ML062750245
| ML062750245 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/20/2006 |
| From: | Caruso J Operations Branch I |
| To: | |
| Sykes, Marvin D. | |
| References | |
| Download: ML062750245 (42) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 TY Pe Code*
Facility: Calvert Cliffs Units 1 & 2 Examination Level (circle one): RO / SRO Describe activity to be performed Date of Examination: 8/28/06 - 9/1/06 Operating Test Number:
2006 N
Administrative Topic (see Note)
Calculate an estimated critical condition (NRC-16)
WA 2.2.34 Knowledge of the process for determining the internal and external effects on core reactivity (2.8, 3.2)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Establish max power limit with plant computer failure (NRC-15)
WA 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data (2.8, 3.1)
N
~~~
Determine radiological conditions for personnel exposure WA 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure (2.9, 3.3)
(N RC-17)
N NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (2 1)
(P)revious 2 exams (s 1 ; randomly selected)
(S)imulator NUREG 1021 REVISION 9
ES-301 Administrative Topics Outline Form ES-301-1 TY Pe Code*
N Facility: Calvert Cliffs Units 1 & 2 Examination Level (circle one):
RO / SRO Describe activity to be performed Identify reporting requirements (NRC-18)
WA 2.1.1 Knowledge of conduct of operations requirements (3.7, 3.8)
Establish max power limit with plant computer failure (N RC-15)
Date of Examination: 8/28/06 - 9/1/OE Operating Test Number:
2006 Administrative Topic Conduct of Operations Equipment Control Radiation Control Emergency Plan
/I N
WA 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data (2.8, 3.1)
Evaluate post-maintenance test requirements (NRC-19)
WA 2.2.21 Knowledge of pre-and post-maintenance operability requirements (2.3, 3.5)
Determine radiological conditions for personnel exposure WA 2.3.1 0 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure (2.9, 3.3)
Determine appropriate emergency response actions N
(N RC-1 7)
N (NRC-20)
D WA 2.4.29 Knowledge of the emergency plan (2.6, 4.0)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
(C)ontrol room (D)irect from bank ( s 3 for ROs; < 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 2 1)
(P)revious 2 exams ( 2 1; randomly selected)
(S)imulator
- Type Codes & Criteria:
NUREG 1021 REVISION 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.:
NRC-14 Task
Title:
Apply Technical Specifications to a Relay Failure Task Number: xxx.xxx WA
Reference:
WA 2.1.12 (2.9,4.0)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
4 Simulator:
Plant:
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
Unit 1 is at 100% power.
An E&C technician performed a visual inspection of ESFAS Channel ZA Actuation Relay Cabinet. The technician reports that two SIAS AS power relays are discolored and shows signs of deformation possibly due to excessive temperature. These relays CANNOT be considered operable.
The affected relays are as follows:
- 3.
0 SIAS AS Relay at B5 (11 LPSI) 0 SIAS AS Relay at BS (11 & 12 CAC Fans)
Initiating Cue:
You are directed to determine which TS LCOs apply, the LCO actions that must be taken and the completion time limits for these actions. Applicable prints and the technical specifications are provided.
Task Standard:
Determine the TS LCOs that apply and the LCO actions that must be taken.
NRC-14 Page 1 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
Technical Specifications
- 7.
Technical Specification Basis 1E-076 Sheet 1, LPSI Pp ll, Revision 22 1E-076 Sheet 11C, Containment Cooling Fan ll, Revision 3 1E-076 Sheet 11D, Containment Cooling Fan 12, Revision 2 1E-058, ESFAS Logic Diagram, Revision 35 lE-O58A, ESFAS Logic Diagram, Revision 48 General
References:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
Technical Specifications
- 8.
SD-048, Engineered Safety Features Actuation System, Revision 3 (Page 13) 1E-076 Sheet 1, LPSI Pp ll, Revision 22 1E-076 Sheet 11C, Containment Cooling Fan ll, Revision 3 1E-076 Sheet 11D, Containment Cooling Fan 12, Revision 2 1E-058, ESFAS Logic Diagram, Revision 35 lE-O58A, ESFAS Logic Diagram, Revision 48 LOI-212-1-5, TS Introduction for Licensed Operator Initial Training Lesson Plan, Revision 12/02/2004, Objective 1.3 - Given a plant or system condition and the Tech Specs be able toapply the appropriate Action requirements.
Time Critical Task:
No NRC-14 Page 2 of 6 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time:
15 minutes Simulator Setup:
None NRC-14 Page 3 of 6 NUREG-102 1, Revision 9
STANDARD ELEMENT
(* = CRITICAL STEP)
TIME START Review prints and initial conditions.
Refer to Technical Specifications Same as element.
Same as element Examiner Note:
Applicant may enter TS LCOs 3.5.2 and 3.6.6 for inoperable components.
This action is not necessarily required but may be entered as a conservative application of Technical Specifications. Further, this is an RO task.
Determines TS LCO 3.3.5 Action C applies for loss of Function 1.b.
(SIAS Actuation Logic) in Table 3.3.5-1.
Note:
Applicant may also identify actions required if 3.3.5 Action A not met.
Action B specifies MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, MODE 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Applicant not required to identify LCO 3.5.5.B actions.
Determines that required action is to restore the affected Actuation Logic channel (SIAS Channel A) to OPERABLE status.
Determines that required completion time is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
TIME STOP Examiner Note:
The task is complete when the applicant has determined which TS LCOs apply, the LCO actions that must be taken and the completion time limits for these actions.
NRC-14 Page 4 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion NRC-14 Job Performance Measure Number:
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-14 Page 5 of 6 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
Unit 1 is at 100% power.
An E&C technician performed a visual inspection of ESFAS Channel ZA Actuation Relay Cabinet. The technician reports that two SIAS A8 power relays are discolored and shows signs of deformation possibly due to excessive temperature. These relays CANNOT be considered operable.
- 3.
The affected relays are as follows:
SIAS A8 Relay at B5 (1 1 LPSI)
SIAS A8 Relay at B8 (1 1 & 12 CAC Fans)
INITIATING CUE:
You are directed to determine which TS LCOs apply, the LCO actions that must be taken and the completion time limits for these actions.
Applicable prints and the technical specifications are provided.
NRC-14 Page 6 of 6 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-15 Task
Title:
Establish Max Power Limit With Plant Computer Failure Task Number: xxx.xxx WA
Reference:
K/A 2.1.25 (2.8,5.1)
Method of testing:
Si mu1 ated Performance:
Actual Performance:
d Classroom:
d Simulator:
Plant:
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
Unit 2 is been operating at 100% for two months.
The plant computer has failed and reboot efforts have not been successful. DAS is also out of service.
A transient occurred immediately after the loss of the plant computer.
However, the plant has been stabilized.
The current highest excore NI reading is 99.2%.
CECOR is not available. Reactor Engineering reports a measured value of FxyT of 1.592 Axial Shape Index is at +0.15.
The Power Ratio Recorder is correctly adjusted.
CEAs are above long term steady state insertion limit.
- 4.
- 5.
- 6.
- 7.
- 8.
Initiating Cue:
You are directed to perform AOP-7H, Loss Of Plant Computer In Mode One Or Two, Step IV.C.3.b and fully complete AOP-7H, Attachment 2.
Task Standard:
Determine maximum allowed power with loss of plant computer.
NRC-15 Page 1 of 6 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1.
Calculator
- 2.
- 3.
Blank AOP-7H Attachment 2
- 4.
AOP-7H, Loss Of Plant Computer In Mode One Or Two, Revision 22 NEOP-23, Technical Data Book, Revision 22 General
References:
- 1.
- 2.
AOP-7H9 Loss Of Plant Computer In Mode One Or Two, Revision 22 (pages 7-10 of 25 and Attachment 2 NEOP-23, Technical Data Book, Revision 22 (pgs 74-76 of 81)
Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
None NRC-15 Page 2 of 6 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Identify and locate AOP-7H, Step IV.C.3.b.
Same as element.
NOTE:
The measured Fxy T is the last value calculated by CECOR or as provided by the Reactor Engineering Work Group when CECOR is NOT available.
NOTE:
The assumed Fxy T is the value of the LHR curve of Figure 2-1V.A. 1, Excore LHR Power vs Peripheral ASI, NEOP-23, that represents the smallest Fxy T that is greater than the measured Fxy T.
.. I power of NEOP-23, Figure 2-IV.A.2, Excore DNBR Power vs Peripheral ASI.
Determines maximum power is 42.5% (+0.5%). Records this value on Attachment 2.
Determines maximum power is
<97.5% (+2.0%). Records this value on Attachment 2.
Records following values on.
0 Measured FxyT = 1.592 0
Assumed FxyT = 1.5925 0 Maximum allowed power from Step (1) = 82.5% 0.5%
Step (2) = 97.5%
critical) 0 Maximum allowed power from 2.0% (not Indicates the following on :
CEAs above LTSS Insertion Lmt Power Ratio Recorder adjusted NRC-15 Page 3 of 6 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME STOP Examiner Note:
The task is complete when the applicant has filled in AOP-7H,.
NRC-15 Page 4 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-IS Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-15 Page 5 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
Unit 2 is been operating at 100% for two months.
The plant computer has failed and reboot efforts have not been successful. DAS is also out of service.
A transient occurred immediately after the loss of the plant computer. However, the plant has been stabilized.
The current highest excore NI reading is 99.2%.
CECOR is not available. Reactor Engineering reports a measured value of F,,T of 1.592.
Axial Shape Index is at +O. 15.
The Power Ratio Recorder is correctly adjusted.
CEAs are above long term steady state insertion limit.
INITIATING CUE:
You are directed to perform AOP-7H, Loss Of Plant Computer In Mode One Or Two, Step IV.C.3. b and fully complete AOP-7H,.
NRC-15 Page 6 of 6 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-16 Task
Title:
Calculate An Estimated Critical Condition Task Number: xxx.xxx WA
Reference:
K/A 2.2.34 (2.8,3.2)
Method of testing:
Simulated Performance:
Actual Performance:
.\\,
Classroom:
4 Simulator:
Plant:
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
Unit 2 is in MODE 3 at normal operating temperature and pressure.
Current time is 8am.
The reactor tripped while performing RPS testing 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> ago.
Preparations are underway for a quick trip recovery startup to begin within the next 30 minutes with criticality anticipated in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at loam, The following conditions exist:
0 PIant trip from 100% power 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> ago Power history - at 100% for the past 68 days Burnup - 16,225 MWDMTU Previous critical condition data, boron correction factor, and xenon worth have been filled in on NEOP-302 Attachment 2.
Initiating Cue:
You are directed to calculate the estimated critical concentration for a quick trip recovery criticality anticipated in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Do not calculate the +lhr or the +2hr values. Do not calculate the ECC tolerance band values.
Task Standard:
Calculate an estimated critical condition.
NRC-1 6 Page 1 of 7 NUREiG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1.
Calculator
- 2.
- 3.
NEOP-302, Estimated Critical Condition, Revision 6 NEOP-23, Technical Data Book, Revision 22 General
References:
- 1.
- 2.
- 3.
- 4.
- 5.
Xenon Worth Calculator Printout NEOP-302, Estimated Critical Condition, Revision 6 NEOP-23, Technical Data Book, Revision 22 Unit 2 ECC performed 5/29/2003 Unit 2 ECC performed 1/25/2004 Time Critical Task:
No Validation Time:
20 minutes Simulator Setup:
None NRC-16 Page 2 of 7 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Refers to NEOP-302 NEOP-302, Section 6.1 A. COMPLETE the previous critical conditions section of Attachment 2.
RECORD the unit and cycle numbers, datehime of shutdown, current burnup.
B. COMPLETE the current conditions section of Attachment 2.
- 1.
RECORD the excess reactivity from
- 2.
DETERMINE the HZP Inverse Fig 2-II.A.7 of NEOP-23 on Att. 2 Boron Worth (IBW) from Fig 2-II.A.2 and record on Att. 2
- 3.
DETERMINE the B-10 Correction Factor and record on Att. 2 C. RECORD the estimated date and time of reactor criticality for the ECC on for time point Oh.
D. RECORD the elapsed time from reactor shutdown to the estimated time of criticality as Hours After Shutdown on Att. 2 for time point Oh.
E. DETERMINE the post shutdown xenon worth for time point Oh.
- H. DETERMINE the desired CEA
- I. DETERMINE the CEA reactivity position for criticality.
worth at the desired CEA position using Fig 2-ll.B.1 of NEOP-23.
- J. CALCULATE the Corrected HZP IBW using the formula.
- K. CALCULATE the boron worth using the formula.
NRC-16 Page 3 of 7 Same as element.
Data filled in on form.
Records 8.549 k0.015
[8.534 to 8.5641 Records 1 1 1.44 +0.02
[ 11 1.42 to 11 1.461 Records 0.971 Records 1000 as estimated time.
Records 34 hrs as elapsed time.
No action required. Value given in initial conditions on form as 1.036
% delta rho.
Records Group 4 at 90 inches on.
Records CEA worth of 0.787 %
delta rho on Attachment 2.
Records corrected HZP IBW as 114.77 k0.12 [ 114.65 to 114.891 Records boron worth as 6.726 k0.02
[6.706 to 6.7461 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
- L. MULTIPLY the Boron Worth by the Records estimated critical Corrected HZP IBW. This value concentration as 772 10 ppm equals estimated critical concentration.
[762 ppm to 782 ppm]
TIME STOP Examiner Note:
The task is complete when the applicant has finished calculating the estimated critical concentration for the planned time of criticality.
NRC-16 Page 4 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion NRC-16 Job Performance Measure Number:
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-16 Page 5 of 7 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
Unit 2 is in MODE 3 at normal operating temperature and pressure. Current time is 8am.
The reactor tripped while performing RPS testing 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> ago.
Preparations are underway for a quick trip recovery startup to begin within the next 30 minutes with criticality anticipated in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at loam.
- 3.
The following conditions exist:
Plant trip from 100% power 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> ago Power history - at 100% for the past 68 days BUITIUP - 16,225 MWD/MTU
- 4.
Previous critical condition data, boron correction factor, and xenon worth have been filled in on NEOP-302 Attachment 2.
INITIATING CUE:
You are directed to calculate the estimated critical concentration for a quick trip recovery criticality anticipated in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Do not calculate the +lhr or the +2hr values. Do not calculate the ECC tolerance band values.
NRC-16 Page 6 of 7 NUREG-102 1, Revision 9
ANSWER KEY
[AI 8.549 50.015 Estimated Critical Condition ANSWER KEY t BI
[Cl 11 1.44 50.02 0.971 Units 1 & 2 NEOP-302/Rev. 5 Page 27 of 35 2
16 I 72 hrs ago I ATTACHMENT 2 - ANSWER KEY ECC -
4-HOUR WINDOW WITH SAME BORON 16,225 Previous Critical Conditions Hours Shutdown Time Date Time After Point
- Burnup, MWD/MTU i
Unit 1
Cycle 1
Date 1
Time Xenon Group Group
- Worth, 3,
4,
%Ap inches inches 0.787 114.772.1 2 6.72620.02 772 +lo
-2h
-1h Time Date Time Point
-2h I
Oh I
I 1000 I 34 I 1.036 I I
90 Lower CEA Bound (ECC Worth + 0.5 %Ap)
Upper CEA Bound (ECC Worth - 0.5 %Ap)
Bounding Group 3, Group 4, Group 5, Bounding Group 3, Group 4, Group 5, Worth inches inches inches Worth inches inches inches
+lh
+2h I
%Ap I
ppm/%~p I Correction Group Corrected Boron Critical
- Worth, Boron
[E] (for Oh) or
[F] = BIC
[GI = A-(D+E)
[HI = F*G
%Ap ppm/%Ap
%Ap Conc., ppm
[E] = A-(D+G)
Excess Reactivity Source:
I BW Source:
B-10 Source:
CEA Worth Source:
Prepared by:
I SRO Verification by:
I signature date signature date
- NOTE: Obtain a sequence number from the Attachment Log Sheet, Attachment 1.
NRC-16 Page 7 of 7 NUREG-1021, Revision 9
Estimated Critical Condition Excess Reactivity,
%Ap Units 1 & 2 Page 27 of 35 NEOP-302/Rev. 5 HZP IBW, B-10 ppml%Ap Correction ATTACHMENT 2 ECC -
4-HOUR WINDOW WITH SAME BORON
[A]
Previous Critical Conditions PI
[Cl I
Unit I Cycle I Date I
Time 1
MWD,MTU
- Burnup, 2
16 I 72 hrs ago I 16,225 Estirr Time Point Time Date Time Point
-2h Lower CEA Bound (ECC Worth + 0.5 %Ap)
Bounding Group 3, 'Group 4, Group 5, Worth inches inches inches
-1h Oh Bounding Worth
+lh Group 3, Group 4, Group 5, inches inches inches
+2h
,led Critical Conditions Hours Shutdown Xenon
- Worth,
%Ap
[Dl Group 3,
inches 1.036 Group 4,
inches Group 5,
- Worth,
%Ap
[E] (for Oh) or
[E] = A-(D+G)
Corrected HZP IBW, ppml%Ap
[F] = BIC Boron
- Worth,
%Ap
[GI = A-(D+E)
Critical Boron Conc., ppm
[HI = F*G Excess Reactivity Source:
IBW Source:
B-IO Source:
CEA Worth Source:
Prepared by:
I SRO Verification by:
I signatu re date signature date
- NOTE: Obtain a sequence number from the Attachment Log Sheet, Attachment 1.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.:
NRC-17 Task
Title:
Determine radiological conditions for personnel exposure Task Number: xxx.xxx WA
Reference:
K/A 2.3.10 (2.9,3.3)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:..I Simulator:
Plant:
.I READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
Unit 2 is at 100% power.
Letdown is in service on CVC-llOQ Control Valve. L/D Control Valve CVC-11OP is isolated and post work testing is in progress on the valve.
Maintenance needs the valve observed for any binding while it is stroked a number of times before returning it to service.
Initiating Cue:
You have been directed to locally observe valve stroke on Letdown Control Valve 2-CVC-11OP-CV and then stand by to clear tags and open the downstream isolation valve. Task time is estimated to take 10 minutes.
State the radiological requirements for entering this area. Include in your discussion:
- 1. Protective clothing required in the work area
- 2. Highest general area radiation level in the room
- 3. Expected dose for this assignment
- 4. Dose rate alarm
- 5. Low dose waiting area What is the definition of a Locked High Radiation Area? What differences, if any, are there in the barrier controls applied to High Radiation Areas as opposed to Locked High Radiation Areas at Calvert Cliffs?
NRC-17 Page 1 of 5 NUREG-102 1, Revision 9
Appendix C Job Performance Measure FOITJ ES-C-1 Worksheet Task Standard:
Determine radiological conditions for personnel exposure Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Rewired Materials:
- 1.
- 2.
Unit 2 Letdown Heat Exchanger Room Survey Map SW-2006-0106, Operations Activities in High Radiation Areas (HRAs)
RP-1-100, Radiation Protection, Revision 8
- 3.
General
References:
RP-1-100, Radiation Protection, Revision 8 (Pages 14,31)
Time Critical Task:
No Validation Time:
10 minutes Simulator Setup:
None NRC-17 Page 2 of 5 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Review survey map and SWP.
TIME STOP Same as element.
Determines that SWP specifies Anti-Cs and conferring with RST (Radiation Safety Technician).
Determines that highest radiation level in the area is 180 mR/hr by the N side of the heat exchanger.
Determines that expected dose in 10 minutes is 1/6
- 6OmR/hr = 10 mR Determines from SWP that dose rate alarm will be set at 800 mR/hr.
Identifies from SWP room low dose waiting area is by the room door, or identifies lowest general area is by the door (5 mFUhr), or states would wait outside of the room in the hallway.
States that Locked HRA is an area where dose could exceed lR/hr at 30 cm.
States that HRAs and Locked HRAs treated the same at Calvert Cliffs.
Both are locked, guarded or electronically surveilled.
Examiner Note:
The task is complete when the applicant has provided requested radiological in formati on.
NRC-17 Page 3 of 5 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-17 Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
~
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-17 Page 4 of 5 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
Unit 2 is at 100% power.
0 Letdown is in service on CVC-1 lOQ Control Valve. L/D ConLLol Valve CVC-1 1OP is isolated and post work testing is in progress on the valve.
0 Maintenance needs the valve observed for any binding while it is stroked a number of times before returning it to service.
INITIATING CUE:
You have been directed to locally observe valve stroke on Letcldwn Control Valve 2-CVC-1 lop-CV and then stand by to clear tags and open the downstream isolation valve. Task time is estimated to take 10 minutes.
State the radiological requirements for entering this area. Include in your discussion:
- 1.
- 2.
- 3.
- 4.
Dose rate alarm Protective clothing required in the work area Highest general area radiation level in the room Expected dose for this assignment
- 5.
Low dose waiting area What is the definition of a Locked High Radiation Area? What differences, if any, are there in the barrier controls applied to High Radiation Areas as opposed to Locked High Radiation Areas at Calvert Cliffs?
NRC-17 Page 5 of 5 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.:
NRC-19 Task
Title:
Evaluate Post-Maintenance Test Requirements Task Number: xxx.xxx WA
Reference:
WA 2.2.21 (2.3,3.5)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
4 Simulator:
Plant:
READ TO THE APPLICANT:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
Unit 1 is at 100% power.
E&C replaced two SIAS AS power relays in ESFAS Channel ZA Actuation Relay Cabinet.
Relay testing was NOT performed on the new relays prior to installation.
The affected relays are as follows:
0 0
SIAS AS Relay at BS (11 & 12 CAC Fans)
- 5.
In addition, mechanics overhauled 11 LPSI Pump.
Initiating Cue:
You are directed to determine post-maintenance testing requirements and to describe the general scope of the testing.
Task Standard:
Evaluate post-maintenance test requirements for the relay replacement.
Evaluation Criteria:
- 1.
All critical steps completed.
NRC-19 Page 1 of 6 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
Technical Specifications
- 7.
- 8.
- 9.
1E-076 Sheet 1, LPSI Pp ll, Revision 22 1E-076 Sheet 11C, Containment Cooling Fan ll, Revision 3 1E-076 Sheet 11D, Containment Cooling Fan 12, Revision 2 1E-058, ESFAS Logic Diagram, Revision 35 1E-O58A, ESFAS Logic Diagram, Revision 48 NO-1-208, Nuclear Operations Post Maintenance Testing, Revision 11 STP 0-7A-1, W A S A-3, SIAS A-8 and RAS A Logic Test (2 copies -
available if requested)
STP 0-73 J-1, 11 LPSI Pump Post-Maintenance Operability Test (Modes 1-4) (2 copies - available if requested)
General
References:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
- 11.
NRC-19 SD-048, Engineered Safety Features Actuation System, Revision 3 1E-076 Sheet 1, LPSI Pp ll, Revision 22 1E-076 Sheet 11C, Containment Cooling Fan ll, Revision 3 1E-076 Sheet 11D, Containment Cooling Fan 12, Revision 2 1E-058, ESFAS Logic Diagram, Revision 35 lE-O58A, ESFAS Logic Diagram, Revision 48 Technical Specifications MN-PMTG, Post Maintenance Testing Guideline, Revision 0 (PMT-70)
NO-1-208, Nuclear Operations Post Maintenance Testing, Revision 11 (Attachment 3)
STP 0-7A-1, WAS A-3, SIAS A-8 and RAS A Logic Test (Section 6.3)
STP 0-735-1, 11 LPSI Pump Post-Maintenance Operability Test (Modes 1-4) (Section 6.1)
(Page 13)
Page 2 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
None NRC-19 Page 3 of 6 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
TIME START Review prints and initial conditions.
Refer to Technical Specifications.
Same as element.
Same as element Refer to Post Maintenance Test Procedure.
Same as element Identifies general post-maintenance test requirements.
Determines need to (1) verify affected motors (1 1 LPSI, 11/12 CAC Fans) can be started using a simulated signal and (2) verify that all equipment affected by the repaired control circuit device operates properly (1 1 LPSI Bkr, 11/12 CAC Fan Bkrs).
Identifies post-maintenance test requirements from NO-1-208.
Determines control circuit maintenance is NOT exempt from testing because relay not tested before installation. (Page 17 of 41)
Perform a channel functional test on SIAS Channel A Actuation Logic Channel under SR 3.3.5.1. (STP 0-7A-1)
Perform post-maintenance surveillance test on 11 LPSI under SR 3.5.2.3. (STP 0-73J-1)
TIME STOP Examiner Note:
The task is complete when the applicant has determined the post-maintenance testing requirements for this activity.
NRC-19 Page 4 of 6 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion NRC-19 Job Performance Measure Number:
Applicant:
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-19 Page 5 of 6 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS :
- 1.
- 2.
- 3.
- 4.
Unit 1 is at 100% power.
E&C replaced two SIAS A8 power relays in ESFAS Channel ZA Actuation Relay Cabinet.
Relay testing was NOT performed on the new relays prior to installation.
The affected relays are as follows:
SIAS A8 Relay at B5 (1 1 LPSI)
SIAS A8 Relay at B8 (1 1 & 12 CAC Fans In addition, mechanics overhauled 11 LPSI Pump.
- 5.
INITIATING CUE:
You are directed to determine post-maintenance testing requirements and to describe the general scope of the testing.
NRC-19 Page 6 of 6 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Calvert Cliffs 1&2 Job Performance Measure No.: NRC-20 Task
Title:
Determine Appropriate Emergency Response Actions Task Number: 204.097 WA
Reference:
KIA 2.4.29 (2.6,4.0)
Method of testing:
Simulated Performance:
Actual Performance:
4 Classroom:
J Simulator:
Plant:
READ TO THE APPLICANT.:
I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
Unit 2 was at 100% power when a loss of 22 SGFP occurred.
A reactor trip was manually initiated by de-energizing 480VAC busses at minus 40 inches in the SGs.
EOP-8 was implemented due to multiple events in progress (steam leak and a LOCA.)
RCS subcooling is 0°F.
SIAS failed to automatically actuate and required manual actuation.
Containment pressure was 30 psig and rising when it suddenly lowered to 1 psig.
Containment High Range Radiation Monitors are currently reading 4000 R e M r.
You are performing the duties of the Shift Manager.
Initiating Cue:
You are to complete the emergency response initial notification form.
Task Standard:
Determine EAL classification and protective action recommendations and complete the emergency response form.
NRC-20 Page 1 of 9 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Evaluation Criteria:
- 1.
All critical steps completed.
- 2.
- 3.
- 4.
All sequential steps completed in order.
All time-critical steps completed within allotted time.
JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.
Required Materials:
- 1.
- 2.
- 3.
- 4.
ERPIP 3.0, Immediate Actions, Revision 38 ERPIP 3.0 Attachment 1, EAL Criteria, Revision 29 DRDT screen showing DIRlO is 82 and DIR60 is 65 Blank Copy of ERPIP 3.0 Attachment 3, Initial Notification Form (ERPIP 3.0 Pages 19 and 20)
General
References:
- 1.
- 2.
ERPIP 3.0, Immediate Actions, Revision 38 (Pages 18 thru 25)
ERPIP 3.0 Attachment 1, EAL Criteria, Revision 29 Time Critical Task:
No Validation Time:
15 minutes Simulator Setup:
None NRC-20 Page 2 of 9 NUREG-102 1, Revision 9
STANDARD ELEMENT
(* = CRITICAL STEP)
TIME START
- 1.
Identify and locate ERPIP.
Same as element.
- 2.
Refers to Immediate Actions and identifies the appropriate category from the listing and go to the appropriate Attachment.
Selects and goes to attachment 2, Emergency Classification.
ATTACHMENT 2 EMERGENCY CLASSIFICATION A.
CLASSIFY THE EMERGENCY NOTE:
The decision to classify an emergency may NOT be delegated.
Fills in Notification Form to indicate a GENERAL EMERGENCY classification is warranted under FISSION PRODUCT BARRIER DEGRADATION, based on a loss of all 3 barriers-H.G.5.1.4 Fuel Clad Barrier-Containment Radiation reading > 3500 rem/hr RCS Barrier-RCS subcooling
< 25?F due to RCS leakage.
Containment Barrier-Rapid unexplained CNTMT pressure decrease following initial increase.
NRC-20 Page 3 of 9 NUREG-1021, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
B.
IMPLEMENT EMERGENCY RESPONSE PLAN ACTIONS (ATTACHMENT 2) 1.0 If an EAL is satisfied, Determines from above evaluation that an EAL is satisfied and obtains an Initial Notification form from the working copy or the extra forms book.
THEN OBTAIN an Attachment 3, Initial Notification Form (from this procedure).
GO TO the respective classification Determines Attachment 4, General tab.
Emergency Actions, is applicable.
ATTACHMENT 4 1.0 COMPLETE Attachment 3, page 1 of 2, Initial Notification Form, using directions on page 2 of 2.
Refers to Attachment 3, Initial Notification Form.
NOTE TO EVALUATOR: The following page 2 instructions may or may not be referred to as the student completes page 1.
ATTACHMENT 3-Page 2 Enters H.G.5.1.4 on Attachment 3.
1.a.
Item A5 RETRIEVE this information from the EAL chart in ERPIP-3.0, Immediate Actions, Attachment 1, Emergency Action Level Criteria.
NRC-20 Page 4 of 9 NUREG-1021, Revision 9
STANDARD ELEMENT
( = CRITICAL STEP)
Radioactivity is beinghas been released:
- 1)
The release flowpath
- 2)
The release idwas greater monitor idwas in alarm.
than Technical Specification limits.
- 3)
The release idwas accidental.
1.c.
Item A8 Refers to Attachment 5.
IF General Emergency is checked in Item 4, THEN DETERMINE appropriate Protective Action Recommmendatein and downwind zones(z) from ERPIP 3.0,, General Emergency Protective Action Recommendations, AND CHECK corresponding box (check one box only).
IF General Emergency is not checked in Item 4, THEN CHECK ~0m.79 1.d.
Item A10 Emergency Director must sign form after Items 1 through 10 have been completed Signs Attachment 3 after items 1 through 10 have been completed ATTACHMENT 3-Page 1
- 1.
Complete Item 1.
Checks is in Item 1.
- 2.
Complete Item 2.
Inserts communicators name in Item 2.
__ 3.
CompleteItem 3.
Checks Unit-2 in Item 3.
plet NRC-20 Page 5 of 9 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP)
NOTE TO EVALUATOR: Attachment 5 should be referenced to complete Item 8.
ATTACHMENT 5 GENERAL EMERGENCY PROTECTIVE ACTION RECOMMENDATIONS A.
NOTE:
SELECT A PROTECTIVE ACTION RECOMMENDATION A prompt protective action recommendation shall be made for General Emergency.
IF a controlled release of radioactive material from containment is to be commenced in less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> AND there is assurance that the release will be a short term puff release lasting no more than 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
1.O THEN MAKE the following Protective Action Recommendation:
Shelter entire 10 mile EPZ Determines step is N/A.
Determines that this step is applicable.
Using DIRlO since the release is not from the main vent and the Control Room map, selects Evacuate PAZ 1 & 2 unless condition make evacuation dangerous, notify the public in PAZ 1 & 2 to take JLI, shelter remainder of the 10 mile EPZ.
ATTACHMENT 3-Page 1 plet
- 9.
Complete Item 9.
Checks is in Item 9.
- 10.
Complete Item 10.
Enters time declared, enters date, prints name, NRC-20 Page 6 of 9 NUREG-102 1, Revision 9
ELEMENT STANDARD
(* = CRITICAL STEP) and signs name in Item 10.
TIME STOP TERMINATING CUE: This JPM is complete when initial notification form completed. No further actions are required.
NRC-20 Page 7 of 9 NUREG-1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Verification of Completion Job Performance Measure Number:
NRC-20 Applicant :
NRC Examiner:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Follow up Question:
Applicant Response:
Result:
SAT UNSAT Examiners Signature and Date:
NRC-20 Page 8 of 9 NUREG-102 1, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet APPLICANTS CUE SHEET INITIAL CONDITIONS:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
Unit 2 was at 100% power when a loss of 22 SGFP occurred.
A reactor trip was manually initiated by de-energizing 480VAC busses at minus 40 inches in the SGs.
EOP-8 was implemented due to multiple events in progress (steam leak and a LOCA.)
RCS subcooling is 0°F.
SIAS failed to automatically actuate and required manual actuation.
Containment pressure was 30 psig and rising when it suddenly lowered to 1 psig.
Containment High Range Radiation Monitors are currently reading 4000 R e a.
You are performing the duties of the Shift Manager.
INITIATING CUE:
You are to complete the emergency response initial notification form.
NRC-20 Page 9 of 9 NUREG-1021, Revision 9