ML031190688

Draft - Section a Operating

ML031190688
Person / Time
Site:	Indian Point  (DPR-026)
Issue date:	04/01/2003
From:	Wilson F Entergy Nuclear Northeast
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-247/03-301 50-247/03-301
Download: ML031190688 (68)

Text

ES-301 Administrative Topics Outline Form-ES-301 -1 acity:

Indian Point 2 Date of Examination:

3/10/2003 Examination Level:

SRO Operating Test Number:

1 Administrative Topic/Subject Describe method of evaluation:

Description I ONE Administrative JPM, OR

2. TWO Administrative Questions A.1 a Conduct of 2.1.7 Ability to evaluate plant performance and make operational Operations judgments based on operating characteristics, reactor behavior, and instrument interpretation. (3.7/4.4)

JPM:

Review a QPTR calculation and direct appropriate actions A.1 b Conduct of 2.1.18 Ability to make accurate, clear, and concise logs, records, status Operations boards, and reports. (2.9/3.0)

JPM:

Review Control Room Log Entries A.2 Equipment Control 2.2.17 Knowledge of the process for managing maintenance activities during power operations. (2.3/3.5)

JPM:

Review (for approval) a completed surveillance for Tech Spec required equipment A.3 Non-Emergency 2.3.4 (3.1)

Knowledge of radiation exposure limits and contamination dose limits control, including permissible levels in excess of those question authorized.

QUESTION: Given the plant in a SAE and a personnel exposure history, determine the exposure limit for a Non-Emergency operation.

2.3.2 (2.9)

Knowledge of facility ALARA program.

EmergencyI Exposure Limits QUESTION: Given a situation requiring valve alignment verification in a Question radiation area, determine the waiver requirements for independent or concurrent verification of a locked valve and identify an alternate process for verification.

A.4 Emergency Plan 2.4.44 Knowledge of Emergency Plan Protective Action Recommendations. (2.1/4.0)

JPM:

Perform Protective Action Recommendation a~_nf &I 6I

?

V11 Form ES-301 -1 SRO ADM Outline NUREG-1021, Revision 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

Indian Point Unit 2 Perform A QPTR Calculation And Direct Appropriate Actions Task No.:

N/A JPM No.:

2003 NRC Ala SRO K/A

Reference:

039 A2.01 (3.2)

Examinee:

NRC Examiner:

Facility Evaluator:

Method of testing:

Date:

Simulated Performance:

Classroom X

Simulator Actual Performance:

Plant X

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 plant is at 100% power.

NIS power range channel N-41 is out of service.

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Determines QPTR outside of TS limits and initiates corrective action IAW Technical Specifications SOP-15.3 Rev 16 DSR 4B Calculator SOP-15.3 Rev 16 DSR-4B Partially completed DSR-4B The Shift manager has directed you to calculate QPTR manually using the given detector currents in accordance with the appropriate procedure, determine if the calculated values meet Technical Specification limits, and any appropriate actions to take, if necessary Time Critical Task:

NO Validation Time:

20 Minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Note: The purpose of this JPM is to have the candidate calculate QPTR and to correctly apply the TS actions. The candidate will be provided a DSR-4B with upper and lower NIS detector currents already filled out.

Performance Step: I Standard:

Comment:

Performance Step: 2 Standard:

Obtain SOP-15.3 Obtains procedure Cue: Hand candidate a copy of partially filled out DSR-4B Record top and bottom detector currents Refers to DSR-4B for currents Comment:

Performance Step: 3 Standard:

Record date, time, and average reactor power Records on DSR-4B Comment:

Performance Step: 4 Standard:

Divide each detector current output by corresponding normalization factor Locates normalization factors and divides. Will only use 3 detectors, so denominator will be 3 Comment:

Performance Step: 5 Standard:

Calculate average normalized ratio for top and bottom detectors Performs calculation Comment:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Standard:

Calculate Quadrant Power Tilt for top and bottom detectors Performs calculation Comment:

Performance Step: 7 Standard:

Record Highest Quadrant Power Tilt and appropriate signatures Records and signs DSR-4B Comment:

Performance Step: 8 Standard:

Comment:

Performance Step: 9 Standard:

Document results Enters data on DSR-1 Cue: DSR-1 entry made be made later Determine requirements of TS 3.10.3 are NOT met Refer to TS 3.10.3 and determine that QPTR exceeds 1.02 and determine that a power reduction is necessary Comment:

Terminating Cue:

When the candidate has determined appropriate action per TS, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement 1

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

IP2 2003 NRC Ala SRO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The plant is at 100% power.

NIS power range channel N-41 is out of service INITIATING CUE:

The Shift manager has directed you to calculate QPTR manually using the given detector currents in accordance with the appropriate procedure, determine if the calculated values meet Technical Specification limits, and any appropriate actions to take, if necessary NUREG 1021, Revision 8, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

Indian Point Unit 2 Review Control Room Log Entries 2.1.18 (3.0)

Task No.:

JPM No.:

N/A 2003 NRC Alb SRO Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

X Simulator Actual Performance:

Plant X

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:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The surveillances required by DSR-1 are complete for 0700 All corrective actions taken or in progress in accordance with DSR-1 DSR-1 Rev 91 DSR-1 Rev 91 DSR-1 Rev 91 Review the log entries taken on the 1900-0700 shift for approval NO 15 minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

NOTE: Candidate may identify deficiencies in any order.

Performance Step: 1 Standard:

Determines CST level is out of spec low Refer to TS 3.4.A.3. Determine TS minimum is met. Action to commence filling. Document by circling reading and informing SM (Any step of this JPM)

Comment:

Performance Step: 2 Standard:

Determines Containment Average Air temperature is out of spec high Refers to TS 3.6.C and commence action to restore Starts Containment FCU or raise service water flow Comment:

Performance Step: 3 Standard:

Comment:

Terminating Cue:

Determines 21 SI Accumulator pressure is out of spec low Refers to TS 3.3.A and commences action to restore pressure Enters the action statement of TS 3.3.A NOTE: Containment Air Temperature and CST level are out of spec but not inoperable per TS. 21 Accumulator is inoperable per TS When log review is complete, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

IP2 2003 NRC Alb SRO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement I

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

INITIATING CUE:

The surveillances required by DSR-1 are complete for 0700 Review the log entries taken on the 1900-0700 shift for approval NUREG 1021, Revision 8, Supplement 1

DSR-1 Remarks

1) Load Limit 1 in service... LL's < Gov. oil pressure IP2-02-02590

2) Local RWST level not taken per SM-Safety concern

3) PI-936C, 23 ACCUM PRESS, CR#200300134, WO#03-10344

4) R-40 IP2-02-56719

5) R-48 O/S -

T.O. 16586

6) R Does Not trip on low flow CR#1P2-2003-00173

7) R-55A - Does Not trip on low flow WRTIIP2-03-10406

8) R-55B-I&C 6 month PM.

9) R-55C - Does Not trip on low flow WRT#IP2-03-10406

10) R-55D - Does Not trip on low flow WRT#IP2-03-10406

11) R-59 O/S - Flange Leak Tag Out #2-02-6-00601

12) FSB charcoal hours WRT # IP2-02-02470

13) HSB 22 out of service Tag Out 2002-N-16406

14) Sequence of events CRs written.

2002-08363, 08164, 05966 & 06909

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

Indian Point Unit 2 Task No.:

N/A Review (For Approval) A Completed JPM No.:

2003 NRC A2 SRO Surveillance K/A

Reference:

2.2.12 (3.4)

Examinee:

Facility Evaluator:

Method of testing:

NRC Examiner:

Date:

Simulated Performance:

Classroom X

Simulator Actual Performance:

Plant X

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 Plant is at 100% power. All equipment in service.

PT-Q26A, 21 Service Water Pump Train Operational Test, was performed on your shift.

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Deficiency identified and TS action PT-Q26A Rev 9 PT-Q26A Rev 9 PT-Q26A Rev 9 You have been directed by the Shift Manager to perform calculations per section 7.4 and acceptance criteria review and approval per section 10.0 of PT-Q26A Time Critical Task:

No Validation Time:

15 minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Calculates total pump head Determines head is approximately 275 feet by adding discharge pressure in feet with calculated value of suction pressure in feet Comment:

Performance Step: 2 Standard:

Determines acceptance criteria for total head is not met Section 10.3; 300.5 - 355.4 is acceptable surveillance value.

Greater than 307 for alert range criteria Comment:

Performance Step: 3 Standard:

Determines action required Step 10.6 requires action for surveillance failure - 21 SWP o Notify SM o Initiate a CR Comment:

Terminating Cue:

When the candidate has completed the acceptance criteria determination, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

IP2 2003 NRC A2 SRO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The Plant is at 100% power. All equipment in service.

PT-Q26A, 21 Service Water Pump Train Operational Test, was performed on your shift.

INITIATING CUE:

You have been directed by the Shift Manager to perform calculations per section 7.4 and acceptance criteria review and approval per section 10.0 of PT-Q26A NUREG 1021, Revision 8, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

India Task

Title:

200' K/A

Reference:

2.3.

2.3.'

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom in Point Unit 2 3 NRC ADMIN A3 SRO 2 (2.9) 4 (3.1)

Task No.:

JPM No.:

N/A N/A NRC Examiner:

Date:

X Simulator Actual Performance:

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:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

N/A Two Questions answered at least 80% Correctly E-Plan E-Plan OASL 15.26 NONE N/A NO 10 Minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 6 Form ES-C-1 VERIFICATION OF COMPLETION ANSWER KEY NRC SRO ADMIN A.3 QUESTION 1 (Reference allowed)

You are the Shift Manager.

An Alert has been declared at Indian Point due to a Steam Generator Tube Rupture.

Elevated radiation levels exist throughout the secondary plant.

An EOP attachment will be performed by an NPO to minimize secondary system contamination.

What are the restrictions on his allowable dose to perform this task?

ANSWER:

• 5 Rem TEDE if possible, (50%) with an extension to 10 Rem possible to protect property (50%)

REFERENCE:

E-Plan Part 2 section K NUREG 1021, Revision 8, Supplement 1

---I Appendix C Page 3 of 6 Form ES-C-1 VERIFICATION OF COMPLETION ANSWER KEY NRC SRO ADMIN A.3 QUESTION 2 (CLOSED Reference)

You are the Shift Manager.

A normally locked manual isolation valve in the Excess Letdown Heat Exchanger discharge line in a High Radiation Area was repositioned by an operator that received 65 millirem. The valve requires independent verification of position.

What are the requirements for independently verifying the position of this valve? Explain your answer.

ANSWER:

The Shift Manager may waive requirements for Independent Verification of this valve. (40%)

Alternate verification techniques may be used. (40%)

o Remote position indicators (5%)

o Use of process parameters (flow, pressure) (5%)

o Valve stem observation (5%)

o Functional mechanical position indicators (5%)

REFERENCE:

OASL 15.26 Attachment 1 NUREG 1021, Revision 8, Supplement 1

Appendix C Page 4 of 6 Form ES-C-1 VERIFICATION OF COMPLETION NRC SRO ADMIN QUESTION 1 (Open Reference)

You are the Shift Manager.

An Alert has been declared at Indian Point due to a Steam Generator Tube Rupture.

Elevated radiation levels exist throughout the secondary plant.

An EOP attachment will be performed by an NPO to minimize secondary system contamination.

What are the restrictions on his allowable dose to perform this task?

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION NRC SRO ADMIN QUESTION 2 (Closed Reference)

You are the Shift Manager.

A normally locked manual isolation valve in the Excess Letdown Heat Exchanger discharge line in a High Radiation Area was repositioned by an operator that received 65 millirem. The valve requires independent verification of position.

What are the requirements for independently verifying the position of this valve? Explain your answer.

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET Job Performance Measure No.:

IP2 SRO ADMIN A3 QUESTIONS Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1

COMPONENT STATUS CONTROL AND POSITION VERIFICATION OASL 15.26 Rev. 1 ATTACHMENT I COMPONENT STATUS CONTROL AND POSITION VERIFICATION (Page 5 of 6) 1 INDEPENDENT VERIFICATION 1.1 For each COL that has an Attachment A. PERFORM the following:

1.1.1 PERFORM the independent verification and document complection in the applicable space on Attachment A.

1.1.1 Upon completion of independent verification, "as found" position SHALL be compared to the "required" positions by the SM OR his designee.

1.1.1 Discrepancies SHALL be listed on the comments/exceptions page AND resolved.

1.1 For each COL that has second verifier blank next to the initial verifier, PERFORM the following:

1.1.1 PERFORM the independent verification and document completion in the applicable space.

1.1.1 IF any discrepancies are noted, CONTACT the FSS for resolution.

1.1 A independent verification requires the following conditions:

The independent verification SHALL be performed by someone different from the individual who performed the initial verification.

The independent verifier SHALL use Attachment(s) provided at the end of the COL being verified.

EXCEPTIONS:

Special Throttled valves with locking devices where the throttled position has been set by an approved test. Flow observation SHALL be observed independently.

When required to perform a independent verification by Technical Specifications or NP procedure, the Section 1 requirements SHALL be followed. The requirements apply to any required calculations, sampling and to the identification of required equipment configuration.

Independent verification may be waived by the Shift Manager if the component to be verified is located within a Hi RAD AREA.

Paae 7 of 9

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

Indian Point Unit 2 Perform Event Classification 2.4.41 (4.1)

Task No.:

JPM No.:

N/A 2003 NRC A4 SRO S1 Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

Plant X

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:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

An event has occurred requiring Emergency classification Classification is correctly made for the event completed Event Classification Guide Event Classification Guide Event Classification Guide Classify the event just completed YES 15 Minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Classify the Event in accordance with the event classification guide Standard:

Classification is a SITR AREA EMERGENCY, Criteria 1.3.1 Comment:

Terminating Cue:

When event classification has been made, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

2003 NRC A4 SRO S1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

INITIATING CUE:

An event has occurred requiring Emergency classification Classify the event just completed NUREG 1021, Revision 8, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

Indian Point Unit 2 Perform Event Classification 2.4.41 (4.1)

Task No.:

JPM No.:

N/A 2003 NRC A4 SRO S2 Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

Plant X

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:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

An event has occurred requiring Emergency classification Classification is correctly made for the event completed Event Classification Guide Event Classification Guide Event Classification Guide Classify the event just completed YES 15 Minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: 1 Classify the Event in accordance with the event classification guide Standard:

Classification is a SITE AREA EMERGENCY, Criteria 1.1.2 Comment:

Terminating Cue:

When event classification has been made, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

2003 NRC A4 SRO S2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

INITIATING CUE:

An event has occurred requiring Emergency classification Classify the event just completed NUREG 1021, Revision 8, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

Indian Point Unit 2 Perform Event Classification 2.4.41 (4.1)

Task No.:

JPM No.:

N/A 2003 NRC A4 SRO S3 Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

Plant X

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:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

An event has occurred requiring Emergency classification Classification is correctly made for the event completed Event Classification Guide Event Classification Guide Event Classification Guide Classify the event just completed YES 15 Minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Performance Step: I Classify the Event in accordance with the event classification guide Standard:

Classification is an ALERT, Criteria 3.1.2 Comment:

Terminating Cue:

When event classification has been made, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

2003 NRC A4 SRO S3 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 4 of 4 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

INITIATING CUE:

An event has occurred requiring Emergency classification Classify the event just completed NUREG 1021, Revision 8, Supplement 1

r7CZqA I

Administrative Topics Outline Form-ES-301 -1 Facility:

Indian Point 2 Date of Examination:

3/10/2003 Examination Level:

RO Operating Test Number:

1 Administrative Describe method of evaluation:

Topic/Subject Description

1. ONE Administrative JPM, OR

2. TWO Administrative Questions A.1 a Conduct of 2.1.7 Ability to evaluate plant performance and make operational Operations judgments based on operating characteristics, reactor behavior, and instrument interpretation. (3.7/4.4)

JPM:

Perform QPTR Calculation Aib Conduct of 2.1.18 Ability to make accurate, clear, and concise logs, records, status Operations boards, and reports. (2.9/3.0)

JPM:

Perform a set of Control Room logs A.2 Equipment 2.2.12 Knowledge of surveillance procedures. (3.0/3.4)

- Control JPM:

Perform the RCS Leak Rate surveillance A.3 Radiation 2.3.2 Knowledge of facility ALARA program. (2.5/2.9)

Exposure Control JPM:

Determine appropriate RWP and take action for High Area Radiation alarm A.4 Emergency Plan 2.4.43 Knowledge of RO responsibilities in E-Plan implementation.

(3.3/3.1)

Question:

Duties of operations department personnel when site accountability is required 2.4.29 Knowledge of the Emergency Plan. (2.6/4.0)

Question: Emergency Response Facilities activated in a Site Area Emergency NUREG-1021, Revision 8 Form ES-301-1 RO ADM Outline

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

Indian Point Unit 2 Perform A QPTR Calculation Task No.:

N/A JPM No.:

2003 NRC Ala RO K/A

Reference:

039 A2.01 (3.2)

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Simulated Performance:

Classroom X

Simulator Actual Performance:

Plant X

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 plant is at 100% power.

NIS power range channel N-41 is out of service.

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Determines QPTR outside of TS limits and inform CRS/SM SOP-15.3 Rev 16 DSR 4B Calculator SOP-1 5.3 Rev 16 DSR-4B Partially completed DSR-4B The Shift Manager has directed you to calculate QPTR manually using the given detector currents in accordance with the appropriate procedure Time Critical Task:

NO Validation Time:

20 Minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Note: The purpose of this JPM is to have the candidate calculate QPTR and to correctly initiate action. The candidate will be provided a DSR-4B with upper and lower NIS detector currents already filled out.

Performance Step: 1 Standard:

Comment:

Performance Step: 2 Standard:

Obtain SOP-15.3 Obtains procedure Cue: Hand candidate a copy of partially filled out DSR-4B Record top and bottom detector currents Refers to DSR-4B for currents Comment:

Performance Step: 3 Standard:

Record date, time, and average reactor power Records on DSR-4B Comment:

Performance Step: 4 Standard:

Divide each detector current output by corresponding normalization factor Locates normalization factors and divides. Will only use 3 detectors, so denominator will be 3 Comment:

Performance Step: 5 Standard:

Calculate average normalized ratio for top and bottom detectors Performs calculation Comment:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Standard:

Calculate Quadrant Power Tilt for top and bottom detectors Performs calculation Comment:

Performance Step: 7 Standard:

Record Highest Quadrant Power Tilt and appropriate signatures Records and signs DSR-4B Comment:

Performance Step: 8 Standard:

Comment:

Performance Step: 9 Standard:

Document results Enters data on DSR-1L (ft 1

Cue: Ef/R-1 entry made be made later A

Determine QPTR is greater than 1.02. Inform CRS/SM Refer to procedure and determine that QPTR >1.02. Inform supervision Comment:

Terminating Cue:

When the candidate has determined QPTR and notified CRS/SM, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement 1

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

IP2 2003 NRC Ala RO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

The plant is at 100% power.

NIS power range channel N-41 is out of service INITIATING CUE:

The Shift manager has directed you to calculate QPTR manually using the given detector currents in accordance with the appropriate procedure NUREG 1021, Revision 8, Supplement 1

4 Ao400)4 UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. 73 PrevousSNSC #2545 115/

(QT-1 6-6)

DATE: ToA h SNSC REVIEW

DATE, TIME: r.oiw WD3S4 AVE REACTOR PWR:

lo° i ° A

LVh E)

DAE A

9 USING DETECTOR OUTPUT CURRENT APPROVED DATE Current QT number and Normalization Factors provided by Reactor Engineer.

1.

Determine normalized ratios by dividing indicated detector current by normalization factor as follows:

Channel Det Current Nor Ratio Channel Det Current Nor Ratio 41Top=41T=

t4A

/11A4.6=

r4Ar 41 Bottom =41B=

r4' /*112 r 42 Top = 42T = Al1 ° 8.3 =

42 Bottom = 42B = t t.*

ri l 8=-

43 Top = 43T = /0°Y1 (

r 108_9 =

43 Bottom = 43B=

r 118.9 =

44 Top = 44T = 6(*.9 1=

0

=_____

44 Bottom = 44B = v

/

j1s -

2.

Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top

ANRT = 41T + 42T + 43T + 44T

4 Average Normalized Ratio Bottom = ANRB = 41 B + 42B + 43B + 44B=

4

3.

Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio.

Quadrant Power Tilt Top = QPTT = Highest value of 41T. 42T. 43T. or 44T ANRT Mfllun =

QPTT= ANRT=

=

Quadrant Power Tilt Bottom = QPTB = Highest value of 41 B. 42B. 43B. or 44B AN RB Value =

QPTB= ANRB=

=

4.

The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of 1.0200.

Enter the Higher QPT(Top or Bottom) = _

Technical Specification Limit

=

1. 0 2 0 0

NOTES:

1.

If the quadrant power tilt exceeds the Tech. Spec. limits, the SM, OM, RE and GM-NPG shall be Informed ASAP.

2.

If one detector is out of service, the three In service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3).

RO:

SM:_

Page 1 of 1

UNIT TWO QUADRANT POWER TILT CALCULATION SHEET DSR-4B Rev. 73 Previous SNSC #2545 11/5/98 (QT-16-6)

DATE:

r0 A-y SNSC REVIEW DATE; TIME: row 1203 AVE REACTOR PWR:

/o° '

0 At VE,(RE) DATE Job Y

USING DETECTOR OUTPUT CURRENT APPROVED DATE Current QT number and Normalization Factors provided by Reactor Engineer.

1.

Determine normalized ratios by dividing indicated detector current by normalization factor as follows:

Channel Det Current Nor Ratio Channel Det Current Nor Ratio 41Top=41T=

MA

/* 1 144.6 A

41 Bottom=41B= rd A Ai26=

t 42 Top = 42T = Z97. D 8

42 Bottom = 42B v

/*

8 = o.-' 3?

43 Top = 43T = /O'f l

08.9 =

O8 '(S579 431Bottom=43B1=

B.%

8 * \\

_9

= o.

I 3

44 Top = 44T = /(

- 9 P 105.9 = k.-O) 0' M

44 Bottom = 44B -

V tv

.3

=

rO

2.

Determine the average normalized ratio for the top and bottom.

Average Normalized Ratio Top

ANRT --,L4ZL+/-A43+/-+4I

.-9 83 Average Normalized Ratio Bottom = ANRB =O.SA2B +A3+/-+44= C) 9 2.9

3.

Determine The quadrant power tilt ratio for the top and bottom by dividing the highest normalized power ratio for the top and bottom respectively by their respective average normalized ratio.

Quadrant Power Tilt Top = QPTT = Highest value of 41 T. 42T. 43T. or 44T ANRT Value= t_____

QPTT= ANRT=,c3S

=3 t

Quadrant Power Tilt Bottom = QPTB = Highest value of 41 B. 42B. 43B. or 44B Value= 0 3ANRB QPTB = ANRB o.'9 7-e Ookv7

4.

The higher of the two quadrant power tilts should be less than or equal to the Technical Specification Limit of 1.0200.

Enter the Higher QPT(Top or Bottom) = -

Technical Specification Limit

=

1. 0 2 0

0 NOTES:

1.

If the quadrant power tilt exceeds the Tech. Spec. limits, the SM, OM, RE and GM-NPG shall be Informed ASAP.

2.

If one detector is out of service, the three in service detectors will be used to compute the average normalized ratios (ensure denominators in step 2 are changed from 4 to 3).

RO:

SM:_

Page 1 of I

Appendix C Page 1 of 5 Form ES-C-1 PERFORMANCE INFORMATION Facility:

Task

Title:

K/A '

Reference:

Indian Point Unit 2 Task No.:

Perform Control Room Lop Entries JPM No.:

2.1.18 (3.0)

N/A 2003 NRC Alb RO Examinee:

Facility Evaluator:'

Method'of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

X Plant X

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:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

You are on shift prior to 0700.

DSR-1 log entries are partially completed.

All corrective actions taken or in progress in accordance with DSR-1 DSR-1 Rev 91 DSR-1 Rev 91 Partially completed DSR-1 Rev 91 Perform the remainder of the log entries taken on the 1900-0700 shift for DSR-1 NO 15 minutes

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

NOTE: Candidate may identify-deficiencies in any order.

Performance Step: I Determines CST level is out of spec low Standard:

Circle reading and enter comment Document by circling reading and informing SM Comment:

Performance Step: 2 Standard:

Determines Containment Average Air temperature is out of spec high Circles reading and enters comment. Inform CRS/SM Comment:

Performance Step: 3 Standard:

• Comment:

Terminating Cue:

Determines 21 SI Accumulator pressure is out of spec low Circles reading and enters comment. Informs CRS/SM NOTE: Containment Air Temperature and CST level are out of spec but not inoperable per TS. 21 Accumulator is inoperable per TS When logs are complete, the evaluation for this JPM is complete.

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

IP2 2003 NRC Alb RO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

You are on shift prior to 0700. DSR-1 log entries are partially completed INITIATING CUE:

Perform the remainder of the log entries taken on the 1900-0700 shift for DSR-1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point Unit 2 Task No.:

N/A Task

Title:

Perform the RCS Leak Rate Surveillance JPM No.:

2003 NRC A2 RO K/A

Reference:

2.2.12 (3.0)

Examinee:

Facility Evaluator:

Method of testing:

NRC Examiner:

Date:

Simulated Performance:

Classroom X

Simulator Actual Performance:

Plant X

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:

Task Standard:

Required Materials:

General

References:

Handouts:

A manual RCS leak rate calculation was started 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago in accordance with SOP-1.7.

RCS leak rate is calculated correctly within +/- 0.1 GPM SOP-1.7 Calculator Steam Tables SOP-1.7 SOP1.7 and completed attachment 1 Initiating Cue:

Time Critical Task:

Validation Time:

Using the final values below, manually calculate RCS leak rate in accordance with SOP-1.7, section 4.2.2.1, RCS Inventory Balance.

NO 20 Minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Note: Hand candidate attachment 1 with initial and final data Performance Step: 1 Standard:

Transfer data to attachment 2 Refer to attachment 1 and place data in appropriate blocks on attachment 2 Comment:

Performance Step: 2 Standard:

Calculate total surveillance period time Calculates 240 minutes Comment:

Performance Step: 3 Standard:

Calculate total volume diverted Calculates zero gallons Comment:

Performance Step: 4 Standard:

Determine total Boric Acid and Primary Water makeup from totalizers Calculates 34 gallons boric acid, 426 gallons primary water Comment:

Performance Step: 5 Standard:

Calculate total volume diverted from total makeup Calculates 460 gallons Comment:

Performance Step: 6 Standard:

Calculate change in VCT volume and convert to gallons Calculates 38.6 gallons Comment:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 7 Standard:

Sum change in VCT volume and net makeup Calculates 498.6 gallons Comment:

Performance Step: 8 Standard:

Calculate change in RCS mass due to change in pressurizer level Calculates 519.9 Ibm Comment:

Performance Step: 9 Standard:

Calculate the change in RCS mass due to Tave Calculates (-) 784 Ibm Comment:

Performance Step: 10 Standard:

Sum the mass changes due to level and temperature changes Calculates (-) 264.1 Ibm and converts to (-) 31.95 gallons Comment:

Performance Step: 11 Standard:

Add total volumes Calculates 466.7 gallons Comment:

Performance Step: 12 Standard:

Divide total elapsed time Total value of leakage is 1.94 gpm (Candidate should arrive at 1.84 to 2.04)

Comment:

Performance Step: 13 Standard:

Subtract identified leakage from last safety evaluation Subtracts 1.7 gpm to arrive at 0.24 GPM total unidentified leakage Comment:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 14 Record the total unidentified leak rate on attachment 5 Standard:

Locates attachment 5 Comment:

Terminating Cue:

When RCS leak rate calculation is complete, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement 1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

IP2 2003 NRC A2 RO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

INITIATING CUE:

A manual RCS leak rate calculation was started 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago in accordance with SOP-1.7.

Using the final values below, manually calculate RCS leak rate in accordance with SOP-1.7, section 4.2.2.1, RCS Inventory Balance.

Final Values:

o Provided on Attachment 1 (provided) o Last Identified leak rate from safety evaluation 3 days ago is 1.7 GPM NUREG 1021, Revision 8, Supplement 1

9 p4,--1(I L

REACTOR COOLANT SYSTEM LEAKAGE SURVEILLANCE SOP 1.7 Rev. 35 N-1 ATTACHMENT 1 LEAKAGE SURVEILLANCE DATA SHEET (PAGE 1 of 2)

DATE __o___t PARAMETER PLANT INDICATION PREVIOUS Present COMPUTER (Initial)

(Firial)

SYSTEM DATA 1 DATA Time Clock Panel I FAF yr RCS Activity (uCi/cc)

Sample 2 L2-Z 2 6 Kr88 Activity (pCi/cc)

Sample I,

7 R-41 Activity (ACicc) 3,(Co 3_____-__

R-41 Background (guCicc) 2 e LA _

E_

BA Integrator Panel FBF 6/

G PW Integrator Panel FBF 2.

'- 5 VC Sump Flow Integrator Panel SFF

) 0 (4 z C, 0

2__C_

VCT Level L0112 LI-112 af. L Average PZR Level 2 U0483 4

i 4 4 Ch.1 PZR Level 2 L0480 Ll-459 L(

Li Li Ch.2 PZR Level 2 L0481 LI-460 4

5 Li Ch.3 PZR Level 2 L0482 LI-461 4 S.

VC Sump Level L6055 Panel SBF-1 t'

C" Lo 4 O O

U0484 or Panel FCF TAVE T0499 or or FDF RCSAVETAVE Ss-*l

___(SAS)

RCS Pressure U0482 or PT455,456 P0499 457,474 2

22.3 5 Weir Level 21 FCU LI-1133

- C O

O 22FCU LI-1134 C

OC C) 09 23FCU 1Ll-1135

-6 24 FCU Ll-1136 O

O0 25FCU LI-1137 O0 o O VC Dew Pt.

21 FCU Recorder 0

0 7

7-70 22 FCU Recorder 7O )

7 Page 26 of 59

REACTOR COOLANT SYSTEM LEAKAGE SURVEILLANCE SOP 1.7 Rev. 35 N-1 ATTACHMENT I LEAKAGE SURVEILLANCE DATA SHEET (PAGE 2 of 2)

DATE 7 lr l PARAMETER PLANT INDICATION PREVIOUS Present COMPUTER (Initial)

(Final)

SYSTEM DATA 1 DATA 23FCU Recorder 7o,.7 C 70,7 O4 l

24 FCU Recorder O7?3 Or 2o,.7 °c l

25 FCU Recorder

?

7? 0F 70 7?

BA makeup to RWST CRS Log

___ll PW makeup to RWST CRS Log

'0 Let Down Integrator 2 Panel SFF RHR Valve Leakage SOP 1.7 Att 6 0

0 Known Leakage other than SOP 1.7 Att 6 RCS in VC S

O P

1.

7 6

Identified RCS Leakage SOP 1.7 Att 6 I t )

C lD o

VC Sump Temperature WDS Panel ICo ° G(O(,O aF VC Sump Boron Chemist Sample 3 t

-4______

VC Sump Sodium Chloride Chemist a

Sample'I VC Sump Molybdenum Chemist

,.q 4 S am ple 3 VC Sump Ph @ 25C Chemist 44 Sam ple 3 VC Sump Activity S

Chemist Sam ple_ 3_

VC Sump Conductivity Chemist S am ple 3 1 Not Required if using PC 2 ZERO the Letdown Integrator af ter recording data by pressing the Control Reset button.

3 IF requested by CRS per step 4.2.2.(2)0)

Page 27 of 59

REACTOR COOLANT SYSTEM LEAKAGE SURVEILLANCE SOP 1.7 Rev. 35 N-1 ATTACHMENT 2 MANUAL RCS WATER INVENTORY BALANCE WORK SHEET (PAGE 1 of 3)

DATE CAUTION Use this attachment ONLY at Normal, Full Power Temperature and Pressure of 5590F, and 2235 psig.

I RCS Water Inventory Balance (Section 4.2.2)

( ) indicates mathematical sign must be observed.

A. Final Time Initial Time Elapsed Time

=

(A)

Minutes B. Make Up to RWST and Letdown diversion to CVCS HUT.

BA MU from CRS log PW MU from CRS log,+

RWSTMU (bl)

LD Integrator gal (b2)

Total Divert gal (bl)

+

gal (b2) gal (B)

C. Total RCS Make up volume Final BA Counter Initial BA Difference (ci) gal Final PW Counter Initial PW Counter Difference

_ gal (c2)

Total Makeup gal

+

(ci) gal (c2) gal (C)

Page 28 of 59

A /\\/ S L-f--e

REACTOR COOLANT SYSTEM LEAKAGE SURVEILLANCE SOP 1.7 Rev. 35 N-1 ATTACHMENT 2 MANUAL RCS WATER INVENTORY BALANCE WORK SHEET (PAGE 1 of 3)

DATE rav4ag CAUTION Use this attachment ONLY at Normal, Full Power Temperature and Pressure of 5590F, and 2235 psig.

RCS Water Inventory Balance (Section 4.2.2)

( ) indicates mathematical sign must be observed.

A. Final Time Initial Time Elapsed Time B. Make Up to RWST BA MU from CRS log PW MU from CRS log +

RWSTMU LD Integrator O

4 c

0=

2 '-O Minutes (A) and Letdown diversion to CVCS HUT.

C (bl)

C gal (b2)

Total Divert 0

gal (bl)

+

C gal (b2)

C) gal (B)

C. Total RCS Make up volume Final BA Counter Initial BA Difference Final PW Counter Initial PW Counter Difference

/00.

6G 3+/- f gal (ci)

L-2,6 gal (c2)

Total Makeup (ci) gal

+

I(2(.

gal (c2)

'LI4 GC gal (C)

Page 28 of 59

REACTOR COOLANT SYSTEM LEAKAGE SURVEILLANCE SOP 1.7 Rev. 35 N-1 ATTACHMENT 2 MANUAL RCS WATER INVENTORY BALANCE WORK SHEET (PAGE 2 of 3)

DATE TOD!44 D. Net MU - Divert 460c gal (C) o gal (B)

=

(4A) 41&

gal (D)

E. Change in VCT Initial VCT Level

. Final VCT Level Difference F. Net VCT plus MU/Divert volume.

(4)7 (d_, %

(t-)

Li(oo gal (D)

X 19.3 gal/%

_,) 38W(

gal (E)

=

(e ) 3Sz( gal (E)

=

( XI )8 e gal (F)

G. Change in RCS mass due to change in PZR level Initial Pzr Level Final Pzr Level Difference Change in Pzr Mass 9*f etLj %

(.-)

t (e-) l S 24 L gal (W1)

X 126.2 gal / %

X 4.12 lb/ gal.

=

(4 (2-C gal (gI)

=

(+ ) )9 q '{fIbm (G)

H. Change in RCS mass due to Tave Final Tv, F0 Initial Tave S

F' Difference

(-)

F0 I. Total change in RCS Mass (Pzr Level plus

(.)Sl 1i Ibm Tave)

(G)

X 784lb/F 0

(-)

-8 y Y Ibm (H)

=

(-) '7?L '

Ibm (H)

=

(.-) Xr--

Ibm (I)

J. Total change in RCS Volume (Referenced to VCT temp.)

(_) Awqu \\ Ibm (I) x 0.121 gal /lb

=

(-)9 TS gal (J)

Page 29 of 59

REACTOR COOLANT SYSTEM LEAKAGE SURVEILLANCE SOP 1.7 Rev. 35 N-1 ATTACHMENT 2 MANUAL RCS WATER INVENTORY BALANCE WORK SHEET (PAGE 3 of 3)

DATE __

K. Change in System Volume

( RCS plus VCT) (t ) 4fq 8 Ca gal (F)

(

gal (W)

=

(-

+)_!

7' gaI (K)

N L. Total System leakage L(~c.7 gal (K) 2-L min (A)

(c5 (

gpm (L)

M. Previously Identified leakage (From last SE) t 7 gpm (M)

N. Unidentified Leakage I '1 gpm (L)

(J v) gpm (M)

=

Oi' 2-(

gpm (N)

A positive number indicates a net removal of mass from the system Page 30 of 59

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

Indian Point Unit 2 Determine Appropriate RWP And Take Action For High Area Radiation Alarm.

2.3.2 (2.5)

Task No.:

JPM No.:

N/A 2003 NRC A3 RO Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

Plant X

X 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:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

You have been directed to align City Water to the Charging Pumps Correct RWP used to perform task and actions to minimize exposure are taken c

4 RWP aft Alarming dosimeter Radiation Protection plan None Enter the RCA using the correct RWP to perform the task NO 5 Minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

NOTE: This JPM is intended to be performed in conjunction with the JPM performed in the RCA. Once the RWP is identified, suspend this JPM until the RCA task is complete, then continue with this JPM Performance Step: I Standard:

Comment:

Performance Step: 2 Standard:

Comment:

Performance Step: 3 Standard:

Identify RWP required for RCA entry Identifies correct RWP (032002 Task 1)

NOTE: Suspend this task when RCA entry is made. When task is complete, cue the candidate that his/her alarming dosimeter is beeping Verify dosimeter alarm condition Checks dosimeter to check dose and dose rate Cue: Inform candidate that dose rate indicates 200 mr/ho Leave the area. Contact HP Leaves to a lower dose area. Contacts HP for guidance Comment:

Terminating Cue:

When the candidate leaves the area of high radiation and informs HP, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 4 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:

IP2 2003 NRC A3 RO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1

Appendix C Page4 of 4 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

INITIATING CUE:

You have been directed to align City Water to the Charging Pumps Enter the RCA using the correct RWP to perform the task NUREG 1021, Revision 8, Supplement 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

Indian Point Unit 2 Emergency Plan Questions 2.4.29 (2.6)

Task No.:

JPM No.:

N/A 2003 NRC A4 RO Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

X Simulator Actual Performance:

Plant X

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:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

N/A Two questions answered 80% correctly E-Plan Implementing Procedures E-Plan Implementing Procedures N/A N/A NO 10 Minutes NUREG 1021, Revision 8, Supplement 1

Appendix C Page 2 of 6 Form ES-C-1 VERIFICATION OF COMPLETION ANSWER KEY NRC RO ADMIN A.4 QUESTION 1 (NO Reference allowed)

You are on shift as a spare RO, doing procedure walkdowns.

A Site Area Emergency has been declared at Indian Point. Site accountability is required.

Where are you required to report?

ANSWER:

The Central Control Room

REFERENCE:

IP-2001, Attachment 5.3 NUREG 1021, Revision 8, Supplement 1

Appendix C Page 3 of 6 Form ES-C-1 VERIFICATION OF COMPLETION ANSWER KEY NRC RO ADMIN A.4 QUESTION 2 (CLOSED Reference)

A Site Area Emergency has been declared at Indian Point.

List 5 of the Emergency Response Facilities that are staffed as a result of this event.

ANSWER:

o Central Control Room (CCR) o Technical Support Center (TSC) o Operations Support Center (OSC) o Emergency Operations Facility (EOF) o Alternate EOF (AEOF) o Joint News Center 20% each for a maximum of 100%

REFERENCE:

E-Plan NUREG 1021, Revision 8, Supplement 1

Appendix C Page 4 of 6 Form ES-C-1 VERIFICATION OF COMPLETION NRC RO ADMIN A4 QUESTION I (Closed Reference)

You are on shift as a spare RO, doing procedure walkdowns.

A Site Area Emergency has been declared at Indian Point. Site accountability is required.

Where are you required to report?

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION NRC RO ADMIN A4 QUESTION 2 (Closed Reference)

A Site Area Emergency has been declared at Indian Point.

List 5 of the Emergency Response Facilities that are staffed as a result of this event.

NUREG 1021, Revision 8, Supplement 1

Appendix C Page 6 of 6 Form ES-C-1 Verification of Completion Job Performance Measure No.:

IP2 2003 NRC A4 RO Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement I