ML093280445

Initial Exam 2009-301 Final Administrative JPMs

ML093280445
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: ML093280445 (90)

Text

ES-301, Rev. 9 Facility: Vogtle Nuclear Plant Examination Level: SRO Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Administrative Topics Outline PI Nil l.

Form ES-301-1 Type Code*

R,M R,D,P R,N R,N R,N Date of Examination: June 1-5, 2009 Operating Test Number: 2009-301 Describe activity to be performed

Title:

Boration Calculation

==

Description:==

Manually calculate boric acid required for reactor trip with 3 rods stuck at different heights. Students are required to determine 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

==

Description:==

A Train "A" Safety Related component will be tagged out when a 120V AC 1E 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 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 LCD 3.4.13 condition A required actions.

KiA: G 2.2.12 (3.7/4.1)

Title:

Emergency Exposure Permit Approvals

==

Description:==

Students will be provided with 3 emergency exposure permits. They will be required to review and either approve or deny approval of each permit.

KiA: G2.3.4 (3.7)

Title:

Classify Emergency

==

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 (S 1; randomly selected)

ES-301, Rev. 9 Facility: Vogtle Nuclear Plant Examination Level: SRO Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Administrative Topics Outline PI Nil l.

Form ES-301-1 Type Code*

R,M R,D,P R,N R,N R,N Date of Examination: June 1-5, 2009 Operating Test Number: 2009-301 Describe activity to be performed

Title:

Boration Calculation

==

Description:==

Manually calculate boric acid required for reactor trip with 3 rods stuck at different heights. Students are required to determine 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

==

Description:==

A Train "A" Safety Related component will be tagged out when a 120V AC 1E 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 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 LCD 3.4.13 condition A required actions.

KiA: G 2.2.12 (3.7/4.1)

Title:

Emergency Exposure Permit Approvals

==

Description:==

Students will be provided with 3 emergency exposure permits. They will be required to review and either approve or deny approval of each permit.

KiA: G2.3.4 (3.7)

Title:

Classify Emergency

==

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 (S 1; randomly selected)

Job Performance Measure "A.1.S" Facility: Vogtle Task No: V-LO-TA-37004 Task

Title:

Calculate Boron Addition With 3 Stuck Rods JPM No: V-LO-JP-19001-003 KIA

Reference:

G2.1.25 Examinee:

NRC Examiner:

Facility Evaluator: _____________ _

Date: ________________________ ___

Method of testing:

Simulated Performance Actual Performance Classroom Simulator Plant ______ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

Given the Following Conditions/Events on Unit 1:

Task Standard:

While in Mode 3, the Reactor is manually tripped.

RCS Boron Concentration is 400 ppm.

BAST Boron Concentration is 7300 ppm.

RCS is at 1600 psig and 500 degrees F.

ORPI indicates the following rod positions.

Shutdown Bank "A" Rod 02 at 216 steps.

Shutdown Bank "B" Rod C9 at 18 steps.

Shutdown Bank "0" Rod E13 at 192 steps.

The operating crew is performing step 7 of 19001*C.

Determine that 4506 gallons of boric acid (+ or - 25 gallons) must be added to the RCS.

Required Materials:

Calculator PTDB (Plant Technical Data Book, Tab 2 is required) 19001-C, Step # 7 General

References:

None 1

Job Performance Measure "A.1.S" Facility: Vogtle Task No: V-LO-TA-37004 Task

Title:

Calculate Boron Addition With 3 Stuck Rods JPM No: V-LO-JP-19001-003 KIA

Reference:

G2.1.25 Examinee:

NRC Examiner: ------------------

Facility Evaluator: _____________ _

Date: ________________ _

Method of testing:

Simulated Performance Actual Performance Classroom Simulator Plant _____ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

Given the Following Conditions/Events on Unit 1:

Task Standard:

While in Mode 3, the Reactor is manually tripped.

RCS Boron Concentration is 400 ppm.

BAST Boron Concentration is 7300 ppm.

RCS is at 1600 psig and 500 degrees F.

ORPI indicates the following rod positions.

Shutdown Bank "A" Rod 02 at 216 steps.

Shutdown Bank "B" Rod C9 at 18 steps.

Shutdown Bank "0" Rod E13 at 192 steps.

The operating crew is performing step 7 of 19001*C.

Determine that 4506 gallons of boric acid (+ or - 25 gallons) must be added to the RCS.

Required Materials:

Calculator PTDB (Plant Technical Data Book, Tab 2 is required) 19001-C, Step # 7 General

References:

None 1

Initiating Cue:

Determine the amount of boric acid in gallons that must be added to the RCS for the current plant conditions.

Time Critical Task:

No Validation Time:

8 minutes 2

Initiating Cue:

Determine the amount of boric acid in gallons that must be added to the RCS for the current plant conditions.

Time Critical Task:

No Validation Time:

8 minutes 2

Performance Information Critical steps denoted with an asterisk Step # 7 Check all Rods - FULLY INSERTED.

Standard:

Determines from initial conditions that all rods are NOT fully inserted.

Comment:

• Step # 7 RNO - IF two or more Rods NOT fully inserted, THEN EMERGENCY BORATE 154 ppm for each Rod not fully inserted by initiating 13009, CVCS REACTOR MAKUP CONTROL SYSTEM.

Standard:

Calculation for 3 stuck rods is (154 ppm) X (3 rods) = 462 ppm.

Comment:

• Calculates the required boration using the equation for PTOB tab 2.3.

Yba = Vrcs X Ln ({Cb-C1nt)/{Cb-Ct1n)

Yba Yrcs =

Cb Cint

• DB Cfin :: --

Standard:

Comment:

VOlUMe of Boric Acid required in gallons VolUMe of ReS water = 613'6 GAL Concentration of BAST Initial concentration of RCS Boron Addition Final concentration of ReS : Cint + D8 61346 x In [(7300 - 400) + (7300 - 862)] = 4251 gallons 3

Performance Information Critical steps denoted with an asterisk Step # 7 Check all Rods - FULLY INSERTED.

Standard:

Determines from initial conditions that all rods are NOT fully inserted.

Comment:

• Step # 7 RNO - IF two or more Rods NOT fully inserted, THEN EMERGENCY BORATE 154 ppm for each Rod not fully inserted by initiating 13009, CVCS REACTOR MAKUP CONTROL SYSTEM.

Standard:

Calculation for 3 stuck rods is (154 ppm) X (3 rods) = 462 ppm.

Comment:

• Calculates the required boration using the equation for PTOB tab 2.3.

Yba = Vrcs X Ln ({Cb-C1nt)/{Cb-Ct1n)

Yba Yrcs =

Cb Cint

• DB Cfin :: --

Standard:

Comment:

VOlUMe of Boric Acid required in gallons VolUMe of ReS water = 613'6 GAL Concentration of BAST Initial concentration of RCS Boron Addition Final concentration of ReS : Cint + D8 61346 x In [(7300 - 400) + (7300 - 862)] = 4251 gallons 3

• Applies correction factor of 1.06 from Tab 2.1 per note at bottom of Tab 2.3 NOTE: For conditions other than normal operating temperature and pressure, multiply gallons by correction factor from tab 2.1.

Standard:

Comment:

4251 gallons x 1.06 = 4506 gallons of boric acid

(+ or - 25 gallons is acceptance criteria)

Terminating cue:

Student returns initiating cue sheet 4

• Applies correction factor of 1.06 from Tab 2.1 per note at bottom of Tab 2.3 NOTE: For conditions other than normal operating temperature and pressure, multiply gallons by correction factor from tab 2.1.

Standard:

Comment:

4251 gallons x 1.06 = 4506 gallons of boric acid

(+ or - 25 gallons is acceptance criteria)

Terminating cue:

Student returns initiating cue sheet 4

Verification of Completion Job Performance Measure No. V-LO-JP-19001-003 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: ______________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _______________ _

5 Verification of Completion Job Performance Measure No. V-LO-JP-19001-003 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: ____________________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date:

5

Initial Conditions:

Given the Following Conditions/Events on Unit 1:

Initiating Cue:

While in Mode 3, the Reactor is manually tripped.

RCS Boron Concentration is 400 ppm.

BAST Boron Concentration is 7300 ppm.

RCS is at 1600 psig and 500 degrees F.

ORPI indicates the following rod positions.

Shutdown Bank "A" Rod 02 at 216 steps.

Shutdown Bank "B" Rod C9 at 18 steps.

Shutdown Bank "0" Rod E13 at 192 steps.

The operating crew is performing step 7 of 19001-C.

Determine the amount of boric acid in gallons that must be added to the RCS for the current plant conditions.

6 Initial Conditions:

Given the Following Conditions/Events on Unit 1:

Initiating Cue:

While in Mode 3, the Reactor is manually tripped.

RCS Boron Concentration is 400 ppm.

BAST Boron Concentration is 7300 ppm.

RCS is at 1600 psig and 500 degrees F.

ORPI indicates the following rod positions.

Shutdown Bank "A" Rod 02 at 216 steps.

Shutdown Bank "B" Rod C9 at 18 steps.

Shutdown Bank "0" Rod E13 at 192 steps.

The operating crew is performing step 7 of 19001-C.

Determine the amount of boric acid in gallons that must be added to the RCS for the current plant conditions.

6

Job Performance Measure "A.2.S" Facility: Vogtle Task No: V-LO-TA-63013 Task

Title:

LOSF Evaluation JPM No: V-LO-JP-10008-001 KIA

Reference:

G2.1.1 Examinee:

NRC Examiner:

Facility Evaluator: ________ _

Date:

Method of testing:

Simulated Performance Actual Performance Classroom _____ _

Simulator ______ _

Plant ------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

LCO 3.S.1 Condition B is in effect and has been recorded due to corrective maintenance on OG-1A.

Task Standard:

A loss of 1 BY2B has occurred due to a fault on inverter 1B01112.

1 BY2B has been re-energized via the regulated transformer.

The Unit is in mode 3.

LOSF evaluation completed per 10008-C, and LCO 3.8.1 Conditions F &

G entered.

Required Materials:

1.

2.

10008-C, Recording Limiting Conditions for Operation VEGP Technical Specifications & Bases General

References:

None Initiating Cue:

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

Identify the flowpath utilized on the 1000S-C Figure 5 "LOSF Evaluation Flowchart".

1 Job Performance Measure "A.2.S" Facility: Vogtle Task No: V-LO-TA-63013 Task

Title:

LOSF Evaluation JPM No: V-LO-JP-10008-001 KIA

Reference:

G2.1.1 Examinee:

NRC Examiner: ------------------

Facility Evaluator:

Date: ---------------------------

Method of testing:

Simulated Performance ________ _

Actual Performance _______________ _

Classroom Simulator Plant _________ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

LCO 3.S.1 Condition B is in effect and has been recorded due to corrective maintenance on OG-1A.

Task Standard:

A loss of 1 BY2B has occurred due to a fault on inverter 1B01112.

1 BY2B has been re-energized via the regulated transformer.

The Unit is in mode 3.

LOSF evaluation completed per 10008-C, and LCO 3.8.1 Conditions F &

G entered.

Required Materials:

1.

2.

10008-C, Recording Limiting Conditions for Operation VEGP Technical Specifications & Bases General

References:

None Initiating Cue:

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

Identify the flowpath utilized on the 1000S-C Figure 5 "LOSF Evaluation Flowchart".

1

Time Critical Task:

No Validation Time:

15 minutes 2

Time Critical Task:

No Validation Time:

15 minutes 2

Performance Information Critical steps denoted with an asterisk

• Step:

CUE:

Standard:

Comment:

• Step:

Standard:

Comment:

• Step:

Standard:

Comment:

LOSF EVALUATION FLOW CHART Determines which technical specification LCOs are in effect.

"A Support Shift Supervisor (SSS) will fill out the LCD form".

TS LCD 3.8.7 Condition A (CRITICAL)

TS LCO 3.8.1 Condition B (previously in effect)

TS LCO 3.8.9 Condition B (may be identified as temporarily being entered prior to bus re-energization)

LOSF EVALUATION FLOW CHART Evaluates if required support or supported systems are inoperable on redundant safety related trains.

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

Performs LOSF Evaluation using Section 3.5 of 10008-C LOSF present DG-1A Inoperable for corrective maintenance DG-1 B Inoperable due inoperable sequencer powered by 1 BY2B from the regulated transformer.

On loss of all AC power 1 BY2B will de-energize while supplied by the regulated transformer.

3 Performance Information Critical steps denoted with an asterisk

• Step:

CUE:

Standard:

Comment:

• Step:

Standard:

Comment:

• Step:

Standard:

Comment:

LOSF EVALUATION FLOW CHART Determines which technical specification LCOs are in effect.

"A Support Shift Supervisor (SSS) will fill out the LCD form".

TS LCD 3.8.7 Condition A (CRITICAL)

TS LCO 3.8.1 Condition B (previously in effect)

TS LCO 3.8.9 Condition B (may be identified as temporarily being entered prior to bus re-energization)

LOSF EVALUATION FLOW CHART Evaluates if required support or supported systems are inoperable on redundant safety related trains.

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

Performs LOSF Evaluation using Section 3.5 of 10008-C LOSF present DG-1A Inoperable for corrective maintenance DG-1 B Inoperable due inoperable sequencer powered by 1 BY2B from the regulated transformer.

On loss of all AC power 1 BY2B will de-energize while supplied by the regulated transformer.

3

• Step:

Standard:

Comment:

Step:

Standard:

Comment:

Additional LeO conditions identified from loss of safety function determination.

TS LCO 3.8.1 Condition F TS LCO 3.8.1 Condition G Report to SS that Loss of Safety function exists due to the inverter failure.

N/A Terminating cue:

Student returns initiating cue sheet 4

• Step:

Standard:

Comment:

Step:

Standard:

Comment:

Additional LeO conditions identified from loss of safety function determination.

TS LCO 3.8.1 Condition F TS LCO 3.8.1 Condition G Report to SS that Loss of Safety function exists due to the inverter failure.

N/A Terminating cue:

Student returns initiating cue sheet 4

Verification of Completion Job Performance Measure No.: V-LO-JP-10008-001 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: ________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _______________ _

5 Verification of Completion Job Performance Measure No.: V-LO-JP-10008-001 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: _________________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date:

5

Initial Conditions:

LCO 3.S.1 Condition B is in effect and has been recorded due to corrective maintenance on OG-1A.

Initiating Cue:

A loss of 1 BY2B has occurred due to a fault on inverter 1B01112.

1 BY2B has been re-energized via the regulated transformer.

The Unit is in mode 3.

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

Identify the flowpath utilized on the 1000S-C Figure 5 "LOSF Evaluation Flowchart".

6 Initial Conditions:

LCO 3.S.1 Condition B is in effect and has been recorded due to corrective maintenance on OG-1A.

Initiating Cue:

A loss of 1 BY2B has occurred due to a fault on inverter 1B01112.

1 BY2B has been re-energized via the regulated transformer.

The Unit is in mode 3.

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

Identify the flowpath utilized on the 1000S-C Figure 5 "LOSF Evaluation Flowchart".

6

Job Performance Measure "B.S" Facility: Vogtle Task No: V-LO-TA-16010 Task

Title:

Perform RCS Leak Rate Calculation JPM No: V-RQ-JP-14905-001S KJA

Reference:

G2.2.12 Examinee:

NRC Examiner:

Facility Evaluator: ________ _

Date:

Method of testing:

Simulated Performance Actual Performance Classroom ------

Simulator -------

Plant _____ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

With Unit 1 in Mode 1, all computers are unavailable. 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.

Task Standard:

RCS Unidentified Leakage determined to exceed technical specification limits per 14905-1 and LCO 3.4.13 entered.

Required Materials:

1.

2.

3.

4.

14905-1, RCS Leakage Calculation PTOS Tab 4.8 for RCOT Tank Levels PTOS Tab 10.1 for Compressed Water Tables VEGP Technical Specifications & Sases (3.4.13)

Instructions:

Initiating Cue:

Complete 14905-1 steps 4.1 through 5.1.15, Data Sheet 5 and prior to administering this JPM 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 14905-1, RCS Leakage Calculation.

Time Critical Task:

No 1

Job Performance Measure "B.S" Facility: Vogtle Task No: V-LO-TA-16010 Task

Title:

Perform RCS Leak Rate Calculation JPM No: V-RQ-JP-14905-001S KJA

Reference:

G2.2.12 Examinee:

NRC Examiner:

Date:

Facility Evaluator:

Method of testing:

Simulated Performance ________ _

Actual Performance _______________ _

Classroom Simulator Plant Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

With Unit 1 in Mode 1, all computers are unavailable. 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.

Task Standard:

RCS Unidentified Leakage determined to exceed technical specification limits per 14905-1 and LCO 3.4.13 entered.

Required Materials:

1.

2.

3.

4.

14905-1, RCS Leakage Calculation PTOS Tab 4.8 for RCOT Tank Levels PTOS Tab 10.1 for Compressed Water Tables VEGP Technical Specifications & Sases (3.4.13)

Instructions:

Initiating Cue:

Complete 14905-1 steps 4.1 through 5.1.15, Data Sheet 5 and prior to administering this JPM 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 14905-1, RCS Leakage Calculation.

Time Critical Task:

No 1

Validation Time:

30 minutes 2

Validation Time:

30 minutes 2

Performance Information Critical steps denoted with an asterisk

• 5.2.1 Standard:

Comment:

• 5.2.2 Standard:

Comment:

5.2.3 Standard

Comment:

Record the required initial data on Data Sheet 1 (use computer points, if available, where listed) and calculate the average values.

Calculates Initial averages of data on Data Sheet 1 PRZR Pressure:

RCS Temperature:

PRZR Level:

2234.4 586.55 57.8 Vt:

0.02259 (NOT CRITICAL)

After at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for a normal test or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for a retest, record the required final data on Data Sheet 1 (use the same indications as used in Step 5.2.1) and calculate the average values.

Calculates Final averages of data on Data Sheet 1 PRZR Pressure:

RCS Temperature:

PRZR Level:

Vt:

2234.4 586.55 57.5 0.02259 (NOT CRITICAL)

Calculate total RCS leak rate per Data Sheet 2.

N/A 3

Performance Information Critical steps denoted with an asterisk

• 5.2.1 Standard:

Comment:

• 5.2.2 Standard:

Comment:

5.2.3 Standard

Comment:

Record the required initial data on Data Sheet 1 (use computer points, if available, where listed) and calculate the average values.

Calculates Initial averages of data on Data Sheet 1 PRZR Pressure:

RCS Temperature:

PRZR Level:

2234.4 586.55 57.8 Vt:

0.02259 (NOT CRITICAL)

After at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for a normal test or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for a retest, record the required final data on Data Sheet 1 (use the same indications as used in Step 5.2.1) and calculate the average values.

Calculates Final averages of data on Data Sheet 1 PRZR Pressure:

RCS Temperature:

PRZR Level:

Vt:

2234.4 586.55 57.5 0.02259 (NOT CRITICAL)

Calculate total RCS leak rate per Data Sheet 2.

N/A 3

DATA SHEET 2 RCS LEAKAGE CALCULATION (TOTAL LEAKAGE)

• (1)

VCT Level Change (Gross Leakage)

Initial Level - Final Level = ( )

() ____ % x 19.20 Gal/%

= () ___

Gal Standard:

48.25 - 40.75 = 7.5%

7.5% x 19.2 gallons/ % = +144.00 gallons Comment:

(2)

RCS Temperature Correction

[

1 1 1

1. M Gal-f/

x 1284 -----'-=-

Vf Initial Vf Final f/

1. M

=() ___

Gal Standard:

o gallons (No change RCS temperature)

Comment:

• (3)

Pressurizer Level Correction Initial Level - Final Level = ( ) ___ %

() ____ % x 126.40 gals/% x 0.49

= ( ) ___

Gal Standard:

57.8% - 57.5% = 0.3%

0.3% x 126.40 gals/% = 37.92% x 0.49 = +18.58 gallons Comment:

4 DATA SHEET 2 RCS LEAKAGE CALCULATION (TOTAL LEAKAGE)

• (1)

VCT Level Change (Gross Leakage)

Initial Level - Final Level = ( )

() ____ % x 19.20 Gal/%

= () ___

Gal Standard:

48.25 - 40.75 = 7.5%

7.5% x 19.2 gallons/ % = +144.00 gallons Comment:

(2)

RCS Temperature Correction

[

1 1] #M Gal-f/

x 1284 ----=-=-

Vf Initial Vf Final f/

1. M

=() ___

Gal Standard:

o gallons (No change RCS temperature)

Comment:

• (3)

Pressurizer Level Correction Initial Level - Final Level = ( ) ___ %

() ____ % x 126.40 gals/% x 0.49

= ( ) ___

Gal Standard:

57.8% - 57.5% = 0.3%

0.3% x 126.40 gals/% = 37.92% x 0.49 = +18.58 gallons Comment:

4

(4)

CUE:

Standard:

Comment:

Enter Crud Tank inleakage determination. (Utilize Data Sheet 4)(Enter 0 if not preformed)

Crud Tank Leakage Volume = (-)

Gal If asked, "The SS has determined Data Sheet 4 for Crud Tank In Leakage is not to be performed.

o gallons (Crud tank leakage not performed)

• (5)

Total leakage Calculation (1) + (2) + (3) + (4)

= ()

Gal Standard:

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

• (6)

Total leak Rate Standard:

Comment:

5.2.6 Standard

(Total leakage + Test Duration)

= ( )

GPM 162.58 gallons 1128 minutes = 1.27 gpm 14905-1, RCS Leakage Calculation (Inventory Balance)

Calculate the preliminary identified and unidentified leakage per instructions on Data Sheet 3, Steps (1) and (2).

N/A Comment:

5 (4)

CUE:

Standard:

Comment:

Enter Crud Tank inleakage determination. (Utilize Data Sheet 4)(Enter 0 if not preformed)

Crud Tank Leakage Volume = (-)

Gal If asked, "The SS has determined Data Sheet 4 for Crud Tank In Leakage is not to be performed.

o gallons (Crud tank leakage not performed)

• (5)

Total leakage Calculation (1) + (2) + (3) + (4)

= ()

Gal Standard:

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

• (6)

Total leak Rate Standard:

Comment:

5.2.6 Standard

(Total leakage + Test Duration)

= ( )

GPM 162.58 gallons 1128 minutes = 1.27 gpm 14905-1, RCS Leakage Calculation (Inventory Balance)

Calculate the preliminary identified and unidentified leakage per instructions on Data Sheet 3, Steps (1) and (2).

N/A Comment:

5

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(1)

Preliminary Identified Leakage

• (a)

PRT Inleakage Standard:

Comment:

Use PTDS, Table 4.7.2, to determine volume change from level change on Data Sheet 1 Final Level - Initial Level

= ( )

GAL Volume + Test Duration

= ( )

GPM 78.42 - 78.42 = 0%

0% = 0 gallons o gallons / 128 minutes = 0 gpm

• (b)

RCDT Inleakage Standard:

Comment:

Use PTDS, Tab 4.8 to determine volume change from level change on Data Sheet 1 Final Level - Initial Level

= ____ GAL Volume + Level Check Duration

= ____ GPM From PTDS tab 4.8:

54.0% = 193.64 gallons 48.0% = 170.22 gallons Calculation:

193.64 - 170.22 = 23.42 gallons 23.42 gallons /131 minutes = 0.18 gpm 6

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(1)

Preliminary Identified Leakage

• (a)

PRT Inleakage Standard:

Comment:

Use PTDS, Table 4.7.2, to determine volume change from level change on Data Sheet 1 Final Level - Initial Level

= ( )

GAL Volume + Test Duration

= ( )

GPM 78.42 - 78.42 = 0%

0% = 0 gallons o gallons / 128 minutes = 0 gpm

• (b)

RCDT Inleakage Standard:

Comment:

Use PTDS, Tab 4.8 to determine volume change from level change on Data Sheet 1 Final Level - Initial Level

= ____ GAL Volume + Level Check Duration

= ____ GPM From PTDS tab 4.8:

54.0% = 193.64 gallons 48.0% = 170.22 gallons Calculation:

193.64 - 170.22 = 23.42 gallons 23.42 gallons /131 minutes = 0.18 gpm 6

(c)

CUE:

Standard:

Comment:

CUE:

Standard:

Comment:

• (e)

Standard:

Comment:

Primary-to-Secondary Leakage Determine leakage using 31120-C, "Chemistry Steam Generator Tube Leakage Actions".

____ GPM "Chemistry has determined SG Tube Leakage to be 0.08 gpm" 0.08 GPM (d)

Pressure Isolation Valve Leakage Determine pressure isolation valve leakage using 14450-1, "RCS Pressure Isolation Valve Inservice Leak Test", Data Sheet 4 (Sum Measured Leak Rates to obtain total PIV Leak Rate using only Measured Leak Rates determined at a Test Pressure approximately equal to the present RCS pressure).

____ GPM "OSP-14450-1/eakage on Data Sheet # 4 has been determined to be 0 gpm" o gpm Total Identified Leak Rate (a) + (b) + (c) + (d)

= ___

GPM 0+ 0.18 + 0.08 + 0 = 0.26 gpm 7

(c)

CUE:

Standard:

Comment:

CUE:

Standard:

Comment:

• (e)

Standard:

Comment:

Primary-to-Secondary Leakage Determine leakage using 31120-C, "Chemistry Steam Generator Tube Leakage Actions".

____ GPM "Chemistry has determined SG Tube Leakage to be 0.08 gpm" 0.08 GPM (d)

Pressure Isolation Valve Leakage Determine pressure isolation valve leakage using 14450-1, "RCS Pressure Isolation Valve Inservice Leak Test", Data Sheet 4 (Sum Measured Leak Rates to obtain total PIV Leak Rate using only Measured Leak Rates determined at a Test Pressure approximately equal to the present RCS pressure).

____ GPM "OSP-14450-1/eakage on Data Sheet # 4 has been determined to be 0 gpm" o gpm Total Identified Leak Rate (a) + (b) + (c) + (d)

= ___

GPM 0+ 0.18 + 0.08 + 0 = 0.26 gpm 7

• (2)

Standard:

Comment:

• 5.2.7 Standard:

Comment:

Preliminary Unidentified Leakage Total Leak Rate - Total Identified Leak Rate

= ____ GPM 1.27 - 0.26 = 1.01 gpm 14905-1, RCS Leakage Calculation (Inventory Balance)

IF calculations do NOT meet Acceptance Criteria (preliminary calculated value of unidentified leakage is greater than 1.0 gpm), THEN Refer To Technical Specification 3.4.13.

Refers to technical specification 3.4.13

• 5.2.8 Determine final Unidentified Leakage value and record on Data Sheet 3, Step (3c).

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(3c)

Final Unidentified Leak Rate Item 2 - Item 3a

= ____ GPM Standard:

1.01 - 0 = 1.01 gpm Comment:

8

• (2)

Standard:

Comment:

• 5.2.7 Standard:

Comment:

Preliminary Unidentified Leakage Total Leak Rate - Total Identified Leak Rate

= ____ GPM 1.27 - 0.26 = 1.01 gpm 14905-1, RCS Leakage Calculation (Inventory Balance)

IF calculations do NOT meet Acceptance Criteria (preliminary calculated value of unidentified leakage is greater than 1.0 gpm), THEN Refer To Technical Specification 3.4.13.

Refers to technical specification 3.4.13

• 5.2.8 Determine final Unidentified Leakage value and record on Data Sheet 3, Step (3c).

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(3c)

Final Unidentified Leak Rate Item 2 - Item 3a

= ____ GPM Standard:

1.01 - 0 = 1.01 gpm Comment:

8

5.2.9 Determine final Identified Leakage value and record on Data Sheet 3, Step (3b).

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(3)

(a)

• (b)

Final Identified and Unidentified Leak Rates List other identified leakage sources as determined by Attachment 1.

1. _________________ = ____ GPM

2. __________________________ = ____ GPM

3. _______________________ = ____ GPM

4. ___________________ = ____ GPM Other Identified Leak Rate = ____ GPM Final Identified Leak Rate Item 1e + Item 3a

= ____ GPM CUE: has identified 0 gpm Identified Leakage.

Standard:

Comment:

5.2.10 Standard:

Comment:

(a)

(b) o gpm 0.26 - 0 = 0.26 gpm Perform Section 5.3 to evaluate leak rate results.

N/A 9

5.2.9 Determine final Identified Leakage value and record on Data Sheet 3, Step (3b).

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(3)

(a)

• (b)

Final Identified and Unidentified Leak Rates List other identified leakage sources as determined by Attachment 1.

1. _________________________________ = _______ GPM

2. _________________________________ = _______ GPM

3. _________________________________ = _______ GPM

4. _________________________________ = _______ GPM Other Identified Leak Rate = ______ GPM Final Identified Leak Rate Item 1e + Item 3a

= _____ GPM CUE: has identified 0 gpm Identified Leakage.

Standard:

Comment:

5.2.10 Standard:

Comment:

(a)

(b) o gpm 0.26 - 0 = 0.26 gpm Perform Section 5.3 to evaluate leak rate results.

N/A 9

5.3.1 Compare and evaluate leak rate results with leak rate trends and take the following actions as required:

NOTES The following steps are not required to be performed in Modes 3 and 4 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation.

The actions of Attachment 1 may be used at anytime to help find leakages if desired by operations management.

5.3.2 Check that IDENTIFIED LEAKAGE is less than or equal to 10 gpm.

Standard:

< 10 gpm Comment:

5.3.3 Check that primary to secondary LEAKAGE is less than 150 gpd through any one SG by establishing an IPC trend on one of the following available continuous process radiation monitors:

a.

b.

Standard:

Comment:

1RE-810 (GAS ROC) __

gpd OR 1RE-724 (N16 ROC) __

,gpd Determines these reading not available from initial conditions given 10 5.3.1 Compare and evaluate leak rate results with leak rate trends and take the following actions as required:

NOTES The following steps are not required to be performed in Modes 3 and 4 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation.

The actions of Attachment 1 may be used at anytime to help find leakages if desired by operations management.

5.3.2 Check that IDENTIFIED LEAKAGE is less than or equal to 10 gpm.

Standard:

< 10 gpm Comment:

5.3.3 Check that primary to secondary LEAKAGE is less than 150 gpd through any one SG by establishing an IPC trend on one of the following available continuous process radiation monitors:

a.

b.

Standard:

Comment:

1RE-810 (GAS ROC) __

,gpd OR 1RE-724 (N16 ROC) __

,gpd Determines these reading not available from initial conditions given 10

5.3.4 CUE:

Standard:

Comment:

5.3.5 Standard

Comment:

IF neither radiation monitor is available, direct Chemistry to determine primary to secondary LEAKAGE by pulling radiochemical grab samples in accordance with EPRI guidelines by initiating 31120-C "Chemistry Steam Generator Tube Leak Actions.

"Primary to secondary leakage is unchanged from the previous values given."

0.08 gpm Check that UNIDENTIFIED LEAKAGE is less than or equal to 1 gpm.

1.01 gpm 5.3.6 Compare the initial and final leak rate parameters to those in Precautions and Limitations 3.5. Ensure validity checks are done to allow data to be used in the RCS Unidentified Leak Rate Data Analysis. If the leak rate is performed outside of the bounds of the validity checks, the result should not be used as input to the baseline statistical data set for the historical mean leakrate. The leak rate test should be repeated or deferred until the plant is in a more stable condition.

Document reasons for invalid result in the comments section below. Initiate a condition report to capture the failure of the validity check.

VALIDITY CHECK o SAT o UNSAT CUE:

If asked, "Another operator will perform this step".

Standard:

N/A Comment:

11 5.3.4 CUE:

Standard:

Comment:

5.3.5 Standard

Comment:

IF neither radiation monitor is available, direct Chemistry to determine primary to secondary LEAKAGE by pulling radiochemical grab samples in accordance with EPRI guidelines by initiating 31120-C "Chemistry Steam Generator Tube Leak Actions.

"Primary to secondary leakage is unchanged from the previous values given."

0.08 gpm Check that UNIDENTIFIED LEAKAGE is less than or equal to 1 gpm.

1.01 gpm 5.3.6 Compare the initial and final leak rate parameters to those in Precautions and Limitations 3.5. Ensure validity checks are done to allow data to be used in the RCS Unidentified Leak Rate Data Analysis. If the leak rate is performed outside of the bounds of the validity checks, the result should not be used as input to the baseline statistical data set for the historical mean leakrate. The leak rate test should be repeated or deferred until the plant is in a more stable condition.

Document reasons for invalid result in the comments section below. Initiate a condition report to capture the failure of the validity check.

VALIDITY CHECK o SAT o UNSAT CUE:

If asked, "Another operator will perform this step".

Standard:

N/A Comment:

11

5.3.7 CUE:

Standard:

Comment:

5.3.8 CUE:

Standard:

Comment:

IF the leak rate data meets the validity check, enter data in the Unit 1 URL Data Analysis Spreadsheet:

If asked, "Another operator will perform this step".

N/A Evaluate the Action Levels for Unidentified RCS Leakage If asked, "Leak Rate Coordinator will evaluate at a later time".

N/A 6.0 ACCEPTANCE CRITERIA

• 6.1 Final UNIDENTIFIED LEAKAGE is less than or equal to 1 gpm.

• 6.2 Final IDENTIFIED LEAKAGE is less than or equal to 10 gpm.

• 6.3 Primary to secondary LEAKAGE is less than 150 gallons per day through anyone SG.

6.4 Action levels for Tier One, Two, or Three have not been exceeded for Unidentified RCS Leakage.

Standard:

Comment:

6.1 6.2 6.3 6.4 NOT MET MET MET incomplete (NOT CRITICAL) 12 5.3.7 CUE:

Standard:

Comment:

5.3.8 CUE:

Standard:

Comment:

IF the leak rate data meets the validity check, enter data in the Unit 1 URL Data Analysis Spreadsheet:

If asked, "Another operator will perform this step".

N/A Evaluate the Action Levels for Unidentified RCS Leakage If asked, "Leak Rate Coordinator will evaluate at a later time".

N/A 6.0 ACCEPTANCE CRITERIA

• 6.1 Final UNIDENTIFIED LEAKAGE is less than or equal to 1 gpm.

• 6.2 Final IDENTIFIED LEAKAGE is less than or equal to 10 gpm.

• 6.3 Primary to secondary LEAKAGE is less than 150 gallons per day through anyone SG.

6.4 Action levels for Tier One, Two, or Three have not been exceeded for Unidentified RCS Leakage.

Standard:

Comment:

6.1 6.2 6.3 6.4 NOT MET MET MET incomplete (NOT CRITICAL) 12

7.0 7.1 7.2 7.2.1 7.3

7.4 Standard

Comment:

EVALUATION AND REVIEW TEST PURPOSE o Surveillance o Maintenance Retest o Other (explain) ______________ _

Results obtained through performance of this procedure meet ACCEPTANCE CRITERIA of Steps 6.1, 6.2, and 6.3 (Tech Spec Requirement).

o YESD NO If NO was checked, initiate 18004-C, "Reactor Coolant System Leakage" OR 18009-C, "Steam Generator Tube Leak" as appropriate, notify SS and refer to Technical Specification LCO 3.4.13.

Results obtained through performance of this procedure meet ACCEPTANCE CRITERIA of Step 6.4 (NMP-OS-009 Requirement) o YESD NO Comments (include any abnormal conditions and corrective actions taken): __________________________________ __

7.1 7.2 7.3 Surveillance box checked No box is checked N/A (not performed) 13 7.0 7.1 7.2 7.2.1 7.3

7.4 Standard

Comment:

EVALUATION AND REVIEW TEST PURPOSE o Surveillance o Maintenance Retest o Other (explain) ______________ _

Results obtained through performance of this procedure meet ACCEPTANCE CRITERIA of Steps 6.1, 6.2, and 6.3 (Tech Spec Requirement).

o YESD NO If NO was checked, initiate 18004-C, "Reactor Coolant System Leakage" OR 18009-C, "Steam Generator Tube Leak" as appropriate, notify SS and refer to Technical Specification LCO 3.4.13.

Results obtained through performance of this procedure meet ACCEPTANCE CRITERIA of Step 6.4 (NMP-OS-009 Requirement) o YESD NO Comments (include any abnormal conditions and corrective actions taken): ____________________________________________ __

7.1 7.2 7.3 Surveillance box checked No box is checked N/A (not performed) 13

7.5 Check below for the attached documents.

IPC printout PC Spread sheet Data Sheets 1 J 2 Data Sheet 3 Data Sheet 4 Data Sheet 5 URL Data Analysis Spread Sheet Test Completed and SS Notified:

Supervisory Review:

Standard:

Data Sheets 1 J 2 Data Sheet 3 Data Sheet 4 Data Sheet 5 URL Data Analysis Spread Sheet 0

0 0

0 0

0 0

0 Signature Signature o CHECKED o CHECKED o

o CHECKED o

o CHECKED Test Completed and SS Notified block is signed and dated.

Comment:

14 Date ITime Date I Time 7.5 Check below for the attached documents.

IPC printout PC Spread sheet Data Sheets 1 J 2 Data Sheet 3 Data Sheet 4 Data Sheet 5 URL Data Analysis Spread Sheet Test Completed and SS Notified:

Supervisory Review:

Standard:

Data Sheets 1 J 2 Data Sheet 3 Data Sheet 4 Data Sheet 5 URL Data Analysis Spread Sheet 0

0 0

0 0

0 0

0 Signature Signature o CHECKED o CHECKED o

o CHECKED o

o CHECKED Test Completed and SS Notified block is signed and dated.

Comment:

14 Date ITime Date I Time

• Step CUE:

Standard:

Comment:

Refers to Technical Specification 3.4.13 IF needed, once completion time of Condition A identified, state "the crew was unsuccessful at 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".

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

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)

Condition 8 Required Actions 81 and 82 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 Reports SS that 14905-1 is UNSAT due to UNIDENTIFIED LEAKAGE exceeding acceptance requirements.

Standard:

N/A Comment:

Terminating cue:

Student returns initiating cue sheet 15

• Step CUE:

Standard:

Comment:

Refers to Technical Specification 3.4.13 IF needed, once completion time of Condition A identified, state "the crew was unsuccessful at 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".

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

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)

Condition 8 Required Actions 81 and 82 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 Reports SS that 14905-1 is UNSAT due to UNIDENTIFIED LEAKAGE exceeding acceptance requirements.

Standard:

N/A Comment:

Terminating cue:

Student returns initiating cue sheet 15

Verification of Completion Job Performance Measure No: V-RQ-JP-14905-001S Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: ------------------------------------------------------

Response: ____________________________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date: __________________ _

16 Verification of Completion Job Performance Measure No: V-RQ-JP-14905-001S Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: ______________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _____________ _

16

Res LEAKAGE TEST DATA Initial Reading Final Reading Start/Stop Time 14:00 16:08 Pressurizer Pressure 1 PI-456 2235.100 2235.000 1PI-455 2235.600 2235.700 1PI-457 2232.400 2232.300 1PI-458 2234.500 2234.600 Pressurizer Temperature 1TI-0453 653.2 653.2 RCS Temperature 1TI-0412 586.400 586.400 1TI-0422 585.500 585.400 1TI-0432 585.900 585.900 1TI-0442 588.400 588.500 Pressurizer Level 1 U-0459 58.100 57.800 1 LI-0460 57.500 57.100 1 U-0461 VCT Level 57.800 57.600 1U-0185 48.250 40.750 PRT Level 1 LI-0470 78.42 78.42 RCDT Level (Data Sheet 5)

Start/Stop Time 13:57 16:08 1 U-1003 48.000 54.000 Crud Tank Leakage Determination (Data Sheet 4)

O/not performed Primary-to-Secondary Leakage (31120-C) 0.08 GPM Pressure Isolation Valve Leakage (14450-1 )

o GPM Other Identified Leakage Sources (Attachment 1) o GPM 17 Res LEAKAGE TEST DATA Initial Reading Final Reading Start/Stop Time 14:00 16:08 Pressurizer Pressure 1 PI-456 2235.100 2235.000 1PI-455 2235.600 2235.700 1PI-457 2232.400 2232.300 1PI-458 2234.500 2234.600 Pressurizer Temperature 1TI-0453 653.2 653.2 RCS Temperature 1TI-0412 586.400 586.400 1TI-0422 585.500 585.400 1TI-0432 585.900 585.900 1TI-0442 588.400 588.500 Pressurizer Level 1 U-0459 58.100 57.800 1 LI-0460 57.500 57.100 1 U-0461 VCT Level 57.800 57.600 1U-0185 48.250 40.750 PRT Level 1 LI-0470 78.42 78.42 RCDT Level (Data Sheet 5)

Start/Stop Time 13:57 16:08 1 U-1003 48.000 54.000 Crud Tank Leakage Determination (Data Sheet 4)

O/not performed Primary-to-Secondary Leakage (31120-C) 0.08 GPM Pressure Isolation Valve Leakage (14450-1 )

o GPM Other Identified Leakage Sources (Attachment 1) o GPM 17

Initial Conditions:

With Unit 1 in Mode 1, all computers are unavailable. 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.

Initiating Cue:

You are the 55, perform a "manual RCS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any).

Use the provided 14905-1, RCS Leakage Calculation.

18 Initial Conditions:

With Unit 1 in Mode 1, all computers are unavailable. 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.

Initiating Cue:

You are the 55, perform a "manual RCS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any).

Use the provided 14905-1, RCS Leakage Calculation.

18

Job Performance Measure "C.S" Facility: Vogtle Task No: N/A Task

Title:

Emergency Director Review and Approval of Emergency Exposure Permits JPM No: V-LO-JP-91301-001 KIA

Reference:

G 2.3.4 Examinee: ___________ _

NRC Examiner:

Facility Evaluator:

Date: -----------------

Method of testing:

Simulated Performance ______ _

Actual Performance ________ _

Classroom Simulator Plant Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

You are the emergency director. A general emergency has been declared. Three emergency exposure permits have been generated for review and approval by the emergency director.

Task Standard:

Emergency exposure permits properly reviewed and approved or disapproved per 91301-C.

Required Materials:

1.

2.

General

References:

None 91301-C, Emergency Exposure Guidelines Emergency exposure permits (3)

Initiating Cue:

Review the emergency exposure permits submitted for your approval.

Time Critical Task:

No Validation Time:

10 minutes 1

Job Performance Measure "C.S" Facility: Vogtle Task No: N/A Task

Title:

Emergency Director Review and Approval of Emergency Exposure Permits JPM No: V-LO-JP-91301-001 KIA

Reference:

G 2.3.4 Examinee: ___________ _

NRC Examiner: _________ _

Facility Evaluator:

Date: ---------------

Method of testing:

Simulated Performance ______ _

Actual Performance ________ __

Classroom ------

Simulator ______ _

Plant ------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

You are the emergency director. A general emergency has been declared. Three emergency exposure permits have been generated for review and approval by the emergency director.

Task Standard:

Emergency exposure permits properly reviewed and approved or disapproved per 91301-C.

Required Materials:

1.

2.

General

References:

None 91301-C, Emergency Exposure Guidelines Emergency exposure permits (3)

Initiating Cue:

Review the emergency exposure permits submitted for your approval.

Time Critical Task:

No Validation Time:

10 minutes 1

Performance Information Critical steps denoted with an asterisk Standard:

Comment:

Standard:

Comment:

Standard:

Comment:

Reviews emergency exposure permit #1 using procedure 91301-C.

Does NOT approve permit #1:

1. It has not been signed by person that will receive the emergency exposure.

Reviews emergency exposure permit #2 using procedure 91301-C.

APPROVES emergency exposure permit #2:

1. Permit is signed by volunteer

2. Dose limit meets 91301-C table 1 requirements for protection of large population.

3. Verbal authorization of Health Physics Supervisor noted by initials of person receiving verbal authorization.

Reviews emergency exposure permit #2 using procedure 91301-C.

Does NOT approve permit #3:

1. Dose limit is incorrect per table 1 requirements (10 REM)

2. Person receiving the emergency exposure initialed the permit instead of signing the permit.

Terminating cue:

Student returns initiating cue sheet 2

Performance Information Critical steps denoted with an asterisk Standard:

Comment:

Standard:

Comment:

Standard:

Comment:

Reviews emergency exposure permit #1 using procedure 91301-C.

Does NOT approve permit #1:

1. It has not been signed by person that will receive the emergency exposure.

Reviews emergency exposure permit #2 using procedure 91301-C.

APPROVES emergency exposure permit #2:

1. Permit is signed by volunteer

2. Dose limit meets 91301-C table 1 requirements for protection of large population.

3. Verbal authorization of Health Physics Supervisor noted by initials of person receiving verbal authorization.

Reviews emergency exposure permit #2 using procedure 91301-C.

Does NOT approve permit #3:

1. Dose limit is incorrect per table 1 requirements (10 REM)

2. Person receiving the emergency exposure initialed the permit instead of signing the permit.

Terminating cue:

Student returns initiating cue sheet 2

Verification of Completion Job Performance Measure No. V-LO-JP-9131 0-001 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: _____________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _____________ _

3 Verification of Completion Job Performance Measure No. V-LO-JP-9131 0-001 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: ___________________________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ____________________ _

3

Prepared by:

Date:

Time:

Task Type:

Task

Description:

DOSE LIMITS:

Name:

SSN:

Signature:

TLD Number HP supervisor block Date Time Prepared by:

Date:

Time:

Task Type:

Task

Description:

DOSE LIMITS:

Name:

SSN:

Signature:

TLD Number HP supervisor block Date Time Prepared by:

Date:

Time:

Task Type:

Task

Description:

DOSE LIMITS:

Name:

SSN:

Signature TLD Number HP supervisor block Date Time John Doe 06-03-2009 1002 Permit #1 Data:

Lifesaving is circled Perform CPR and removed injured person from high radiation area.

28 REM TEDE Jackie Smith 123-45-6789 Left Blank 50612 Initialed 6-3-2009 1005 John Doe 06-03-2009 1003 Permit #2 Data:

protection of large population is circled Isolate failed open steam generator ARV 1 PV-3000 to stop emergency release.

29 REM TEDE Jane Doe 111-22-3333 Signed 78393 Initialed 6-3-2009 1010 John Doe 06-03-2009 1005 Permit #3 Data:

Protecting Valuable Property is circled Restore cooling water to containment coolers to help lower containment pressure.

12 REM TEDE (acknowledgement limit is N/A)

John Doe Jr.

811-11-1111 Initialed 71347 Initialed 6-3-2009 1015 4

Prepared by:

Date:

Time:

Task Type:

Task

Description:

DOSE LIMITS:

Name:

SSN:

Signature:

TLD Number HP supervisor block Date Time Prepared by:

Date:

Time:

Task Type:

Task

Description:

DOSE LIMITS:

Name:

SSN:

Signature:

TLD Number HP supervisor block Date Time Prepared by:

Date:

Time:

Task Type:

Task

Description:

DOSE LIMITS:

Name:

SSN:

Signature TLD Number HP supervisor block Date Time John Doe 06-03-2009 1002 Permit #1 Data:

Lifesaving is circled Perform CPR and removed injured person from high radiation area.

28 REM TEDE Jackie Smith 123-45-6789 Left Blank 50612 Initialed 6-3-2009 1005 John Doe 06-03-2009 1003 Permit #2 Data:

protection of large population is circled Isolate failed open steam generator ARV 1 PV-3000 to stop emergency release.

29 REM TEDE Jane Doe 111-22-3333 Signed 78393 Initialed 6-3-2009 1010 John Doe 06-03-2009 1005 Permit #3 Data:

Protecting Valuable Property is circled Restore cooling water to containment coolers to help lower containment pressure.

12 REM TEDE (acknowledgement limit is N/A)

John Doe Jr.

811-11-1111 Initialed 71347 Initialed 6-3-2009 1015 4

Initial Conditions:

You are the emergency director. A general emergency has been declared. Three emergency exposure permits have been generated for review and approval by the emergency director.

Initiating Cue:

Review the emergency exposure permits submitted for your approval.

5 Initial Conditions:

You are the emergency director. A general emergency has been declared. Three emergency exposure permits have been generated for review and approval by the emergency director.

Initiating Cue:

Review the emergency exposure permits submitted for your approval.

5

Job Performance Measure "D.S" Facility: Vogtle Task No: V-LO-TA-40001 Task

Title:

Classify an Emergency Event and Complete the ENN form JPM No: V-RQ-JP-91001-016 KIA

Reference:

G2.4.38 Examinee:

NRC Examiner: -------------------

Facility Evaluator:

Date: __________________________ __

Method of testing:

Simulated Performance Actual Performance Classroom ------

Simulator ------------

Plant __________ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

Unit 1 is in Mode 5 for fueled mid-loop operations when the following occurs:

- Containment sump levels are rising unexpectedly for unknown reasons.

- Reactor vessel level has lowered from 62% to 58% on RVLlS Full Range over the last 45 minutes and is still lowering.

- Containment Equipment Hatch closure has not been established.

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

- Wind direction is from 069 degrees at a speed of 5.8 mph.

- Stability class - 0, with no precipitation.

- PAGs at the site boundary are < 1.0 REM TEDE and < 5.0 REM Thyroid CDE.

- Unit 1 was shutdown at 1200 on 05-08-09 1

Job Performance Measure "D.S" Facility: Vogtle Task No: V-LO-TA-40001 Task

Title:

Classify an Emergency Event and Complete the ENN form JPM No: V-RQ-JP-91001-016 KIA

Reference:

G2.4.38 Examinee:

NRC Examiner:

Facility Evaluator: _______________ _

Date: _________________ __

Method of testing:

Simulated Performance Actual Performance Classroom ------

Simulator -----------

Plant _________ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

Unit 1 is in Mode 5 for fueled mid-loop operations when the following occurs:

- Containment sump levels are rising unexpectedly for unknown reasons.

- Reactor vessel level has lowered from 62% to 58% on RVLlS Full Range over the last 45 minutes and is still lowering.

- Containment Equipment Hatch closure has not been established.

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

- Wind direction is from 069 degrees at a speed of 5.8 mph.

- Stability class - 0, with no precipitation.

- PAGs at the site boundary are < 1.0 REM TEDE and < 5.0 REM Thyroid CDE.

- Unit 1 was shutdown at 1200 on 05-08-09 1

Task Standard:

Event classified within 15 minutes per 91001-C and ENN form properly completed per 91002-C, checklist 2.

Required Materials:

1.

2.

General

References:

None ED packet NMP-EP-109, Protective Action Recommendations Initiating Cue:

Using Data Sheet 1 of 91001*C, determine the HIGHEST emergency classification level and PARs if applicable. Take appropriate actions for notification of state and local authorities.

Time Critical Task:

YES Validation Time:

15 minutes to classify, 15 minutes to complete ENN form 2

Task Standard:

Event classified within 15 minutes per 91001-C and ENN form properly completed per 91002-C, checklist 2.

Required Materials:

1.

2.

General

References:

None ED packet NMP-EP-109, Protective Action Recommendations Initiating Cue:

Using Data Sheet 1 of 91001*C, determine the HIGHEST emergency classification level and PARs if applicable. Take appropriate actions for notification of state and local authorities.

Time Critical Task:

YES Validation Time:

15 minutes to classify, 15 minutes to complete ENN form 2

Performance Information Critical steps denoted with an asterisk 91001-C DATA SHEET 1 CLASSIFICATION DETERMINATION START TIME CRITICAL, ___

1.

Standard:

Comment:

2.

Standard:

Considering events which are in progress, past events, and their impact on current plant conditions, evaluate the status of the fission product barriers.

Step initialed by the ED.

IF the affected Unit is in Modes 1, 2, 3, or 4, go to step 4 to evaluate the Barriers.

Step marked N/A Comment:

3.

Standard:

Comment:

6.

Standard:

Comment:

IF the affected Unit is in Modes 5, 6, or Defueled, go to step 6.

Step is initialed by the ED Use Figure 5 to evaluate and determine the Cold Initiating Condition based on events which are in progress, considering past events, and their impact on current plant conditions. As needed, refer to the Threshold Value page associated with the Initiating Condition chosen to ensure that the Threshold is met.

Step is initialed by the ED, EAL # CG1 is filled in 3

Performance Information Critical steps denoted with an asterisk 91001-C DATA SHEET 1 CLASSIFICATION DETERMINATION START TIME CRITICAL ___

1.

Standard:

Comment:

2.

Standard:

Considering events which are in progress, past events, and their impact on current plant conditions, evaluate the status of the fission product barriers.

Step initialed by the ED.

IF the affected Unit is in Modes 1, 2, 3, or 4, go to step 4 to evaluate the Barriers.

Step marked N/A Comment:

3.

Standard:

Comment:

6.

Standard:

Comment:

IF the affected Unit is in Modes 5, 6, or Defueled, go to step 6.

Step is initialed by the ED Use Figure 5 to evaluate and determine the Cold Initiating Condition based on events which are in progress, considering past events, and their impact on current plant conditions. As needed, refer to the Threshold Value page associated with the Initiating Condition chosen to ensure that the Threshold is met.

Step is initialed by the ED, EAL # CG1 is filled in 3

• 7.

Standard:

Comment:

8.

Standard:

Comment:

9.

Check ~ One:

o o o o

General Emergency is checked Notification Of Unusual Event Alert Site Area Emergency General Emergency Maintain a log of the incident. (This may be delegated).

N/A Assume the position of Emergency Director.

STOP TIME CRITICAL. ___ _

Standard:

Comment:

Step is signed, with date and time completed 91002*C CHECKLIST 2 EMERGENCY DIRECTOR INSTRUCTIONS FOR ENN FORM IMPLEMENTATION

1.

Direct the ENN Communicator to activate the Emergency Recall System and then establish communications and complete roll call in accordance with Checklist 4.

CUE:

Activate the Emergency Recall System and then establish communications and complete roll call in accordance with Checklist 4.

Standard:

Step is initialed by the ED 4

• 7.

Standard:

Comment:

8.

Standard:

Comment:

9.

Check ~ One:

o o o o

General Emergency is checked Notification Of Unusual Event Alert Site Area Emergency General Emergency Maintain a log of the incident. (This may be delegated).

N/A Assume the position of Emergency Director.

STOP TIME CRITICAL, ___

Standard:

Comment:

Step is signed, with date and time completed 91002*C CHECKLIST 2 EMERGENCY DIRECTOR INSTRUCTIONS FOR ENN FORM IMPLEMENTATION

1.

Direct the ENN Communicator to activate the Emergency Recall System and then establish communications and complete roll call in accordance with Checklist 4.

CUE:

Activate the Emergency Recall System and then establish communications and complete roll call in accordance with Checklist 4.

Standard:

Step is initialed by the ED 4

Comment:

2.

Standard:

Comment:

Complete or direct the completion of the Emergency Notification Form Checklist 2, except portions of items 1 (message #), items 2 (Notification time, date and authentication #), items 3 (Confirmation Phone #) and items 17 (notified by) which will be completed by the communicator.

Items a through i completed by the ED.

Each step is initialed by the ED.

5 Comment:

2.

Standard:

Comment:

Complete or direct the completion of the Emergency Notification Form Checklist 2, except portions of items 1 (message #), items 2 (Notification time, date and authentication #), items 3 (Confirmation Phone #) and items 17 (notified by) which will be completed by the communicator.

Items a through i completed by the ED.

Each step is initialed by the ED.

5

ENN FORM

• Line 1

• Block A is checked Line 2 - Block A is checked.

• Line 3

• Vogtle 1 is already filled in

• Line 4

• Block 0 is checked

• Line 4 EAL # CG1 is filled in

• 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.

• Line 5

• Block B is checked

• Line 5 EVACUATE Zones A, C5, 05, E5 and SRS to 2 miles

• Line 5

• Block 0 checked.

• Line 6

• Block B is checked.

Line 7 - Block 0 is checked.

Line 8 - Stable is checked.

Line 9 - :

• Wind Direction 069 filled in

• Wind Speed 5.8 mph filled in Precipitation - None Stability Class - Block 0 is checked

• Line 10* Block A checked and time and date filled in from 91001*C Data Sheet 1.

• Line 11

• Block 1 is checked Line 12 - Block A is checked and appropriate power and shutdown time are filled in.

Line 13 - None is filled in Line 14 through Line 16 - BLANK Line 17 - Signature and time / date filled in within 15 minutes of classification declaration block on data sheet 1 of 91001-C.

6 ENN FORM

• Line 1

• Block A is checked Line 2 - Block A is checked.

• Line 3

• Vogtle 1 is already filled in

• Line 4

• Block 0 is checked

• Line 4 EAL # CG1 is filled in

• 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.

• Line 5

• Block B is checked

• Line 5 EVACUATE Zones A, C5, 05, E5 and SRS to 2 miles

• Line 5

• Block 0 checked.

• Line 6

• Block B is checked.

Line 7 - Block 0 is checked.

Line 8 - Stable is checked.

Line 9 - :

• Wind Direction 069 filled in

• Wind Speed 5.8 mph filled in Precipitation - None Stability Class - Block 0 is checked

• Line 10* Block A checked and time and date filled in from 91001*C Data Sheet 1.

• Line 11

• Block 1 is checked Line 12 - Block A is checked and appropriate power and shutdown time are filled in.

Line 13 - None is filled in Line 14 through Line 16 - BLANK Line 17 - Signature and time / date filled in within 15 minutes of classification declaration block on data sheet 1 of 91001-C.

6

Standard:

As noted above for each line Comment:

Terminating cue:

Student returns initiating cue sheet 7

Standard:

As noted above for each line Comment:

Terminating cue:

Student returns initiating cue sheet 7

Verification of Completion Job Performance Measure No. V-RQ-JP-91001-016 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: ________________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date:

8 Verification of Completion Job Performance Measure No. V-RQ-JP-91001-016 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: ___________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________ _

8

\\

Initial Conditions:

Initiating Cue:

THIS IS A TIME CRITICAL JPM Unit 1 is in Mode 5 for fueled mid-loop operations when the following occurs:

- Containment sump levels are rising unexpectedly for unknown reasons.

- Reactor vessel level has lowered from 62% to 58% on RVLlS Full Range over the last 45 minutes and is still lowering.

- Containment Equipment Hatch closure has not been established.

- 1RE-12444C has risen from 2.3 E-6 f,JCi/cc to 1.6 E-1 f,JCi/cc over the last 45 minutes.

- Wind direction is from 069 degrees at a speed of 5.8 mph.

- Stability class - D, with no precipitation.

- PAGs at the site boundary are < 1.0 REM TEDE and < 5.0 REM Thyroid CDE.

- Unit 1 was shutdown at 1200 on 05-08-09 Using Data Sheet 1 of 91001-C, determine the HIGHEST emergency classification level and PARs if applicable. Take appropriate actions for notification of state and local authorities.

9

\\

Initial Conditions:

Initiating Cue:

THIS IS A TIME CRITICAL JPM Unit 1 is in Mode 5 for fueled mid-loop operations when the following occurs:

- Containment sump levels are rising unexpectedly for unknown reasons.

- Reactor vessel level has lowered from 62% to 58% on RVLlS Full Range over the last 45 minutes and is still lowering.

- Containment Equipment Hatch closure has not been established.

- 1RE-12444C has risen from 2.3 E-6 f,JCi/cc to 1.6 E-1 f,JCi/cc over the last 45 minutes.

- Wind direction is from 069 degrees at a speed of 5.8 mph.

- Stability class - D, with no precipitation.

- PAGs at the site boundary are < 1.0 REM TEDE and < 5.0 REM Thyroid CDE.

- Unit 1 was shutdown at 1200 on 05-08-09 Using Data Sheet 1 of 91001-C, determine the HIGHEST emergency classification level and PARs if applicable. Take appropriate actions for notification of state and local authorities.

9

ES*301, Rev. 9 Administrative Topics Outline P/IIfIIL Form ES*301*1 Facility: Vogtle Nuclear Plant Date of Examination: June 1-5, 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.

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 (.s 1; randomly selected)

ES*301, Rev. 9 Administrative Topics Outline P/IIfIIL Form ES*301*1 Facility: Vogtle Nuclear Plant Date of Examination: June 1-5, 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.

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 2.1.7J4.4t

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 (.s 1; randomly selected)

Job Performance Measure "A.1.R" Facility: Vogtle Task No: V-LO-TA-37004 Task

Title:

Calculate Boron Addition With 3 Stuck Rods JPM No: V-LO-JP-19001-003 KIA

Reference:

G2.1.25 Examinee:

NRC Examiner: -------------

Facility Evaluator:

Date: ____________________ ___

Method of testing:

Simulated Performance Actual Performance Classroom Simulator Plant _____ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

Given the Following Conditions/Events on Unit 1:

Task Standard:

While in Mode 3, the Reactor is manually tripped.

RCS Boron Concentration is 400 ppm.

BAST Boron Concentration is 7300 ppm.

RCS is at 1600 psig and 500 degrees F.

ORPI indicates the following rod positions.

Shutdown Bank "A" Rod 02 at 216 steps.

Shutdown Bank "B" Rod C9 at 18 steps.

Shutdown Bank "0" Rod E13 at 192 steps.

The operating crew is performing step 7 of 19001*C.

Determine that 4506 gallons of boric acid (+ or - 25 gallons) must be added to the RCS.

Required Materials:

Calculator PTDB (Plant Technical Data Book, Tab 2 is required) 19001-C, Step # 7 General

References:

None 1

Job Performance Measure "A.1.R" Facility: Vogtle Task No: V-LO-TA-37004 Task

Title:

Calculate Boron Addition With 3 Stuck Rods JPM No: V-LO-JP-19001-003 KIA

Reference:

G2.1.25 Examinee:

NRC Examiner: ________ _

Facility Evaluator: ________ _

Date: ____________ _

Method of testing:

Simulated Performance Actual Performance Classroom _____ _

Simulator _____ _

Plant _____ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

Given the Following Conditions/Events on Unit 1:

Task Standard:

While in Mode 3, the Reactor is manually tripped.

RCS Boron Concentration is 400 ppm.

BAST Boron Concentration is 7300 ppm.

RCS is at 1600 psig and 500 degrees F.

ORPI indicates the following rod positions.

Shutdown Bank "A" Rod 02 at 216 steps.

Shutdown Bank "B" Rod C9 at 18 steps.

Shutdown Bank "0" Rod E13 at 192 steps.

The operating crew is performing step 7 of 19001*C.

Determine that 4506 gallons of boric acid (+ or - 25 gallons) must be added to the RCS.

Required Materials:

Calculator PTDB (Plant Technical Data Book, Tab 2 is required) 19001-C, Step # 7 General

References:

None 1

Initiating Cue:

Determine the amount of boric acid in gallons that must be added to the RCS for the current plant conditions.

Time Critical Task:

No Validation Time:

8 minutes 2

Initiating Cue:

Determine the amount of boric acid in gallons that must be added to the RCS for the current plant conditions.

Time Critical Task:

No Validation Time:

8 minutes 2

Performance Information Critical steps denoted with an asterisk 19001*C, Reactor Trip Response Step # 7 Check all Rods - FULLY INSERTED.

Standard:

Determines from initial conditions that all rods are NOT fully inserted.

Comment:

• Step # 7 RNO

• IF two or more Rods NOT fully inserted, THEN EMERGENCY BORATE 154 ppm for each Rod not fully inserted by initiating 13009, CVCS REACTOR MAKUP CONTROL SYSTEM.

Standard:

Calculation for 3 stuck rods is (154 ppm) X (3 rods) = 462 ppm.

Comment:

• Calculates the required boration using the equation for PTOB tab 2.3.

Yba Vba Yrcs Cb Cint DB Cfin Standard:

Comment:

3 Vrcs X Ln {(Cb-C1nt)/{Cb-Ct1n)

VOlUMe of Boric Acid required in gallons VolUMe of ReS water:

613~6 GAL Concentration of BAST Initial concentration of RCS Boron Addition Final concentration of ReS : Cint + 08 61346 x In [(7300 - 400) + (7300 - 862)] = 4251 gallons 3

Performance Information Critical steps denoted with an asterisk 19001*C, Reactor Trip Response Step # 7 Check all Rods - FULLY INSERTED.

Standard:

Determines from initial conditions that all rods are NOT fully inserted.

Comment:

• Step # 7 RNO

• IF two or more Rods NOT fully inserted, THEN EMERGENCY BORATE 154 ppm for each Rod not fully inserted by initiating 13009, CVCS REACTOR MAKUP CONTROL SYSTEM.

Standard:

Calculation for 3 stuck rods is (154 ppm) X (3 rods) = 462 ppm.

Comment:

• Calculates the required boration using the equation for PTOB tab 2.3.

Yba Vba Yrcs Cb Cint DB Cfin Standard:

Comment:

3 Vrcs X Ln {(Cb-C1nt)/{Cb-Ct1n)

VOlUMe of Boric Acid required in gallons VolUMe of ReS water:

613~6 GAL Concentration of BAST Initial concentration of RCS Boron Addition Final concentration of ReS : Cint + 08 61346 x In [(7300 - 400) + (7300 - 862)] = 4251 gallons 3

• Applies correction factor of 1.06 from Tab 2.1 per note at bottom of Tab 2.3 NOTE: For conditions other than normal operating temperature and pressure, multiply gallons by correction factor from tab 2.1.

Standard:

Comment:

4251 gallons x 1.06 = 4506 gallons of boric acid

(+ or - 25 gallons is acceptance criteria)

Terminating cue:

Student returns initiating cue sheet 4

• Applies correction factor of 1.06 from Tab 2.1 per note at bottom of Tab 2.3 NOTE: For conditions other than normal operating temperature and pressure, multiply gallons by correction factor from tab 2.1.

Standard:

Comment:

4251 gallons x 1.06 = 4506 gallons of boric acid

(+ or - 25 gallons is acceptance criteria)

Terminating cue:

Student returns initiating cue sheet 4

Verification of Completion Job Performance Measure No. V-LO-JP-19001-003 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: _____________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date:

5 Verification of Completion Job Performance Measure No. V-LO-JP-19001-003 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: _________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date:

5

Initial Conditions:

Given the Following Conditions/Events on Unit 1:

Initiating Cue:

While in Mode 3, the Reactor is manually tripped.

RCS Boron Concentration is 400 ppm.

BAST Boron Concentration is 7300 ppm.

RCS is at 1600 psig and 500 degrees F.

DRPI indicates the following rod positions.

Shutdown Bank "A" Rod 02 at 216 steps.

Shutdown Bank "B" Rod C9 at 18 steps.

Shutdown Bank "0" Rod E13 at 192 steps.

The operating crew is performing step 7 of 19001-C.

Determine the amount of boric acid in gallons that must be added to the RCS for the current plant conditions.

6 Initial Conditions:

Given the Following Conditions/Events on Unit 1:

Initiating Cue:

While in Mode 3, the Reactor is manually tripped.

RCS Boron Concentration is 400 ppm.

BAST Boron Concentration is 7300 ppm.

RCS is at 1600 psig and 500 degrees F.

DRPI indicates the following rod positions.

Shutdown Bank "A" Rod 02 at 216 steps.

Shutdown Bank "B" Rod C9 at 18 steps.

Shutdown Bank "0" Rod E13 at 192 steps.

The operating crew is performing step 7 of 19001-C.

Determine the amount of boric acid in gallons that must be added to the RCS for the current plant conditions.

6

Job Performance Measure "A.2.R" Facility: Vogtle Task No: V-LO-TA-37004 Task

Title:

Monitor I Evaluate CSFSTs - Subcriticality JPM No: V-RQ-JP-19200-005 KIA

Reference:

G2.1.7 Examinee:

NRC Examiner: _________ _

Facility Evaluator:

Date: _____________ _

Method of testing:

Simulated Performance Actual Performance Classroom -------

Simulator ______ _

Plant _____ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

A Reactor trip occurred 30 minutes ago.

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

Task Standard:

Properly identifies the status of all CSFSTs, determine that Subcriticality is highest priority and a transition to 19211-C is required.

Required Materials:

19200-C, F-O Critical Safety Function Status Trees Steam Tables Provided table of plant data (attached following student cue sheet)

General

References:

None Initiating Cue:

The SS has directed you to "use 19200-C to evaluate all CSFSTs and identify any required transition".

Time Critical Task:

No Validation Time:

minutes 1

Job Performance Measure "A.2.R" Facility: Vogtle Task No: V-LO-TA-37004 Task

Title:

Monitor I Evaluate CSFSTs - Subcriticality JPM No: V-RQ-JP-19200-005 KIA

Reference:

G2.1.7 Examinee:

NRC Examiner:

Date:

Facility Evaluator:

Method of testing:

Simulated Performance Actual Performance Classroom ____________ _

Simulator ____________ _

Plant _____ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

A Reactor trip occurred 30 minutes ago.

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

Task Standard:

Properly identifies the status of all CSFSTs, determine that Subcriticality is highest priority and a transition to 19211-C is required.

Required Materials:

19200-C, F-O Critical Safety Function Status Trees Steam Tables Provided table of plant data (attached following student cue sheet)

General

References:

None Initiating Cue:

The SS has directed you to "use 19200-C to evaluate all CSFSTs and identify any required transition".

Time Critical Task:

No Validation Time:

minutes 1

Performance Information Critical steps denoted with an asterisk

• Sheet 1 Standard:

Comment:

• Sheet 2 Standard:

Comment:

Evaluates F- 0.1, the Subcriticality Status Tree Power Range greater than 5% - NO Intermediate Range SUR positive - YES Go to 19211-C (ORANGE)

Properly evaluates Subcriticality to be ORANGE status.

Continues with evaluation of the other CSFST status trees.

Evaluates F- 02, the Core Cooling Status Tree Core Exit TCs less than 1200 degrees F - YES RCS Subcooling greater than 24 (38) degrees F - YES CSF Sat (GREEN)

Properly evaluates Core Cooling to be GREEN status (sat)

Continues with evaluation of the other CSFST status trees.

2 Performance Information Critical steps denoted with an asterisk

• Sheet 1 Standard:

Comment:

• Sheet 2 Standard:

Comment:

Evaluates F- 0.1, the Subcriticality Status Tree Power Range greater than 5% - NO Intermediate Range SUR positive - YES Go to 19211-C (ORANGE)

Properly evaluates Subcriticality to be ORANGE status.

Continues with evaluation of the other CSFST status trees.

Evaluates F- 02, the Core Cooling Status Tree Core Exit TCs less than 1200 degrees F - YES RCS Subcooling greater than 24 (38) degrees F - YES CSF Sat (GREEN)

Properly evaluates Core Cooling to be GREEN status (sat)

Continues with evaluation of the other CSFST status trees.

2

• Sheet 3 Standard:

Comment:

• Sheet 4 Standard:

Comment:

Evaluates F- 0.3, the Heat Sink Status Tree Narrow Range level in at least one SG greater than 10% (32%) - NO Total Available Feedwater flow to SGs greater than 570 gpm - YES Pressure in all SGs less than 1240 psig - YES Narrow Range level in all SGs Less than 82% - YES Pressure in all SGs less than 1180 psig - YES Narrow Range level in all SGs greater than 10% (32%) - NO Go to 19235-C (YELLOW)

Properly evaluates Heat Sink to be YELLOW status.

Continues with evaluation of the other CSFST status trees.

Evaluates F- 0.4, the Integrity Status Tree Temperature decreases in all RCS Cold Legs less than 100 degrees F in the last 60 minutes. - NO All RCS Pressure WR Cold Leg temperature points to the right of Limit A -

YES All RCS WE Cold Leg temperatures greater than 265 degrees F - NO Go to 19241-C (ORANGE)

Properly evaluates Integrity to be ORANGE status.

Continues with evaluation of the other CSFST status trees.

3

• Sheet 3 Standard:

Comment:

• Sheet 4 Standard:

Comment:

Evaluates F- 0.3, the Heat Sink Status Tree Narrow Range level in at least one SG greater than 10% (32%) - NO Total Available Feedwater flow to SGs greater than 570 gpm - YES Pressure in all SGs less than 1240 psig - YES Narrow Range level in all SGs Less than 82% - YES Pressure in all SGs less than 1180 psig - YES Narrow Range level in all SGs greater than 10% (32%) - NO Go to 19235-C (YELLOW)

Properly evaluates Heat Sink to be YELLOW status.

Continues with evaluation of the other CSFST status trees.

Evaluates F- 0.4, the Integrity Status Tree Temperature decreases in all RCS Cold Legs less than 100 degrees F in the last 60 minutes. - NO All RCS Pressure WR Cold Leg temperature points to the right of Limit A -

YES All RCS WE Cold Leg temperatures greater than 265 degrees F - NO Go to 19241-C (ORANGE)

Properly evaluates Integrity to be ORANGE status.

Continues with evaluation of the other CSFST status trees.

3

• Sheet 5 Standard:

Comment:

• Sheet 6 Standard:

Comment:

Evaluates F* 0.5, the Containment Status Tree Containment Pressure less than 52 psig - YES Containment Pressure less than 21.5 psig - YES Containment Sump level less than 105 inches - YES Containment Radiation less than 750 mr I hr - YES CSF Sat (GREEN)

Properly evaluates Containment to be GREEN status.

Continues with evaluation of the other CSFST status trees.

Evaluates F* 0.6, the Inventory Status Tree PRZR level less than 92%

• NO At least one RCP running - NO RVLlS indicates upper head greater than 98% full - YES Go to 19261*C (YELLOW)

Properly evaluates Inventory to be YELLOW status.

• Notifies SS of required procedural transition based on CSFST status.

Standard:

Determines F- 0.1 Subcriticality is highest priority CSFST Determines transition to 19211-C is required.

Comment:

4

• Sheet 5 Standard:

Comment:

• Sheet 6 Standard:

Comment:

Evaluates F* 0.5, the Containment Status Tree Containment Pressure less than 52 psig - YES Containment Pressure less than 21.5 psig - YES Containment Sump level less than 105 inches - YES Containment Radiation less than 750 mr I hr - YES CSF Sat (GREEN)

Properly evaluates Containment to be GREEN status.

Continues with evaluation of the other CSFST status trees.

Evaluates F* 0.6, the Inventory Status Tree PRZR level less than 92%

• NO At least one RCP running - NO RVLlS indicates upper head greater than 98% full - YES Go to 19261*C (YELLOW)

Properly evaluates Inventory to be YELLOW status.

• Notifies SS of required procedural transition based on CSFST status.

Standard:

Determines F- 0.1 Subcriticality is highest priority CSFST Determines transition to 19211-C is required.

Comment:

4

Terminating cue:

Student returns initiating cue sheet 5

Terminating cue:

Student returns initiating cue sheet 5

Verification of Completion Job Performance Measure No. V-RQ-JP-19200-005 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: ---------------------------------------------------------------

Response: __________________________________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's Signature and date:

6 Verification of Completion Job Performance Measure No. V-RQ-JP-19200-005 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: _____________________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's Signature and date: _____________________ _

6

Initial Conditions:

A Reactor trip occurred 30 minutes ago.

Initiating Cue:

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

The SS has directed you to "use 19200-C to evaluate all CSFSTs and identify any required transition".

7 Initial Conditions:

A Reactor trip occurred 30 minutes ago.

Initiating Cue:

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

The SS has directed you to "use 19200-C to evaluate all CSFSTs and identify any required transition".

7

Cha"nellLoop Channel/Loop Channel/Loop Channel I Loop Parameter 1

Z 3

4 PRNI 0%

0%

0%

0%

IRSUR

+0.1DPM

+0.13DPM IR NI 3.0x10-4%

3.2x10-4%

SRSUR o DPM o DPM 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 mR I Hr 31 mR/Hr PRZR level 100%

100%

100%

8 Channol>l._

Ctr.nnoJ >1._

ChannoI I Loop CItenneI I Loop p.,.-

2 3

4 PRNI 0%

0%

0%

0%

IR SUR

+0.1 DPM

+0.13DPM IR NI 3.0xl 04%

3.2x10-4%

SR SUR ODPM ODPM Res WR Pressure 1980 psig 2000 psig 1990 psig 2010 psig Core Exit TIC's 329 F Rep status Off Off Off Off RVlIS Full Range 100%

100%

100%

100%

RVlIS 100%

100%

100%

100%

Upper Head SG NR level 0%

0%

0%

0%

AFWflow 205 GPM OGPM 210 GPM 200 GPM SG Pressure 950 pSig 26 pSig 973 psig 987 pslg RCSWR Cold leg Temperature 540F 261 F 538 F 54 1 F CNMT Pressure o psig Opsig o psig o psig CNMT Emergency Sump l evels o inches o inches CNMT Radiation 24mR / Hr 31mR / Hr PRZR level 100%

100%

100%

8

Job Performance Measure "B.R" Facility: Vogtle Task No: V-LO-TA-16010 Task

Title:

Perform RCS Leak Rate Calculation JPM No: V-RQ-JP-14905-001S KIA

Reference:

G2.2.12 Examinee:

NRC Examiner:

Facility Evaluator: ________ _

Date:

Method of testing:

Simulated Performance Actual Performance Classroom ______ _

Simulator -------

Plant _____ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

With Unit 1 in Mode 1, all computers are unavailable. 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.

Task Standard:

RCS Unidentified Leakage determined to exceed technical specification limits per 14905-1.

Required Materials:

1.

2.

3.

4.

14905-1, RCS Leakage Calculation PTDB Tab 4.8 for RCDT Tank Levels PTDB Tab 10.1 for Compressed Water Tables VEGP Technical Specifications & Bases (3.4.13)

Instructions:

Initiating Cue:

Complete 14905-1 steps 4.1 through 5.1.15. Data Sheet 5 and prior to administering this JPM You are the 55, perform a "manual RCS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any).

Use the provided 14905-1, RCS Leakage Calculation.

Time Critical Task:

No 1

Job Performance Measure "B.R" Facility: Vogtle Task No: V-LO-TA-16010 Task

Title:

Perform RCS Leak Rate Calculation JPM No: V-RQ-JP-14905-001S KIA

Reference:

G2.2.12 Examinee:

NRC Examiner:

Date:

Facility Evaluator:

Method of testing:

Simulated Performance Actual Performance Classroom _____ _

Simulator _____ _

Plant -----------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

With Unit 1 in Mode 1, all computers are unavailable. 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.

Task Standard:

RCS Unidentified Leakage determined to exceed technical specification limits per 14905-1.

Required Materials:

1.

2.

3.

4.

14905-1, RCS Leakage Calculation PTDB Tab 4.8 for RCDT Tank Levels PTDB Tab 10.1 for Compressed Water Tables VEGP Technical Specifications & Bases (3.4.13)

Instructions:

Initiating Cue:

Complete 14905-1 steps 4.1 through 5.1.15. Data Sheet 5 and prior to administering this JPM You are the 55, perform a "manual RCS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any).

Use the provided 14905-1, RCS Leakage Calculation.

Time Critical Task:

No 1

Validation Time:

30 minutes 2

Validation Time:

30 minutes 2

Performance Information Critical steps denoted with an asterisk

• 5.2.1 Standard:

Comment:

• 5.2.2 Standard:

Comment:

5.2.3 Standard

Comment:

Record the required initial data on Data Sheet 1 (use computer points, if available, where listed) and calculate the average values.

Calculates Initial averages of data on Data Sheet 1 PRZR Pressure:

RCS Temperature:

PRZR Level:

2234.4 586.55 57.8 Vt:

0.02259 (NOT CRITICAL)

After at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for a normal test or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for a retest, record the required final data on Data Sheet 1 (use the same indications as used in Step 5.2.1) and calculate the average values.

Calculates Final averages of data on Data Sheet 1 PRZR Pressure:

RCS Temperature:

PRZR Level:

Vt:

2234.4 586.55 57.5 0.02259 (NOT CRITICAL)

Calculate total RCS leak rate per Data Sheet 2.

Uses Data Sheet 2 to calculate (following pages show calculations) 3 Performance Information Critical steps denoted with an asterisk

• 5.2.1 Standard:

Comment:

• 5.2.2 Standard:

Comment:

5.2.3 Standard

Comment:

Record the required initial data on Data Sheet 1 (use computer points, if available, where listed) and calculate the average values.

Calculates Initial averages of data on Data Sheet 1 PRZR Pressure:

RCS Temperature:

PRZR Level:

2234.4 586.55 57.8 Vt:

0.02259 (NOT CRITICAL)

After at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for a normal test or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for a retest, record the required final data on Data Sheet 1 (use the same indications as used in Step 5.2.1) and calculate the average values.

Calculates Final averages of data on Data Sheet 1 PRZR Pressure:

RCS Temperature:

PRZR Level:

Vt:

2234.4 586.55 57.5 0.02259 (NOT CRITICAL)

Calculate total RCS leak rate per Data Sheet 2.

Uses Data Sheet 2 to calculate (following pages show calculations) 3

DATA SHEET 2 RCS LEAKAGE CALCULATION (TOTAL LEAKAGE)

• (1)

VCT Level Change (Gross Leakage)

Initial Level - Final Level = ( )

() ____ % x 19.20 Gall%

= () ___

Gal Standard:

48.25 - 40.75 = 7.5%

7.5% x 19.2 gallons/ % = +144.00 gallons Comment:

(2)

RCS Temperature Correction

[

1 1] #M Gal - f/

-x1284---=-=----

Vf Initial V, Final f/

1. M

= () ___

Gal Standard:

o gallons (No change RCS temperature)

Comment:

• (3)

Pressurizer Level Correction Initial Level - Final Level = ( ) ___ %

() ____ % x 126.40 gals/% x 0.49

= ( ) ___

Gal Standard:

57.8% - 57.5% = 0.3%

0.3% x 126.40 gals/% = 37.92% x 0.49 = +18.58 gallons Comment:

4 DATA SHEET 2 RCS LEAKAGE CALCULATION (TOTAL LEAKAGE)

• (1)

VCT Level Change (Gross Leakage)

Initial Level - Final Level = ( )

() ____ % x 19.20 Gall%

= () ___

Gal Standard:

48.25 - 40.75 = 7.5%

7.5% x 19.2 gallons/ % = +144.00 gallons Comment:

(2)

RCS Temperature Correction

[

1 1] #M Gal - f/

-x1284------'---

Vf Initial V, Final f/

1. M

= () ___

Gal Standard:

o gallons (No change RCS temperature)

Comment:

• (3)

Pressurizer Level Correction Initial Level - Final Level = ( ) ___ %

() ____ % x 126.40 gals/% x 0.49

= ( ) ___

Gal Standard:

57.8% - 57.5% = 0.3%

0.3% x 126.40 gals/% = 37.92% x 0.49 = +18.58 gallons Comment:

4

(4)

CUE:

Standard:

Comment:

Enter Crud Tank inleakage determination. (Utilize Data Sheet 4)(Enter 0 if not preformed)

Crud Tank Leakage Volume = (-)

Gal If asked, "The SS has determined Data Sheet 4 for Crud Tank In Leakage is not to be performed.

o gallons (Crud tank leakage not performed)

• (5)

Total Leakage Calculation (1) + (2) + (3) + (4)

= ()

Gal Standard:

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

• (6)

Total Leak Rate Standard:

Comment:

5.2.6 Standard

(Total Leakage + Test Duration) = ( )

GPM 162.58 gallons /128 minutes = 1.27 gpm 14905-1, RCS Leakage Calculation (Inventory Balance)

Calculate the preliminary identified and unidentified leakage per instructions on Data Sheet 3, Steps (1) and (2).

Uses Data Sheet 3 to calculate (following pages show calculations)

Comment:

5 (4)

CUE:

Standard:

Comment:

Enter Crud Tank inleakage determination. (Utilize Data Sheet 4)(Enter 0 if not preformed)

Crud Tank Leakage Volume = (-)

Gal If asked, "The SS has determined Data Sheet 4 for Crud Tank In Leakage is not to be performed.

o gallons (Crud tank leakage not performed)

• (5)

Total Leakage Calculation (1) + (2) + (3) + (4)

= ()

Gal Standard:

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

• (6)

Total Leak Rate Standard:

Comment:

5.2.6 Standard

(Total Leakage + Test Duration) = ( )

GPM 162.58 gallons /128 minutes = 1.27 gpm 14905-1, RCS Leakage Calculation (Inventory Balance)

Calculate the preliminary identified and unidentified leakage per instructions on Data Sheet 3, Steps (1) and (2).

Uses Data Sheet 3 to calculate (following pages show calculations)

Comment:

5

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(1)

Preliminary Identified Leakage

• (a)

PRT Inleakage Standard:

Comment:

• (b)

Standard:

Comment:

Use PTDS, Table 4.7.2, to determine volume change from level change on Data Sheet 1 Final Level - Initial Level

= ( )

GAL Volume + Test Duration

= ( )

GPM 78.42 - 78.42 = 0%

0% = 0 gallons o gallons / 128 minutes = 0 gpm RCDT Inleakage Use PTDS, Tab 4.8 to determine volume change from level change on Data Sheet 1 Final Level - Initial Level

= ____ GAL Volume + Level Check Duration

= ____ GPM From PTDB tab 4.8:

54.0% = 193.64 gallons 48.0% = 170.22 gallons Calculation:

193.64 - 170.22 = 23.42 gallons 23.42 gallons / 131 minutes = 0.18 gpm 6

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(1)

Preliminary Identified Leakage

• (a)

PRT Inleakage Standard:

Comment:

• (b)

Standard:

Comment:

Use PTDS, Table 4.7.2, to determine volume change from level change on Data Sheet 1 Final Level - Initial Level

= ( )

GAL Volume + Test Duration

= ( )

GPM 78.42 - 78.42 = 0%

0% = 0 gallons o gallons / 128 minutes = 0 gpm RCDT Inleakage Use PTDS, Tab 4.8 to determine volume change from level change on Data Sheet 1 Final Level - Initial Level

= ____ GAL Volume + Level Check Duration

= ____ GPM From PTDB tab 4.8:

54.0% = 193.64 gallons 48.0% = 170.22 gallons Calculation:

193.64 - 170.22 = 23.42 gallons 23.42 gallons / 131 minutes = 0.18 gpm 6

• (c)

CUE:

Standard:

Comment:

(d)

CUE:

Standard:

Comment:

• (e)

Standard:

Comment:

Primary-to-Secondary Leakage Determine leakage using 31120-C, "Chemistry Steam Generator Tube Leakage Actions".

____ GPM "Chemistry has determined SG Tube Leakage to be 0.08 gpm" 0.08 GPM Pressure Isolation Valve Leakage Determine pressure isolation valve leakage using 14450-1, "RCS Pressure Isolation Valve Inservice Leak Test", Data Sheet 4 (Sum Measured Leak Rates to obtain total PIV Leak Rate using only Measured Leak Rates determined at a Test Pressure approximately equal to the present RCS pressure).

____ GPM UOSP-14450-1/eakage on Data Sheet # 4 has been determined to be 0 gpm" Ogpm Total Identified Leak Rate (a) + (b) + (c) + (d)

= ___

GPM 0+ 0.18 + 0.08 + 0 = 0.26 gpm 7

• (c)

CUE:

Standard:

Comment:

(d)

CUE:

Standard:

Comment:

• (e)

Standard:

Comment:

Primary-to-Secondary Leakage Determine leakage using 31120-C, "Chemistry Steam Generator Tube Leakage Actions".

____ GPM "Chemistry has determined SG Tube Leakage to be 0.08 gpm" 0.08 GPM Pressure Isolation Valve Leakage Determine pressure isolation valve leakage using 14450-1, "RCS Pressure Isolation Valve Inservice Leak Test", Data Sheet 4 (Sum Measured Leak Rates to obtain total PIV Leak Rate using only Measured Leak Rates determined at a Test Pressure approximately equal to the present RCS pressure).

____ GPM UOSP-14450-1/eakage on Data Sheet # 4 has been determined to be 0 gpm" Ogpm Total Identified Leak Rate (a) + (b) + (c) + (d)

= ___

GPM 0+ 0.18 + 0.08 + 0 = 0.26 gpm 7

• (2)

Standard:

Comment:

• 5.2.7 Standard:

Comment:

Preliminary Unidentified Leakage Total Leak Rate* Total Identified Leak Rate

= ____ GPM 1.27 - 0.26 = 1.01 gpm 14905-1, RCS Leakage Calculation (Inventory Balance)

IF calculations do NOT meet Acceptance Criteria (preliminary calculated value of unidentified leakage is greater than 1.0 gpm), THEN Refer To Technical Specification 3.4.13.

Refers to technical specification 3.4.13

• 5.2.8 Determine final Unidentified Leakage value and record on Data Sheet 3, Step (3c).

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(3c)

Final Unidentified Leak Rate Item 2 - Item 3a

= ____ GPM Standard:

1.01 - 0 = 1.01 gpm Comment:

8

• (2)

Standard:

Comment:

• 5.2.7 Standard:

Comment:

Preliminary Unidentified Leakage Total Leak Rate* Total Identified Leak Rate

= ____ GPM 1.27 - 0.26 = 1.01 gpm 14905-1, RCS Leakage Calculation (Inventory Balance)

IF calculations do NOT meet Acceptance Criteria (preliminary calculated value of unidentified leakage is greater than 1.0 gpm), THEN Refer To Technical Specification 3.4.13.

Refers to technical specification 3.4.13

• 5.2.8 Determine final Unidentified Leakage value and record on Data Sheet 3, Step (3c).

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(3c)

Final Unidentified Leak Rate Item 2 - Item 3a

= ____ GPM Standard:

1.01 - 0 = 1.01 gpm Comment:

8

5.2.9 Determine final Identified Leakage value and record on Data Sheet 3, Step (3b).

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(3)

(a)

• (b)

Final Identified and Unidentified Leak Rates List other identified leakage sources as determined by Attachment 1.

1. _________________ = ____ GPM

2. _________________ = ____ GPM

3. _________________ = ____ GPM

4. _________________ = ____ GPM Other Identified Leak Rate = ____ GPM Final Identified Leak Rate Item 1e + Item 3a

= ____ GPM CUE: has identified 0 gpm Identified Leakage.

Standard:

Comment:

5.2.10 Standard:

Comment:

(a)

(b)

Ogpm 0.26 - 0 = 0.26 gpm Perform Section 5.3 to evaluate leak rate results.

N/A 9

5.2.9 Determine final Identified Leakage value and record on Data Sheet 3, Step (3b).

DATA SHEET 3 RCS LEAKAGE CALCULATION (IDENTIFIED & UNIDENTIFIED LEAKAGE)

(3)

(a)

• (b)

Final Identified and Unidentified Leak Rates List other identified leakage sources as determined by Attachment 1.

1. _________________ = ____ GPM

2. ____________________________ = _____ GPM

3. __________________________ = _____ GPM

4. ______________________ = _____ GPM Other Identified Leak Rate = _____ GPM Final Identified Leak Rate Item 1e + Item 3a

= ____ GPM CUE: has identified 0 gpm Identified Leakage.

Standard:

Comment:

5.2.10 Standard:

Comment:

(a)

(b)

Ogpm 0.26 - 0 = 0.26 gpm Perform Section 5.3 to evaluate leak rate results.

N/A 9

5.3.1 Compare and evaluate leak rate results with leak rate trends and take the following actions as required:

NOTES The following steps are not required to be performed in Modes 3 and 4 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation.

The actions of Attachment 1 may be used at anytime to help find leakages if desired by operations management.

5.3.2 Check that IDENTIFIED LEAKAGE is less than or equal to 10 gpm.

Standard:

Notes IDENTIFIED LEAKAGE < 10 gpm Comment:

5.3.3 Check that primary to secondary LEAKAGE is less than 150 gpd through any one SG by establishing an IPC trend on one of the following available continuous process radiation monitors:

a.

b.

Standard:

Comment:

1RE-810 (GAS ROC) __

,gpd OR 1RE-724 (N16 ROC) __

g,pd Determines these reading not available from initial conditions given 10 5.3.1 Compare and evaluate leak rate results with leak rate trends and take the following actions as required:

NOTES The following steps are not required to be performed in Modes 3 and 4 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation.

The actions of Attachment 1 may be used at anytime to help find leakages if desired by operations management.

5.3.2 Check that IDENTIFIED LEAKAGE is less than or equal to 10 gpm.

Standard:

Notes IDENTIFIED LEAKAGE < 10 gpm Comment:

5.3.3 Check that primary to secondary LEAKAGE is less than 150 gpd through any one SG by establishing an IPC trend on one of the following available continuous process radiation monitors:

a.

b.

Standard:

Comment:

1RE-810 (GAS ROC) __

,gpd OR 1RE-724 (N16 ROC) __

g,pd Determines these reading not available from initial conditions given 10

5.3.4 CUE:

Standard:

Comment:

5.3.5 Standard

Comment:

IF neither radiation monitor is available, direct Chemistry to determine primary to secondary LEAKAGE by pulling radiochemical grab samples in accordance with EPRI guidelines by initiating 31120-C "Chemistry Steam Generator Tube Leak Actions.

"Primary to secondary leakage is unchanged from the previous values given."

0.08 gpm Check that UNIDENTIFIED LEAKAGE is less than or equal to 1 gpm.

Determines UNIDENTIFIED LEAKAGE is 1.01 gpm 5.3.6 Compare the initial and final leak rate parameters to those in Precautions and Limitations 3.5. Ensure validity checks are done to allow data to be used in the RCS Unidentified Leak Rate Data Analysis. If the leak rate is performed outside of the bounds of the validity checks, the result should not be used as input to the baseline statistical data set for the historical mean leakrate. The leak rate test should be repeated or deferred until the plant is in a more stable condition.

Document reasons for invalid result in the comments section below. Initiate a condition report to capture the failure of the validity check.

VALIDITY CHECK o SAT o UNSAT CUE:

If asked, "Another operator will perform this step".

Standard:

N/A Comment:

11 5.3.4 CUE:

Standard:

Comment:

5.3.5 Standard

Comment:

IF neither radiation monitor is available, direct Chemistry to determine primary to secondary LEAKAGE by pulling radiochemical grab samples in accordance with EPRI guidelines by initiating 31120-C "Chemistry Steam Generator Tube Leak Actions.

"Primary to secondary leakage is unchanged from the previous values given."

0.08 gpm Check that UNIDENTIFIED LEAKAGE is less than or equal to 1 gpm.

Determines UNIDENTIFIED LEAKAGE is 1.01 gpm 5.3.6 Compare the initial and final leak rate parameters to those in Precautions and Limitations 3.5. Ensure validity checks are done to allow data to be used in the RCS Unidentified Leak Rate Data Analysis. If the leak rate is performed outside of the bounds of the validity checks, the result should not be used as input to the baseline statistical data set for the historical mean leakrate. The leak rate test should be repeated or deferred until the plant is in a more stable condition.

Document reasons for invalid result in the comments section below. Initiate a condition report to capture the failure of the validity check.

VALIDITY CHECK o SAT o UNSAT CUE:

If asked, "Another operator will perform this step".

Standard:

N/A Comment:

11

5.3.7 CUE:

Standard:

Comment:

5.3.8 CUE:

Standard:

Comment:

IF the leak rate data meets the validity check, enter data in the Unit 1 URL Data Analysis Spreadsheet:

If asked, "Another operator will perform this step".

N/A Evaluate the Action Levels for Unidentified RCS Leakage If asked, "Leak Rate Coordinator will evaluate at a later time".

N/A 6.0 ACCEPTANCE CRITERIA

• 6.1 Final UNIDENTIFIED LEAKAGE is less than or equal to 1 gpm.

• 6.2 Final IDENTIFIED LEAKAGE is less than or equal to 10 gpm.

• 6.3 Primary to secondary LEAKAGE is less than 150 gallons per day through anyone SG.

6.4 Action levels for Tier One, Two, or Three have not been exceeded for Unidentified RCS Leakage.

Standard:

Comment:

6.1 6.2 6.3 6.4 NOT MET MET MET incomplete (NOT CRITICAL) 12 5.3.7 CUE:

Standard:

Comment:

5.3.8 CUE:

Standard:

Comment:

IF the leak rate data meets the validity check, enter data in the Unit 1 URL Data Analysis Spreadsheet:

If asked, "Another operator will perform this step".

N/A Evaluate the Action Levels for Unidentified RCS Leakage If asked, "Leak Rate Coordinator will evaluate at a later time".

N/A 6.0 ACCEPTANCE CRITERIA

• 6.1 Final UNIDENTIFIED LEAKAGE is less than or equal to 1 gpm.

• 6.2 Final IDENTIFIED LEAKAGE is less than or equal to 10 gpm.

• 6.3 Primary to secondary LEAKAGE is less than 150 gallons per day through anyone SG.

6.4 Action levels for Tier One, Two, or Three have not been exceeded for Unidentified RCS Leakage.

Standard:

Comment:

6.1 6.2 6.3 6.4 NOT MET MET MET incomplete (NOT CRITICAL) 12

7.0 7.1 7.2 EVALUATION AND REVIEW TEST PURPOSE o Surveillance o Maintenance Retest o Other (explain) ______________ _

Results obtained through performance of this procedure meet ACCEPTANCE CRITERIA of Steps 6.1, 6.2, and 6.3 (Tech Spec Requirement).

o YESO NO 7.2.1 If NO was checked, initiate 18004-C, "Reactor Coolant System Leakage" OR 18009-C, "Steam Generator Tube Leak" as appropriate, notify SS and refer to Technical Specification LCO 3.4.13.

7.3 Results obtained through performance of this procedure meet ACCEPTANCE

7.4 Standard

Comment:

CRITERIA of Step 6.4 (NMP-OS-009 Requirement) o YESO NO Comments (include any abnormal conditions and corrective actions taken): ________________________ __

7.1 7.2 7.3 Surveillance box checked No box is checked N/A (not performed) 13 7.0 7.1 7.2 EVALUATION AND REVIEW TEST PURPOSE o Surveillance o Maintenance Retest o Other (explain) ______________ _

Results obtained through performance of this procedure meet ACCEPTANCE CRITERIA of Steps 6.1, 6.2, and 6.3 (Tech Spec Requirement).

o YESO NO 7.2.1 If NO was checked, initiate 18004-C, "Reactor Coolant System Leakage" OR 18009-C, "Steam Generator Tube Leak" as appropriate, notify SS and refer to Technical Specification LCO 3.4.13.

7.3 Results obtained through performance of this procedure meet ACCEPTANCE

7.4 Standard

Comment:

CRITERIA of Step 6.4 (NMP-OS-009 Requirement) o YESO NO Comments (include any abnormal conditions and corrective actions taken): _________________________ __

7.1 7.2 7.3 Surveillance box checked No box is checked N/A (not performed) 13

7.5 Check below for the attached documents.

IPC printout PC Spread sheet Data Sheets 1, 2 Data Sheet 3 Data Sheet 4 Data Sheet 5 URL Data Analysis Spread Sheet Test Completed and SS Notified:

Supervisory Review:

Standard:

Data Sheets 1,2 Data Sheet 3 Data Sheet 4 Data Sheet 5 URL Data Analysis Spread Sheet 0

0 0

0 0

0 0

0 Signature Signature o CHECKED o CHECKED o o CHECKED o o CHECKED Test Completed and SS Notified block is signed and dated.

Comment:

14 Date I Time Date ITime 7.5 Check below for the attached documents.

IPC printout PC Spread sheet Data Sheets 1, 2 Data Sheet 3 Data Sheet 4 Data Sheet 5 URL Data Analysis Spread Sheet Test Completed and SS Notified:

Supervisory Review:

Standard:

Data Sheets 1,2 Data Sheet 3 Data Sheet 4 Data Sheet 5 URL Data Analysis Spread Sheet 0

0 0

0 0

0 0

0 Signature Signature o CHECKED o CHECKED o o CHECKED o o CHECKED Test Completed and SS Notified block is signed and dated.

Comment:

14 Date I Time Date ITime

Reports SS that 14905-1 is UNSAT due to UNIDENTIFIED LEAKAGE exceeding acceptance requirements.

Standard:

N/A Comment:

Terminating cue:

Student returns initiating cue sheet 15 Reports SS that 14905-1 is UNSAT due to UNIDENTIFIED LEAKAGE exceeding acceptance requirements.

Standard:

N/A Comment:

Terminating cue:

Student returns initiating cue sheet 15

Verification of Completion Job Performance Measure No: V-RQ-JP-14905-001S Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: _____________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date:

16 Verification of Completion Job Performance Measure No: V-RQ-JP-14905-001S Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Response: _____________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date:

16

Res LEAKAGE TEST DATA Initial Reading Final Reading Start/Stop Time 14:00 16:08 Pressurizer Pressure 1PI-456 2235.100 2235.000 1PI-455 2235.600 2235.700 1PI-457 2232.400 2232.300 1PI-458 2234.500 2234.600 Pressurizer Temperature 1TI-0453 653.2 653.2 RCS Temperature 1TI-0412 586.400 586.400 1TI-0422 585.500 585.400 1TI-0432 585.900 585.900 1TI-0442 588.400 588.500 Pressurizer Level 1 U-0459 58.100 57.800 1 U-0460 57.500 57.100 1 U-0461 57.800 57.600 VCT Level 1U-0185 48.250 40.750 PRT Level 1 U-0470 78.42 78.42 RCDT Level (Data Sheet 5)

Start/Stop Time 13:57 16:08 1 U-1003 48.000 54.000 Crud Tank Leakage Determination (Data Sheet 4)

O/not performed Primary-to-Secondary Leakage (31120-C) 0.08 GPM Pressure Isolation Valve Leakage (14450-1) o GPM Other Identified Leakage Sources (Attachment 1) o GPM 17 Res LEAKAGE TEST DATA Initial Reading Final Reading Start/Stop Time 14:00 16:08 Pressurizer Pressure 1PI-456 2235.100 2235.000 1PI-455 2235.600 2235.700 1PI-457 2232.400 2232.300 1PI-458 2234.500 2234.600 Pressurizer Temperature 1TI-0453 653.2 653.2 RCS Temperature 1TI-0412 586.400 586.400 1TI-0422 585.500 585.400 1TI-0432 585.900 585.900 1TI-0442 588.400 588.500 Pressurizer Level 1 U-0459 58.100 57.800 1 U-0460 57.500 57.100 1 U-0461 57.800 57.600 VCT Level 1U-0185 48.250 40.750 PRT Level 1 U-0470 78.42 78.42 RCDT Level (Data Sheet 5)

Start/Stop Time 13:57 16:08 1 U-1003 48.000 54.000 Crud Tank Leakage Determination (Data Sheet 4)

O/not performed Primary-to-Secondary Leakage (31120-C) 0.08 GPM Pressure Isolation Valve Leakage (14450-1) o GPM Other Identified Leakage Sources (Attachment 1) o GPM 17

Initial Conditions:

With Unit 1 in Mode 1, all computers are unavailable. 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.

Initiating Cue:

You are the 55, perform a "manual RCS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any).

Use the provided 14905-1, RCS Leakage Calculation.

18 Initial Conditions:

With Unit 1 in Mode 1, all computers are unavailable. 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.

Initiating Cue:

You are the 55, perform a "manual RCS leakage calculation" using 14905-1, evaluate the data, and take appropriate actions (if any).

Use the provided 14905-1, RCS Leakage Calculation.

18

Job Performance Measure "D.R" Facility: Vogtle Task No: V-LO-TA-40003 Task

Title:

ENN Notification and Recall - Alert Emergency JPM No: V-RQ-JP-91 002-004 KIA

Reference:

G2.4.43 Examinee:

NRC Examiner:

Facility Evaluator: _________ _

Date:

Method of testing:

Simulated Performance ______ _

Actual Performance ----------

Classroom _____ _

Simulator ______ _

Plant ------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

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 Director position.

Task Standard:

Emergency Recall and Roll Call performed lOA Checklist 4 and ENN message properly transmitted.

Required Materials:

Procedure 91002-C, Emergency Notifications, Checklist 4 Pre-filled out copy of 91 002-C, Emergency Notification, Checklist 2 VEGP ERTD Phone Book and Emergency Recall Packet General

References:

None Initiating Cue:

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.

Time Critical Task:

Yes Validation Time:

15 minutes Job Performance Measure "D.R" Facility: Vogtle Task No: V-LO-TA-40003 Task

Title:

ENN Notification and Recall - Alert Emergency JPM No: V-RQ-JP-91 002-004 KIA

Reference:

G2.4.43 Examinee:

NRC Examiner: _________ _

Facility Evaluator: ________ _

Date:

Method of testing:

Simulated Performance _______ _

Actual Performance -------------

Classroom _________ _

Simulator __________ _

Plant _____ _

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

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 Director position.

Task Standard:

Emergency Recall and Roll Call performed lOA Checklist 4 and ENN message properly transmitted.

Required Materials:

Procedure 91002-C, Emergency Notifications, Checklist 4 Pre-filled out copy of 91 002-C, Emergency Notification, Checklist 2 VEGP ERTD Phone Book and Emergency Recall Packet General

References:

None Initiating Cue:

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.

Time Critical Task:

Yes Validation Time:

15 minutes

SIMULATOR SeTUP:

(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 and NOT the real ENN phone jack.

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

(5) Test the emergency recall phone number for Alert Emergency prior to initiation.

Setup time: 10 minutes 2

SIMULATOR SeTUP:

(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 and NOT the real ENN phone jack.

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

(5) Test the emergency recall phone number for Alert Emergency prior to initiation.

Setup time: 10 minutes 2

Performance Information Critical steps denoted with an asterisk Candidate should be given Checklist 4, Directions for ENN Communicators at this time.

Standard:

Not applicable.

Comment:

START TIME FOR TIME CRITICAL ___

Candidate reviews notes prior to Section I, step 1 of Checklist 4 regarding recall to be performed by ENN communicators only, ERO recall only if Alert or higher declared, if under attack by a hostile force to activate security recall, only management recalled on NOUE, and a 3 to 4 minute time delay before callback to Control Room.

Standard:

Comment:

• Step 1 CUE:

Standard:

Comment:

Not applicable.

Section I, EMERGENCY RESPONSE ORGANIZATION RECALL Operations personnel shall activate the "Primary" emergency recall system in accordance with posted system instructions. (Either NOUE or Alert/Site Area/General or Security Scenario as appropriate)

Activates the "Primary" emergency recall system for Alert Emergency.

Dials 706-554-4316 Enters Activation Password {93 49 87 50 90} followed by the # sign.

Enters Scenario 10 {917 566 662} followed by the # sign.

Presses three <3> when prompted to start the scenario.

Waits for the message "the scenario is building".

Presses the # sign and hangs up.

"PLEASE USE THE SPEAKER PHONE AND TURN ON THE SPEAKER" Pulls Primary Recall System packet from drawer and properly performs the steps for remote activation for an Alert emergency (white sheet) 3 Performance Information Critical steps denoted with an asterisk Candidate should be given Checklist 4, Directions for ENN Communicators at this time.

Standard:

Not applicable.

Comment:

START TIME FOR TIME CRITICAL ___

Candidate reviews notes prior to Section I, step 1 of Checklist 4 regarding recall to be performed by ENN communicators only, ERO recall only if Alert or higher declared, if under attack by a hostile force to activate security recall, only management recalled on NOUE, and a 3 to 4 minute time delay before callback to Control Room.

Standard:

Comment:

• Step 1 CUE:

Standard:

Comment:

Not applicable.

Section I, EMERGENCY RESPONSE ORGANIZATION RECALL Operations personnel shall activate the "Primary" emergency recall system in accordance with posted system instructions. (Either NOUE or Alert/Site Area/General or Security Scenario as appropriate)

Activates the "Primary" emergency recall system for Alert Emergency.

Dials 706-554-4316 Enters Activation Password {93 49 87 50 90} followed by the # sign.

Enters Scenario 10 {917 566 662} followed by the # sign.

Presses three <3> when prompted to start the scenario.

Waits for the message "the scenario is building".

Presses the # sign and hangs up.

"PLEASE USE THE SPEAKER PHONE AND TURN ON THE SPEAKER" Pulls Primary Recall System packet from drawer and properly performs the steps for remote activation for an Alert emergency (white sheet) 3

Step 2 Standard:

Comment:

Step 5 Standard:

Comment:

Operations personnel should verify the "Primary" emergency recall system is operable via a callback to the control room by the emergency recall system. In addition, the Shift Manager's beeper should activate and display a predetermined emergency pager message. The number displayed on the pager for an actual emergency will be three 9'5 (999) and a call-in number. The number displayed on the pager for a security emergency will be three 6'5 (666) and a call-in number.

Verifies the "Primary" emergency recall system is operable via a callback.

Extension # 3652 rings shortly after recall system activation.

NOTE: The candidate will have to go answer the phone and go through a short menu to prevent multiple callbacks by the recall system.

Record date, time and name below after completing the 'Steps For Remote Activation' as delineated within the posted system instructions.

Checks N/A blocks on steps # 3 and # 4 since recall system works.

Records date, time, and name on step 5.

Proceeds to Section II, step 1 for Notification Roll Call.

4 Step 2 Standard:

Comment:

Step 5 Standard:

Comment:

Operations personnel should verify the "Primary" emergency recall system is operable via a callback to the control room by the emergency recall system. In addition, the Shift Manager's beeper should activate and display a predetermined emergency pager message. The number displayed on the pager for an actual emergency will be three 9'5 (999) and a call-in number. The number displayed on the pager for a security emergency will be three 6'5 (666) and a call-in number.

Verifies the "Primary" emergency recall system is operable via a callback.

Extension # 3652 rings shortly after recall system activation.

NOTE: The candidate will have to go answer the phone and go through a short menu to prevent multiple callbacks by the recall system.

Record date, time and name below after completing the 'Steps For Remote Activation' as delineated within the posted system instructions.

Checks N/A blocks on steps # 3 and # 4 since recall system works.

Records date, time, and name on step 5.

Proceeds to Section II, step 1 for Notification Roll Call.

4

SECTION II, NOTIFICATION ROLL CALL Reviews NOTES prior to Section II for notifications must be made within 15 minutes, do not wait for ED for fill out form, if using an outside line not to use a "9" and to use "9" is using plant extensions.

Standard:

Comment:

Step 1.

Standard:

Comment:

Step 2 Standard:

Comment:

Not applicable.

If appropriate, receive turnover from respective emergency response facility (control room, TSC, or EOF) using General Relief checklist in procedure 91101-C, "Emergency Response Organization" Not applicable.

Ensure that the following items are present:

a.

Emergency Response Telephone Directory (ERTD)

b.

Log Book Removes ERTD from drawer and places on desk (blue colored book)

Log Book is not applicable.

5 SECTION II, NOTIFICATION ROLL CALL Reviews NOTES prior to Section II for notifications must be made within 15 minutes, do not wait for ED for fill out form, if using an outside line not to use a "9" and to use "9" is using plant extensions.

Standard:

Comment:

Step 1.

Standard:

Comment:

Step 2 Standard:

Comment:

Not applicable.

If appropriate, receive turnover from respective emergency response facility (control room, TSC, or EOF) using General Relief checklist in procedure 91101-C, "Emergency Response Organization" Not applicable.

Ensure that the following items are present:

a.

Emergency Response Telephone Directory (ERTD)

b.

Log Book Removes ERTD from drawer and places on desk (blue colored book)

Log Book is not applicable.

5

Step 3 Standard:

Comment:

• Step 3.c agencies:

Standard:

Comment:

Perform a roll call.

a.

Press **on the ENN phone to ring ALL stations.

b.

States the following:

(select one)

"THIS (IS liS NOT) A DRILL!

HELLO, THIS IS (Name)

AT THE VOGTLE ELECTRIC GENERATING PLANT. PLEASE OBTAIN A COPY OF THE EMERGENCY NOTIFICATION FORM. STANDBY TO RECEIVE A MESSAGE."

Dials ** on ENN phone States THIS IS A DRILL when simbooth operator answers.

Reads greeting statement with candidates name inserted.

Proceed with roll call in the following order, check box for responding o

Burke County o

State of Georgia o

Aiken County o

Savannah River Site o

Allendale County o

State of South Carolina o

Barnwell County Reads roll call for all 7 agencies and ensures response.

NOTE: The Simbooth operator will be on an ENN phone to respond. All agencies respond in this scenario.

6 Step 3 Standard:

Comment:

• Step 3.c agencies:

Standard:

Comment:

Perform a roll call.

a.

Press **on the ENN phone to ring ALL stations.

b.

States the following:

(select one)

"THIS (IS liS NOT) A DRILL!

HELLO, THIS IS (Name)

AT THE VOGTLE ELECTRIC GENERATING PLANT. PLEASE OBTAIN A COPY OF THE EMERGENCY NOTIFICATION FORM. STANDBY TO RECEIVE A MESSAGE."

Dials ** on ENN phone States THIS IS A DRILL when simbooth operator answers.

Reads greeting statement with candidates name inserted.

Proceed with roll call in the following order, check box for responding o

Burke County o

State of Georgia o

Aiken County o

Savannah River Site o

Allendale County o

State of South Carolina o

Barnwell County Reads roll call for all 7 agencies and ensures response.

NOTE: The Simbooth operator will be on an ENN phone to respond. All agencies respond in this scenario.

6

Step 3.d Standard:

Comment:

Step 3.e Standard:

Comment:

If multiple agencies fail to respond to the roll call in step c. above, perform steps

h. and i. below.

Not applicable.

Go to 'Transmission of Notification Message" (Section III) of this checklist if either of the following conditions exist:

(1)

All stations respond to the roll call.

Proceeds to section III, "Transmission of Notification Message".

SECTION III, TRANSMISSION OF NOTIFICATION MESSAGE Reviews NOTES prior to Section III regarding lines filled out by communicator, all blocks checked for PARS, ED signing the form, first follow-up notification, faxing should not interfere with transmission time requirements.

Standard:

Not applicable.

Comment:

7 Step 3.d Standard:

Comment:

Step 3.e Standard:

Comment:

If multiple agencies fail to respond to the roll call in step c. above, perform steps

h. and i. below.

Not applicable.

Go to 'Transmission of Notification Message" (Section III) of this checklist if either of the following conditions exist:

(1)

All stations respond to the roll call.

Proceeds to section III, "Transmission of Notification Message".

SECTION III, TRANSMISSION OF NOTIFICATION MESSAGE Reviews NOTES prior to Section III regarding lines filled out by communicator, all blocks checked for PARS, ED signing the form, first follow-up notification, faxing should not interfere with transmission time requirements.

Standard:

Not applicable.

Comment:

7

Step 1 CUE:

Standard:

Comment:

Transmit the notification form via voice and facsimile in the following manner:

a.

If time permits, fax the notification form.

(1) Place a copy or one sheet of the triplicate form face down in the transmit tray of the fax machine.

(2) Depress the appropriate one-touch speed dial button.

(Control Room use NOTIFY)

Do NOT depress any of the buttons on the fax machine.

Demonstrates proper methods to fax the form.

Shows where to lay form face down.

Points to the NOTIFY (training) push button. (Do NOT let him press) 8 Step 1 CUE:

Standard:

Comment:

Transmit the notification form via voice and facsimile in the following manner:

a.

If time permits, fax the notification form.

(1) Place a copy or one sheet of the triplicate form face down in the transmit tray of the fax machine.

(2) Depress the appropriate one-touch speed dial button.

(Control Room use NOTIFY)

Do NOT depress any of the buttons on the fax machine.

Demonstrates proper methods to fax the form.

Shows where to lay form face down.

Points to the NOTIFY (training) push button. (Do NOT let him press) 8

• Step 1.b Read the notification form (Checklist 2) starting at line 1, through line 13 then line 17.

Line 1 - Block A, DRILL and message # 001 Line 2 - Block A, INITIAL, Notification Time and Date, Authentication #

END TIME FOR TIME CRITICAL, ____ (after reading Notification Time and Date)

CUE: The State of South Carolina request authentication for code word # 27 Standard:

Line 3 - Site, VOGTLE, confirmation phone # (706) 826-3652 Line 4 - Emergency Classification, Block B, Alert Based on EAL # FA1 EAL

Description:

ANY Loss or ANY Potential Loss Of EITHER Fuel Clad Barrier OR RCS Barrier Line 5 - Protective Action Recommendations, Block A - NONE Line 6 - Emergency Release, Block A, NONE Line 7 -

Release significance, Block A, Not Applicable Line 8 -

Event Prognosis, Block B, Stable Line 9 - Meteorological data.

Wind direction - 69 degrees, Wind speed - 4.6 mph Precipitation - None, Stability Class - D Line 10 - Block A, DECLARATION, Time and Date (TBD at exam time)

Line 11 - Affected Unit (s), One (1)

Line 12 - Unit Status, Unit 1 at 0%, Shutdown at time TBD at exam time Unit 2 at 100%, Shutdown time N/A Line 13 - Remarks, None Lines 14, 15, 16 - Not applicable at this time Line 17 - Approved by, Thad N. Thompson, Title - Emergency Director, Time and Date, Notified by CANDIDATE Lines 1 through 17 areas highlighted in YELLOW must be read properly.

Comment:

9

• Step 1.b Read the notification form (Checklist 2) starting at line 1, through line 13 then line 17.

Line 1 - Block A, DRILL and message # 001 Line 2 - Block A, INITIAL, Notification Time and Date, Authentication #

END TIME FOR TIME CRITICAL ____ (after reading Notification Time and Date)

CUE: The State of South Carolina request authentication for code word # 27 Standard:

Line 3 - Site, VOGTLE, confirmation phone # (706) 826-3652 Line 4 - Emergency Classification, Block B, Alert Based on EAL # FA1 EAL

Description:

ANY Loss or ANY Potential Loss Of EITHER Fuel Clad Barrier OR RCS Barrier Line 5 - Protective Action Recommendations, Block A - NONE Line 6 - Emergency Release, Block A, NONE Line 7 -

Release significance, Block A, Not Applicable Line 8 -

Event Prognosis, Block B, Stable Line 9 - Meteorological data.

Wind direction - 69 degrees, Wind speed - 4.6 mph Precipitation - None, Stability Class - D Line 10 - Block A, DECLARATION, Time and Date (TBD at exam time)

Line 11 - Affected Unit (s), One (1)

Line 12 - Unit Status, Unit 1 at 0%, Shutdown at time TBD at exam time Unit 2 at 100%, Shutdown time N/A Line 13 - Remarks, None Lines 14, 15, 16 - Not applicable at this time Line 17 - Approved by, Thad N. Thompson, Title - Emergency Director, Time and Date, Notified by CANDIDATE Lines 1 through 17 areas highlighted in YELLOW must be read properly.

Comment:

9

Terminating cue:

Student returns initiating cue sheet 10 Terminating cue:

Student returns initiating cue sheet 10

Verification of Completion Job Performance Measure No. V-RQ-JP-91 002-004 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Res po nse: ___________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _____________ _

11 Verification of Completion Job Performance Measure No. V-RQ-JP-91 002-004 Examinee's Name:

Examiner's Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question: _____________________________ _

Res po nse: __________________________________ __

Result: Satisfactory/Unsatisfactory Examiner's signature and date:

11

Initial Conditions:

Initiating Cue:

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 Director 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.

12 Initial Conditions:

Initiating Cue:

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 Director 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.

12