ML093280323

Initial Exam 2009-301 Draft Administrative JPMs

ML093280323
Person / Time
Site:	Vogtle
Issue date:	11/18/2009
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
50-424/09-301, 50-425/09-301
Download: ML093280323 (66)

Text

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1

.D RflJrT Facility: Vogtle Nuclear Plant Date of Examination: June 1-12, 2009 Examination Level: RO Operating Test Number: 2009-301 Administrative Topic (see Type Describe activity to be performed Note)

Code*

Title:

Boration Calculation

==

Description:==

Manually calculate boric acid required for reactor trip with 3 Conduct of Operations rods stuck at different heights. Students are required to determine R,M required increase in boric acid and the total volume of boric acid to add to the RCS. This task will also will require referencing the Plant Technical Data Book Tab 2.3 to determine boric acid volume. This JPM has been modified to use different data to determine the volume of boric acid to add to the RCS.

KIA: G2.1.25 (3.9)

Title:

Critical Safety Function Status Tree Evaluation Conduct of Operations R,D,P

==

Description:==

Students will be provided a listing of plant parameters.

This will require manually evaluating each status tree to determine the challenges to each tree and identify the highest priority challenge.

KIA: G 2.1.7 (4.4)

Title:

RCS Leak Rate Calculation

==

Description:==

Students will be required to perform a manual RCS leak Equipment Control R,N rate calculation given a set of initial and final plant data. This will also require calculating the average initial and final values. The initial leak rates will be adjusted for RCDT in leakage and SGTL. Final values will exceed Tech Spec limit for unidentified leakage.

KIA: G 2.2.12 (3.7)

Radiation Control N/A

Title:

N/A

==

Description:==

N/A KIA: N/A

Title:

Emergency Notification Emergency Procedures/Plan R,D

==

Description:==

Student will be required to select and activate the alert emergency recall scenario and complete a proper ENN notification.

KIA: G2.4.43 (3.2)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (~ 1; randomly selected)

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 nRfll=-I Facility: Vogtle Nuclear Plant Date of Examination: June 1-12, 2009 Examination Level: RO Operating Test Number: 2009-301 Administrative Topic (see Type Describe activity to be performed Note)

Code*

Title:

Boration Calculation

==

Description:==

Manually calculate boric acid required for reactor trip with 3 rods stuck at different heights. Students are required to determine Conduct of Operations R,M required increase in boric acid and the total volume of boric acid to add to the RCS. This task will also will require referencing the Plant Technical Data Book Tab 2.3 to determine boric acid volume. This JPM has been modified to use different data to determine the volume of boric acid to add to the RCS.

KJA: G2.1.25 (3.9)

Title:

Critical Safety Function Status Tree Evaluation Conduct of Operations R,D,P

==

Description:==

Students will be provided a listing of plant parameters.

This will require manually evaluating each status tree to determine the challenges to each tree and identify the highest priority challenge.

KJA: G 2.1.7 (4.4)

Title:

RCS Leak Rate Calculation

==

Description:==

Students will be required to perform a manual RCS leak Equipment Control R,N rate calculation given a set of initial and final plant data. This will also require calculating the average initial and final values. The initial leak rates will be adjusted for RCDT in leakage and SGTL. Final values will exceed Tech Spec limit for unidentified leakage.

KJA: G 2.2.12 (3.7)

Radiation Control N/A

Title:

N/A

==

Description:==

N/A KJA: N/A

Title:

Emergency Notification Emergency Procedures/Plan R,D

==

Description:==

Student will be required to select and activate the alert emergency recall scenario and complete a proper ENN notification.

KJA: G2.4.43 (3.2)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (.:::..3 for ROs;.::: 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (.::: 1; randomly selected)

SOUTHERN t\\

COMPANY Energy to Serve Your World"M PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Administrative JPM "a.1" V-RQ-JP-19001-003 Calculate Boron Addition Following Reactor Trip With 3 Stuck Rods (This is a Modified JPM For The Hl-15 NRC Exam)

Revision 0 March 5th, 2009 Written By

Thad N. Thompson Date:

3/05/2009 Approved By : Dan Scukanec Date:

4/20/2009

(

SOUTHERN.\\

COMPANY Energy to Serve Your World""

PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Administrative JPM "a.1" V-RQ-JP-19001-003 Calculate Boron Addition Following Reactor Trip With 3 Stuck Rods (This is a Modified JPM For The HL-15 NRC Exam)

Revision 0 March 5th, 2009 Written By

Thad N. Thompson Date:

3/05/2009 Approved By

Dan Scukanec Date:

4/20/2009

V-RQ-JP-19001-003 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip I)

EOL RCS Boron Concentration is at 400 ppm BAST Boron Concentration is 7300 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates the following rod positions Control Bank "B" rod F-14 = 18 steps Shutdown Bank "A" Rod D-2 = 216 steps Control Bank "D" Rod M-4 = 192 steps The RO actuates both the QMeB Reactor Trip Hand switches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 7 of 19001-C the SS checks "all Rods - FULLY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

(

V-RQ-JP-19001-003 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be aI/owed access to any item normal/y used to perform this task.

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOl RCS Boron Concentration is at 400 ppm BAST Boron Concentration is 7300 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates the following rod positions Control Bank "B" rod F-14 = 18 steps Shutdown Bank "A" Rod D-2 = 216 steps Control Bank "D" Rod M-4 = 192 steps The RO actuates both the QMCB Reactor Trip Hand switches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 7 of 19001-C the SS checks "all Rods - FUllY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

\\.

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

I JPM TITLE:

Boron Addition Calculation - 3 Stuck Rods COMPLETION TIME:

8 minutes Application:

Task Number:

KIA Number:

Evaluation Method RO/SRO 37004 G2.1.25 RO:

3.9

[ ] Performed SRO:

4.2 V-RQ-JP-19001-003

[ ] Simulated Evaluation Location

[ ] Simulator

[ ] Control Room

[] Unit 1

[ ] Unit 2 Performance Time: __

minutes OVERALL JPM EVALUATION

[ ] SATISFACTORY

[ ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

(

(

\\

(

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

JPM TITLE:

Boron Addition Calculation - 3 Stuck Rods COMPLETION TIME:

8 minutes Application:

Task Number:

KJA Number:

Evaluation Method RO/SRO 37004 G2.1.25 RO:

3.9

[ ] Performed SRO:

4.2 V-RQ-JP-19001-003

[ ] Simulated Evaluation Location

[ ] Simulator

[ ] Control Room

[] Unit 1

[ ] Unit 2 Performance Time: __

minutes OVERALL JPM EVALUATION

[ ] SATISFACTORY

[ ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

V-RQ-JP-19001-003 INSTRUCTIONS TO EXAMINER This JPM is based on latest revision of 19001-C. If this revision is no longer current, verify this JPM is in accord with the latest procedural revision. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable.

REQUIRED ITEMS:

1. Calculator

2. PTOB (Plant Technical Data Book, Tab 2 in particular is required)

3. 19001-C, step # 7 Direction To Operator:

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip It EOl It RCS Boron Concentration is at 400 ppm III BAST Boron Concentration is 7300 ppm It RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

It Reactor Trip Breakers are open III Power Range NI's indicate 0%

III DRPI indicates the following rod positions Control Bank "B" rod F-14 = 6 steps Shutdown Bank "A" Rod 0-2 = 216 steps Control Bank "0" Rod M-4 = 192 steps III The RO actuates both the QMCS Reactor Trip Hand switches and announces the Reactor Tripped III The Operating Crew has entered 19001-C to stabilize the plant On Step 7 of 19001-C the SS checks "all Rods - FULLY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

(

V -RQ-JP-19001-003 INSTRUCTIONS TO EXAMINER This JPM is based on latest revision of 19001-C. Ifthis revision is no longer current, verify this JPM is in accord with the latest procedural revision. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable.

REQUIRED ITEMS:

1. Calculator

2. PTDB (Plant Technical Data Book, Tab 2 in particular is required)

3. 19001-C, step # 7 Direction To Operator:

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOl RCS Boron Concentration is at 400 ppm BAST Boron Concentration is 7300 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates the following rod positions Control Bank "B" rod F-14 = 6 steps Shutdown Bank "A" Rod 0-2 = 216 steps Control Bank "0" Rod M-4 = 192 steps The RO actuates both the QMCB Reactor Trip Hand switches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 7 of 19001-C the SS checks "all Rods - FUllY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

V-RQ-JP-19001-003 START TIME: ___

STEP 1 CRITICAL ( + )

SAT D.g UNSAT D.g Boron Addition to the RCS calculated a..D

+ Determine that 154 ppm per rod is required for 3 stuck rods (NOTE: Plausible they may not count the shutdown bank rod which would be incorrect and a failure of the JPM).

a..D

+ For three stuck rods boration required is: (154 ppm) X (3 rods) = 462 ppm a..D

+ Calculate the required boration using equation for PTDS tab 2.3 (expected)

(Note: Tolerance data is based on a candidate using the tables - interpolation, and possible rounding off of In calculation) a..D

+ 4251 (+/- 50) gallons of boric acid added to the RCS STOP TIME: _____

Field Notes Calculation:

(154 ppm) X (3 rods) = 462 ppm RCS Boron Concentration = 61346 x Ln [(7300 - 400) + (7300 - 862)] = 4251 gallons of Boric Acid V-RQ-JP-19001-003 START TIME: ___

STEP 1 CRITICAL ( * )

SAT D~

UNSAT D~

Boron Addition to the RCS calculated

~D

• Determine that 154 ppm per rod is required for 3 stuck rods (NOTE: Plausible they may not count the shutdown bank rod which would be incorrect and a failure of the JPM).

~D

• For three stuck rods boration required is: (154 ppm) X (3 rods) = 462 ppm

~D

• Calculate the required boration using equation for PTDB tab 2.3 (expected)

(Note: Tolerance data is based on a candidate using the tables - interpolation, and possible rounding off of In calculation)

~D

• 4251 (+/- 50) gallons of boric acid added to the RCS STOP TIME: ______ _

Field Notes Calculation:

(154 ppm) X (3 rods) = 462 ppm RCS Boron Concentration = 61346 x Ln [(7300 - 400) -;- (7300 - 862)] = 4251 gallons of Boric Acid

SOUTHERN.\\

COMPA Calculate Boron ddition Following

~.G1or Trip Wit 3 Stuck Control Rods October 04, 2002 Rev #0

(

(

SOUTHERN" COMPA Calculate Boron ddition Following R

or Trip Wit,,, '3 Stuck Control Rods October 04, 2002 Rev #0

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOl RCS Boron Concentration is at 200 ppm BAST Boron Concentration is 7100 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates that 3 rods failed to fully insert The RO actuates both the QMCB Reactor Trip Handswitches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 3 on 19001-C the USS checks all "FUllY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOL RCS Boron Concentration is at 200 ppm BAST Boron Concentration is 7100 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates that 3 rods failed to fully insert The RO actuates both the QMCB Reactor Trip Handswitches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 3 on 19001-C the USS checks all "FULLY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

I I

JPM TITLE Calculate Boron Addition Following Reactor Trip With 3 Stuck Control Rods REVISION:

o Date: October 04, 2002 COMPLETION TIME: 15 minutes Application:

RO Evaluation Method

[ ] Performed

[ ] Simulated Evaluation Location

[ ] Simulator

[ ] Control Room

[] Unit 1 Performance Time:

minutes

[ ] Unit 2 OVERALL JPM EVALUATION

[ ] SATISFACTORY

[ ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

(

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

I I

JPM TITLE Calculate Boron Addition Following Reactor Trip With 3 Stuck Control Rods REVISION:

o Date: October 04, 2002 COMPLETION TIME: 15 minutes Application:

RO Evaluation Method

[ ] Performed

[ ] Simulated Evaluation Location

[ ] Simulator

[ ] Control Room

[] Unit 1 Performance Time:

minutes

[ ] Unit 2 OVERALL JPM EVALUATION

[ ] SATISFACTORY

[ ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

INSTRUCTIONS TO EXAMINER This JPM is based on latest revision of 19001-C. If this revision is no longer current, verify this JPM is in accord with the latest procedural revision. Cues preceded by a.. ©..... are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable.

REQUIRED ITEMS:

1. Calculator

2. PTDB (Plant Technical Data Book)

3. 19001-C Direction To Operator:

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOl RCS Boron Concentration is at 200 ppm BAST Boron Concentration is 7100 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates that 3 rods failed to fully insert The RO actuates both the QMCB Reactor Trip Handswitches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 3 on 19001-C the USS checks all "FUllY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

(

(

INSTRUCTIONS TO EXAMINER This JPM is based on latest revision of 19001-C. If this revision is no longer current, verify this JPM is in accord with the latest procedural revision. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable.

REQUIRED ITEMS:

1. Calculator

2. PTDB (Plant Technical Data Book)

3. 19001-C Direction To Operator:

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOl RCS Boron Concentration is at 200 ppm BAST Boron Concentration is 7100 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates that 3 rods failed to fully insert The RO actuates both the QMCB Reactor Trip Handswitches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 3 on 19001-C the USS checks all "FUllY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

START TIME: ____ _

STEP 1 CRITICAL (.)

SAT O~

UNSAT O~

Boron Addition to the RCS calculated

"&.0

• Determine that 154 ppm is required for each stuck rod

"&.0

• For three stuck rods boration required is: (154 ppm) X (3 rods) = 462 ppm

"&.0

• Calculate the required boration using equation for PTDB tab 2.3

"&.0

• 4251 (+/- 50) gallons of boric acid added to the RCS STOP TIME: ______ _

Field Notes Calculation:

(154 ppm) X (3 rods) = 462 ppm RCS Boron Concentration = 61346 x Ln [(7100 - 200) + (7100 - 662)] = 4251 gallons of Boric Acid

(

START TIME: ___

STEP 1 CRITICAL ( * )

SAT OA'S' UNSAT OA'S' Boron Addition to the RCS calculated

"&0

• Determine that 154 ppm is required for each stuck rod

"&0

• For three stuck rods boration required is: (154 ppm) X (3 rods) = 462 ppm

"&0

• Calculate the required boration using equation for PTDB tab 2.3

"&0

• 4251 (+/- 50) gallons of boric acid added to the RCS STOP TIME: _____

Field Notes Calculation:

(154 ppm) X (3 rods) = 462 ppm RCS Boron Concentration = 61346 x Ln [(7100 - 200) + (71 00 - 662)] = 4251 gallons of Boric Acid

SOUTHERN I

COMPANY Energy to Serve Your World'M PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "a.2" V-RQ-J P-19200-005 MONITOR I EVALUATE CSFSTs - SUBCRITICAUTY THIS Is A BANK JPM FOR THE Hl-15 NRC EXAM (THIS JPM Is A RANDOMLY SELECTED JPM FOR RE-USE FROM THE Hl~13 NRC EXAM)

Revision 0 April 6, 2009 Written By Thad N. Thompson Date:

4/06/2009 Approved By Dan Scukanec Date:

4/20/2009

(

SOUTHERN'\\'

COMPANY Energy to Serve Your WorldS" PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "a.2" V-RQ-J P-19200-005 MONITOR I EVALUATE CSFSTs - SUBCRITICALITY THIS Is A BANK JPM FOR THE HL-15 NRC EXAM (THIS JPM Is A RANDOMLY SELECTED JPM FOR RE-USE FROM THE HL-13 NRC EXAM)

Revision 0 April 6, 2009 Written By Thad N. Thompson Date:

4/06/2009 Approved By Dan Scukanec Date:

4/20/2009

V-RQ-JP-19200-00S This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: Following a transition from 19000-C, the crew determined that Critical Safety Function monitoring should be implemented.

Assigned Task:

The SS has directed you to "Evaluate all the CSFSTs and identify any required transition".

2

(

v -RQ-JP-19200-00S This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

Following a transition from 19000-C, the crew determined that Critical Safety Function monitoring should be implemented.

Assigned Task:

The SS has directed you to "Evaluate all the CSFSTs and identify any required transition".

2

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

I I

JPM TITLE:

Monitor I Evaluate CSFSTs - Subcriticality COMPLETION TIME:

8 minutes Application:

Task Number:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

RO/SRO 37004 G2.1.7

[ ] Performed

[ ] Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

RO:

4.2 SRO:

4.7

[ ] Simulated

[ ] Control Room

[ ] SATISFACTORY Examiner's Signature: ______________ _

3 V-RQ-J P-19200-005

[ ] Unit 1

[ ] Unit 2

[ ] UNSATISFACTORY

(

\\

(

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

JPM TITLE:

Monitor / Evaluate CSFSTs - Subcriticality COMPLETION TIME:

8 minutes Application:

Task Number:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

RO/SRO 37004 G2.1.7

[ ] Performed

[ ] Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

RO:

4.2 SRO:

4.7

[ ] Simulated

[ ] Control Room

[ ] SATISFACTORY Examiner's Signature: _______________ _

3 V-RQ-JP-19200-005

[ ] Unit 1

[ ] Unit 2

[ ] UNSATISFACTORY

V-RQ-JP-19200-005 This JPM is based on 19200-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

2.

19200-C, Critical Safety Function Status Trees Plant Parameter datasheet from examiner DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

Following a transition from 19000-C, the crew determined that Critical Safety Function monitoring should be implemented.

The SS has directed you to "Evaluateall the CSFSTs and identify any required transition".

4

/

i, V-RQ-JP-19200-005 This JPM is based on 19200-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

2.

19200-C, Critical Safety Function Status Trees Plant Parameter datasheet from examiner DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

Following a transition from 19000-C, the crew determined that Critical Safety Function monitoring should be implemented.

The SS has directed you to "Evaluateall the CSFSTs and identify any required transition".

4

START TIME: ___

STEP 1 CRITICAL ( * )

SAT D.@S' UNSAT D.@S' Determine highest CSF challenge

~D

• Subcriticality - ORANGE

~D

• Core Cooling - Green

~D

• Heat Sink - Yellow

~D

• Integrity - Orange

~D

• Containment - Green

~D

• . Inventory - Yellow STEP 2 CRITICAL ( * )

SAT D.@S' UNSAT D.@S' Determine appropriate FRP

~D

• 19211-C selected V-RQ-JP-19200-005 NOTE: Notifying the SS that an ORANGE path on subcriticality exists would also be appropriate and satisfy the intent of the step.

STEP 3 SAT D£5' UNSAT D£5' Report to 55

~D

• Transition to 19211 is required based on the CSFSTs.

NOTE: Notification that a transition to the ORAGNE path procedure for Subcriticality is also appropriate.

STOP TIME: _____

Field Notes 5

(

START TIME: ___

STEP 1 CRITICAL (.)

SAT O~

UNSAT O~

Determine highest CSF challenge

&0

+ Subcriticality - ORANGE

&0

• Core Cooling - Green

&0

• Heat Sink - Yellow

&0

• Integrity - Orange

&0

• Containment - Green

&0

• . Inventory - Yellow STEP 2 CRITICAL (.)

SAT O~

UNSAT O~

Determine appropriate FRP

&0

+ 19211-C selected V-RQ-JP-19200-005 NOTE: Notifying the SS that an ORANGE path on subcriticality exists would also be appropriate and satisfy the intent of the step.

STEP 3 SAT O~

UNSAT O~

Report to 55

&0

• Transition to 19211 is required based on the CSFSTs.

NOTE: Notification that a transition to the ORAGNE path procedure for Subcriticality is also appropriate.

STOP TIME: ______ _

Field Notes 5

V-RQ-JP-19200-005 PRNI 0%

0%

0%

0%

IRSUR

+0.1 DPM

+0.13 DPM IRNI 3.0x10-4%

3.2x10-4%

SRSUR ODPM ODPM RCS WR Pressure 1980 psig 2000 psig 1990 psig 2010 psig Core Exit TIC's 329 F RCP status Off Off Off Off RVLlS Full Range 100%

100%

100%

100%

RVLlS 100%

100%

100%

100%

Upper Head SG NR Level 0%

0%

0%

0%

AFW flow 205 GPM OGPM 210 GPM 200 GPM SG Pressure 950 psig 26 psig 973 psig 987 psig RCSWR Cold Leg Temperature 540 F 261 F 538 F 541 F CNMT Pressure o psig o psig o psig o psig CNMT Emergency Sump Levels o inches o inches CNMT Radiation 24 mRI Hr 31 mR/Hr PRZR level 100%

100%

100%

6 V-RQ-JP-19200-005 PRNI 0%

0%

0%

0%

IRSUR

+0.1 DPM

+0.13DPM IR NI 3.0x10-4%

3.2x10-4%

SRSUR o DPM ODPM RCS WR Pressure 1980 psig 2000 psig 1990 psig 2010 psig Core Exit TIC's 329 F RCP status Off Off Off Off RVLlS Full Range 100%

100%

100%

100%

RVLlS 100%

100%

100%

100%

(

Upper Head SG NR Level 0%

0%

0%

0%

AFW flow 205 GPM o GPM 210 GPM 200 GPM SG Pressure 950 psig 26 psig 973 psig 987 psig RCSWR Cold Leg Temperature 540 F 261 F 538 F 541 F CNMT Pressure o psig o psig o psig o psig CNMT Emergency Sump Levels o inches o inches CNMT Radiation 24 mR I Hr 31 mR/Hr

(

PRZR level 100%

100%

100%

6

SOUTHERN.\\

COMPANY Energy to Serve Your World'"

PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "b" V-RQ-JP-14905-001 R PERFORM RCS LEAK RATE CALCULATION THIS Is A NEW JPM FOR THE HL-15 NRC EXAM (RO Version)

Revision 0 April 6, 2009 Written By Thad N. Thompson Date:

Approved By Dan Scukanec Date:

4/06/2009 4/20/2009

(

SOUTHERN'\\'

COMPANY Energy to Serve Your WorldS" PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "b" V -RQ-J P-14905-00 1 R PERFORM RCS LEAK RATE CALCULATION THIS Is A NEW JPM FOR THE HL-15 NRC EXAM (RO Version)

Revision 0 April 6, 2009 Written By Thad N. Thompson Date:

Approved By Dan Scukanec Date:

4/06/2009 4/20/2009

V -RQ-JP-14905-001R This information describes the Initial Conditions and the Assigned Task. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: With Unit 1 in Mode 1, the ability to perform aRCS leakrate using the IPC calculation is not functional. The RCS leakrate surveillance is due.

The plant has been stable at 100% power for 322 days. The prerequisites and initial conditions in OSP 14905-1 section 4.0 have been satisfied.

Assigned Task:

The SS has directed you to perform a "manual RCS leakage calculation" using 14905-1 and determine if RCS leakage is within acceptable limits.

Use the provided ReS Leakage Test Data for this determination.

2

(

V-RQ-JP-14905-001R This information describes the Initial Conditions and the Assigned Task. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: With Unit 1 in Mode 1, the ability to perform aRCS leakrate using the IPC calculation is not functional. The RCS leakrate surveillance is due.

The plant has been stable at 100% power for 322 days. The prerequisites and initial conditions in OSP 14905-1 section 4.0 have been satisfied.

Assigned Task:

The SS has directed you to perform a "manual RCS leakage calculation" using 14905-1 and determine if RCS leakage is within acceptable limits.

Use the provided ReS Leakage Test Data for this determination.

2

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

/

/

JPM TITLE:

Title - RCS Leak Rate Calculation VERSION:

o April 6, 2009 COMPLETION TIME:

30 minutes Application:

Task Number:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

RO/SRO 16010 G2.2.12

[ 1 Performed

[ 1 Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

RO:

3.7 SRO:

4.1

[ 1 Simulated

[ 1 Control Room

[ ] SATISFACTORY Examiner's Signature: ______________ _

3 V-RQ-JP~14905-001R

[ 1 Unit 1

[ 1 Unit 2

[ ] UNSATISFACTORY

(

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

JPM TITLE:

Title - RCS Leak Rate Calculation VERSION:

o April 6, 2009 COMPLETION TIME:

30 minutes Application:

Task Number:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

RO/SRO 16010 G2.2.12

[ 1 Performed

[ 1 Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

RO:

3.7 SRO:

4.1

[ 1 Simulated

[ 1 Control Room

[ ] SATISFACTORY Examiner's Signature: _______________ _

3 v -RQ-JP-14905-00 lR

[ 1 Unit 1

[ 1 Unit 2

[ ] UNSATISFACTORY

V -RQ-JP-14905-001R This JPM is based on the latest revision of 14905-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a n©... n are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

14905-1 "RCS Leakage Calculation (Inventory Balance)"

2.

PTDB Tab 4.8 for RCDT Tank Levels SIMULATOR SETUP:

Performance of this JPM does not require the simulator.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions and the Assigned Task. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

With Unit 1 in Mode 1, the ability to perform aRCS leakrate using the IPC calculation is not functional. The RCS leak rate surveillance is due. The plant has been stable at 100% power for 322 days. The prerequisites and initial conditions in asp 14905-1 section 4.0 have been satisfied.

The SS has directed you to perform a "manual ReS leakage calculation" using 14905-1 and determine if RCS leakage is within acceptable limits.

Use the provided ReS Leakage Test Data for this determination.

NOTE TO EXAMINER: It is intended to fill out the RCS Leakage Test Data on Data Sheet 1 and provide to the candidate to eliminate possible transpositional errors. The data is normally collected on Data Sheet 1. The sheet at the back of the JPM is just to keep the data to be provided.

4

(

V-RQ-JP-14905-001R This JPM is based on the latest revision of 14905-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

14905-1 "RCS Leakage Calculation (Inventory Balance)"

2.

PTDB Tab 4.8 for RCDT Tank Levels SIMULATOR SETUP:

Performance of this JPM does not require the simulator.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions and the Assigned Task. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

With Unit 1 in Mode 1, the ability to perform aRCS leak rate using the IPC calculation is not functional. The RCS leak rate surveillance is due. The plant has been stable at 100% power for 322 days. The prerequisites and initial conditions in OSP 14905-1 section 4.0 have been satisfied.

The SS has directed you to perform a "manual ReS leakage calculation" using 14905-1 and determine if RCS leakage is within acceptable limits.

Use the provided ReS Leakage Test Data for this determination.

NOTE TO EXAMINER: It is intended to fill out the RCS Leakage Test Data on Data Sheet 1 and provide to the candidate to eliminate possible transpositional errors. The data is normally collected on Data Sheet 1. The sheet at the back of the JPM is just to keep the data to be provided.

4

START TIME: ___

STEP 1 SAT D~

UNSAT D~

Records Initial and Final Data

~D

• Initiates section 5.2 (# 1)

~D

• Records initial and final data on Data Sheet 1 CUES:

(# 1)

If asked, the PC based spreadsheet data is not available.

STEP 2 CRITICAL (.)

SAT D~

UNSAT D~

Calculates and Determines Total Leak Rate Results per Data Sheet 2.

~D

• Calculates the VCT Gross Leakage to be 144.00 gallons per Data Sheet 2.

Calculation: 48.25% - 40.75% = 7.5% x 19.2 gallons per % = 144 gallons

~D

• Determines RCS Temperature Correction not required per Data Sheet 2.

V-RQ-JP-14905-001R NOTE: Since no RCS temperature or pressure change, no RCS specific volume (Vf) change.

~D

• Calculates the PRZR Level Correction to be 18.58 gallons per Data Sheet 2.

Calculation: 57.8% ave - 57.5% ave = 0.3% x 126.40% = 37.92% x 0.49gal per % = 18.58 gallons

~D

• Crud Tank Inleakage should be entered as O. (CUE # 1)

~D

• Calculates the Total Leakage to be 162.58 gallons per Data Sheet 2.

Calculation: 144 gallons + 0 gallons + 18.58 gallons + 0 gallons = 162.58 gallons

~D

• Calculates the Total Leak Rate of 1.27 gpm per Data Sheet 2.

Calculation: 162.58 gallons 1128 minutes = 1.27 gpm CUES:

(#1) If asked, "The SS has determined Data Sheet 4 for Crud Tank Inleakage is not to be performed".

5 START TIME: ___

STEP 1 SAT O.e:s-UNSAT O.e:s-Records Initial and Final Data

&0

• Initiates section 5.2 (# 1)

&0

• Records initial and final data on Data Sheet 1 CUES:

(# 1)

If asked, the PC based spreadsheet data is not available.

STEP 2 CRITICAL ( +)

SAT O~

UNSAT O~

Calculates and Determines Total Leak Rate Results per Data Sheet 2.

&0

+ Calculates the VCT Gross Leakage to be 144.00 gallons per Data Sheet 2.

Calculation: 48.25% -40.75% = 7.5% x 19.2 gallons per % = 144 gallons

&0

• Determines RCS Temperature Correction not required per Data Sheet 2.

V -RQ-JP-14905-00 lR NOTE: Since no RCS temperature or pressure change, no RCS specific volume (Vf) change.

&0

+ Calculates the PRZR Level Correction to be 18.58 gallons per Data Sheet 2.

Calculation: 57.8% ave - 57.5% ave = 0.3% x 126.40% = 37.92% x 0.49gal per % = 18.58 gallons

&0

• Crud Tank Inleakage should be entered as O. (CUE # 1)

&0

+ Calculates the Total Leakage to be 162.58 gallons per Data Sheet 2.

Calculation: 144 gallons + 0 gallons + 18.58 gallons + 0 gallons = 162.58 gallons

&0

+ Calculates the Total Leak Rate of 1.27 gpm per Data Sheet 2.

Calculation: 162.58 gallons / 128 minutes = 1.27 gpm CUES:

(#1) If asked, 'The SS has determined Data Sheet 4 for Crud Tank Inleakage is not to be performed".

5

STEP 3 CRITICAL ( * )

SAT D.@S" UNSAT D.@S" v -RQ-JP-14905-001R Performs Data Sheet 3 to Evaluate Leak Rate Results (Identified & Unidentified Leakage)

~n

• Returns VCT makeup and letdown to normal, notifies chemistry to resume sampling. (CUE # 1)

~D

• Determines!l..9:2m. PRT in leakage.

NOTE: No PRT level change.

~D

• Calculates RCDT Inleakage to be 23.42 gallons.

Calculation: 193.64 gallons -170.22 gallons = 23.42 gallons NOTE: This is from Tab 4.8 of PTDB (RCDT Levels), 54.0 percent - 48.0 percent values.

~D

• Calculates RCDT Inleakage Rate to be 0.18 gpm.

Calculation: 23.42 gallons 1131 minutes = 0.18 gpm

~D

• Determines Primary-to-Secondary Leakage to be 0.08 gpm.(CUE # 2)

~D

• Determines!l..9:2m. Pressure Isolation Valve Leakage. (CUE # 3)

~D

• Calculates Total Identified Leak Rate to be 0.26 gpm.

Calculation: 0 gpm + 0.18 gpm + 0.08 gpm + 0 gpm = 0.26 gpm (a + b + c + d)

~D

• Determines preliminary leak rate results NOT within acceptance criteria (1.01 gpm).

Calculation: 1.27 Total Leakage - 0.26 Identified = 1.01 Unidentified Leakage

~D

• Determines!l..9:2m. Identified Leakage from other sources. (CUE # 4)

~D

• Determines Final Unidentified Leak Rate results NOT within acceptance criteria (1.01 gpm).

CUES:

Calculation: 1.01 gpm - 0 gpm = 1.01 gpm Unidentified Leakage (Step 5.3.5)

(# 1) The SS reports, "The UO will return VCT makeup and letdown to normal operation. Chemistry will be notified to resume sampling".

(# 2) The SS reports, "Chemistry has determined SG Tube Leakage to be 0.08 gpm".

(# 3) The SS reports, "OSP-14450-1 leakge on Data Sheet # 4 has been determined to be 0 gpm"

(# 4) The SS reports, "Attachment 1 has identified !l..9:2m. Identified Leakage.

6

(

(

STEP 3 CRITICAL (.)

SAT D~

UNSAT D~

v -RQ-JP-1490S-001R Performs Data Sheet 3 to Evaluate Leak Rate Results (Identified & Unidentified Leakage) i:9-D

• Returns VCT makeup and letdown to normal, notifies chemistry to resume sampling. (CUE # 1) i:9-D

• Determines.Q....amn PRT in leakage.

NOTE: No PRT level change.

i:9-D

• Calculates RCDT Inleakage to be 23.42 gallons.

Calculation: 193.64 gallons - 170.22 gallons = 23.42 gallons NOTE: This is from Tab 4.8 of PTDB (RCDT Levels), 54.0 percent - 48.0 percent values.

i:9-D

• Calculates RCDT Inleakage Rate to be 0.18 gpm.

Calculation: 23.42 gallons / 131 minutes = 0.18 gpm i:9-D

• Determines Primary-to-Secondary Leakage to be 0.08 gpm. (CUE # 2) i:9-D

• Determines.Q....amn Pressure Isolation Valve Leakage. (CUE # 3)

• Calculates Total Identified Leak Rate to be 0.26 gpm.

Calculation: 0 gpm + 0.18 gpm + 0.08 gpm + 0 gpm = 0.26 gpm (a + b + c + d) i:9-D

• Determines preliminary leak rate results NOT within acceptance criteria (1.01 gpm).

Calculation: 1.27 Total Leakage - 0.26 Identified = 1.01 Unidentified Leakage i:9-D

• Determines.Q....amn Identified Leakage from other sources. (CUE # 4) i:9-D

• Determines Final Unidentified Leak Rate results NOT within acceptance criteria (1.01 gpm).

CUES:

Calculation: 1.01 gpm - 0 gpm = 1.01 gpm Unidentified Leakage (Step 5.3.5)

(# 1) The SS reports, "The UO will return VCT makeup and letdown to normal operation. Chemistry will be notified to resume sampling".

(# 2) The SS reports, "Chemistry has determined SG Tube Leakage to be 0.08 gpm".

(# 3) The SS reports, "OSP-14450-1 leakge on Data Sheet # 4 has been determined to be 0 gpm"

(# 4) The SS reports, "Attachment 1 has identified.Q....amn Identified Leakage.

6

STEP 4 SAT D£S' UNSAT D£S' Report to 55

~D

• ReS leakage is NOT is within acceptable limits for leakage values.

STOP TIME: _____

Field Notes 7

V-RQ-JP-14905-001R

(

STEP 4 SAT D£S' UNSAT D£S' Report to SS i:Sn

• ReS leakage is NOT is within acceptable limits for leakage values.

STOP TIME: _____

Field Notes 7

v -RQ-JP-14905-00 lR

Res LEAKAGE TEST DATA Start/Stop Time Pressurizer Pressure 1PI-456 1 PI-455 1PI-457 1PI-458 Pressurizer Temperature 1TI-0453 RCS Temperature 1 TI-0412 1TI-0422 1TI-0432 1TI-0442 Pressurizer Level 1 U-0459 1 U-0460 1 U-0461 VCT Level 1 U-0185 PRT Level 1 U-0470 RCDT Level (Data Sheet 5)

Start/Stop Time 1 U-1 003 Crud Tank Leakage Determination (Data Sheet 4)

Primary-to-Seconday Leakage (31120-C)

Pressure Isolation Valve Leakage (14450-1)

Other Identified Leakage Sources (Attachment 1) 8 Initial Reading 14:00 2235.100 2235.600 2232.400 2234.500 653.2 586.400 585.500 585.900 588.400 58.100 57.500 57.800 48.250 78.42 13:57 48.000 V-RQ-JP-14905-001R Final Reading 16:08 2235.000 2235.700 2232.300 2234.600 653.2 586.400 585.400 585.900 588.500 57.800 57.100 57.600 40.750 78.42 16:08 54.000 O/not performed 0.08 o

o

(

Res LEAKAGE TEST DATA Start/Stop Time Pressurizer Pressure 1 PI-456 1 PI-455 1 PI-457 1 PI-458 Pressurizer Temperature 1TI-0453 RCS Temperature 1TI-0412 1TI-0422 1TI-0432 1TI-0442 Pressurizer Level 1 LI-0459 1 LI-0460 1 LI-0461 VCT Level 1 LI-0185 PRT Level 1 LI-0470 RCDT Level (Data Sheet 5)

Start/Stop Time 1L1-1003 Crud Tank Leakage Determination (Data Sheet 4)

Primary-to-Seconday Leakage (31120-C)

Pressure Isolation Valve Leakage (14450-1)

Other Identified Leakage Sources (Attachment 1) 8 Initial Reading 14:00 2235.100 2235.600 2232.400 2234.500 653.2 586.400 585.500 585.900 588.400 58.100 57.500 57.800 48.250 78.42 13:57 48.000 V-RQ-JP-14905-00IR Final Reading 16:08 2235.000 2235.700 2232.300 2234.600 653.2 586.400 585.400 585.900 588.500 57.800 57.100 57.600 40.750 78.42 16:08 54.000 O/not performed 0.08 o

o

SOUTHERN.\\.

COMPANY Energy to Serve Your Worlds.

PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "d" V-RQ-JP-91 002-004 MAKE EMERGENCY NOTIFICATIONS AND RECALL FOR AN ALERT EMERGENCY THIS Is A BANK JPM FOR THE H L-15 NRC EXAM Revision 0 April 6, 2009 Written By Thad N. Thompson Date:

Approved By Dan Scukanec Date:

4/06/2009 4/20/2009 SOUTHERN..

\\

COMPANY Energy to Serve Your World'"

PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "d" V-RQ-JP-91 002-004 MAKE EMERGENCY NOTIFICATIONS AND RECALL FOR AN ALERT EMERGENCY THIS Is A BANK JPM FOR THE HL-15 NRC EXAM Revision 0 April 6, 2009 Written By Thad N. Thompson Date:

Approved By Dan Scukanec Date:

4/06/2009 4/20/2009

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

(9 THIS IS A TIME CRITICAL JPM (9 Initial Conditions: Unit 1 Reactor has been manually tripped in accordance with AOP-18004-C, "RCS Leakage", an emergency has been declared and the Shift Manager has assumed the Emergency Direction position.

Assigned Task:

The Emergency Director has directed you to "Perform the duties of the ENN Communicator" and perform a recall for an Alert Emergency and a roll call in accordance with Checklist 4 and standby to transmit a message.

2

(

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

(9 THIS IS A TIME CRITICAL JPM (9 Initial Conditions: Unit 1 Reactor has been manually tripped in accordance with AOP-18004-C, "RCS Leakage", an emergency has been declared and the Shift Manager has assumed the Emergency Direction position.

Assigned Task:

The Emergency Director has directed you to "Perform the duties of the ENN Communicator" and perform a recall for an Alert Emergency and a roll call in accordance with Checklist 4 and standby to transmit a message.

2

V-RQ-JP-91 002-004 JPM INFORMATION OPERATOR'S NAME: ____________

EVALUATION DATE:

/

/

JPM TITLE:

Make Emergency Notifications and Recall - Alert Emergency REVISION:

o April 6, 2009 COMPLETION TIME:

15 minutes Application:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

RO/SRO G2.4.43

[ ] Perform ed

[ ] Simulator

,minutes OVERALL JPM EVALUATION Examiner Comments:

TIME CRITICAL (9

RO:

3.2 SRO:

4.6

[ ] Simulated

[ ] Control Room

[ ] SATISFACTORY Examiner's Signature: ______________ _

3

[ ] UNSATISFACTORY V-RQ-JP-91 002-004 JPM INFORMATION OPERATOR'S NAME: ____________ _

EVALUATION DATE: _1 __

JPM TITLE:

Make Emergency Notifications and Recall - Alert Emergency REVISION:

o April 6, 2009 COMPLETION TIME:

15 minutes Application:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

ROISRO G2.4.43

[ ] Performed

[ ] Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

TIME CRITICAL

~

RO:

3.2 SRO:

4.6

[ ] Simulated

[ ] Control Room

[ ] SATISFACTORY Examiner's Signature: _______________ _

3

[ ] UNSATISFACTORY

V-RQ-JP-91 002-004 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 91002-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

2.

Procedure 91 002-C, Emergency Notifications, Checklist 2 & 4 VEGP Emergency Response Telephone Directory Simulator not required for JPM performance, however, the ENN phones on the SS throne are required to be utilized.

Notes to Examiner:

(1)

Checklist 2, Sheet 4, Emergency Notification, should be completed with the exception of Steps 1, 2, 3, 10, 12, and 17 prior to the start of this JPM. Step 1.A, THIS IS A DRILL, should always be recorded.

(2)

Step 2 of the Emergency Notification form must be completed within 15 minutes of the time documented in Step 10.A. Once line 2 of the Notification Form (checklist 2) has been read, the time requirement is considered to be met. The start time of this JPM should be the time recorded in Step 10.A.

(3)

Ensure the ENN telephone jack in the rear of the ENN telephone has the "Simulator" cord installed.

(4)

Ensure the ENN telephone in the instructor simbooth is plugged into the phone jack and test communications with SS throne before initiation.

(5)

Test the emergency recall phone number for Alert Emergency with a Security Emergency prior to initiation.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

This is a TIME CRITICAL JPM Unit 1 Reactor has been manually tripped in accordance with AOP-18004-C, "RCS Leakage", an emergency has been declared and the Shift Manager has assumed the Emergency Direction position.

The Emergency Director has directed you to "Perform the duties of the ENN Communicator" and perform a recall for an Alert Emergency and a roll call in accordance with Checklist 4 and standby to transmit a message.

4 V-RQ-JP-91 002-004 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 91 002-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a n©... n are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

2.

Procedure 91 002-C, Emergency Notifications, Checklist 2 & 4 VEGP Emergency Response Telephone Directory Simulator not required for JPM performance, however, the ENN phones on the SS throne are required to be utilized.

Notes to Examiner:

(1)

Checklist 2, Sheet 4, Emergency Notification, should be completed with the exception of Steps 1, 2, 3, 10, 12, and 17 prior to the start of this JPM. Step 1.A, THIS IS A DRILL, should always be recorded.

(2)

Step 2 of the Emergency Notification form must be completed within 15 minutes of the time documented in Step 10.A. Once line 2 of the Notification Form (checklist 2) has been read, the time requirement is considered to be met. The start time of this JPM should be the time recorded in Step 10.A.

(3)

Ensure the ENN telephone jack in the rear of the ENN telephone has the "Simulator" cord installed.

(4)

Ensure the ENN telephone in the instructor simbooth is plugged into the phone jack and test communications with SS throne before initiation.

(5)

Test the emergency recall phone number for Alert Emergency with a Security Emergency prior to initiation.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

This is a TIME CRITICAL JPM Unit 1 Reactor has been manually tripped in accordance with AOP-18004-C, "RCS Leakage", an emergency has been declared and the Shift Manager has assumed the Emergency Direction position.

The Emergency Director has directed you to "Perform the duties of the ENN Communicator" and perform a recall for an Alert Emergency and a roll call in accordance with Checklist 4 and standby to transmit a message.

4

JPM STEPS START TIME FOR TIME CRITICAL: ___

TIME CRITICAL (9 STEP 1 SAT D2S' UNSAT D2S' Locate PRIMARY Recall System Remote Activation Instructions V-RQ-JP-91 002-004 Note:

The Emergency Preparedness Primary Recall System Remote Activation Instructions should be located in the middle drawer(Labeled ENN Communicator) of the file drawer on the Shift Supervisor Area Of The Simulator.

~D

• Envelope Located STEP 2 CRITICAL ( * )

SAT D2S' UNSAT D2S' Call Emergency Recall System Note:

The requirement for using 9 prior to dialing the number will depend on which phone the Examinee uses. If the Plant Vogt/e PBX System Phones are used a 9 will be required. If a Bell South Outside Une is used, dialing 9 prior to the to the number is NOT required.

~D

• Dial 554-4316 (this is the phone # for an ALERT classification) (CUE # 1)

CUES: (# 1) "please turn on the speaker".

STEP 3 CRITICAL ( * )

SAT D2S' UNSAT D2S' Scenario Activation Password

~D

• Enter {934 987 509} followed by the # sign STEP 4 CRITICAL ( * )

SAT D2S' UNSAT D2S' Scenario 10

~D

• Enter {917 566 662} followed by the (pound sign) # sign 5

(

JPM STEPS START TIME FOR TIME CRITICAL: ___

TIME CRITICAL ~

STEP 1 SAT O£)'

UNSAT O£)'

Locate PRIMARY Recall System Remote Activation Instructions V-RQ-JP-91 002-004 Note:

The Emergency Preparedness Primary Recall System Remote Activation Instructions should be located in the middle drawer(Labeled ENN Communicator) of the file drawer on the Shift Supervisor Area Of The Simulator.

&0

• Envelope Located STEP 2 CRITICAL (. )

SAT O£)'

UNSAT O£)'

Call Emergency Recall System Note:

The requirement for using 9 prior to dialing the number will depend on which phone the Examinee uses. If the Plant Vogt/e PBX System Phones are used a 9 will be required. If a Bell South Outside Line is used, dialing 9 prior to the to the number is NOT required.

&0

+ Dial 554-4316 (this is the phone # for an ALERT classification) (CUE # 1)

CUES: (# 1) "please turn on the speaker".

STEP 3 CRITICAL (. )

SAT O£)'

UNSAT O£)'

Scenario Activation Password

&0

+ Enter {934 987 509} followed by the # sign STEP 4 CRITICAL (. )

SAT O£)'

UNSAT O£)'

Scenario 10

&0

+ Enter {917 566 662} followed by the (pound sign) # sign 5

STEPS CRITICAL ( * )

SAT D.@S" UNSAT D.@S" Start Scenario V-RQ-JP-91 002-004 JPM STEPS Note:

The (pound sign) # should only be pressed AFTER the completion of the message "the scenario is building".

~D

• Press {3}

~D

• Press (pound sign) # and hang up STEP 6 SAT D.@S" UNSAT D.@S" Verify Recall System Working Properly

~D

• Extension 3652 called by the recall system 6

STEP 5 CRITICAL (+)

SAT O~

UNSAT O~

Start Scenario V-RQ-JP-91 002-004 JPM STEPS Note:

The (pound sign) # should only be pressed AFTER the completion of the message "the scenario is building".

&0

+ Press {3}

&0

+ Press (pound sign) # and hang up STEP 6 SAT O£S" UNSAT O~

Verify Recall System Working Properly

&0

• Extension 3652 called by the recall system 6

(

STEP 7 CRITICAL ( * )

SAT D~

UNSAT D~

JPM STEPS NOTIFICATION ROLL CALL per section II V-RQ-JP-91 002-004 Note:

The Emergency Response Telephone Directory, or the dial code card, should be consulted as needed for required ENN dial codes. The dial code, **, should be used initially to ring ALL required agencies.

~D

• Step # 1, N/A, this is the initial notification.

~D

• Step # 2a, Ensures Emergency Response Telephone Directory is present (ERTD)

~D

• Step # 2b, ensures the Log Book is present.

~D

• Step # 3a, performs a roll call by depressing ** on the ENN phone to ring ALL stations.

~D

• Step # 3b, states "this is a drill" when simbooth operator responds.

~D

• Step # 3b, states Hello, this is "Operator's Name" and informs offsite agencies to get a copy of the notification form and standby to receive a message.

~D

• Step # 3c, proceeds with roll call.

~D

• Burke County notified (CUE # 1, simbooth operator)

~D

• GEMA notified (CUE # 1, simbooth operator)

~D

• Aiken County notified (CUE # 1, simbooth operator)

~D

• SRS notifed (CUE # 1, simbooth operator)

~D

• Allendale County notified (CUE # 1, simbooth operator)

~D

• State of South Carolina notified (CUE # 1, simbooth operator)

~D

• Barnwell County (CUE # 1, simbooth operator)

CUES:

(# 1, simbooth operator) Respond with the name of the offsite agency hailed.

7 STEP 7 CRITICAL ( + )

SAT D~

UNSAT D~

JPM STEPS NOTIFICATION ROLL CALL per section II V-RQ-JP-91 002-004 Note:

The Emergency Response Telephone Directory, or the dial code card, should be consulted as needed for required ENN dial codes. The dial code, **, should be used initially to ring ALL required agencies.

13..0

• Step # 1, N/A, this is the initial notification.

13..0

• Step # 2a, Ensures Emergency Response Telephone Directory is present (ERTD) 13..0

• Step # 2b, ensures the Log Book is present.

13..0

• Step # 3a, performs a roll call by depressing ** on the ENN phone to ring ALL stations.

"&0

• Step # 3b, states "this is a drill" when simbooth operator responds.

"&0

• Step # 3b, states Hello, this is "Operator's Name" and informs offsite agencies to get a copy of the notification form and standby to receive a message.

"&0

• Step # 3c, proceeds with roll call.

"&0

+ Burke County notified (CUE # 1, simbooth operator)

"&0

+ GEMA notified (CUE # 1, simbooth operator)

"&0

+ Aiken County notified (CUE # 1, simbooth operator)

"&0

+ SRS notifed (CUE # 1, simbooth operator)

"&0

+ Allendale County notified (CUE # 1, simbooth operator)

"&0

+ State of South Carolina notified (CUE # 1, simbooth operator)

"&0

+ Barnwell County (CUE # 1, simbooth operator)

CUES:

(# 1, simbooth operator) Respond with the name of the offsite agency hailed.

7

STEP 8 SAT D~

UNSAT D~

JPM STEPS Section III, Transmission of Notification Message Step 1a. Transmit fascimile V-RQ-JP-91 002-004 Note:

On the Fax machine in the Simulator, the pushbutton labelled "NOOiOITI/IFI~ITiiiralinlinll"lslhOlulldlblelidlelnlti"iiierid.ais.th.eibiutt.on to simulate "NOTIFY", A cue to the examinee should be provided !ill CUES:

• Place message face down in transmit

• NOTIFY(Training) pushbutton depressed (# 1)

NOTE: If the operator feels pressed for time, the operator may transmit the data on the notification form first, then perform the fax. This is acceptable performance. The last bullet in the notes prior to the transmission steps states the faxing should not delay transmittal.

(# 1)

When proper button is identified performed" STEP 9 CRITICAL ( * )

SAT D..@S' UNSAT D..@S' Communicate notification via ENN Note:

Examiner should arbitrarily pick a number between 1 and 100 and verify that the authentication codeword is correctly identified by examinee.

~n

• Lines 1 & 2 transmitted (DRILL and message #)

~D

• Line 2, (block A for INITIAL, Notification time & date completed (# 1)

~D. Line 3, Site Vogtle, Control Room confirmation phone number transmitted CUES:

(# 1)

After completion of Emergency Notification form line 2, provide the following cue, "The State of South Carolina request that you authenticate number 27.

Don't read this word, just verify he gets the right word (Mustang)."

STOP TIME FOR TIME CRITICAL: ___

STEP 10 CRITICAL ( * )

SAT D..@S' UNSAT D..@S' Message authentication Note:

The authentication codes are located in the Emergency Response Telephone Directory. The codeword provided should match the number given in the cue of JPM Step 3.

~D

• Line # 2, Authentication codeword correctly provided. (# 1) 8

(

V-RQ-JP-91 002-004 JPM STEPS STEP 8 SAT D~

UNSAT D~

Section III, Transmission of Notification Message Step 1a. Transmit fascimile Note:

On the Fax machine in the Simulator, the pushbutton labelled "NOTlFY(Training)" should be identified as the button to simulate "NOTIFY", A cue to the examinee should be provided NOT to depress any pushbuttons for Exam Sequrity.

'l:s..D

• Place message face down in transmit tray

'l:s..D

• NOTIFY(Training) pushbutton SIMULAtED depressed (# 1)

CUES:

NOTE: If the operator feels pressed for time, the operator may transmit the data on the notification form first, then perform the fax. This is acceptable performance. The last bullet in the notes prior to the transmission steps states the faxing should not delay transmittal.

(# 1)

When proper button is identified, provide the cue that "Notification via the Fax has been performed" (qp NOT.let Ex~fninee\\.*depr~$s any of the buttons).

STEP 9 CRITICAL (. )

SAT D~

UNSAT D~

CUES:

Communicate notification via ENN Note:

Examiner should arbitrarily pick a number between 1 and 100 and verify that the authentication codeword is correctly identified by examinee.

• Lines 1 & 2 transmitted (DRILL and message #)

• Line 2, (block A for INITIAL, Notification time & date completed (# 1)

• Line 3, Site Vogtle, Control Room confirmation phone number transmitted

(# 1)

After completion of Emergency Notification form line 2, provide the following cue, "The State of South Carolina request that you authenticate number 27.

Don't read this word, just verify he gets the right word (Mustang)."

STOP TIME FOR TIME CRITICAL: ___

STEP 10 CRITICAL ( * )

SAT D~

UNSAT D~

Message authentication Note:

The authentication codes are located in the Emergency Response Telephone Directory. The codeword provided should match the number given in the cue of JPM Step 3.

'l:s..D

• Line # 2, Authentication codeword correctly provided. (# 1) 8

STEP 11 CRITICAL ( * )

SAT O..@S" UNSAT O..@S" Transmit classification data JPM STEPS

'2:s..D

• Line 4, Emergency Classification - block B, ALERT

'2:s..D

• Emergency description - FA1

'2:s..D

• Line 5, Protective Action Recommendations - block A, NONE

'2:s..D

• Line 6, Emergency Release, block A - None 9

V-RQ-JP-91 002-004

(

(

STEP 11 CRITICAL ( + )

SAT O,g-UNSAT O,g-Transmit classification data JPM STEPS

&0

+ Line 4, Emergency Classification - block B, ALERT

&0

• Emergency description - FA1

&0

+ Line 5, Protective Action Recommendations - block A, NONE

&0

+ Line 6, Emergency Release, block A - None 9

V-RQ-JP-91 002-004

STEP 12 CRITICAL ( * )

SAT D£S' UNSAT D£S' JPM STEPS Transmit current plant radiological I plant conditions Ci-D

• Line 7, Release significance, block A, not applicable Ci-D

• Line 8, Event prognosis, block B, stable V-RQ-JP-91 002-004 Ci-D

• Line 9, Meteorological data, wind direction 69 degrees, wind speed 4.6 mph, stability class - D, no precipitation Ci-D

• Line 10, Declaration Time and Date Ci-D

• Line 11, Affected Unit(s) - Unit 1 Ci-D

• Line 12, Unit Status - Unit 1 at 0%, Unit 2 at 100%, both shutdown at time (NOTE: Same time as line 10)

Ci-D

• Line 13, Remarks - none Ci-D

• Line 17, Approved by Date and Time - Thad N. Thompson Ci-D

• Notified by Date and Time - the candidate's name STEP 13 SAT D£S' UNSAT D£S' Notify ED Ci-D

• Initial Emergency Notification completed Field Notes:

10 STEP 12 CRITICAL (+)

SAT 0-6 UNSAT 0-6 JPM STEPS Transmit current plant radiological! plant conditions

'&0

• Line 7, Release significance, block A, not applicable

'&0

• Line 8, Event prognosis, block B, stable V-RQ-JP-91 002-004

'&0

+ Line 9, Meteorological data, wind direction 69 degrees, wind speed 4.6 mph, stability class - D, no precipitation

'&0

+ Line 10, Declaration Time and Date

'&0

• Line 11, Affected Unit(s) - Unit 1

'&0

• Line 12, Unit Status - Unit 1 at 0%, Unit 2 at 100%, both shutdown at time (NOTE: Same time as line 10)

'&0

• Line 13, Remarks - none

'&0

• Line 17, Approved by Date and Time - Thad N. Thompson

'&0

• Notified by Date and Time - the candidate's name STEP 13 SAT O£\\'

UNSAT O£\\'

Notify ED

'&0

• Initial Emergency Notification completed Field Notes:

10

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Vogtle Nuclear Plant Date of Examination: June 1-12,2009 Examination Level: SRO Operating Test Number: 2009-301 Administrative Topic (see Type Describe activity to be performed Note)

Code*

Title:

Boration Calculation

==

Description:==

Manually calculate boric acid required for reactor trip with 3 Conduct of Operations rods stuck at different heights. Students are required to determine R,M required increase in boric acid and the total volume of boric acid to add to the RCS. This task will also will require referencing the Plant Technical Data Book Tab 2.3 to determine boric acid volume. This JPM has been modified to use different data to determine the volume of boric acid to add to the RCS.

KIA: G2.1.25 (3.9/4.2)

Title:

Loss of Safety Function Evaluation Conduct of Operations R, D, P

==

Description:==

A Train "A" Safety Related component will be tagged out when a 120V AC 1 E Vital Bus is required to be put on the regulated transformer (alternate source). The candidate will have to perform a LOSF Evaluation and determine that a loss of safety function exists.

KIA: G 2.1.1 (4.2)

Title:

RCS Leak Rate Calculation

==

Description:==

Students will be required to perform a manual RCS leak Equipment Control R,N rate calculation given a set of initial and final plant data. This will also require calculating the average initial and final values. The initial leak rates will be adjusted for RCDT in leakage and SGTL. Final values will exceed Tech Spec limit for unidentified leakage. SRO's will be required to identify LCO 3.4.13 condition A required actions.

KIA: G 2.2.12(3.7/4.1)

Title:

Stay Time Calculation for High Radiation Area Radiation Control R,N

==

Description:==

Students will be provided with room survey data. From the survey they will be required to calculate allowable stay time for an individual based on the work required and the persons previous dose history.

KIA: G2.3.12 (3.7)

Title:

Classify Emergency Emergency Procedures/Plan R,N

==

Description:==

Scenario will require classification of a general emergency with the new shutdown EALs and proper completion of the ENN form including PARs. Loss of RV inventory to the extent fuel is uncovered while RCS and CNMT barriers are opened.

KIA: G2.4.41 (4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (~ 1; randomly selected)

(

ES*301, Rev. 9 Administrative Topics Outline Form ES*301*1

\\

Facility: Vogtle Nuclear Plant Date of Examination: June 1-12, 2009 Examination Level: SRO Operating Test Number: 2009-301 Administrative Topic (see Type Describe activity to be performed Note)

Code*

Title:

Boration Calculation

==

Description:==

Manually calculate boric acid required for reactor trip with 3 rods stuck at different heights. Students are required to determine Conduct of Operations R,M required increase in boric acid and the total volume of boric acid to add to the RCS. This task will also will require referencing the Plant Technical Data Book Tab 2.3 to determine boric acid volume. This JPM has been modified to use different data to determine the volume of boric acid to add to the RCS.

KIA: G2.1.25 (3.9 14.2)

Title:

Loss of Safety Function Evaluation Conduct of Operations R,D, P

==

Description:==

A Train "A" Safety Related component will be tagged out when a 120V AC 1 E Vital Bus is req uired to be put on the regulated transformer (alternate source). The candidate will have to perform a LOSF Evaluation and determine that a loss of safety function exists.

KIA: G 2.1.1 (4.2)

Title:

RCS Leak Rate Calculation

==

Description:==

Students will be required to perform a manual RCS leak Equipment Control R,N rate calculation given a set of initial and final plant data. This will also require calculating the average initial and final values. The initial leak

(

rates will be adjusted for RCDT in leakage and SGTL. Final values will exceed Tech Spec limit for unidentified leakage. SRO's will be required to identify LCO 3.4.13 condition A required actions.

KIA: G 2.2.12 (3.7 I 4.1)

Title:

Stay Time Calculation for High Radiation Area Radiation Control R,N

==

Description:==

Students will be provided with room survey data. From the survey they will be required to calculate allowable stay time for an individual based on the work required and the persons previous dose history.

KIA: G2.3.12(3.7)

Title:

Classify Emergency Emergency Procedures/Plan R,N

==

Description:==

Scenario will require classification of a general emergency with the new shutdown EALs and proper completion of the ENN form including PARs. Loss of RV inventory to the extent fuel is uncovered while RCS and CNMT barriers are opened.

KIA: G2.4.41 (4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ::: 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (::: 1; randomly selected)

(

SOUTHERN COMPANY Energy to Serve Your World'M PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Administrative JPM "a.1" V-RQ-JP-19001-003 Calculate Boron Addition Following Reactor Trip With 3 Stuck Rods (This is a Modified JPM For The HL-15 NRC Exam)

Revision 0 March 5th, 2009 Written By

Thad N. Thom pson Date:

3/05/2009 Approved By : Dan Scukanec Date:

4/20/2009 SOUTHERN.\\

COMPANY Energy to Serve Your World'"

PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Administrative JPM "a.1" V-RQ-JP-19001-003 Calculate Boron Addition Following Reactor Trip With 3 Stuck Rods (This is a Modified JPM For The HL-15 NRC Exam)

Revision 0 March 5th, 2009 Written By

Thad N. Thompson Date:

3/05/2009 Approved By

Dan Scukanec Date:

4/20/2009

V-RQ-JP-19001-003 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOl RCS Boron Concentration is at 400 ppm BAST Boron Concentration is 7300 ppm It RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates the following rod positions Control 8ank "8" rod Fm14::: 18 steps Shutdown Bank "A" Rod D-2 ::: 216 steps Control Bank "D" Rod M-4::: 192 steps The RO actuates both the QMCB Reactor Trip Hand switches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 7 of 19001-C the SS checks "all Rods - FUllY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

(

V-RQ-JP-19001-003 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOl RCS Boron Concentration is at 400 ppm BAST Boron Concentration is 7300 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range Ni's indicate 0%

DRPI indicates the following rod positions Control Bank "B" rod F-14 = 18 steps Shutdown Bank "A" Rod D-2 = 216 steps Control Bank "D" Rod M-4 = 192 steps The RO actuates both the QMCB Reactor Trip Hand switches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 7 of 19001-C the SS checks "all Rods - FUllY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

/

/

JPM TITLE:

Boron Addition Calculation - 3 Stuck Rods COMPLETION TIME:

8 minutes Application:

Task Number:

KIA Number:

Evaluation Method RO/SRO 37004 G2.1.25 RO:

3.9

[ 1 Performed SRO:

4.2 V-RQ-JP-19001-003

[ 1 Simulated Evaluation Location

[ 1 Simulator

[ 1 Control Room

[1 Unit 1

[ 1 Unit 2 Performance Time: __

minutes OVERALL JPM EVALUATION*

[ 1 SATISFACTORY

[ 1 UNSATISFACTORY Examiner Comments:

Examiner's Signature:

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

/

/

JPM TITLE:

Boron Addition Calculation - 3 Stuck Rods COMPLETION TIME:

8 minutes Application:

Task Number:

KIA Number:

Evaluation Method RO/SRO 37004 G2.1.25 RO:

3.9

[ ] Performed SRO:

4.2 V-RQ-JP-19001-003

[ ] Simulated Evaluation Location

[ ] Simulator

[ ] Control Room

[] Unit 1

[ ] Unit 2 Performance Time:

minutes OVERALL JPM EVALUATION

[ ] SATISFACTORY

[ ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

(

V-RQ-JP-19001-003 INSTRUCTIONS TO EXAMINER This JPM is based on latest revision of 19001-C. If this revision is no longer current, verify this JPM is in accord with the latest procedural revision. Cues preceded by a.. ©..... are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable.

REQUIRED ITEMS:

1. Calculator

2. PTDB (Plant Technical Data Book, Tab 2 in particular is required)

3. 19001-C, step # 7 Direction To Operator:

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOL RCS Boron Concentration is at 400 ppm BAST Boron Concentration is 7300 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates the following rod positions Control Bank "B" rod F-14 = 6 steps Shutdown Bank "A" Rod 0-2 = 216 steps Control Bank "0" Rod M-4 = 192 steps The RO actuates both the QMCB Reactor Trip Hand switches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 7 of 19001-C the SS checks "all Rods - FULLY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

V -RQ-JP-19001-003 INSTRUCTIONS TO EXAMINER This JPM is based on latest revision of 19001-C. If this revision is no longer current, verify this JPM is in accord with the latest procedural revision. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable.

REQUIRED ITEMS:

1. Calculator

2. PTDB (Plant Technical Data Book, Tab 2 in particular is required)

3. 19001-C, step # 7 Direction To Operator:

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip EOl RCS Boron Concentration is at 400 ppm BAST Boron Concentration is 7300 ppm RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

Reactor Trip Breakers are open Power Range NI's indicate 0%

DRPI indicates the following rod positions Control Bank "B" rod F-14 = 6 steps Shutdown Bank "A" Rod D-2 = 216 steps Control Bank "D" Rod M-4 = 192 steps The RO actuates both the QMCB Reactor Trip Hand switches and announces the Reactor Tripped The Operating Crew has entered 19001-C to stabilize the plant On Step 7 of 19001-C the SS checks "all Rods - FUllY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

(

V-RQ-JP-19001-003 START TIME: ___

STEP 1 CRITICAL ( * )

SAT OAS' UNSAT OAS' Boron Addition to the RCS calculated

'1::5..0

• Determine that 154 ppm per rod is required for 3 stuck rods (NOTE: Plausible they may not count the shutdown bank rod which would be incorrect and a failure of the JPM).

'1::5..0

• For three stuck rods boration required is: (154 ppm) X (3 rods) = 462 ppm

'1::5..0

• Calculate the required boration using equation for PTDS tab 2.3 (expected)

(Note: Tolerance data is based on a candidate using the tables - interpolation, and possible rounding off of In calculation)

'1::5..0

• 4251 (+/- 50) gallons of boric acid added to the RCS STOP TIME: _____

Field Notes Calculation:

(154 ppm) X (3 rods) = 462 ppm RCS Boron Concentration = 61346 x Ln [(7300 - 400) + (7300 - 862)] = 4251 gallons of Boric Acid V-RQ-JP-19001-003 START TIME: ____ _

STEP 1 CRITICAL ( + )

SAT O~

UNSAT O~

Boron Addition to the RCS calculated

&0 + Determine that 154 ppm per rod is required for 3 stuck rods (NOTE: Plausible they may not count the shutdown bank rod which would be incorrect and a failure of the JPM).

&0 + For three stuck rods boration required is: (154 ppm) X (3 rods) = 462 ppm

&0 + Calculate the required boration using equation for PTDB tab 2.3 (expected)

(Note: Tolerance data is based on a candidate using the tables - interpolation, and possible rounding off of In calculation)

&0 + 4251 (+/- 50) gallons of boric acid added to the RCS STOP TIME: ______ _

Field Notes Calculation:

(154 ppm) X (3 rods) = 462 ppm RCS Boron Concentration = 61346 x Ln [(7300 - 400) + (7300 - 862)] = 4251 gallons of Boric Acid

SOUTHERN.\\

COMPANY Energy to Serve Your "WOrld'"

PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "a.2" V-LO-JP-10008-001 LOSF EVALUATION THIS Is A BANK JPM FOR THE HL-15 NRC EXAM (THIS Is A PREVIOUSLY USED JPM FROM THE HL-14 JPM EXAM THAT WAS RANDOMLY SELECTED)

Revision 0 March 4th, 2009 Written By:

Thad N. Thompson Date:

3/04/2009 Approved By: Dan Scukanec Date:

4/20/2009 SOUTHERN'\\

COMPANY Energy to Serve Your World SM PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "a.2" V-LO-JP-10008-001

(

LOSF EVALUATION THIS Is A BANK JPM FOR THE HL-15 NRC EXAM (THIS Is A PREVIOUSLY USED JPM FROM THE HL-14JPM EXAM THAT WAS RANDOMLY SELECTED)

Revision 0 March 4th, 2009 Written By:

Thad N. Thompson Date:

3/04/2009 Approved By: Dan Scu kanec Date:

4/20/2009

(

V-LO-JP-I0008-001 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: With OG '1A' out of service for corrective maintenance, a loss of 1 BY2B occurs due to a fault on inverter 1B01112. 1BY2B has been subsequently reenergized via the regulated transformer power source.

Assigned Task:

LCO 3.B.1 Condition B is in effect and has been recorded.

LCO 3.B.9 Condition B is in effect and has been recorded.

The SS has directed you to use 1000B-C, "Recording Limiting Conditions for Operation" and determine what LCO conditions are required to be entered and if a LOSF exists. Using a highlighter, also trace the flowpath utilized on the 1000B-C Figure 5 "LOSF Evaluation Flowchart".

2 v -LO-JP-1 0008-001 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: With OG '1A' out of service for corrective maintenance, a loss of 1 BY2B occurs due to a fault on inverter 1 B01112. 1 BY2B has been subsequently reenergized via the regulated transformer power source.

Assigned Task:

LCO 3.B.1 Condition B is in effect and has been recorded.

LCO 3.B.9 Condition B is in effect and has been recorded.

The SS has directed you to use 1000B-C, "Recording Limiting Conditions for Operation" and determine what LCO conditions are required to be entered and if a LOSF exists. Using a highlighter, also trace the flowpath utilized on the 1000B-C Figure 5 "LOSF Evaluation Flowchart".

2

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

1 1

JPM TITLE:

LOSF Evaluation REVISION:

1 3/4/2009 COMPLETION TIME:

15 minutes Application:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

ROISRO G2.1.1

[ 1 Performed

[ 1 Simulator

,minutes RO:

2.1.1 SRO:

4.2

[,l Simulated

[ 1 Control Room OVERALL JPM EVALUATION

[ ] SATISFACTORY Examiner Comments:

Examiner's Signature: ______________ _

3 V-LO-J P-1 0008-001

[ 1 Unit 1

[ 1 Unit2

[ ] UNSATISFACTORY

(

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

1 JPM TITLE:

LOSF Evaluation REVISION:

1 3/4/2009 COMPLETION TIME:

15 minutes Application:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

ROISRO G2.1.1

[ 1 Performed

[ 1 Simulator minutes RO:

2.1.1 SRO:

4.2

[ 1 Simulated

[ 1 Control Room OVERALL JPM EVALUATION

[ ] SATISFACTORY Examiner Comments:

Examiner's Signature: _______________ _

3 V-LO-JP-10008-001

[ 1 Unit 1

[ 1 Unit 2

[ ] UNSATISFACTORY

V -LO-JP-1 0008-001 This JPM is based on the latest rev of 10008-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

2.

10008-1, "Recording Limiting Conditions For Operation" Technical Specifications Performance of this JPM does not require the simulator.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

With DG 'A' out of service for corrective maintenance, a loss of 1 BY2B occurs due to a fault on inverter 1 BD1112. 1 BY2B has been subsequently reenergized via the regulated transformer power source.

LCO 3.8.1 Condition B is in effect and has been recorded.

LCO 3.8.9 Condition B is in effect and has been recorded.

The SS has directed you to use 10008-C, "Recording Limiting Conditions for Operation" and determine what LCO conditions are required to be entered and if a LOSF exists.

Using a highlighter, also trace the flowpath utilized on the 10008-C Figure 5 "LOSF Evaluation Flowpath.

4

(

V-LO-JP-10008-001 This JPM is based on the latest rev of 1000B-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

2.

1 000B-1, "Recording Limiting Conditions For Operation" Technical Specifications Performance of this JPM does not require the simulator.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

With OG 'A' out of service for corrective maintenance, a loss of 1 BY2B occurs due to a fault on inverter 1 B01112. 1 BY2B has been subsequently reenergized via the regulated transformer power source.

LCO 3.B.1 Condition B is in effect and has been recorded.

LCO 3.B.9 Condition B is in effect and has been recorded.

The SS has directed you to use 1000B-C, "Recording Limiting Conditions for Operation" and determine what LCO conditions are required to be entered and if a LOSF exists.

Using a highlighter, also trace the flowpath utilized on the 1000B-C Figure 5 "LOSF Evaluation Flowpath.

4

START TIME: ___

STEP 1 CRITICAL ( * )

SAT 0,.(6 UNSAT 0,.(6 LCO Conditions Identified v -LO-JP-l 0008-001 Note:

The previously in effect LCO Conditions may be identified but are not required for satisfactory performance.

~O

• TS LCO 3.B.1 Condition B (previously in effect)

~O

• TS LCO 3.B.9 Condition B (may be identified as temporarily being entered prior to bus reenegization)

~O

• TS LCO 3.B.7 Condition A (# 1)

CUE: (# 1) "A Support Shift Supervisor (SSS) will fill out the LCO form".

STEP 2 CRITICAL (.)

SAT 0,.(6 UNSAT 0,.(6 LOSF Evaluation Note:

LOSF exists via inoperability of both OG's (OG 'A' initially OOS and declaration of DB 'B' via 1B01l12 support inoperability to the 'B'sequencer).

~O

• Determines YES to "are required SUPPORT or SUPPORTED systems INOPERABLE on redundant Safety Related Trains ?"

~O

• Performs LOSF Evaluation (Step 3.5.6) of 1000B-C

~O

• Determines YES to LOSF present (due to the other DG is INOPERABLE)

STEP 3 CRITICAL ( * )

SAT 0,.(6 UNSAT 0,.(6 LCO Conditions Identified

~O

• TS LCO 3.8.1 Condition F identified to be entered due to the LOSF exists determination

~O

• TS LCO 3.B.1 Condition G and B (specifically note the offsite source verification) identified to be entered STEP 4 SAT O~

UNSAT O~

Report to SS

~O

• LCO conditions identified and LOSF exists determination made STOP TIME: _____

Field Notes

(

START TIME: ___

STEP 1 CRITICAL (.)

SAT D~

UNSAT D~

LCO Conditions Identified V-LO-JP-I0008-001 Note:

The previously in effect LCO Conditions may be identified but are not required for satisfactory performance.

i:s.D

• TS LCO 3.8.1 Condition B (previously in effect) i:s.D

• TS LCO 3.8.9 Condition B (may be identified as temporarily being entered prior to bus reenegization) i:s.D

• TS LCO 3.8.7 Condition A (# 1)

CUE: (# 1) "A Support Shift Supervisor (SSS) will fill out the LCO form".

STEP 2 CRITICAL (.)

SAT D~

UNSAT D~

LOSF Evaluation Note:

LOSF exists via inoperability of both OG's (OG 'A' initially OOS and declaration of DB 'B' via 1B01l12 support inoperability to the 'B'sequencer).

• Determines YES to "are required SUPPORT or SUPPORTED systems INOPERABLE on redundant Safety Related Trains ?"

• Performs LOSF Evaluation (Step 3.5.6) of 10008-C

• Determines YES to LOSF present (due to the other DG is INOPERABLE)

STEP 3 CRITICAL (.)

SAT D~

UNSAT D~

LCO Conditions Identified i:s.D

• TS LCO 3.8.1 Condition F identified to be entered due to the LOSF exists determination i:s.D

• TS LCO 3.8.1 Condition G and B (specifically note the offsite source verification) identified to be entered STEP 4 SAT D£S" UNSAT D~

Report to SS i:s.D

• LCO conditions identified and LOSF exists determination made STOP TIME: _____

Field Notes

SOUTHERN.\\

COMPANY Energy to Serve Your World'M PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "b" V-RQ-JP-14905-001 S PERFORM RCS LEAK RATE CALCULATION THIS 15 A NEW JPM FOR THE HL-15 NRC EXAM (SRO Version)

Revision 0 April 6, 2009 Written By Thad N. Thompson Date:

Approved By Dan Scukanec Date:

4/06/2009 4/20/2009

(

SOUTHERN.\\'

COMPANY Energy to Serve Your World'"

PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "b" V-RQ-JP-14905-001 S PERFORM RCS LEAK RATE CALCULATION THIS Is A NEW JPM FOR THE HL-15 NRC EXAM (SRO Version)

Revision 0 April 6, 2009 Written By Thad N. Thompson Date:

Approved By Dan Scukanec Date:

4/06/2009 4/20/2009

V-RQ-JP-14905-001S This information describes the Initial Conditions and the Assigned Task. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: With Unit 1 in Mode 1, the ability to perform aRCS leakrate using the IPC calculation is not functional. The RCS leakrate surveillance is due.

The plant has been stable at 100% power for 322 days. The prerequisites and initial conditions in OSP 14905-1 section 4.0 have been satisfied.

Assigned Task:

You are the SS, perform a "manual ReS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any).

Use the provided ReS Leakage Test Data for this determination.

2

(

(

V-RQ-JP-14905-001S This information describes the Initial Conditions and the Assigned Task. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: With Unit 1 in Mode 1, the ability to perform a ReS leakrate using the IPe calculation is not functional. The ReS leakrate surveillance is due.

The plant has been stable at 100% power for 322 days. The prerequisites and initial conditions in OSP 14905-1 section 4.0 have been satisfied.

Assigned Task:

You are the SS, perform a "manual ReS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any).

Use the provided ReS Leakage Test Data for this determination.

2

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

I

/

JPM TITLE:

Title - RCS Leak Rate Calculation VERSION:

o April 6, 2009 COMPLETION TIME:

30 minutes Appl ication:

Task Number:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

RO/SRO 16010 G2.2.12

[ 1 Performed

[ 1 Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

RO:

3.7 SRO:

4.1

[ 1 Simulated

[ 1 Control Room

[ ] SATISFACTORY Examiner's Signature: _______________ _

3 V-RQ-JP-14905-001S

[ J Unit 1

[ 1 Unit 2

[ ] UNSATISFACTORY OPERATOR'S NAME: ____________ _

EVALUATION DATE:

/

/

JPM TITLE:

Title - RCS Leak Rate Calculation VERSION:

o April 6, 2009 COMPLETION TIME:

30 minutes Application:

Task Number:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

RO/SRO 16010 G2.2.12

[ 1 Performed

[ 1 Simulator

,minutes OVERALL JPM EVALUATION Examiner Comments:

RO:

3.7 SRO:

4.1

[ 1 Simulated

[ 1 Control Room

[ ] SATISFACTORY Examiner's Signature: _______________ _

3 V-RQ-JP-14905-001S

[ 1 Unit 1

[ 1 Unit 2

[ ] UNSATISFACTORY

V-RQ-JP-14905-001S This JPM is based on the latest revision of 14905-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

14905-1 "ReS Leakage Calculation (Inventory Balance)"

2.

PTDB Tab 4.8 for RCDT Tank Levels SIMULATOR SETUP:

Performance of this JPM does not require the simulator.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions and the Assigned Task. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

With Unit 1 in Mode 1, the ability to perform aRCS leakrate using the IPC calculation is not functional. The RCS leak rate surveillance is due. The plant has been stable at 100% power for 322 days. The prerequisites and initial conditions in OSP 14905-1 section 4.0 have been satisfied.

You are the SS, perform a "manual RCS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any)..

Use the provided ReS Leakage Test Data for this determination.

NOTE TO EXAMINER: It is intended to fill out the ReS Leakage Test Dataon Data Sheet 1 and provide to the candidate to eliminate possible transpositional errors. The data is normally collected on Data Sheet 1. The sheet at the back of the JPM is just to keep the data to be provided.

4 v -RQ-JP-14905-00 IS This JPM is based on the latest revision of 14905-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a H©... H are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

14905-1 "RCS Leakage Calculation (Inventory Balance)"

2.

PTDB Tab 4.8 for RCDT Tank Levels SIMULATOR SETUP:

Performance of this JPM does not require the simulator.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions and the Assigned Task. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

With Unit 1 in Mode 1, the ability to perform aRCS leakrate using the IPC calculation is not functional. The RCS leakrate surveillance is due. The plant has been stable at 100% power for 322 days. The prerequisites and initial conditions in OSP 14905-1 section 4.0 have been satisfied.

You are the SS, perform a "manual RCS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any)..

Use the provided ReS Leakage Test Data for this determination.

NOTE TO EXAMINER: It is intended to fill out the RCS Leakage Test Dataon Data Sheet 1 and provide to the candidate to eliminate possible transpositional errors. The data is normally collected on Data Sheet 1. The sheet at the back of the JPM is just to keep the data to be provided.

4

START TIME: ___

STEP 1 SAT DJe:S' UNSAT DJe:S' Records Initial and Final Data

~D

• Initiates section 5.2 (# 1)

~D

• Calculates averages of provided data on Data Sheet 1 CUES:

(# 1)

If asked, the I PC based spreadsheet data is not available.

STEP 2 CRITICAL (.)

SAT D~

UNSAT D~

Calculates and Determines Total Leak Rate Results per Data Sheet 2.

~D

• Calculates the VCT Gross Leakage to be 144.00 gallons per Data Sheet 2.

Calculation: 48.25% -40.75% = 7.5% x 19.2 gallons per % = 144 gallons

~D

• Determines RCS Temperature Correction not required per Data Sheet 2.

V-RQ-JP-1490S-001S NOTE: Since no RCS temperature or pressure change, no RCS specific volume (Vf) change.

~D

• Calculates the PRZR Level Correction to be 18.58 gallons per Data Sheet 2.

Calculation: 57.8% ave - 57.5% ave = 0.3% x 126.40% = 37.92% x 0.49gal per % = 18.58 gallons

~D

• Crud Tank Inleakage should be entered as O. (CUE # 1)

~D

• Calculates the Total Leakage to be 162.58 gallons per Data Sheet 2.

Calculation: 144 gallons + 0 gallons + 18.58 gallons + 0 gallons = 162.58 gallons

~D

• Calculates the Total Leak Rate of 1.27 gpm per Data Sheet 2.

Calculation: 162.58 gallons /128 minutes = 1.27 gpm CUES:

(#1) If asked, "The SS has determined Data Sheet 4 for Crud Tank Inleakage is not to be performed".

5

(

START TIME: ____ _

STEP 1 SAT D~

UNSAT D~

Records Initial and Final Data

~D

• Initiates section 5.2 (# 1)

~D

• Calculates averages of provided data on Data Sheet 1 CUES:

(# 1)

If asked, the I PC based spreadsheet data is not available.

STEP 2 CRITICAL (.)

SAT D~

UNSAT D~

Calculates and Determines Total Leak Rate Results per Data Sheet 2.

~D

• Calculates the VCT Gross Leakage to be 144.00 gallons per Data Sheet 2.

Calculation: 48.25% -40.75% = 7.5% x 19.2 gallons per % = 144 gallons

~D

• Determines RCS Temperature Correction not required per Data Sheet 2.

V-RQ-JP-14905-001S NOTE: Since no RCS temperature or pressure change, no RCS specific volume (Vf) change.

~D

• Calculates the PRZR Level Correction to be 18.58 gallons per Data Sheet 2.

Calculation: 57.8% ave - 57.5% ave = 0.3% x 126.40% = 37.92% x 0.49gal per % = 18.58 gallons

~D

• Crud Tank Inleakage should be entered as O. (CUE # 1)

~D

• Calculates the Total Leakage to be 162.58 gallons per Data Sheet 2.

Calculation: 144 gallons + 0 gallons + 18.58 gallons + 0 gallons = 162.58 gallons

~D

• Calculates the Total Leak Rate of 1.27 gpm per Data Sheet 2.

Calculation: 162.58 gallons /128 minutes = 1.27 gpm CUES:

(#1) If asked, "The SS has determined Data Sheet 4 for Crud Tank Inleakage is not to be performed".

5

(

STEP 3 CRITICAL (.)

SAT D..@I' UNSAT D..@I' V-RQ-JP-14905-001S Performs Data Sheet 3 to Evaluate Leak Rate Results (Identified & Unidentified Leakage)

~D

• Returns VCT makeup and letdown to normal, notifies chemistry to resume sampling. (CUE # 1)

~D

• Determines Q..mu:n PRT inleakage.

NOTE: No PRT level change.

~D

+ Calculates RCDT Inleakage to be 23.42 gallons.

Calculation: 193.64 gallons - 170.22 gallons = 23.42 gallons NOTE: This is from Tab 4.8 of PTDS (RCDT Levels), 54.0 percent - 48.0 percent values.

~D

+ Calculates RCDT Inleakage Rate to be 0.18 gpm.

Calculation: 23.42 gallons /131 minutes = 0.18 gpm

~D

• Determines Primary-to-Secondary Leakage to be 0.08 gpm. (CUE # 2)

~D

• Determines Q..mu:n Pressure Isolation Valve Leakage. (CUE # 3)

~D

+ Calculates Total Identified Leak Rate to be 0.26 gpm.

Calculation: 0 gpm + 0.18 gpm + 0.08 gpm + 0 gpm = 0.26 gpm (a + b + c + d)

~D

+ Determines preliminary leak rate results NOT within acceptance criteria (1.01 gpm).

Calculation: 1.27 Total Leakage - 0.26 Identified = 1.01 Unidentified Leakage

~D

• Determines Q..mu:n Identified Leakage from other sources. (CUE # 4)

~D

+ Determines Final Unidentified Leak Rate resultsNOT within acceptance criteria (1.01 gpm).

CUES:

Calculation: 1.01 gpm - 0 gpm = 1.01 gpm Unidentified Leakage (Step 5.3.5)

(# 1) "The OATC has returned VCT makeup and letdown to normal, Chemistry has been notified to resume sampling".

(# 2) "Chemistry has determined SG Tube Leakage to be 0.08 gpm".

(# 3) "OSP-14450-1 leakge on Data Sheet # 4 has been determined to be 0 gpm"

(# 4) "Attachment 1 has identified Q..mu:n Identified Leakage.

6

(

(

STEP3 CRITICAL (.)

SAT D~

UNSAT D~

V-RQ-JP-14905-001S Performs Data Sheet 3 to Evaluate Leak Rate Results (Identified & Unidentified Leakage)

~D

• Returns VCT makeup and letdown to normal, notifies chemistry to resume sampling. (CUE # 1)

~D

• Determines Q...smn PRT in leakage.

NOTE: No PRT level change.

~D

• Calculates RCDT Inleakage to be 23.42 gallons.

Calculation: 193.64 gallons - 170.22 gallons = 23.42 gallons NOTE: This is from Tab 4.8 of PTDB (RCDT Levels), 54.0 percent - 48.0 percent values.

~D

• Calculates RCDT Inleakage Rate to be 0.18 gpm.

Calculation: 23.42 gallons /131 minutes = 0.18 gpm

~D

• Determines Primary-to-Secondary Leakage to be 0.08 gpm. (CUE # 2)

~D

• Determines Q...smn Pressure Isolation Valve Leakage. (CUE # 3)

• Calculates Total Identified Leak Rate to be 0.26 gpm.

Calculation: 0 gpm + 0.18 gpm + 0.08 gpm + 0 gpm = 0.26 gpm (a + b + c + d)

~D

• Determines preliminary leak rate results NOT within acceptance criteria (1.01 gpm).

Calculation: 1.27 Total Leakage - 0.26 Identified = 1.01 Unidentified Leakage

~D

• Determines Q...smn Identified Leakage from other sources. (CUE # 4)

~D

• Determines Final Unidentified Leak Rate results NOT within acceptance criteria (1.01 gpm).

CUES:

Calculation: 1.01 gpm - 0 gpm = 1.01 gpm Unidentified Leakage (Step 5.3.5)

(# 1) "The OATC has returned VCT makeup and letdown to normal, Chemistry has been notified to resume sampling".

(# 2) "Chemistry has determined SG Tube Leakage to be 0.08 gpm".

(# 3) "OSP-14450-1 leakge on Data Sheet # 4 has been determined to be 0 gpm"

(# 4) "Attachment 1 has identified Q...smn Identified Leakage.

6

(

STEP 4 CRITICAL (.)

SAT O,g UNSAT O,g Identify Technical Specification Actions V-RQ-JP-14905-001S

~n

+ Identifies Tech Spec 3.4.13, "RCS Operational Leakage" limits exceeded - UNIDENTIFIED LEAKAGE.

&0

+ Identifies Condition A Required Action A 1 Completion Time - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. (Cue # 1)

&0

• Identifies Condition B Required Actions B1 and B2 Completion Times - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> respectively CUES:

(# 1) IF needed, once completion time of Condition A identified, state "the crew was unsuccessful reducing RCS Leakage within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit".

STOP TIME: _____

Field Notes 7

STEP4 CRITICAL (.)

SAT O~

UNSAT O~

Identify Technical Specification Actions V-RQ-JP-14905-001S

'&n

• Identifies Tech Spec 3.4.13, "RCS Operational Leakage" limits exceeded - UNIDENTIFIED LEAKAGE.

&0

• Identifies Condition A Required Action A 1 Completion Time - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. (Cue # 1)

&0

• Identifies Condition B Required Actions B1 and B2 Completion Times - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> respectively CUES:

(# 1) IF needed, once completion time of Condition A identified, state "the crew was unsuccessful reducing RCS Leakage within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit".

STOP TIME: ______ _

Field Notes 7

Res LEAKAGE TEST DATA Start/Stop Time Pressurizer Pressure 1 PI-456 1PI-455 1 PI-457 1 PI-458 Pressurizer Temperature 1TI-0453 RCS Temperature 1TI-0412 1TI-0422 1TI-0432 1TI-0442 Pressurizer Level 1 U-0459 1 U-0460 1 U-0461 VCT Level 1 U-0185 PRT Level 1 U-0470 RCDT Level (Data Sheet 5)

Start/Stop Time 1 U-1 003 Crud Tank Leakage Determination (Data Sheet 4)

Primary-to-Seconday Leakage (31120-C)

Pressure Isolation Valve Leakage (14450-1)

Other Identified Leakage Sources (Attachment 1) 8 Initial Reading 14:00 2235.100 2235.600 2232.400 2234.500 653.2 586.400 585.500 585.900 588.400 58.100 57.500 57.800 48.250 78.42 13:57 48.000 V-RQ-JP-14905-001S Final Reading 16:08 2235.000 2235.700 2232.300 2234.600 653.2 586.400 585.400 585.900 588.500 57.800 57.100 57.600 40.750 78.42 16:08 54.000 Olnot performed 0.08 o

o

(

Res LEAKAGE TEST DATA Start/Stop Time Pressurizer Pressure 1 PI-456 1 PI-455 1 PI-457 1 PI-458 Pressurizer Temperature 1TI-0453 RCS Temperature 1TI-0412 1TI-0422 1TI-0432 1TI-0442 Pressurizer Level 1 LI-0459 1 LI-0460 1 LI-0461 VCT Level 1 LI-0185 PRT Level 1 LI-0470 RCDT Level (Data Sheet 5)

Start/Stop Time 1L1-1003 Crud Tank Leakage Determination (Data Sheet 4)

Primary-to-Seconday Leakage (31120-C)

Pressure Isolation Valve Leakage (14450-1)

Other Identified Leakage Sources (Attachment 1) 8 Initial Reading 14:00 2235.100 2235.600 2232.400 2234.500 653.2 586.400 585.500 585.900 588.400 58.100 57.500 57.800 48.250 78.42 13:57 48.000 V-RQ-JP-14905-001S Final Reading 16:08 2235.000 2235.700 2232.300 2234.600 653.2 586.400 585.400 585.900 588.500 57.800 57.100 57.600 40.750 78.42 16:08 54.000 O/not performed 0.08 o

o

SOUTHERN COMPANY Energy to Serve Your World SM PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "c" V-NRC-JP-38001-001 STAY TIME CALCULATION FOR HIGH RADIATION AREA THIS Is A NEW JPM FOR Hl-15 NRC EXAM Revision 0 March 23, 2009 Written By

Thad N. Thompson Date:

3/23/2009 Approved By

Dan Scukanec Date:

3/23/2009 SOUTHERN" COMPANY Energy to Serve Your WorldS" PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "e" V-NRC-JP-38001-001 STAY TIME CALCULATION FOR HIGH RADIATION AREA THIS Is A NEW JPM FOR HL-15 NRC EXAM Revision 0 March 23, 2009 Written By

Thad N. Thompson Date:

3/23/2009 Approved By

Dan Scukanec Date:

3/23/2009

V-RQ-JP-91001-016 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: A locally controlled process must be performed during an AOP.

Assigned Task:

You have two choices for the operator:

1) A room with a general area dose rate reading of 100 mRlhr, or

2) A room where he must stand 6 inches from a valve with a hot spot reading of 1 Rlhr at 1 inch.

The operator has an annual dose history of 4658 mr.

Determine which room would result in the longest stay time for the operator and how long his stay time would be without violating federal limits on TEDE.

2

(

V-RQ-JP-91001-016 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: A locally controlled process must be performed during an AOP.

Assigned Task:

You have two choices for the operator:

1) A room with a general area dose rate reading of 100 mRlhr, or

2) A room where he must stand 6 inches from a valve with a hot spot reading of 1 Rlhr at 1 inch.

The operator has an annual dose history of 4658 mr.

Determine which room would result in the longest stay time for the operator and how long his stay time would be without violating federal limits on TEDE.

2

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

I I

JPM TITLE:

Stay Time Calculation for High Radiation Area REVISION:

o March 23, 2009 COMPLETION TIME:

15 minutes Application:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

SRO ONLY G2.3.12

[ 1 Performed

[ 1 Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

RO: 3.2 SRO: 3.7

[ 1 Simulated

[ 1 Control Room

[ ] SATISFACTORY Examiner's Signature: ______________ _

3 V-NRC-JP-38001-001

[ 1 Unit 1

[ 1 Unit 2

[ ] UNSATISFACTORY

(

OPERATOR'S NAME: ____________ _

EVALUATION DATE:

JPM TITLE:

Stay Time Calculation for High Radiation Area REVISION:

o March 23, 2009 COMPLETION TIME:

15 minutes Application:

KJA Number:

Evaluation Method Evaluation Location Performance Time:

SRO ONLY G2.3.12

[ 1 Performed

[ 1 Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

RO: 3.2 SRO: 3.7

[ 1 Simulated

[ 1 Control Room

[ ] SATISFACTORY Examiner's Signature: _______________ _

3 V-NRC-JP-38001-001

[ 1 Unit 1

[ 1 Unit 2

[ ] UNSATISFACTORY

V-NRC-JP-38001-001 This JPM is based on the latest rev of NMP-HP-001. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

SIMULATOR SETUP:

None DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITiONS:

ASSIGNED TASK:

A locally controlled process must be performed during an AOP. You have two choices for the operator:

1) A room with a general area dose rate reading of 100 mRem I hr, or

2) A room where he must stand 6 inches from a valve with a hot spot reading of 1 Rem I hr at 1 inch.

The operator has an annual dose history of 4658 mr.

Determine which room would result in the longest stay time for the operator and how long his stay time would be without violating federal limits on TEDE.

STARTTIME: ______

STEP 1 CRITICAL ( * )

SAT O~

UNSAT O~

Determine dose rate at 6 inches from hot spot

'&0

• Dose Rate = 1 Rem/hr x 1000mRem 1 1Rem x (1/6)2 = 27.8 mRem 1 hr (+/-. 0.1) 4

(

V-NRC-JP-38001-001 This JPM is based on the latest rev of NMP-HP-001. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

SIMULATOR SETUP:

None DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

A locally controlled process must be performed during an AOP. You have two choices for the operator:

1) A room with a general area dose rate reading of 100 mRem I hr, or

2) A room where he must stand 6 inches from a valve with a hot spot reading of 1 Rem I hr at 1 inch.

The operator has an annual dose history of 4658 mr.

Determine which room would result in the longest stay time for the operator and how long his stay time would be without violating federal limits on TEDE.

START TIME: ______ _

STEP 1 CRITICAL (.)

SAT D~

UNSAT D~

Determine dose rate at 6 inches from hot spot

'&0

• Dose Rate = 1 Rem/hr x 1000mRem 1 1 Rem x (1/6)2 = 27.8 mRem 1 hr ( :!:. 0.1) 4

STEP 2 CRITICAL ( * )

SAT O,g UNSAT O,g Determine maximum stay time V-NRC-JP-38001-001

'&0

• Stay time for room 1 = (5000 mRem - 4658 mRem) / (100 mRem / hr) = 3.42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />

'&0

• Stay time for room 2 = (5000 mRem - 4658 mRem) / (27.8 mRem / hr) = 12.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (.:!:. 0.1)

'&0

• Maximum stay time = 12.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> STOP TIME: _____

Field Notes 5

STEP 2 CRITICAL ( * )

SAT D~

UNSAT D~

Determine maximum stay time V -N RC-J P-38001-001

~D

• Stay time for room 1 = (5000 mRem - 4658 mRem) / (100 mRem / hr) = 3.42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />

~D

• Stay time for room 2 = (5000 mRem - 4658 mRem) / (27.8 mRem / hr) = 12.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (.:!:. 0.1)

~D

• Maximum stay time = 12.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> STOP TIME: _____

Field Notes 5

Written By SOUTHERN COMPANY Energy to Serve Your World"M PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "d" V-RQ-JP-91001-016 CLASSIFY AN EMERGENCY EVENT AND FILL OUT NOTIFICATION FORM FOR COLD INITIATING CONDITIONS THIS Is A NEW JPM FOR Hl*15 NRC EXAM Revision 0 March 6, 2009

Thad N. Thompson Date:

3/06/2009 Approved By : Dan Scu kanec Date:

4/20/2009 Written By SOUTHERN..

\\

COMPANY Energy to Serve Your World""

PLANT VOGTLE CONTROL ROOM OPERA TOR JOB PERFORMANCE MEASURE Admin JPM "d" V-RQ-JP-91001*016 CLASSIFY AN EMERGENCY EVENT AND FILL OUT NOTIFICATION FORM FOR COLD INITIATING CONDITIONS THIS Is A NEW JPM FOR HL*15 NRC EXAM Revision 0 March 6, 2009

Thad N. Thompson Date:

3/06/2009 Approved By

Dan Scu kanec Date:

4/20/2009

V-RQ-JP-91001-016 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: Unit 1 is in Mode 5 for fueled mid-loop operatons per UOP-12008-C, "Mid-Loop Operations", when the following occurs.

Assigned Task:

- Containment sump levels are rising unexpectedly for unknown reasons.

- Reactor vessel level has been - 58% on RVUS Full Range for the last 45 minutes.

- Containment Equipment Hatch closure has not been established.

- 1 RE-12444C has risen 2.3 E-6 micro Cilcc to 1.6 E-1 micro Ci/cc in the last 45 minutes.

- - Wind direction is from 69 degrees at a speed of 5.8 mph

- Stability class - 0, with no precipitation

- PAGS at the site boundary is < 1.0 REM TEDE and < 5.0 REM Thyroid CDE You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress and PARS if applicable, considering past events, and their impact on the current plant conditions" and take appropriate actions for notification of state and local authorities.

2

(

V-RQ-JP-91001-016 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

Unit 1 is in Mode 5 for fueled mid-loop operatons per UOP-12008-C, "Mid-Loop Operations", when the following occurs.

Assigned Task:

- Containment sump levels are rising unexpectedly for unknown reasons.

- Reactor vessel level has been - 58% on RVLlS Full Range for the last 45 minutes.

- Containment Equipment Hatch closure has not been established.

- 1 RE-12444C has risen 2.3 E-6 micro Cilcc to 1.6 E-1 micro Cilcc in the last 45 minutes.

- - Wind direction is from 69 degrees at a speed of 5.8 mph

- Stability class - D, with no precipitation

- PAGS at the site boundary is < 1.0 REM TEDE and < 5.0 REM Thyroid CDE You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress and PARS if applicable, considering past events, and their impact on the current plant conditions" and take appropriate actions for notification of state and local authorities.

2

V-RQ-JP-91001-016 OPERATOR'S NAME: ____________ _

EVALUATION DATE:

I JPM TITLE:

REVISION:

o March 6, 2009 COMPLETION TIME:

30 minutes (15 minutes to classify, 15 minutes to fill out notification form)

Application:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

SRO ONLY G2.4.38

[ J Performed

[ J Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

RO: 2.2 SRO: 4.0

[ 1 Simulated

[ 1 Control Room

[ ] SATISFACTORY Examiner's Signature: _______________ _

3

[ 1 Unit 1

[ 1 Unit 2

[ ] UNSATISFACTORY V-RQ-JP-91001-016 OPERATOR'S NAME: ____________ _

EVALUATION DATE:

/

/

JPM TITLE:

REVISION:

o March 6, 2009 COMPLETION TIME:

30 minutes (15 minutes to classify, 15 minutes to fill out notification form)

Application:

KIA Number:

Evaluation Method Evaluation Location Performance Time:

SRO ONLY G2.4.38

[ 1 Performed

[ 1 Simulator minutes OVERALL JPM EVALUATION Examiner Comments:

RO: 2.2 SRO: 4.0

[ 1 Simulated

[ 1 Control Room

[ ] SATISFACTORY Examiner's Signature: _______________ _

3

[ 1 Unit 1

[ 1 Unit 2

[ ] UNSATISFACTORY

V-RQ-JP-91001-016 This JPM is based on the latest rev of 91001-C and 91002-C and NMP-EP-109. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

2.

3.

4.

None 91 001-C, Emergency Classification and Implementing Instructions 91002-C, Checklist 2, Emergency Notifications Form 91002-C, Figure 5 "Cold Initiating Condition Matrix (Modes 5, 6, and Oefueled Only)

NMP-EP-109, Protective Action Recommendations DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

Unit 1 is in Mode 5 for fueled mid-loop operatons per UOP-12008-C, "Mid-Loop Operations", when the following occurs.

- Containment sump levels are rising unexpectedly for unknown reasons.

- Reactor vessel level has been - 58% on RVLlS Full Range for the last 45 minutes.

- Containment Equipment Hatch closure has not been established.

- 1 RE-12444C has risen 2.3 E-6 micro Cilcc to 1.6 E-1 micro Ci/cc in the last 45 minutes.

- Wind direction is from 69 degrees at a speed of 5.8 mph

- Stability class - 0, with no precipitation

- PAGS at the site boundary is < 1.0 REM TEOE and < 5.0 REM Thyroid COE You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress and PARS if applicable, considering past events, and their impact on the current plant conditions" and take appropriate actions for notification of state and local authorities.

4 V-RQ-JP-91001-016 This JPM is based on the latest rev of 91001-C and 91002-C and NMP-EP-109. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©... " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

2.

3.

4.

None 91001-C, Emergency Classification and Implementing Instructions 91002-C, Checklist 2, Emergency Notifications Form 91002-C, Figure 5 "Cold Initiating Condition Matrix (Modes 5, 6, and Oefueled Only)

NMP-EP-109, Protective Action Recommendations DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

Unit 1 is in Mode 5 for fueled mid-loop operatons per UOP-12008-C, "Mid-Loop Operations", when the following occurs.

- Containment sump levels are rising unexpectedly for unknown reasons.

- Reactor vessel level has been - 58% on RVLlS Full Range for the last 45 minutes.

- Containment Equipment Hatch closure has not been established.

- 1 RE-12444C has risen 2.3 E-6 micro Cilcc to 1.6 E-1 micro Cilcc in the last 45 minutes.

- Wind direction is from 69 degrees at a speed of 5.8 mph

- Stability class - 0, with no precipitation

- PAGS at the site boundary is < 1.0 REM TEOE and < 5.0 REM Thyroid COE You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress and PARS if applicable, considering past events, and their impact on the current plant conditions" and take appropriate actions for notification of state and local authorities.

4

START TIME (Classification): ____ _

STEP 1 CRITICAL (+)

SAT D~

UNSAT D~

Classify the event

'&0

• Plant conditions evaluated V-RQ-JP-91001-016

'&0

+ Emergency event classified as a General Emergency (Loss of 3 barriers) within 15 minutes.

STOP TIME (Classification): ____ _

START TIME (Notification Form) ____ (NOTE: Should be same as STOP TIME above) 5 START TIME (Classification): ____ _

STEP 1 CRITICAL (.)

SAT O~

UNSAT O~

Classify the event

&0

• Plant conditions evaluated V-RQ-JP-91001-016

&0

+ Emergency event classified as a General Emergency (Loss of 3 barriers) within 15 minutes.

STOP TIME (Classification): ____ _

START TIME (Notification Form) ____ (NOTE: Should be same as STOP TIME above) 5

STEP 2 CRITICAL (.)

SAT D~

UNSAT D~

Fill out notification form. (NOTE 1)

V-RQ-JP-91 001-016 AD

• Line 1 block A for this is a drill checked, Message # left blank for ENN Communicator AD

• Line 2 block A for INITIAL checked, Notification: Time and Date and Authentication left blank.

AD

• Line 3 Vogtle 1 is already filled in, Confirmation Phone # left blank.

AD

• Line 4 block D for GENERAL EMERGENCY checked and event based on EAL # CG1.

AD

• Line 4 Event description "Loss of RPV Inventory Affecting Fuel Clad Integrity with Containment Challenged With Irradiated Fuel In The RPV. Modes 5 and 6 Only.

AD

• Line 5 block 8 checked to EVACUATE 0 - 2 mile radius and downwind to 5 miles.

ZONES affected should be listed as A, 85, C5, D5, and SRS to 2 miles (These are the PAR 2 recommendations)

AD

• Line 5 block D checked to Advise Remainder of EPZ to monitor Local Radio / TV Stations / TARS for additional information and consider the use of KI ) potassium iodide) in accordance with State plans and policy.

AD

• Line 6 block 8 checked for EMERGENCY RELEASE "is occurring".

AD

• Line 7 block C checked for RELEASE SIGNIFICANCE "above normal operating limits".

AD

• Line 8 for EVENT PROGNOSIS, candidate checks the block he feels is appropriate.

AD

• Line 9 METEOROLOGICAL DATA filled in according to turnover.

AD

• Line 1 0 block A checked for DECLARATION with proper time and date filled in.

AD

• Line 11 block 1 checked for AFFECTED UNIT(S) - Unit 1.

AD

• Line 12 block 1 check and appropriate power and shutdown time, etc. filled in.

AD

• Line 13 REMARKS filled in, something to effect of Loss of Reactor Vessel Level with inability to close Containment Hatch.

AD

• Line 14 through Line 16 NOT REQUIRED ON AN INITIAL NOTIFICATION.

AD

• Line 17 Approved by HL-14 candidate signature and time / date filled in within 15 minutes. (2)

AD

• Line 17 Notified by left blank for the ENN Communicator.

NOTE:

(1)

Evaluator will have markups of expectations for notification form attached with JPM with proper dates, etc. filled in at time of exam.

(2)

When candidate bring forward notification form, this will stop his 15 minute notification clock.

STOP TIME: (Notification Form) ______ _

6

(

V-RQ-JP-91 001-016 STEP 2 CRITICAL (.)

SAT D~

UNSAT D~

Fill out notification form. (NOTE 1)

~D

• Line 1 block A for this is a drill checked, Message # left blank for ENN Communicator

~D

• Line 2 block A for INITIAL checked, Notification: Time and Date and Authentication left blank.

~D

• Line 3 Vogtle 1 is already filled in, Confirmation Phone # left blank.

~D

• Line 4 block D for GENERAL EMERGENCY checked and event based on EAL # CG1.

~D

• Line 4 Event description "Loss of RPV Inventory Affecting Fuel Clad Integrity with Containment Challenged With Irradiated Fuel In The RPV. Modes 5 and 6 Only.

~D

• Line 5 block 8 checked to EVACUATE 0 - 2 mile radius and downwind to 5 miles.

ZONES affected should be listed as A, 85, C5, D5, and SRS to 2 miles (These are the PAR 2 recommendations)

~D

• Line 5 block D checked to Advise Remainder of EPZ to monitor Local Radio / TV Stations / TARS for

~D

~D

~D

~D

~D

~D

~D

~D

~D

~D

~D NOTE:

additional information and consider the use of KI ) potassium iodide) in accordance with State plans and policy.

• Line 6 block 8 checked for EMERGENCY RELEASE "is occurring".

• Line 7 block C checked for RELEASE SIGNIFICANCE "above normal operating limits".

• Line 8 for EVENT PROGNOSIS, candidate checks the block he feels is appropriate.

• Line 9 METEOROLOGICAL DATA filled in according to turnover.

• Line 10 block A checked for DECLARATION with proper time and date filled in.

• Line 11 block 1 checked for AFFECTED UNIT(S) - Unit 1.

• Line 12 block 1 check and appropriate power and shutdown time, etc. filled in.

• Line 13 REMARKS filled in, something to effect of Loss of Reactor Vessel Level with inability to close Containment Hatch.

• Line 14 through Line 16 NOT REQUIRED ON AN INITIAL NOTIFICATION.

• Line 17 Approved by HL-14 candidate signature and time / date filled in within 15 minutes. (2)

• Line 17 Notified by left blank for the ENN Communicator.

(1)

Evaluator will have markups of expectations for notification form attached with JPM with proper dates, etc. filled in at time of exam.

(2)

When candidate bring forward notification form, this will stop his 15 minute notification clock.

STOP TIME: (Notification Form) ______ _

6

V-RQ-JP-91001-016 Field Notes 7

V-RQ-JP-91001-016 Field Notes

(

7