ML13248A035

Initial Exam 2013-301 Draft Administrative JPMs

ML13248A035
Person / Time
Site:	Oconee
Issue date:	09/04/2013
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-269/13-301, 50-270/13-301, 50-287/13-301
Download: ML13248A035 (70)

Text

Admin-130 1.1S Page 1 of 11 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-130 Perform Manual RCS Leakage Calculation and TS Determination (SRO Only)

CANDIDATE EXAMINER

Admin-130 1.1S Page 2 of 11 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Perform Manual RCS Leakage Calculation and TS Determination Alternate Path:

N/A Facility JPM #:

CRO-43 K/A Rating(s):

System: Gen K/A: 2.1.7 Rating: 4.4/4.7 Task Standard:

RCS Leakage is calculated per the attached key.

TS 3.4.13 Condition A entered.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator _____ In-Plant __ ___ Classroom __X___ Perform __X___ Simulate __ __

References:

PT/O/A/0600/001A (Loss Of Computer)

PT/1/A/0600/010 (Reactor Coolant Leakage)

TS 3.4.13 (RCS Operational LEAKAGE)

Validation Time: 18 minutes Time Critical: NO

=========================================================================

Candidate: _______________________________________ Time Start: ____________

NAME Time Finish: ___________

Performance Rating: SAT ______ UNSAT ______ Performance Time ___________

Examiner: ______________________________ ____________________________________/_________

NAME SIGNATURE DATE

=========================================================================

COMMENTS

Admin-130 1.1S Page 3 of 11 SIMULATOR OPERATOR INSTRUCTIONS NONE

Admin-130 1.1S Page 4 of 11 Tools/Equipment/Procedures Needed:

PT/1/A/0600/010 (Reactor Coolant Leakage) Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet)

Technical Specifications READ TO OPERATOR 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 Oconee Unit 1 computer repairs are expected to be extended through turnover for hardware replacement. The Loss of Computer procedure PT/O/A/0600/001A, Loss of Computer, is in progress; however an RCS Leakage Calculation has not been performed during this shift.

INITIATING CUES The OSM directs you to perform a manual RCS leakage calculation per PT/1A/0600/010 (Reactor Coolant Leakage) Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Evaluate leakage and determine if any Tech Spec Conditions that apply.

Assume all leakage is unidentified but is NOT Pressure Boundary leakage Manual RCS Leakage Data Parameter Initial Final Time 0015 0115 Pzr level 219.0 inches 219.5 inches Tave Indication 579.0°F 579.1°F Quench Tank Level 86.5 inches 86.5 inches LDST Level 76.7 inches 74.0 inches Power Range NI 100.0% 100.1%

RCS NR Pressure 2150 psig 2150 psig Group 7 Control Rod Position 92.7% 92.7%

Admin-130 1.1S Page 5 of 11 START TIME: _______

STEP 1: Step 2.1 Record Initial Data in "Table #1".

Value Initial Data Minus Final Data Equals Change PZR Level 219.0 inches - =

RCS Temp 579.0°F - =

QT Level 86.5 inches - = ____Sat LDST Level 76.7 inches - =

Rx Power 100.0% - =

RCS Press 2150 psig - = ____Unsat CR Pos 92.7% - =

STANDARD: Candidate enters initial set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) from the initiating cue.

COMMENTS STEP 2: Step 2.2 Record time Initial Data recorded: ____________

____Sat STANDARD: Candidate enters 0015 (from initiating cue)

COMMENTS ____Unsat

Admin-130 1.1S Page 6 of 11 STEP 3: Step 2.3 After 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, record Final Data in "Table #1".

Value Initial Data Minus Final Data Equal Change PZR Level 219.0 inches - 219.5 inches =

RCS Temp 579.0°F - 579.1°F =

QT Level 86.5 inches - 86.5 inches =

LDST Level 76.7 inches - 74.0 inches = ____Sat Rx Power 100.0% - 100.1% =

RCS Press 2150 psig - 2150 psig =

CR Pos 92.7% - 92.7% = ____Unsat STANDARD: Candidate enters final set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) (from initiating cue)

COMMENTS STEP 4: Step 2.4 Record time Final Data recorded: ____________

____Sat STANDARD: Candidate enters 0115 COMMENTS ____Unsat STEP 5: Step 2.5 CRITICAL STEP Record time elapsed time: ____________ minutes STANDARD: Candidate enters 60 minutes

____Sat COMMENTS

____Unsat

Admin-130 1.1S Page 7 of 11 STEP 6: Step 2.6 CRITICAL STEP Calculate and record "Change" values in "Table # 1"..

Value Initial Data Minus Final Data Equal Change PZR Level 219.0 inches - 219.5 inches = -.5 inches RCS Temp 579.0°F - 579.1°F = -.1°F ____Sat QT Level 86.5 inches - 86.5 inches = 0 inches LDST Level 76.7 inches - 74.0 inches = +2.7 inches Rx Power 100.0% - 100.1% = -.1% ____Unsat RCS Press 2150 psig - 2150 psig = 0 psig CR Pos 92.7% - 92.7% = 0%

STANDARD: Candidate calculates the change in data and fills in Table 1 change column.

COMMENTS STEP :7 Step 2.7 CRITICAL STEP Calculate Corrected Pzr Level Change:

STANDARD: -0.5 inches - (6.831 inches/°F X -.1°F) = +.1831 inches ____Sat

(+.18 to +.2)

____Unsat COMMENTS STEP :8 Step 2.8 CRITICAL STEP Convert Corrected Pzr Level Change to gallons STANDARD: +.1831 inches X 14.364 gallons / inch = +2.63 gallons

____Sat

(+.18 to +.2) ( 2.585 to 2.873)

COMMENTS ____Unsat

Admin-130 1.1S Page 8 of 11 STEP :9 Step 2.9 CRITICAL STEP Convert QT Level Change to gallons:

STANDARD: No change

____Sat COMMENTS

____Unsat STEP :10 Step 2.10 CRITICAL STEP Convert LDST Level Change to gallons STANDARD: +2.7 inches X 30.956 gallons / inch = +83.5812 gallons

____Sat

(+83.5 to +83.6)

COMMENTS ____Unsat STEP :11 Step 2.11 CRITICAL STEP Calculate Total Volume Change STANDARD: 2.63 gallons + 0 gallons + 83.5812 gallons = 86.2112 gallons

____Sat

( 2.585 to 2.873) (+83.5 to +83.6) (86.08 to 86.47)

COMMENTS ____Unsat STEP :12 Step 2.12 CRITICAL STEP Calculate "RCS Unidentified Leakage Rate" STANDARD: 86.2112 gallons / 60 minutes = 1.437 gpm

____Sat (86.08 to 86.47) (1.434 to 1.441)

COMMENTS ____Unsat

Admin-130 1.1S Page 9 of 11 STEP :13 Refer to TS 3.4.13 RCS Operational LEAKAGE CRITICAL STEP STANDARD: Determine leakage exceeds 1 gpm unidentified and TS 3.4.13 Condition A applies. Reduce LEAKAGE to within limits with a completion ____Sat time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

____Unsat COMMENTS END TASK STOP TIME: ____________

Admin-130 1.1S Page 10 of 11 CRITICAL STEP EXPLANATIONS STEP # Explanation 5 Necessary data calculation to properly determine manual RCS leakage rate.

6 Necessary data calculation to properly determine manual RCS leakage rate.

7 Necessary data calculation to properly determine manual RCS leakage rate.

8 Necessary data calculation to properly determine manual RCS leakage rate.

9 Necessary data calculation to properly determine manual RCS leakage rate.

10 Necessary data calculation to properly determine manual RCS leakage rate.

11 Necessary data calculation to properly determine manual RCS leakage rate.

12 Necessary data calculation to properly determine manual RCS leakage rate.

13 Necessary to refer to correct TS and conclude 1 gpm unidentified is exceeded.

1.1S CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Oconee Unit 1 computer repairs are expected to be extended through turnover for hardware replacement. The Loss of Computer procedure PT/O/A/0600/001A, Loss of Computer, is in progress; however an RCS Leakage Calculation has not been performed during this shift.

INITIATING CUES The OSM directs you to perform a manual RCS leakage calculation per PT/1A/0600/010 (Reactor Coolant Leakage) Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Evaluate leakage and determine if any Tech Spec Conditions that apply.

Assume all leakage is unidentified but is NOT Pressure Boundary leakage Manual RCS Leakage Data Parameter Initial Final Time 0015 0115 Pzr level 219.0 inches 219.5 inches Tave Indication 579.0°F 579.1°F Quench Tank Level 86.5 inches 86.5 inches LDST Level 76.7 inches 74.0 inches Power Range NI 100.0% 100.1%

RCS NR Pressure 2150 psig 2150 psig Group 7 Control Rod Position 92.7% 92.7%

Admin-131 1.1R Page 1 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-131 Perform Manual RCS Leakage Calculation (RO Only)

CANDIDATE EXAMINER

Admin-131 1.1R Page 2 of 10 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Perform Manual RCS Leakage Calculation Alternate Path:

N/A Facility JPM #:

CRO-43 K/A Rating(s):

System: Gen K/A: 2.1.7 Rating: 4.4/4.7 Task Standard:

RCS Leakage is calculated per the attached key.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator _____ In-Plant __ ___ Classroom __X___ Perform __X___ Simulate __ __

References:

PT/O/A/0600/001A (Loss Of Computer)

PT/1/A/0600/010 (Reactor Coolant Leakage)

Validation Time: 18 minutes Time Critical: NO

=========================================================================

Candidate: _______________________________________ Time Start: ____________

NAME Time Finish: ___________

Performance Rating: SAT ______ UNSAT ______ Performance Time ___________

Examiner: ______________________________ ____________________________________/_________

NAME SIGNATURE DATE

=========================================================================

COMMENTS

Admin-131 1.1R Page 3 of 10 SIMULATOR OPERATOR INSTRUCTIONS NONE

Admin-131 1.1R Page 4 of 10 Tools/Equipment/Procedures Needed PT/1/A/0600/010 (Reactor Coolant Leakage) Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet)

READ TO OPERATOR 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 Oconee Unit 1 computer repairs are expected to be extended through turnover for hardware replacement. The Loss of Computer procedure PT/O/A/0600/001A, Loss of Computer, is in progress, however an RCS Leakage Calculation has not been performed during this shift.

INITIATING CUES The Control Room SRO directs you to perform a manual RCS leakage calculation per PT/1A/0600/010 (Reactor Coolant Leakage) Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Manual RCS Leakage Data Parameter Initial Final Time 0015 0115 Pzr level 219.0 inches 219.5 inches Tave Indication 579.0°F 579.1°F Quench Tank Level 86.5 inches 86.5 inches LDST Level 76.7 inches 74.0 inches Power Range NI 100.0% 100.1%

RCS NR Pressure 2150 psig 2150 psig Group 7 Control Rod Position 92.7% 92.7%

Admin-131 1.1R Page 5 of 10 START TIME: _______

STEP 1: Step 2.1 Record Initial Data in "Table #1".

Value Initial Data Minus Final Data Equals Change PZR Level 219.0 inches - =

RCS Temp 579.0°F - =

QT Level 86.5 inches - = ____Sat LDST Level 76.7 inches - =

Rx Power 100.0% - =

RCS Press 2150 psig - = ____Unsat CR Pos 92.7% - =

STANDARD: Student enters initial set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) from the initiating cue.

COMMENTS STEP 2: Step 2.2 Record time Initial Data recorded: ____________

____Sat STANDARD: Student enters 0015 (from initiating cue)

COMMENTS ____Unsat

Admin-131 1.1R Page 6 of 10 STEP 3: Step 2.3 After 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, record Final Data in "Table #1".

Value Initial Data Minus Final Data Equal Change PZR Level 219.0 inches - 219.5 inches =

RCS Temp 579.0°F - 579.1°F =

QT Level 86.5 inches - 86.5 inches =

LDST Level 76.7 inches - 74.0 inches = ____Sat Rx Power 100.0% - 100.1% =

RCS Press 2150 psig - 2150 psig =

CR Pos 92.7% - 92.7% = ____Unsat STANDARD: Student enters final set of data into Table #1 of Enclosure 13.3 (Manual Leakage Calculation Data Sheet) (from initiating cue)

COMMENTS STEP 4: Step 2.4 Record time Final Data recorded: ____________

____Sat STANDARD: Student enters 0115 COMMENTS ____Unsat STEP 5: Step 2.5 CRITICAL STEP Record time elapsed time: ____________ minutes STANDARD: Student enters 60 minutes

____Sat COMMENTS

____Unsat

Admin-131 1.1R Page 7 of 10 STEP 6: Step 2.6 CRITICAL STEP Calculate and record "Change" values in "Table # 1"..

Value Initial Data Minus Final Data Equal Change PZR Level 219.0 inches - 219.5 inches = -.5 inches RCS Temp 579.0°F - 579.1°F = -.1°F ____Sat QT Level 86.5 inches - 86.5 inches = 0 inches LDST Level 76.7 inches - 74.0 inches = +2.7 inches Rx Power 100.0% - 100.1% = -.1% ____Unsat RCS Press 2150 psig - 2150 psig = 0 psig CR Pos 92.7% - 92.7% = 0%

STANDARD: Student calculates the change in data and fills in Table 1 change column.

COMMENTS STEP :7 Step 2.7 CRITICAL STEP Calculate Corrected Pzr Level Change:

____Sat STANDARD: -0.5 inches - (6.831 inches/°F X -.1°F) = +.1831 inches

(+.18 to +.2)

____Unsat COMMENTS STEP :8 Step 2.8 CRITICAL STEP Convert Corrected Pzr Level Change to gallons STANDARD: +.1831 inches X 14.364 gallons / inch = +2.63 gallons

____Sat

(+.18 to +.2) ( 2.585 to 2.873)

COMMENTS

____Unsat

Admin-131 1.1R Page 8 of 10 STEP :9 Step 2.9 CRITICAL STEP Convert QT Level Change to gallons:

STANDARD: No change

____Sat COMMENTS

____Unsat STEP :10 Step 2.10 CRITICAL STEP Convert LDST Level Change to gallons STANDARD: +2.7 inches X 30.956 gallons / inch = +83.5812 gallons

____Sat

(+83.5 to +83.6)

COMMENTS ____Unsat STEP :11 Step 2.11 CRITICAL STEP Calculate Total Volume Change STANDARD: 2.63 gallons + 0 gallons + 83.5812 gallons = 86.2112 gallons

____Sat (2.585 to 2.873) (+83.5 to +83.6) (86.08 to 86.47)

COMMENTS

____Unsat STEP :12 Step 2.12 CRITICAL STEP Calculate "RCS Unidentified Leakage Rate" STANDARD: 86.2112 gallons / 60 minutes = 1.437 gpm

____Sat (86.08 to 86.47) (1.434 to 1.441)

COMMENTS ____Unsat END TASK STOP TIME: ____________

Admin-131 1.1R Page 9 of 10 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 5 Necessary data calculation to properly determine manual RCS leakage rate.

6 Necessary data calculation to properly determine manual RCS leakage rate.

7 Necessary data calculation to properly determine manual RCS leakage rate.

8 Necessary data calculation to properly determine manual RCS leakage rate.

9 Necessary data calculation to properly determine manual RCS leakage rate.

10 Necessary data calculation to properly determine manual RCS leakage rate.

11 Necessary data calculation to properly determine manual RCS leakage rate.

12 Necessary data calculation to properly determine manual RCS leakage rate.

1.1R CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Oconee Unit 1 computer repairs are expected to be extended through turnover for hardware replacement. The Loss of Computer procedure PT/O/A/0600/001A, Loss of Computer, is in progress, however an RCS Leakage Calculation has not been performed during this shift.

INITIATING CUES The Control Room SRO directs you to perform a manual RCS leakage calculation per PT/1A/0600/010 (Reactor Coolant Leakage) Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Manual RCS Leakage Data Parameter Initial Final Time 0015 0115 Pzr level 219.0 inches 219.5 inches Tave Indication 579.0°F 579.1°F Quench Tank Level 86.5 inches 86.5 inches LDST Level 76.7 inches 74.0 inches Power Range NI 100.0% 100.1%

RCS NR Pressure 2150 psig 2150 psig Group 7 Control Rod Position 92.7% 92.7%

Admin 140 - 1.2B Page 1 of 12 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-140 CALCULATE AN ESTIMATED CRITICAL ROD POSITION CANDIDATE EXAMINER

Admin 140 - 1.2B Page 2 of 12 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Calculate an Estimated Critical Rod Position Alternate Path:

No Facility JPM #:

CRO-037 K/A Rating(s):

System: GEN K/A: 2.1.19 Rating: 3.9/3.8 Task Standard:

ECP calculation for 1200 on 06/13/13 is Group 6 @ 58% +/- 5% withdrawn.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X___ In-Plant _____ Perform __X___ Simulate ____

References:

PT/1/A/1103/15 (Reactivity Balance Procedure), Encl. 13.4 (Computerized ECP Calculation)

PT/0/A/1103/020 (Power Maneuvering Predictions)

Rho Calc computer program Validation Time: 17 minutes Time Critical: NO

========================================================================

Candidate: _______________________________________ Time Start: _________

NAME Time Finish: ________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ____________________________________/________

NAME SIGNATURE DATE

========================================================================

COMMENTS

Admin 140 - 1.2B Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS:

None

Admin 140 - 1.2B Page 4 of 12 Tools/Equipment/Procedures Needed:

PT/1/A/1103/15 (Reactivity Balance Procedure), Encl. 13.4 (Computerized ECP Calculation)

Printout of ECP HELP file Computer that is NOT connected to LAN Rho Calc program running from DVD READ TO OPERATOR 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:

Unit 1 operated from initial new cycle startup to 6/12/13 at 100% power A Main Turbine trip resulted in a reactor trip at 1301 on 6/12/13 EFPD = 110 PRESENT CONDITIONS:

Date/Time = 6/13/13 at 0300 The cause of the trip is understood and repaired RCS Boron = 1337 RCS Temperature = 532oF.

Group 8 positioned at 35% withdrawn INITIATING CUES:

The Control Room SRO directs you to calculate an original Estimated Critical Rod Position for 1200 today (06/13/13) by performing PT/1/A/1103/015 (Reactivity Balance Procedure) Encl.

13.4 (Computerized Estimated Critical Rod Position Calculation) through step 2.7.

Admin 140 - 1.2B Page 5 of 12

. SIMULATOR OPERATOR INSTRUCTIONS NONE

Admin 140 - 1.2B Page 6 of 12 START TIME: _______

STEP 1: Step 2.1 This enclosure must be performed twice - the second is the separate ___ SAT verification. Circle whether this is the original or the verification.

STANDARD: Candidate should check original. ___ UNSAT Continue to Step 2.2 COMMENTS:

STEP 2: Step 2.2 Ensure that the OAC B-10 program has been updated per Reference ___ SAT 2.10 (N/A for original calculation).

STANDARD: Candidate should N/A this step. ___ UNSAT Continue to Step 2.3 COMMENTS:

NOTE: The intent is to verify that the measured RCS % design flow is greater than that required. RPS flows can be expected to deviate from baseline. ___ SAT STEP 3: Step 2.3 IF returning from a forced outage, perform an RCS flow check using POWCALC.XLS and attach results to this enclosure. (N/A for original ___ UNSAT calculation)

STANDARD: Candidate should N/A this step.

Continue to Step 2.4 COMMENTS:

Admin 140 - 1.2B Page 7 of 12 STEP 4: Step 2.4 If returning from a forced outage, verify the measured % Design Flow is ___ SAT

<116.4% design flow (Reference 2.7) using the results from POWERCALC.XLS. (N/A for original calculation)

___ UNSAT STANDARD: Candidate should N/A this step.

Continue to Step 2.5 COMMENTS:

CAUTION: IF the power history information from the last equilibrium Xe/Sm condition is NOT input into the code, significant error may result. ___ SAT NOTE: If conducting an initial cycle startup the power history is 0% FP.

___ UNSAT STEP 5: Step 2.5 If returning from a forced outage:

• Obtain the power history back to the last time of Xenon equilibrium to perform the Xenon calculation from a source such as PI Server, OAC, RO Log, etc.

• Attach actual power history to this enclosure.

STANDARD: Power history is provided with the Candidates Cue sheet.

CUE: Indicate to the candidate that the provided power history is an acceptable source of the power history for this JPM.

COMMENTS:

STEP 6: Step 2.6 Open RhoCalc.

___ SAT STANDARD: Candidate locates the RhoCalc icon on the PC and opens the program.

Note: For the purposes of this JPM the RhoCalc program will already be open on ___ UNSAT the computer.

Continue to Step 2.7 COMMENTS:

Admin 140 - 1.2B Page 8 of 12 Cue: If anytime during this JPM the candidate attempts to open the HELP file on *CRITICAL STEP the top menu, provide the candidate with the hard copy of the HELP file that is attached. Selecting the HELP file from the menu will result in the

___ SAT program closing and all data entered will be lost since it is being run from a disc rather than the DAE.

STEP 7: Step 2.7.1 ___ UNSAT INPUT appropriate data for the estimated critical rod position calculation, STANDARD: Under the Input Information tab, candidate inserts the data given to him into the program.

Cue: When the candidate begins to input data an error message that reads Error connecting to PI server ons0pi PI error will be received. Inform the candidate to select OK and continue. The message is a result of not being connected to the LAN but will NOT have an impact on the ECP.

• Name - Candidates name

• *Select Unit 1

• *RCS Temperature - 532°F

• *Current Boron Concentration - 1338 ppm

• *EFPD - 110

• *Group 8 position - 35% withdrawn

• Fully Conditioned fuel status

• 4 RCPs in operation

• NO inoperable rods COMMENTS:

Admin 140 - 1.2B Page 9 of 12 STEP 8: Step 2.7.1 (cont.) CRITICAL STEP INPUT appropriate data for the estimated critical rod position calculation,

___ SAT STANDARD: Under the Power History tab, candidate inserts the power history given to him into the program.

• Power History: (Standard is met as long as power history entered will

___ UNSAT result in projection going out to at least 6/14 at 1300 but it is acceptable if the ECP forecasts beyond that point) 6/12 @ 1300 - 100%

6/12 @ 1301 - 0%

• 6/13 @ 1200 - 0%

• Examiner Note: Entering any final time/date > the above time is acceptable.

Cue: If candidate attempts to open the HELP file on the top menu, provide the candidate with the hard copy of the HELP file that is attached. Selecting the HELP file from the menu will result in the program closing and all data entered will be lost since it is being run from a disc rather than the DAE.

COMMENTS:

STEP 9: Step 2.7.2 CRITICAL STEP Select Calculate ECP.

___ SAT STANDARD: Candidate selects the Calculations tab and then selects the Calculate ECP button NOTE/CUE: The three windows related to Boron Correction factors will all read 0. ___ UNSAT This is because the program is not connected to the Pi server to obtain RCS boron information from the unit. It will NOT have an impact on the ECP.

COMMENTS:

Admin 140 - 1.2B Page 10 of 12 STEP 10: Step 2.7.3 Print the ECP

___ SAT STANDARD: Candidate prints the ECP

___ UNSAT COMMENTS:

STEP 11: Step 2.7.3 (continued) CRITICAL STEP

___ SAT STANDARD: The candidate, using the ECP printed out, finds 1200 on 06/13/13 and determines that the ECP is Group 6 at 58%. The candidates answer must be +/- 5% (53% to 63%)

___ UNSAT COMMENTS:

END TASK STOP TIME: ____________

Admin 140 - 1.2B Page 11 of 12 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 7 Candidate needs to perform this step for the computer to calculate the ECP 8 Candidate needs to perform this step for the computer to calculate the ECP 9 Candidate needs to perform this step for the computer to calculate the ECP 11 Candidate needs to perform this step to determine what the critical position is for the time given.

1.2B CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 operated from initial new cycle startup to 6/12/13 at 100% power A Main Turbine trip resulted in a reactor trip at 1301 on 6/12/13 EFPD = 110 PRESENT CONDITIONS:

Date/Time = 6/13/13 at 0300 The cause of the trip is understood and repaired RCS Boron = 1337 RCS Temperature = 532oF.

Group 8 positioned at 35% withdrawn INITIATING CUES:

The Control Room SRO directs you to calculate an original Estimated Critical Rod Position for 1200 today (06/13/13) by performing PT/1/A/1103/015 (Reactivity Balance Procedure) Encl.

13.4 (Computerized Estimated Critical Rod Position Calculation) through step 2.7.

Admin-240 2R Page 1 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-240 Perform SG Downcomer Temperature Surveillance CANDIDATE EXAMINER

Admin-240 2R Page 2 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Perform SG Downcomer Temperature Surveillance Alternate Path:

N/A Facility JPM #:

Admin-237 K/A Rating(s):

System: Gen K/A: 2.2.12 Rating: 3.7/4.1 Task Standard:

Perform SG Downcomer Temperature Surveillance by procedure for the 1A (ONLY) SG and determine that the surveillance requirement is NOT met for either of the specified computer points.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator ___ __ In-Plant __ ___ Classroom __X__ Perform __X__ Simulate _____

References:

OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl 4.1 (Mode 1 & 2)

OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.19 (Channel Check Of OTSG Downcomer Temperatures)

Validation Time: 18 minutes Time Critical: NO

========================================================================

Candidate: _______________________________________ Time Start: _________

NAME Time Finish: ________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ____________________________________/________

NAME SIGNATURE DATE

========================================================================

COMMENTS

Admin-240 2R Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS NONE

Admin-240 2R Page 4 of 9 Tools/Equipment/Procedures Needed:

OP/1/A/1105/014 (Control Room Instrumentation Operation And Information)

OAC Screen capture image for SG information READ TO OPERATOR 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:

Reactor power = 75%

OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) in progress.

INITIATING CUES:

CR SRO directs you to perform OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) on page 6 of 15 component check for the 1A SG Downcomer Temperature.

Admin-240 2R Page 5 of 9 START TIME: _______

STEP 1: Enclosure 4.1 (page 6 of 15) CRITICAL STEP Verify All SG Downcomer Temperature computer points agree within 3°F of each other.

___ SAT IF All SG Downcomer Temperatures DO NOT agree within 3°F of each other, then perform Enclosure "Channel Check Of OTSG Downcomer Temperatures".

___ UNSAT O1E2008 - 528.87°F O1E2009 - 538.97°F O1E2012 - 532.78°F O1E2013 - 533.65°F STANDARD: Determine that the above OAC points do NOT agree within 3°F of each other, and perform Enclosure 4.19 "Channel Check of OTSG Downcomer Temperatures".

COMMENTS:

STEP 2: Step 3.1 (Enclosure 4.19)

Determine saturation temperature for 1A OTSG based on power level and 1A OTSG outlet pressure as follows:

___ SAT Step 3.1.1 Determine 1A OTSG outlet pressure using any one of the following computer points:

___ UNSAT

• O1E2281 - 888.5 psig

• O1E2283 - 888.5 psig

• O1E2031 - 888.5 psig

• O1E2032 - 888.5 psig STANDARD: Using the OAC determine that 1A OTSG pressure is 888.5.

COMMENTS:

Admin-240 2R Page 6 of 9 STEP 3: Step 3.1.2 CRITICAL STEP Using table in Section 4, determine the 1A OTSG saturation temperature based on power level and 1A OTSG Outlet Pressure obtained in step 3.1.1.

___ SAT

____________ 1A OTSG saturation temperature STANDARD: Determine that 1A OTSG saturation temperature is 533.9ºF by using ___ UNSAT the table in section 4.

COMMENTS:

STEP 4: Step 3.1.3 CRITICAL STEP Compare O1E2008 SG Lower Downcomer Temperature Loop A to the 1A OTSG saturation temperature determined in step 3.1.2:

___ SAT Step 3.1.4 IF O1E2008 SG Lower Downcomer Temperature Loop A is NOT within

+/- 4.9 °F of the 1A OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable. ___ UNSAT STANDARD: Determine that O1E2008 SG Lower Downcomer Temperature Loop A (528.87°F) is NOT within +/- 4.9 °F of the 1A OTSG saturation temperature (533.9°F), and entry Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable is required.

COMMENTS:

Admin-240 2R Page 7 of 9 STEP 5: Step 3.1.5 CRITICAL STEP Compare O1E2009 SG Lower Downcomer Temperature Loop A to the 1A OTSG saturation temperature determined in step 3.1.2:

___ SAT Step 3.1.6 IF O1E2009 SG Lower Downcomer Temperature Loop A is NOT within

+/- 4.9 °F of the 1A OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable. ___ UNSAT STANDARD: Determine that O1E2009 SG Lower Downcomer Temperature Loop A (538.97) is NOT within +/- 4.9 °F of the 1A OTSG saturation temperature (533.9°), and entry Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable is required.

Cue: Inform the candidate that another operator will complete this procedure.

COMMENTS:

END TASK STOP TIME: ____________

Admin-237 Page 8 of 9 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 Step is required to complete the surveillance.

3 Step is required to complete the surveillance.

4 Determining that the computer points in both Step 4 and Step 5 are out of the allowable band is critical to ensure that SLC 16.7.5 Condition A is not exited prior to BOTH computer points being repaired.

5 Determining that the computer points in both Step 4 and Step 5 are out of the allowable band is critical to ensure that SLC 16.7.5 Condition A is not exited prior to BOTH computer points being repaired.

2R CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Reactor power = 75%

OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 &

2) in progress.

INITIATING CUES:

CR SRO directs you to perform OP/1/A/1105/014 (Control Room Instrumentation Operation And Information) Encl. 4.1 (Mode 1 & 2) on page 6 of 15 component check for the 1A SG Downcomer Temperature.

ADMIN-241 2S Page 1 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-241 Complete a Surveillance Evaluation (SRO ONLY)

CANDIDATE EXAMINER

ADMIN-241 2S Page 2 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Complete PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.12 (Surveillance Evaluation)

Alternate Path:

N/A Facility JPM #:

New K/A Rating(s):

System: Gen K/A: 2.2.12 Rating: 3.7/4.1 Task Standard:

Complete PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.12 (Surveillance Evaluation)

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __ ___ In-Plant ___ ___ Classroom __ X___ Perform __ X__ Simulate_ __

References:

PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) page 25 of 26 PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.9 (RCP Power Supply Verification)

PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.12 (Surveillance Evaluation)

Validation Time: 20 min. Time Critical: No

=========================================================================

Candidate: _______________________________________ Time Start: _________

NAME Time Finish: ________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

ADMIN-241 2S Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS NONE

ADMIN-241 2S Page 4 of 9 Tools/Equipment/Procedures Needed:

PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) page 25 of 26 PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.9 (RCP Power Supply Verification)

PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.12 (Surveillance Evaluation)

Surveillance Frequency List READ TO OPERATOR DIRECTIONS TO STUDENT 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:

Time/Date = 0830 on Saturday, June 8.

RCS Temperature = 298 °F.

1/0 RCP operation in progress (1A1 RCP in operation).

PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) in progress.

SR 3.4.5.2 on page 25 of 26 of PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) is being performed.

Step 2.2 of Encl. 13.9 (RCP Power Supply Verification) is determined to NOT be satisfied because neither the 1B1 nor the 1B2 RCP has power available.

INITIATING CUE:

Based on the above conditions, complete PT/1/A/0600/001 (Periodic Instrument Surveillance)

Encl. 13.12 (Surveillance Evaluation)

ADMIN-241 2S Page 5 of 9 START TIME: _______

STEP 1: Surveillance

Description:

STANDARD: Documents that this is a Tech Spec required verification of correct RCP ___ SAT breaker alignment of power available to the required pump this is not in operation

___ UNSAT COMMENTS:

STEP 2: Applicable TS(s)/SLC(s)/Site Directive(s), etc.: CRITICAL STEP STANDARD: Determines that Tech Spec 3.4.5 (RCS Loops Mode 3) is applicable and documents in Step 2 ___ SAT COMMENTS:

___ UNSAT STEP 3: Description of discrepancy/deficiency:

STANDARD: Documents that the required RCP Breaker alignment does not exist. ___ SAT NOTE: TS 3.4.5 requires that either the 1B1 or 1B2 have power available

___ UNSAT COMMENTS:

STEP 4: Is surveillance applicable for present plant conditions? CRITICAL STEP STANDARD: Marks yes

___ SAT COMMENTS:

___ UNSAT

ADMIN-241 2S Page 6 of 9 STEP 5: If surveillance is applicable, what is the latest due date for surveillance CRITICAL STEP OR applicable LCO?

STANDARD: Documents that the latest due date is 0830 on Tuesday, June 11 (72 ___ SAT hours from discovery) per Condition A of TS 3.4.5 COMMENTS:

___ UNSAT STEP 6: Is applicable TS(s)/SLC(s)/Site Directive(s), etc. satisfied with existing *CRITICAL STEP discrepancy/deficiency?

STANDARD: ___ SAT

• *Marks no

• Explains in justification that TS 3.4.5 requires both RCS loops be Operable and with no power available to the 1B1 and 1B2 RCPs, the B RCS loop is NOT operable ___ UNSAT COMMENTS:

STEP 7: Support personnel/groups contacted (if any) AND information provided:

STANDARD: Candidate may indicate requesting SPOC assistance to determine why ___ SAT neither of the required RCP breakers are racked in however since there is no indication of mechanical failures it would not be required.

___ UNSAT COMMENTS:

ADMIN-241 2S Page 7 of 9 STEP 8: Describe corrective/compensatory actions being taken (procedure change, WR, PIP, etc.), and resolution date for those actions. ___ SAT STANDARD:

• Corrective/Compensatory Action: ___ UNSAT Candidate should indicate that actions will commence to establish the required breaker alignment. This could be by issuing a Work Request, writing a PIP, or dispatching personnel to determine why the breakers are open and if the breakers could be racked in.

Resolution Date:

This blank may be left open at this time since the investigation is just beginning however in no case should a date and time that would result in exceeding the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time be entered.

COMMENTS:

STEP 9: Approval:

STANDARD: Signs and Dates either of the blanks provided ___ SAT COMMENTS:

___ UNSAT END OF TASK

ADMIN-241 2S Page 8 of 9 CRITICAL STEP EXPLANATIONS STEP # Explanation 2 Required to determine the applicable Tech Spec 4 Required to determine if this Tech Spec is applicable in Mode 3 5 Incorrect documentation could lead to exceeding allowed time to complete Tech Spec Required Actions.

6 Required to determine if the LCO is met

2S CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Time/Date = 0830 on Saturday, June 8.

RCS Temperature = 298 °F.

1/0 RCP operation in progress (1A1 RCP in operation).

PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) in progress.

SR 3.4.5.2 on page 25 of 26 of PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) is being performed.

Step 2.2 of Encl. 13.9 (RCP Power Supply Verification) is determined to NOT be satisfied because neither the 1B1 nor the 1B2 RCP has power available.

INITIATING CUE:

Based on the above conditions, complete PT/1/A/0600/001 (Periodic Instrument Surveillance)

Encl. 13.12 (Surveillance Evaluation)

Admin-306 3B Page 1 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-306 Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits (EDL)

CANDIDATE EXAMINER

Admin-306 3B Page 2 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Calculate the Maximum Permissible Stay Time Within the Emergency Dose Limits.

Alternate Path:

N/A Facility JPM #:

Admin 305 K/A Rating(s):

System: Gen K/A: 2.3.4 Rating: 3.2/3.7 Task Standard:

Calculate the Maximum Permissible Stay Time Within the Emergency Dose Limits.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator _____ In-Plant ______ Classroom _ _X_ Perform __X__ Simulate _____

References:

NSD-507 (Radiation Protection)

OMP 1-18 (Implementation Standard During Abnormal And Emergency Events)

Validation Time: 20 min. Time Critical: No

=========================================================================

Candidate: _______________________________________ Time Start: _________

NAME Time Finish: ________

Performance Rating: SAT ______ UNSAT ______ Performance Time _________

Examiner: ______________________________ ____________________________________/_________

NAME SIGNATURE DATE

=========================================================================

=

COMMENTS

Admin-306 3B Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS NONE

Admin-306 3B Page 4 of 8 Tools/Equipment/Procedures Needed:

Calculator Note tablet READ TO OPERATOR DIRECTIONS TO STUDENT 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 Steam Generator Tube Rupture has occurred on Unit 3 Emergency Dose Limits are in effect NEO A has received 1.26 Rem TEDE this year The following tasks are required to be performed:

0B TASK 1B TIME REQUIRED 2B DOSE RATE 3B 1

4B Close 3C-573 5B 11 min 6B 6.15 R/hr 7B 2

8B Open 3FDW-313 9B 6 min 10B 18.25 R/hr 1B 3

12B Open all Unit 3s ADVs 13B 4.65 R/hr 14B Note: Assume no dose is received while traveling between tasks.

INITIATING CUE Refer to the above information. NEO A has completed tasks 1 and 2 in the time required.

Determine how long the NEO has to complete task 3 without exceeding his/her Emergency Dose Limits.

Admin-306 3B Page 5 of 8 START TIME: _______

Examiner Note:

• Candidate may perform these steps in a different order; however, the calculated stay time must be correct.

• EDL is 5 Rem per event (LOCA or SGTR).

• Current exposure for the year is not counted toward the Emergency Dose Limits (EDL).

STEP 1: Determine dose received while performing task 1. CRITICAL STEP STANDARD: Determine dose received while performing task 1. ___ SAT 6.15 R/hr X 1hr/60 min X 11 min = 1.1275 R (1.12 to 1.13 R) ___ UNSAT COMMENTS:

STEP 2: Determine dose received while performing task 2. CRITICAL STEP

___ SAT STANDARD: Determine dose received while performing task 2.

18.25 R/hr X 1hr/60 min X 6 min = 1.825 R

___ UNSAT (1.82 to 1.83 R)

COMMENTS:

STEP 3: Determine dose remaining from EDLs. CRITICAL STEP

___ SAT STANDARD: Determine dose remaining from EDLs.

5R - 1.1275R - 1.825R = 2.0475 R

___ UNSAT (2.04 to 2.06 R)

COMMENTS:

Admin-306 3B Page 6 of 8 STEP 4: Determine time available for the NEO to complete task 3 without CRITICAL STEP exceeding EDL.

___ SAT STANDARD: Stay time is calculated to be:

Available Dose = 2.0475 R = .44 hr X 60 min = 26.42 min Dose Rate 4.65 R/hr 1hr ___ UNSAT (26 to 27 Minutes)

COMMENTS:

END OF TASK STOP TIME: ________

Admin-306 3B Page 7 of 8 CRITICAL STEP EXPLANATIONS STEP # Explanation 1 Required to calculate stay time.

2 Required to calculate stay time.

3 Required to calculate stay time.

4 Required to calculate stay time.

3B CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS Steam Generator Tube Rupture has occurred on Unit 3 Emergency Dose Limits are in effect NEO A has received 1.26 Rem TEDE this year The following tasks are required to be performed:

15B TASK 16B TIME REQUIRED 17B DOSE RATE 18B 1

19B Close 3C-573 20B 11 min 21B 6.15 R/hr 2B 2

23B Open 3FDW-313 24B 6 min 25B 18.25 R/hr 26B 3

27B Open all Unit 3s ADVs 28B 4.65 R/hr 29B Note: Assume no dose is received while traveling between tasks.

INITIATING CUE Refer to the above information. NEO A has completed tasks 1 and 2 in the time required.

Determine how long the NEO has to complete task 3 without exceeding his/her Emergency Dose Limits.

ADMIN-412 4S Page 1 of 11 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-412 Determine Emergency Classification and complete the initial Emergency Notification form (SRO Only)

CANDIDATE EXAMINER

ADMIN-412 4S Page 2 of 11 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Determine Emergency Classification and complete the initial Emergency Notification form Alternate Path:

N/A Facility JPM #:

N/A K/A Rating(s):

System: Gen K/A: 2.4.38 Rating: 2.4/4.4 Task Standard:

Appropriate classification is determined and associated Emergency Notification Form is completed with the time critical criteria.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __ ___ In-Plant ___ ___ Classroom __ X___ Perform __ X__ Simulate_ __

References:

RP/0/B/1000/001 (Emergency Classification)

RP/0/B/1000/002 (Control Room Emergency Coordinator Procedure)

Nuclear Power Plant Emergency Notification Form 4.1.A.1 Validation Time: 20 min. Time Critical: Yes

=========================================================================

Candidate: _______________________________________ Time Start: _________

NAME Time Finish: ________

Performance Rating: SAT ______ UNSAT ______ Performance Time: _________

Examiner: ______________________________ ___________________________________/_________

NAME SIGNATURE DATE

=========================================================================

Comments

ADMIN-412 4S Page 3 of 11 SIMULATOR OPERATOR INSTRUCTIONS NONE

ADMIN-412 4S Page 4 of 11 Tools/Equipment/Procedures Needed:

RP/0/B/1000/001 (Emergency Classification)

RP/0/B/1000/002 (Control Room Emergency Coordinator Procedure)

READ TO OPERATOR DIRECTIONS TO STUDENT 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:

0800 Unit 1 experiences a runback and trip due to a loss of Stator Coolant.

0805 The Operator dispatched to determine if the MS Relief Valves have reseated reports that 1B SG appears to have two MSRVs damaged and still passing steam.

0806 1B SG has been isolated and RCS Temperature stabilized at 520°F CETCs.

0815 Calculations indicate a 1A S/G Tube leak of 240 gpm is occurring.

0816 The 1A S/G is being fed by the 1A MDEFWP and is being used for RCS Temperature control. Feeding the 1B S/G for Tube to Shell Delta Temperature concerns is NOT required at this time.

INITIATING CUE:

Perform the required actions of the Emergency Coordinator:

1. Determine Emergency Classification at Time = 0816

2. Complete appropriate Emergency Notification Form THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinators judgment while classifying the event. When required, other operators will maintain the Emergency Coordinators Log and perform the duties of the Control Room Offsite Communicator.

ADMIN-412 4S Page 5 of 11 START TIME: _______

(Actual time)

STEP 1: Classify the Event CRITICAL STEP STANDARD: Refer to RP/0/B/1000/01 (Emergency Classification) Enclosure 4.1 (Fission Product Barrier Matrix) ___ SAT Classify as an ALERT due to:

• RCS Barriers - 4 points due to SGTR >160 gpm

___ UNSAT Time of Classification: _________________

Examiner Note: The criteria for getting 3 points for a SGTL in one S/G and the other S/G faulted is not met because the faulted S/G (1B) has been isolated.

COMMENTS:

STEP 2: Commence the Off-Site Notification Form.

STANDARD: Go to RP/0/B/1000/002 (Control Room Emergency Coordinator ___ SAT Procedure) and initiate procedure by determining symptoms for entry exist and check Step 1.1

___ UNSAT COMMENTS:

STEP 3: Step 2.1.

STANDARD: Determine step 2.1 does not apply ___ SAT COMMENTS:

___ UNSAT

ADMIN-412 4S Page 6 of 11 NOTE:

State and County agencies shall be notified within 15 minutes of E-plan declaration, Classification upgrades, and Protective Action Recommendations.

___ SAT STEP 4: Step 2.2 Declare the appropriate Emergency Classification level.

Classification __ALERT_____ (UE, ALERT, SAE, GE)

Time Declared: _________ ___ UNSAT STANDARD: Declare an ALERT due to:

1A SGTR > 160 gpm ( 4 pts.) and the SG with an open path to the environment (1B SG) is NOT being fed by the affected unit nor does it contain a SG Tube Leak

• Time ALERT Declared documented in Step 1

• (SAT is < Start Time + 15 minutes)

COMMENTS:

STEP 5: Step 2.3 & 2.4 STANDARD: Determine Steps 2.3 and 2.4 do not apply ___ SAT COMMENTS:

___ UNSAT STEP 6: Step 2.5 Appoint Control Room Offsite Communicator(s) and perform the following: N/A

___ SAT STANDARD: Any name (real or imaginary) is acceptable.

Note: Initiating Cue indicates these actions will be performed by another operator.

___ UNSAT COMMENTS:

ADMIN-412 4S Page 7 of 11 STEP 7: Step 2.6 IAAT Changing plant conditions require an emergency classification upgrade,

___ SAT THEN Notify Offsite Communicator to complete the in-progress notifications per RP/0/B/1000/15A, (Offsite Communications From The CR)

AND Re-initiate a clean copy of this procedure for the upgraded

___ UNSAT classification and stop this procedure.

STANDARD: An Upgrade is not expected.

COMMENTS:

STEP 8: Step 2.7 CRITICAL STEP Obtain the appropriate Offsite Notification form from the Emergency

___ SAT Plan cart.

STANDARD: Initial ALERT form # 4.1.A.1 is selected and candidate continues to fill-

___ UNSAT out form per the Step 2.7 substeps.

COMMENTS:

ADMIN-412 4S Page 8 of 11 STEP 9: Step 2.7 (continued) *CRITICAL STEP 2.7.1. Ensure EAL # as determined by RP/0/B/1000/001 matches Line 4.

(4.1.A.1) 2.7.2. Line 1 - Mark appropriate box "Drill" or "Actual Event" (DRILL) 2.7.3. *Line 1 - Enter Message # (#1) 2.7.4. *Line 2 - Mark Initial (INITIAL marked) ___ SAT 2.7.5. *Line 6 - (Is Occurring marked)

A. Mark "Is Occurring" if any of the following are true:

• RIAs 40, 45, or 46 are increasing or in alarm ___ UNSAT

• If containment is breached

• Containment pressure > 1 psig B. Mark "None" if none of the above is applicable.

2.7.6. *Line 7 - If Line 6 Box B or C is marked, mark Box D. Otherwise mark Box A (D marked) 2.7.7. *Line 8 - Mark "Stable" unless an upgrade or additional PARs are anticipated within an hour.

• Refer to Enclosure 4.9, (Event Prognosis Definitions) 2.7.8. *Line 10 - Military time and date of declaration (Refer to date/time in Step 2.2) (Insert time from STEP 1 and todays date, military time is not critical as long as time is specific and accurate.)

2.7.9. Line 11 - If more than one unit affected, mark "All" (Unit 1 marked) 2.7.10. Line 12 - Mark affected unit(s) (reference Line 11) AND enter power level of affected unit(s) or time/date of shutdown (Unit 1 - 0% power, Shutdown at 0800 with todays date.)

2.7.11. Line 13 - If the OSM has no remarks, write "None" (indicate NONE) 2.7.12. If Condition "A" exists ensure following PARs are included Line 5.

A. Evacuate: Move residents living downstream of the Keowee Hydro Project dams to higher ground B. Other: Prohibit traffic flow across bridges identified on your inundation maps until the danger has passed. (Condition A does not exist. No PAR required)

STANDARD: Correctly fills out Emergency Notification Form in accordance with Key.

COMMENTS:

ADMIN-412 4S Page 9 of 11 STEP 10: Step 2.7 (Continued) CRITICAL STEP 2.7.13. Line 17 - OSM signature, CURRENT Time/Date (MUST SIGN)

STANDARD: Indicate that OSM signature will be obtained on the completed Emergency Notification Form within 15 minutes of classification time recorded in step 1.

STOP TIME #2: Time for Notification __________

(SAT is < Step 1 Time + 15 minutes)

COMMENTS:

END OF TASK

ADMIN-412 4S Page 10 of 11 CRITICAL STEP EXPLANATIONS STEP # Explanation 1 The candidate needs to be able to utilize the procedure and determine the conditions meet a Site Area Emergency classification within 15 minutes.

8 The correct form that matches the EAL # is selected.

9 The emergency notification form is filled-out with each line entry identified as critical complete and accurate.

10 This is a time critical step. The Candidate needs to complete the notification form within 15 minutes from the time the EAL was declared. (Declaration time is the time recorded in JPM step 4)

4S CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

0800 Unit 1 experiences a runback and trip due to a loss of Stator Coolant.

0805 The Operator dispatched to determine if the MS Relief Valves have reseated reports that 1B SG appears to have two MSRVs damaged and still passing steam.

0806 1B SG has been isolated and RCS Temperature stabilized at 520°F CETCs.

0815 Calculations indicate a 1A S/G Tube leak of 240 gpm is occurring.

0816 The 1A S/G is being fed by the 1A MDEFWP and is being used for RCS Temperature control. Feeding the 1B S/G for Tube to Shell Delta Temperature concerns is NOT required at this time.

INITIATING CUE:

Perform the required actions of the Emergency Coordinator:

1. Determine Emergency Classification at Time = 0816

2. Complete appropriate Emergency Notification Form THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinators judgment while classifying the event. When required, other operators will maintain the Emergency Coordinators Log and perform the duties of the Control Room Offsite Communicator.