ML13248A111

Oconee Initial Exam 2013-301 Final Administrative JPMs

ML13248A111
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: ML13248A111 (68)

Text

Admin-130 2.1S Page 1 of 12 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

Admin-130 Perform Manual RCS Leakage Calculation and TS Determination (SRO Only)

CANDIDATE EXAMINER Admin-130 2.1S Page 2 of 12 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Perform Manual RCS Leakage Calculation and T S 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 B 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/0 600/010 (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 2.1S Page 3 of 12 SIMULATOR OPERATOR INSTRUCTIONS NONE Admin-130 2.1S Page 4 of 12 Tools/Equipment/Procedures Needed:

PT/1/A/0600/0 10 (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/1 A/0 600/0 10 (Reactor Coolant Leakage)

Encl. 13.3 (Manual RCS Leakage Calculation Data Sheet) using the data collected below.

Evaluate leakage and determine if a ny Tech S pec Conditions that apply. 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 8 6.5 inches 8 6.5 inches LDST Level 76.7 inches 7 5.2 inches Power Range NI 100.0% 100.1% RCS NR Pressure 2150 psig 2150 psig Group 7 Control Rod Position 9 2.7% 9 2.7%

Admin-130 2.1S Page 5 of 12 START TIME: _______

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

____Sat ____Unsat Value Initial Data Minus Final Data Equals Change PZR Level 219.0 inches - = RCS Temp 579.0°F - = QT Level 86.5 inches - = LDST Level 76.7 inches - = Rx Power 100.0% - = RCS Press 2150 psig - = 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: ____________

STANDARD: Candidate enters 0015 (from initiating cue)

COMMENTS

____Sat ____Unsat Admin-130 2.1S Page 6 of 12 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. 1". ____Sat ____Unsat 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 - 7 5.2 inches = Rx Power 100.0% - 100.1% = RCS Press 2150 psig - 2150 psig = CR Pos 92.7% - 92.7% = 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 Fi n al Data recorded: ____________

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

____Sat ____Unsat Admin-130 2.1S Page 7 of 12 STEP 6: Step 2.6 Calculate and record "Change" values in "Table # 1"..

CRITICAL STEP

____Sat ____Unsat 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 QT Level 86.5 inches - 86.5 inches = 0 inches LDST Level 76.7 inches - 7 5.2 inches = +1.5 inches Rx Power 100.0% - 100.1% = -.1% 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 Calculate Corrected Pzr Level Change:

STANDARD: -0.5 inches - (6.831 inches/°F X

-.1°F) = +.1831 inches

(+.18 to +.2) COMMENTS CRITICAL STEP

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

+2.63 gallons (+.18 to +.2) ( 2.585 to 2.873) COMMENTS CRITICAL STEP

____Sat ____Unsat Admin-130 2.1S Page 8 of 12 STEP :9 Step 2.9 Convert QT Level Change to gallons:

STANDARD: No change COMMENTS CRITICAL STEP

____Sat

____Unsat STEP :10 Step 2.10 Convert LDST Level Change to gallons STANDARD: +1.5 inches X 30.956 gallons / inch =

+46.434 gallons (+46.4 to +46.5) COMMENTS CRITICAL STEP

____Sat

____Unsat STEP :11 Step 2.11 Calculate Total Volume Change STANDARD: 2.63 gallons + 0 gallons + 46.434 gallons = 49.064 gallons ( 2.585 to 2.873) (+46.4 to +46.5) (48.98 to 49.37) COMMENTS CRITICAL STEP

____Sat

____Unsat STEP :12 Step 2.12 Calculate "RCS Unidentified Leakage Rate" STANDARD: 49.064 gallons / 60 minutes = .818 gpm (48.98 to 49.37) (.816 to .823) COMMENTS CRITICAL STEP

____Sat

____Unsat Admin-130 2.1S Page 9 of 12 STEP :13 Refer to TS 3.4.13 RCS Operational LEAKAGE STANDARD: Candidate determines that the Tech Spec limit for Unidentified Leakage is 1 gpm therefore entry into the Actions Table is NOT required

. COMMENTS ____Sat

____Unsat STEP :1 4 Refer to TS 3.4.13 RCS Operational LEAKAGE EXAMINER CUE: Hand the candidate Cue sheet #2 STANDARD: NOTE: After second cue sheet handed to candidate, he/she determines the leakage is pressure boundary leakage (see below)

Pressure Boundary: Determine that leakage exceeds the 0 gpm Pressure Boundary leakage limit and TS 3.4.13 Condition B applies. This required Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

COMMENTS END TASK CRITICAL STEP

____Sat ____Unsat STOP TIME: ____________

Admin-130 2.1S Page 10 of 12 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 limits are not exceeded. 1 4 Necessary to refer to correct TS and conclude limits are exceeded

.

1.1S CANDIDATE CUE SHEET

1. 1 (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.

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 8 6.5 inches 8 6.5 inches LDST Level 76.7 inches 7 5.2 inches Power Range NI 100.0% 100.1% RCS NR Pressure 2150 psig 2150 psig Group 7 Control Rod Position 9 2.7% 9 2.7%

1.1S CANDIDATE CUE SHEET #2 (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIATING CUES Since completing the RCS Manual Leakage calculation, the RCS leak rate has increased to 2.17 gpm and the location of the leak has been determined to be the weld that connects the 1A1 HPI injection nozzle to the RCS piping.

Indicate below what (if any) Tech Spec Conditions, Required Actions, and Completion Times that apply.

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/0 600/010 (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/0600/0 10 (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/1 A/0 600/010 (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 8 6.5 inches 8 6.5 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 9 2.7% 9 2.7%

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

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

____Sat ____Unsat Value Initial Data Minus Final Data Equals Change PZR Level 219.0 inches - = RCS Temp 579.0°F - = QT Level 86.5 inches - = LDST Level 76.7 inches - = Rx Power 100.0% - = RCS Press 2150 psig - = 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: ____________

STANDARD: Student enters 0015 (from initiating cue)

COMMENTS

____Sat ____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".

____Sat ____Unsat 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

= Rx Power 100.0% - 100.1% = RCS Press 2150 psig - 2150 psig = CR Pos 92.7% - 92.7% = 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 Fi n al Data recorded: ____________

STANDARD: Student enters 0115 COMMENTS

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

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

CRITICAL STEP

____Sat ____Unsat 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 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% 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 Calculate Corrected Pzr Level Change:

STANDARD: -0.5 inches - (6.831 inches/°F X

-.1°F) = +.1831 inches

(+.18 to +.2) COMMENTS CRITICAL STEP

____Sat

____Unsat STEP :8 Step 2.8 Convert Corrected Pzr Level Change to gallons STANDARD: +.1831 inches X 14.364 gallons / inch = +2.63 gallons (+.18 to +.2) ( 2.585 to 2.873) COMMENTS CRITICAL STEP

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

STANDARD: No change COMMENTS CRITICAL STEP

____Sat

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

(+83.5 to +83.6)

COMMENTS CRITICAL STEP

____Sat

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

8 6.2112 gallons (2.585 to 2.873) (+83.5 to +83.6)

(86.08 to 86.47) COMMENTS CRITICAL STEP

____Sat

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

1.437 gpm (86.08 to 86.47

) (1.434 to 1.44 1) COMMENTS END TASK CRITICAL STEP

____Sat

____Unsat 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 8 6.5 inches 8 6.5 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 9 2.7% 9 2.7%

Admin-142 - 1.2B Page 1 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

Admin-142 Determine Time for SFP to reach 180

ºF CANDIDATE EXAMINER Admin-142 - 1.2B Page 2 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: Determine Time for SFP to reach 180ºF Alternate Path:

N/A Facility JPM #:

New K/A Rating(s):

System: GEN K/A: 2.1.25 Rating: 3.9/4.2 Task Standard:

Tables in AP/1

-2/A/1700/035 (Loss of SF P Cooling And/Or Level) are used to determine total time required for SFP temperature to reach 180

ºF Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator _____ In-Plant _____ Classroom

__ X ___ Perform __X___ Simulate ____

References:

AP/1-2/A/1700/035 (Loss of SF P Cooling And/Or Level) Validation Time

15 minutes Time Critical

NO ====================================================================================

Candidate:

_______________________________________

Time Start: _____

____ NAME Time Finish: ________

Performance Rating:

SAT ______ UNSAT ______

Performance Time

_________

Examiner: ______________________________ ____________________________________/________

NAME SIGNATURE DATE

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

COMMENTS Admin-142 - 1.2B Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS:

NONE Admin-142 - 1.2B Page 4 of 9 Tools/Equipment/Procedures Needed:

AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level)

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 is at 100% stable Unit 1 EFPD = 278 Unit 2 EFPD = 47 Unit 2 was operating at 100% when it experienced a Unit blackout SSF has been activated for Unit 2 Unit 2 RCMUP is aligned and operating 2HP-426 is being cycled to maintain Pressurizer Level as directed by AP/25 AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) has been initiated Unit 1 & 2 SFP level = 0" stable Unit 1 & 2 SFP temperature = 102 ºF INITIATING CUES:

CRS has directed you to utilize AP/35 Enclosure 5.4 and determine the time for Unit 1&2 SFP to reach 180 ºF

Admin-142 - 1.2B Page 5 of 9 START TIME: _______

STEP 1: 1. Refer to tables A, B, and C below.

2. ONLY one row from one table below applies

3. Check the row in Table A, B, or C that applies to current conditions, and then use Tables listed on subsequent pages of Encl 5.4, as directed, to calculate SFP heat up times. STANDARD: Candidate selects Table B and then chooses to use Table 10 based on

1. SSF Event in progress for U1 or U2 with Unit letdown going to SFP AND 2. U1 and U2 each have 177 Fuel Assemblies in RB Candidate proceeds to Table 10 (page 33 of 63)

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT Admin-142 - 1.2B Page 6 of 9 STEP 2: Determine the Time (in days) row based on direction from page 5 of 63 STANDARD: Candidate selects the lower EFPD unit and adds 20 which results in 67 days. Determine that 67 days is between 60 and 70 days on the far left column of Table 10 Based on guidance in Step 7 on Page 7 of 63, elects to use 60 days (the shorter time).

Note: Step 2 and Step 3 can be performed in any order COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 3: Determine initial Spent Fuel Pool Temperature column based on directions from page 7 of 63 Step 6

. STANDARD: Actual SFP temp = 102

ºF Temperature columns available are 100 and 105 Based on directions in step 6, elects to use the 105 (higher) column Note: Step 2 and Step 3 can be performed in any order COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT Admin-142 - 1.2B Page 7 of 9 STEP 4: Find the Time in hours based on the intersection of the 60 day row and the 105 degree column.

STANDARD: Based on the intersection of the 60 day row and the 105 degree column, determine that 16.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is the time to reach 180ºF COMMENTS: END TASK CRITICAL STEP

___ SAT

___ UNSAT STOP TIME: ____________

Admin-142 - 1.2B Page 8 of 9 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 Required to determine the time to reach 180

ºF 2 Required to determine the time to reach 180

ºF 3 Required to determine the time to reach 180

ºF 4 Required to determine the time to reach 180

ºF

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

INITIAL CONDITIONS:

Unit 1 is at 100% stable Unit 1 EFPD =

278 Unit 2 EFPD = 47 Unit 2 was operating at 100% when it experienced a Unit blackout SSF has been activated for Unit 2 Unit 2 RCMUP is aligned and operating 2HP-426 is being cycled to maintain Pressurizer Level as directed by AP/25 AP/1-2/A/1700/035 (Loss of SFP Cooling And/Or Level) has been initiated Unit 1 & 2 SFP level = 0" stable Unit 1 & 2 SFP temperature = 102 ºF INITIATING CUES:

CRS has directed you to utilize AP/35 Enclosure 5.4 and determine the time for Unit 1&2 SFP to reach 180 ºF

Admin-240 2R Page 1 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

Admin-2 40 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-23 7 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. 4.1 9 (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)

Verify All SG Downcomer Temperature computer points agree within 3°F of each other.

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

O1E2008 - 5 28.8 7°F O1E2009 - 53 8.97°F O1E2012 - 532.78°F O1E2013 - 53 3.65°F STANDARD: Determine that the above OAC point s do NOT agree within 3°F of each other, and perform Enclosure 4.19 "Channel Check of OTSG Downcomer Temperatures".

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT 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:

Step 3.1.1 Determine 1A OTSG outlet pressure using any one of the following computer points: O1E2281 - 88 8.5 psig O1E2283 - 88 8.5 psig O1E2031 - 88 8.5 psig O1E2032 - 88 8.5 psig STANDARD: Using the OAC determine that 1A OTSG pressure is 888.5. COMMENTS:

___ SAT

___ UNSAT Admin-240 2R Page 6 of 9 STEP 3: Step 3.1.2 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. ____________ 1A OTSG saturation temperature STANDARD: Determine that 1A OTSG saturation temperature is 53 3.9ºF (533.8 - 534.0) by using the table in section 4.

COMMENTS:

CRITICAL STEP

___ SAT

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

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.

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:

CRITICAL STEP

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

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.

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 CRITICAL STEP

___ SAT

___ UNSAT 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.

ADM IN-241 2S Page 1 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

ADMIN-241 Complete a Surveillance Evaluation (SRO ONLY)

CANDIDATE EXAMINER ADM IN-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: G en 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 2 5 of 2 6 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 ADM IN-241 2S Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS NONE ADM IN-241 2S Page 4 of 9 Tools/Equipment/Procedures Needed

PT/1/A/0600/001 (Periodic Instrument Surveillance) Encl. 13.2 (Mode 3) page 2 5 of 2 6 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)

ADM IN-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 breaker alignment of power available to the required pump this is not in operation COMMENTS: ___ SAT

___ UNSAT STEP 2: Applicable TS(s)/SLC(s)/Site Directive(s), etc.:

STANDARD: Determines that Tech Spec 3.4.5 (RCS Loops Mode 3) is applicable and documents in Step 2 COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT STEP 3: Description of discrepancy/deficiency:

STANDARD: Documents that the required RCP Breaker alignment does not exist.

NOTE: TS 3.4.5 requires that either the 1B1 or 1B2 have power available COMMENTS: ___ SAT

___ UNSAT STEP 4: Is surveillance applicable for present plant condit ions? STANDARD: Marks "yes" COMMENTS:

CRITICAL STEP

___ SAT

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

STANDARD: Documents that the latest due date is 0830 on Tuesday , June 11 (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from discovery) per Condition A of TS 3.4.5 COMMENTS:

CRITICAL STEP

___ SAT

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

STANDARD: *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 RCP's, the B RCS loop is NOT operable COMMENTS: *CRITICAL STEP

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

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

COMMENTS:

___ SAT ___ UNSAT ADM IN-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.

STANDARD: *Corrective/Compensatory Action:

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:

___ SAT ___ UNSAT STEP 9: Approval: STANDARD: Signs and Dates either of the blanks provided COMMENTS: END OF TASK

___ SAT

___ UNSAT ADM IN-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 satisfie d 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-30 6 3B Page 1 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

Admin-30 6 Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits (EDL)

CANDIDATE EXAMINER Admin-30 6 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

N o =====================================================================================

Candidate: _______________________________________

Time Start: _____

____ NAME Time Finish: ________

Performance Rating

SAT ______ UNSAT ______

Performance Time __

_______

Examiner: ______________________________ ____________________________________/___

______ NAME SIGNATURE DATE

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

= COMMENTS Admin-30 6 3B Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS NONE Admin-30 6 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 R em TEDE this year The following tasks are required to be performed:

0B# 1BTASK 2BTIME REQUIRED 3BDOSE RATE 4B 1 5BClose 3C-573 6B11 min 7B6.15 R/hr 8B 2 9BOpen 3FDW-313 10B6 min 11B18.25 R/hr 12B 3 13BOpen all Unit 3's ADVs 14B4.65 R/hr 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-30 6 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 R em per event (LOCA or SGTR).

Current exposure for the year is not counted toward the Emergency Dose Limit s (EDL). STEP 1: Determine dose received while performing task 1.

STANDARD: Determine dose received while performing task 1.

6.15 R/hr X 1hr/60 min X 11 min = 1.1275 R (1.12 to 1.13 R)

COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT STEP 2: Determine dose received while performing task 2.

STANDARD: Determine dose received while performing task 2.

18.2 5 R/hr X 1hr/60 min X 6 min = 1.8 25 R (1.82 to 1.83 R)

COMMENTS: CRITICAL STEP

___ SAT ___ UNSAT STEP 3: Determine dose remaining from EDLs.

STANDARD: Determine dose remaining from EDLs.

5R - 1.1275 R - 1.8 25R = 2.04 75 R (2.04 to 2.06 R)

COMMENTS:

CRITICAL STEP

___ SAT ___ UNSAT Admin-30 6 3B Page 6 of 8 STEP 4: Determine time available for the NEO to complete task 3 without exceeding EDL

. STANDARD: Stay time is calculated to be:

Available Dose

= 2.04 75 R = .44 hr X 60 min = 26.4 2 min Dose Rate 4.65 R/hr 1hr (26 to 27 Minutes

) COMMENTS: END OF TASK CRITICAL STEP

___ SAT

___ UNSAT STOP TIME: ________

Admin-30 6 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 R em TEDE this year The following tasks are required to be performed:

15B# 16BTASK 17BTIME REQUIRED 18BDOSE RATE 19B 1 20BClose 3C-573 21B11 min 22B6.15 R/hr 23B 2 24BOpen 3FDW-313 25B6 min 26B18.25 R/hr 27B 3 28BOpen all Unit 3's ADVs 29B4.65 R/hr 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.

ADM IN-412 4S Page 1 of 11 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE

ADMIN-4 12 Determine Emergency Classification and complete the initial Emergency Notification form (SRO Only)

CANDIDATE EXAMINER ADM IN-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: G en 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/1000/0 0 1 (Emergency Classification

) RP/0/B/1000/0 0 2 (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 ADM IN-412 4S Page 3 of 11 SIMULATOR OPERATOR INSTRUCTIONS NONE ADM IN-412 4S Page 4 of 11 Tools/Equipment/Procedures Needed

RP/0/B/1000/0 0 1 (Emergency Classification)

RP/0/B/1000/0 0 2 (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 520F CETCs. 0815 Calculations indicate a 1A S/G Tube leak of 240 gpm is occurring

. 1RIA-40 = 1,245 cps and increasing.

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 Coordinator's judgment while classifying the event. When required, other operator s will maintain the Emergency Coordinator's Log and perform the duties of the Control Room Offsite Communicator.

ADM IN-412 4S Page 5 of 11 START TIME: _______ (Actual time)

STEP 1: Classify the Event STANDARD: Refer to RP/0/B/1000/01 (Emergency Classification) Enclosure 4.

1 (Fission Product Barrier Matrix)

Classify as an ALERT due to:

RCS Barriers - 4 points due to SGTR

>160 gpm 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: CRITICAL STEP

___ SAT

___ UNSAT STEP 2: Commence the Off-Site Notification Form

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

___ UNSAT STEP 3: Step 2.1. STANDARD: Determine step 2.1 does not apply COMMENTS: ___ SAT ___ UNSAT ADM IN-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.

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

Classification __ALERT_____ (UE, ALERT, SAE, GE)

Time Declared: _________

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 Declar ed documented in Step 1 (SAT is < Start Time + 15 minutes)

COMMENTS:

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

___ SAT

___ UNSAT STEP 6: Step 2.5 Appoint Control Room Offsite Communicator(s) and perform the following: N/A STANDARD: Any name (real or imaginary) is acceptable.

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

COMMENTS:

___ SAT ___ UNSAT ADM IN-412 4S Page 7 of 11 STEP 7: Step 2.6 IAAT Changing plant conditions require an emergency classification upgrade, 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 classification and stop this procedure.

STANDARD: An Upgrade is not expected.

COMMENTS:

___ SAT

___ UNSAT STEP 8: Step 2.7 Obtain the appropriate Offsite Notification form from the Emergency Plan cart.

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

-out form per the Step 2.7 substeps.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT ADM IN-412 4S Page 8 of 11 STEP 9: Step 2.7 (continued) 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) 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 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' mark ed) 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) (Inser t time from STEP 1 and today's 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 today's 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: *CRITICAL STEP

___ SAT ___ UNSAT ADM IN-412 4S Page 9 of 11 STEP 10: Step 2.7 (Continued) 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 CRITICAL STEP

ADM IN-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 520F CETCs. 0815 Calculations indicate a 1A S/G Tube leak of 240 gpm is occurring

. 1RIA-40 = 1,245 cps and increasing.

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 Coordinator's judgment while classifying the event. When required, other operator s will maintain the Emergency Coordinator's Log and perform the duties of the Control Room Offsite Communicator.