ML111570047
| ML111570047 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/02/2011 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| 50-413/10-301, 50-414/10-301 50-413/10-301, 50-414/10-301 | |
| Download: ML111570047 (94) | |
Text
Catawba Nuclear Station Adm+n JPM AROISRO Dec. 2010 NRC Exam Admin JPM A Perform A Shutdown Margin Calculation With Xenon Credit In Mode 3 PA1 I flP IR
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam EVALUATION SHEET Task: Perform a Shutdown margin calculation in Mode 3 with Xenon Credit Alternate Path: None.
Facility JPM #: RB-i 06 Safety Function: I
Title:
KIA 004 A4.04 Ability to manually operate and/or monitor in the control room:
Calculation of boron concentration changes.
Rating(s): 3.2 I 3.6 CFR: 41.7 I 45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator Room X Perform X Simulate
References:
OP/0/N6100/006 (Reactivity Balance Calculation) End. 4.6 and 4.9 Task Standard: Perform a manual shutdown margin calculation (with Xenon credit) and properly determine when the shutdown margin will be lost.
Validation Time: 15 minutes Time Critical: Yes No X Applicant: Time Start:
NAME Docket # Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: I NAME SIGNATURE DATE COMMENTS PA( 9 (W 1
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam 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:
- 1. Unit I was shutdown October 8 2010 at 0130 from 100% power after a 20 day continuous run.
- 2. Current date: October 8, 2010 Time: 0430
- 3. There are no inoperable rods.
- 4. NC Tavg = 557°F, NC boron from last sample = 1225 ppm, Core Life = 25 EFPD, difference from equilibrium Samarium worth = 19.6 PCM
- 5. Duty reactor engineer reports current Iodine concentration is 6094.2 atm/cc and current Xenon concentration is 4280.4 atm/cc.
INITIATING CUES:
I. The CRS has instructed you to perform a Shutdown Margin Calculation per OP/0/A16100/006 (Reactivity Balance Calculation) End. 4.6 to maintain current NC system temperature and pressure.
- 2. The CRS instructs you to determine using provided Xenon predict, when shutdown margin will be lost.
- The REACTBAL computer program is out of service.
- Independent Verification has been waived.
EXAMINER NOTE: After reading cue, provide applicant with current ROD book, Xenon predict printout, and a copy of OP/0/A161001006.
PA(.F flIt IR
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam START TIME:
STEP 1: 2.1 IF using effective boron concentration, ensure latest NC SAT system boron sample has been entered into the OAC.
UNSAT STANDARD:
Applicant determine step is N/A. .
COMMENTS:
STEP 2: 3.1 Determine the following information: CRITICAL 3.1.1 Unit (1) STEP 3.1.2 Date/Time (1018110 0430) 3.1.3 Present NC System Boron Conc Minus 50 ppm SAT OR Effective Boron Concentration (1175 ppm) UNSAT STANDARD:
Applicant fills in above information.
Step is critical, since an incorrect entry will affect the calculated value forSDM COMMENTS:
PAGE 4 OF 18
Catawba Nuclear Static>n Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 3: 3.2 IF NC System Boron Concentration the Refueling SAT Operations Boron Concentration per the COLR, Section 2.15, then Shutdown Margin is met and perform the UNSAT following:
STANDARD:
Applicant determines that this step is N/A.
COMMENTS:
PAGE 5 OF 18
Catawba Nuclear Station Admin JPM A RO/SRO Dec. 2010 NRC Exam STEP 4: 3.3 Determine the following information: CRITICAL 3.3.1 Present NC System Temperature 557°F STEP 3.3.2 Desired NC System Temperature 557°F SAT 3.3.3 Present cycle burnup 25 EFPD UNSAT 3.3.4 Present Difference from Equilibrium Samarium Worth (+) 19.6 pcm 3.3.5 Number of Known Untrippable Control Rods 0 3.3.6 Untrippable RCCA Core Locations NIA 3.3.7 Date and time of latest valid Iodine and Xenon concentrations; 10/8/10 0430 3.3.8 Iodine concentration at time listed in Step 3.3.7; 0 if xenon free. 6094.2 atm/cc 3.3.9 Xenon concentration at time listed in Step 3.3.7; 0 if xenon free. 4280.4 atmlcc 3.3.10 Shutdown Fission Product Correction Factor 3 ppm (This value is from performing End. 4.9)
STANDARD:
Applicant records information given in cue in spaces provided The Shutdown fission product correction factor is obtained by performing the first step of Enclosure 4 9 Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
PAGE 6 OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 5: End. 4.9 (3.1) IF the Unit operated for> 3 EFPD from the CRITICAL previous shutdown to the current shutdown, STEP determine the Shutdown Fission Product Correction Factor as follows: SAT A. Date/Time of current Unit Trip or Shutdown: UNSAT 1018110 0130 B. Current Date/Time or projected time used in the appropriate calculation:
1018110 0430 C. Duration of Shutdown 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> D. Shutdown Fission Product Correction Factor(using duration from 3.1.C) 3 ppm STANDARD:
Applicant determines that the Shutdown fission product correction factor j 3 ppm per ROD Mnual section 51.3.
Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
PAGE 7 OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 6: 3.4 Select the highest boron concentration for the T-AVGs CRITICAL between the range of Step 3.3.1 (Present NC System STEP Temperature) and Step 3.3.2 (Desired NC System Temperature) at current cycle burnup (Step 3.3.3) in Section SAT 5.11 of the R.O.D. manual. {PIP 0-C99-0318}
1428 ppm UNSAT STANDARD:
Applicant determines required boron concentration of 1428 ppm for 1300 pcm shutdown margin from sectIon 5.11 of the ROD M anual.
Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
STEP 7: 3.5 Calculate additional boron concentration penalties: CRITICAL 3.5.1 Calculate untrippable RCCA penalty: STEP A. Number of Untrippable RCCA(s) NOT fully Inserted 2 SAT B. Boron Penalty per Untrippable rod UNSAT Untrippable RCCA Penalty (A) X (B) = 0 ppm STANDARD:
Applicant determines Untrippable RCCA Penalty to be 0 ppm Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
PAGE 8 OF 18
Catawba Nuclear Stathm Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 8: 3.5.2 IF physics testing is NOT complete enter Zero Power CRITICAL Physics Testing penalty of 100 ppm, otherwise, enter 0 STEP ppm. 0 ppm SAT STANDARD:
UNSAT Applicant determines that physics testing has already been completed during original startup and enters a 0 ppm penalty Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
STEP 9: 3.5.3 Enter Shutdown Fission Product Correction Factor from CRITICAL Step 3.3.10. 3 ppm STEP STANDARD: SAT Applicant records value of 3 ppm from step 3.3.10, UNSAT Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
PAGE 9 OF 18
Catawba*NucIear Station AdminJPMARO/SRO Dec. 2010 NRC Exam STEP 10: 3.5.4 Calculate total additional boron concentration penalty: CRITICAL A. Untrippable RCCA Penalty 0 ppm STEP B. Additional Boron Conc Penalty for ZPPT 0 ppm SAT C. Shutdown Fission Product Correction Factor 3 ppm UNSAT Total Boron Penalty 3 ppm STANDARD:
Applicant determines Total Boron Penalty to be 3 ppm Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
PAGE 10 OF 18
Catawba Nuclear Station Adm1nJPMAROISRO Dec. 2010 NRC Exam STEP 11: 3.6 Calculate total required boron concentration for SDM: CRITICAL A. Required SDM Boron 1428 ppm STEP B. Total Boron Penalty 3 ppm SAT Total Required Boron Concentration for SDM (Xenon UNSAT Free) (A) + (B) = 1431 ppm STANDARD:
Applicant determines Total Required Boron Concentration for Xenon free shutdown margin to be 1431 ppm.
Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
PAGE 11 OF 18
Catawba *NicIear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 12: 3.7 Determine the Boron Difference between Required Boron CRITICAL Concentration for SDM and current NC System boron STEP concentration.
SAT A. Total Required Boron Concentration for SDM 1431 ppm UNSAT B. Present NC System Boron Concentration Minus 50 ppm OR Effective Boron Conc 1175 ppm Boron Difference (A) (B)
- = 1+) 256 ppm STANDARD:
Applicant determines that the Boron difference will be a positive 256 ppm.
Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
STEP 13: 3.7.1 IF the Boron Difference determined in Step 3.7 is SAT negative, SDM is maintained for Xenon free conditions.
UNSAT STANDARD:
Applicant determines that this step is N/A.
COMMENTS:
PAGE 12 OF 18
Catawba. NuclearStation Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 14: 3.7.2 IF the Boron Difference determined in Step 3.7 is positive SAT AND Xenon credit is NOT being used, NCS boration is required to maintain SDM. UNSAT STANDARD:
Applicant determines that this step is N/A.
COMMENTS:
STEP 15: 3.8 IF the Boron Difference determined in Step 3.7 is positive CRITICAL AND Xenon credit is being used, determine the Xenon STEP Credit as follows:
SAT 3.8.1 Determine the ARI, Differential Boron Worth at lower T-AVG of Step 3.3.1 or 3.3.2 AND cycle burnup of UNSAT Step 3.3.3 from Section 5.3 of the R.O.D.manual.
6.61 pcmlppm STANDARD:
Applicant determines the Differential Boron Worth to be 6.61 pcm/ppm*
from section 5.3 of the ROD manual.
Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
PAGE 13 OF 18
- Catawba -Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 16: 3.8.2 Calculate the reactivity worth of the boron difference: CRITICAL A. Boron Difference 256 ppm STEP B. ARI Differential Boron Worth 6.61 pcm/ppm SAT Reactivity Worth of Boron Difference (A) X (B) = UNSAT 1692.16 pcm STANDARD:
Applicant determines Reactivity Worth of Boron Difference to be 169216 porn .A range o 1692 +/- 1 porn is acceptable. .
Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
PAGE 14 OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 17: 3.8.3 Calculate the xenon worth that is required to ensure SDM CRITICAL at the present NC System boron. STEP 3.8.3.1 IF the desired T-AVG from Step 3.3.2 is > 500°F, SAT calculate the Xenon Worth as follows:
UNSAT A. Reactivity Worth 1692.16 pcm B. Difference from Eq Sm Worth (+) 19.6 pcm Xenon Worth {(A) (B)) ÷ 0.85
- = 1967.71 pcm STANDARD:
Applicant determines Xenon Worth requIred to maintain shutdown margin at the present NC system Boron concentration to be 196711 pcm. 1968 +/- I pcm is acceptable.
Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
STEP 18: 3.8.3.3 Predict Xenon for approximately two days into the SAT future using OAC Xenon Predict Program or REACT program and data from steps 3.1 and 3.3. UNSAT STANDARD:
Applicant was provided with a Xenon predict with initiating cue.
COMMENTS:
PAGE 15 OF 18
Catawba Nuclear Station Admin JPM A RO/SRO Dec. 2010 NRC Exam STEP 19: 3.8.3.4 Record the last Date/Time from the xenon predict of CRITICAL Step 3.8.3.3 that is greater than the xenon worth of STEP Step 3.8.3.1 or step 3.8.3.2 in the following step.
SAT 3.8.3.5 Loss of SDM Date/Time 10/9/10 0410 UNSAT STANDARD:
Applicant determines from Xenon predict provided that shutdown margin will be lost on 10/9/10 at 0410.
Step is critical to determine the exact time that shutdown margin will be lost.
COMMENTS:
STEP 20: 3.9 Sign below to document performance. SAT Performed by: Date/Time: /
UNSAT STANDARD:
Applicant signs and dates the performance of this enclosure COMMENTS:
PAGE 16 OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 21: 3.10 Ensure that an independent calculation per this enclosure SAT has been separately performed.
UNSAT STANDARD:
Applicant determines that this step is not needed per initiating cue.
COMMENTS:
END OF TASK STOP TIME PAGE 17 OF 18
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
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:
- 1. Unit I was shutdown October 8 2010 at 0130 from 100% power after a 20 day continuous run.
- 2. Current date: October 8, 2010 Time: 0430
- 3. There are no inoperable rods.
- 4. NC Tavg = 557°F, NC boron from last sample = 1225 ppm, Core Life = 25 EFPD, difference from equilibrium Samarium worth = 19.6 PCM
- 5. Duty reactor engineer reports current Iodine concentration is 6094.2 atm/cc and current Xenon concentration is 4280.4 atm!cc.
INITIATING CUES:
- 1. The CRS has instructed you to perform a Shutdown Margin Calculation per OPIO/A161001006 (Reactivity Balance Calculation) End. 4.6 to maintain current NC system temperature and pressure.
- 2. The CRS instructs you to determine using provided Xenon predict, when shutdown margin will be lost.
- The REACTBAL computer program is out of service.
- Independent Verification has been waived.
Catawba Nuclear Station RO Admiri JPM B Dec. 2010 NRC Exam RO Admin JPM B Determine License Status PA(P I (W c
Catawba Nuclear Station
- RQAdm1nJPMB Dec. 2010 NRC Exam EVALUATION SHEET Task: Determine License Status Active / Inactive Alternate Path: None.
Facility JPM #: None.
Safety Function:
Title:
KIA 2.1.1 Knowledge of conduct of operations requirements Rating(s): 3.8 / 4.2 CFR: 41.10 /45.13 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator Room X Perform X Simulate
References:
NSD 512 Maintenance of RO/SRO Licenses Task Standard: Applicant determines the correct status of each of the three Reactor Operator licenses. Operator A and C are active, Operator B is inactive.
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 PAtI 9 flP R
Catawba Nuclear Station
-ROAdrninJPMB Dec. 2010 NRC Exam 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:
- 1. Three Reactor Operators have the following history:
- 2. All three have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.
- 3. None of the 3 has worked any shift since 12/01/10.
- 4. Active/Inactive status and time on shift since October 1, 2010 is as follows for each of the Reactor Operators:
Operator A License was active on October 1, 2010.
10/02/10 Worked 0700-1 900 shift as Unit I OATC.
10/03/10 Worked 0700-1 900 shift as Unit 1 OATC.
10/04/10 Worked 0700-1 900 shift as Containment Closure Coordinator.
10/05/10 Worked 0700-1 900 shift as Unit I BOP.
10/06/10 Worked 0700-1 900 shift as Unit I BOP.
11/14/10 Worked 1900-0700 shift as Unit 1 OATC.
11/17/10 Worked 1900-0700 shift as Containment Closure Coordinator.
Operator B License was active on October 1, 2010.
10/01/10 Worked 0700-1 900 shift as Unit 1 OATC 10/02/10 Worked 0700-1 900 shift in the Tagging Office 10/03/10 Worked 0700-1 900 shift as Containment Closure Coordinator.
10/05/10 Worked 0700-1 900 shift as Unit 1 OATC.
10/14/10 Worked 1900-0700 shift as Unit I OATC.
11/02/10 Worked 0700-1900 shift in the Tagging Office.
License was inactive on October 1, 2010.
10/5/10 thru 10/09/10 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit I OAC and completed all requirements for license reactivation.
11/12/10 Worked 0700-1900 shift as Unit 1 OATC.
11/13/10 Worked 0700-1900 shift as Unit I OATC.
11/15/10 Worked 0700-1 900 shift as Unit I OATC.
11/16/10 Worked 1900-0700 shift as Unit I OATC.
11/21/10 Worked 1900-0700 shift as Unit I OATC.
n1
Catawba Nuclear Station ROAdminJPMB Dec. 2010 NRC Exam INITIATING CUES:
- 1. You are to determine if each of the Reactor Operators is eligible to work the Unit I OATC position on the 0700 1900 shift on January 31, 2011. Record your answer in the blanks below (yes or no).
Operator A Operator B Operator C 4 (M R
Catawba Nuclear Station RO Admin JPM B Dec. 2010 NRC Exam START TIME:
STEP 1: Determine the Active I Inactive status of Operator A license. CRITICAL STEP STANDARD: SAT Candidate determines the license is Active because the operator UNSAT worked the required 5 complete twelve hour shifts in a qualifying license position during the previous quarter.
This step is critical to ensure that the individual is qualified to stand license duties in the control room.
COMMENTS:
STEP 2: Determine the Active I Inactive status of Operator B license. CRITICAL STEP STANDARD: SAT Candidate determines the license is Inactive because the operator did UNSAT not work the required 5 complete twelve hour shifts in a qualifying license position during the previous quarter.
This step is critical to preclude a non qualified individual from fulfilling license duties in the control room.
COMMENTS:
PAGE 5 OF 8
Catawba Nuclear Station RO Admin JPM B Dec. 2010 NRC Exam STEP 3: Determine the Active I Inactive status of Operator C license. CRITICAL STEP STANDARD:
SAT Candidate determines the license is Active because the license was reactivated in the previous quarter and that the required 5 complete UNSAT twelve hour shifts in a qualifying license position during the quarter have also been completed.
This step is critical to ensure that the individual is qualified to stand license duties in the control room.
COMMENTS:
END OF TASK STOP TIME PAGE 6 OF 8
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
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:
- 1. Three Reactor Operators have the following history:
- 2. All three have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.
- 3. None of the 3 has worked any shift since 12/01/09.
- 4. Active/Inactive status and time on shift since October 1, 2010 is as follows for each of the Reactor Operators:
Operator A License was active on October 1, 2010.
10/02/10 Worked 0700-1 900 shift as Unit 1 OATC.
10/03/10 Worked 0700-1 900 shift as Unit 1 OATC.
10/04/10 Worked 0700-1900 shift as Containment Closure Coordinator.
10/05/10 Worked 0700-1 900 shift as Unit 1 BOP.
10/06/10 Worked 0700-1 900 shift as Unit 1 BOP.
11/14/10 Worked 1900-0700 shift as Unit 1 OATC.
11/17/10 Worked 1900-0700 shift as Containment Closure Coordinator.
Operator B License was active on October 1, 2010.
10/01/10 Worked 0700-1 900 shift as Unit 1 OATC.
10/02/10 Worked 0700-1 900 shift in the Tagging Office.
10/03/10 Worked 0700-1 900 shift as Containment Closure Coordinator.
10/05/10 Worked 0700-1 900 shift as Unit I OATC.
10/14/10 Worked 1900-0700 shift as Unit I OATC.
11/02/10 Worked 0700-1900 shift in the Tagging Office.
Operator C License was inactive on October 1, 2010.
10/5/10 thru 10/09/10 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit 1 OAC and completed all requirements for license reactivation.
11/12/10 Worked 0700-1 900 shift as Unit 1 OATC.
11/13/10 Worked 0700-1 900 shift as Unit I OATC.
11/15/10 Worked 0700-1 900 shift as Unit I OATC.
11/16/10 Worked 1900-0700 shift as Unit 1 OATC.
11/21/10 Worked 1900-0700 shift as Unit 1 OATC.
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIATING CUES:
- 1. You are to determine if each of the Reactor Operators is eligible to work the Unit I OATC position on the 0700 -1900 shift on January 31, 2011. Record your answer in the blanks below (yes or no).
Operator A Operator B Operator C
Catawba Nuclear Station ROAdrriInJPMC Dec. 2010 NRC Exam Admin JPM C Perform A Manual NC Leakage Detection Calculation Per PT111A146001009 (Loss Of Operator Aid Computer)
PAt I (ThP
Catawba Nuclear Station ROAdminJPMC Dec. 2010 NRC Exam EVALUATION SHEET Task: Perform a Manual NC Leakage Calculation per PT/l/A146001009 (Loss of Operator Aid Computer)
Alternate Path: None.
Facility JPM #: NC-095 Safety Function:
Title:
Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
KIA 2.2.42 Rating(s): 3.9 / 4.6 CFR: 41.7 /41.10 /43.2 / 43.3 /
45.3 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator Room X Perform X Simulate
References:
PT/1/N4600/009 End. 13.5 and T.S. 3.4.13 Task Standard: Applicant determines NC system leakage to be 1.05 GPM.
Validation Time: 10 Time Critical: Yes No X Applicant: Time Start:
NAME Docket # Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS PAt 9 fl1 R
atawba Nuclear Station RO Admin JPM C Dec. 2010 NRC Exam 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:
- 1. The OAC has been out of service for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
INITIATING CUES:
- 1. You have been directed to perform Enclosure 13.5 of PT111A146001009 (Loss of Operator Aid Computer) steps 1.3 through 1.6 to determine input to the Containment Floor and Equipment Sump.
- 2. CFES Sump levels at 0800:
1WLP5740 6.2 inches 1WLP5750 7.1 inches
- 3. CFES Sump levels at 0900:
1WLP5740 6.9 inches 1WLP5750 7.6 inches CFES input GPM.
PAGE 3 OF 6
Catawba Nuclear Station ROAdminJPMC Dec. 2010 NRC Exam START TIME:
STEP 1: 1.3 Record initial sump readings on the Containment Floor and SAT Equipment Sump Inleakage Rate Log Sheet.
UNSAT STANDARD:
Applicant records intial Containment Floor and Equipment sump level values on EncL 13.5 page 3 of 4.
COMMENTS:
STEP 2: 1.4 Once per hour, record sump level readings on the SAT Containment Floor and Equipment Sump lnleakage Rate Log Sheet. UNSAT STANDARD:
Applicant records current Containment Floor and Equipment sump level values on End. 13.5 page 3 of 4.
COMMENTS:
PAGE4OF6
Catawba Nuclear Station RO Admin JPM C Dec. 2010 NRC Exam STEP 3: 1.5 Calculate the leakage rate using the Sump Volume vs. CRITICAL Level Indication Table. STEP STANDARD: SAT (Sump A Gals.(T2) Sump A Gals.(Tl)) + (Sump B Gals.(T2) Sump B Gals. (TI)) UNSAT (Time at T2 Time at TI)
(280.1 243.3) + (317.1 290.7) 60 mm.
Applicant determines the NC system ieakrate is 1 05 GPM (+/- 01 GPM)
This step is critical to verify that a limit for unidentified leakage has been exceeded.
COMMENTS:
STEP 4: 1.6 Verify leakage is < 1 gpm. CRITICAL STEP STANDARD:
SAT Applicant determines leakage Is> 1 GPM UNSAT This step is critical to verify that a limit for unidentified leakage has been exceeded.
COMMENTS:
END OF TASK STOP TIME PAGE 5 OF 6
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
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:
- 1. The OAC has been out of service for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
INITIATING CUES:
- 1. You have been directed to perform Enclosure 13.5 of PT!11A146001009 (Loss of Operator Aid Computer) steps 1.3 through 1.6 to determine input to the Containment Floor and Equipment Sum p.
- 2. CFES Sump levels at 0800:
1WLP5740 6.2 inches 1WLP5750 7.1 inches
- 3. CFES Sump levels at 0900:
1WLP5740 6.9 inches 1WLP5750 7.6 inches CFES input GPM.
Catawba Nuclear Station RGAdmin JPM E Dec. 2010 NRC Exam RO Admin JPM E Perform Emergency Plan Requirements For A Site Fire Emergency PA( I flP 19
Catawba Nuclear Station ROAdminJPM E Dec. 2010 NRC Exam EVALUATION SHEET Task: Perform emergency plan requirements for a site fire emergency.
Alternate Path: None.
Facility JPM #: 2004 NRC initial license examination NRC-RO-3/Admin.
Safety Function:
Title:
KIA 2.4.43 Knowledge of emergency communication systems and techniques.
Rating(s): 3.2 I 3.8 CFR: 41.10 I 45.13 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
RP101B150001029 (Fire Brigade Response)
Task Standard: Applicant completes the immediate action steps of RP/0/B/5000/029 enclosure 3.1 steps 1.1 through 1.5 to activate a fire brigade response.
Validation Time: 10 minutes Time Critical: Yes No X Applicant: Time Start:
NAME Docket # Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: I NAME SIGNATURE DATE COMMENTS PA(F 9 flP 19
Catawba Nuclear Station
- ROAdminJPME Dec. 2010 NRC Exam 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:
- 1. Unit I is at 100% power.
INITIATING CUES:
- 1. You are the Unit I BOP.
- 2. The OATC is monitoring the control boards.
- 3. Monitor the plant.
PAt flP 19
Catawba Nuclear Station RO Admin JPM E Dec. 2010 NRC Exam BOOTH OPERATOR INSTRUCTION Call applicant on the 4911 phone and report This is J 00 Smith with Maintenance.
There is a fire in warehouse # 2.
Provide Applicant with the following information when asked:
Name: Joe Smith Work group: Maintenance.
Location: Warehouse # 2 Smoke and flames visible: Yes.
Equipment!components affected: Contents in the warehouse.
Any injured or missing people: No.
Any people in the immediate area that need to be relocated to a safer area: No.
Callback number: 5562 EXAMINER CUE: After applicant finishes recording information, state to applicant:
I understand, there is a fire. I will implement AP145, Plant Fire. I need you to perform the immediate actions 1.1 through 1.5 of RPIOIBI5000!029, Fire Brigade Response.
EXAMINER NOTE: Provide applicant with a copy of RP101B150001029 (Fire Brigade Response.)
PAGE4OF 12
Catawba NucIearStatiGn RO Admin JPM E Dec. 2010 NRC Exam START TIME:
STEP 1: 1.1 Record the following information taken from the caller: CRITICAL STEP
- Name/group of person reporting fire: Joe Smith, Maint.
- Location of fire: Warehouse # 2 SAT
- Are smoke and flames visible? Yes
- Equipment/components affected Contents in warehouse UNSAT
- Are there any injured/missing people? No How Many?
- Are there people in the immediate area who need to be relocated to a safer area? No
- Call back number: 5562
- Time of call: Todays date and time STANDARD:
Applicant records correct information in the blanks provided This step is critical to ensure proper information is given to the fire brigade for response to the fire, and to be able to contact the person making the call if needed.
COMMENTS:
PAGE 5 OF 12
-Catawba Nuclear Station ROAdm1nJPME Dec. 2010 NRC Exam STEP 2: 1.2 IF flames or smoke and sensed heat are reported, perform SAT the following:
UNSAT
- Dispatch the Fire Brigade. Refer to Enclosure 3.3.
- Concurrently implement AP101A155001045 (Plant Fire).
STANDARD:
Applicant determines from cue that this step does apply and refers to enclosure 3.3.
EXAMINER CUE: If asked, CRS is implementing AP1045.
COMMENTS:
PAGE 6 OF 12
Catawba Nuclear Staticrn RO Admin JPM E Dec. 2010 NRC Exam STEP 3: End. 3.3 1. Begin Fire Brigade Response activation by CRITICAL selecting one of the following: STEP 1.1 Ensure confirmation pagers are turned on. SAT 1.2 Fire Brigade activation for Actual Fire Emergency, go to Step 2. UNSAT 1.3 Fire Brigade activation for On-Shift Fire Brigade Drill, go to Step 3.
1.4 Fire Brigade activation for ERO Drill Fire Brigade Activation, go to Step 4.
STANDARD:
Applicant will ensure confirmation pagers are turned on and goes to step 2 . ... . .. . .
EXAMINER CUE: Confirmation pagers are turned on.
This step is critical to ensure that the page sent out to the fire brigade is correct and timely.
COMMENTS:
PAGE 7 OF 12
Catawba Nuclear Station RO Admin JPM E Dec. 2010 NRC Exam STEP 4: 2. Fire Brigade Response Activation for Actual Fire SAT Emergency 2.1 Activate Fire Brigade Pagers using EROpage link. UNSAT EXAMINER CUE: The DAE is not available at this time.
2.2 IF the DAE is not available, immediately go to step 2.4.
STANDARD:
Applicant determines from cue that the DAE is not available and immediatelygoes to step 2.4. .
COMMENTS:
STEP 5: 2.4 Activate Fire Brigade Pagers using Quiktel Key Pad SAT 2.4.1 IF the Quiktel key pads are not available, the Site UNSAT Public Address System shall be used to initiate a Fire Brigade response STANDARD:
Appilcant determines that. step 2.4.1 is N/A.
COMMENTS:
PAGE 8 OF 12
- Catawba Nuclear Station RO Admin JPM E Dec. 2010 NRC Exam STEP 6: 2.4.2 Activate the Fire Brigade Pagers at a Quiktel key pad as CRITICAL follows: STEP A. Press the <EXIT> key to assure key pad is cleared. SAT B. Type Fire. UNSAT C. Press <ENTER> key.
D. Press <M> key (for Message).
E. Type the following message:
Fire Brigade Emergency at Warehouse # 2 (location). Fire Brigade, please respond.
F. Press <ENTER> key.
G. Monitor the confirmation pager located at the Quiktel key pad to verify proper pager activation.
STANDARD:
Applicant performs step 2.4.2 as written and then proceeds back to enclosure 3.1 to finish the immediate actions.
EXAMINER CUE: Confirmation pagers read the sent fire brigade message.
This step is critical to ensure that the fire brigade receives the correct location of the fire to aid in response.
COMMENTS:
PAGE 9 OF 12
Catawba Nuclear Station -
RO Admin JPM E Dec. 2010 NRC Exam STEP 7: 1.3 IF a Fire Brigade response is NOT needed and no flames or SAT smoke have been reported, complete procedure steps 2.10 and 2.11 and exitprocedure UNSAT STANDARD:
Applicant determines that this step is N/A.
COMMENTS:
STEP 8: 1.4 Announce the following over the PA system: CRITICAL STEP Attention Fire Brigade members. Attention Fire Brigade members. This is the Control Room. A fire has been SAT reported at (give location/elev., etc.) All Fire Brigade members please respond. All other plant personnel please UNSAT stay clear of the area until further notice.
STANDARD:
Applicant describes making the announcement over the PA system This step is critical to ensure plant personnel are aware of the fire.
COMMENTS:
PAGE 10 OF 12
Catawba Nuclear Station RO Admin JPM E Dec. 2010 NRC Exam STEP 9: 1.5 Announce the following on the Fire Brigade radio, channel 1: CRITICAL STEP Catawba Control Room to all units clear channel I for emergency use. SAT STANDARD: UNSAT Applicant describes making Fire Brigade radio announcement EXAMINER CUE: Fire Brigade radio announcement has been made.
Another operator will perform the rest of Enclosure 3.1.
This step is critical to ensure that fire brigade communications are not precluded or interrupted.
COMMENTS:
END OF TASK STOP TIME PAGE lICE 12
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
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:
- 1. Unit I is at 100% power.
INITIATING CUES:
I. You are the Unit I BOP.
- 2. The OATC is monitoring the control boards.
- 3. Monitor the plant.
Catawba Nuclear Station AdniirrJPM A ROISRO Dec. 2010 NRC Exam Admin JPM A Perform A Shutdown Margin Calculation With Xenon Credit In Mode 3 PAtIZ I flP IR
Catawba Nuclear Station Adm1nJPMARO!SRO Dec. 2010 NRC Exam EVALUATION SHEET Task: Perform a Shutdown margin calculation in Mode 3 with Xenon Credit Alternate Path: None.
Facility JPM #: RB-I 06 Safety Function: I
Title:
KIA 004 A4.04 Ability to manually operate and/or monitor in the control room:
Calculation of boron concentration changes.
Rating(s): 3.2 / 3.6 CFR: 41.7 / 45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator Room X Perform X Simulate
References:
OP/0/A16100/006 (Reactivity Balance Calculation) End. 4.6 and 4.9 Task Standard: Perform a manual shutdown margin calculation (with Xenon credit) and properly determine when the shutdown margin will be lost.
Validation Time: 15 minutes Time Critical: Yes No X Applicant: Time Start:
NAME Docket # Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: I NAME SIGNATURE DATE COM ME NTS 9 flFZ IR
Catawba Nuclear Station AdminJPMAROISRO Dec. 2010 NRC Exam 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:
- 1. Unit I was shutdown October 8 2010 at 0130 from 100% power after a 20 day continuous run.
- 2. Current date: October 8, 2010 Time: 0430
- 3. There are no inoperable rods.
- 4. NC Tavg = 557°F, NC boron from last sample = 1225 ppm, Core Life = 25 EFPD, difference from equilibrium Samarium worth = 19.6 PCM
- 5. Duty reactor engineer reports current Iodine concentration is 6094.2 atm/cc and current Xenon concentration is 4280.4 atm/cc.
INITIATING CUES:
- 1. The CRS has instructed you to perform a Shutdown Margin Calculation per OPIOIAI6IOO/006 (Reactivity Balance Calculation) End. 4.6 to maintain current NC system temperature and pressure.
- 2. The CRS instructs you to determine using provided Xenon predict, when shutdown margin will be lost.
- The REACTBAL computer program is out of service.
- Independent Verification has been waived.
EXAMINER NOTE: After reading cue, provide applicant with current ROD book, Xenon predict printout, and a copy of OP/OIA/6100/006.
PA( fl1 IR
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam START TIME:
STEP 1: 2.1 IF using effective boron concentration, ensure latest NC SAT system boron sample has been entered into the OAC.
UNSAT STANDARD:
Applicant determines this step is N/A COMMENTS:
STEP 2: 3.1 Determine the following information: CRITICAL 3.1.1 Unit (1) STEP 3.1.2 Date/Time (1018/10 0430) 3.1.3 Present NC System Boron Conc Minus 50 ppm SAT OR Effective Boron Concentration (1175 ppm) UNSAT STANDARD:
Applicant fills in above information.
Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
PAGE4OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 3: 3.2 IF NC System Boron Concentration the Refueling SAT Operations Boron Concentration per the COLR, Section 2.15, then Shutdown Margin is met and perform the UNSAT following:
STANDARD:
Applicant determines that this step is N/A.
COMMENTS:
PAGE 5 OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 4: 3.3 Determine the following information: CRITICAL 3.3.1 Present NC System Temperature 557°F STEP 3.3.2 Desired NC System Temperature 557°F SAT 3.3.3 Present cycle burnup 25 EFPD UNSAT 3.3.4 Present Difference from Equilibrium Samarium Worth (+) 19.6 pcm 3.3.5 Number of Known Untrippable Control Rods 0 3.3.6 Untrippable RCCA Core Locations N/A 3.3.7 Date and time of latest valid Iodine and Xenon concentrations; 1018110 0430 3.3.8 Iodine concentration at time listed in Step 3.3.7; 0 if xenon free. 6094.2 atm/cc 3.3.9 Xenon concentration at time listed in Step 3.3.7; 0 if xenon free. 4280.4 atmlcc 3.3.10 Shutdown Fission Product Correction Factor 3 ppm (This value is from performing End. 4.9)
STANDARD:
Applicant records information given in cue in spaces provided The Shutdown fission product correction factor is obtained by performing the first step of Enclosure 4.9. .
Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
PAGE 6 OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 5: End. 4.9 (3.1) IF the Unit operated for> 3 EFPD from the CRITICAL previous shutdown to the current shutdown, STEP determine the Shutdown Fission Product Correction Factor as follows: SAT A. Date/Time of current Unit Trip or Shutdown: UNSAT 1018110 0130 B. Current Date/Time or projected time used in the appropriate calculation:
1018110 0430 C. Duration of Shutdown 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> D. Shutdown Fission Product Correction Factor(using duration from 3.1.C) 3 ppm STANDARD:
Applicant determines that the Shutdown fission product correction factor is 3 ppm per ROD Man ual section 513. ... . . .
Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
PAGE 7 OF 18
.- Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 6: 3.4 Select the highest boron concentration for the T-AVGs CRITICAL between the range of Step 3.3.1 (Present NC System STEP Temperature) and Step 3.3.2 (Desired NC System Temperature) at current cycle burnup (Step 3.3.3) in Section SAT 5.11 of the R.O.D. manual. {PIP O-C99-0318}
1428 ppm UNSAT STANDARD:
Applicant determines required boron concentration of 1428 ppm for 1300. porn shutdown margin from section 5.11 of the ROD Manual.
Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
STEP 7: 3.5 Calculate additional boron concentration penalties: CRITICAL 3.5.1 Calculate untrippable RCCA penalty: STEP A. Number of Untrippable RCCA(s) NOT fully Inserted 0 SAT B. Boron Penalty per Untrippable rod UNSAT Untrippable RCCA Penalty (A) X (B) = 0 ppm STANDARD:
Applicant determines Untrippable RCCA Penalty to be 0 ppm Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
PAGE 8 OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 8: 3.5.2 IF physics testing is NOT complete enter Zero Power CRITICAL Physics Testing penalty of 100 ppm, otherwise, enter 0 STEP ppm. 0 ppm SAT STANDARD:
UNSAT Applicant determines that physics testing has already been completed during original startup and enters a 0 ppm penalty.
Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
STEP 9: 3.5.3 Enter Shutdown Fission Product Correction Factor from CRITICAL Step 3.3.10. 3 ppm STEP STANDARD: SAT Applicant recordsvalue of 3 ppm from step 3.3.10. UNSAT Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
PAGE 9 OF 18
- Gatawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 10: 3.5.4 Calculate total additional boron concentration penalty: CRITICAL A. Untrippable RCCA Penalty 0 ppm STEP B. Additional Boron Conc Penalty for ZPPT 0 ppm SAT C. Shutdown Fission Product Correction Factor 3 ppm UNSAT Total Boron Penalty 3 ppm STANDARD:
Applicant determines Total Boron Penalty to be 3 ppm.
Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
PAGE 10 OF 18
Catawba Nuclear Station Admin JPM A RO/SRO Dec. 2010 NRC Exam STEP 11: 3.6 Calculate total required boron concentration for SDM: CRITICAL A. Required SDM Boron 1428 ppm STEP B. Total Boron Penalty 3 ppm SAT Total Required Boron Concentration for SDM (Xenon UNSAT Free) (A) + (B) = 1431 ppm STANDARD:
Applicant determines Total Required Boron Concentration for Xenon free shutdown margin to be 1431 ppm.
Step is critical, since an incorrect entry will affect the calculated value for 5DM.
COMMENTS:
PAGE liCE 18
Catawba Nuclear Station Admin JPM A RO/SRO Dec. 2010 NRC Exam STEP 12: 3.7 Determine the Boron Difference between Required Boron CRITICAL Concentration for SDM and current NC System boron STEP concentration.
SAT A. Total Required Boron Concentration for SDM 1431 ppm UNSAT B. Present NC System Boron Concentration Minus 50 ppm OR Effective Boron Conc 1175 ppm Boron Difference (A) - (B) = (+) 256 ppm STANDARD:
Applicant determines that the Boron difference will be a positive 256 ppm .
Step is critical, since an incorrect entry will affect the calculated value for 5DM.
COMMENTS:
STEP 13: 3.7.1 IF the Boron Difference determined in Step 3.7 is SAT negative, SDM is maintained for Xenon free conditions.
UNSAT STANDARD:
Applicant determines that this step is N/A.
COMMENTS:
PAGE 12 OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 14: 3.7.2 IF the Boron Difference determined in Step 3.7 is positive SAT AND Xenon credit is NOT being used, NCS boration is required to maintain SDM UNSAT STANDARD:
Applicant determines that this step is N/A.
COMMENTS:
STEP 15: 3.8 IF the Boron Difference determined in Step 3.7 is positive CRITICAL AND Xenon credit is being used, determine the Xenon STEP Credit as follows:
SAT 3.8.1 Determine the ARI, Differential Boron Worth at lower T-AVG of Step 3.3.1 or 3.3.2 AND cycle burnup of UNSAT Step 3.3.3 from Section 5.3 of the R.O.D.manual.
6.61 pcmlppm STANDARD:
Applicant determines the Differential Boron Worth to be 6 61 porn/ppm from section 5.3 of the ROD manual.
Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
PAGE 13 OF 18
Catawba Nuclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 16: 3.8.2 Calculate the reactivity worth of the boron difference: CRITICAL A. Boron Difference 256 ppm STEP B. ARI Differential Boron Worth 6.61 pcmlppm SAT Reactivity Worth of Boron Difference (A) X (B) = UNSAT 1692.16 pcm STANDARD:
Applicant determines Reactivity Worth of Boron Difference to be 169 2.1 6 porn. range of 1692 +/- 1 pcrn is acceptable.
Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
PAGE 14 OF 18
Catawba NucIearStation Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 17: 3.8.3 Calculate the xenon worth that is required to ensure SDM CRITICAL at the present NC System boron. STEP 3.8.3.1 IF the desired T-AVG from Step 3.3.2 is > 500°F, SAT calculate the Xenon Worth as follows:
UNSAT A. Reactivity Worth 1692.16 pcm B. Difference from Eq Sm Worth (+) 19.6 pcm Xenon Worth {(A) (B))
- + 0.85 = 1967.71 pcm STANDARD:
Applicant determines Xenon Worth required to maintain shutdown margin at the present NC system Boron concentration to be 1967J1 pcm. 1968+/- 1 pcrn is acceptable.
Step is critical, since an incorrect entry will affect the calculated value forSDM.
COMMENTS:
STEP 18: 3.8.3.3 Predict Xenon for approximately two days into the SAT future using OAC Xenon Predict Program or REACT program and data from steps 3.1 and 3.3. UNSAT STANDARD:
App!icant was provided with a Xenon predict with initiating cue.
COMMENTS:
PAGE 15 OF 18
Catawba Nuclear-Statian Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 19: 3.8.3.4 Record the last Date/Time from the xenon predict of CRITICAL Step 3.8.3.3 that is greater than the xenon worth of STEP Step 3.8.3.1 or step 3.8.3.2 in the following step.
SAT 3.8.3.5 Loss of SDM Date/Time 1019110 0410 UNSAT STANDARD:
Applicant determines from Xenon predict provided that shutdown margin will be lost on 10/9/10 at 0410.
Step is critical to determine the exact time that shutdown margin will be lost.
COMMENTS:
STEP 20: 3.9 Sign below to document performance. SAT Performed by: Date/Time: I UNSAT STANDARD:
Applicant signs and dates the performance of this enclosure COMMENTS:
PAGE 16 OF 18
Catawba N uclear Station Admin JPM A ROISRO Dec. 2010 NRC Exam STEP 21: 3.10 Ensure that an independent calculation per this enclosure SAT has been separately performed.
UNSAT STANDARD:
Applicant determihes that this step is not needed per initiating cue.
COMMENTS:
END OF TASK STOP TIME PAGE 17 OF 18
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETIC)N OtASK)
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:
- 1. Unit I was shutdown October 8 2010 at 0130 from 100% power after a 20 day continuous run.
- 2. Current date: October 8, 2010 Time: 0430
- 3. There are no inoperable rods.
- 4. NC Tavg = 557°F, NC boron from last sample = 1225 ppm, Core Life = 25 EFPD, difference from equilibrium Samarium worth = 19.6 PCM
- 5. Duty reactor engineer reports current Iodine concentration is 6094.2 atm/cc and current Xenon concentration is 4280.4 atm/cc.
INITIATING CUES:
- 1. The CRS has instructed you to perform a Shutdown Margin Calculation per 0P101A161001006 (Reactivity Balance Calculation) End. 4.6 to maintain current NC system temperature and pressure.
- 2. The CRS instructs you to determine using provided Xenon predict, when shutdown margin will be lost.
- The REACTBAL computer program is out of service.
- Independent Verification has been waived.
Catawba Nuclear Station SRO Admin JPM B Dec. 2010 NRC Exam SRO Admin JPM B Determine License Status PA(P I (M R
Catawba Nuclear Station SROAdminJPMB Dec. 2010 NRC Exam EVALUATION SHEET Task: Determine License Status Active / Inactive Alternate Path: None.
Facility JPM #: None.
Safety Function:
Title:
KIA 2.1.1 Knowledge of conduct of operations requirements Rating(s): 3.8 /4.2 CFR: 41.10 /45.13 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator Room X Perform X Simulate
References:
NSD 512 Maintenance of RO/SRO Licenses Task Standard: Applicant determines the correct status of each of the three Senior Reactor Operator licenses. SRO A and C are active, SRO B is inactive.
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 PA( 9 flR R
Catawba Nuclear Station SRO Admin JPM B Dec. 2010 NRC Exam 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:
- 1. Three Senior Reactor Operators have the following history:
- 2. All three have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.
- 3. None of the 3 has worked any shift since 12/01/10.
- 4. Active/Inactive status and time on shift since October 1, 2010 is as follows for each of the Senior Reactor Operators:
SRO A License was active on October 1, 2010.
10/02/10 Worked 0700-1900 shift as CRS.
10/03/10 Worked 0700-1 900 shift as OSM.
10/04/10 Worked 0700-1 900 shift as Unit 1 Supervisor 10/05/10 Worked 0700-1 900 shift as OSM.
10/06/10 Worked 0700-1 900 shift as CRS.
11/14/10 Worked 1900-0700 shift as CRS.
11/17/10 Worked 1900-0700 shift as Unit 2 Supervisor SRO B License was active on October 1, 2010.
10/01/10 Worked 0700-1 900 shift as CRS 10/02/10 Worked 0700-1 700 shift as OSM.
10/03/10 Worked 0700-1 900 shift as OSM 10/05/10 Worked 0700-1 900 shift as CRS 10/14/10 Worked 1900-0700 shift as CRS
- 11/02/10 Worked 0700-1900 shift as Unit 1 Supervisor.
SRO C License was inactive on October 1, 2010.
10/5/10 thru 10/09/10 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the CRS and completed all requirements for license reactivation.
11/12/10 Worked 0700-1900 shift as CRS.
11/13/10 Worked 0700-1900 shift as CRS 11/15/10 Worked 0700-1 900 shift as OSM 11/16/10 Worked 1900-0700 shift as OSM 11/21/10 Worked 1900-0700 shift as CRS PA(FZ
Catawba Nuclear Station SROAcImin JPM B-Dec. 2010 NRC Exam INITIATING CUES:
- 1. You are to determine if each of the Senior Reactor Operators is eligible to work the CRS position on the 0700 1900 shift on January 31, 2011. Record your answer below (yes or no).
SROA____________
SROB SROC 4 flP R
Catawba Nuclear Station SRO Admin JPM B Dec. 2010 NRC Exam START TIME:
STEP 1: Determine the Active I Inactive status of Operator A license. CRITICAL STEP STANDARD: SAT Candidate determines the license is Active because the operator IJNSAT worked the required 5 complete twelve hour shifts in a qualifying license position during the previous qu rter. . .
This step is critical to ensure that the individual is qualified to stand license duties in the control room.
COMMENTS:
STEP 2: Determine the Active I Inactive status of Operator B license. CRITICAL STEP STANDARD: SAT Candidate determines the license is Inactive because the operator did UNSAT not work the required 5 complete twelve hour shifts in a qualifying license posItion during the previous quarter.
This step is critical to preclude a non qualified individual from fulfilling license duties in the control room.
COMMENTS:
PAGE 5 OF 8
- Catawba Nuclear Station SRO Admin JPM B Dec. 2010 NRC Exam STEP 3: Determine the Active I Inactive status of Operator C license. CRITICAL STEP STANDARD:
SAT Candidate determines the license is Active because the license was reactivated in the previous quarter and that the required 5 complete UNSAT twelve hour shifts in a qualifying license position during the quarter have also been completed.
This step is critical to ensure that the individual is qualified to stand license duties in the control room.
COMMENTS:
END OF TASK STOP TIME PAGE 6 OF 8
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
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:
- 1. Three Senior Reactor Operators have the following history:
- 2. All three have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.
- 3. None of the 3 has worked any shift since 12/01/10.
- 4. Active/Inactive status and time on shift since October 1, 2010 is as follows for each of the Senior Reactor Operators:
SRO A License was active on October 1, 2010.
10/02/10 Worked 0700-1900 shift as CRS.
10/03/10 Worked 0700-1 900 shift as OSM.
10/04/10 Worked 0700-1 900 shift as Unit 1 Supervisor 10/05/10 Worked 0700-1900 shift as OSM.
10/06/10 Worked 0700-1 900 shift as CRS.
11/14/10 Worked 1900-0700 shift as CRS.
11/17/10 Worked 1900-0700 shift as Unit 2 Supervisor SRO B License was active on October 1, 2010.
10/01/10 Worked 0700-1 900 shift as CRS.
10/02/10 Worked 0700-1 700 shift as OSM 10/03/10 Worked 0700-1 900 shift as OSM 10/05/10 Worked 0700-1 900 shift as CRS 10/14/10 Worked 1900-0700 shift as CRS 11/02/10 Worked 0700-1900 shift as Unit 1 Supervisor.
SRO C License was inactive on October 1, 2010.
10/5/10 thru 10/09/10 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the CRS and completed all requirements for license reactivation 1/1 2/10 Worked 0700-1 900 shift as CRS 11/13/10 Worked 0700-1900 shift as CRS 11/15/10 Worked 0700-1 900 shift as OSM 11/16/10 Worked 1900-0700 shift as OSM 11/21/10 Worked 1900-0700 shift as CRS
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIATING CUES:
- 1. You are to determine if each of the Senior Reactor Operators is eligible to work the CRS position on the 0700 1900 shift on January 31, 2011. Record your answer below (yes or no).
SROA SROB SROC
Catawba Nuclear Station SRO Admin JPM C Dec. 2010 NRC Exam Admin JPM C Perform A Manual NC Leakage Detection Calculation Per PT111A146001009 (Loss Of Operator Aid Computer)
PA( I (W 7
Catawba Nuclear Station SRO Admin JPIV[C Dec. 2010 NRC Exam EVALUATION SHEET Task: Perform a Manual NC Leakage Calculation per PT/1/A14600/009 (Loss of Operator Aid Computer)
Alternate Path: None.
Facility JPM #: NC-095 Safety Function:
Title:
Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
KIA 2.2.42 Rating(s): 3.9 /4.6 CFR: 41.7 / 41.10 / 43.2 /43.3 /
45.3 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator Room X Perform X Simulate
References:
PT/1/N4600/009 End. 13.5 and T.S. 3.4.13 Task Standard: Applicant determines NC system leakage to be 1.05 GPM and enters T.S.
3.4.13 condition A.
Validation Time: 10 Time Critical: Yes No X Applicant: Time Start:
NAME Docket # Time Finish:
Performance Rating: SAT UNSAT Performance Time Examiner: /
NAME SIGNATURE DATE COMMENTS PA(F 9 flF 7
Catawba Nuclear Station
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:
- 1. The OAC has been out of service for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
INITIATING CUES:
- 1. You have been directed to perform Enclosure 13.5 of PT111A146001009 (Loss of Operator Aid Computer) steps 1.3 through 1.7 to determine input to the Containment Floor and Equipment Sump.
- 2. Determine any Tech Spec actions (If applicable).
- 3. CFES Sump levels at 0800:
1WLP5740 6.2 inches 1WLP5750 7.1 inches
- 4. CFES Sump levels at 0900:
1WLP5740 6.9 inches 1WLP5750 7.6 inches CFES input GPM.
Tech Spec (If Applicable) flR 7
Catawba Nuclear Station SRO Admin JPM C Dec. 2010 NRC Exam START TIME:
STEP 1: 1.3 Record initial sump readings on the Containment Floor and SAT Equipment Sump Inleakage Rate Log Sheet.
UNSAT STANDARD:
Applicant records initial Containment Floor and Equipment sump level values on ncL 1..3. page 3 of 4.
COMMENTS:
STEP 2: 1.4 Once per hour, record sump level readings on the SAT Containment Floor and Equipment Sump Inleakage Rate Log Sheet. UNSAT STANDARD:
Applicant records current Containment Floor and Equipment sump level values on EncL135 page 3 pf*4 . . .
COMMENTS:
PAGE4OF7
Catawba Nuclear Station SRO Admin JPM C Dec. 2010 NRC Exam STEP 3: 1.5 Calculate the leakage rate using the Sump Volume vs. CRITICAL Level Indication Table. STEP STANDARD: SAT (Sum A Gals.(T2) Sump A GaIs.(Tl)) + (Sump B Gals.(T2) Sump B Gals. (Ti)) UNSAT (TimeatT2TimeatTi)
(280.1 243.3) + (317.1 290.7) 60 mm.
Applicant determines the NC system leakrate is 1 05 GPM (+/- 01 GPM)
This step is critical to verify that a limit for unidentified leakage has been exceeded.
COMMENTS:
STEP 4: 1.6 Verify leakage is < I gpm. CRITICAL STEP STANDARD:
SAT Applicant determines leakage is> I GPM UNSAT This step is critical to verify that a limit for unidentified leakage has been exceeded.
COMMENTS:
PAGE 5 OF 7
Catawba Nuclear Station SROAdminJPMC Dec. 2010 NRC Exam STEP 5: 1.7 IF the input to the Containment Floor and Equipment Sumps CRITICAL is> I gpm, perform the following: STEP
- Determine if NC System leakage is> 1 gpm. UNSAT STANDARD:
Apphcant refers to TS 34 13 and determines that Action A is applicable This step is critical to ensure that proper actions are taken for the limit on unidentified leakage being exceeded.
COMMENTS:
END OF TASK STOP TIME PAGE6OF7
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
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:
- 1. The OAC has been out of service for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
INITIATING CUES:
- 1. You have been directed to perform Enclosure 13.5 of PT111A146001009 (Loss of Operator Aid Computer) steps 1.3 through 1.7 to determine input to the Containment Floor and Equipment Sump.
- 2. Determine any Tech Spec actions (If applicable).
- 3. CFES Sump levels at 0800:
1WLP5740 6.2 inches 1WLP5750 7.1 inches
- 4. CFES Sump levels at 0900:
1WLP5740 6.9 inches 1WLP5750 7.6 inches CFES input GPM.
Tech Spec actions (If Applicable)
Catawba Nuclear Station SROAdminJPMD Dec. 2010 NRC Exam SRO Admin JPM D Calculate Low Pressure Service Water Discharge Flow For Radioactive Release PA( I flR II
Catawba Nuclear Station
- SROAcIminJPMD Dec. 2010 NRC Exam EVALUATION SHEET Task: Calculate Low Pressure Service Water Discharge flow for a liquid radioactive release.
Alternate Path: None.
Facility JPM #: 2004 NRC initial license exam SRO-4 Admin Safety Function:
Title:
KIA 2.3.11 Ability to control radiation releases Rating(s): 3.8 /4.3 CFR: 41.11 /43.4/45.10 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator Room X Perform X Simulate
References:
PT/0/N4250/01 1 (RL Temperature And Discharge Flow Determination)
Task Standard: Applicant obtains needed data, correctly calculates total discharge flow, and determines that the liquid waste release can continue.
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 COM ME NTS 9 flF 11
Catawba Nuclear Station SROAdm1nJPMD Dec. 2010 NRC Exam 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:
- 1. Unit I is currently performing a liquid waste release from the Monitor Tank Building.
- 2. Low Pressure Service Water (RL) Flow transmitter ORLP5O8O (RL Disch Flow) and OAC points CI P0903 and C2P0903 (RL Line A Disch Flow-Hourly Average) are inoperable and have been removed from service.
- 3. The RN system is aligned to the RL discharge header.
- 4. PT101A14250101 I (RL Temperature and Discharge Flow Determination) was last completed at 0700.
- 5. Current time is 1030.
- 6. Units I and 2 are both at 100% power.
INITIATING CUES:
- 1. You are directed to calculate the total RL discharge flow using Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT101A142501011 and determine if adequate flow exists to continue the release per the LWR currently in progress. Record your answer in the spaces below.
Total RL Discharge Flow GPM.
Adequate Flow Exists YesIN o EXAMINER NOTE: After reading initiating cue, provide applicant with a copy of PTIO!A14250101 I Enclosures 4.1 signed off up to step to perform End. 4.2, Enclosures 4.2 and 4.7, appropriate data sheet, and a copy of the LWR permit report.
flP 11
Catawba Nuclear Station SRO Admin JPM D Dec. 2010 NRC Exam START TIME:
STEP 1: 1.1.1 Perform the following calculations to obtain Total Discharge CRITICAL Head: STEP RL Disch Pressure = ORLP5O3O ÷ 3.9 psi SAT RL Disch Pressure = 68 + 3.9 psi = 71.9 psig UNSAT Lake Elevation = 569 0RNP7380 (Lake Wylie Level) or obtained from hydro central per Step 1.1.4.2 of Enclosure 13.1.
( 71.9 psigx2.311ft/psig)+(571.75- 569 ft)= 168.9 ft RL Disch Pressure Lake Elev Total Disch Head STANDARD:
Applicant Calculates RL Discharge pressure This step is critical because improper entry could affect the calculation for Total RL Discharge Flow.
COMMENTS:
PAGE4OF 11
Gatawba Nuclear Station SRO Admin JPM D Dec. 2010 NRC Exam STEP 2: 1.1.2 Using Total Discharge Head from Step 1.1.1 obtain the RL CRITICAL Pump Flow value using one of the following: STEP U Enclosure 13.7 (RL Pumps Head I Capacity Table) SAT OR UNSAT U OAC Databook in Secondary Systems Databook Calcs usingRL Total Discharge Head vs. RL Pump Flow Rate.
STANDARD:
Applicant determines that RL Pump Flow per Enclosure 13 7 is 32755 GPM EXAMINER NOTE: Range of 31,416 34,036 GPM is acceptable.
This step is critical because improper entry could affect the calculation for Total RL Discharge Flow.
COMMENTS:
PAGE 5011
Catawba Nuclear Station SRO Admin JPM D Dec. 2010 NRC Exam STEP 3: 1.1.3 Once RL Pump Flow value is obtained, calculate Total RL CRITICAL Supply based on number of RL pumps in operation: STEP 32,755 X 2 = 65,510 RL Pump Flow # of pumps in op. Total RL Supply (A) SAT STANDARD: UNSAT Applicant calculates Total RL Supply to be 65,510 GPM EXAMINER NOTE: Range carried forward is 62,832 to 68,072 GPM.
This step is critical because improper entry could affect the calculation for Total RL Discharge Flow.
COMMENTS:
STEP 4: 1.1.4 Enter Total RL supply (A) value in Step 1.4. CRITICAL STEP STANDARD:
SAT Applicant enters value calculated for Total RL Supply in blank (A) on page 3of3, UNSAT EXAMINER NOTE: Steps 1.2.1 and 1.2.2 are not applicable per initiating cue.
This step is critical because improper entry could affect the calculation for Total RL Discharge Flow.
COMMENTS:
PAGE 6 OF 11
Catawba Nuclear Station SRO Admin JPM D Dec. 2010 NRC Exam STEP 5: 1.2.3 IF either Cl P5854 (RN Train A Calculated Total Flow) OR CRITICAL Cl P5855 (RN Train B Calculated Total Flow) is NOT STEP available, perform the following to obtain total RN flow:
SAT 1.2.3.1 Calculate RN Pump Train A flow:
0 + 0 = 0 gpm UNSAT I RN P7520 + 2RNP7520 = RN Pump Train A flow 1.2.3.2 Calculate RN Pump Train B flow:
17,000 + 0 = 17,000 gpm IRNP75IO + 2RNP7510 = RN Pump Train Bflow STANDARD:
Applicant calculates total RN flow to be 17,000 GPM.
This step is critical because improper entry could affect the calculation for Total RL Discharge Flow.
COMMENTS:
STEP 6: 1.2.4 Perform the following calculations to obtain Total RN Flow: CRITICAL STEP 0 ÷ 17,000 = 17,000 gpm (B)
RN Pump Train A Flow + RN Pump Train B Flow = Total RN Flow SAT STANDARD: UNSAT Applicant calculates total RN flow to be 17,000 GPM.
This step is critical because improper entry could affect the calculation for Total RL Discharge Flow.
COMMENTS:
PAGE 7 OF 11
- -Catawba Nuclear Station SRO Admin JPM D Dec. 2010 NRC Exam STEP 7: 1.2.5 Enter Total RN Flow (B) in Step 1.4. CRITICAL STEP STANDARD:
SAT Applicant enters Total RN Flow calculated in previous step in blank (B) on page 3 of 3*. .. .
.. UNSAT EXAMINER NOTE: Steps 1.3.1 and 1.3.2 are not applicable per data sheet.
This step is critical because improper entry could affect the calculation for Total RL Discharge Flow.
COMMENTS:
STEP 8: 1.3.3 Calculate Cooling Tower Total Evaporation as follows: CRITICAL STEP 13,500 + 14,000 = 27,500 gpm (C)
(C1P5853) (C2P5853) Tot. Cooling Twr Evap. SAT STANDARD: UNSAT Applicant calculates Total Cooling Tower Evaporation to be 27,500 GPM and enters this value in blank (C) of step IA.
This step is critical because improper entry could affect the calculation for Total RL Discharge Flow.
COMMENTS:
PAGE 8 OF 11
-Catawba NuclearStatioft SRO Admin JPM D Dec. 2010 NRC Exam STEP 9: 1.4 Perform the following calculation to obtain Total RL Disch CRITICAL Flow: STEP 65,510 ÷ 17,000 - 27,500 = 55,010 gpm SAT (A) (B) (C)
UNSAT STANDARD:
Applicant calculates Total RL discharge flow to be 55,010 GPM EXAMINER NOTE: Calculation range carried forward would be 52,332 to 57,572 GPM.
This step is critical to ensure that enough RL flow exists to dilute the liquid waste release that is in progress.
COMMENTS:
STEP 10: SAT STANDARD: UNSAT Applicant determines that Total RL Discharge Flow is greater than the recommended RL Flow interlock, and that the release may continue.
COMMENTS:
END OF TASK STOP TIME PAGE 9 OF 11
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
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:
- 1. Unit 1 is currently performing a liquid waste release from the Monitor Tank Building.
- 2. Low Pressure Service Water (RL) Flow transmitter ORLP5O8O (RL Disch Flow) and OAC points CI P0903 and C2P0903 (RL Line A Disch Flow-Hourly Average) are inoperable and have been removed from service.
- 3. The RN system is aligned to the RL discharge header.
- 4. PT101A14250101 I (RL Temperature and Discharge Flow Determination) was last completed at 0700.
- 5. Current time is 1030.
- 6. Units I and 2 are both at 100% power.
INITIATING CUES:
I. You are directed to calculate the total RL discharge flow using Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PTIOIAI425OIOII and determine if adequate flow exists to continue the release per the LWR currently in progress. Record your answer in the spaces below.
Total RL Discharge Flow GPM.
Adequate Flow Exists YesINo
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
Unit I and Unit 2 Data Sheet for 1030 Unit I Cooling Tower Evaporation (PID CI P5853) 13,500 GPM Unit 2 Cooling Tower Evaporation (PID C2P5853) 14,000 GPM Low Pressure Service Water (RL) Status RL pumps A and B are in service Lake Wylie Level (0RNP7380) 569 Feet RL Header Pressure (ORLP5O3O) 68 PSIG Nuclear Service Water (RN) Status lB RN pump is in service OAC points Cl P5854, Cl P5855, and Cl P5856 are removed from service RN Pump Train A flow (IRNP7520) 0 GPM RN Pump Train A flow (2RNP7520) 0 GPM RN Pump Train B flow (IRNP75IO) 17,000 GPM RN Pump Train B Flow (2RNP7510) 0 GPM
Catawba Nuclear Station SRGAdmInJPME Dec. 2010 NRC Exam SRO Admin JPM E Determine Guidance For Protective Action Recommendations PA(P I flP R
Catawba Nuclear Station
- SROAdminJPME Dec. 2010 NRC Exam EVALUATION SHEET Task: Determine guidance for Protective Action Recommendations per RP-05 (General Emergency)
Alternate Path: None.
Facility JPM #: SEP-098 Safety Function:
Title:
KIA 2.4.44 Knowledge of emergency plan protective action recommendations.
Rating(s): 2.4/4.4 CFR: 41.10/41.12/43.5/45.11 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator Room X Perform X Simulate
References:
RP-05 (General Emergency)
Task Standard: Applicant recommends that Zones C2, D2, E2, and F2 be evacuated.
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 PA( 9 flP
Catawba Nuclear Station SROAdmInJPME Dec. 2010 NRC Exam 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:
- 1. A General Emergency has been declared.
- 2. Immediate Protective Action Recommendations have been made with the wind direction 58 degrees, and wind speed being 4 MPH, to evacuate zones A0, Al, BI, Cl, Dl, El, Fl and to shelter in place zones A2, A3, B2, C2, 02, E2, F2, and F3.
- 3. It has been 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> since the Unit shutdown.
- 4. New data has shown the wind speed to be 4 MPH (OAC Pt Cl P0250), Wind direction 58 degrees (from National Weather Service), EMF 53A reading 623 RIHr and EMF 53B reading 632 RIHr.
INITIATING CUES:
- 1. You are to perform step 3.3 of RP!01A150001005 (General Emergency) and determine if any Protective Actions need to be updated.
- 2. If needed, the EOF will evaluate evacuation times per End. 4.4.
Additional recommendations (if any)
EXAMINER NOTE: After reading initiating cue, provide applicant with a copy of RPIOIAI5000IOO5 completed through step 3.2.
PA(F flR R
Catawba Nuclear Station SRO Admin JPM E Dec. 2010 NRC Exam START TIME:
STEP 1: 3.3 Evaluate specific plant conditions, off-site dose projections, SAT field monitoring team data, and assess need to update Protective Action Recommendations made to states and UNSAT counties in previous notification. Refer to:
- Enclosure 4.3, page 1 of 3, Guidance for Protective Actions, Protective Action Recommendation Flowchart
- Enclosure 4.4, Evacuation Time Estimates for Catawba Plume Exposure EPZ STANDARD:
Applicant refers to Enclosure 4.3 to determine actions.
COMMENTS:
STEP 2: (End. 4.3) 1. Use flowchart to determine if large fission product CRITICAL inventory is greater than gap activity. STEP STANDARD: SAT Applicant determines from flowchart that large fission product inventory UNSAT is greater than gap activity. .
This step is critical to ensure that an upgrade in PARs is realized and that needed zones get evacuated.
COMMENTS:
PAGE4OF6
Catawba Nuclear Station SRO Admin JPM E Dec. 2010 NRC Exam STEP 3: (End 4.3) 2. Make recommendation. CRITICAL STEP STANDARD:
SAT Applicant determines that zones C2, D2, E2, and F2 should be evacuated. . .
. UNSAT This step is critical to ensure the health and safety of the public is maintained and that proper zones are evacuated.
COMMENTS:
STEP 4: (End 4.3) Applicant continues through the remainder of the SAT flowchart.
UNSAT STANDARD:
Applicant determines that no further recommendations will be made for the rest of the flowchart. ..
COMMENTS:
END OF TASK STOP TIME PAGE 5 OF 6
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
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:
- 1. A General Emergency has been declared.
- 2. Immediate Protective Action Recommendations have been made with the wind direction 58 degrees, and wind speed being 4 MPH, to evacuate zones A0, Al, BI, Cl, Dl, El, Fl and to shelter in place zones A2, A3, B2, C2, D2, E2, F2, and F3.
- 3. It has been 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> since the Unit shutdown.
- 4. New data has shown the wind speed to be 4 MPH (OAC Pt Cl P0250), Wind direction 58 degrees (from National Weather Service), EMF 53A reading 623 RIHr and EMF 53B reading 632 RIHr.
INITIATING CUES:
I. You are to perform step 3.3 of RPIOIAI5000IOO5 (General Emergency) and determine if any Protective Actions need to be updated.
- 2. If needed, the EOF will evaluate evacuation times per End. 4.4.
Additional recommendations (if any)