ML102870093

Initial Exam 2010-301 Final Administrative JPMs

ML102870093
Person / Time
Site:	Vogtle
Issue date:	04/12/2010
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
50-424/10-301, 50-425/10-301
Download: ML102870093 (61)

Text

RO Job Performance Measure A Facility:

Vogtle Task No:

V-LO-TA-37004 Task

Title:

Monitor I Evaluate CSFSTs Subcriticality JPM No:

V-NRC-JP-19200-005 K/A:

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

Required Materials:

19200-C, F-0 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. Document your evaluation of CSFSTs on 19200-C.

Time Critical Task:

No Validation Time:

10 minutes

Performance Information Critical steps denoted with an asterisk

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

Standard:

Properly evaluates Subcriticality to be ORANGE status.

Continues with evaluation of the other CSFST status trees.

Comment:

• Sheet 2 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 CSFSat(GREEN)

Standard:

Properly evaluates Core Cooling to be GREEN status (sat)

Continues with evaluation of the other CSFST status trees.

Comment:

2

• Sheet 3 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)

Standard:

Properly evaluates Heat Sink to be YELLOW status.

Continues with evaluation of the other CSFST status trees.

Comment:

• Sheet 4 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)

Standard:

Properly evaluates Integrity to be ORANGE status.

Continues with evaluation of the other CSFST status trees.

Comment:

3

• Sheet 5 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)

Standard:

Properly evaluates Containment to be GREEN status.

Continues with evaluation of the other CSFST status trees.

Comment:

• Sheet 6 Evaluates F- 0.6, the Inventory Status Tree PRZR level less than 92% - NO At least one RCP running NO RVLIS indicates upper head greater than 98% full YES Go to 19261-C (YELLOW)

Standard:

Properly evaluates Inventory to be YELLOW status.

Comment:

• 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:

Terminating cue:

Student returns initiating cue sheet 4

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

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

5

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.

Initiating Cue:

The SS has directed you to use 19200-C to evaluate all CSFSTs and identify any required transition. Document your evaluation of CSFSTs on 19200-C.

Channel/Loop ChannelJLoop Channel/Loop Channel!Loop Parameter 1

2 3

4 PRNI 0%

0%

0%

0%

IR SUR

+0.1 DPM

+0.13 DPM IR NI 3.Ox10 3.2x10 SRSUR ODPM ODPM RCS WR Pressure 1980 psig 2000 psig 1990 psig 2010 psig Core Exit TICs 329 F RCP status Off Off Off Off RVLIS Full Range 100%

100%

100%

100%

RVLIS 100%

100%

100%

100%

Upper Head SGNRLeveI 0%

0%

0%

0%

AFWfIow 2O5GPM OGPM 21OGPM 200GPM SG Pressure 950 psig 26 psig 973 psig 987 psig RCS WR Cold Leg Temperature 540 F 261 F 538 F 541 F CNMT Pressure 0 psig 0 psig 0 psig 0 psig CNMT Emergency Sump Levels 0 inches 0 inches CNMT Radiation 24 mR I Hr 31 mR I Hr PRZR level 100%

100%

100%

RO Job Performance Measure B Facility:

Vogtle Task No:

V-LO-TA-1 7007 Task

Title:

Perform Manual QPTR Calculation JPM No:

V-NRC-JP-14915-001 K/A:

G2.1.37 (RD 4.3)

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 unit is at 100% power. The current tilt deviation from Reactor Engineering is 0.

Task Standard:

QPTR is correctly calculated per 14915-1 Data Sheet 7.

Required Materials:

1491 5-1, Data Sheet 7 Unit 1 Plant Technical Data Book Tab 5.0 Calculator Initiating Cue:

You have been directed to perform 14915-1 Data Sheet 7 to manually calculate QPTR using the data supplied.

Time Critical Task:

No Validation Time:

15 minutes 1

Performance Information Critical steps denoted with an asterisk

• Completes sheet 2 of datasheet 7 of 14915-1 Standard:

All blanks on datasheet 7 are filled in and data = answer key Comment:

Terminating cue:

Student returns initiating cue sheet 2

DATA SHEET 7 (ANSWER KEY)

DATE TIME NI Channel Detector Current Factor*

41 A

424 xl.117

=473.608(1) 42 A

380 xl.124

=427.120(1) 43 A

450 xl.005

= 452.250(1) 44 A

415 xl.113

=461.895(1)

Avg = 453.718(1)

QPTR (Upper) = Max(upper) = 1.04 (2)

Avg(upper)

NI Channel Detector Current Factor*

41 B

454 xl.072

=486.688(1) 42 B

395 xl.106

= 436.870(1) 43 B

460 xl.000

=460.000(1) 44 B

425 xl.084

= 460.700(1)

Avg = 461.065 (1)

QPTR (Lower) = Max(lower) = 1.06 (2)

Avg(lower)

QPTR = Max of QPTR(upper) or QPTR(Iower)

= 1.06 TILT DEVIATION

=0 (from Reactor Engineering if applicable)

COMPLETED BY:

Shift Supervisor Review:

I I

Initial Date Time

• Factor = Normalization Factor from Plant Technical Data Book tab 5.0 Note 1 = Calculations should be performed to 3 decimal places Note 2 = Round to 2 decimal places (if the 3rd decimal is 5 round up, if 3rd decimal is <5, round down) 3

Verification of Completion Job Performance Measure No:

V-NRC-JP-14915-OO1 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

4

Initial Conditions:

The unit is at 100% power. The current tilt deviation from Reactor Engineering is 0.

Initiating Cue:

You have been directed to perform 1491 5-1 Data Sheet 7 to manually calculate QPTR using the data supplied.

NI Channel Detector Current N41 A

424 mA N42 A

380 mA N43 A

450 mA N44 A

415 mA N41 B

454 mA N42 B

395 mA N43 B

460 mA N44 B

425 mA

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 K/A

Reference:

G2.2.13 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:

NSCW pump #4 on Unit 2 needs to be danger tagged to perform pump bearing repairs. The pump motor will not be pulled.

Task Standard:

Tagout hold points and required positions listed.

Required Materials:

1.

Plant Drawings 2X4DB133-1, 133-2, 134, 135-1, 135-2 2X3D-AA-DO3A, DO3B 2X3D-BA-AO1 F 2X3D-BD-KO4D, KO4Y 2.

NMP-AD-003, Equipment Clearance and Tagging General

References:

None Initiating Cue:

Determine the appropriate hold points and required positions of components to safely isolate NSCW pump 2-1202-P4-004.

Identification of K-2 links to clear control room alarms is not necessary.

Time Critical Task:

No Validation Time:

30 minutes 1

Performance Information Critical steps denoted with an asterisk Student references NMP-AD-003.

Standard:

NMP-AD-003 referenced by student.

Comment:

Determines the following components are positions are required to safely tagout NSCW Pump # 4 on unit 2.

2HS-1635A, NSCW Pump #4 Hand Switch, Pull-to-Lock 2HS-1635C, NSCW Pump #4 Transfer Switch Control Room 2BA03-11, NSCW Pump # 4 Motor Switchgear Breaker, in the Disconnect position.

2BBB-36, NSCW Pump #4 Discharge MOV Breaker, Off 2HV-11613, NSCW Pump # 4 Discharge MOV Hand Wheel, Close 2-1202-U4-A18, NSCW Pump #4 Discharge MOV Bypass Valve, Unlocked I Shut 2-1 202-X4-847, NSCW Pump # 4 Motor Cooler Vent Isolation, Uncapped I Open Standard:

Student correctly identifies the above listed positions to safely tag out the NSCW pump #4. The ones in BOLD are the critical points.

Comment:

Terminating cue:

Student informs SS of completion of the identified points to safely tag out NSCW pump # 4 or returns the cue sheet.

2

Verification of Completion Job Performance Measure No. V-RQ-JP-NMP-AD-003 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

3

Initial Conditions:

NSCW pump #4 on Unit 2 needs to be danger tagged to perform pump bearing repairs. The pump motor will not be pulled.

Initiating Cue:

Determine the appropriate hold points and required positions of components to safely isolate NSCW pump 2-1202-P4-004.

Identification of K-2 links to clear control room alarms is not necessary.

Component Number Noun Name Required Position

RO Job Performance Measure D Facility: Vogtle Task No: V-LO-TA-40003 Task

Title:

ENN Notification and Recall Security Alert Emergency JPM No: V-RQ-JP-91002-005 KJA

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 I Reactor has been manually tripped due to a validated security threat. An emergency has been declared and the Shift Manager has assumed the Emergency Director position.

Task Standard:

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

Required Materials:

Procedure 91002-C, Emergency Notifications, Checklist 4 Pre-filled out copy of 91002-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 I) perform a recall for a Security Emergency 2) a roll call in accordance with Checklist 4 and, 3) to transmit the ENN message.

Time Critical Task:

Yes Validation Time:

15 minutes 1

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 1 0.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:

Not applicable.

Comment:

Section I, EMERGENCY RESPONSE ORGANIZATION RECALL

• Step I 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)

CUE:

PLEASE USE THE SPEAKER PHONE AND TURN ON THE SPEAKER Activates the Primary emergency recall system for Security Emergency.

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

Enters Scenario ID {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.

Standard:

Pulls Primary Recall System packet from drawer and properly performs the steps for remote activation for a SECURITY emergency (White sheet)

Comment:

3

Step 2 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 Managers beeper should activate and display a predetermined emergency pager message. The number displayed on the pager for an actual emergency will be three 9s (999) and a call-in number. The number displayed on the pager for a security emergency will be three 6s (666) and a call-in number.

Standard:

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

Extension # 3652 rings shortly after recall system activation.

NOTE:

The student will have speak into the phone to get the system to properly respond. Then the candidate will have to go through a short menu to prevent multiple calibacks by the recall system.

Comment:

Step 5 Record date, time and name below after completing the Steps For Remote Activation as delineated within the posted system instructions.

Standard:

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.

Comment:

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 to fill out form, if using an outside line not to use a 9 and to use 9 is using plant extensions.

Standard:

Not applicable.

Comment:

Step 1.

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 Standard:

Not applicable.

Comment:

Step 2 Ensure that the following items are present:

a.

Emergency Response Telephone Directory (ERTD) b.

Log Book Standard:

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

Log Book is not applicable.

Comment:

5

Step 3 Perform a roll call.

a.

Press ** the ENN phone to ring ALL stations.

b.

States the following:

(select one)

THIS (IS I IS 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.

Standard:

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

Reads greeting statement with candidates name inserted.

Comment:

• Step 3.c Proceed with roll call in the following order, check box for responding agencies:

NOTE:

Allendale County will fail to respond, this will require the operator to pull out the sliding tray under the ENN phone and dial Allendale Counties 2 digit number that individually rings their station. After successfully identifying the number, Allendale County will respond.

D Burke County D

State of Georgia D

Aiken County D

Savannah River Site D

Allendale County D

State of South Carolina D

Barnwell County Standard:

Reads roll call for all 7 agencies.

NOTE:

The Simbooth operator will be on an ENN phone to respond. 6 of 7 agencies respond to the ENN call, Allendale Country will respond after dialing their 2 digit number.

Comment:

6Y

Step 3.d If multiple agencies fail to respond to the roll call in step c. above, perform steps

h. and i. below.

Standard:

Not applicable.

Comment:

Step 3.e 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.

Standard:

Proceeds to section III, Transmission of Notification Message.

Comment:

SECTION III, TRANSMISSION OF NOTIFICATION MESSAGE Reviews NOTES prior to Section Ill 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 Transmit the notification form via voice and facsimile in the following manner:

CUE:

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

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)

Standard:

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)

Comment:

8

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

• Line I 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:

South Carolina requests authentication for code word #27

• Line 3 Site, VOGTLE, confirmation phone # (706) 826-3652

• Line 4 Emergency Classification, Block B, Alert Based on EAL # HA7 EAL

Description:

Notification of an Airborne Attack Threat

• 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), Both (2)

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 9

CUE: Another ENN communicator will complete the roll call.

Standard:

Lines 1 through 17 areas highlighted in YELLOW must be read properly.

Comment:

Terminating cue:

Student returns initiating cue sheet 10

Verification of Completion Job Performance Measure No. V-RQJP-91OO2-OO5 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

11

TIME CRITICAL Initial Conditions:

Unit I Reactor has been manually tripped due to a validated security threat. An emergency has been declared and the Shift Manager has assumed the Emergency Director position.

Initiating Cue:

The Emergency Director has directed you to Perform the duties of the ENN Communicator and I) perform a recall for a Security Emergency 2) a roll call in accordance with Checklist 4 and, 3) to transmit the ENN message.

SRO Admin Job Performance Measure A Facility:

Vogtle Task No:

N/A Task

Title:

Perform Emergency Boration Flow Path Verification JPM No:

V-NRC-JP-14405-OO1 K/A:

G2.1.7 (SRO 4.7)

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:

RCS Tave is 300°F.

1-HV-8806 is danger tagged shut.

1-HV-0182 is danger tagged shut.

CCP-1 B is danger tagged in the PTL position.

All required actions of Technical Specifications for CCP-1 B have been taken.

All other powered components are operable.

All manual valves listed in figure 1 of 14405-1 are open or locked open as required.

VCT pressure is 30 psig 14225-1, Operations Weekly Surveillance Logs is active for the BAST and the RWST.

14705-1, Boron Injection Flow Rate Verification is active.

14811A-1 and 14811B-1, Boric Acid Transfer Pumps and Discharge Check Valves Inservice Test are both active.

14808A-1 and 14808B-1, Centrifugal Charging Pump and Check Valves 1ST and Response Time Test are both active.

RWST temperature is within limits per 14000-1, Operations Shift and Daily Surveillance Logs.

1

Task Standard:

1. 14405-1 is evaluated as unsatisfactory because 1 -HV-8438 (powered component) is commonto the 2 required flow paths.

2. TR 13.1.3 condition A identified.

Required Materials:

1. 14405-1, Boron Injection Flow Path Verification During Operation NOTE:

(Ensure step 4.1 is initialed)

2. Technical Requirements Manual Initiating Cue:

1. Complete surveillance procedure 14405-1, Boron Injection Flow Path Verification During Operation.

2. Based on your completed 14405-1, determine the required Technical Requirements Manual actions, if any. Record in step 7.4 of 14405-1.

Time Critical Task:

No Validation Time:

30 minutes 2

Performance Information Critical steps denoted with an asterisk 5.0 INSTRUCTIONS TEST STARTED DATE TIME MODE Standard:

Current date & time filled in, mode 4.

Comment:

NOTES Power operated valves (motor, air or solenoid) will be considered in the proper position if valves have power available and are capable of being repositioned to establish flow.

Valves or breakers should not be repositioned unless directed to do so by the SS.

VCT pressure must be maintained equal to or less than 45 psig if taking credit for Boric Acid Transfer pumps in the required flow path.

Standard:

Notes reviewed. Determines VCT pressure meets requirements for operable boric acid transfer pumps.

Comment:

3

• 5 1 Verify operable borated water sources and pumps by performing the following:

a.

For each operable boric acid source, check 14225-1, Operations Weekly Surveillance Logs is active and initial Figure 1, b.

IF the Normal Charging Pump is operable, check 14705-1, Boron Injection Flow Rate Verification is active and initial Figure 1, c.

IF the Boric Acid Transfer Pump(s) are operable, check 14811-1 Boric Acid Transfer Pumps and Discharge Check Valves lnservice Test is active and initial Figure 1, d.

IF the Centrifugal Charging Pump(s) are operable, check 14808-1 Centrifugal Charging Pump and Check Valves 1ST and Response Time Test is active and initial Figure 1, e.

Verify RWST Temperature per 14000-1 Operations Shift and Daily Surveillance Logs and initial Figure 1.

Standard:

1. Steps 5.1 a through 5.1 e are initialed.

2. Figure 1:

• CCPB block is NOT initialed BATP-A, BATP-B, NCP, CCP-A blocks are initialed Active surveillance lines are initialed for all surveillances Corn ment:

4

• 5.2 For each operable power operated valve, complete Figure 1 by placing initials in the appropriate blocks.

Standard:

All blocks for power operated valves in figure 1 are initialed except for:

1 -HV-8806 i-HV-i 82 Comment:

NOTE Locked valves may be verified in the correct position by reviewing the Safety Related Locked Valve manipulation log. Unlocked valves must be locally verified in the correct position.

Standard:

Note reviewed Comment:

• 5*3 Verify each manual valve is open and complete Figure 1 by placing initials in the appropriate blocks.

Standard:

All blocks for manual valves on figure 1 are initialed.

Comment:

5

NOTE The independent flow paths must not share any active components noted in Figure 1.

Standard:

Note reviewed.

Comment:

• 54 Using Figure 1, verify at least two independent flow paths from borated water source(s) through operable pump(s) to the RCS exist.

Standard:

Step 5.4 is NOT initialed.

Comment:

6.0 ACCEPTANCE CRITERIA The valves in the boron injection flow paths shown on Figure 1 were found to be in the required status to provide at least two independent flow paths of borated water to the Reactor Coolant System. All required surveillances are active.

Standard: Acceptance criteria read and used to complete step 7.2.

Comment:

6

7.1 TEST PURPOSE D Surveillance D Maintenance Retest D Other (explain)

Standard:

Surveillance block is checked.

Comment:

• 7.2 Results obtained through performance of this procedure meet ACCEPTANCE CRITERIA of Section 6.0.

DYES

• QNO Standard:

NO block is checked Comment:

• 73 If NO was checked, immediately notify the SS and refer to Technical Requirements Manual TR 13.1.3.

Standard:

SS immediately notified that only one of the 2 required boron injection flow paths are operable.

Determines TR 13.1.3 condition A is applicable and the second required boric acid flow path must be restored in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Comment:

7

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

Standard:

1-HV-182, 1-HV-8806, and COP-B listed as inoperable components and TR 13.1.3 condition A listed as a required corrective action in addition to a condition report number.

Comment:

Test Completed and SS Notified:

Signature Date/Time Standard:

Signature and date/time blocks completed.

Comment:

Terminating cue:

Student returns initiating cue sheet 8

Verification of Completion Job Performance Measure No: V-NRC-JP-14405-OO1 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

9

Initial Conditions:

RCS Tave is 300°F.

1-HV-8806 is danger tagged shut.

1-HV-0182 is danger tagged shut.

CCP-1 B is danger tagged in the PTL position.

All required actions of Technical Specifications for CCP-1 B have been taken.

All other powered components are operable.

All manual valves listed in figure 1 of 14405-1 are open or locked open as required.

VCT pressure is 30 psig 14225-1, Operations Weekly Surveillance Logs is active for the BAST and the RWST.

14705-1, Boron Injection Flow Rate Verification is active.

14811A-1 and 14811B-1, Boric Acid Transfer Pumps and Discharge Check Valves Inservice Test are both active.

14808A-1 and 14808B-1, Centrifugal Charging Pump and Check Valves 1ST and Response Time Test are both active.

RWST temperature is within limits per 14000-1, Operations Shift and Daily Surveillance Logs.

Initiating Cue:

1. Complete surveillance procedure 14405-1, Boron Injection Flow Path Verification During Operation.

2. Based on your completed 14405-1, determine the required Technical Requirements Manual actions, if any. Record in step 74 of 14405-1.

SRO Admin Job Performance Measure B Facility: Vogtle Task No: V-LO-TA-63021 Task

Title:

Determine Active-Inactive Operator License Status JPM No: V-NRC-JP-1001O-OO1 K/A

Reference:

G2.1.4 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:

Three Reactor Operators have the following history:

• All three have off-shift assignments in the plant, are current in License Operator Requal training and have had a medical examination in the past 2 years.

• None of the 3 have worked any shift since 12-31-2009.

• Activelinactive status and time on shift since October 1, 2009 is as follows for each of the Reactor Operators.

• Operator A

- License was active on October 1, 2009 10/02109 worked 0700-1 900 as Unit 2 OATC 10/03/09 worked 0700-1 900 as Unit I OATC 10/04/09 worked 0700-1 900 as Unit I UO 10/05/09 worked 0700-1900 as Unit 2 OATC 10/14/09 worked 1900-0700 as Unit 2 OATC 11117/09worked 1900-0700 as Unit I UO 1

• Operator B

- License was active on October 1, 2009 10128109 worked 0700-1900 as Unit I OATC 11103/09worked 0700-1900 as Unit 2 UO 11105109 worked 0700-1900 as Unit I Extra RO I 1/14I09 worked 1900-0700 as Unit I OATC 12/02109 worked 1900-0700 as Unit I OATC

• Operator C

- License was inactive on October 1, 2009 11/12I09 thru 1I/16I09 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit I OATC and completed all requirements for license reactivation.

12/I 0!09 worked 0700-1900 as Unit I OATC 1211 2/09 worked 0700-1 900 as Unit 2 UO 12/14109 worked 1900-0700 as Unit 2 OATC 12/31109 worked 1900-0700 as Unit I OATC Task Standard:

Correctly identifies the active status of all 3 operators.

Required Materials:

1.

10010-C, Operator Qualification Program General

References:

None Initiating Cue:

You are to determine each of the Licensed Operators active /

inactive status to cover the 0700 1900 shift on January 31, 2010.

Time Critical Task:

No Validation Time:

30 minutes 2

Performance Information Critical steps denoted with an asterisk Student references 10010-C, Operator Qualification Program Standard:

10010-C referenced by the student (In particular, the following sections)

Section 3.9, Licensed Individual (Active Status)

Section 3.10, Licensed Individual (Inactive Status)

Comment:

• Step I Determines the Active I Inactive Status of Operator A license.

Standard:

Determines Operator A license is Active because the operator worked the required 5 twelve hour shifts in a license position during the previous quarter.

Comment:

• Step 2 Determines the Active I Inactive Status of Operator B license.

Standard:

Determines Operator A license is Inactive because the operator did not work the required 5 twelve hour shifts in a license position during the previous quarter.

Comment:

• Step 3 Determines the Active I Inactive Status of Operator C license.

Standard:

Determines the license is Active because the license was reactivated in the previous quarter there is not a requirement to complete the normally required 5 twelve hour shifts in a license position during the quarter.

Comment:

3

Terminating Cue:

The student gives back the cue sheet after determining the active/inactive status of the 3 operators.

4

Verification of Completion Job Performance Measure No. V-NRC-JP-1001O-OO1 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

5

Initial Conditions:

Three Licensed Operators have the following history:

All three have off-shift assignments in the plant, are current in License Operator Requal training and have had a medical examination in the past 2 years.

• None of the 3 have worked any shift since 12-31-2009.

• Active/inactive status and time on shift since October 1, 2009 is as follows for each of the Licensed Operators.

• Operator A

- License was active on October 1, 2009 10I02I09 worked 0700-1900 as Unit 2 OATC 10103109 worked 0700-1900 as Unit I OATC 10/04/09 worked 0700-1900 as Unit I UO 10/05/09 worked 0700-1900 as Unit 2 OATC 10/14109 worked 1900-0700 as Unit 2 OATC 11/17/09worked 1900-0700 as Unit I UO

• Operator B

- License was active on October 1, 2009 10/28/09 worked 0700-1900 as Unit I OATC 11I03/09worked 0700-1900 as Unit 2 UO I 1/05I09 worked 0700-1900 as Unit I Extra RO 11I14I09worked 1900-0700 as Unit I OATC 12l02I09 worked 1900-0700 as Unit I OATC

• Operator C

- License was inactive on October 1, 2009 11/12I09 thru 1111 6/09 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit I SS and completed all requirements for license reactivation.

12/10/09 worked 0700-1900 as Unit I SS 12/11/09worked 0700-1900 as SSS at C & T 12/12/09 worked 0700-1900 as Unit 2 SS 12/16/09 worked 1900-0700 as SSS at C & T 12/17/09 worked 1900-0700 as Unit 2 SS 12/31/09 worked 1900-0700 as Unit I SS Initiating Cue:

You are to determine each of the Licensed Operators active I inactive status to cover the 0700 1900 shift on January 31, 2010.

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 K/A

Reference:

G2.2.13 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:

NSCW pump #4 on Unit 2 needs to be danger tagged to perform pump bearing repairs. The pump motor will not be pulled.

Task Standard:

Tagout hold points and required positions listed.

Required Materials:

1.

Plant Drawings 2X4DB133-1, 133-2, 134, 135-1, 135-2 2X3D-AA-DO3A, DO3B 2X3D-BA-AO1 F 2X3D-BD-KO4D, KO4Y 2.

NMP-AD-003, Equipment Clearance and Tagging General

References:

None Initiating Cue:

Determine the appropriate hold points and required positions of components to safely isolate NSCW pump 2-1202-P4-004.

Identification of K-2 links to clear control room alarms is not necessary.

Time Critical Task:

No Validation Time:

30 minutes 1

Performance Information Critical steps denoted with an asterisk Student references NMP-AD-003.

Standard:

NMP-AD-003 referenced by student.

Comment:

Determines the following components are positions are required to safely tagout NSCW Pump #4 on unit 2.

2HS-1635A, NSCW Pump #4 Hand Switch, Pull-to-Lock 2HS-1635C, NSCW Pump #4 Transfer Switch Control Room 2BA03-11, NSCW Pump #4 Motor Switchgear Breaker, in the Disconnect position.

2BBB-36, NSCW Pump #4 Discharge MOV Breaker, Off 2HV-11613, NSCW Pump #4 Discharge MOV Hand Wheel, Close 2-1202-U4-A18, NSCW Pump #4 Discharge MOV Bypass Valve, Unlocked I Shut 2-1 202-X4-847, NSCW Pump # 4 Motor Cooler Vent Isolation, Uncapped I Open Standard:

Student correctly identifies the above listed positions to safely tag out the NSCW pump #4. The ones in BOLD are the critical points.

Comment:

Terminating cue:

Student informs SS of completion of the identified points to safely tag out NSCW pump # 4 or returns the cue sheet.

2

Verification of Completion Job Performance Measure No. V-RQ-JP-NMP-AD-003 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

3

Initial Conditions:

NSCW pump #4 on Unit 2 needs to be danger tagged to perform pump bearing repairs. The pump motor will not be pulled.

Initiating Cue:

Determine the appropriate hold points and required positions of components to safely isolate NSCW pump 2-1202-P4-004.

Identification of K-2 links to clear control room alarms is not necessary.

Component Number Noun Name Required Position

SRO Admin Job Performance Measure D Vogtle N/A Determine Emergency Exposure Limit V-NRC-JP-91 301-001 G2.3.4 (SRQ 3.7)

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance Classroom Simulator 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 general emergency has been declared. Both trains of ECCS have been aligned for cold leg recirculation. The RHR B pump room is filling with water. The room drain valve needs to be opened to prevent submersing the pump motor in water.

The dose rate is 550 Remlhr at RHR Pump B room drain valve.

Estimated time to open the room drain valve is 45 seconds.

Worker B is selected for the task, and the 10 Rem emergency exposure limit of 91301-C is selected.

91301-C, Emergency Exposure Guidelines Determine the following:

1.

The estimated dose for this task.

2.

The emergency worker you would select to perform this task.

Facility:

Task No:

Task

Title:

JPM No:

K/A:

NRC Examiner:

Date:

Actual Performance Plant Task Standard:

Required Materials:

Initiating Cue:

1

3.

The emergency dose limit you would assign as the Emergency Director using 91301-C, Emergency Exposure Guidelines.

Repair and Corrective Action Team Members 2010 occupational exposure Emergency exposure Worker history history (this event)

A 250 mRem 500 mRem B

l700mRem 300mRem C

512 mRem 1500 mRem Time Critical Task:

Validation Time:

10 minutes No 2

Performance Information Critical steps denoted with an asterisk

• Dose for task is calculated 550 Rem/hr x (1 hr160 mm) x (1 min/60 sec) x 45 sec = 6.875 Rem Standard:

6.875 Rem Comment:

• Dose for emergency task is added to each workers emergency exposure dose history, and worker (B) with lowest emergency dose is selected.

Standard:

Worker A:

6.875 Rem + 0.5 Rem = 7.375 Rem Worker B:

6.875 Rem + 0.3 Rem = 7.175 Rem Worker C:

6.875 Rem + 1.5 Rem = 8.375 Rem Comment:

3

• Emergency dose limit determined using Table I of 91301-C:

TABLE 1 EMERGENCY EXPOSURE GUIDELINES NOTES a.

Dose limits listed in this table apply to doses incurred over the duration of the emergency.

b.

Dose to workers performing emergency services may be treated as a once-in-a-lifetime exposure and should not be added to occupational exposure accumulated under non-emergency conditions.

c.

Workers performing services during emergencies shall limit dose to the lens of the eyes to three times the listed value and doses to any other organ (including skin and body extremities) to ten times the listed value.

Dose Limit (REM)

Total Effective Dose Activity Condition Equivalent 5

All 10 Protecting Valuable Property Lower Dose not practicable 25 Lifesaving or protection of Lower Dose not large population practicable

>25 Lifesaving or protection of Only on a voluntary basis large population to persons fully aware of the risks involved Standard:

10 Rem emergency dose limit is selected.

Comment:

Terminating cue:

Student returns initiating cue sheet 4

Verification of Completion Job Performance Measure No. V-NRC-JP-91301-OO1 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

5

Initial Conditions:

A general emergency has been declared. Both trains of ECCS have been aligned for cold leg recirculation. The RHR B pump room is filling with water. The room drain valve needs to be opened to prevent submersing the pump motor in water.

The dose rate is 550 Remlhr at RHR Pump B room drain valve.

Estimated time to open the room drain valve is 45 seconds.

Initiating Cue:

Determine the following:

1.

The estimated dose for this task.

2.

The emergency worker you would select to perform this task.

3.

The emergency dose limit you would assign as the Emergency Director using 91301-C, Emergency Exposure Guidelines.

Repair and Corrective Action Team Members 2010 occupational exposure Emergency exposure Worker history history (this event)

A 250 mRem 500 mRem B

1700 mRem 300 mRem C

5l2mRem l500mRem

SRO Job Performance Measure E Facility: Vogtle Task No: V-LO-TA-40001 Task

Title:

Classify An Emergency Event I Upgrade JPM No: V-RQ-JP-91001-017 K/A

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 I is in Mode 3 following a reactor trip from power when the MFRV for loop # I failed shut:

- SG # I later developed a 375 gpm SGTR, the crew actuated SI and have entered 19030, E-3, Response to SGTR.

- An Alert Emergency was previously declared.

Current Plant Conditions:

Chemistry has just reported that RCS coolant activity is 269 micro Curies per gram Equivalent 1-131.

I RE-005 and I RE-006 are both indicating 2.6 E+6 mr/hr.

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.

1

Task Standard:

Event ólassified within 15 minutes per 91001-C Data Sheet 1 and Figures 1,2,3, and 4.

Required Materials:

91001-C, entire procedure in color.

General

References:

None Initiating Cue:

Determine the highest emergency classification. Document your emergency classification on Data Sheet I of 91001-C.

Time Critical Task:

YES Validation Time:

15 minutes to classify 2

Performance Information Critical steps denoted with an asterisk 91001-C DATA SHEET I CLASSIFICATION DETERMINATION START TIME CRITICAL________

1.

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

Standard:

Step initialed by the ED.

Comment:

2.

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

Standard:

Step initialed by the ED.

Comment:

3.

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

Standard:

Student marks this step as N/A as it is not applicable.

Comment:

3

4.

Evaluate the status of the fission product barriers using Figures 1, 2, and 3.

Note to examiner: The student may refer to Page 36 of the Threshold Value page to determine if the Containment Barrier is breached.

Standard:

Evaluates the fission product barriers as follows:

a.

Fuel Cladding Integrity

• INTACT b.

Reactor Coolant System Integrity

• LOSS c.

Containment Integrity

• LOSS Comment:

5.

Use Figure 4 to evaluate and determine the Hot 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 to ensure that the Threshold is met.

Note to examiner: The student may refer to Page 36 of the Threshold Value page to determine if the Containment Barrier is breached.

Standard:

Determines that a *Site Area Emergency should be declared due to *FSI Loss or Potential Loss of ANY Two Barriers.

Comment:

6.

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.

Standard:

Student marks this step as N/A since it is not applicable.

Comment:

4

EAL#

FS1

• 7 Check One:

11 Notification Of Unusual Event D

Alert Site Area Emergency E1 General Emergency Note to examiner: The student should enter the EAL # on the blank on Data Sheet 1 as *FSI However, determining a *Site Area Emergency exists is the critical part.

Standard:

Site Area Emergency is checked, and EAL #FS1 Comment:

8.

Maintain a tog of the incident (This may be delegated)

CUE: An extra SRO will maintain the log.

Standard: Student indicates he would initiated a log of the incident.

Comment:

• 9 Assume the position of Emergency Director.

Signature___________________________

Emergency Director Date:

I I__________

Time:___________________________

STOP TIME CRITICAL________

Standard:

Student signs, dates and fills in time within 15 minutes:

Comment:

Terminating cue:

Student returns initiating cue sheet 5

Verification of Completion Job Performance Measure No. V-RQ-JP-91001-017 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

6

TIME CRITICAL Initial Conditions:

- Unit I is in Mode 3 following a reactor trip from power when the MFRV for loop # I failed shut:

- SG # I later developed a 375 gpm SGTR, the crew actuated SI and have entered 19030, E-3, Response to SGTR.

- An Alert Emergency was previously declared.

Current Plant Conditions:

- Chemistry has just reported that RCS coolant activity is 269 micro Curies per gram Equivalent 1-131.

- IRE-005 and IRE-006 are both indicating 2.6 E+6 mr/hr.

- 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.

Initiating Cue:

Determine the highest emergency classification. Document your emergency classification on Data Sheet I of 91001-C.