Text

Final As- Administered Administrative Jpms for the LaSalle Initial Examination - April 2002
	ML022130463
Person / Time
Site:	LaSalle
Issue date:	04/08/2002
From:	Bielby M; NRC/RGN-III/DRS/OLB
To:	;
References
	ER-02-301
	Download: ML022130463 (98)
	v • d • e

FINAL AS-ADMINISTERED ADMINISTRATIVE JPMS FOR THE LASALLE INITIAL EXAMINATION - APRIL 2002

Facility:

LaSalle County Nuclear Station Date of Examination:

04/08/02 Examination Level (circle one):90 SRO Operating Test Number:

2002301 Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions Conduct of Operations - 1) Overtime Question (2.1.1);

2) Replaced 1) with SBLC Sodium Pentaborate Determination Conduct of (2.1.1);

Operations

3) Replaced 2) with Stack Flow Determination (2.1.1)

A.1 Conduct of Operations - License Reactivation Question (2.1.1)

Conduct of Operations Perform Core Operating Limits Surveillance (2.1.7)

Equipment A.2 Control Review an Out of Service (2.2.13)

Radiological A.3 Controls Review a Radiological Work Permit (2.3.10)

Emergency A.4 Plan Activate Plant Siren from Remote Shutdown Panel (2.4.43)

ES-301 Form 1=,*301-1

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

LaSalle County Nuclear Station Date of Examination:

04/08/02 Examination Level (circle one): RO Operating Test Number 2002301 Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions Conduct of Operations - Overtime Question (2.1.1);

2) Replaced 1) with SBLC Sodium Pentaborate Determination Conduct of (2.1.1);

Operations

3) Replaced 2) with Stack Flow Determination (2.1.1)

A.1 Conduct of Operations - License Reactivation Question (2.1.1)

Conduct of Operations Review Core Operating Limits Surveillance (2.1.7)

Equipment Review an Out of Service (2.2.13)

A.2 Control Radiological A.3 Controls Review a Radiological Work Permit (2.3.10)

Emergency Classify GSEP event, Determine PARS and Complete a NARS A.4 Plan Form for Transmittal (2.4.38)

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Conduct of Operations Questions:

Overtime Question License Reactivation Question Examination Level: SRO /SRO(I)

Date: April 8, 2002 Developed by: Raymond Keith Walton Reviewed by:

Date:

Approved by:

JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:

A.1.a Task

Title:

Overtime Question & License Reactivation Question (Conduct of Operations)

Job Performance Measure No:

K/A

Reference:

2.1.1 K/A Importance:

3.7/3.8 Examinee:

NRC Examiner:

Time Started:_______

Time Critical Task: NO Method of testing:

Performance:

Date:

Time Finished:

Estimated Completion Time: __

Simulated X

Actual Location:

X Simulator Plant Task Standard:

Required Materials:

General

References:

LS-AA-1 19, Overtime Controls, Rev. 0 OP-AA-101-701, NRC Active License Maintenance, Rev. 2.

READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task. References are available for use.

QI: The plant is in Mode 1 with normal maintenance activities in progress. You are a unit supervisor on Unit 1 working an 8-hour shift. You take the shift (after turnover) at 6:30 am. You take a total of 30 minutes for lunch and breaks on the 2n" shift. Your relief calls in sick and you must work a double shift.

You take another 30 minutes for dinner and breaks on the 3 r, shift. You commence turnover at midnight and leave the site shortly thereafter. Tomorrow, you must take the unit supervisor position on Unit 1 (after turnover) by 6:30 am. Do you need an Overtime Guidance Deviation Authorization prior to taking the watch? Why or why not? Justify your answer.

Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit Supervisor position.

Can you stand watch as the Unit Supervisor without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1.

None

JOB PERFORMANCE MEASURE Operating Test Al, Conduct of Operations 01: The plant is in Mode 1 with normal maintenance activities in progress. You are a unit supervisor on Unit 1 working an 8-hour shift. You take the shift (after turnover) at 6:30 am. You take a total of 30 minutes for lunch and breaks on the 2 nd shift. Your relief calls in sick and you must work a double shift. You take another 30 minutes for dinner and breaks on the 3r' shift. You commence turnover at midnight and leave the site shortly thereafter. Tomorrow, you must take the unit supervisor position on Unit 1 (after turnover) by 6:30 am. Do you need an Overtime Guidance Deviation Authorization prior to taking the watch? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit Supervisor position. Can you stand watch as the Unit Supervisor without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE QI: The plant is in Mode 1 with normal maintenance activities in progress. You are a unit supervisor on Unit 1 working an 8-hour shift. You take the shift (after turnover) at 6:30 am. You take a total of 30 minutes for lunch and breaks on the 2 nd shift. Your relief calls in sick and you must work a double shift. You take another 30 minutes for dinner and breaks on the 3 rd shift. You commence turnover at midnight and leave the site shortly thereafter. Tomorrow, you must take the unit supervisor position on Unit 1 (after turnover) by 6:30 am. Do you need an Overtime Guidance Deviation Authorization prior to taking the watch? Why or why not? Justify your answer.

Al:

Yes you need an Overtime Guidance Deviation Authorization prior to taking the watch. You have worked a total of 17.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months but must exclude 1.0 hour0 days 0 hours 0 weeks 0 months of non Generic Letter 82-12 hours (breaks and meals). This totals 16.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months worked in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period. You must have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of rest prior to taking the watch. Those 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months started when you commenced turnover at midnight. Therefore, you can not take the watch prior to 8:00 am the following day.

Reference LS-AA-119, Overtime Controls

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit Supervisor position.

Can you stand watch as the Unit Supervisor without instruction today? Why or why not? Justify your answer.

A2: No. RO and SRO licenses can be maintained by actively performing the functions of RO (Unit NSO or Assistant NSO) or SRO (Shift Manager or Unit Supervisor) for a minimum of seven 8-hour or five 12-hour shifts per calendar quarter.

Reference:

OP-AA-101-701, NRC Active License Maintenance (CUE) THIS COMPLETES THIS JPM Record Stop Time:

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Conduct of Operations Questions:

Overtime Question License Reactivation Question Examination Level: RO

,1 Date: April 8, 2002 Developed by: Raymond Keith Walton Reviewed by:

Date:

Approved by:

Date:

Examination Level: RO A\\ý

JOB PERFORMANCE MEASURE Facility:

LaSalle Nuclear Station Task No:

A.1.a Task

Title:

Overtime Question & License Reactivation Question (Conduct of Operations)

Job Performance Measure No:

K/A

Reference:

2.1.1 K/A Importance:

3.7/3.8 Examinee:

NRC Examiner:

Date:

Time Started:

Time Critical Task: NO Time Finished:

Estimated Completion Time:

Method of testing:

Performance:

Simulated X

Actual Location:

X Simulator Plant Task Standard:

Required Materials:

General

References:

LS-AA-1 19, Overtime Controls, Rev. 3.

OP-AA-1 01-701, NRC Active License Maintenance, Rev. 2.

READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task. References can be used.

Q1: The plant is in Mode 1 with normal maintenance activities in progress. You are a reactor operator on Unit 1 working an 8-hour shift. You take the shift (after turnover) at 6:30 am. You take a total of 30 minutes for lunch and breaks on the 2 nd shift. Your relief calls in sick and you must work a double shift.

You take another 30 minutes for dinner and breaks on the 3 rd shift. You commence turnover at midnight and leave the site shortly thereafter. Tomorrow, you must take the reactor operators position on Unit 1 (after turnover) by 6:30 am. Do you need an Overtime Guidance Deviation Authorization prior to taking the watch? Why or why not? Justify your answer.

Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit NSO position. Can you stand watch as the Unit NSO without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1.

None

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Conduct of Operations Questions:

SBLC Sodium Pentaborate Question License Reactivation Question Examination Level: RO Date: April 8, 2002 Developed by: Raymond Keith Walton Date:

JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:

A.1.a Task

Title:

SBLC Sodium Pentaborate & License Reactivation Questions (Conduct of Operations)

Job Performance Measure No:

K/A

Reference:

2.1.1 K/A Importance:

3.7/3.8 Examinee:

NRC Examiner:

Time Started:

Date:

Time Finished:

Estimated Completion Time:

10 min Time Critical Task: NO Method of testing:

Performance:

Simulated X

Actual Location:

X Simulator Plant Task Standard:

Identify that Sodium Pentaborate Solution does not meet technical requirements.

Identify that individual does not meet requirements for license reactivation.

Required Materials:

LCP-1 10-9, Attachment A, "Sample Information Sheet for Sodium Pentaborate."

LOS-AA-S101, Figure A-3, Sodium Pentaborate Solutions Temperature/Concentration Rqts.

LOS-AA-S1 01, Figure A-4, Sodium Pentaborate Volume/Concentration Rqts.

General

References:

OP-AA-1 01-701, NRC Active License Maintenance, Rev. 2.

READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task. References can be used.

QI: Chemistry has completed LCP-1 10-9, "Determination of High Range Boron (Sodium Pentaborate),"

for the Unit 1 Standby Liquid Control (SBLC) Storage Tank. The shift Manager has asked you to review the attached LCP-1 10-9, Attachment A surveillance results for the Unit 1 SBLC storage tank. Based on these results, does the Unit 1 SBLC Storage Tank meet Technical Specification surveillance requirements? Why or why not.

Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit NSO position. Can you stand watch as the Unit NSO without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1.

None

JOB PERFORMANCE MEASURE Operating Test Al, Conduct of Operations QI:

Chemistry has completed LCP-1 10-9, "Determination of High Range Boron (Sodium Pentaborate)," for the Unit 1 Standby Liquid Control (SBLC) Storage Tank. The shift Manager has asked you to review the attached LCP-1 10-9, Attachment A surveillance results for the Unit 1 SBLC storage tank.

Based on these results, does the Unit 1 SBLC Storage Tank meet Technical Specification surveillance requirements? Why or why not.

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit NSO position. Can you stand watch as the Unit NSO without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE QI: Chemistry has completed LCP-110-9, "Determination of High Range Boron (Sodium Pentaborate)," for the Unit 1 Standby Liquid Control (SBLC) Storage Tank. The shift Manager has asked you to review the attached LCP-1 10-9, Attachment A surveillance results for the Unit 1 SBLC storage tank. Based on these results, does the Unit 1 SBLC Storage Tank meet Technical Specification surveillance requirements? Why or why not.

Al:

No, the SBLC solution does not meet Technical Specification surveillance requirement 3.1.7.1 and 3.1.7.5. since the solution/volume numbers are outside the acceptable range. (It does meet TS SR 3.1.7.2. since temperature/concentration requirements are within the acceptable operating region).

Reference:

LOS-AA-1 01 Figures A-3 & A-4.

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit NSO position. Can you stand watch as the Unit NSO without instruction today? Why or why not? Justify your answer.

A2: No. RO and SRO licenses can be maintained by actively performing the functions of RO (Unit NSO or Assistant NSO) or SRO (Shift Manager or Unit Supervisor) for a minimum of seven 8-hour shifts or five 12-hour shifts per calendar quarter.

Reference:

OP-AA-1 01-701, NRC Active License Maintenance (CUE) THIS COMPLETES THIS JPM Record Stop Time:

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Conduct of Operations Questions:

SBLC Sodium Pentaborate Question License Reactivation Question Examination Level: SRO /SRO(l)

Date: April 8, 2002 Developed by: Raymond Keith Walton Date:

JOB PERFORMANCE MEASURE Facility:

LaSalle Nuclear Station Task No:

A.1.a Task

Title:

SBLC Sodium Pentaborate & License Reactivation Questions (Conduct of Operations)

Job Performance Measure No:

K/A

Reference:

2.1.1 K/A Importance:

3.7/3.8 Examinee:

NRC Examiner:

Date:

Time Started:

Time Finished:

Time Critical Task: NO Estimated Completion Time:

10 min Method of testing:

Performance:

Simulated Location:

X Simulator X

Actual Plant Task Standard:

Identify that Sodium Pentaborate Solution does not meet technical requirements.

Identify that individual does not meet requirements for license reactivation.

Required Materials:

LCP-1 10-9, Attachment A, "Sample Information Sheet for Sodium Pentaborate."

LOS-AA-S1 01, Figure A-3, Sodium Pentaborate Solutions Temperature/Concentration Rqts.

LOS-AA-S1 01, Figure A-4, Sodium Pentaborate Volume/Concentration Rqts.

General

References:

OP-AA-101 -701, NRC Active License Maintenance, Rev. 2.

READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task. References can be used.

QI: Chemistry has completed LCP-1 10-9, "Determination of High Range Boron (Sodium Pentaborate),"

for the Unit 1 Standby Liquid Control (SBLC) Storage Tank. The shift Manager has asked you to review the attached LCP-1 10-9, Attachment A surveillance results for the Unit 1 SBLC storage tank. Based on these results, does the Unit 1 SBLC Storage Tank meet Technical Specification surveillance requirements? Why or why not.

Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit Supervisor position.

Can you stand watch as the Unit Supervisor without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1.

None

JOB PERFORMANCE MEASURE Operating Test Al, Conduct of Operations QI:

Chemistry has completed LCP-110-9, "Determination of High Range Boron (Sodium Pentaborate)," for the Unit 1 Standby Liquid Control (SBLC) Storage Tank. The shift Manager has asked you to review the attached LCP-1 10-9, Attachment A surveillance results for the Unit 1 SBLC storage tank.

Based on these results, does the Unit 1 SBLC Storage Tank meet Technical Specification surveillance requirements? Why or why not.

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit Supervisor position. Can you stand watch as the Unit Supervisor without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE Q1: Chemistry has completed LCP-1 10-9, "Determination of High Range Boron (Sodium Pentaborate)," for the Unit 1 Standby Liquid Control (SBLC) Storage Tank. The shift Manager has asked you to review the attached LCP-1 10-9, Attachment A surveillance results for the Unit 1 SBLC storage tank. Based on these results, does the Unit 1 SBLC Storage Tank meet Technical Specification surveillance requirements? Why or why not.

Al: No, the SBLC solution does not meet Technical Specification surveillance requirement 3.1.7.1 and 3.1.7.5. since the solution/volume numbers are outside the acceptable range. (It does meet TS SR 3.1.7.2. since temperature/concentration requirements are within the acceptable operating region).

Reference:

LOS-AA-1 01 Figures A-3 & A-4.

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit Supervisor position. Can you stand watch as the Unit Supervisor without instruction today? Why or why not? Justify your answer.

A2: No. RO and SRO licenses can be maintained by actively performing the functions of RO (Unit NSO or Assistant NSO) or SRO (Shift Manager or Unit Supervisor) for a minimum of seven 8-hour or five 12-hour shifts per calendar quarter.

Reference:

OP-AA-1 01-701, NRC Active License Maintenance (CUE) THIS COMPLETES THIS JPM Record Stop Time:

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Conduct of Operations Questions:

Stack Flow Question License Reactivation Question Examination Level: RO Date: April 8, 2002 Developed by: Raymond Keith Walton Date:

JOB PERFORMANCE MEASURE Facility:

LaSalle Nuclear Station Task No:

A.1.a Task

Title:

Stack Flow & License Reactivation Questions (Conduct of Operations)

Job Performance Measure No:

K/A

Reference:

2.1.1 K/A Importance:

3.7/3.8 Examinee:

NRC Examiner:

Time Started:

Date:

Time Finished:

Estimated Completion Time:

10 min Time Critical Task: NO Method of testing:

Performance:

Simulated X

Actual Location:

X Simulator

___ Plant Task Standard:

Identify that Station Vent Stack effluent sample flow is not in the acceptable range.

Identify that individual does not meet requirements for license reactivation.

Required Materials:

General

References:

OP-AA-1 01-701, NRC Active License Maintenance, Rev. 2.

LOP-PR-04, Startup, Operation, and Troubleshooting of the Station Vent Stack Wide Range Radiation Monitoring System READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task. References can be used.

QI: Unit 1 and 2 are operating at full power. Instrument Maintenance Department is performing LIS-PR-02, Station Vent Main Stack Effluent and Sampler Flow Rate Monitor Calibration. IMD contacts the control room to verify proper isokinetic flow is established with Low Range pumps running per the applicable steps of LOP-PR-04.

Stack Flow (MON 029) 7.0x1 05 CFM Low Range Flow (MON 028) 1.8 CFM Is Sample Flow in an acceptable range? Explain your answer.

Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit NSO position. Can you stand watch as the Unit NSO without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1.

None

JOB PERFORMANCE MEASURE Operating Test Al, Conduct of Operations QI:

Unit 1 and 2 are operating at full power. Instrument Maintenance Department is performing LIS-PR-02, Station Vent Main Stack Effluent and Sampler Flow Rate Monitor Calibration. IMD contacts the control room to verify proper isokinetic flow is established with Low Range pumps running per the applicable steps of LOP PR-04.

Stack Flow (MON 029) 7.Oxl O0 CFM Low Range Flow (MON 028) 1.8 CFM Is Sample Flow in an acceptable range? Explain your answer.

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit NSO position. Can you stand watch as the Unit NSO without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE Q1:

Unit 1 and 2 are operating at full power. Instrument Maintenance Department is performing LIS-PR-02, Station Vent Main Stack Effluent and Sampler Flow Rate Monitor Calibration. IMD contacts the control room to verify proper isokinetic flow is established with Low Range pumps running per the applicable steps of LOP PR-04.

Stack Flow (MON 029) 7.0x105 CFM Low Range Flow (MON 028) 1.8 CFM Is Sample Flow in an acceptable range? Explain your answer.

Al: No, sample flow is too high for the given stack flow rate.

Reference:

LOP-PR-04, Step E.2.5

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit NSO position. Can you stand watch as the Unit NSO without instruction today? Why or why not? Justify your answer.

A2: No. RO and SRO licenses can be maintained by actively performing the functions of RO (Unit NSO or Assistant NSO) or SRO (Shift Manager or Unit Supervisor) for a minimum of seven 8-hour shifts or five 12-hour shifts per calendar quarter.

Reference:

OP-AA-1 01-701, NRC Active License Maintenance (CUE) THIS COMPLETES THIS JPM Record Stop Time:

ATTACHMENT A ISOKINETIC FLOW FOR THE MAIN STACK WRGM Appropriate Range of Vent Stack FlowVs Sampling FlowRate for the Wide Range Gas Monitor Based on 4

+

4 1

0.0 0,2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 SAMPLE FLOW RATE (CFM)

.8 2.0 2.2, 2.4 2.6 2.8 3.0 Low Range:

RM-23 (Mon 028)

Mid/Hi Range: RM-23 (Mon 033) + Aux Sample Pump Local Flow Indicator (GD18-N532)

Level of Use LOP-PR-04 Reference 20 of 28 Revision 18 September 27, 2001 11-9 E

7 LL C) 0 U

F F-J 4

3 1

0 SAL Study, October 8-10, 981, Table 6, 0

6 5

ATTACHMENT B ISOKINETIC FLOW FOR THE MAIN STACK WRGM (NARROW RANGE)

C~'j F

Co C'j Q0 C'j "1"J Odj U

0

.UJ H-,<

0

-J U

UJJ S1_

C\\J CO)

C0 "M

00 (0

( 9o01. x A-O) MO-I_

IOVi. iN3A Level of Use Reference 21 of 28 LOP-PR-04 Revision 18 September 27, 2001

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Conduct of Operations Questions:

Stack Flow Question License Reactivation Question Examination Level: SRO /SRO(I)

Date: April 8, 2002 Developed by: Raymond Keith Walton Date:

JOB PERFORMANCE MEASURE Facility:

LaSalle Nuclear Station Task No:

A.1.a Task

Title:

Stack Flow & License Reactivation Questions (Conduct of Operations)

Job Performance Measure No:

K/A

Reference:

2.1.1 K/A Importance:

3.7/3.8 Examinee:

NRC Examiner:

Time Started:

Date:

Time Finished:

Estimated Completion Time:

10 min Time Critical Task: NO Method of testing:

Performance:

Simulated X

Actual Location:

X Simulator Plant Task Standard:

Identify that Station Vent Stack effluent sample flow is not in the acceptable range.

Identify that individual does not meet requirements for license reactivation.

Required Materials:

General

References:

OP-AA-1 01-701, NRC Active License Maintenance, Rev. 2.

LOP-PR-04, Startup, Operation, and Troubleshooting of the Station Vent Stack Wide Range Radiation Monitoring System READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task. References can be used.

Q1: Unit 1 and 2 are operating at full power. Instrument Maintenance Department is performing LIS-PR-02, Station Vent Main Stack Effluent and Sampler Flow Rate Monitor Calibration. IMD contacts the control room to verify proper isokinetic flow is established with Low Range pumps running per the applicable steps of LOP-PR-04.

Stack Flow (MON 029) 7.Oxl 0 CFM Low Range Flow (MON 028) 1.8 CFM Is Sample Flow in an acceptable range? Explain your answer.

02: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit Supervisor position.

Can you stand watch as the Unit Supervisor without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1.

None

JOB PERFORMANCE MEASURE Operating Test Al, Conduct of Operations Q1:

Unit 1 and 2 are operating at full power. Instrument Maintenance Department is performing LIS-PR-02, Station Vent Main Stack Effluent and Sampler Flow Rate Monitor Calibration. IMD contacts the control room to verify proper isokinetic flow is established with Low Range pumps running per the applicable steps of LOP-PR-04.

Stack Flow (MON 029)

Low Range Flow (MON 028) 7.Oxl O'CFM 1.8 CFM Is Sample Flow in an acceptable range? Explain your answer.

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit Supervisor position. Can you stand watch as the Unit Supervisor without instruction today? Why or why not? Justify your answer.

JOB PERFORMANCE MEASURE QI:

Unit 1 and 2 are operating at full power. Instrument Maintenance Department is performing LIS-PR-02, Station Vent Main Stack Effluent and Sampler Flow Rate Monitor Calibration. IMD contacts the control room to verify proper isokinetic flow is established with Low Range pumps running per the applicable steps of LOP PR-04.

Stack Flow (MON 029)

Low Range Flow (MON 028) 7.Oxl0 5CFM 1.8 CFM Is Sample Flow in an acceptable range? Explain your answer.

Al:

No, sample flow is too high for the given stack flow rate.

Reference:

LOP-PR-04, Step E.2.5

JOB PERFORMANCE MEASURE Operating Test A.1, Conduct of Operations Q2: During the last quarter you were on medical leave for 6 weeks, then returned to work as an operations procedure writer for the remainder of the quarter. Your requalification and respirator training is current. You have returned to the control room 4 days ago and have performed a plant tour and shift turnover. You have completed three 12-hour shifts, under instruction, in the Unit Supervisor position. Can you stand watch as the Unit Supervisor without instruction today? Why or why not? Justify your answer.

A2: No. RO and SRO licenses can be maintained by actively performing the functions of RO (Unit NSO or Assistant NSO) or SRO (Shift Manager or Unit Supervisor) for a minimum of seven 8-hour or five 12-hour shifts per calendar quarter.

Reference:

OP-AA-101-701, NRC Active License Maintenance (CUE) THIS COMPLETES THIS JPM Record Stop Time:

ATTACHMENT A ISOKINETIC FLOW FOR THE MAIN STACK WRGM

'11 r

1 A

Appropriate Range of Vent Stack FlowVs Sampling Flow Rate for the Wide Range Gas Monitor Based on

,r t-

,C SAL Study, October 8-10, 1981, Table 6 0-I -I__/____//

0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 2.2 2.4 2.6 2.8 SAMPLE FLOW RATE (CFM)

Low Range:

RM-23 (Mon 028)

Mid/Hi Range: RM-23 (Mon 033) + Aux Sample Pump Local Flow Indicator (0D18-N532)

Level of Use LOP-PR-04 Reference 20 of 28 Revision 18 September 27, 2001 L

11 9

8 7

X LL (9

O 0

-j LL Y (.9 F

LU LLJ 6

5 4

3 2

1 0

3.0 I

1

ATTACHMENT B ISOKINETIC FLOW FOR THE MAIN STACK WROM (NARROW RANGE)

O (0

C\\j U

L)

NJ It_

C\\

w 0

-j LL

_'J C ')

tt.I o

0o (O9 X IAX:YIO) MO-I NIOViS iN3A Level of Use Reference 21 of 28 LOP-PR-04 Revision 18 September 27, 2001 C\\1

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Perform Core Operating Limits Surveillance Examination Level: RO/SRO Date: April 8, 2002 Developed by: Raymond Keith Walton Date: 3/14/2002

JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:

A.1.b Task

Title:

Core Operating Limits Reports Surveillance Job Performance Measure No:

K/A

Reference:

2.1.7 K/A Importance:

Examinee:

NRC Examiner:

Time Started:

Estimated Completion Time:

5 min Time Finished:

Time Critical Task: NO Method of testing:

Performance:

Simulated X

Actual Location:

X Simulator Plant Task Standard:

Identify rod out of symmetry, MAPRAT outside of limits, 3 APRMs out of tolerance, and operating outside of MELLLA.

Required Materials:

CMSS Core Performance Log for Unit at full power - OD20 (defective).

Control Rod Position (OD 7),

Core Performance Log and Fuel Bundle Thermal Data (OD6)

Power/Flow Map General

References:

LOS-AA-S101, Unit 1 Shiftly Surveillance, Rev 7, 4/26/2001 READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task.

Initial Conditions:

You are the NSO on Unit 1. Unit 1 is operating at full power on 108% rod line.

Initiating Cue:

The 0700 PowerPlex printout has just printed. Perform LOS-AA-S1 01, Unit 1 Shiftly Surveillance, Section E.1.2.

Page 2 of 7 3.7/4.4 Date:

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1.

Faults on printouts:

MAPRAT reads 1.01 Control Rod out of sequence/symmetry 3 APRMs read greater than 2% from calculated power Outside MELLLA region Page 3 of 7

JOB PERFORMANCE MEASURE INITIAL CONDITIONS Initial Conditions:

You are the NSO on Unit 1. Unit 1 is operating at full power on 108% rod line.

Initiating Cue:

The 0700 PowerPlex printout has printed. Perform LOS-AA-S101, "Unit 1 Shiftly Surveillance,"

Section E.1.2.

Page 4 of 7

JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)

E E

F--

(I)

E z

o W3 D

0 Expected Response

1.

REVIEWs LOS-AA-S101, Unit 1 Shiftly Surveillance and OD printouts.

2.

REVIEWS printout for core symmetry and rods out of position. NOTIFIES Supervisor

3.

CHECK APLHGR by verifying MAPRAT < 1.00. REPORT that MAPRAT NOT

<1.00. IDENTIFY TS 3.2.1.1.

applies.

4.

CHECK MFLPD is < 1.00 and MFDLRX is < 1.00

5.

CHECK MCPR by verifying MFLCPR is < 1.00 Notifies Supervisor core NOT symmetrical, rod out of position.

MAPRAT NOT < 1.00 CUE: Unit Supv. will review TS ACTION statement to ensure compliance.

MFLPD is < 1.00 and MFDLRX is < 1.00 MFLCPR is < 1.00 Page 5 of 7 Element

JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)

E Uc)

E Z

o WO D

0 Expected Response

6.

CHECK difference between APRM channels & calculated power. VERIFY difference

<2%.

7.

CHECK Power to Flow Map that unit operation is in Region C (Ill).

8.

CHECK Power to Flow Map that unit is not operating outside of the analyzed MELLLA region.

(CUE) THIS COMPLETES THIS JPM Record Stop Time:

Absolute difference between APRM channels and calculated power Greater than 2% for APRMs A, D, & E.

Unit is operating in Region C (111).

Unit I.SS operating outside of analyzed MELLLA region.

Page 6 of 7 Element

E.

PROCEDURE E.1 IN Mode 1, 2 OR 3 COMPLETE ATTACHMENT A AS FOLLOWS:

E. 1.1 RECORD current plant status 1, 2 or 3:

E. 1.1.1 REQUEST an Inserted Value Summary LOP-CX-44, ATTACH to this surveillance.

E. 1.1.2 REQUEST an Alarm Summary per LOP-CX-45, EVALUATE alarms and ATTACH to this surveillance.

E. 1.2 Mode 1, 2 E. 1.2.1 DEMAND process computer program OD-7 option 2 per LOP-CX-07.

REVIEW for core symmetry, control rods out of position, and inoperable position indications and attach to this surveillance. (Tech Spec SR 3.1.3.1)

E. 1.2.2 If Core Power is > twenty-five (25) Percent, OBTAIN a copy of a CMSS Core Performance Log that was generated during this shift after OD-7 option 2 program, USE this Log for subsequent steps and ATTACH to this surveillance.

E. 1.2.2.1 If a new CMSS Core Performance Log is desired immediately, DEMAND OD-20 Option 1 per LOP-CX-20. Edit should be available within five to seven minutes. After this edit is complete, DEMAND OD-06 option I per LOP-CX-06 to obtain a copy of this Log and ATTACH to this surveillance.

E. 1.2.2.2 CHECK Average Planar Linear Heat Generation Rate (APLHGR) by verifying MAPRAT < 1.00. (Tech Spec SR 3.2.1.1)

E. 1.2.2.3 CHECK Linear Heat Generation Rate (LHGR) by verifying MFLPD is

< 1.00 and MFDLRX is < 1.00. (Tech Spec SR 3.2.3.1).

E. 1.2.2.4 CHECK Minimum Critical Power Ratio (MCPR) by verifying MFLCPR is

< 1.00. (Tech Spec SR 3.2.2.1)

E. 1.2.2.5 CHECK the absolute difference between the average power range monitor (APRM) channels and the calculated power. Verify the absolute difference is *2% RTP while operating at > 25% RTP. (Tech Spec 3.3.1.1 Actions Note 2 and SR 3.3.1.1.2) This check can be accomplished by comparing Core Power (GMWT) to APRM Calibration readings (RAP), listed on either an OD-3 or OD-20.

Level of Use LOS-AA-S 101 Reference 7 of 76 Revision 8 January 17, 2002

E. 1.2.2.6 CHECK using Power to Flow Map that unit operation is in Region C (III).

(Reference G. 1 and G.5) (Tech Spec SR 3.4.1.2)

E. 1.2.2.6.1 If Power >30% AND Flow <50% but unit is NOT inside Region A (I) or B (II) of Power to Flow Map, INITIATE stability monitoring per LOS-RR-SR1.

E. 1.2.2.7 CHECK using Power to Flow Map that unit is NOT operating outside of the analyzed MELLLA region.

E. 1.2.2.8 If Power is < 10% RTP, CHECK that all OPERABLE control rods comply with the analyzed control rod sequence. This step may be accomplished in one of two ways: verification received from the QNE or by selecting the last step inserted and verifying that no rod block was received.

(Tech Spec SR 3.1.6.1)

E. 1.3 OPM14J/OPM15J E. 1.3.1 If VG is running on either unit, PERFORM following:

E. 1.3.1.1 PERFORM Channel Check of VG Noble Gas Activity Monitor by checking LOW, MID, and HIGH readings against 0D 18-R519.

(ODCM 12.2.2-2.4.a., TRM 3.3.d)

E. 1.3.1.2 PERFORM a Channel Check of VG Effluent Flow 1(2)FR-VG009.

(ODCM 12.2.2-2.4.d)

E. 1.3.1.3 PERFORM a Channel Check of VG sample flow and VERIFY isokinetic per Figure A-1. MID/HI Range Sample Flow will indicate zero unless MID/HI Sample Pump is in operation. (ODCM 12.2.2-2.4.e)

E. 1.3.2 PERFORM a Channel Check of SVS Noble Gas Activity Monitors by checking LOW, MID, and HIGH readings against 0D 18-R521 and 0D 18-R522. (ODCM 12.2.2-2.2.a) ( TRM 3.3.d)

E. 1.3.3 PERFORM a Channel Check of SVS Effluent System Flow Rate Monitor by checking values from OD I 8-R518 to OFR-VRO 19.

(ODCM 12.2.2-2.2.d)

E. 1.3.4 PERFORM a Channel Check of SVS Sample Flow Rate Monitor (Mon 033 on 0D 18-R518) and verify isokinetic per Figure A-2. Flow indicators at skids are NOT calibratable and should only be used as a backup. (ODCM 12.2.2-2.2.e.)

Level of Use LOS-AA-S101 Reference 8 of 76 Revision 8 January 17, 2002

ATTACHMENT A UNIT 1 SHIFTLY SURVEILLANCE FOR MODE 1, 2, OR 3 Current Plant condition (1, 2, 3)

(¢) Process Computer Out of Scan Summary (OD-44)

(¢) Alarm Summary (OD-45).

(/)

Control rod position OD-7 option 2.

(/)

If> 25% power CMSS Core Performance Log mill

('/')

MAPRAT < 1.00.

(')

MFLPD and MFDLRX < 1.00.

(')

MFLCPR*< 1.00.

('/')

APRM +/- 2% RTP from calculated power

(/)

Outside region A (I) or B (II) of Power to Flow Map

(/)

Operating within the analyzed MELLLA region on the Power to Flow Map

(') If !5 10% RTP, all OPERABLE control rods comply with analyzed control rod sequence.

(,/)

Channel Check VG noble gas activity monitor.

(/')

Channel Check VG effluent flow.

(/)

Channel Check VG sample flow isokinetic per Fig. A-I

(/')

Channel Check SVS noble gas activity monitor

(/')

Channel Check SVS effluent flow

(/)

Channel Check sample flow isokinetic per Fig. A-2.

(/')

Channel Check all VC rad monitors on both Units.

Level of Use Reference 38 of 76 LOS-AA-S 101 Revision 8 January 17, 2002

OD-7 CONTROL ROD NOTCH POSITIONS, NEW SCAN, 04/16/02,

1602, LASALLE UNIT 1.

59 48 48 48 55 48 48 48 48 51 48 48 48 48 48 47 48 48 48 48 24 48 43 48 48 48 48 48 48 48 39 48 48 48 24 48 48 48 35 48 48 48 48 48 48 48 31 48 48 48 48 48 18 48 27 48 48 48 48 48 48 48 23 48 48 48 18 48 48 48 19 48 48 48 48 48 48 48 15 48 48 48 48 24 48 11 48 48 48 48 48 07 48 48 48 48 03 48 48 48 02 06 10 14 18 22 26 48 48 48 48 48 18 48 48 48 18 48 48 48 48 48 30 48 48 48 48 48 48 48 24 48 48 48 48 48 48 48 18 48 48 48 48 48 48 48 24 48 48 48 48 48 48 34 38 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 42 48 48 48 48 48 48 48 48 48 48 24 48 48 48 48 48 48 48 48 48 48 48 48 48 48 48 24 48 48 48 48 48 48 48 48 48 48 48 48 48 46 50 54 58

LaSalle-i WK-0216 02APR15-16.12.28 284 MWD/MTU TRIGR=BACKUP REV=ddec9 TBLNAM:

EOOS MCPR(P)

AND OLMCPR = 1.35 CORE PERFORMANCE LOG LONG EDIT CTP CALCULATION

HEAT BALANCE SYMMETRY : FULL STATE CONDITIONS MWE MWT EFF PR DHS ER ERATI TARGE KEFF CRD 1158.89 WT 3493.3 (100.1%)WTSUB 33.17 %

WTFLAG 1015.0 PSIA WFW 22.09 BTU/LB WD 0

T 1.08

.98 1.11 1.0000 0.0358 FLOW RATES / CORE PARAMETERS 94.2 (86.8%)

90.01 2

14.94 28.27 CRD FLOW 0.033 AVG VOID FRAC AVG POW DEN PRESS DROP (MEAS)

PRESS DROP (CALC)

MLB/HR MLB/HR MLB/HR MLB/HR

.4100 50.06 KW/L 19.02 PSIA 13.01 PSIA NUCLEAR LIMITS MPF MFLCPR MAPRAT MFDLRX MFLPD MAX (P-PCS)

FCL XENON CYCLE EXPOSURE LOCATION RING REL POWER FLCPR LOC 0.895 0.895 0.895 0.895 0.878 37-36 23-36 37-26 23-26 49-52 284.2 MWD/MTU CAVEX 12573.8 MWD/MTU 1

2 3

4 5

6 7

8

.52 1.35 1.12 1.13 0.91 1.15 0.97 0.84 NUCLEAR LIMITS APRAT LOC FDLRX LOC 0.919 0.919 0.919 0.919 0.885 55-42-09 55-42-09 55-20-09 05-20-09 45-36-07 FLPD LOC 0.900 0.900 0.900 0.900 0.892 0.875 0.875 0.875 0.875 0.868 55-42-09 55-42-09 55-20-09 05-20-09 47-36-06 TPF LOC 55-42-09 55-42-09 55-20-09 05-20-09 47-36-06 MLHGR BY TYPE LHGR LOCATION 1

14.2 31-40-21 2

13.9 31-32-20 4

11.8 35-34-20 5

10.5 33-30-20 10 8.3 37-34-20 11 9.1 35-32-20 12 u.4

.- 411.-

.1.

0

.00 0

0

.00

.00 2.550 2.540 2.520 2.520 2.510 35-32-20 31-36-20 33-30-20 31-28-20 35-35-20 FUEL TYPE TYPE LHGR LOCATION 0

.00 0

.00 U

.00 0

.00

AXIAL REL POWER*

NODE NOTCH REL-POW 25 24 00 0.435 23 02 0.738 22 04 0.932 21 06 1.042 20 08 1.092 19 10 1.103 18 12 1.089 17 14 16 16 15 18 14 20 13 22 12 24 11 26 10 9

8 7

6 5

4 3

2 1

28 30 32 34 36 38 40 42 4 /,

48 1.064

1. 037 1.016 1.005 1.004 1.017 1.039 1.066 1.092 1.113 1.119 1.102 1.054 0.963 0.821 U. 61 U 0.345 APRM READINGS 97.4 99.1 100.9 97.7 97.2 101.5 APRM GAFS 1.031 1.012 0.995 1.030 1.019 0.990 1

2.550 0.895 1.001 0.875 0.900

.00 LOCATION 35-22-20 37-36 55-42-09 55-42-09 55-42-09 31-40-21 108. 1%

100.43%

WK-0216 02APR15-16.06.48 284 MWD/MTU TRIGR BACKUP REV ddec9

- - - - -k*

CONTROL ROD DATA 02 06 10 14 18 22 26 30 24 24 18 18 18 18 24 02 06 10 14 18 22 26 30 RODS OUT OF MIRROR SYMMETRY:

SUBST.

RODS:

34 38 24

-R 18 24 34 38 42 46 50 54 58 24 24 42 46 50 59 55 DISPLAY KEY 51 R = MFLCPR 47 M = MAPRAT 43 X = FDLRX 39 C = FDLRC 35 P = PRECOND 31 D = MFLPD 27

= MULTPL.

23 19 15 11 07 03 54 58 14-23

- - - - h***

CALIBRATED LPRM READINGS *****k***

57 10.1 10.1 11.1 33.4 34.9 37.6 55.1 56.7 60.7 53.2 61.9 70.8 49 10.9 36.5 59.0 57.6 41 12.9 43.7 68.4 76.0 33 13.3 43.9 70.4 87.2 25 12.7 42.1 08.2 80.5 17 11.6 38.1 64. 4 68.3 14.2 47.4 71.1 80.3 17.7 57.4 71.8 79.1 18.6 56.7 79.8 93.0 18.8 53.7

/2. 9 80.5 16.1 50.2 74.7 87.9 11.7 39.9 64.2 68.8 08 16 16.6 55.1 70.8 79.9 19.8 60.4 80.7 88.5 21.2 59.5 75.7 81.0 20.2 60.0 8.1.6 90.2 18.4 57.8 72.5 84.0 12.9 44.7 69.5 80.6 24 16.7 54.1 78.2 96.2 20.7 59.4 75.7 81.7 21.2 60.1 81.2 88.4 21.4 60.0

/5. U 80.1 18.6 58.1 81.3 93.7 13.3 45.1 72.2 86.4 32 10.0 33.7 55.0 56.9 16.2 53.8 70.0 77.5 19.2 59.3 79.9 89.7 20.9 59.7 75.4 79.7 19.7 60.3 80.2 90.3 18.0 58.2 72.6 79.2 13.1 44.6 68.4 76.2 40 12.3 41.5 65.2 69.6 16.5 54.0 70.0 75.7 17.1 54.2 78.4 93.6 16.9 55.0 69.7 78.3 14.3 47.7 72.7 80.7 11.1 37.1 59.7 58.6 48 9.9 33.8 54.7 55.4 11.2 38.1 59.7 67.5 10.2 35.7

57. 1 62.3 10.4 34.1 55.7 53.4 56

LPRM FAILED SENSORS*

LOCATION STATUS AOIIER [VAILE)D SENSORS' SENSOR STATUS 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 09 LaSalle-I

LaSalle-1 WK-0216 02APR15-16.12.28 284 MWD/MTU TRIGR=BACKUP REV=ddec9 TBLNAM:

EOOS MCPR(P)

AND OLMCPR = 1.35 CORE PERFORMANCE LOG LONG EDIT CTP CALCULATION

HEAT BALANCE SYMMETRY

FULL STATE CONDITIONS MWE 1158.89 MWT 3493.3 (100.1 EFF 33.17 %

PR 1015.0 PSIA DHS 22.09 BTU/LB ER ERATIO TARGET KEFF CRD 1.08

.98 1.11 1.0000 0.0358 FLOW RATES /

CORE PARAMETERS WT 94.2 (86.8%)

MLB/HR WTSUB 90.01 MLB/HR WTFLAG WFW WD 2

14.94 28.27 CRD FLOW 0.033 AVG VOID FRAC AVG POW DEN PRESS DROP (MEAS)

PRESS DROP (CALC)

MLB/HR MLB/HR

.4100 50.06 KW/L 19.02 PSIA 13.01 PSIA NUCLEAR MPF MFLCPR MAPRAT MFDLRX MFLPD MAX(P-PC FCL XENON CYCLE EXPOSURE LOCATION RING REL POWER FLCPR LOC 0.895 0.895 0.895 0.895 0.878 37-36 23-36 37-26 23-26 49-52 FLPD LOC 0.900 0.900 0.900 0.900 0.892 284.2 MWD/MTU CAVEX 12573.8 MWD/MTU 1

2 3

4 5

6 7

8

.52 1.35 1.12 1.13 0.91 1.15 0.97 0.84 NUCLEAR LIMITS ***************

APRAT LOC FDLRX LOC 0.919 55-42-09 0.875 55-42-09 0.919 55-42-09 0.875 55-42-09 0.919 55-20-09 0.875 55-20-09 0.919 05-20-09 0.875 05-20-09 0.885 45-36-07 0.868 47-36-06 TPF LOC 55-42-09 55-42-09 55-20-09 05-20-09 47-36-06 2.550 2.540 2.520 2.520 2.510 35-32-20 31-36-20 33-30-20 31-28-20 35-35-20 MLHGR BY FUEL TYPE ****k*

TYPE LHGR LOCATION 1

14.2 31-40-21 2

13.9 31-32-20 4

11.8 35-34-20 5

10.5 33-30-20 10 8.3 37-34-20 11 9.1 35-32-20 12 6.4 51-41-21 0

0 0

.00

.00 TYPE LHGR LOCATION 0

.00 0

.00

AXIAL REL POWER*

NODE NOTCH REL-POW 25 24 00 0.435 23 02 0.738 22 04 0.932 21 06 1.042 20 08 1.092 19 10 1.103 18 12 1.089 17 16 15 14 13 12 11 10 9

8 7

6 5

4 3

2 1

14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 48 1.064

1. 037 1.016 1.005 1.004 1.017 1.039 1.066 1.092 1.113 1.119 1.102 1.054 0.963 0.821 0.618 0.345 APRM READINGS APRM GAFS 97.4 99.1 100.9 97.7 97.2 101.5 1.031 1.012 0.995 1.030 1.019 0.990 LIMITS 2.550 0.895 1.001 0.875 0.900 S)

.00 LOCATION 35-22-20 37-36 55-42-09 55-42-09 55-42-09 31-40-21 108.1%

100.43%

1

%)

WK-0216 02APR1S-16.06.48 284 MWD/MTU TRIGR=BACKUP REV=ddec9

- - - - ~**~***

CONTROL ROD DATA ************

02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 24 18 02 06 10 14 18 24 L 18 24 22 26 18 18 30

--3 34 24 18 24 38 24 24 42 46 50 54 58 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 DISPLAY KEY R = MFLCPR M = MAPRAT X = FDLRX C = FDLRC P = PRECOND D = MFLPD

= MULTPL.

RODS OUT OF MIRROR SYMMETRY:

SUBST.

RODS:

CALIBRATED LPRM 10.1 10.1 11.1 33.4 34.9 37.6 55.1 56.7 60.7 53.2 61.9 70.8 14.2 47.4 71.1 80.3 17.7 57.4 71.8 79.1 18.6 56.7 79.8 93.0 18.8 53.7 72.9 80.5 16.1 50.2 74.7 87.9 11.7 39.9 64.2 68.8 08 16 16.6 55.1 70.8 79.9 19.8 60.4 80.7 88.5 21.2 59.5 75.7 81.0 20.2 60.0 81.6 90.2 18.4 57.8 72.5 84.0 12.9 44.7 69.5 80.6 24 16.7 54.1 78.2 96.2 20.7 59.4 75.7 81.7 21.2 60.1 81.2 88.4 21.4 60.0 75.8 80.1 18.6 58.1 81.3 93.7 13.3 45.1 72.2 86.4 32

LPRM FAILED SENSORS*

LOCATION STATUS READINGS 10.0 33.7 55.0 56.9 16.2 53.8 70.0 77.5 19.2 59.3 79.9 89.7 20.9 59.7 75.4 79.7 19.7 60.3 80.2 90.3 18.0 58.2 72.6 79.2 13.1 44.6 68.4 76.2 40 12.3 41.5 65.2 69.6 16.5 54.0 70.0 75.7 17.1 54.2 78.4 93.6 16.9 55.0 69.7 78.3 14.3 47.7 72.7 80.7 11.1 37.1 59.7 58.6 48 9.9 33.8 54.7 55.4 11.2 38.1 59.7 67.5 10.2 35.7 57.1 62.3 10.4 34.1 55.7 53.4 56

OTHER FAILED SENSORS*

SENSOR STATUS 59 55 51 47 43 39 35 31 27 23 19 15 11 07 03 57 14-23 49 10.9 36.5 59.0 57.6 41 12.9 43.7 68.4 76.0 33 13.3 43.9 70.4 87.2 25 12.7 42.1 68.2 80.5 17 11.6 38.1 64.4 68.3 09 LaSalle-i

(

0 5

10 15 20 25 Core Flow (Percent) 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 120 115 110 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5

A:l 0

5 10 15 20 25 30 35 Follow-Up Procedure: LOA-RR-101 Level of Use Continuous 40 45 50 55 60 65 Core Flow (M#/Hr) 70 75 80 85 90 95 100 105 Reference Procedure: LOA-RR-101 39 of 41 LOA-RR-101 Revision 10 January 17, 2002

(

ATTACHMENT A HARDCARD - LASALLE COUNTY NUCLEAR STATION POWER - TO - FLOW MAP LaSalle County Nuclear Station Power-to-Flow Map, Rev. 0

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Recirculation Loops Operating 3.4.1 20 30 40 50 60 70 80 90 100 Total Core Flow (% of Rated)

Figure 3.4.1-1 (Page 1 of 1)

Power versus Flow LaSalle I and 2 Amendment No.

147/133 0.-,

0 H

0-)

0 100 90 80 70 60 50 40 30 20 10 0

3.4.1-7

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

Page 7 of 7 0l

CLEARANCE #

CHK#

CHECKLIST TYPE: 3 MO SFH OP-AA-101-201 Revision 6 Page 44 of 52 RH PC@

PRINCIPLE EQUIPMENT:

Exceptional C/O: D I E21-C0142 Condition Dependent 0/0: D Mode Dependent 0/0: D Production Risk C/O: D ATTACHMENT 4 Clearance Hang Checklist Preparation, Approval and Authorization Page 1 of I CLEARANCE HANG CHECKLIST PREPARATIOW AkIfl APRtUAt Required Actions Approve Approve Risk Consideration Special instructions reviewed/entered N

Causes Effects Exceptional C/O criteria evaluated Fuse or circuit board removal Auto-starts Containment Integrity considered

____DrainingNenting Equipment trips C/O Positions and Sequences correct

,.__Isolating instruments Reactor Protection Logic sigrals All attached work scope understood Jumper installation Control Room Indication char.ges Drain and vent requirements identified (drain permits)

Breaking daisy chains Control Room Annunciators Tech Spec applicability assessed Isolating control air Opposite Unit/Train affects Fire Protection concerns noted/addressed De-energizing control power Turbine Supervisory Logic C/O step types and tag types correct Lifting of Leads Radioactive Release C/O Production Risk Considered (next column)

__--_Installing Grounds Loss of Main Condenser Vac-urm C/O Production Risk Critical Steps Identified Requestor notified if work not isolated as requested CLEARANCE PRE-HANG SUPERVISORY AUTHORIZATION N/A)

Plant conditions acceptable C/O Production Risks Considered HLA criteria evaluated and initiated if required Probabilistic Risk Assessment/Shutdown Risk Assessment considered/OSPRE Fire Protection actions initiated Tech Spec requirements met/initiated Redundant Train operability assessed Applicable procedure prerequisites satisfied M

I ýý (I (P I

OP-AA-1 01-201 Revision 6 Page 39 of 52 ATTACHMENT 2 Personal Clearance Form Part 1: Hang/Lift Section Page 1 of 4 EXCEPTIONAL DCO PERSON1AL -LEARANCE#.....

MASTER TAG LOCATION:...

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DATE:

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EQUIP. TAG /EQUIPMENT NAME CIO TAG C/O C/O VERIF.

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SEQ TYPE POSITION BY BY VERIF.

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DATE: _"-LCOta_

.PAI-f" ON ORDERS OF:

/9 1/A)7-5__.2_*.S_

SPECIAL INSTRUCTIONS Y

NO [

IFYESSEE ATTACHMENT 2PART4 FIRST APPROVAL:

SECOND APPROVAL:

IF WORK V.!'LL CONTINUE UN5IE NT CREW, THEN ATTACH PART 2 WORK CONTINUATION SECTION TO RECORD ADDITIONAL HOLDER STATUS OF THE PCLR.

WORKER RELEASE:

DATEfTIME OF COMPLETION:

WORK WILL CONTINUE. SEE ATTACHED PART 2

('1)

ATTACHMENT 2 Personal Clearance Form Part 3: Testing/Manipulation Section Page 3 of 4 PERSONAL CLEARANCE#_____

RECORD ALL MANIPULATIONS (HANG AND LIFT) ASSOCIATED WITH THIS PCO (ADDITIONAL COPIES MAY BE USED AS NEEDED)

OP-AA-101-201 Revision 6 Page 41 of 52 PAGE OF EXCEPTIONAL PCC W

EQUIP. TAG /EQUIPMENT NAME SEQ AS FOUND MANIP.

POSIT.

VERIF.

RH RH RH VERIF.

SFTY.

____________________________POSITION POSITION BY BY SEQ POSITION By BY VERIF.

OP-AA-101-201 Revision 6 Page 42 of 52 ATTACHMENT 2 Personal Clearance Form Part 4: Special Instructions Section Page 4 of 4 EXCEPTIONAL PCO F

PCO #

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OP-AA-101-201 Revision 6 Page 40 of 52 ATTACHMENT 2 Personal Clearance Form Part 2: Work Continuation Section Page 2 of 4 EXCEPTIONAL PCO InI WORK S-,PERVISOR EXT.

BEEPER LEAD WORKER EXT.

I BEEPER SIGN ON SIGN ON S!,GN OFF S;,.N OFF I

DATE TIME DATE TIME ORIGI-NAL LEAD WORKER INFORMATION IS LISTED ON ATTACHMENT 2 PERSONAL CLEARANCE FORM PART 1: HANG/LIFT SECTION PCO #

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

Page 6 of 6

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Review a Radiation Work Permit Examination Level: RO /SRO /SRO(I)

Date: April 8, 2002 Developed by: Raymond Keith Walton Date: March 14, 2002

JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task No:

A.3 Task

Title:

Review a Radiation Work Permit Job Performance Measure No:

K/A

Reference:

2.3.10 K/A Importance:

2.9/3.3 Examinee:

NRC Examiner:

Date:

Time Started:

Time Finished:

Estimated Time to Completion:

Time Critical Task: NO Method of testing:

Performance:

X Simulated Location:

X Simulator Actual Plant Task Standard:

Worker will exceed yearly allowed dose limit but not daily dose limit. Worker needs dosimetry and Full Set of anticontamination clothing. Worker needs RP coverage into Locked High Radiation Area.

Required Materials:

A completed RWP for TIP room. Ensure dose rate on the survey map is >500rad/hr in the work area.

Expected time to complete the task is 15 minutes.

General References (Available for candidate review):

RP-AA-203, Exposure Review and Authorization, Rev 0 RP-AA-460, Controls for High and Very High Radiation Areas, Rev 1.

READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task.

Initial Conditions:

Unit 1 is operating in Mode 1. Your current radiation exposure history is as follows:

Annual Non LaSalle Station TEDE Dose 1490 mrem Annual LaSalle Station TEDE Dose 420 mrem Previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DDE dose at LaSalle from 10 mrem RWPs other than RWP 2002-0999 You are not considered to have a High Lifetime Exposure.

Initiating Cue:

You have been assigned to the FIN maintenance team and have been tasked to support a maintenance activity inside the TIP room. To complete the task will take at least 15 minutes. Review your dose and area maps to determine how to complete this task:

Without exceeding any exposure control levels What controls you need to gain access to the room Suiting requirements Dosimetry.

Page 2 of 8

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1.

Need: an RWP Rad Survey map of TIP room with radiation levels of 500 mrad/hr.

Page 4 of 8

LaSalle Station Radiation Work Permit Radiation Protection Information I RWP#:

01010805 Survey Frequency Requirements:

Shielding Recommended:

Radiation:

Routine I

None Contamination:

Routine Temporary Airborne:

Routine I Permanent Pre-Job Briefing Notes:

THIS IS A HIGH RISK RWP. A PRE-JOB BRIEFING IS REQUIRED FOR ALL HIGH RISK EVOLUTIONS.

RPT Coverage / Com I

Initial I

Continuous nents:

ENSURE ADEQUATE SURVEYS FOR WORK UNDER THIS RWP.

Identify low dose area to workers when performing job specific surveys.

Perform pre and post shield surveys as needed.

If insulation is removed from contaminated system, survey exposed area and survey/label bags of removed insulation.

Survey waste generated during job and direct transport if ALARA is compromised.

Survey catch containments during and after breach/ use.

Obtain representative air samples for breach (particulate, iodine, and/or noble gas as appropriate)and document results.

If alpha, hot particles, or noble gas conditions are encountered follow station procedures for contingency.

Old RAPS RWP#: 010162 Rev:

0 RP Supervisor ALARA Review By 064640917 12/27/2000 N/A Prepared By Terminated By 353587633 09/25/2000 Job Supervisor Page 2

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REVIEWED BY:

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fim

RP-AA-1 RADIATION PROTECTION (NO SITE APPROVAL)

RP-AA-10 RADIATION PROTECTION PROCESS DESCRIPTION (NO SITE APPROVAL)

RP-AA-1002 RADIATION PROTECTION STOP WORK AUTHORITY RP-AA-1003 RADIATION PROTECTION EVENT-FREE CLOCK RP-AA-1004 CORPORATE ROG RPM EVENT NOTIFICATIONS RP-AA-1005 CONDITION REPORT (CR) INITIATION RP-AA-1081 RADIATION PROTECTION FUNDAMENTALS RP-AA-200 NRC FORM 4 AND BADGE REGISTRATION FORM RP-AA-201 ACCESS TO THE RCA FOR ESCORTED VISITORS RP-AA-201-1001 RADIOLOGICAL INSTRUCTION SHEET FOR ESCORTED VISITORS RP-AA-202 QUANTITATIVE RESPIRATOR FIT TESTING RP-AA-203 EXPOSURE CONTROL AND AUTHORIZATION RP-AA-210 DOSIMETRY ISSUE, USAGE, AND CONTROL RP-AA-210-1001 DOSIMETRY LOGS AND FORMS RP-AA-211 PERFORMANCE TESTING OF PERSONNEL DOSIMETRY SERVICES RP-AA-212 QUARTERLY AREA TLD SURVEILLANCE hRP-AA-213 PERSONNEL EXPOSURE INVESTIGATIONS RP-AA-220 BIOASSAY PROGRAM RP-AA-221 WHOLE BODY COUNT DATA REVIEW RP-AA-222 METHODS FOR ESTIMATING INTERNAL EXPOSURE FROM IN VIVO AND IN VITRO BIOASSAY DATA RP-AA-250 EXTERNAL DOSE ASSESSMENTS FROM CONTAMINATION RP-AA-270 PRENATAL AND POSTNATAL PROGRAMS RP-AA-271 CALCULATING DOSE EQUIVALENT TO THE EMBRYO/FETUS RP-AA-280 GENERATION OF THE REGULATORY GUIDE 1.16 REPORT RP-AA-280 OCCUPATIONAL EXPOSURE REPORTING RP-AA-281 COMPARISON OF PERSONAL DOSIMETER RESULTS RP-AA-282 PERSONAL DOSE REQUESTS / NRC FORM 5 REPORT RP-AA-282 PERSONAL DOSE REQUESTS / NRC FORM 5 REPORT SUPERSEDED BY RP-AA-280 RP-AA-304 UNCONDITIONAL RELEASE SURVEYS RP-AA-350 ASSESSMENT OF RADIOLOGICALLY CONTAMINATED PERSONNEL RP-AA-351 DECONTAMINATION OF PERSONNEL RP-AA-376 RADIOLOGICAL POSTINGS, LABELING, AND MARKINGS RP-AA-376-1001 RADIOLOGICAL POSTING, LABELING, AND MARKING STANDARD RP-AA-376-2001 LABELING CONTAINERS AND MARKING OF MATERIAL FOR RADIOLOGICAL PURPOSES RP-AA-400 ALARA PROGRAM I.-

RP-AA-400 ALARA PROGRAM I.-

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

Page 8 of 8

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Sound Site Assembly Siren from Remote Shutdown Panel Examination Level: RO Date: April 8, 2002 Developed by: Raymond Keith Walton Reviewed by:

Date: March 21, 2002 Date:

Date:

Approved by:

JOB PERFORMANCE MEASURE Facility: LaSalle Nuclear Station Task

Title:

NARS Form Notification K/A

Reference:

2.4.43 Examinee:

NRC Examiner:

Time Started:

Task No:

A.4 K/A Importance:

2.8/3.5 Date:

Time Finished:

Estimated Time to Completion:

Method of testing:

Performance:

X Simulated Actual Time Critical Task: NO Location:

Simulator X

Plant Task Standard:

Required Materials:

EP-AA-1 13, Protective Actions, Rev 2 LOP-CQ-02, LOP-CQ-02, Rev. 3,4/29/98 General

References:

EP-AA-1 13, Protective Actions READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task.

Initial Conditions:

You are an extra NSO. An Emergency has been declared on Unit 1. The control room has been evacuated.

Initiating Cue:

The Shift Manager has directed you to sound the assembly siren from the remote shutdown panel lAW EP-AA-1 13, "Protective Actions," Attachment 4, step 1.1.2.

Page 2 of 6

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1. None (In Plant)

Page 3 of 6

JOB PERFORMANCE MEASURE Initial Conditions:

You are an extra NSO. An Emergency has been declared on Unit 1. The control room has been evacuated.

Initiating Cue:

The Shift Manager has directed you to sound the assembly siren from the remote shutdown panel lAW EP-AA-113, "Protective Actions", Attachment 4, step 1.1.2.

Page 4 of 6

JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)

CUE: Provide candidate copy of completed NARS form.

START time clock when candidate understands task.

Element E

H-CO E

Z o

CO D

0 Expected Response

1. REFERs to EP-AA-1 13, Attach. 4 Reviews EP-AA-1 13, attachment 4.

2. LOCATES Remote Shutdown Panel

3. PUSHES large button labeled, "EVAC Initiate".

4. Uses plant Gaitronics mounted on column south of divisional separation door (in Div 1 room) aisle-way.

"Attention, attention, plant assembly has been ordered. All persons are to report to your assigned assembly area."

CUE: This completes this JPM.

Enter Stop Time:

Locates Remote Shutdown Panel.

Cue: Alarm sounds for 2 minutes.

(May use time compression)

Locates Gaitronics (may also use plant telephone by dialing #4747, although this message is limited by a 30 second timer.)

Repeats message 3 times maximum over the next 10 - 15 minutes.

Page 5 of 6

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

Page 6 of 6

LASALLE COUNTY NUCLEAR STATION JOB PERFORMANCE MEASURE Classify the GSEP Event, Determine PARS and Complete a NARS Form for Transmittal Examination Level: SRO / SRO(U)

Date: April 8, 2002 Developed by: Raymond Keith Walton Date: 3/14/2002

JOB PERFORMANCE MEASURE Facility:

LaSalle Nuclear Station Task No:

A.4 Task

Title:

Classify GSEP Event, Determine PARS and Complete a NARS Form for Transmittal K/A

Reference:

2.4.38 Examinee:

NRC Examiner:

Time Started:

K/A Importance:

2.2/4.0 Date:

Time Finished:

Time Critical Task: YES, From time candidate classifies the event, the candidate must complete NARS form and complete data transmission within 15 minutes.

Estimated Time to Completion:

10 min Method of testincq:

Performance:

X Simulated Actual Location:

Task Standard:

Classify event as FG-1 and recommend evacuation of Sub-area 1.

Required Materials:

Blank NARS form from EP-AA-1 14, Attachment 1.

General

References:

EP-AA-1 14, Notifications, Rev. 0 LaSalle JPM P-EP-04, Rev 3, 7/21/1999 READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. Tell me when you have successfully complete the task.

Initial Conditions:

You are the Shift Manager with the following plant conditions: Unit 1 has experienced a small LOCA. All rods are in, Drywell pressure is stable a 4 psig, All required PCIS isolations are complete, Reactor pressure is 800 psig and lowering slowly, Reactor level is 36" with the MDRFP on line, Containment rad levels have risen to 8100 R/hr, Ul SBGT operating maintaining dP at -0.3 inch water. Stack WRGM reading 7.8E2 uCi/sec, SBGT WRGM reading 6.5E2 uCi/sec. The A-Model is NOT available.

Initiating Cue:

As Acting Station Director, classify this GSEP event, determine the Protective Action Recommendations for Offsite Personnel and prepare a Nuclear Accident Reporting System form for transmittal by a GSEP communicator. This is a time critical JPM.

Page 2 of 6 X

Simulator Plant

JOB PERFORMANCE MEASURE Simulator Setup Instructions:

1.

None Page 3 of 6

JOB PERFORMANCE MEASURE INITIAL CONDITIONS This is a Time Critical JPM.

Initial Conditions:

You are the Shift Manager with the following plant conditions:

Unit 1 has experienced a small LOCA.

All rods are in Drywell pressure is stable a 4 psig, (no venting in progress)

All required PCIS isolations are complete Reactor pressure is 800 psig and lowering slowly Reactor level is 36" with the MDRFP on line Containment rad levels have risen to 8100 R/hr Ul SBGT operating maintaining dP at -0.3 inch water Stack WRGM reading 7.8E2 uCi/sec, SBGT WRGM reading 6.5E2 uCi/sec.

The A-Model is NOT available.

Wind Direction is 295 degrees.

Wind Speed is 10 mph.

Initiating Cue:

As the Acting Station Director, you must:

1.

Classify this GSEP event

2.

Determine the Protective Action Recommendations for Offsite Personnel

3.

Prepare a Nuclear Accident Reporting System form for transmittal by a GSEP communicator.

Page 4 of 6

JOB PERFORMANCE MEASURE (Denote critical steps with an asterisk)

Provide candidate with copy of EP-AP-1 14, Notifications after candidate locates procedure.

Element E

I-E I--

E z

o Co) 0 Expected Response

"*1. Determines that GSEP event is an General Emergency FG-1.

2. Locates/Review EP-AP-1 14-100 Locates blank copy of NARs form.

3. FILLS out NARS form.

4. REFERS to EP-AA-1 11, Attach.

5, "LaSalle PAR Determination Flowchart."

CUE: Start time for 15-minute reporting requirement CUE: Provide blank NARS form to candidate.

Fills out NARS form as follows:

1. Status: Exercise or Drill.

2. Station: LaSalle

3. Accident Classification: General Emergency.

4. Accident Classification Time: actual time.

5. Release to Env.: Occurring or None.

6. Type of Release: Gas.

NARS Form Block 9, Recommended Actions: Candidate Circles [B]. Enters "Sub Area 1 "

5. Task Completed.

Hands form to examiner.

(CUE) THIS COMPLETES THIS JPM Record Stop Time:

Page 5 of 6

ATTACHMENT 1 Nuclear Accident Reporting System (NARS)

Page 5 of 6 EP-AA-1 14-100 Revision 2 Page 8 of 16 STATE MESSAGE NO.

JA

1. STATUS

2.

S

[A] ACTUAL

[V RILL/EXERCISE

[E

3. ONSITE CONDITION

[A] UNUSUAL EVENT

[B] ALERT

[C SITE AREA EMERGENCY ENERAL EMERGENCY RECOVERY

[F] TERMINATED TATION

,] BRAIDWOOD

[C] CLINTON 3] BYRON

[D] DRESDEN

4. ACCIDENT CLASSIFIED TIME:

DATE:

EAL#:

P&

(OLASALLE

[G] ZION

[F] QUAD CITIES ACCIDENT TERMINATED TIME:

/o[I DATE:

N (A

5. RELEASE STATUS

[A] NONE

([-9CCURRING TERMINATED

6. TYPE OF RELEASE A] NOT APPLICABLE (jGASEOUS 7] LIQUID

7. WIND DIR (DEGREES FROM)

8. WIND SPEED

[A] METERS/SEC.:

OMILES/HR.: -1.Q

9.

RECOMMENDED ACTIONS UTILITY RECOMMENDATION

[A] NONE O*VACUATE SUB-AREAS (ILLINOIS):

[C] EVACUATE SUB-AREAS (IOWA):

STATE RECOMMENDATION

[D] NONE

[E] SHELTER SUB-AREAS:

[F] EVACUATE SUB-AREAS:

[G] RECOMMEND POTASSIUM IODIDE

[H] COMMENCE RETURN OF PUBLIC

[I] OTHER

10. ADDITIONAL INFORMATION

11. TRANSMITTED BY:

NAME I

(KI) PER PROCEDURES PHONE NUMBER

[A] EXELON:

[B] STATE:

[C] COUNTY:

12. RECEIVED BY:

NAME ORGANIZATION Approved By:

Verified With:

NAME s;.

M~j4C_

ORGANIZATION UTILITY MESSAGE NO. _A TIME/DATE TIME/DATE TIME/DATE

/

ATTACHMENT 1 Nuclear Accident Reporting System (NARS)

Page 6 of 6 EP-AA-1 14-100 Revision 2 Page 9 of 16 Initia El n]

Braidwood (UE, Alert, Site Area and escalated Generals)

NARS Code 20

1 Final

Illinois EMA El Illinois DNS El (Initial General Emergency Only)

NARS Code 38 Initial Final El

Illinois EMA E]

El

Grundy Co. Sheriff El El # Kankakee Co. Sheriff El El

Will County Sheriff El El Illinois DNS El El Grundy Co. EMA El El Kankakee Co. EOC El El Will Co. EOC El Byron (UE, Alert, Site Area and escalated Generals)

NARS Code 20 Initial Final El # Illinois EMA El El Illinois DNS E]

(Initial General Emergency Only)

NARS Code 37 Initial Final L]f# Illinois EMA El LI #-1 Ogle Co. Sheriff El El #-1 Rochelle Police El LI Illinois DNS El El Ogle Co. ESDA El El Ogle Co. EOC El Commercial numbers:

IEMA 217-782-7860 IDNS 217-785-0600 (QC only)

Iowa EMD 515-281-3231 ROLL CALL Initial Roll Call Complete:

(time / date)

Initial El LI

Illinois EMA Illinois DNS LaSalle (UE, Alert, Site Area and escalated Generals)

NARS Code 20 Final E]

El (Initial General Emergency Only)

NARS Code 25 Initial Final El

Illinois EMA El E] # Grundy Co. Sheriff El E] # LaSalle Co. Sheriff El E]

Illinois DNS -

El El Grundy Co. EMA El E]

LaSalle Co. ESDA El NOTE: # Indicates that this agency is required to be notified within 15 minutes.

-1, Only one needs to answer for notification Clinton (UE, Alert, Site Area and escalated Generals)

NARS Code 98 Initial Final Rl

Illinois EMA nl El Illinois DNS El (Initial General Emergency Only)

NARS Code 36 Initial Final El

Illinois EMA Ql El

DeWitt Co. Sheriff El El Illinois DNS El El DeWitt Co. EOC El Dresden (UE, Alert, Site Area and escalated Generals)

NARS Code 20 Initial Final El # Illinois EMA El El Illinois DNS El (Initial General Emergency Only)

NARS Code 22 Initial Final El #Illinois EMA El

[Ef #Grundy Co. Sheriff Fl El #Kendall Co. Sheriff El El #Will County Sheriff El El Illinois DNS El El Grundy Co. EMA El LI Kendall Co. EOC El El Will Co. EOC El Quad Cities (UE, Alert, Site Area and escalated General Emergencies)

NARS Code 43 Initial Final E] # Illinois EMA El El # Iowa EMD El E] Illinois DNS El El Scott Co. Sheriff El El Clinton Co. EOC El (Initial General Emergency Only)

NARS Code 23 Initial Final E] # Illinois EMA Fl LI#

Iowa EMD El El # Clinton Co. EOC El El #Rock Island Co. Sheriff El El # Whiteside Co. Sheriff EL El # Scott Co. Sheriff El El Whiteside Co. ESDA El E] Rock Island ESDA El E] Illinois DNS El

ATTACHMENT 1 Nuclear Accident Reporting System (NARS)

Page 5 of 6 UTILITY MESSAGE NO.

ST*

1.

STATUS

2.

STATION

[A] ACTUAL

[A] BRAIDWOOD

[C] CLINTON

[B] DRILL/EXERCISE

[B] BYRON

[D] DRESDEN

3. ONSITE CONDITION

4. ACCIDENT CLASSIFIED

[A] UNUSUAL EVENT TIME:

[B] ALERT

[C] SITE AREA EMERGENCY DATE:

[D] GENERAL EMERGENCY EAL#:

[El RECOVERY

[F] TERMINATED

5. RELEASE STATUS

6. TYPE OF RELEASE

7. WIND DIR

[A] NONE

[A] NOT APPLICABLE

[B] OCCURRING

[B] GASEOUS (DEGREES FROM

[C] TERMINATED

[C] LIQUID

9.

RECOMMENDED ACTIONS UTILITY RECOMMENDATION

[A] NONE

[B] EVACUATE SUB-AREAS (ILLINOIS):

[C] EVACUATE SUB-AREAS (IOWA):

STATE RECOMMENDATION

[D] NONE

[E] SHELTER SUB-AREAS:

[F] EVACUATE SUB-AREAS:

[G] RECOMMEND POTASSIUM IODIDE (KI) PER PROCEDURES

[H] COMMENCE RETURN OF PUBLIC

[I] OTHER

10. ADDITIONAL INFORMATION EP-AA-114-100 Revision 2 Page 8 of 16 ATE MESSAGE NO.

[E] LASALLE

[G] ZION

[F] QUAD CITIES ACCIDENT TERMINATED TIME:

DATE:

8. WIND SPEED

[A] METERS/SEC.:

[B] MILES/HR.:

11. TRANSMITTED BY:

[A] EXELON:

[B] STATE:

[C] COUNTY:

12. RECEIVED BY:

NAME NAME NAME PHONE NUMBER ORGANIZATION ORGANIZATION Approved By:

Verified With:

TIME/DATE TIME/DATE TIME/DATE

EP-AA-1 14-100 Revision 2 Page 9 of 16 ATTACHMENT I Nuclear Accident Reporting System (NARS)

Page 6 of 6 ROLL CALL Initial Roll Call Complete:

Braidwood LaSalle (UE, Alert, Site Area and (time / date)

(UE, Alert, Site Area and escalated Generals) escalated Generals)

NARS Code 20 NARS Code 20 Initial Final Clinton Initial Final U

Illinois EMA CU (UE, Alert, Site Area and E]

Illinois EMA

[i El Illinois DNS El escalated Generals)

EU Illinois DNS U

NARS Code 98 (Initial General Emergency Only)

Initial Final (Initial General Emergency Only)

NARS Code 38 D

Illinois EMA E]

NARS Code 25 Initial Final El Illinois DNS U

Initial Final nI

Illinois EMA

[E]

D

Illinois EMA Eli n

Grundy Co. Sheriff El (Initial General Emergency Only)

El # Grundy Co. Sheriff LI El # Kankakee Co. Sheriff It NARS Code 36

[] # LaSalle Co. Sheriff

[]

17

Will County Sheriff EU FL Illinois DNS EL Ln Illinois DNS U]

El

Illinois EMA EI L]

Grundy Co. EMA EU Ln Grundy Co. EMA El

[]

DeWitt Co. Sheriff EU

[U LaSalle Co. ESDA U

n Kankakee Co. EOC Li U

Illinois DNS nI LI Will Co. EOC U

DeWitt Co. EOC LI Quad Cities (UE, Alert, Site Area and Byron Dresden escalated General Emergencies)

(UE, Alert, Site Area and (UE, Alert, Site Area and escalated Generals) escalated Generals)

NARS Code 43 NARS Code 20 NARS Code 20 Initial Final Initial Final Initial Final El # Illinois EMA LI n # Illinois EMA EU # Illinois EMA LI Ul # Iowa EMD El nI Illinois DNS U

U Illinois DNS E]

U Illinois DNS EU F] Scott Co. Sheriff U

(Initial General Emergency Only)

[I Clinton Co. EOC U

NARS Cde 37NARS Code 22 Initial Final Initial Final (Initial General Emergency Only)

LI# Illinois EMA E lI #Illinois EMA EL NARS Code 23 LI #-1 Ogle Co. Sheriff Ul Ul #Grundy Co. Sheriff EI Initial Final U #-1 Rochelle Police U

Ul #Kendall Co. Sheriff El Ul # Illinois EMA EL U Illinois DNS Ul U] #Will County Sheriff LI U # Iowa EMD EL U Ogle Co. ESDA U]

U7 Illinois DNS U]

Ul # Clinton Co. EOC EU U] Ogle Co. EOC Ul El Grundy Co. EMA EU EL

Rock Island Co. Sheriff EU LI Kendall Co. EOC U1 U # Whiteside Co. Sheriff

[U Commercial numbers:

U Will Co. EOC U]

U # Scott Co. Sheriff Ul Com mer217782-786s U Whiteside Co. ESDA LI IFLA 217-782-71360 r-..

(QC only)

Iowa EMD 515-281-3231 NOTE: # Indicates that this agency is required to be notified within 15 minutes.

-1, Only one needs to answer for notification IDNS 217-785-0600 I IliOCK Isa N

_*S t II F1 Illinois DNS El

ATTACHMENT 1 Nuclear Accident Reporting System (NARS)

Page 5 of 6 UTILITY MESSAGE NO.

ST

1. STATUS

2.

STATION

[A] ACTUAL

[A] BRAIDWOOD

[C] CLINTON

[B] DRILL/EXERCISE

[B] BYRON

[D] DRESDEN

3. ONSITE CONDITION

4. ACCIDENT CLASSIFIED

[A] UNUSUAL EVENT TIME:

[B] ALERT

[C] SITE AREA EMERGENCY DATE:

[D] GENERAL EMERGENCY EAL#:

[E] RECOVERY

[F] TERMINATED

5. RELEASE STATUS

6. TYPE OF RELEASE

7. WIND DIR

[A] NONE

[A] NOT APPLICABLE

[B] OCCURRING

[B] GASEOUS (DEGREES FROM

[C] TERMINATED

[C] LIQUID

9.

RECOMMENDED ACTIONS UTILITY RECOMMENDATION

[A] NONE

[B] EVACUATE SUB-AREAS (ILLINOIS):

[C] EVACUATE SUB-AREAS (IOWA):

STATE RECOMMENDATION

[D] NONE

[E] SHELTER SUB-AREAS:

[F] EVACUATE SUB-AREAS:

[G] RECOMMEND POTASSIUM IODIDE (KI) PER PROCEDURES

[H] COMMENCE RETURN OF PUBLIC

[I] OTHER

10. ADDITIONAL INFORMATION EP-AA-114-100 Revision 2 Page 8 of 16 ATE MESSAGE NO.

[E] LASALLE

[G] ZION

[F] QUAD CITIES ACCIDENT TERMINATED TIME:

DATE:

8. WIND SPEED

[A] METERS/SEC.:

[B] MILES/HR.:

11. TRANSMITTED BY:

[A] EXELON:

[B] STATE:

[C] COUNTY:

12. RECEIVED BY:

NAME PHONE NUMBER NAME NAME ORGANIZATION ORGANIZATION Approved By:

Verified With:

TIME/DATE TIME/DATE TIME/DATE

EP-AA-114-100 Revision 2 Page 9 of 16 ATTACHMENT I Nuclear Accident Reporting System (NARS)

Page 6 of 6 Commercial numbers:

IEMA 217-782-7860 IDNS 217-785-0600 (QC only)

Iowa EMD 515-281-3231 ROLL CALL Initial Roll Call Complete:

I (time I date)

Clinton (UE, Alert, Site Area and escalated Generals)

NARS Code 98 Initial Final LI

Illinois EMA LI DI Illinois DNS LI (Initial General Emergency Only)

NARS Code 36 Initial Final

[]

Illinois EMA El El

DeWitt Co. Sheriff El El Illinois DNS LI EL DeWitt Co. EOC El Dresden (UE, Alert, Site Area and escalated Generals)

NARS Code 20 Initial Final

I

Illinois EMA El LI Illinois DNS LI (Initial General Emergency Only)

NOTE: # Indicates that this agency is required to be notified within 15 minutes.

-1, Only one needs to answer for notification Braidwood (UE, Alert, Site Area and escalated Generals)

NARS Code 20 Initial Final LI

Illinois EMA LI LI Illinois DNS El (Initial General Emergency Only)

NARS Code 38 Initial Final El

Illinois EMA E]

El

Grundy Co. Sheriff El LI # Kankakee Co. Sheriff El El

Will County Sheriff El El Illinois DNS El LI Grundy Co. EMA El El Kankakee Co. EOC El El Will Co. EOC El LaSalle (UE, Alert, Site Area and escalated Generals)

NARS Code 20 Initial Final DI

Illinois EMA

[]

0i Illinois DNS LI (Initial General Emergency Only)

NARS Code 25 Initial Final El

Illinois EMA 11 EL # Grundy Co. Sheriff

[]

E] # LaSalle Co. Sheriff El EL Illinois DNS L]

El Grundy Co. EMA

[1 El LaSalle Co. ESDA El Byron (UE, Alert, Site Area and escalated Generals)

NARS Code 20 Initial Final El # Illinois EMA El EL Illinois DNS LI (Initial General Emergency Only)

NARS Code 37 Initial Final El# Illinois EMA LI I #-11 Ogle Co. Sheriff El El #-1 Rochelle Police El LI Illinois DNS El El Ogle Co. ESDA El El Ogle Co. EOC El NARS Code 22 Initial El #Illinois EMA El #Grundy Co. Sheriff LI #Kendall Co. Sheriff

[E MWill County Sheriff El Illinois DNS nl Grundy Co. EMA El Kendall Co. EOC El Will Co. EOC Quad Cities (UE, Alert, Site Area and escalated General Emergencies)

NARS Code 43 Initial Final El # Illinois EMA El El # Iowa EMD El El Illinois DNS LI EL Scott Co. Sheriff El El Clinton Co-EOC El (Initial General Emergency Only)

NARS Code 23 Initial Final El # Illinois EMA El El

Iowa EMD El El # Clinton Co. EOC EL El #Rock Island Co. Sheriff E]

El # Whiteside Co. Sheriff El El # Scott Co. Sheriff El El Whiteside Co. ESDA El El Rock Island ESDA El EL Illinois DNS LI Final 11 ID 11 El 1:1 El

mmm

VERIFICATION OF COMPLETION Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date performed:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT or UNSAT Examiner's signature and date:

Page 6 of 6

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