ML13347B141

301 Final Administrative JPMs

ML13347B141
Person / Time
Site:	Vogtle
Issue date:	12/11/2013
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
V-NRC-JP-14915-HL17
Download: ML13347B141 (68)

Text

RO Job Performance Measure A Facility: Vogtle Task No: V-LO-TA-63005 Task

Title:

Perform AFD Monitoring JPM No: V-NRC-JP-14915-HL17 K/A: G2.1 .37 RO 4.3 SRO 4.6 Examinee: Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Perlormance Actual Performance Classroom 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 has recently recovered from a load rejection. The unit is at 70% power. Annunciator ALB1 0-F06 is lit.

I&C has reported that the AFD monitor alarm ALB1 0-F06 is inoperable.

Initiating Cue: The SS directs you to perform 14915-1 for AFD Monitoring, including Data Sheet 6 and completing section 7.0, Evaluation and Review, for all the following provided data.

Time NI Channel Reading AFlux Channel Reading 0700 1NI-41B 70% 1-N-41C -15%

0700 1 Nl-42B 68% 1 -N-42C -22%

0700 1 NI-43B 70% 1 -N-43C -25%

0700 1 Nl-44B 70% 1 -N-44C -15%

0800 1NI-41B 70% 1-N-41C -17%

0800 1 NI-42B 69% 1 -N-42C -21 %

0800 1 NI-43B 70% 1 -N-43C -23%

0800 1 Nl-44B 69% 1 -N-44C -17%

0900 1NI-41B 70% 1-N-41C -18%

0900 1 NI-42B 69% 1-N-42C -20%

0900 1 Nl-43B 70% 1 -N-43C -22%

0900 1 NI-44B 70% 1 -N-44C -18%

2

Task Standard: AFD monitoring per 14915-1 Data Sheet 6 performed correctly.

Required Materials: 14915-1, Data Sheet 6 Unit 1 Plant Technical Data Book Tab 6.0 Calculator Red Ink Pen This JPM is a reuse from Exam 2011-301. The JPM number was V-NRC-JP-1 9105-004.

Time Critical Task: No Validation Time: 15 minutes 3

Performance Information Critical steps denoted with an asterisk

• Step 1 Determine upper and lower limits of AFD from PTDB-1 Tab 6.0.

Standard: Candidate fills in date and power level 70% and records the value of the doghouse limit at 70%. Upper limit +19.5% +/- 0.5% (calculated value is 19.6%) Lower limit -24% +/- 0.5%.

Comment:

Step 2 Record indicated Axial Flux Difference for each operable Excore Channel.

Standard: Candidate records Delta Flux values for all channels.

Comment:

• Step 3 Verify the Axial Flux Difference is within limits of PTDB-1 Tab

6.0. Standard

Candidate verifies that three are within limits and initials or signs Verified block to complete the surveillance satisfactory.

Comment:

4

Step 4 With the indicated AFD outside of the above required limits on 2 or more channels and with THERMAL POWER greater than or equal to 50% of RATED THERMAL POWER, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes.

Per Precautions and Limitations, Step 3.0, 1 -Nl-43C will be Red Circled as being out of tolerance.

Standard: This step does not apply.

Comment:

5

DATA SHEET 6 (ANSWER KEY)

DATA SHEET 6 Sheet2of4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE Date Todays date Power ZQ%

Upper Limit = +.i..9..5% +/- O5°/ø (from PTDB Tab 6.0)

Lower Limit = -24% +/-05%

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED 0700  % 25% -1 5% Initials 0800 17% B% -23% -17% Initials 0900 -18% 11% -22% -18% Initials 6

ACCEPTANCE CRITERIA (ANSWER KEY) 7.0 EVALUATION AND REVIEW 7.1 TEST PURPOSE Special Condition(s):

AFD Monitor Inoperable Data Sheet(s) completed (Circle Appropriate Sheets):

1 2 3 4a 4b 18 c:\ 8 9 10 11 12 13 14 15 16 17 7.2 Results obtained through the performance of this procedure meet the ACCEPTANCE CRITERIA of Section 6.0.

EYES DNO 7.3 IF no was checked, immediately notify the SS and initiate action in accordance with the actions specified on the data sheet(s) not meeting the acceptance criteria.

7.4 Comments (include any abnormal conditions and corrective actions taken):

None Test Completed and SS Notified:

Supervisory Review:

Signature Date Time Terminating cue: Student returns initiating cue sheet.

7

Verification of Completion Job Performance Measure No: V-NRC-JP-14915-HL17 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

8

Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. Annunciator ALB1 0-F06 is lit.

l&C has reported that the AFD monitor alarm ALB1O-F06 is inoperable.

Initiating Cue: The SS directs you to perform 14915-1 for AFD Monitoring, including Data Sheet 6 and completing section 7.0, Evaluation and Review, for all the following provided data.

Time NI Channel Reading AFlux Channel Reading 0700 1NI-41B 70% 1-N-41C -15%

0700 1 Nl-42B 68% 1 -N-42C -22%

0700 1 Nl-43B 70% 1 -N-43C -25%

0700 1 Nl-44B 70% 1 -N-44C -15%

0800 1NI-41B 70% 1-N-41C -17%

0800 1 Nl-42B 69% 1 -N-42C -21 %

0800 1 NI-43B 70% 1 -N-43C -23%

0800 1 Nl-44B 69% 1 -N-44C -17%

0900 lNl-41B 70% 1-N-41C -18%

0900 1 Nl-42B 69% 1 -N-42C -20%

0900 1 NI-43B 70% 1 -N-43C -22%

0900 1 Nl-44B 70% 1 -N-44C -18%

SRO Job Performance Measure A Facility: Vogtle Task No: V-LO-TA-63005 Task

Title:

Evaluate Inoperable AFD Monitor Alarm JPM No: V-NRC-JP-14915-HL17 K/A: G2.1 .37 (SRO 4.6)

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 has recently recovered from a load rejection. The unit is at 70% power. Annunciator ALB1 0-FOG is lit.

l&C has reported that the AFD monitor alarm ALB1 0-FOG is inoperable.

Initiating Cue: The SS directs you to perform 14915-1 for AFD Monitoring, including Data Sheet 6 and completing section 7.0, Evaluation and Review, for all the following provided data.

Time NI Channel Reading AFlux Channel Reading 0700 1Nl41B 70% 1-N-41C -15%

0700 1 NI-42B 68% 1 -N-42C -22%

0700 1 Nl-43B 70% 1 -N-43C -25%

0700 1 Nl-44B 70% 1 -N-44C -15%

0800 1NI-41B 70% 1-N-41C -17%

0800 1 Nl-42B 69% 1 -N-42C -21 %

0800 1 Nl-43B 70% 1 -N-43C -23%

0800 1 Nl-44B 69% 1 -N-44C -17%

0900 1 N 1-41 B 70% 1 -N-41 C -18%

0900 1 NI-42B 69% 1-N-42C -20%

0900 1 Nl-43B 70% 1 -N-43C -22%

0900 1 Nl-44B 70% 1 -N-44C -18%

Based on the results of the surveillance, is any Technical Specification (TS) LCO NOT met? If any TS LCO is NOT met, THEN determine aN TS REQUIRED ACTIONS, if any, for the given plant conditions.

2

Task Standard: Inoperable AFD monitor alarm ALB1 0-F06 is evaluated and applicable actions taken (AFD calculated and LCO evaluated).

Required Materials: 14915-1, Data Sheet 6 Unit 1 Plant Technical Data Book Tab 6.0 Tech Specs, Tech Spec Bases, COLR Calculator Red Ink Pen This JPM is a reuse from Exam 2011-301. The JPM number was V-NRC-JP-1 4915-004.

Time Critical Task: No Validation Time: 15 minutes 3

Performance Information Critical steps denoted with an asterisk

• Step 1 Determine upper and lower limits of AFD from PTDB-Unit 1 Tab 6.0.

Standard: Candidate fills in date and power level 70% and records the value of the doghouse limit at 70% Upper limit +19.5% +/- 0.5% (calculated value is 19.6%) Lower limit -24% +/- 0.5%.

Comment:

Step 2 Record indicated Axial Flux Difference for each operable Excore Channel.

Standard: Candidate records Delta Flux values for all channels.

Comment:

• Step 3 Verify the Axial Flux Difference is within limits of PTDB-Unit 1 Tab 6.0.

Standard: Candidate verifies that all channels are within limits and initials the verified column.

Comment:

4

• Step 4 Determine required action.

With the indicated AFD outside of the above required limits on 2 or more channels and with THERMAL POWER greater than or equal to 50% of RATED THERMAL POWER, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes.

Note to the examiner: The critical element is to determine the surveillance is SAT. If the candidate determines actions are required ,then the critical step is not met.

Standard: Candidate should report no action required.

Comment:

5

DATA SHEET 6 (ANSWER KEY)

DATA SHEET 6 Sheet2of4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE Date Todays date. Power ZQ%

Upper Limit = 1 95% +/- 0.5% (from PTDB Tab 6.0)

Lower Limit = +/- 0.5%

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED 0700 -15% -22% -25% -15% laIs 0800 -17% -21 % -23% 1 7% aIs 0900 -18% -20% -22% -18% IlaIs Tech Specs 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology)

LCO 3.2.3 The AFD shall be maintained within the limits specified in the COLR.

NOTE The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

APPLICABILITY: MODE 1 with THERMAL POWER 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits. A.1 Reduce THERMAL 30 minutes POWER to < 50% RTP.

6

14915-1 ACCEPTANCE CRITERIA (ANSWER KEY) 7.0 EVALUATION AND REVIEW 7.1 TEST PURPOSE Special Condition(s):

AFD MohWdéEie Data Sheet(s) completed (Circle Appropriate Sheets):

1 2 3 4a 4b 5J7 8 9 10 11 12 13 14 15 16 17 18 7.2 Results obtained through the perlormance of this procedure meet the ACCEPTANCE CRITERIA of Section 6.0.

EYES DNO 7.3 IF no was checked, immediately notify the SS and initiate action in accordance with the actions specified on the data sheet(s) not meeting the acceptance criteria.

7.4 Comments (include any abnormal conditions and corrective actions taken):

None Test Completed and SS Notified:

Supervisory Review:

Signature Date Time Terminating cue: Student returns initiating cue sheet.

7

Verification of Completion Job Performance Measure No: V-NRC-JP-14915-HL17 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

8

Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. Annunciator ALB1 0-F06 is lit.

l&C has reported that the AFD monitor alarm ALB1 0-F06 is inoperable.

Initiating Cue: The SS directs you to perform 14915-1 for AFD Monitoring, including Data Sheet 6 and completing section 7.0, Evaluation and Review, for all the following provided data.

Time NI Channel Reading EFlux Channel Reading 0700 1NI-41B 70% 1-N-41C -15%

0700 1 Nl-42B 68% 1 -N-42C -22%

0700 1 Nl-43B 70% 1 -N-43C -25%

0700 1 NI-44B 70% 1 -N-44C -15%

0800 1NI-41B 70% 1-N-41C -17%

0800 1 Nl-42B 69% 1 -N-42C -21 %

0800 1 NI-43B 70% 1 -N-43C -23%

0800 1 NI-44B 69% 1 -N-44C -17%

0900 1 N 1-41 B 70% 1 -N-41 C -18%

0900 1 Nl-42B 69% 1 -N-42C -20%

0900 1 Nl-43B 70% 1 -N-43C -22%

0900 1 NI-44B 70% 1 -N-44C -18%

Based on the results of the surveillance, is any Technical Specification (TS) LCO NOT met? If any TS LCO is NOT met, THEN determine aN TS REQUIRED ACTIONS, if any, for the given plant conditions.

RO/SRO Admin Job Performance Measure B Facility: Vogtle Task No: V-LO-TA-27003 Task

Title:

Keff Determination for Shutdown Banks withdrawn JPM No: V-NRC-JP-14005-HL17 KlA

Reference:

G2.1.25 R03.9SR04.2 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: The crew is performing a reactor startup on Unit 1 following a trip from 1 00% power, steady state conditions.

Initiating Cue: Using the data below, the SS has directed you to Determine Keff for withdrawal of the Shutdown Banks. Perform calculation to three decimal places.

Reactor Trip occurred 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> ago:

Current Plant Conditions The following values are from Rx Engineering Boron Concentration 1400 ppm Cycle Burnup 1250 MWD/MTU Tavg 557°F Axial Offset Reactivity Correction 0 pcm All rods are inserted Boron-free Xenon plus Samarium Worth 2350 pcm ECC Boron Concentration 1400 ppm ECP Control Rod Position 120 steps CBD

Task Standard: KEFF calculated with the shutdown banks withdrawn.

Required Materials: 1. 14005-1, Shutdown Margin and KEFF Calculations Ver 27.0

2. PTDB Tab 1.0 for Cycle 17 General

References:

None Time Critical Task: No Validation Time: 20 minutes 2

Performance Information Critical steps denoted with an asterisk 14005-1 Data Sheet 3 selected.

Standard: Candidate selects Data Sheet 3.

Comment:

Sheet 1 of Data Sheet 3 completed.

Standard: Candidate completes Sheet 1 as indicated on KEY from plant conditions given.

Comment:

Sheet 2 of Data Sheet 3 completed.

Standard: Candidate completes Sheet 2 using the PTDB as indicated on KEY.

Step J.1 obtained from Table 1 .5.4-Ti BOL value.

Step J.2 obtained from Table 1.5.1 -T2 at CBD =120.

Step J.3 obtained from plant conditions.

Step J.4 completed from J.1, J.2, J.3 and math performed.

Step J.5 completed from J.4 and math performed.

Comment:

Terminating cue: Candidate returns cue sheet and completed Data sheet 3.

3

KEY DATA SHEET 3 Sheet 1 of 2 KEFF WITH SHUTDOWN BANKS WITHDRAWN G. CONDITIONS PRIOR TO ENTERING MODE 3 (SUBCRITICALITY)

G.1 Mode 3 declared Date áreimI6 hours Time G.2 Cycle Burnup 1 250 MWD/MTU (from Reactor Engineering)

G.3 Power Level 100 %

H. NTROJECTED CONDITIONS (circle one)

H 1

. Date N/A Time N/A (If this Keff is being calculated for projected conditions, then enter the projected time.)

H.2 Core Average Temperature 557 +/-1 °F H.3 Length of Shutdown 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> H.4 Estimated Critical Boron Concentration (ECC) at (H.3) hours after Mode 3 entry

_14OO ppm H.5 Estimated Critical Position (ECP) at (H.3) hours after Mode 3 entry CBC 228 CBD:12o 4

KEY DATA SHEET 3 Sheet2of2 J. KEFF CALCULATION NOTE For all calculations, record the ABSOLUTE VALUES of the reactivity values obtained from the PTDB.

J.1 Cumulative Control Rod Worth for D+C+B+A Configuration at HZP and Burnup (G.2) (PTDB TAB 1 .5.4-Ti) ÷3039 pcm J.2 Integral Rod Worth BOL, MOL or EOL at ECP (H.5) and Burnup (G.2) [If the Length of Shutdown (H.3) is less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> OR greater than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, then USE HZP, HFP-Eq-Xe PTDB TAB 1.5.1-T2, T5, orT8. If the Length of Shutdown (H.3) is between 4 and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, then USE HZP, HZP-Peak-Xe PTDB TAB 1.5.1 -T3, T6, or T9.] + 366 pcm J.3 Axial Offset Reactivity Correction (From Reactor Engineering) +J**__pcm J.4 Shutdown Reactivity:

(J.i) (J.2) (J.3) =

3O39 _366- - 0 = ( )2673 pcm J.5 Keff: 1.0000 / [1.0000 + ((J.4)/1 00,000)1 =

1.0000/ [1.0000 + (2673ji 00,000)] = + 0.974 ACCEPTANCE CRITERIA Keff (J.5) shall be less than ÷0.99.

EYES LIN0 Completed By: SiGNATURE CURRENT DATE/TIME Signature Date/Time Verified By:

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Initial Conditions: The crew is performing a reactor startup on Unit 1 following a trip from 1 00% power, steady state conditions.

Initiating Cue: Using the data below, the SS has directed you to Determine Keff for withdrawal of the Shutdown Banks. Perform calculation to three decimal places.

Reactor Trip occurred 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> ago.

Current Plant conditions:

Boron Concentration 1400 ppm Tavg 557°F Current Rod Height All rods are inserted ECC Boron Concentration 1400 ppm ECP Control Rod Position 120 steps CBD The following values are from Rx Engineering:

Cycle Burnup 1250 MWD/MTU Axial Offset Reactivity Correction 0 pcm Boron-free Xenon plus Samarium Worth 2350 pcm

RO Admin Job Performance Measure C Facility: Vogtle Task No: V-LO-TA-63004 Task

Title:

Determine Tagging Requirements JPM No: V-NRC-JP-NMP-AD-003-HL17 KlA

Reference:

G2.2.13 P04.1 SRO4.3 Examinee: NRC Examiner:

Facility Evaluator: Date:______________

Method of testing:

Simulated Pertormance Actual Performance Classroom 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 at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work are tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work are tagged under another referenced Tagout.

Initiating Cue: Determine the appropriate boundary points and required positions of components to isolate the fluid boundary and drain CSP A, 1-1206-P6-OO1.

Task Standard: Boundary points for isolation and drains for CSP A are determined.

Required Materials: Provide following references to candidate NMP-AD-003, Equipment Clearance and Tagging Ver. 14.0 NMP-AD-003-002 Tagout Standards Ver. 7.0 P&lD 1X4DB131 Ver. 35.0 Provide to candidate if requested.

1 X4DROO3 Ver. 1.0 Fill and Vent Diagram For Containment Spray System General

References:

none Time Critical Task: No Validation Time: 45 minutes 2

Performance Information Critical steps denoted with an asterisk References NMP-AD-003, NMP-AD-003-002, and P&ID 1 X4DB1 31.

Standard: Candidate uses references.

Comment:

Determines the following components and positions are required to isolate and drain fluid boundary for CSP A.

Standard:

• Candidate correctly identifies the listed points to tag out CSP as listed below.

• The ones in BOLD are the critical points.

• The description should describe valve function.

• The description listed is expected description.

• The lineup description is listed in parentheses.

• The additional drains may be added but are not required.

3

Component Description Required Position Number 1-HV-9001A CSP A Pump Discharge Isolation Valve CLOSED (CNMT SPRAY ISO) 1-HV-9017A CSP A RWST Suction Isolation Valve CLOSED (CNMT SPRAY PUMP A RWST SUCT ISO VLV) 1-HV-9003A CSP A CNMT Sump Suction Isolation CLOSED Valve (CNMT SPRAY PUMP A CNMT SUMP SUCT ORC) 1 -1 206-U4-1 1 5 1 HV-9003A Bypass Line Isolation Valve CLOSED (CNMT SPRAY PUMP TRAIN A SUMP SUPPLY HV 9003A BYP) 1-1206-U4-006 CSP A RWST Test line Isolation Valve CLOSED (CNMT SPRAY PUMP TRAIN A TEST FLOWPATH ISOLATION) 1-1206-U4-034 CSP A Discharge to Eductor Isolation CLOSED Valve (CNMT SPRAY SPRAY ADD TK DISCH ISO TO EDUCTOR 1) 1-1206-U4-109 CSP A Pump Casing Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE CASING DRAIN) 1-1206-U4-112 CSP A Pump Casing Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION CASING DRAIN) 1-1206-U4-108 CSP A Pump Casing Vent Valve UNFLANGEIOPEN or (CNMT SPRAY PUMP TRAIN A CASE VENT)

UNCAP/OPEN 1-1206-X4-108 CSP A Header Vent Valve UNCAP/OPEN (CNMT SPRATY HEADER TRAIN A VENT) 1 -1 206-U4-002 CSP A Suction Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION FLOOR DRAIN ISO) 1-1206-X4-005 CSP A RWST Supply Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A RWST SUPPLY DRN TO FLOOR) 1-1206-X4-009 CSP A Suction Vent Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION PRESS TEST ROOT) 4

1-1 206-X4-026 CSP A Discharge Drain Valve UNCAP/OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE LINE DRAIN) 1-1 206-X4-01 3 CSP A Discharge to Eductor Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE TO EDUCTOR DRN) 1-1 206-X4-035 CSP A Header Drain Valve OPEN (CNMT SPRAY HEADER TRAIN A DRAIN) 1-1 206-U4-O1 1 CSP A Discharge Flush Conn Isolation UNFLANGE/OPEN or CLOSED (CNMT SPRAY PUMP TRAIN A DISCH FLUSH CONN ISO)

Comment:

Terminating cue: Candidate informs SS of completion of the identified points to Tagout Containment Spray Pump A or returns the cue sheet.

5

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Initial Conditions: Unit 1 is at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work are tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work are tagged under another referenced Tagout.

Initiating Cue: Determine the appropriate boundary points and required positions of components to isolate the fluid boundary and drain CSP A, 1-1206-P6-001.

Component Number Description Required Position

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SRO Admin Job Performance Measure C Facility: Vogtle Task No: V-LO-TA-63004 Task

Title:

Determine Tagging Requirements JPM No: V-NRC-JP-NMP-AD-003-HL17 K/A

Reference:

G2.2.13 R04.1 SRO4.3 Examinee: NRC Examiner:

Facility Evaluator: Date:_______________

Method of testing:

Simulated Performance Actual Performance Classroom 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 at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work are tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work is tagged under another referenced Tagout.

Initiating Cue: Determine the appropriate boundary points and required positions of components to isolate the fluid boundary and drain CSP A, 1-1206-P6-OO1.

Determine the Tech Spec LCO(s), required actions, and completion times (if any) that result from authorizing the given tagout.

Task Standard: Boundary points for isolation and drains for CSP A are determined. LCO, required actions, and completion times are determined.

Required Materials: Provide following references to candidate NMP-AD-003, Equipment Clearance and Tagging Ver. 14.0 NM P-AD-003-002 Tagout Standards Ver. 7.0 P&lD 1X4DB131 Ver. 35.0 Tech Specs Provide to candidate if requested.

1 X4DROO3 Ver. 1.0 Fill and Vent Diagram For Containment Spray System General

References:

none Time Critical Task: No Validation Time: 45 minutes 2

Performance Information Critical steps denoted with an asterisk References NMP-AD-003, NMP-AD-003-002, and P&ID 1 X4DB1 31.

Standard: Candidate uses references.

Comment:

Determines the following components and positions are required to isolate and drain fluid boundary for CSP A.

Standard:

• Candidate correctly identifies the listed points to tag out CSP as listed below.

• The ones in BOLD are the critical points.

• The description should describe valve function.

• The description listed is expected description.

• The lineup description is listed in parentheses.

• The additional drains may be added but are not required.

3

Component Description Required Position Number 1-HV-9001A CSP A Pump Discharge Isolation Valve CLOSED (CNMT SPRAY ISO) 1-HV-9017A CSP A RWST Suction Isolation Valve CLOSED (CNMT SPRAY PUMP A RWST SUCT ISO VLV) 1-HV-9003A CSP A CNMT Sump Suction Isolation CLOSED Valve (CNMT SPRAY PUMP A CNMT SUMP SUCT ORC) 1 -1 206-U4-1 1 5 1 HV-9003A Bypass Line Isolation Valve CLOSED (CNMT SPRAY PUMP TRAIN A SUMP SUPPLY HV 9003A BYP) 1 -1 206-U4-006 CSP A RWST Test line Isolation Valve CLOSED (CNMT SPRAY PUMP TRAIN A TEST FLOWPATH ISOLATION) 1-1206-U4-034 CSP A Discharge to Eductor Isolation CLOSED Valve (CNMT SPRAY SPRAY ADD TK DISCH ISO TO EDUCTOR 1) 1-1206-U4-109 CSP A Pump Casing Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE CASING DRAIN) 1-1206-U4-112 CSP A Pump Casing Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION CASING DRAIN) 1-1206-U4-108 CSP A Pump Casing Vent Valve UNFLANGEIOPEN or (CNMT SPRAY PUMP TRAIN A CASE VENT)

UNCAP/OPEN 1-1206-X4-108 CSP A Header Vent Valve UNCAP/OPEN (CNMT SPRATY HEADER TRAIN A VENT) 1-1206-U4-002 CSP A Suction Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION FLOOR DRAIN ISO) 1-1206-X4-005 CSP A RWST Supply Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A RWST SUPPLY DRN TO FLOOR) 1-1 206-X4-009 CSP A Suction Vent Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION PRESS TEST ROOT) 4

1-1 206-X4-026 CSP A Discharge Drain Valve UNCAP/OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE LINE DRAIN) 1-1 206-X4-O1 3 CSP A Discharge to Eductor Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE TO EDUCTOR DRN) 1-1 206-X4-035 CSP A Header Drain Valve OPEN (CNMT SPRAY HEADER TRAIN A DRAIN) 1-1 206-U4-O1 1 CSP A Discharge Flush Conn Isolation UNFLANGE/OPEN or CLOSED (CNMT SPRAY PUMP TRAIN A DISCH FLUSH CONN ISO)

Comment:

• Candidate determines the Tech Spec LCO(s), required actions, and completion times.

Standard: Candidate determines the following (bolded items are critical):

LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s*

train inoperable, spray train to OPERABLE status. AND 6 days from discovery of failure to meet the LCO*

B. One containment B.1 Restore containment 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 5

CONDITION REQUIRED ACTION COMPLETION TIME cooling train inoperable, cooling train to OPERABLE status. AND 6 days from discovery of failure to meet the LCO C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time notmet. AND C.2 Be in MODE 5. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> For the VEGP Unit 2 June 23, 2008 entry into Technical Specification 3.6.6, the Containment Spray Pump B may be inoperable for a period not to exceed 7 days.

Terminating cue: Candidate informs SS of completion of the identified points to Tagout Containment Spray Pump A or returns the cue sheet.

6

Verification of Completion Job Performance Measure No. V-N RC-JP-NMP-AD-003-HL1 7 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:_______________________________

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

7

Initial Conditions: Unit 1 is at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work are tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work is tagged under another referenced Tagout.

Initiating Cue: Determine the appropriate boundary points and required positions of components to isolate the fluid boundary and drain CSP A, 1-1206-P6-OO1.

Determine the Tech Spec LCO(s), required actions, and completion times (if any) that result from authorizing the given tagout.

Component Number Description Required Position

0 0

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RO SRO Job Performance Measure D Facility: Vogtle Task No: N/A Task

Title:

Determine Minimum Protective Clothing Requirements and Total Projected Dose, and Determine if task can be completed without exceeding any Radiological Limits JPM No: V-NRC-JP-00930-HL-17 K/A

Reference:

G2.3.7 (3.5 / 3.6)

Examinee:

NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Perlormance Actual Performance Classroom Simulator Plant

. Read to the examinee:

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

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

Initial Conditions: Unit 1 is at 100% power.

You have been assigned to close and danger tag 1-1204-U4-111 in Unit 1 containment.

You have been briefed by HP on the limitations of RWP 12-0101.

HP has permitted the minimum protective clothing requirements stated in the RWP.

Your accumulated dose for this year to date is 960 mrem.

The TOTAL round-trip TRANSIT dose will be 6 mrem.

The TOTAL time at the job site will be 5 minutes.

Assume neutron dose exposure is negligible.

Initiating Cue: Using RWP 12-0101 and the survey map of the Unit 1 containment work area, determine and document in the table below:

a. Your protective clothing requirements.

b. Your projected total gamma dose.

c. If you can or cannot perform the task without exceeding any limits. If not, then state the reason.

Protective clothing requirements Projected total gamma dose (CIRCLE ONE)

Can you complete this task without exceeding any limits?

YES NO REASON, if applicable 2

Task Standard: Upon successful completion of this JPM, the examinee will correctly:

1. Identify the protective clothing requirements.

2. Calculate the projected total gamma dose.

3. Determine if the task can be performed without exceeding any limits, and if not, then state the reason.

Required Materials: Calculator Containment survey map RWP 12-01 01 NMP-HP-001, Radiation Protection Standard Practices General

References:

None Time Critical Task: No Validation Time: 15 minutes 3

Performance Information Critical steps denoted with an asterisk Determine protective clothing requirements.

Refer to RWP 12-0101 Protective Clothing Requirements, which states the minimum requirements for a C zone are booties, gloves, and a lab coat.

Cue: If asked if the dress requirements were changed per HP direction, state See initial conditions.

Standard: Correct protective clothing requirements determined.

Comment:

Calculate projected total gamma dose.

Using survey map, a dose rate of 84 mrem/hour at the valve is determined.

The tagging task will take 5 minutes.

84 mrem/hour (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> /60 minutes) (5 minutes) = 7 mrem [no range on calculated value]

Transit dose of 6 mrem is added to calculated dose.

7 mrem + 6 mrem = 13 mrem [no range on calculated value]

Standard: Projected total dose calculated to be 13 mrem.

Comment:

4

Determine if the task can be performed without exceeding any limits From NMP-HP-OO1, the admin annual dose limit is 1000 mrem.

Total calculated annual dose would be 960 mrem + 1 3 mrem = 973 mrem (annual limit exceeded)

RWP 12-0101 task dose rate limit is 80 mrem/hour. Dose rate at valve is 84 mrem/hour on the survey map (task dose rate limit is exceeded).

RWP 12-0101 task dose limit is 15 mrem. Calculated dose received is 13 mrem (task dose limit is not exceeded)

NOTE TO EXAMINER: Examinee may indicate that 13 mrem exceeds the task dose limit since HP briefings require workers to notify HP when they reach 80% of their task dose limit (12 mrem for this task). This response is acceptable.

Standard: Determination is made that the task can NOT be performed without exceeding a limit.

Comment:

State the reason that the task was NOT permitted.

Examinee identifies that the RWP task dose rate limit is exceeded (dose rate at valve is 84 mrem/hour with an RWP task dose rate limit of 80 mrem/hour)

NOTE TO EXAMINER: Examinee may indicate that 13 mrem exceeds the task dose limit since HP briefings require workers to notify HP when they reach 80% of their task dose limit (12 mrem for this task). This response is acceptable.

Standard: Correct reason is provided for why the task can NOT be performed.

Comment:

Terminating cue: Student returns initiating cue sheet.

5

KEY q3ooties Protective clothing requirements oves Lab Coat Projected total gamma dose 13 mrem (CIRCLE ONE)

Can you complete this task YES without exceeding any limits?

T?WP tas/ tiose rate limit of 80 mrem/Ftour Lc eaceedeé REASON, if applicable NOTE: Examinee may indicate that 13 mrem exceeds the task dose limit since HP briefings require workers to notify HP when they reach 80% of their task dose limit (12 mrem for this task). This response is acceptable.

6

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Initial Conditions: Unit 1 is at 100% power.

You have been assigned to close and danger tag 1 -1 204-U4-1 1 1 in Unit 1 containment.

You have been briefed by HP on the limitations of RWP 12-0101.

HP has permitted the minimum protective clothing requirements stated in the RWP.

Your accumulated dose for this year to date is 960 mrem.

The TOTAL round-trip TRANSIT dose will be 6 mrem.

The TOTAL time at the job site will be 5 minutes.

Assume neutron dose exposure is negligible.

Initiating Cue: Using RWP 12-0101 and the survey map of the Unit 1 containment work area, determine and document in the table below:

a. Your protective clothing requirements.

b. Your projected total gamma dose.

c. If you can or cannot perform the task without exceeding any limits. If not, then state the reason.

Protective clothing requirements Projected total gamma dose (CIRCLE ONE)

Can you complete this task without exceeding any limits?

YES NO REASON, if applicable 8

current user V.is 9 Kenneth Aç4ervisor) on Plant Vo tle RadiS 23 00 ile View Search iy PCEIPCR Admin User Routines Help evA Upper Overview (1 RXA) (316) jDose Rate Gamma G/A (mrem/hr) it>

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j 261 Gy# 146131 02113/2012 1337 21236 - _JS Approved 1 220 Subnitted By Hall Roert AuJ 210 Purpose Specific Survey

? U-1CTMTCage Aj 197 Remarks Ui ECCS VentinQ Dcor Posted B [184 J Power 100 ci 171 !Rx Mode 1-12 inj Lvi 0 iVoid Lvi 0 System System Running Component N/A Max Rate 21 mrem?hr Max Cntrn 1000 dcm100 cm2 S Dose 4 10 12O4-X4-41O/41j 14 mrem/hr 67 mrem/hr

[2o4-U4-19o/2cOJ 70 mrem/hr

[2o4-U41 1 1/285 84 mrem/hr

Plant Vogtle Unit Radiation Work Permit ACTIVE 0 MINOR WORK TASK, OPS TOURS AND SURVEILLANCES IN UNIT ONE CONTAINMENT.

Description Location GENERAL ENTRY INTO UNIT I CONTAINMENT HP Coverage Authorization Briefing 12/31/2012 Start Date 1/1/2012 End Date 11:59:00 PM CONTINUOUS SINGLE USE SINGLE USE Job Supv. I KOCHERY Ext. 3229 Radiological Conditions Tasks AIRBORNE LEVELS: > 0.3 DAC PARTICULATE AND Description

[ODINE, >1.0 DAC NOBLE GAS [

CONTAMINATION: > 500,000 DPM/100CM2 BETA/GAMMA, SURVEILLANCES/TRANSMITTER CALS 15 80

>20 DPM/IOOCM2 ALPHA WALKDOWNS/INSPECTIONS 15 80 RAD LEVELS:> 1000 MREM/HR LLRTS 15 80 Dosimetry HP JOB COVERAGE 15 80 OSLD & ED, RELOCATE ONLY PER HP CORRECTIVE MAINTENANCE 15 80 -

Protective Clothing Requirements PREVENTATIVE MAINTENANCE 15 80 MINIMUM REQUIREMENTS IN C ZONE S SUPPORT/TAGGING BOOTIES/GLOVES/LAB COAT 15 80 DRESS REQ. MAY BE CHANGED AS HP DIRECTS Respirators NP PAPR SCBA Usage is Conditional per HP Instructions

• FOLLOW ALL HP INSTRUCTIONS. STAY IN DESIGNATED LOW DOSE AREAS WHENEVER POSSIBLE.

NO ENTRY BEHIND BIOSHIELD IN RX MODES 1 OR 2.

• ALL PERSONNEL ARE TO REMAIN IN LINE OF SIGHT OF HP TECH WHEN RX IS IN MODES 1 OR 2.

ALARA IS TO BE NOTIFIED IF ANY ONE OF THE FOLLOWING UNEXPECTED RAD CONDITIONS ARE ENCOUNTERED: 1) AREAS > OR = 250 MREM/HR GAMMA (OR)

2) AREAS > OR = 100 MREM/HR NEUTRON WHEN COMPOSITE SURVEYS CAN NOT BE USED AND A NEUTRON SURVEY INSTRUMENT IS USED. *AVOID HOT SPOTS.

YOUR ENTRY SIGNATURE ON DATA SHEET 1 OF 00303-C INDICATES THAT YOU UNDERSTAND THAT MATERIAL TAKEN INTO CONTAINMENT MUST BE: (A) APPROVED (A PERMIT ISSUED PER PROCEDURE 00309-C) TO BE LEFT IN CONTAINMENT, OR

• (B) BE ATTENDED AT ALL TIMES AND CAPABLE OF BEING REMOVED IN ONE TRIP.

YOUR EXIT SIGNATURE ON DATA SHEET 1 OF 00303-C SIGNIFIES THAT THERE IS NO LOOSE DEBRIS PRESENT IN ALL AREAS THAT YOU ENCOUNTERED THAT COULD BE TRANSPORTED TO THE CONTAINMENT SUMP AND CAUSE RESTRICTION OF THE ECCS PUMP SUCTIONS.

IF THE ROBOT IS TO BE USED FOR INSPECTION INSIDE THE BIOSHIELD, THE POTENTIAL EXISTS THAT THE ROBOT MAY BE TIPPED OVER DUE TO THE FORCE OF BLOWN AIR FROM THE CONTAINMENT CIRCULATOR FANS.

• t\5 A PRECAUTION, HP SHOULD REQUEST FOR OPERATIONS TO TURN OFF THE CONTAINMENT CIRCULATOR 45 IN THE AFFECTED INSPECTION AREA WHENEVER THE ROBOT IS TO BE USED INSIDE THE BIOSHIELD.

• THE FANS SHOULD REMAIN OFF UNTIL THE INSPECTION IS COMPLETE.

THE UNIT 1 CIRCULATOR FAN NUMBERS ARE AS FOLLOWS: I 1503B7008 WEST BIOSHIELD ENTRANCE, 1 1503B7004 EAST BIOSHIELD ENTRANCE, 1 1503B7006 BETWEEN LOOPS 1 & 4, AND 1 1503B7002 BETWEEN LOOPS 2

& 3.

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• SRO Admin Job Performance Measure E Facility: Vogtle Task No: V-LO-TA-40005 Task

Title:

Classify an Emergency Event, Complete EN Form JPM No: V-NRC-JP-NMP-EP-11O-HLI7 K/A

Reference:

G2.4.41 SRO4.6 Examinee:

NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance Classroom Simulator Plant I

Read to the examinee:

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.

THIS IS A TIME CRITICAL JPM Initial Conditions: - Unit I is in Mode 3 following a reactor trip from power 20 minutes ago:

SG # I has developed a 375 gpm SGTR, the crew actuated SI and has entered 19030-C, E-3 Steam Generator Tube Rupture.

I RE-005 and I RE-006 are both indicating 2.6 E+6 mrlhr.

The Unit Operator after investigating a Main Steam Safety Leaking annunciator has just reported a Code Safety has lifted for SG # I and will NOT reseat.

The Outside Area Operator has confirmed steam blowing out of the safety valve.

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

Stability class D, no precipitation.

RE-12839C is in HIGH alarm.

- WebEOC is not functional at all facilities.

- The ENN communicator has completed roll call.

Initiating Cue: Complete Checklist 1-Classification Determination of NMP-EP-1 10, Emergency Classification Determination and Initial Action to determine the HIGHEST emergency classification level, (Do NOT use ED judgment as the basis for classification)

AND Complete Figure 1-Emergency Notification Form of NMP-EP-1 11, Emergency Notifications.

2

Task Standard: A Site Area Emergency declared with Emergency Notification Form (Figure 1) completed. No PARs are required.

Required Materials: 1. NMP-EP-1 10, Emergency Classification Determination Ver 1.0

2. NMP-EP-1 11, Emergency Notifications Ver 4.0 Signoff Checklist 2 steps I through 5.

3. NMP-EP-112, Protective Action Recommendations Ver 1.0 General

References:

None Time Critical Task: YES Validation Time: 15 minutes separately for both Classification Determination and Emergency Notification Form completion (30 minutes total).

Critical items on Emergency Notification Form are per Procedure 60201-C, Simulator Training & Documentation, which specifies lines required to be done correctly to be satisfactory performance for Emergency Preparedness NRC Performance Indicator.

3

Performance Information Cnt:cal steps denoted with an astensk NMP-EP-1 I 0 Checklist I CLASSIFICATION DETERMINATION START TIME CRITICAL FOR CLASSIFICATION DETERMINATION________

I . Determine the appropriate Initiating Condition Matrix for the classification of the event based on the current operating mode:

I HOT IC/EAL Matrix Evaluation Chart (Go to step 2) to evaluate the Barriers D COLD IC/EAL Matrix Evaluation Chart (Go to step 3)

Standard: HOT IC/EAL checked and initialed by the ED.

Comment:

Evaluate the status of the fission product barrier using Figure 1 Fission Product Barrier Evaluation.

a. Select the condition of each fission product barrier:

LOSS POTENTIAL LOSS INTACT Fuel Cladding Integrity D D E Reactor Coolant System l1 D D Containment Integrity IE D

b. Determine the highest applicable fission product barrier Initiating Condition (IC):

(select one) D FG1 E FSI D FAI D FUI D None Standard: LOSS of RCS Barrier and LOSS of Containment Integrity barriers checked.

Fuel Cladding Integrity checked as INTACT.

Comment:

I 4

3. Evaluate and determine the highest applicable IC/EAL using the Matrix Evaluation Chart identified in step 1, then go to step 4.

IC# FS1 or D None Standard: Figure 3, HOT Initiating Matrix chosen and EAL FS1 filled in IC# line.

Comment:

• 4 Check the highest emergency classification level identified from either step2bor3.

Classification Based on IC# Classification Based on lC#

D General 1] Alert l1 Site-Area FSI D NOUE D None N/A Remarks (Identify the specific EAL, as needed):

Standard: Site-Area Classification block is checked and lC# FSI filled in.

Comment:

5

5. Declare the event by approving the Emergency Classification.

Date: I I Time:

Emergency Director Standard: Signature, Date and Time filled in.

STOP TIME CRITICAL FOR CLASSIFICATION DETERMINATION_________

Comment:

6. Obtain Meteorological Data (not required prior to event declaration):

Wind Direction (from) Wind Speed 5.8 mph Stability Class D Precipitation None Standard: Candidate obtains Met Tower Data from Initial Conditions.

Comment:

7. Initiate Checklist 2, Emergency Plan Initiation Standard: Complete steps 6 and 7 of Checklist 2, Emergency Plan Initiation.

Comment:

START TIME CRITICAL FOR EMERGENCY NOTIFICATION FORM________

NMP-EP.-1 11, Attachment 1, Part I Guidance for Initial EN Form Completion Standard: Candidate selects NMP-EP-I 11 Attachment I, Part I Comment:

6

Item 1: Message Number is automatically assigned during the transmittal process if using the electronic EN Form tool. Message numbers are sequential for the duration of the Event.

Standard: Block A (Drill) is checked.

Comment:

• 2. Item 2: INITIAL will be checked for any notification associated with the declaration andlor change of an emergency classification.

Standard: Block A (Initial) is checked.

Comment:

I

3. Item 3: SITE Confirm the correct site is displayed. The site location is automatically completed based on prior selections.

CONFIRMATION PHONE NUMBER: Select from the drop down list Standard: Vogtle is already filled in.

Comment:

7

• 4 Item 4: EMERGENCY CLASSIFICATION EAL NUMBER: Select from the drop down list (N/A for Manual method)

EVENT DESCRIPTION: Confirm the brief description of the initiating conditions for the emergency classification declared is auto completed based on the EAL number selected. The event description block cannot be edited. Additional information or information relative to competing events should be included on line 13, REMARKS.

(N/A for Manual method)

Standard: SITE AREA EMERGENCY block checked. BASED ON EAL # FS1 filled in.

EAL description: Loss or Potential Loss of ANY Two Barriers.

Comment:

• 5 Item 5: PROTECTIVE ACTION RECOMMENDATIONS Check Block A NONE Standard: Block A NONE is checked.

Comment:

• 6. Item 6: EMERGENCY RELEASE NOTES: 1. The Emergency Director has the discretion to declare that a radiological release is occurring based on plant conditions that indicate a release is in progress. (i.e., A Steam Generator Tube Rupture with an ARV lifting, site specific effluent radiation monitor readings, etc.)

2. Information for items 6, 7, and 9 are obtained from dose assessment (e.g., Dose Assessment Staff in either the TSC or the EOF, as appropriate).

8

!i THEN:

Dose assessment results (automated or manual) have been completed indicate an emergency radiological release is underway Check . Is Occurring At least one effluent monitor* is in alarm, NJ completed dose Check Is Occurring projection results (automated or manual) are not available*

Elevated indications do not exist on any effluent monitor* Check . None Dose assessment results (automated or manual) have been completed A1U2 indicate an emergency radiological release is NOT underway Check .

None Dose assessment results indicate an emergency radiological release occurred previously is no longer underway. Check . Has Occurred

• Applicable monitors are listed in Table 3 Standard: Block B (Is Occurring) is checked.

Comment:

7. Item 7: RELEASE SIGNIFICANCE (Monitors are listed in table 3)

Use the following table to determine the release significance:

jf an abnormal plant condition exists AND: THEN:

Elevated indications do not exist on any effluent monitor* Check . Not applicable Elevated indications exist on at least one effluent monitor* j4fJ no effluent monitors are in alarm AND completed dose assessment results Check Under evaluation (automated or manual) are not available Item 6B or 6C is marked and NO effluent monitor is or has been in Check Within normal operating alarm OR has exceeded the specified threshold limits 6B or 6C is marked and ANY effluent monitor is or has been in Check Above normal alarm OR has exceeded the specified threshold operating limits Dose assessment results indicate an emergency radiological release Check . Above normal operating occurred previously is no longer underway. limits

• Applicable monitors are listed in Table 3 Standard: Block C Above normal operating limits, is checked.

Comment:

9

Item 8: EVENT PROGNOSIS Indicative of plant conditions and the ability to prevent core damage (e.g., improving, stable, or degrading).

Mark box Improving if mitigation efforts appear successful, progressing toward termination.

Mark box Stable if escalation to a higher classification is unlikely based on current conditions.

Mark box j Degrading if escalation to a higher emergency classification or PAR change is likely.

Standard: Block B (Stable) is checked.

Comment:

NOTE: 1. All reported meteorological data should be 15 minute average data.

Data provided for meteorological parameters should be consistent with data utilized for PARs dose projections reported in line 16, if applicable.

2. Inconsistencies in meteorological data utilized for dose projections and the meteorological data reported on emergency notification forms can result in discrepancies in dose assessments performed by SNC and applicable State and Federal agencies.

• 9 Item 9: METEOROLOGICAL DATA Record the 15-minute averaged Wind Direction from, Wind Speed and Precipitation values and check the appropriate Stability Class (AT). Sources for meteorological data are listed in Table 4.

Standard: Met Tower Data given in Initial Conditions. Wind direction is from 69 degrees at a speed of 5.8 mph. Stability class D, with no precipitation. Only direction and speed are critical.

Comment:

10

• 10. Item 10: DECLARATION or TERMINATION Enter the time and date (mmlddlyy) when the current emergency classification was declared or terminated.

Standard: Block A (Declaration) checked. Time and Date filled in from Checklist 1, NMP-EP-1 10, Emergency Classification Determination.

Comment:

• 11. Item 11: AFFECTED UNIT(S) Check the affected unit or ALL block if both units are affected by the EAL indicated in item 4. For events involving equipment that is common to both units, ALL should be selected.

Standard: Block 1 checked.

Comment:

NOTE: The unaffected units status is not required for initial notifications.

However, the unaffected units status is required for follow-up notifications.

12. Item 12: UNIT STATUS IF the affected unit is operating, THEN indicate the % power. If the affected unit is shutdown, then enter the time (HH:MM) and date of the shutdown.

Standard: Block A (Unit 1) checked. Appropriate power and shutdown time (20 minutes ago) filled in.

No information for Unit 2 is given, no information required.

Comment:

11

1 G 3 Item 13: REMARKS Standard: None filled in.

Comment:

NOTE: Lines 14 through 16 (FOLLOW-UP ACTIONS) should be completed and transmitted as soon as dose projection information is available after the onset of any release otherwise, GO to Step 17 APPROVAL.

14. Item 14: RELEASE CHARACTERIZATION

15. Item 15: PROJECTION PARAMETERS

16. Item 16: PROJECTED DOSE Standard: Items 14 16 are left blank.

Comment:

STOP TIME CRITICAL FOR EMERGENCY NOTIFICATION FORM________

• 17. Item 17: Review and Approval

a. Manual Form IF possible, obtain a peer check of the completed form. The Emergency Director must approve the form. Verbal authorization may be given to a delegate such as the EOF Manager to sign on behalf of the ED.

Standard: Signature Time and Date filled in within 15 minutes of Classification Declaration Block on Line 10.

Comment:

12

_________Hours KEY Darkened boxes and highlighted text are critical Figure 1 Emergency Notification Form (page 1 of 2)

V DRILL B ACTUAL EVENT MESSAGE#

1

2. INITIAL B FOLLOW-UP NOTIFICATION: TIME DATE/I AUTHENTICATION #_____

3. SITE: Vogtle Confirmation Phone #1 -706-826-3562(SIML

4. EMERGENCY CLASSIFICATION: j UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY BASED ON EAL# FS1 EAL DESCRIPTION Loss or Potential Loss of Two Barriers

5. PROTECTIVE ACTION RECOMMENDATIONS:

I NONE EVACUATE SHELTER I Advise Remainder of EPZ to Monitor Local Radio/TV Stations/Tone Alert Radios for Additional Information and Consider the use of KI (potassium iodide) in accordance with State plans and policy.

OTHER

6. EMERGENCY RELEASE: None Is Occurring Has Occurred

7. RELEASE SIGNIFICANCE: Not applicable jj Within normal operating NAbove normal operating Under limits limits evaluation

8. EVENT PROGNOSIS: Improving Stable Degrading

9. METEOROLOGICAL DATA: Wind Direction from _ degrees* Wind Speed mph*

(*May not be available for Initial Notifications)* Precipitation iiQii* Stability Class* N II

10. DECLARATION TERMINATION Time Checklist 1 line 5 Date checklist 1 date I /

11. AFFECTED UNIT(S): II1

12. UNIT STATUS: Ui 0% Power Shutdown at Time T -20 min_ Date yj (Unaffected Unit(s) Status Not Required for N Initial Notifications) U2  % Power Shutdown at Time Date II

13. REMARKS: None FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)

EMERGENCY RELEASE DATA NOT REQUIRED IF LINE 6 A IS SELECTED.

14. RELEASE CHARACTERIZATION: TYPE: Elevated Mixed Ground UNITS: Ci j Ci/sec j jiCi/sec MAGNITUDE: Noble Gases:__________ Iodines:___________ Particulates:__________ Other:

FORM: Airborne Start Time Date I/Stop Time Date II Liquid Start Time Date I/Stop Time Date /1 1 5. PROJECTION PARAMETERS: Projection period: Estimated Release Duration Projection performed: Time Date /1 Accident Type:

16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem)

Site boundary 2 Miles 5 Miles 10 Miles

17. APPROVED BY: Title Time .............I jf NOTIFIED RECEIVED BY:

BY: Time (To be completed by receiving organization) 13

Verification of Completion Job Performance Measure No. V-NRC-JP-NMP-EP-1 I 2-HLI 7 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:_______________________

Response:_____________________

Result: Satisfactory/Unsatisfactory Examiners signature and date:

14

THIS IS A TIME CRITICAL JPM Initial Conditions: -

Unit I is in Mode 3 following a reactor trip from power 20 minutes ago:

SG # I has developed a 375 gpm SGTR, the crew actuated SI and has entered 19030-C, E-3 Steam Generator Tube Rupture.

I RE-005 and I RE-006 are both indicating 2.6 E+6 mrlhr.

The Unit Operator after investigating a Main Steam Safety Leaking annunciator has just reported a Code Safety has lifted for SG # I and will NOT reseat.

- The Outside Area Operator has confirmed steam blowing out of the safety valve.

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

- Stability class D, no precipitation.

- RE-I 2839C is in HIGH alarm.

- WebEOC is not functional at all facilities.

- The ENN communicator has completed roll call.

Initiating Cue: Complete Checklist 1-Classification Determination of NMP-EP-1I0, Emergency Classification Determination and Initial Action to determine the HIGHEST emergency classification level, (Do NOT use ED judgment as the basis for classification)

AND Complete Figure 1-Emergency Notification Form of NMP-EP-1 II, Emergency Notifications.