ML090720040
| ML090720040 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 02/04/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| IR-09-301 | |
| Download: ML090720040 (59) | |
See also: IR 05000327/2009301
Text
JPM A.1.a
Page 1 of 7
SEQUOYAH NUCLEAR PLANT
JPM A.1.a
Evaluate Overtime Requirements
JPM A.1.a
Page 2 of 7
NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION
NUMBER
DESCRIPTION OF
REVISION
V
DATE
PAGES
AFFECTED
PREPARED/
REVISED BY:
0
Modified JPM
Y
All
V - Specify if the JPM change will require another validation (Y or N).
See cover sheet for criteria.
JPM A.1.a
Page 3 of 7
SEQUOYAH NUCLEAR PLANT
RO/SRO
Task:
Evaluate Overtime Requirements
JA/TA task:
3430050302 (SRO)
0001650302 (SRO)
1190030301 (RO)
K/A Ratings:
2.1.5 Ability to use procedures related to shift staffing, such as minimum crew
complement, overtime limitations, etc. 2.9* / 3.9
Task Standard:
1) The candidate identifies the need for on 2 occasions:
On 01/30/09 to allow exceeding 24hours in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period
On 02/04/09 to allow exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days
Evaluation Method :
Classroom ___X_____
=======================================================================
Performer:
_______________________________________
NAME
Start Time ________
Performance Rating : SAT _____ UNSAT _____ Performance Time _____
Finish Time _______
Evaluator:
_________________________________/________
SIGNATURE
DATE
=======================================================================
COMMENTS
JPM A.1.a
Page 4 of 7
JPM A.1.a
Page 5 of 7
SPECIAL INSTRUCTIONS TO EVALUATOR:
1. JPM can be administered in any setting
Validation Time: CR. 13 min
Local ____________
Tools/Equipment/Procedures Needed:
References:
Reference
Title
Rev No.
1.
SPP-1.5
Overtime Restrictions (Regulatory)
0005
2.
0-PI-OPS-000-027.0
Shift Manager Clerk Duty Station Shift Relief and
Office Round Sheets.
0034
=================================================================
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be
performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
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:
You are a Licensed Operator that has worked the following schedule:
Date
Hours
Status
Notes
01/26/09
OFF
01/27/09
OFF
01/28/09
OFF
01/29/09
0630 -2230
Normal Off Day
Worked on an Off day and
stayed over 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until relief
arrived
01/30/09
1830-0645
Normal Work Day
15 minute turnover
01/31/01
1830-0645
Normal Work Day
15 minute turnover
02/01/09
1830-0645
Normal Work Day
15 minute turnover
02/02/09
1830-0645
Normal Work Day
15 minute turnover
02/03/09
OFF
Normal Off Day
02/04/09
0630-1845
Normal Off Day
Called in to cover shift(15
minute turnover)
02/05/09
1300-1845
Normal Off Day
Called in to cover shift to relieve
a sick operator.
(15 minute turnover)
02/06/09
A/L
Normal Work Day
Took Annual Leave for the shift
02/07/09
0630-1845
Normal Work Day
15 minute turnover
02/08/09
0630-1845
Normal Work Day
15 minute turnover
02/09/09
OFF
Normal Off Day
INITIATING CUES:
Determine the date(s) that would require an Overtime Limitation Exception Report to be completed prior to you
completing the identified working hours and the reason(s) for the report(s) being required.
JPM A.1.a
Page 6 of 7
Job Performance Checklist
STEP/STANDARD
SAT/UNSAT
STEP 1.:
Evaluate the hours worked against the requirements.
STANDARD:
Candidate identifies an Overtime Limitation Exception Report is
required prior to completing the 01/30/09 shift to allow exceeding
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period
Start Time____
___ SAT
___ UNSAT
Critical
Step
STEP 2.: Evaluate the hours worked against the requirements.
STANDARD:
Candidate identifies an Overtime Limitation Exception Report is
required prior to completing the 02/04/09 shift to allow exceeding
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period
COMMENTS:
___ SAT
___ UNSAT
Critical
Step
End of JPM
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
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:
You are a Licensed Operator that has worked the following schedule:
Date
Hours
Status
Notes
01/26/09
OFF
01/27/09
OFF
01/28/09
OFF
01/29/09
0630 -2230
Normal Off Day
Worked on an Off day and
stayed over 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until
relief arrived
01/30/09
1830-0645
Normal Work Day
15 minute turnover
01/31/01
1830-0645
Normal Work Day
15 minute turnover
02/01/09
1830-0645
Normal Work Day
15 minute turnover
02/02/09
1830-0645
Normal Work Day
15 minute turnover
02/03/09
OFF
Normal Off Day
02/04/09
0630-1845
Normal Off Day
Called in to cover shift(15
minute turnover)
02/05/09
1300-1845
Normal Off Day
Called in to cover shift to
relieve a sick operator.
(15 minute turnover)
02/06/09
A/L
Normal Work Day
Took Annual Leave for the
shift
02/07/09
0630-1845
Normal Work Day
15 minute turnover
02/08/09
0630-1845
Normal Work Day
15 minute turnover
02/09/09
OFF
Normal Off Day
INITIATING CUES:
Determine the date(s) that would require an Overtime Limitation Exception Report to be
completed prior to you completing the identified working hours and the reason(s) for the
report(s) being required.
JPM A.1.b
Page 1 of 8
SEQUOYAH NUCLEAR PLANT
A.1.b
Calculate Manual Makeup
to the Volume Control Tank
JPM A.1.b
Page 2 of 8
NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION
NUMBER
DESCRIPTION OF
REVISION
V
DATE
PAGES
AFFECTED
PREPARED/
REVISED BY:
V - Specify if the JPM change will require another validation (Y or N).
See cover sheet for criteria.
JPM A.1.b
Page 3 of 8
SEQUOYAH NUCLEAR PLANT
RO/SRO
Task:
Calculate Manual Makeup to the Volume Control Tank
JA/TA task # : 0040250101
(RO)
K/A Ratings:
004A1.06 (3.0/3.2)
004A4.07 (3.9/3.7)
004A4.13 (3.3/2.9)
004A4.15 (3.6/3.7)
Task Standard:
Manual make up to the VCT to bring level up 10% is determined to be 168+/-2 gallons water and
32+/-2 gallons of boric acid.
Evaluation Method :
Simulator ___X_____ In-Plant ________
======================================================================
Performer:
_______________________________________
NAME
Start Time _______
Performance Rating : SAT _____ UNSAT _____ Performance Time _____
Finish Time _______
Evaluator:
________________________________/__________
SIGNATURE
DATE
======================================================================
COMMENTS
JPM A.1.b
Page 4 of 8
SPECIAL INSTRUCTIONS TO EVALUATOR:
1. Sequenced steps identified by an "s"
2. Any UNSAT requires comments
3. Initialize the simulator in IC-176. Ensure VCT level is approximately 24% prior to start of JPM.
4. Ensure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.
Validation Time: CR. 22 mins
Local ____________
Tools/Equipment/Procedures Needed:
1. 0-SO-62-7, "Boron Concentration Control", Section 6.5, Appendix C
2. TI-44, Boron Tables.
References:
Reference
Title
Rev No.
1.
0-SO-62-7
Boron Concentration Control
51
2.
TI-44
Boron Tables
12
==================================================================
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall
be performed for this JPM. I will provide initiating cues and reports on other actions when directed
by you. When you complete the task successfully, the objective for this job performance measure
will be satisfied. 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 is at 100% full power, steady state.
2. Reactor coolant system boron concentration is 1117 ppm and BAT boron concentration is
6820 ppm.
3. B-10 depletion value is 15 ppm
4. REACTF software is not available for boron calculations.
INITIATING CUES:
1. You are the Unit 1 OATC and are to perform a calculation for a manual blended makeup to the
Chemical Volume Control System to increase Volume Control Tank level from 41% to 51%.
2. Notify the SRO when the calculation is completed.
JPM A.1.b
Page 5 of 8
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 1.:
Operator obtains appropriate copy of procedure and determines the
appropriate section to perform.
STANDARD: Operator obtains copy of 0-SO-62-7 and determines that section 6.5 is the
appropriate section.
___ SAT
___ UNSAT
Start Time____
STEP 2.:
[2] PERFORM Appendix C Calculation of Boric Acid and Primary
Water Integrator setting for manual makeup.
STANDARD: Operator goes to Appendix C
___ SAT
___ UNSAT
NOTE:
Following steps are contained in 0-SO-62-7, Appendix C CALCULATION OF
BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL
STEP 3.:
[1] OBTAIN Current RCS Boric Acid Concentration
STANDARD: Operator obtains current RCS boron concentration or uses initial
conditions. RCS Boric acid concentration 1117 ppm
___ SAT
___ UNSAT
STEP 4.:
[2] OBTAIN Current BAT Boric Acid Concentration
STANDARD: Operator obtains current BAT boron concentration from Chem Lab or uses
initial conditions. BAT Boric acid concentration 6820 ppm
___ SAT
___ UNSAT
STEP 5.:
[3] OBTAIN B-10 depletion value from Rx Eng Information page
______________PPM
Cue:
Current depletion value is 15 ppm, after operators asks for information
page.
STANDARD: Operator obtains current boron depletion value and records 15 ppm.
___ SAT
___ UNSAT
NOTE
Result in Step [4] should be rounded to the second decimal place.
STEP 6.:
[4] CALCULATE BAT Boric Acid Concentration Ratio (BACR):
NOTE:
6820 ppm ÷ 6820 ppm (from step 2) = 1.0
STANDARD: Operator observes that BACR is one (1.0).
___ SAT
___ UNSAT
Critical Step
JPM A.1.b
Page 6 of 8
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 7.:
[5] CALCULATE B-10 corrected boron concentration:
_________ ____________ = ____________
STEP [1] STEP [3] B-10 corrected boron
NOTE:
1117 ppm - 15 ppm (from step 2) = 1102 ppm
STANDARD: Operator calculates corrected B-10 concentration
___ SAT
___ UNSAT
STEP 8.:
[6] DETERMINE Corrected Boric Acid Flow Rate and Controller Setting
using appropriate table from TI-44 Appendix C.
[a] RECORD Corrected Boric Acid Flow Rate from TI-44 Appendix C
Table 1.
NOTE:
TI-44, Appendix C, Table 1, BA flow for 1100 ppm is 13.32 gpm; BA
flow rate for 1110 ppm is 13.46 gpm. Interpolating for 1102 ppm. BA
flow rate is 13.35 gpm
STANDARD: Operator calculates the Corrected Boric Acid Flow rate from TI-44
Appendix C Table 1. 13.35 gpm
___ SAT
___ UNSAT
Critical Step
STEP 9.:
[b] RECORD Correct Boric Acid Controller Setting from TI-44
Appendix C Table 2
NOTE:
TI-44, Appendix C, Table 2, BA controller setting for 1100ppm is
26.6%; BA controller setting for 1110 ppm is 26.9%. Interpolating for
1102 ppm, BA controller setting for is 26.66% (26.7%).
STANDARD: Operator calculates the Corrected Boric Acid Controller Setting from TI-44
Appendix C Table 2 for a value of 26.77% (26.7%)
___ SAT
___ UNSAT
Critical Step
STEP 10.:
[7] Calculate Boric Acid Controller Setting
[Corrected BA Controller Setting] x [BACR] = [Boric Acid Controller
Setting]
NOTE:
26.66% (26.7%) x 1.0 = 26.66% (26.7%)
STANDARD: Operator calculates the Boric Acid Controller Setting.
___ SAT
___ UNSAT
Critical Step
STEP 11.:
[8] Desired VCT level - Actual VCT level X 20 gal = ________
NOTE:
(51% - 41) X 20 gal = 200 gal
STANDARD: Operator calculates total volume of water to raise VCT level 10% to be 200
gallons.
___ SAT
___ UNSAT
Critical Step
JPM A.1.b
Page 7 of 8
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 12.:
[9] [Corrected BA Flow Rate] x [BACR] + 70 gpm = [Total Flow Rate]
NOTE:
13.35 gpm x 1.0 + 70 gpm = 83.35 gpm ( ~ 83.4 gpm)
STANDARD: Operator determines total flow rate of ~ 83.4 gpm +/- 1% (82.52-84.18)
___ SAT
___ UNSAT
Critical Step
STEP 13.:
[Corrected BA Flow Rate) X BACR] ÷ Total Flow Rate X Total Volume
Change = BORIC ACID INTEGRATOR SETTING
NOTE:
((13.35 x 1.0) / (83.35)) x 200 = 32.03 gal. Note tolerance in previous
steps calculation.
STANDARD: Operator establishes correct integrator setting as below
[13.4 gpm X 1(BACR) ÷ 83.4 gpm] X 200 gal = ~ 32.1 gal
___ SAT
___ UNSAT
Critical Step
STEP 14.:
70 GPM (PW) ÷ Total Flow Rate X Total Volume = PRIMARY WATER
INTEGRATOR SETTING
NOTE:
The total of this step and the previous step should be ~ the same as
the total volume needed to raise level 10% in the VCT.
(32.1 gal +167.9 gal. = 200 gal)
NOTE:
Operator may CHECK calculation using INFORMATION ONLY
SPREADSHEET.
STANDARD: Operator establishes correct integrator setting as below
[70 gpm ÷ 84.1gpm] X 200 gal = ~ 167.9gal (167.97 using 83.35)
___ SAT
___ UNSAT
Critical Step
Stop Time____
End of JPM
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control
room steps shall be performed for this JPM. I will provide initiating cues and
reports on other actions when directed by you. When you complete the task
successfully, the objective for this job performance measure will be satisfied.
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 is at 100% full power, steady state.
2. Reactor coolant system boron concentration is 1117 ppm and BAT boron
concentration is 6820 ppm.
3. B-10 depletion value is 15 ppm.
4. REACTF software is not available for boron calculations.
INITIATING CUES:
1. You are the Unit 1 OATC and are to perform a calculation for a manual blended
makeup to the Chemical Volume Control System to increase Volume Control
Tank level from 41% to 51%.
2. Notify the SRO when the calculation is completed.
RO A.2
Page 1 of 10
SEQUOYAH NUCLEAR PLANT
RO ADMIN A.2
Perform Monthly Shift Log
0-SI-OPS-000-003.M
RO A.2
Page 2 of 10
NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION
NUMBER
DESCRIPTION OF
REVISION
V
DATE
PAGES
AFFECTED
PREPARED/
REVISED BY:
0
Y
All
V - Specify if the JPM change will require another validation (Y or N).
See cover sheet for criteria.
RO A.2
Page 3 of 10
SEQUOYAH NUCLEAR PLANT
RO/SRO
Task:
Perform Monthly Shift Log 0-SI-OPS-000-003.M
JA/TA task:
1190090301 (RO)
K/A Ratings:
2.2.12 Knowledge of surveillance procedures. 3.7 / 4.1
(CFR: 41.10 / 45.13) l
Task Standard:
Candidate performs the identified portion of 0-SI-OPS-000-003.M and identifies instruments that do do
meet the acceptable range indentified in the instruction.
Evaluation Method :
Simulator ___X_____ In-Plant ________
=======================================================================
Performer:
_______________________________________
NAME
Start Time ________
Performance Rating : SAT _____ UNSAT _____ Performance Time _____
Finish Time _______
Evaluator:
_________________________________/________
SIGNATURE
DATE
=======================================================================
COMMENTS
RO A.2
Page 4 of 10
SPECIAL INSTRUCTIONS TO EVALUATOR:
1. Sequenced steps identified by an "s"
2. Any UNSAT requires comments
3. Place MODE 1 sign on the simulator.
4. This task is to be performed using the simulator in IC 178. If not available then reset to 1C-16. perform
step 5 below.
5. Insert overrides:
ZAOPI18C to 845
ZAOPI126C to 830
ZAOPI119C to 805
ZAOFI3163C to 36
ZAOFI3147C to 10
6. Ensure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.
Validation Time: CR. 20 min
Local ____________
Tools/Equipment/Procedures Needed:
1-SI-OPS-000-003.M
References:
Reference
Title
Rev No.
1.
1-SI-OPS-000-003.M
Monthly Shift Log
0038
=================================================================
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be
performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
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 in service at 100% rated power.
INITIATING CUES:
1. You are an RO on shift.
2. You are to perform 1-SI-OPS-000-003.M, Monthly Shift Log, Appendix A pages 1 through 4 in
accordance with the requirement of the Surveillance Instruction.
3. After completing pages 1 through 4 and complying with the requirements of the instruction, return the
surveillance instruction to the Unit Supervisor.
RO A.4
Page 5 of 10
Job Performance Checklist
STEP/STANDARD
SAT/UNSAT
STEP 1.:
Obtain the appropriate procedure.
STANDARD:
Operator obtains 1-SI-OPS-000-003.M, Monthly Shift Log,
Appendix A.
Start Time____
___ SAT
___ UNSAT
STEP 2.: Turbine Driven AFW Pump Speed Control Light Green
STANDARD: Candidate determines green light lit on 1-HC-46-57-S on 1-M-3.
COMMENTS:
___ SAT
___ UNSAT
STEP 3.: Auxiliary Feedwater Valve Mode Indicator Light Blue
STANDARD: Candidate determines blue lights lit on 1-XX-148 for each of the 8 valves
listed. The blue lights are on the top 2 rows.
COMMENTS:
___ SAT
___ UNSAT
RO A.4
Page 6 of 10
Job Performance Checklist
STEP/STANDARD
SAT/UNSAT
STEP 4.: Auxiliary Feedwater Valve Position Indication
STANDARD: Candidate determines green lights lit on 1-XX-55-6K and 1-XX-55-6L for
each of the 12 valves listed. The green lights are in the MANUAL
sections of Panels K and L. Panel K windows 75, 88, 114-117and Panel
L Windows 62, 75, 114-117
COMMENTS:
___ SAT
___ UNSAT
STEP 5.: Motor Driven AFW Flowrate
STANDARD: Using note 5 at the bottom of page the candidate determines 1-FI-3-163C
does not meet acceptance criteria.
Candidate determines the reading from the identified flow instruments. All
are 0 to 5 except for 1-FI-3-163C which reads between slightly over 30
gpm and 1-FI-3-147C which reads approximately 15 gpm.
COMMENTS:
___ SAT
___ UNSAT
Critical
Step
RO A.4
Page 7 of 10
Job Performance Checklist
STEP/STANDARD
SAT/UNSAT
STEP 6.: ERCW to AFW Valve Position Indication
STANDARD: Candidate verifies green lights lit above each of the listed handswitches
located on 1-M-3.
COMMENTS:
___ SAT
___ UNSAT
STEP 7.: Containment Isolation Valve Position Indication
STANDARD: Candidate pushes TEST pushbuttons on both 1-XX-55-6K (white
push button) and 1-XX-55-6L 6K (red push button) control panels
and verifies both bulbs( red and green) for each position indicator
illuminate in accordance with note 7 at bottom of page.
COMMENTS:
___ SAT
___ UNSAT
RO A.4
Page 8 of 10
Job Performance Checklist
STEP/STANDARD
SAT/UNSAT
STEP 8.: Main Steam Line Pressure
STANDARD: Using note 8 at the bottom of page the candidate determines 1-PI-1-19C
does not meet acceptance criteria.
Candidate determines the reading from the identified flow instruments.
Aux Control Room instrument 1-PI-1-19C reads 810 psig and the MCR
instruments (1-PI-1-20A & 1-PI-20B) read 880 psig for a 70 psig
difference (only 53 psig is allowed for acceptance criteria.)
COMMENTS:
___ SAT
___ UNSAT
Critical
Step
STEP 9.: PLACE initials in the lower block of the column in appendix A to signify that all
data listed in the column is complete, satisfies specified NOTES, and complies
with acceptance criteria or has a DN assigned. (mark non - applicable steps
N/A).
STANDARD: Candidate identifies the Motor Driven AFW Flow Rate and the the Main
Steam Line Pressure instruments that are outside the acceptable
deviation ranges.
COMMENTS:
___ SAT
___ UNSAT
Critical
Step
RO A.4
Page 9 of 10
Job Performance Checklist
STEP/STANDARD
SAT/UNSAT
STEP 10.: DELIVERS package to Unit SRO for review and approval.
Cue: state We will stop here
STANDARD:
COMMENTS:
___ SAT
___ UNSAT
Stop Time____
END of JPM
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
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 in service at 100% rated power.
INITIATING CUES:
1. You are an RO on shift.
2. You are to perform 1-SI-OPS-000-003.M, Monthly Shift Log, Appendix A pages 1
through 4 in accordance with the requirement of the Surveillance Instruction.
3. After completing pages 1 through 4 and complying with the requirements of the
instruction, return the surveillance instruction to the Unit Supervisor.
Page 1 of 6
SEQUOYAH NUCLEAR PLANT
ADMIN
RO A-3
(#180)
2A RHR Heat Exchanger
Radiological Work Permit and
Survey Map Usage
Page 2 of 6
NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION
NUMBER
DESCRIPTION OF
REVISION
V
DATE
PAGES
AFFECTED
PREPARED/
REVISED BY:
0
V - Specify if the JPM change will require another Validation (Y or N).
See cover sheet for criteria.
Page 3 of 6
SEQUOYAH NUCLEAR PLANT
RO/SRO
Task:
2A RHR Heat Exchanger Radiological Work Permit and Survey Map Usage
Task Number
Task Title
Cont TRN
1190100301
Apply radiation and contamination safety procedures
N
3430290302
Knowledge of 10CFR20 and related facility radiation control requirements
N
K/A Rating:
2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal
conditions. 3.5 / 3.6
Task Standard: Using the RWP and Survey Map provided: the trainee will determine the anti-contamination
clothing and dosimetry requirements also dose and dose rate alarm limits.
Evaluation Method :
Simulator ___X_____ In-Plant ________
========================================================================
Performer:
_______________________________________
NAME
Start time ________
Performance Rating : SAT _____ UNSAT _____ Performance Time _____
Finish time ________
Evaluator:
_________________________/______________
SIGNATURE DATE
========================================================================
COMMENTS
Page 4 of 6
SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
A Critical step is identified bold type in the SAT/UNSAT column.
2.
Sequenced steps identified by an "s".
3.
Any UNSAT requires comments.
4.
Task should begin at the Plant, Classroom, or Simulator.
5.
Insure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.
Validation Time: CR 16 min Local ____________
Tools/Equipment/Procedures Needed:
RWP 08000003 & Survey #051508-10
REFERENCES:
Reference
Title
Rev No.
1
Permit Number 08000003
Radiological Work Permit
0
2
Survey #051508-10
Map: A414 RHR & Containment Spray Heat
Exchanger 2A-A
5/15/08
=================================================================
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. I will provide initiating cues
and reports on other actions when directed by you. All steps shall be simulated for this task.
When you complete the task successfully, the objective for this job performance measure will be
satisfied. 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. Both Units are operating at 100% power.
2. System alignment and inspection will result in you being in the 2A-A RHR and Containment Spray
Heat Exchanger Room for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
INITIATING CUES:
You are to use the supplied RWP and survey Map to determine the following:
1. Anti-contamination clothing requirements to enter the Contamination Area between the heat
exchangers on the top elevation.
2. Which of the electronic dosimeter alarms would alarm if an individual was exposed to the
General Area Dose Rate near the lead shielded line on the lower elevation for the entire time
spent in the room.
3. How often an individual is required to be briefed on the requirements of the RWP.
JPM A3 - #180 A3
Page 5 of 6
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 1:
Anti-contamination clothing requirements to enter the
Contamination Area between the heat exchangers on the top
elevation.
STANDARD: On the RWP in the Anti-Contamination Clothing Requirements
Matrix list every item that has a 2 in its block.
The list will include: Rubber, One Pair;
Lab Coat;
Surgeons Cap;
Secure Gloves/Booties;
Cloth Inserts;
Booties, Cloth, One Pair;
Shoe Covers, One Pair;
___ SAT
___ UNSAT
Critical Step
STEP 2:
Which of the electronic dosimeter alarms would alarm if an
individual was exposed to the General Area Dose Rate near the
lead shielded line on the lower elevation for the entire time spent
in the room.
STANDARD: Candidate identifies that the Dose Alarm would alarm.
20mr/hr X 3hr = 60mr which is greater than the dose alarm
setpoint of 50mr.
___ SAT
___ UNSAT
Critical Step
STEP 3:
How often an individual is required to be briefed on the
requirements of the RWP.
STANDARD: Candidate identifies a briefing is required quarterly.
___ SAT
___ UNSAT
Critical Step
End Of JPM
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. I will
provide initiating cues and reports on other actions when directed by you. All
steps shall be simulated for this task. When you complete the task successfully,
the objective for this job performance measure will be satisfied. 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. Both Units are operating at 100% power.
2. System alignment and inspection will result in you being in the 2A-A RHR and
Containment Spray Heat Exchanger Room for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
INITIATING CUES:
You are to use the supplied RWP and survey Map to determine the following:
1. Anti-contamination clothing requirements to enter the Contamination Area
between the heat exchangers on the top elevation.
2. Which of the electronic dosimeter alarms would alarm if an individual was
exposed to the General Area Dose Rate near the lead shielded line on the
lower elevation for the entire time spent in the room..
3. How often an individual is required to be briefed on the requirements of the
RWP.
K:\\SCANDOCS\\OPERATOR LICENSING\\BALDWIN\\SEQUOYAH DRAFT MATERIAL\\ADMIN JPMS\\SEQUOYAH 2009-301 ADMIN JPM REVIEW SPREAD SHEET.DOC
2009-301 Admin JPM
- Page 1 -
Sequoyah
APPENDIX E - REGION II OPERATING TEST JOB PERFORMANCE MEASURE QUALITY REVIEW MATRIX
4. Attributes
5. Job Content
Errors
Admin
1.
Safety
function
2.
Dyn
(D/S)
3.
(1-5)
Focus
Cues
Critical
Steps
Scope
(N/B)
Over-
lap
Job-
Link
Minutia
6.
U/E/S
7.
Explanation
(See below for instructions)
1
RO/SRO
No Comments.
2
RO/SRO
Step #12 - +/-1% acceptable range is too wide. This would allow applicants that incorrectly applied the
B-10 Depletion correction to achieve satisfactory results (i.e. 13.58 gpm + 70 gpm = 83.58 gpm). For
this critical step, suggest +/- 0.1 gpm range. Carry adjusted acceptable range forward throughout the
calculations.
EC
3
RO Only
Step #8 - Revise the standard from the identified flow instruments. to the identified pressure
instruments.
EC
3
Only
Initiating Cue - Reword second paragraph from current run-on sentence. See below
You are to determine the adequacy of the SDM calculation performed by Reactor
Engineering based on the following assumptions:
A low Tavg of 530ºF over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
No change in boron concentration
RC
4
RO Only
No comments.
RC
4
Only
General Comments - 1) Other than step 1, I couldnt find in the references supplied to the applicant
the information that would lead to the determinations expected in the standards for steps 2 and 3 of
this JPM.
2) The initial conditions state that 0-RM-90-118A is inoperable. However, the supplied references
only address the operability of 0-RM-90-118. Are these the same instruments or is it a typo in the
initial conditions?
E Plan
5
Only
No comments.
Instructions for Completing Matrix
This form is not contained in or required by NUREG-1021. Utilities are not required or encouraged to use it. The purpose of this form is to enhance regional consistency in reviewing
operating tests. Check or mark any item(s) requiring comment and explain the issue in the space provided.
1.
Safety function characteristics: RO & SRO-I JPMs should evaluate different safety functions for the simulator/control room, and spearately for
the in-plant JPMs. SRO-Us should evaluate 5 different safety functions. One SRO-U should evaluate an engineered safety feature. At least
one should be shutdown or low power, 4-6 should be alternate path for the RO/SRO-I and 2-5 for the SRO-Us.
2.
Determine whether the task is dynamic (D) or static (S). A dynamic task is one that involves continuous monitoring and response to varying
parameters. A static task is basically an system reconfiguration or realignmen
3.
Determine level of difficulty (LOD) using established 1-5 rating scale. Levels 1 and 5 represent inappropriate (low or high) discriminatory level
for the license being tested.
4.
Check the appropriate box when an attribute weakness is identified:
- Page 2 -
$
The initiating cue is not sufficiently clear to ensure the operator understands the task and how to begin.
$
The JPM does not contain sufficient cues that are objective (not leading).
$
All critical steps (elements) have not been properly identified.
$
Scope of the task is either too narrow (N) or too broad (B).
$
Excessive overlap with other part of operating test or written examination.
5.
.
Check the appropriate box when a job content error is identified:
$
Topics not linked to job content (e.g., disguised task, not required in real job).
$
Task is trivial and without safety significance.
6.
Based on the reviewer=s judgment, is the JPM as written (U)nacceptable (requiring repair or replacement), in need of (E)ditorial enhancement,
or (S)satisfactory?
7.
Provide a brief description of problem in the explanation column. Provide conclusion on whether JPM SET criteria satisfied (i.e.,
number/distribution of safety functions, A.3 and A.4 integrated with parts B/C, Admin topics per section meet ES).
1.
Should attempt to have 5 ALT PATH JPMs to add flexibility to prep week and the exam.
Page 1 of 7
SEQUOYAH NUCLEAR PLANT
ADMIN
SRO A-2
JPM 175-AP
Review SDM Calculation - Incorrect Tavg
Page 2 of 7
NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION
NUMBER
DESCRIPTION OF
REVISION
V
DATE
PAGES
AFFECTED
PREPARED/
REVISED BY:
0
Y
V - Specify if the JPM change will require another Validation (Y or N).
See cover sheet for criteria.
Page 3 of 7
SEQUOYAH NUCLEAR PLANT
RO/SRO
Task
JA/TA task #
Review shutdown margin calculations
0010040101 (RO)
Perform/Verify shutdown margin calculations using REACTINF
0010040102 (SRO)
K/A Ratings:
001A4.11 (3.5/4.1)
Task Standard:
Review Shutdown Margin Calculation and Identify Incorrect Tavg Parameter Entry.
Evaluation Method :
Simulator ___X____ In-Plant ________
========================================================================
Performer:
_______________________________________
NAME
Start time ________
Performance Rating : SAT _____ UNSAT _____ Performance Time _____
Finish time ________
Evaluator:
_________________________/______________
SIGNATURE DATE
========================================================================
COMMENTS
Page 4 of 7
SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
A Critical step is identified in bold type in the SAT/UNSAT column.
2.
Sequenced steps identified by an "s"
3.
Any UNSAT requires comments
4.
Task should begin at the at any location.
5.
Insure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.
Validation Time: CR 16
Tools/Equipment/Procedures Needed:
Appendix A of this JPM. NOTE: ENSURE JPM NUMBER IS NOT LEGIBLE ON COPY PROVIDED TO
PERFORMER.
REFERENCES:
Reference
Title
Rev No.
A.
0-SI-NUC-000-038.0
54
Task Number
Task Title
Cont TRN
0010040101
Review shutdown margin calculations
Y
0010040102
Perform/Verify shutdown margin calculations using REACTINF
Y
=================================================================
Page 5 of 7
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. I will provide initiating cues
and reports on other actions when directed by you. All steps shall be Performed for this task
When you complete the task successfully, the objective for this job performance measure will be
satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that
you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 1 Tripped 48 Hours ago on 01-20-09 at 0700 after a 60 day continuous run at 100% steady state
power. All shutdown and control rods fully inserted on the trip.
The unit is being maintained in mode 3 at Approx. 547°F Tavg until repairs are completed when the Unit
will be started back up.
The Duty Reactor Engineer has performed a Shutdown Margin (SDM) Calculation using the QA Certified
Software program ReactINF.
Current Conditions are:
UNIT 1 Cycle 16
Burnup: 5750 MWD/MTU
Current Boron Concentration: 1250 ppm
Current M-P Factor: 0 ppm
Date/Time: 01/22/09 / 0700
INITIATING CUES:
You are the Unit 1 Unit Supervisor.
You to Review the SDM Calculation performed by Reactor Engineering to ensure that SDM is adequate
assuming a conservatively low Tavg of 530°F anytime during the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and no boron
concentration changes.
After you have reviewed the SDM calculation, determine if the SDM calculation by the Reactor Engineer
is correct and meets the requirements for the conditions established for the calculation.
Page 6 of 7
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP :
Obtains Copy of SDM Calculation.
NOTE:
ENSURE JPM NUMBER IS NOT LEGIBLE ON COPY
PROVIDED TO PERFORMER.
STANDARD: Operator obtains Copy of Appendix A SDM Calculation from
Evaluator.
___ SAT
___ UNSAT
Start Time____
STEP :
Operator Reviews the following Parameters on the SDM
calculation in any order:
Correct Unit and Cycle: Sequoyah Unit 1 Cycle 16
Previous Conditions: Xenon Conc 100% FP EQ
Date and Time Unit Was Shutdown: 01/20/09 / 0700
Current Date and Time: 01/22/09 / 0700
Mode for SDM: 3
Minimum Expected Core Avg Temp (Tavg): 547°F
(Critical -
Should be 530°F)
Time Since Shutdown: 48 Hours
Reactor Power Prior to Shutdown: 100%
Core Avg Burnup: 5750 MWD/MTU
Current/Projected Boron Conc: 1250 ppm
Correction to Boron Conc (M-P): 0 ppm
Rx Conditions Prior to Shutdown: Steady State
Surveillance Interval: 24 Hours
Number of Immovable or Untrippable Rods: 0
STANDARD: Operator Reviews all parameters and notes that Min Expected
Tavg (547°F) is not consistent with the Unit Supervisors SDM
requirements of 530°F.
___ SAT
___ UNSAT
Critical Step
Stop Time____
End Of JPM
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. I will
provide initiating cues and reports on other actions when directed by you. All
steps shall be Performed for this task When you complete the task successfully,
the objective for this job performance measure will be satisfied. Ensure you
indicate to me when you understand your assigned task. To indicate that you
have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
Unit 1 Tripped 48 Hours ago on 01-20-09 at 0700 after a 60 day continuous run at
100% steady state power. All shutdown and control rods fully inserted on the trip.
The unit is being maintained in mode 3 at Approx. 547°F Tavg until repairs are
completed when the Unit will be started back up.
The Duty Reactor Engineer has performed a Shutdown Margin (SDM) Calculation using
the QA Certified Software program ReactINF.
Current Conditions are:
UNIT 1 Cycle 16
Burnup: 5750 MWD/MTU
Current Boron Concentration: 1250 ppm
Current M-P Factor: 0 ppm
Date/Time: 01/22/09 / 0700
INITIATING CUES:
You are the Unit 1 Unit Supervisor.
You to Review the SDM Calculation performed by Reactor Engineering to ensure that
SDM is adequate assuming a conservatively low Tavg of 530°F anytime during the next
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and no boron concentration changes.
After you have reviewed the SDM calculation, determine if the SDM calculation by the
Reactor Engineer is correct and meets the requirements for the conditions established
for the calculation.
JPM -A.3
Page 1 of 7
SEQUOYAH NUCLEAR PLANT
ADMIN
SRO A.3
Approval of a
Waste Gas Tank Release
JPM -A.3
Page 2 of 7
NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION
NUMBER
DESCRIPTION OF
REVISION
V
DATE
PAGES
AFFECTED
PREPARED/
REVISED BY:
0
New
Y
All
V - Specify if the JPM change will require another validation (Y or N).
See cover sheet for criteria.
JPM -A.3
Page 3 of 7
SEQUOYAH NUCLEAR PLANT
RO/SRO
Task:
Approval of a Waste Gas Tank Release
JA/TA task:
5030010102 (SRO)
0690150102 (SRO)
K/A Ratings:
2.3.11 Ability to Approve Release Permits. (CFR: 41.13 / 45.4 / 45.10) 2.0 / 3.8
Task Standard:
Candidate identifies
(1) the US/SRO must approve the release if the tank if the release is to be made at 2300.
(2) the required actions to allow a release with 0-RM-90-118A out of service as identified in
ODCM 1/21.2.
(3) the required action if it takes 40 days to get parts to restore the monitor to Operable
status.
valuation Method :
Simulator ___X_____ In-Plant ________
=======================================================================
Performer:
_______________________________________
NAME
Start Time ________
Performance Rating : SAT _____ UNSAT _____ Performance Time _____
Finish Time _______
Evaluator:
_________________________________/________
SIGNATURE
DATE
=======================================================================
COMMENTS
JPM -A.3
Page 4 of 7
SPECIAL INSTRUCTIONS TO EVALUATOR:
1. Any UNSAT requires comments
2. This task can be performed in a classroom setting.
Validation Time: CR. 24 min
Local ____________
Tools/Equipment/Procedures Needed:
OPDP-1, Conduct of Operations
References:
Reference
Title
Rev No.
1.
Offsite Dose Calculation Manual
53
2.
0-SI-CEM-077-410.4
Waste Gas Decay Tank Release
0014
3.
0-SI-77-15
Waste Gas Decay Tank Release
15
=================================================================
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be
performed for this JPM. I will provide initiating cues and reports on other actions when directed by you.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
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:
The operating crew is preparing to release the Waste Gas Tank D.
0-RM-90-118A, Waste Gas Radiation Monitor, is inoperable.
The monthly projected offsite dose limits have not been exceeded.
INITIATING CUES:
You are to identify
(1) Who must approve the release if the tank is to be released on the night shift at 2300.
(2) The required actions to allow a release with 0-RM-90-118A out of service.
(3) The required action if it takes 40 days to get parts to restore the monitor to Operable status.
JPM -A.3
Page 5 of 7
Job Performance Checklist
STEP/STANDARD
SAT/UNSAT
STEP 1.:
Identify who must approve the release if the tank is to be
released on the night shift at 2300.
STANDARD:
Candidate identifies the approval of the US/SRO is required.
COMMENTS:
Start Time____
___ SAT
___ UNSAT
Critical
Step
STEP 2.: The required actions to allow a release with 0-RM-90-118A out
of service.
STANDARD:
Candidate identifies the ODCM 1/2/1/2 required Action 40
With the number of channels OPERABLE less than required by
the Minimum Channels OPERABLE requirement, the contents of
the tank(s) may be released to the environment provided that prior
to initiating the release:
a. At least two independent samples of the tank's contents
obtained by two technically qualified members of the facility staff
are analyzed, and
b. At least two technically qualified members of the Facility Staff
independently verify the release rate calculations and;
c. At least two technically qualified members of the Facility Staff
independently verify the discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this
pathway.
COMMENTS:
___ SAT
___ UNSAT
Critical
Step
STEP 3.: The required action if it takes 40 days to get parts to restore the
monitor to Operable status.
STANDARD:
Candidate identifes that if the inoperable instruments cannot be
restored to OPERABLE status within 30 days, the next Annual
Radioactive Effluent Report, pursuant to ODCM Administrative
Control 5.2, is to explain why the inoperability could not be
corrected within 30 days.
COMMENTS:
___ SAT
___ UNSAT
Critical
Step
Stop Time____
JPM -A.3
Page 6 of 7
Job Performance Checklist
STEP/STANDARD
SAT/UNSAT
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room
steps shall be performed for this JPM. I will provide initiating cues and reports on other
actions when directed by you. When you complete the task successfully, the objective
for this job performance measure will be satisfied. 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:
- The operating crew is preparing to release the Waste Gas Tank D.
- 0-RM-90-118A, Waste Gas Radiation Monitor, is inoperable.
- The monthly projected offsite dose limits have not been exceeded.
INITIATING CUES:
You are to identify
(1) Who must approve the release if the tank is to be released on the night shift at
2300.
(2) The required actions to allow a release with 0-RM-90-118A out of service.
(3) The required action if it takes 40 days to get parts to restore the monitor to
Operable status.
Page 1 of 12
SEQUOYAH NUCLEAR PLANT
ADMIN
SRO -A-4
JPM18
Classify the Event per the REP
(Primary System Leakage with Potential Loss of Cntmt)
Page 2 of 12
NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION
NUMBER
DESCRIPTION OF
REVISION
V
DATE
PAGES
AFFECTED
PREPARED/
REVISED BY:
7
Changed JPM steps 12 and 13 to not be
a critical steps. They do not meet the
definition of critical step in TRN-11.12.
N
11/23/99
All
SR Taylor
pen/ink
EPIP-1 Rev Change only
N
3/21/00
4
SR Taylor
8
EPIP-4 revision
Y
9/5/00
All
J P Kearney
pen/ink
EPIP-1 and 4 Rev Change only
N
12/21/00
4
W. R. Ramsey
pen/ink
EPIP-1 and 4 Rev Change only
N
07/31/01
4
W. R. Ramsey
pen/ink
Minor clarifications for to be
consistent with other REP JPMs.
N
12/27/01
All
L. Pauley
9
Incorporated pen/ink changes; revised to
recent EPIP changes; no impact on JPM
flow
N
8/16/02
4,7,8,9
J P Kearney
10
Incorporated changes to EPIP-1 and 4
Y
9/9/03
All
G S Poteet
12
Incorporated changes in EPIP-1 and 4.
Y
10/07/05
All
JJ Tricoglou
13
Incorporated changes in EPIP-1 and 4.
Add EAL 1.3.2 L as possible barrier loss.
Several minor chgs based on proced
chgs. Add non action step at ODS
notification step to address EPS failure.
Split NRC notification step into 2 steps.
Added should be made in 5 min to ODS
std
N
8/18/08
All
H J Birch
V - Specify if the JPM change will require another Validation (Y or N).
See cover sheet for criteria.
Page 3 of 12
SEQUOYAH NUCLEAR PLANT
Task:
Classify the Event per the REP (Primary System Leakage with Leakage Outside Cntmt)
JA/TA task # : 3440030302
(SRO)
3440190302
(SRO)
K/A Ratings:
2.4.29 (2.6/4.0)
2.4.38 (2.2/4.0)
2.4.30 (2.2/3.6)
2.4.40 (2.3/4.0)
2.4.37 (2.0/3.5)
2.4.41 (2.3/4.1)
Task Standard:
The event is classified as an SAE based on Primary System Leakage exceeding capacity of one charging
pump with Leakage Outside Cntmt. All notifications are made per the EPIP.
Evaluation Method :
Simulator ___X_____ In-Plant ________
- This JPM will be simulated
=======================================================================
Performer:
_______________________________________
NAME
Start Time ________
Performance Rating: SAT _____ UNSAT _____ Performance Time _____
Finish Time _______
Evaluator:
___________________________________/________
SIGNATURE
DATE
========================================================================
COMMENTS
Page 4 of 12
SPECIAL INSTRUCTIONS TO EVALUATOR:
1. Sequenced steps identified by an "s"
2. Any UNSAT requires comments
3. Initialize the simulator in IC-10 and leave in FREEZE.
4. Insure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.
5. Caution: DO NOT LET THE EXAMINEE FAX THE NOTIFICATION FORM
Validation Time: CR. 19 mins Local ____________
Tools/Equipment/Procedures Needed:
EPIP-1 and EPIP-4
References:
Reference
Title
Rev No.
A. EPIP-1
Emergency Plan Initiating Conditions Matrix
40
B. EPIP-4
Site Area Emergency
30
READ TO OPERATOR
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps of this JPM shall be
simulated. I will provide initiating cues and reports on other actions when directed by you. When you
complete the task successfully, the objective for this job performance measure will be satisfied. 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.
The simulator is NOT representative of the scenario you are about to address.
INITIAL CONDITIONS:
1. Unit 1 was operating at 100% (BOL) when indications of a primary system leak developed.
2. AOP-R.05, RCS Leak and Source Identification has been implemented; a second CCP was started due
to decreasing Pressurizer level.
3. The operators are attempting to identify the source of the leak.
4. Unit 2 is in MODE 6 with refueling operations in progress (core being unloaded).
INITIATING CUES:
1. The US has informed you, the SED, of the leak.
2. The operators have not identified the leak source but, AOP-R.05 is in progress at this time.
3. Using the following parameters provided to you by the control room operating crew, classify the event
according to the EPIPs and perform any required actions.
PZR level is 58% and stable.
Charging flow is 140 gpm.
Letdown flow is 0 gpm.
Cntmt. pressure is +0.2 psid and steady.
Cntmt. radiation (RM-90-106 & 112) has not changed since the event began.
RHR Pipe Break White Lights have just illuminated.
RM-90-101B is increasing.
Several Area Rad Monitors on El 669 and 690 are in Hi Rad.
Elements of this JPM are time critical
Page 5 of 12
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 1.:
Refers to EPIP-1 to determine level of event.
NOTE:
The leak rate is ~128 gpm (140 - 12 gpm RCP seal leakoff).
NOTE:
If the Operator declares an NOUE and enters EPIP-2 based on 2.5
"RCS leakage greater than 10 gpm then the critical step is not
satisfied.
STANDARD: Operator refers to EPIP-1, Section 1, Fission Product Barrier Matrix.
Operator determines that they have met the conditions for SITE AREA
EMERGENCY based on EAL 1.2.2 Potential LOSS (RCS
Leakage/LOCA) AND EAL 1.3.4 Potential LOSS (Containment Bypass)
[OR EAL 1.3.2 LOSS (Cntmt Normal w/ LOCA.)]
___ SAT
___ UNSAT
Critical Step
Task Start
Time
__________
STEP 2.:
Implements EPIP-4 SITE AREA EMERGENCY.
Enter time Declaration made_________________
Time from Task Start Time to Declaration:____________
STANDARD: Operator implements an SITE AREA EMERGENCY utilizing EPIP-4,
Section 3.1. Operator should classify the event within 15 minutes of the
time the task was accepted. Declaration Time should be consistent with
the time the examinee transitions from EPIP-1 to EPIP-4.
___ SAT
___ UNSAT
STEP 3.:
IF TSC is OPERATIONAL, (SED ttransferred to TSC), THEN. . .
CUE:
TSC is not manned at this time. You are the SED.
STANDARD: Operator N/As the step and continues with the procedure
____ SAT
____ UNSAT
STEP 4.:
RECORD time of Declaration.
STANDARD: Operator writes time of Declaration and continues..
___ SAT
___ UNSAT
Page 6 of 12
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 5.:
Activate Emergency Paging System (EPS).
Cue:
If operator asks if EPS has already been activated, respond that
the EPS has not been activated.
If Operator asks if Security Events are in progress, respond that
There are no security events in progress.
If Operator asks if any ongoing events make site access dangerous
to the life and health of emergency responders, respond that
There are no ongoing events that make site access dangerous to
the life and health of emergency responders.
STANDARD: Operator utilizes Touch Screen to activate the EPS.
___ SAT
___ UNSAT
Critical Step
STEP 6.:
Complete Appendix B, TVAN Initial Notification for Site Area
Emergency.
STANDARD:
Operator completes the Appendix using information from turnover
sheet and EPIP-1.
___ SAT
___ UNSAT
STEP 7.
IF EPS failed to activate from SQN THEN DIRECT ODS to activate
STANDARD:
Operator will N/A this step and the next step since EPS did not fail
____ SAT
____ UNSAT
Page 7 of 12
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 8.
READ completed Appendix B to ODS.
NOTE:
Enter time call is made to the ODS_________________
Time from Declaration (step 2) to ODS Notification:____________
a. This is a Drill
b. Their name, Shift Manager at SQN Plant.
c. SAE declared on UNIT 1
d. EAL No. Potential LOSS 1.2.2 and Potential LOSS 1.3.4 [Also
accept LOSS 1.3.2]
e. Brief description of incident: [Leak exceeding one CCP capacity
AND Unexpected VALID increase in Area or Vent Rad
Monitors OR Cntmt Normal w/ LOCA]
f.
Radiological Conditions [Minor releases within federally
approved limits
g. Event Declared: [Time and Date]
h. Protective Action Recommendation: [NONE]
i. Ask the ODS to repeat the information he has received to ensure
accuracy.
j. Fax information to ODS
Cue:
Role play as the ODS and acknowledge report.
STANDARD: Operator should notify the ODS within 5 minutes after declaration is
made giving the above information from Appendix B. ODS Shall be
notified in 10 minutes.
___ SAT
___ UNSAT
Critical Step
STEP 9.:
FAX Notification Form to the ODS.
Cue:
The support AUO will send the FAX for you.
Caution: DO NOT LET THE EXAMINEE FAX THE FORM
STANDARD: Operator addresses Faxing the Notification Form to the ODS.
___ SAT
___ UNSAT
STEP 10.:
Monitor for confirmation call from ODS that State/Local notifications are
complete.
Cue:
The support AUO will monitor for confirmation call.
STANDARD: Operator addresses monitoring for the call.
___ SAT
___ UNSAT
Page 8 of 12
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 11.:
IF ODS CANNOT be contacted within 10 minutes of declaration....
STANDARD:
Operator N/As this step and continues.
___ SAT
___ UNSAT
STEP 12.:
ENSURE MSS/WWM in the OSC (X6428) is monitoring Emergnecy
Response Organization (ERO) responses.
Cue:
Role play as person directed and report all positions responded.
STANDARD:
Operator monitors responses by using touch screen or directs another
person to do this task.
___ SAT
___ UNSAT
STEP 13.:
PERFORM Appendix A, Notifiations and Announcements.
CUE:
If Operator attempts to delegate the assignment, inform them that
no one is available to delegate this function.
The following steps are from Appendix A of EPIP-4.
STEP 14.:
IF there has been a security threat THEN, NOTIFY Security Shift
Supervisor to IMPLEMENT SSI-1.
Cue:
There have been no reports of a security threat.
STANDARD: Operator should N/A this step.
___ SAT
___ UNSAT
STEP 15.:
NOTIFY Radiation Protection: STATE: A SITE AREA EMERGENCY
HAS BEEN DECLARED BASED ON LEAK EXCEEDING ONE CCP
CAPACITY AND UNEXPECTED VALID INCREASE IN AREA OR VENT
RAD MONITORS [OR Cntmt Normal w/ LOCA], AFFECTING UNIT 1.
Cue:
Acknowledge the report.
STANDARD: Operator makes the notification and directs Radcon to implement EPIP-
14 AND CECC EPIP-9.
___ SAT
___ UNSAT
Page 9 of 12
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 16.:
NOTIFY personnel in the Chemistry Lab: STATE A SITE AREA
EMERGENCY HAS BEEN DECLARED BASED ON LEAK EXCEEDING
ONE CCP CAPACITY AND UNEXPECTED VALID INCREASE IN
AREA OR VENT RAD MONITORS [OR Cntmt Normal w/ LOCA],
AFFECTING UNIT 1.
Cue:
Acknowledge the report.
STANDARD: Operator makes the notification and directs Chemistry to implement
EPIP-14.
___ SAT
___ UNSAT
STEP 17.:
Announce to plant personnel on the old Plant PA and x4800:
ATTENTION PLANT PERSONNEL. ATTENTION PLANT
PERSONNEL. A SITE AREA EMERGENCY HAS BEEN DECLARED
BASED ON Potential LOSS (RCS LEAKAGE/LOCA) AND POTENTIAL
LOSS (CONTAINMENT BYPASS) [OR Cntmt Normal w/ LOCA].
AFFECTING UNIT 1. ALL TSC AND OSC PERSONNEL REPORT TO
THE EMERGENCY FACILITIES IMMEDIATELY. Repeat the
announcement.
STANDARD: Operator makes the PA announcements.
___ SAT
___ UNSAT
STEP 18.:
Notify the Plant Management in accordance with SPP-3.5.
NOTE:
Activation of the EPS will make the Plant Management aware of the
REP actuation, however administrative procedures require
notification.
Cue:
Acknowledge the report as:
Plant Manager
Senior Vice President (SVP), Nuclear Operations
Duty Plant Manager
STANDARD: Operator contacts Plant Management and informs him of the REP
classification and provides SAE information (Appendix B)
___ SAT
___ UNSAT
STEP 19.:
Notify the On Call resident inspector and NRC via ENS in accordance
with SPP-3.5.
Cue:
As the NRC, acknowledge the report.
STANDARD: Operator should notify the NRC (headquarters) as soon as practicable,
but within 1 Hr. of declaration of the event. Operator provides SAE
information (Appendix B)
___ SAT
___ UNSAT
Critical Step
Page 10 of 12
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
STEP 20.:
Notify the NRC of plan activation via ENS phone.
Cue:
As the NRC, acknowledge the report.
STANDARD: Operator should notify the NRC (headquarters) as soon as practicable,
but within 1 Hr. of declaration of the event. Operator provides SAE
information (Appendix B).
____ SAT
____ UNSAT
Time Critical
Step
Time of
Notification:
The following steps are from Section 3.3, MONITOR CONDITIONS OF EPIP-4.
STEP 21.:
MONITOR radiation monitors. When indication of an unplanned
radiological release, Then ENSURE Dose Assessment is performed.
Cue:
Per initiating cues, RM 101B is increasing.
When examinee uses ICS or RM indication to determine effluent
radiation levels per Tables 7-1and 7-2 of EPIP-1, cue the operator:
0-RM-90-101B: ~ 7.9E+4 cpm
1-RM-90-400: ~ 4E+4 µCi/s
0-RM-90-400: ~ 1E+3 mr/hr
All other RM reading ~ normal
Field Surveys are in progress
STANDARD: Operator directs Radiation Protection to perform a dose assessment per
EPIP-13, provides type of event, release path, and expected duration.
The event type is a LOCA outside containment, release path through the
AB stack.
___ SAT
___ UNSAT
Critical Step
STEP 22.:
If personnel accountability has not been previously initiated, THEN
Activate assembly & accountability using EPIP-8, Appendix C.
Cue:
The U2 CRO will perform EPIP-8 Appendix C or Role play as
Security Shift Supervisor and acknowledge.
STANDARD:
1.
Operator addresses EPIP-8, Appendix C.
___ SAT
___ UNSAT
Critical Step
STEP 23.:
MONITOR plant conditions AND EVALUATE using EPIP-1......
Cue:
If operator begins Monitoring plant conditions, THEN tell him The
TSC is staffed and will COMPLETE SAE follow-up Form.
STANDARD:
Operator addresses completing SAE follow-up Form.
___ SAT
___ UNSAT
Stop Time____
Page 11 of 12
Job Performance Checklist:
STEP/STANDARD
SAT/UNSAT
End of JPM
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps of this
JPM shall be simulated. I will provide initiating cues and reports on other actions when
directed by you. When you complete the task successfully, the objective for this job
performance measure will be satisfied. 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.
The simulator is NOT representative of the scenario you are about to address.
INITIAL CONDITIONS:
1. Unit 1 was operating at 100% (BOL) when indications of a primary system leak
developed.
2. AOP-R.05, RCS Leak and Source Identification has been implemented; a second
CCP was started due to decreasing Pressurizer level.
3. The operators are attempting to identify the source of the leak.
4. Unit 2 is in MODE 6 with refueling operations in progress (core being unloaded).
INITIATING CUES:
1. The US has informed you, the SED, of the leak.
2. The operators have not identified the leak source but, AOP-R.05 is in progress at this
time.
3. Using the following parameters provided to you by the control room operating crew,
classify the event according to the EPIPs and perform any required actions.
- PZR level is 58% and stable.
- Charging flow is 140 gpm.
- Letdown flow is 0 gpm.
- Cntmt. pressure is +0.2 psid and steady.
- Cntmt. radiation (RM-90-106 & 112) has not changed since the event began.
- RHR Pipe Break White Lights have just illuminated.
- RM-90-101B is increasing.
- Several Area Rad Monitors on El 669 and 690 are in Hi Rad.
Elements of this JPM are time critical