer.
EXAMINER NOTE: Each applicant should receive a copy of PT/0/A/4250/011 Enclosures 13.4, 13.5, and 13.6 (step 1.1 complete).
Catawba Nuclear Station Admin. JPM A.2 May 2015 NRC Exam PAGE 4 0F 7 START TIME: _______
STEP 1 1.2 Calculate RL System Heat Rise.
1.2.1 Record RL Discharge Temperatures from Enclosure 13.5 (RL Discharge Temperature Determination)
A Train 83.7 °F (RLADT)
B Train 85.3 °F (RLBDT)
STANDARD:
Applicant records values from Enclosure 13.5.
COMMENTS:
___ SAT
___ UNSAT STEP 2 1.2.2 Record RL Discharge Flows from Enclosure 13.2 (Total Discharge Flow Calculation Sheet).
A Train 21,355 gpm (RLAF)
B Train 24,560 gpm (RLBF)
STANDARD:
Applicant records values given in the cue for RL discharge flows.
COMMENTS:
___ SAT
___UNSAT
Catawba Nuclear Station Admin. JPM A.2 May 2015 NRC Exam PAGE 5 0F 7 STEP 3 1.2.3 Record RL Intake Temperature from Enclosure 13.4 (RL Intake Temperature Determination).
73 °F (RLIT)
STANDARD:
Applicant records value from Enclosure 13.4.
COMMENTS:
___ SAT
___ UNSAT STEP 4 1.2.4 Calculate RL Heat Rise (T).
(83.7 X 21,355) + (85.3 X 24,560)
RLADT RLAF RLBDT RLBF
___________________________ - 73 = 11.6 °F (21,355 + 24,560) RLIT RL Heat Rise (T)
RLAF RLBF STANDARD:
T Calculated to be 11.6°F.
No, NPDES permit requirements are not met since it is May.
This step is critical to come up with the correct T required by the JPM standard.
NOTE TO EXAMINER: Allowable range is 11-12°F based on how the applicant rounded the answer. Both of these values are above the NPDES permit requirements for the Apr. 1 - Sep. 30 timeframe.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.2 May 2015 NRC Exam PAGE 6 0F 7 STEP 5 1.3 Determine whether RL Heat Rise (T) Step 1.2.4 is less than limits listed:
RL Heat Rise (T) < 10.0°F (Apr. 1 - Sep. 30)
< 14.0°F (Oct. 1 - Mar. 31)
STANDARD:
Applicant determines that the RL Heat Rise of 11.6°F is > the limit of 10°F required from Apr. 1 through Sep. 30.
COMMENTS:
___ SAT
___ UNSAT STEP 6 1.4 IF the RL Heat Rise (T) is greater than the limits of Step 1.3 (NPDES Permit), notify the Operations Shift Manager that a plant heat load reduction on the RL system is required.
STANDARD:
Applicant determines that this step needs to be performed.
This step is critical to meet the task and JPM standard.
COMMENTS:
END OF TASK CRITICAL STEP
___ SAT
___ UNSAT STOP TIME ________
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Catawba 2015 NRC Exam - Admin. JPM A.2 INITIAL CONDITIONS:
A loss of both Unit 1 and Unit 2 OACs occurred 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.
INITIATING CUES:
The CRS directs you to perform PT/0/A/4250/011 (RL Temperature And Discharge Flow Determination) Enclosure 13.6 (RL System Heat Rise (T) Calculation).
RL discharge flows from Enclosure 13.2 were determined to be the following:
- A train RL discharge flow (RLAF) = 21,355 gpm
- B train RL discharge flow (RLBF) = 24,560 gpm Record below the RL Heat Rise T and whether NPDES permit requirements are met for todays date.
RL Heat Rise T ___________
A Plant heat load reduction is / is NOT required. Circle the correct answer.
Catawba Nuclear Station Admin. JPM A.3 May 2015 NRC Exam PAGE 1 OF 6 JPM A.3 RO / SRO
Catawba Nuclear Station Admin. JPM A.3 May 2015 NRC Exam PAGE 2 OF 6 EVALUATION SHEET Task:
Determine Radiation Protection Requirements for an activity Alternate Path:
N/A Facility JPM #:
2005 Admin JPM R03/SRO4 Modified Safety Function:
N/A K/A G 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
Importance:
3.5 / 3.6 CFR:
41.12 / 45.10 Preferred Evaluation Location:
Preferred Evaluation Method:
Simulator Classroom X
Perform X
Simulate
References:
Radiation Work Permit # 5021, Room 105 (ND Pump 1A) Survey Map Task Standard:
Correctly determine that total dose received for the job is 15 mR and maximum time to complete venting without exceeding RWP dose limits is 0854 hrs.
Validation Time:
14 minutes Time Critical:
Yes No X
Applicant:
Time Start: __________
NAME___________________________
Docket #_______________
Time Finish: __________
Performance Rating:
SAT ____ UNSAT ____
Performance Time _____
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE COMMENTS
Catawba Nuclear Station Admin. JPM A.3 May 2015 NRC Exam PAGE 3 OF 6 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 1 is in AP/1/A/5500/019 (Loss of Residual Heat Removal)
The CRS has dispatched you to 1A ND pump room to vent the 1A ND pump casing when directed.
You are to stage yourself where you can minimize your dose while waiting.
The following is the timeline for the venting evolution:
0800 - You enter room 105 0830 - You are directed to vent using 1ND-88 (1A ND Pump Seal Water Hx Inlet Vent).
0842 - Venting is complete. You immediately exit the room and report back to the Control Room.
INITIATING CUES:
Based on the time line, RWP # 5021, and Room 105 Survey Map provided:
- 1. State the amount of dose that was received for the duration of the task.
Amount of dose received - ________________ mR
- 2. Assuming you entered the room and began venting at the stated times, determine the latest clock time that venting could complete without exceeding a limit imposed by the RWP.
Latest clock time for venting without exceeding the MAXIMUM Dose listed on RWP 5021 - ___________
EXAMINER NOTE: Each applicant should receive a copy of RWP # 5021 and the Room Survey for room 105.
Catawba Nuclear Station Admin. JPM A.3 May 2015 NRC Exam PAGE 4 0F 6 START TIME: _______
STEP 1 Determine dose received for the venting evolution:
Applicant is to stage themselves at the Low Exposure Waiting Area (LEWA) where they wait for 30 minutes (.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)
LEWA dose: 10 mR/hr X.5 hr = 5 mR Venting time is 12 minutes (.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
Area dose: 40 mR/hr X.2 hr = 8 mR Total amount of dose received = 5 mR + 8 mR = 13 mR STANDARD:
Applicant determines the total amount of dose received for the evolution to be 13 mR.
This step is critical to meet the task requirements and standard for this JPM to determine the total amount of dose received.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Catawba Nuclear Station Admin. JPM A.3 May 2015 NRC Exam PAGE 5 0F 6 STEP 2 Determine the latest clock time that venting could complete without exceeding RWP dose requirements:
The RWP limits total exposure to 25 mR 25 mR - 5 mR (LEWA dose) = 20 mR left for venting 20 mR ÷ 40 mR/hr =.5 hr (30 minutes) 0830 + 30 = 0900 STANDARD:
Applicant determines the latest time that venting could complete to meet the RWP dose requirement is 0900.
This step is critical to meet the task requirements and standard for this JPM to determine the latest time that venting could complete without exceeding RWP dose requirements.
COMMENTS:
END OF TASK CRITICAL STEP
___ SAT
___UNSAT STOP TIME ________
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Catawba 2015 NRC Exam - Admin. JPM A.3 INITIAL CONDITIONS:
Unit 1 is in AP/1/A/5500/019 (Loss of Residual Heat Removal)
The CRS has dispatched you to 1A ND pump room to vent the 1A ND pump casing when directed.
You are to stage yourself where you can minimize your dose while waiting.
The following is the timeline for the venting evolution:
0800 - You enter room 105 0830 - You are directed to vent using 1ND-88 (1A ND Pump Seal Water Hx Inlet Vent).
0842 - Venting is complete. You immediately exit the room and report back to the Control Room.
INITIATING CUES:
Based on the time line, RWP # 5021, and Room 105 Survey Map provided:
- 1. State the amount of dose that was received for the duration of the task.
Amount of dose received - ________________ mR
- 2. Assuming you entered the room and began venting at the stated times, determine the latest clock time that venting could complete without exceeding a limit imposed by the RWP.
Latest clock time for venting without exceeding the MAXIMUM Dose listed on RWP 5021 - ___________
Catawba Nuclear Station Admin. JPM A.4 May 2015 NRC Exam PAGE 1 OF 6 JPM A.4 SRO
Catawba Nuclear Station Admin. JPM A.4 May 2015 NRC Exam PAGE 2 OF 6 EVALUATION SHEET Task:
Determine Reporting Per RP/0/B/5000/013 (NRC Notification Requirements)
Alternate Path:
N/A Facility JPM #:
SEP-025 Safety Function:
N/A K/A G 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.
Importance:
2.7 / 4.5 CFR:
41.10 / 43.5 / 45.11 Preferred Evaluation Location:
Preferred Evaluation Method:
Simulator Classroom X
Perform X
Simulate
References:
RP/0/B/5000/013 (NRC Notification Requirements) rev 37 Task Standard:
Determines that 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notifications are required per parts 10CFR50.72(b)(2)(xi) and 10CFR50.72(b)(3)(xii) respectively.
Validation Time:
10 minutes Time Critical:
Yes No X
Applicant:
Time Start: __________
NAME___________________________
Docket #_______________
Time Finish: __________
Performance Rating:
SAT ____ UNSAT ____
Performance Time _____
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE COMMENTS
Catawba Nuclear Station Admin. JPM A.4 May 2015 NRC Exam PAGE 3 OF 6 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
A vendor was performing work activities in the S/G bowl area during No Mode.
The latest RP survey of the S/G bowl area indicated removable surface contamination was 42,000 dpm/100 square cm.
The vendor was overcome with heat exhaustion and fell into the S/G bowl area.
The fall caused a compound fracture on his right leg that pierced his bubble suit.
Due to congested conditions and other delays in lifesaving activities, the injured individual received an estimated exposure of 16 Rem.
Due to the nature of his injury, he was immediately transferred via ambulance to Piedmont Medical Center.
A news van is parked at the access road and site personnel are preparing a press release for immediate delivery to the media.
INITIATING CUES:
You are the CRS. Determine ALL applicable NRC notifications of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less. Record your answers on the attached page.
Catawba Nuclear Station Admin. JPM A.4 May 2015 NRC Exam PAGE 4 0F 6 START TIME: _______
STEP 1 Determine the appropriate NRC notifications from the following sources:
- Enclosure 4.1, Events Requiring Immediate NRC Notification
- Enclosure 4.2, Events Requiring 1-Hour NRC Notification
- Enclosure 4.3, Events Requiring 4-Hour NRC Notification
- Enclosure 4.4, Events Requiring 8-Hour NRC Notification
- Enclosure 4.5, Events Requiring 24-Hour NRC Notification
- Enclosure 4.6, Events Requiring 30 Day NRC Notification
- Enclosure 4.7, Events Requiring 60 Day NRC Notification
- Enclosure 4.8, List of System (ESF) Actuations for Catawba
- AD-LS-ALL-006, Notification/Reportability Evaluation STANDARD:
Both of the following notifications are required and critical items:
4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification
- 10CFR50.72(b)(2)(xi) Offsite Notification (News Release)
Any event or situation related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an on-site fatality, transport of an injured or ill employee to a hospital by ambulance, or an inadvertent release of radioactively contaminated materials.
8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification
- 10CFR50.72(b)(3)(xii) Offsite Medical (Contaminated Injury)
Any event requiring the transport of a radioactively contaminated person to an off-site medical facility for treatment.
This step is critical to meet the task requirements and standard for this JPM to determine all applicable NRC notifications of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less COMMENTS:
END OF TASK CRITICAL STEP
___ SAT
___ UNSAT STOP TIME ________
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Catawba 2015 NRC Exam - Admin. JPM A.4 INITIAL CONDITIONS:
A vendor was performing work activities in the S/G bowl area during No Mode.
The latest RP survey of the S/G bowl area indicated removable surface contamination was 42,000 dpm/100 square cm.
The vendor was overcome with heat exhaustion and fell into the S/G bowl area.
The fall caused a compound fracture on his right leg that pierced his bubble suit.
Due to congested conditions and other delays in lifesaving activities, the injured individual received an estimated exposure of 16 Rem.
Due to the nature of his injury, he was immediately transferred via ambulance to Piedmont Medical Center.
A news van is parked at the access road and site personnel are preparing a press release for immediate delivery to the media.
INITIATING CUES:
You are the CRS. Determine ALL applicable NRC notifications of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less. Record your answers on the attached page.
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Catawba 2015 NRC Exam - Admin. JPM A.4 CANDIDATE NAME: __________________________________
IMMEDIATE NOTIFICATION(S) 1 HOUR NOTIFICATION(S) 4 HOUR NOTIFICATION(S) 8 HOUR NOTIFICATION(S) 24 HOUR NOTIFICATION(S)