ML100350993

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DAEC 2009 Initial Exam Proposed Administrative JPMs
ML100350993
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 09/21/2009
From:
Division of Reactor Safety III
To:
References
Download: ML100350993 (179)


Text

QF-1030-11 Rev. 7 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2009 NRC RO JPM A-1 TITLE: Perform Control Room Weekly Panel Checks Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM RO A-1

QF-1030-11 Rev. 7 JOB PERFORMANCE MEASURE (JPM)

JPM TITLE: PERFORM CONTROL ROOM WEEKLY PANEL CHECKS JPM NUMBER: 2009 NRC JPM RO A-1 REV. 0 TASK NUMBER(S) / 97.12 / Perform Control Room Checks TASK TITLE(S):

K/A NUMBERS: 2.1.18 K/A VALUE: 3.6 Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY: RO SRO STA NSPEO SRO CERT APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 30 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:

Instructor Date Validated by:

Validation Instructor Date Reviewed by:

Plant Reviewer Date Approved by:

Training Supervisor Date Commitments: {C001} ACE 001729, Review recommendation 4 of OE 001501.

{C002} CA046394, Improvements needed for Operations Simulator JPMs.

Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM RO A-1 Page 1 of 1

QF-1030-11 Rev. 7 2009 NRC JPM RO A-1, Perform Control Room Weekly Panel Checks, Rev. 0 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?
2. Has the JPM been reviewed and validated by SMEs?
3. Can the required conditions for the JPM be appropriately established in the simulator if required?
4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
6. Has the completion time been established based on validation data or incumbent experience?
7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
8. Is the Licensee level appropriate for the task being evaluated if required?
9. Is the K/A appropriate to the task and to the licensee level if required?
10. Is justification provided for tasks with K/A values less than 3.0?
11. Have the performance steps been identified and typed (Critical / Sequence

/ Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
13. Are all references identified, current, accurate, and available to the trainee?
14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
15. Are all critical steps clearly identified by procedural guidance? If licensing, EP or other groups were needed to determine correct actions, then the answer should be NO. {C001}
16. If the JPM is to be administered to an ILT student, has the required knowledge been taught to the individual prior to administering the JPM?

TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. {C001}

All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

RE-VALIDATION SIGNATURE JPMs must be re-validated prior to use. Verify the above Review Statements are YES or N/A. When it is determined that the JPM is still valid and can be performed as written, sign and date the form below.

Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date DAEC 2009 NRC JPM RO A-1 Page 2 of 2

QF-1030-11 Rev. 7 2009 NRC JPM RO A-1, Perform Control Room Weekly Panel Checks, Rev. 0 SIMULATOR SET UP:

Simulator Setup Instructions:

1. Restore the IC for J-RO-A-1_ic.000 from the Thumb Drive that it is stored on. This Thumb Drive also has the malfunction and override files on it.
a. Log onto one of the Computer Terminals using the logon from Lowell
1. If the malfunction file is the exam file, go to c), otherwise:
2. With a file manager, go to the \\greg\c$\opensim directory, and copy the Malfunc-New.dat file into that directory.
3. Rename the Malfunc.dat file to Malfunc-OLD.dat
4. Rename the Malfunc-NEW.dat file to Malfunc.dat
5. Make a copy of the exam scenario IC file and rename it as d_ic.000
6. Copy the IC file from the thumb drive to the \\greg\ryandev\ops\ic directory.

This makes the exam IC number 000.

b. Reset to IC 000.
c. Verify Remote functions
2. If the thumbdrive is not available, then reset to IC 20 and perform the following:
a. At 1C03 place HPCI Flow Controller in MANUAL
b. At 1C04 place Outbd Main Steam Line Drain MO-4424 to OPEN, then allow it to return to mid-position.
c. At 1C05 place the RWM in Bypass and return the key to its clip
d. At 1C06 place the Load Shed Auto Start RWS Pump Select HSS-2911A to the running pump
3. PROVIDE Candidate with copy of STP 3.0.0-02 SIMULATOR MALFUNCTIONS: - None SIMULATOR OVERRIDES:- None SIMULATOR REMOTE FUNCTIONS:

TIME REMOTE REMOTE FUNCTION TITLE VALUE RAMP FUNCTION #

Setup RH05 RHR V-19-48 Closed 0 Required Materials: STP 3.0.0-02, Control Room Panel Checks General

References:

STP 3.0.0-02, Revision 43 Task Standards: 1) Determine that the position/condition of the items listed below do not agree with the desired position/condition:

a) HPCI Flow Control FIC-2309 b) RHR Manual Xtie Valve V-19-48 c) Outbd Main Steam Line Drain MO-4424 d) RWM Operators Display Mode Switch e) Load Shed Auto Start RWS Pump Select HSS-2911A

2) Inform the CRS of each condition that does not agree with the desired condition.

DAEC 2009 NRC JPM RO A-1 Page 3 of 3

QF-1030-11 Rev. 7 TURNOVER SHEET INITIAL CONDITIONS:

  • DAEC is operating near full power
  • DAEC is currently not in any LCO conditions INITIATING CUES (IF APPLICABLE):
  • The CRS has directed you to perform STP 3.0.0-02, CONTROL ROOM PANEL CHECKS, for Panels 1C35, 1C03, 1C04, 1C05, 1C06, 1C07, and 1C08
  • Inform the CRS when you have completed these Panel Checks NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

DAEC 2009 NRC JPM RO A-1 Page 4 of 4

QF-1030-11 Rev. 7 2009 NRC JPM RO A-1, Perform Control Room Weekly Panel Checks, Rev. 0 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

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

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

  • DAEC is operating near full power
  • DAEC is currently not in any LCO conditions INITIATING CUES (IF APPLICABLE):
  • The CRS has directed you to perform STP 3.0.0-02, CONTROL ROOM PANEL CHECKS, for Panels 1C35, 1C03, 1C04, 1C05, 1C06, 1C07, and 1C08
  • Inform the CRS when you have completed these Panel Checks NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

DAEC 2009 NRC JPM RO A-1 Page 5 of 5

QF-1030-11 Rev. 7 2009 NRC JPM RO A-1, Perform Control Room Weekly Panel Checks, Rev. 0 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Compare the as found position/condition against the desired position/condition Critical Y listed in the Desired column.

Standard: The Candidate compares the as found position/condition against the desired position/condition listed in the Desired column and determines that the position/condition of the items listed below do not agree with the desired position/condition:

a) HPCI Flow Control FIC-2309 b) RHR Manual Xtie Valve V-19-48 c) Outbd Main Steam Line Drain MO-4424 d) RWM Operators Display Mode Switch e) Load Shed Auto Start RWS Pump Select HSS-2911A Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 For any as found positions/conditions that do not agree with the desired Critical Y position/condition and do not have a known or valid reason for not agreeing, inform the CRS immediately and take actions to correct the condition.

Standard: The Candidate informs the CRS of each of the above conditions and recommends actions be taken to correct the condition.

Evaluator Cue: For each report of a mispositioned component, inform the operator that the CRS will initiate actions to enter the appropriate LCO statement and have another operator correct the lineup.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: The Candidate has completed STP 3.0.0-02, CONTROL ROOM PANEL CHECKS, for Panels 1C35, 1C03, 1C04, 1C05, 1C06, 1C07, and 1C08.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002}

Stop Time:

DAEC 2009 NRC JPM RO A-1 Page 6 of 6

QF-1030-11 Rev. 7 2009 NRC JPM RO A-1, Perform Control Room Weekly Panel Checks, Rev. 0 Examinee: Evaluator:

RO SRO STA NSPEO SRO CERT Date:

ILT RO ILT SRO PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

DAEC 2009 NRC JPM RO A-1 Page 7 of 7

QF-1030-11 Rev. 7 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2009 NRC RO JPM A-2 TITLE: Operate the Plant Process Computer Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File NRC JPM RO A-2 REV 7-15-09.DOC

QF-1030-11 Rev. 7 JOB PERFORMANCE MEASURE (JPM)

JPM TITLE: OPERATE THE PLANT PROCESS COMPUTER JPM NUMBER: RO JPM A-2 REV. 0 TASK NUMBER(S) / 71.01 / Perform Normal Operation of the Process Computer System TASK TITLE(S):

K/A NUMBERS: Generic 2.1.19 K/A VALUE: 3.9/3.8 Justification (FOR K/A N/A VALUES <3.0):

TASK APPLICABILITY: RO SRO STA NSPEO SRO CERT APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 20 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:

Instructor Date Validated by:

Validation Instructor Date Reviewed by:

Plant Reviewer Date Approved by:

Training Supervisor Date Commitments: {C001} ACE 001729, Review recommendation 4 of OE 001501.

{C002} CA046394, Improvements needed for Operations Simulator JPMs.

Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File NRC JPM RO A-2 REV 7-15-09.DOC Page 1 of 9

QF-1030-11 Rev. 7 RO JPM A-2, Operate the PPC, Rev. 0 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?
2. Has the JPM been reviewed and validated by SMEs?
3. Can the required conditions for the JPM be appropriately established in the simulator if required?
4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
6. Has the completion time been established based on validation data or incumbent experience?
7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
8. Is the Licensee level appropriate for the task being evaluated if required?
9. Is the K/A appropriate to the task and to the licensee level if required?
10. Is justification provided for tasks with K/A values less than 3.0?
11. Have the performance steps been identified and typed (Critical / Sequence

/ Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
13. Are all references identified, current, accurate, and available to the trainee?
14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
15. Are all critical steps clearly identified by procedural guidance? If licensing, EP or other groups were needed to determine correct actions, then the answer should be NO. {C001}
16. If the JPM is to be administered to an ILT student, has the required knowledge been taught to the individual prior to administering the JPM?

TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. {C001}

All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

RE-VALIDATION SIGNATURE JPMs must be re-validated prior to use. Verify the above Review Statements are YES or N/A. When it is determined that the JPM is still valid and can be performed as written, sign and date the form below.

Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date NRC JPM RO A-2 REV 7-15-09.DOC Page 2 of 9

QF-1030-11 Rev. 7 RO JPM A-2, Operate the PPC, Rev. 0 SIMULATOR SET UP:

Simulator Setup Instructions:

1. Ensure the PPC is running
2. If the RWCU system is running, ensure the flow is within limits (to prevent alarms from coming up on PPC).
3. No other simulator setup is required SIMULATOR MALFUNCTIONS:

TIME MALFUNCTION # MALFUNCTION ET DELAY F. SEV. RAMP I. SEV.

TITLE SIMULATOR OVERRIDES:

TIME OVERRIDE ID OVERRIDE ET DELAY VALUE RAMP DESCRIPTION SIMULATOR REMOTE FUNCTIONS:

TIME REMOTE REMOTE FUNCTION TITLE VALUE RAMP FUNCTION #

Required Materials: OI 831.4, Plant Process Computer General

References:

OI 831.4, Plant Process Computer, Rev. 64 Task Standards: 1. Value of 0 for point B017 substituted.

2. Point B017 restored to scan.

NRC JPM RO A-2 REV 7-15-09.DOC Page 3 of 9

QF-1030-11 Rev. 7 TURNOVER SHEET INITIAL CONDITIONS:

The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.

  • The plant experienced a RWCU isolation due to a relay failure.
  • To ensure that the 3D Monicore periodic logs are maintained accurate, RWCU System Flow needs to be substituted to zero INITIATING CUES (IF APPLICABLE):
  • The CRS directs you to substitute computer point B017, RWCU System Flow, to zero.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC JPM RO A-2 REV 7-15-09.DOC Page 4 of 9

QF-1030-11 Rev. 7 RO JPM A-2, Operate the PPC, Rev. 0 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

The initial conditions that I read may not exactly match the simulator setup, assume that the conditions that I read you are the correct plant conditions.

  • The plant experienced a RWCU isolation due to a relay failure.
  • To ensure that the 3D Monicore periodic logs are maintained accurate, RWCU System Flow needs to be substituted to zero INITIATING CUES (IF APPLICABLE):
  • The CRS directs you to substitute computer point B017, RWCU System Flow, to zero.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC JPM RO A-2 REV 7-15-09.DOC Page 5 of 9

QF-1030-11 Rev. 7 RO JPM A-2, Operate the PPC, Rev. 0 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: At a SELECT FUNC. KEY OR TURN-ON CODE prompt, type IV and then press Critical N <ENTER>.

Standard: Brings up the Insert Value prompt Evaluator Note: This prompt is at the very top of the screen.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: At the ENTER POINT ID prompt, type in B017, and then press <ENTER>.

Critical Y Standard: Enters B017 and presses ENTER Evaluator Note: The top of the PPC screen will show:

B017 Clean-Up System Flow [present value] MLBH GOOD Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC JPM RO A-2 REV 7-15-09.DOC Page 6 of 9

QF-1030-11 Rev. 7 RO JPM A-2, Operate the PPC, Rev. 0 Performance Step: At the ENTER SUBSTITUTE VALUE prompt, type in 0 (zero) and then presses Critical Y <ENTER>.

Standard: Enters a value of ZERO for the point B017 and presses <ENTER>

Evaluator Note: PPC screen will display:

507 THE SPECIFIED VALUE HAS BEEN SUBSTITUTED B017 The information below will be displayed on the alarm typer screen:

B017 CLEAN-UP SYSTEM FLOW 0 MLBH SUB The above info will also be shown if the B017 is entered into the IV prompt again.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Evaluator Cue: Once the B017 point has been substituted to ZERO, then cue the candidate that the RWCU system has been repaired and placed in service. The CRS directs you to remove the substituted value for point B017.

Performance Step: At a SELECT FUNC. KEY OR TURN-ON CODE prompt, type ENSC and then Critical Y press <ENTER>.

Standard: Candidate brings up the enable scan entry display (at the top of the PPC screen.)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: At the SELECT FUNCTION KEY prompt, press <F2> (POINT ID).

Critical Y Standard: Candidate depresses <F2> to allow the point ID to be entered.

Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC JPM RO A-2 REV 7-15-09.DOC Page 7 of 9

QF-1030-11 Rev. 7 RO JPM A-2, Operate the PPC, Rev. 0 Performance Step: At the ENTER POINT ID prompt, type in B017 and then press <ENTER>.

Critical Y Standard: Candidate enters B017 and depresses <ENTER>

Evaluator Note: The top of the PPC screen will show the following display:

B017 Clean-Up System Flow [present value] MLBH GOOD This shows that the value is not substitued any longer.

This information will also be displayed on the alarm typer screen.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When B017 is restored to scan, then the JPM is complete.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002}

Stop Time:

NRC JPM RO A-2 REV 7-15-09.DOC Page 8 of 9

QF-1030-11 Rev. 7 RO JPM A-2, Operate the PPC, Rev. 0 Examinee: Evaluator:

RO SRO STA NSPEO SRO CERT Date:

ILT RO ILT SRO PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC JPM RO A-2 REV 7-15-09.DOC Page 9 of 9

QF-1030-11 Rev. 7 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2009 NRC RO JPM A-3 TITLE: Perform Jet Pump Operability Surveillance Test Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM RO A-1

QF-1030-11 Rev. 7 JOB PERFORMANCE MEASURE (JPM)

JPM TITLE: PERFORM JET PUMP OPERABILITY SURVEILLANCE TEST JPM NUMBER: 2009 NRC JPM RO A-3 REV. 0 TASK NUMBER(S) / 1.07 / Perform Surveillance Testing TASK TITLE(S):

K/A NUMBERS: 2.2.12 K/A VALUE: 3.7 Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY: RO SRO STA NSPEO SRO CERT APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:

Instructor Date Validated by:

Validation Instructor Date Reviewed by:

Plant Reviewer Date Approved by:

Training Supervisor Date Commitments: {C001} ACE 001729, Review recommendation 4 of OE 001501.

{C002} CA046394, Improvements needed for Operations Simulator JPMs.

Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM RO A-3 Page 1 of 1

QF-1030-11 Rev. 7 2009 NRC JPM RO A-3, Perform Jet Pump Operability Surveillance Test, Rev. 0 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?
2. Has the JPM been reviewed and validated by SMEs?
3. Can the required conditions for the JPM be appropriately established in the simulator if required?
4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
6. Has the completion time been established based on validation data or incumbent experience?
7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
8. Is the Licensee level appropriate for the task being evaluated if required?
9. Is the K/A appropriate to the task and to the licensee level if required?
10. Is justification provided for tasks with K/A values less than 3.0?
11. Have the performance steps been identified and typed (Critical / Sequence

/ Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
13. Are all references identified, current, accurate, and available to the trainee?
14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
15. Are all critical steps clearly identified by procedural guidance? If licensing, EP or other groups were needed to determine correct actions, then the answer should be NO. {C001}
16. If the JPM is to be administered to an ILT student, has the required knowledge been taught to the individual prior to administering the JPM?

TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. {C001}

All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

RE-VALIDATION SIGNATURE JPMs must be re-validated prior to use. Verify the above Review Statements are YES or N/A. When it is determined that the JPM is still valid and can be performed as written, sign and date the form below.

Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date DAEC 2009 NRC JPM RO A-3 Page 2 of 2

QF-1030-11 Rev. 7 2009 NRC JPM RO A-3, Perform Jet Pump Operability Surveillance Test, Rev. 0 SIMULATOR SET UP:

NOTE: The IC files for NRC JPM RO-A-1 and NRC JPM RO-J-3 may be combined.

1. Restore the IC for J-RO-A-3_ic.000 from the Thumb Drive that it is stored on. This Thumb Drive also has the malfunction and override files on it.
a. Log onto one of the Computer Terminals using the logon from Lowell
1. If the malfunction file is the exam file, go to ii), otherwise:
a. With a file manager, go to the \\greg\c$\opensim directory, and copy the Malfunc-New.dat file into that directory.
b. Rename the Malfunc.dat file to Malfunc-OLD.dat
c. Rename the Malfunc-NEW.dat file to Malfunc.dat
2. Make a copy of the exam scenario IC file and rename it as d_ic.000
3. Copy the IC file from the thumb drive to the \\greg\ryandev\ops\ic directory. This makes the exam IC number 000.
b. Reset to IC 000.
c. Verify Malfunction and Override per tables below
2. If the thumbdrive is not available, then reset to IC 20 and perform the following:
a. Insert the malfunction and override per the tables below.
3. Place the simulator in RUN.

SIMULATOR MALFUNCTIONS:

TIME MALFUNCTION MALFUNCTION ET DELAY F. SEV. RAMP I. SEV.

No. TITLE Setup RR14b Recirc jet pump riser 0 0 12 0 0 failure JP11 and 12 SIMULATOR OVERRIDES:

TIME OVERRIDE ID OVERRIDE ET DELAY VALUE RAMP DESCRIPTION Setup RR FI4523 Jet Pump Loop A 0 0 0.630 0 Flowrate SIMULATOR REMOTE FUNCTIONS: None Required Materials: Simulator Marked up copy of STP 3.4.2-01, Daily Jet Pump Operability Test (See Attached).

Mark up through Step 7.2.4 as complete. Also fill in required graphs per data in steps 7.1.3, 7.2.2, and 7.2.3.

Calculator General

References:

STP 3.4.2-01, Rev. 26 Task Standards:

  • After correctly calculating and plotting the points on Attachment 4, determine that jet pump 11 is out of the acceptable band.
  • After correctly calculating and plotting the points on Attachment 4, determine that jet pump 12 is out of the acceptable band.
  • Candidate answers NO all of the points plotted on Attachment 4 are not between the lines.
  • Candidate notifies the CRS that Jet Pumps 11 and 12 out of spec. for the STP.

DAEC 2009 NRC JPM RO A-3 Page 3 of 3

QF-1030-11 Rev. 7 TURNOVER SHEET INITIAL CONDITIONS:

  • The plant is operating at approximately 98% Thermal Power.
  • Another operator was performing STP 3.4.2-01, DAILY JET PUMP OPERABILITY TEST, but he was called away for other plant issues.
  • The JETS program is unavailable on ANY computer.

INITIATING CUES (IF APPLICABLE):

  • The CRS directs you to continue with STP 3.4.2-01, DAILY JET PUMP OPERABILITY TEST, beginning at step 7.2.5.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

DAEC 2009 NRC JPM RO A-3 Page 4 of 4

QF-1030-11 Rev. 7 2009 NRC JPM RO A-3, Perform Jet Pump Operability Surveillance Test, Rev. 0 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

  • The plant is operating at approximately 98% Thermal Power.
  • Another operator was performing STP 3.4.2-01, DAILY JET PUMP OPERABILITY TEST, but he was called away for other plant issues.
  • The JETS program is unavailable on ANY computer.

INITIATING CUES (IF APPLICABLE):

  • The CRS directs you to continue with STP 3.4.2-01, DAILY JET PUMP OPERABILITY TEST, beginning at step 7.2.5.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

DAEC 2009 NRC JPM RO A-3 Page 5 of 5

QF-1030-11 Rev. 7 2009 NRC JPM RO A-3, Perform Jet Pump Operability Surveillance Test, Rev. 0 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 At 1C38, record jet pump total developed head as read on PDI 4567, Jet Pump Critical N Total Head.

Standard: Record jet pump total developed head as read on PDI 4567: Jet Pump Total Head should be recorded as approximately 25 psid.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 At 1C38, record the indicated RECIRC LOOP A Jet Pump differential pressure Critical Y value for each Jet Pump in column "A" of Table A (contained in Step 7.2.11).

Standard: Record Jet pump differential pressures in column A. Values should be approximately as follows:

JP-9 15.0 JP-10 13.0 JP-11 7.5 JP-12 8.0 JP-13 13.5 JP-14 13.5 JP-15 14.5 JP-16 14.5 Performance: SATISFACTORY UNSATISFACTORY Comments:

DAEC 2009 NRC JPM RO A-3 Page 6 of 6

QF-1030-11 Rev. 7 2009 NRC JPM RO A-3, Perform Jet Pump Operability Surveillance Test, Rev. 0 Performance Step: 3 If the JETS program is available, "N/A" Steps 7.2.9 through 7.2.11 and then Critical N perform the remainder of Section 7.2. If the JETS program is not available, "N/A" Steps 7.2.8 and 7.2.8.a and then perform the remainder of Section 7.2.

Standard: Initial conditions stated that JETS program is unavailable; therefore, the candidate will N/A Steps 7.2.8 and 7.2.8.a and then proceed with the remaining steps Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 Calculate the sum of the individual Jet Pump Ps and record the value in the Critical Y appropriate space at the bottom of Table A.

Standard: Calculates the sum of the individual Jet Pump Ps as approximately 99.5 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 Calculate the average Jet Pump P and record the value in the appropriate Critical Y space at the bottom of Table A.

Standard: Calculates the average Jet Pump P as approximately 12.4.

Performance: SATISFACTORY UNSATISFACTORY Comments:

DAEC 2009 NRC JPM RO A-3 Page 7 of 7

QF-1030-11 Rev. 7 2009 NRC JPM RO A-3, Perform Jet Pump Operability Surveillance Test, Rev. 0 Performance Step: 6 Calculate the difference between each individual Jet Pump P and the average Critical Y P and record the results in column "B" of Table A.

Standard: Calculates the differences to be approximately as follows:

JP-9 2.6 JP-10 0.6 JP-11 -4.9 JP-12 -4.4 JP-13 1.1 JP-14 1.1 JP-15 2.1 JP-16 1.1 Evaluator Note: Depending upon how the Candidate rounds the differences answer in the previous steps, these numbers may differ a little. This is acceptable.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 Using the equation, calculate the percent deviation of each individual Jet Pump Critical Y P from the average P, and record the result in column "C" of Table A.

Standard: Calculates the percent deviation of each individual Jet Pumps to be approximately as follows; JP-9 21%

JP-10 4.8%

JP-11 -39.5%

JP-12 -35.5%

JP-13 8.9%

JP-14 8.9%

JP-15 16.9%

JP-16 16.9%

Evaluator Note: Depending upon how the Candidate rounds the differences answer in the previous steps, these numbers may differ by about 5%. This is acceptable.

Performance: SATISFACTORY UNSATISFACTORY Comments:

DAEC 2009 NRC JPM RO A-3 Page 8 of 8

QF-1030-11 Rev. 7 2009 NRC JPM RO A-3, Perform Jet Pump Operability Surveillance Test, Rev. 0 Performance Step: 8 Plot each individual Recirc Loop "A" Jet Pump % deviation value (from column Critical Y "C" of Table A) on Attachment 4.

Standard: Plot each point correctly. The critical portion of this step is to plot JP11 and JP12 below the allowable area.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 9 Perform the following evaluation; Critical Y Are all of the points plotted on Attachment 4 on or between the lines of the allowable band?

Standard: Candidate answers NO; all of the points plotted on Attachment 4 are NOT between the lines.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 10 Perform the following evaluation; Critical N If the answer to Step 7.2.13.a is YES, Jet Pumps 9-16 are OPERABLE. "N/A" Steps 7.2.13.c, 7.1.13.d, and 7.2.13.e.

Standard: Candidate DOES NOT "N/A" Steps 7.2.13.c, 7.1.13.d, and 7.2.13.e per this step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

DAEC 2009 NRC JPM RO A-3 Page 9 of 9

QF-1030-11 Rev. 7 2009 NRC JPM RO A-3, Perform Jet Pump Operability Surveillance Test, Rev. 0 Performance Step: 11 Perform the following evaluation; Critical Y If the answer to Step.2.13.a is NO and Recirc Pump speed is greater than or equal to () 60% of rated, immediately notify the CRS. Then, "N/A" Steps7.2.13.b,7.2.13.d, and 7.2.13.e.

Standard: Candidate notifies the CRS that Jet Pumps 11 and 12 are out of specification for the STP.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: WHEN the candidate reports that Jet Pumps 11 and 12 are out of specification, inform the candidate that the JPM is complete and record the Stop Time.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002}

Stop Time:

DAEC 2009 NRC JPM RO A-3 Page 10 of 10

QF-1030-11 Rev. 7 2009 NRC JPM RO A-3, Perform Jet Pump Operability Surveillance Test, Rev. 0 Examinee: Evaluator:

RO SRO STA NSPEO SRO CERT Date:

ILT RO ILT SRO PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

DAEC 2009 NRC JPM RO A-3 Page 11 of 11

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

1 of 25 26 Usage Level CONTINUOUS Effective Date: __________________

Approved for Point-of-Use printing IF NO DCFs are in effect for this procedure.

(on designated printers)

Record the following: Date / Time: __________________ / ______________

Printer ID: DA - ____________________ Initials: ________

NOTE: Per ACP 106.1, a DCF/REV check shall be performed and documented every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if active document use exceeds a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period as determined from the date and time recorded above.

Document approval signatures on file Prepared By: Michael Winchester / Date:

Print Signature CROSS-DISCIPLINE REVIEW (AS REQUIRED)

Reviewed By: / Date:

Print Signature Reviewed By: / Date:

Print Signature Reviewed By: / Date:

Print Signature PROCEDURE APPROVAL BY QUALIFIED REVIEWER Approved By / Date:

Print Signature

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

2 of 25 26 1.0 PURPOSE 1.1 The purpose of this STP is to log Recirc Pump speeds daily to ensure Recirc Pumps are not operating at a significant speed mismatch and to verify Jet Pump operability. Verification of Jet Pump operability shall be made daily, following startup of a Recirculation Pump, and after any unexplained changes in core flow, Jet Pump Loop flow, Recirc Loop flow, or core plate differential pressure.

1.2 When this procedure is performed in its entirety it FULLY SATISFIES Recirculation Loop Operations Recirc Pump speed mismatch surveillance requirements.

1.3 When this procedure is performed in its entirety it FULLY SATISFIES Jet Pumps surveillance requirements.

2.0 BRIEFING INFORMATION 2.1 PERFORMANCE INFORMATION 2.1.1 This STP is organized as follows:

STP Sections Evolution 7.1 Recirc Pump Speed Mismatch Check 7.2 Jet Pumps 9-16 Operability Check 7.3 Jet Pumps 1-8 Operability Check 7.4 Jet Pump M-Ratio Determination All steps within a section are to be performed in sequence and the STP steps carried through to completion, unless otherwise indicated. The sections may be performed concurrently for ease of recording data.

Sections 7.2 and 7.3 are not required to be performed when reactor power is less than or equal to () 21.7% RTP. If this procedure is being performed when reactor power is less than or equal to () 21.7% RTP, Prerequisite 6.2 and Sections 7.2 and 7.3 are to be marked "N/A".

2.1.2 Personnel recommended to perform this procedure:

1 Operations 2.1.3 Special Test Equipment required:

None 2.1.4 If Recirculation Pump speed is less than 60% of rated, an Engineering evaluation may be performed to determine Jet Pump OPERABILITY.

2.1.5 M-Ratio determination does not affect Jet Pump operability. If M-Ratio data is not within the upper and lower limits of the curves shown in Attachments 8 and 9, it does not mean that the Jet Pumps are inoperable. Engineering will perform an evaluation as potential causes may be due to normal process measurement noise, changes in core parameters, or instrumentation problems.

{C001}

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

3 of 25 26 2.2 GENERAL CAUTIONS 2.2.1 None 2.3 SPECIAL PRECAUTIONS 2.3.1 None

3.0 REFERENCES

3.1 Commitment items:

3.1.1 C001 - GE SIL-605 (AR 96-2880 and 96-2880.02) 4.0 GENERAL INSTRUCTIONS 4.1 Steps marked with a "TS" immediately to the right of the step sign-off line are required by Technical Specifications. If these steps do not meet their acceptance criteria or cannot be performed, a NRC reportable condition may exist and shall be reported to the Control Room Supervisor (CRS) immediately.

4.2 The CRS shall be immediately notified and the appropriate Limiting Condition for Operations section of Technical Specifications referred to whenever problems are encountered during the performance of this STP.

4.3 An Action Request (AR) should be completed for any problems encountered with TS marked steps during the performance of this test.

5.0 APPENDICES 5.1 Appendix A - JETS Program Instructions

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

4 of 25 26 Appendix A JETS PROGRAM INSTRUCTIONS Sheet 1 of 1

1. If at a workstation desktop, log onto SSE as follows:
a. Click: Start : Programs: PDA APPS: IBM Personal Communications PC3270: PPC
b. At Username Prompt, type SSE <Enter>.
c. Enter the appropriate password and press <Enter>.
d. At the $ prompt, type JETS and press <Enter>.

The Jet Pump Program main menu should come up on the screen.

2. If at a VAX/PPC terminal, log onto SSE as follows:
a. Log onto the SSE account.
b. At the PPC1_SSE prompt, type JETS and press <Enter>. The Jet Pump program main menu should come up on the screen.
3. Type 1 to access combined Loop A and Loop B Jet Pump tables. Type 2 to access only the Loop A Jet Pump table (Jet Pumps 9-16). Type 3 to access only the Loop B Jet Pump table (Jet Pumps 1-8).

NOTE All Ps must be a positive value between 0 and 30, but not including 0 (0<P30). The program will automatically tab forward as each Jet Pump's P is entered. The <Tab> key may be used to move forward to the next Jet Pump, if desired. The <Control> and <H> keys pressed simultaneously may be used to move backward to the previous Jet Pump, if desired. If desired to change a P, use the <Backspace> key to erase all numerals to the left of the decimal point before entering the new numbers.

4. Type in each Jet Pumps P.

NOTE If all fields are not filled with a positive number between 0 and 30, but not including 0 (0<P30) when Step 5.0 is performed, the program will not calculate the % deviations and will return to the Jet Pump main menu.

5. Press the <Enter> key to calculate the % deviations. The printout will automatically print on laser printer LTA14 and the program will automatically terminate.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

5 of 25 26 Prerequisites Performance Date: ____Today_____ INITIALS 6.0 PREREQUISITES 6.1 The reactor is in two-loop operation. (If the reactor is in single loop _ HDM__

operation, perform STP 3.4.2-03 instead.) (OPS) 6.2 For sections 7.2 and 7.3, reactor power is greater than (>) 21.7% RTP. _ HDM__

(See Performance Information Step 2.1.1.) (OPS)

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

6 of 25 26 Performance Date: ______ Today______ INITIALS 7.0 PROCEDURE 7.1 RECIRC PUMP SPEED MISMATCH CHECK 7.1.1 At 1C04, using the "D" button on SIC-9245A, A MG SET SPEED ___HDM__

CONTROL, select "X" - PERCENT SPEED mode of indication.

a. Record the percent speed indication. ___HDM__ TS A MG SET PERCENT SPEED (SIC-9245A.X) ___99.5__ %
b. Record the percent speed indication in Step 7.2.1. (Mark this ___HDM__

step N/A if Section 7.2 is not required.)

c. Using the "D" button on SIC-9245A, select "S" - SETPOINT ___HDM__

mode of indication.

7.1.2 At 1C04, using the "D" button on SIC-9245B, B MG SET SPEED ___HDM__

CONTROL, select "X" - PERCENT SPEED mode of indication.

a. Record the percent speed indication. ___HDM__ TS B MG SET PERCENT SPEED (SIC-9245B.X) ___99.3___%
b. Record the percent speed indication in Step 7.3.1. (Mark this ___HDM__

step N/A if Section 7.3 is not required.)

c. Using the "D" button on SIC-9245B, select "S" - SETPOINT ___HDM__

mode of indication.

7.1.3 On Attachment 1, plot the intersection of the Recirc Pump speed _HDM__

values using the data recorded in Steps 7.1.1.a and 7.1.2.a.

7.1.4 Confirm that the point plotted on Attachment 1 is within the ___HDM__ TS appropriate limit for the current core power. If the point is outside the limit, immediately notify the CRS.

____Hugh D. Mann_____________ Today Now _HDM_

Performed by: Date: Time:

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

7 of 25 26 Performance Date: ______ Today______ INITIALS 7.2 JET PUMPS 9-16 OPERABILITY CHECK 7.2.1 At 1C04, record the following data for the "A" Recirc Pump: ___HDM__

A MG SET PERCENT SPEED (SIC-9245A.X) _99.5_%

DISCHARGE FLOW (FI-4634A) __29.8__ KGPM LOOP A (FI-4523) ___23.5____ Mlbm/hr 7.2.2 Using the data recorded in Step 7.2.1, plot "A" Recirc MG Set ___HDM__ TS speed vs. "A" Recirc Pump discharge flow on Attachment 2.

7.2.3 Using the data recorded in Step 7.2.1, plot "A" Recirc MG Set ___HDM__ TS speed vs. Loop "A" Jet Pump flow on Attachment 3.

NOTE ___HDM__

If Step 7.2.4.a is answered NO, Acceptance Criteria Step 8.3.2 should be answered YES if either Step 7.2.13.a or Step 7.2.13.e is answered YES.

7.2.4 Perform the following evaluation:

a. Are all of the points that were plotted on Attachment 2 and ___HDM__ TS Attachment 3 between or on the sloped lines?

(YES/NO) _____NO______

b. If the answer to Step 7.2.4.a was YES, Jet Pumps 9-16 are ___N/A__

OPERABLE. "N/A" Step 7.2.4.c, Steps 7.2.7 through 7.2.13.e, and Attachment 4. Then continue with Step 7.2.5.

c. If the answer to Step 7.2.4.a was NO, immediately notify the ___HDM__

CRS. Then, "N/A" Step 7.2.4.b and perform the remainder of Section 7.2.

7.2.5 At 1C38, record jet pump total developed head as read on ________

PDI-4567, Jet Pump Total Head:

PDI-4567: ________ psid 7.2.6 At 1C38, record the indicated RECIRC LOOP A Jet Pump ________

differential pressure value for each Jet Pump in column "A" of Table A (contained in Step 7.2.11).

7.2.7 If the JETS program is available, "N/A" Steps 7.2.9 through 7.2.11 ________

and then perform the remainder of Section 7.2. If the JETS program is not available, "N/A" Steps 7.2.8 and 7.2.8.a and then perform the remainder of Section 7.2.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

8 of 25 26 Performance Date: ______ Today______ INITIALS 7.2.8 Using the instructions provided in Appendix "A", obtain a printout ________

of "A" Recirc Loop Ps.

a. Attach the printout to the STP. ________

7.2.9 Calculate the sum of the individual Jet Pump Ps and the ________

average Jet Pump P and record those values in the appropriate spaces at the bottom of Table A.

7.2.10 Calculate the difference between each individual Jet Pump P ________

and the average P and record the results in column "B" of Table A.

7.2.11 Using the following equation, calculate the percent deviation of ________

each individual Jet Pump P from the average P, and record the result in column "C" of Table A.

Ind. P - Avg. P

% Deviation = 100 x Avg. P TABLE A A B C JET PUMP (P) (Ind.P - Avg.P) (% Deviation)

JP-9 JP-10 JP-11 JP-12 JP-13 JP-14 JP-15 JP-16

÷8=

(Sum of Ps) (Avg.P) 7.2.12 Plot each individual Recirc Loop "A" Jet Pump % deviation value ________

(from column "C" of Table A or JETS program calculation) on Attachment 4.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

9 of 25 26 Performance Date: ______ Today______ INITIALS NOTE If Step 7.2.13.a is answered NO, Acceptance Criteria Step 8.3.2 shall be answered NO also, unless Recirc Pump speed is less than 60% of rated and an Engineering evaluation determines that the Jet Pumps are OPERABLE.

7.2.13 Perform the following evaluation:

a. Are all of the points plotted on Attachment 4 on or between ________ TS the lines of the allowable band?

(YES/NO) ________

b. If the answer to Step 7.2.13.a is YES, Jet Pumps 9-16 are ________

OPERABLE. "N/A" Steps 7.2.13.c, 7.2.13.d, and 7.2.13.e.

c. If the answer to Step 7.2.13.a is NO and Recirc Pump speed ________

is greater than or equal to () 60% of rated, immediately notify the CRS. Then, "N/A" Steps 7.2.13.b, 7.2.13.d, and 7.2.13.e.

d. If the answer to Step 7.2.13.a is NO and Recirc Pump speed ________

is less than (<) 60% of rated, immediately inform the CRS and then contact Engineering to perform an evaluation of Jet Pump operability. Then, "N/A" Steps 7.2.13.b and 7.2.13.c.

e. If an Engineering evaluation was performed, are Jet Pumps ________ TS 9-16 OPERABLE? ("N/A" if an Engineering evaluation is not Engineering required to be performed.)

(YES/NO) __________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

10 of 25 26 Performance Date: ______ Today______ INITIALS 7.3 JET PUMPS 1-8 OPERABILITY CHECK 7.3.1 At 1C04, record the following data for the "B" Recirc Pump: ________

B MG SET PERCENT SPEED (SIC-9245B.X) ______%

DISCHARGE FLOW (FI-4634B) __________ KGPM LOOP B (FI-4526) ___________ Mlbm/hr 7.3.2 Using the data recorded in Step 7.3.1, plot "B" Recirc MG Set ________ TS speed vs. "B" Recirc Pump discharge flow on Attachment 5.

7.3.3 Using the data recorded in Step 7.3.1, plot "B" Recirc MG Set ________ TS speed vs. Loop "B" Jet Pump flow on Attachment 6.

NOTE If Step 7.3.4.a is answered NO, Acceptance Criteria Step 8.3.3 should be answered YES if either Step 7.3.12.a or Step 7.3.12.e is answered YES.

7.3.4 Perform the following evaluation:

a. Are all of the points that were plotted on Attachment 5 and ________ TS Attachment 6 between or on the sloped lines?

(YES/NO) _____________

b. If the answer to Step 7.3.4.a was YES, Jet Pumps 1-8 are ________

OPERABLE. "N/A" Step 7.3.4.c, Steps 7.3.6 through 7.3.12.e, and Attachment 7. Then, perform Step 7.3.5.

c. If the answer to Step 7.3.4.a was NO, immediately notify the ________

CRS. Then, "N/A" Step 7.3.4.b and perform the remainder of Section 7.3.

7.3.5 At 1C38, record the indicated RECIRC LOOP B Jet Pump ________

differential pressure value for each Jet Pump in column "A" of Table B (contained in Step 7.3.10).

7.3.6 If the JETS program is available, "N/A" Steps 7.3.8 through 7.3.10 ________

and then perform the remainder of Section 7.3. If the JETS program is not available, "N/A" Steps 7.3.7 and 7.3.7.a, then perform the remainder of Section 7.3.

7.3.7 Using the instructions provided in Appendix "A", obtain a printout ________

of "B" Recirc Loop Ps.

a. Attach the printout to the STP. ________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

11 of 25 26 Performance Date: ______ Today______ INITIALS 7.3.8 Calculate the sum of the individual Jet Pump Ps and the ________

average Jet Pump P and record the results in the appropriate spaces at the bottom of Table B.

7.3.9 Calculate the difference between each individual Jet Pump P ________

and the average P and record the result in column "B" of Table B.

7.3.10 Using the following equation, calculate the percent deviation of ________

each individual Jet Pump P from the average P and then record the result in column "C" of Table B.

Ind. P - Avg. P

% Deviation = 100 x Avg. P TABLE B A B C JET PUMP (P) (Ind.P - Avg.P) (% Deviation)

JP-1 JP-2 JP-3 JP-4 JP-5 JP-6 JP-7 JP-8

÷ 8 =

(Sum of Ps) (Avg. P) 7.3.11 Plot each individual Recirc Loop "B" Jet Pump % deviation value ________

(from column "C" of Table B or JETS program calculation) on Attachment 7.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

12 of 25 26 Performance Date: ______ Today______ INITIALS NOTE If Step 7.3.12.a is answered NO, Acceptance Criteria Step 8.3.3 shall be answered NO also, unless Recirc Pump speed is less than 60% of rated and an Engineering evaluation determines that Jet Pumps are OPERABLE.

7.3.12 Perform the following evaluation:

a. Are all of the points plotted on Attachment 7 on or between ________ TS the lines of the allowable band?

(YES/NO) __________

b. If the answer to Step 7.3.12.a is YES, Jet Pumps 1-8 are ________

OPERABLE. "N/A" Steps 7.3.12.c, 7.3.12.d, and 7.3.12.e.

c. If the answer to Step 7.3.12.a is NO and Recirc Pump speed ________

is greater than or equal to () 60% of rated, immediately notify the CRS. Then, "N/A" Steps 7.3.12.b, 7.3.12.d, and 7.3.12.e.

d. If the answer to Step 7.3.12.a is NO and Recirc Pump speed ________

is less than (<) 60% of rated, immediately inform the CRS and then contact Engineering to perform an evaluation of Jet Pump operability. Then, "N/A" Steps 7.3.12.b and 7.3.12.c.

e. If an Engineering evaluation was performed, are Jet Pumps ________ TS 1-8 OPERABLE? ("N/A" if an Engineering evaluation is not Engineering required to be performed.)

(YES/NO) __________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

13 of 25 26 Performance Date: ______ Today______ INITIALS 7.4 JET PUMP M-RATIO DETERMINATION NOTE The following steps verify Jet Pump M-Ratio. M-Ratio can help determine Jet Pump degradation. This section of the STP does not determine Jet Pump operability, it is for trending only.

{C001}

7.4.1 If the PPC is not available, mark Steps 7.4.2 through 7.4.7 N/A. ________

Otherwise, mark this step N/A.

7.4.2 Record the value of computer point B062, A Recirc Loop Flow, ________

below:

B062 ______________

7.4.3 Record the value of computer point B026SM, A Recirc Pump ________

Discharge Flow, below:

B026SM ______________

7.4.4 If the computer point B062 value recorded in Step 7.4.2 is greater than or equal to () 10 Mlbm/hr, perform Steps 7.4.4.a through 7.4.4.c. If the computer point B062 value is less than (<) 10 Mlbm/hr, mark Steps 7.4.4.a through 7.4.4.c N/A.

a. Determine M-Ratio by completing the following calculation: ________

M-Ratio = (value from Step 7.4.2) - (value from Step 7.4.3)

(value from Step 7.4.3)

M-Ratio = ( )-( )

( )

M-Ratio = ___________

b. Plot "A" Recirc Loop M-Ratio (value from Step 7.4.4.a) against ________

"A" Recirc Loop flow (value from Step 7.4.2) on Attachment 8.

c. If the "A" Recirc Loop M-Ratio is not within the upper and ________

lower limits, initiate an Action Request (AR) and contact the System Engineer to perform an evaluation (see Performance Information Step 2.1.5). Otherwise, mark this step N/A.

7.4.5 Record the value of computer point B061, B Recirc Loop Flow, ________

below:

B061 ______________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

14 of 25 26 Performance Date: ______ Today______ INITIALS 7.4.6 Record the value of computer point B028SM, B Recirc Pump ________

Discharge Flow, below:

B028SM ______________

7.4.7 If the computer point B061 value recorded in Step 7.4.5 is greater than or equal to () 10 Mlbm/hr perform Steps 7.4.7.a through 7.4.7.c. If the computer point B061 value is less than (<) 10 Mlbm/hr mark Steps 7.4.7.a through 7.4.7.c "N/A":

a. Determine M-Ratio by completing the following calculation: ________

M-Ratio = (value from Step 7.4.5) - (value from Step 7.4.6)

(value from Step 7.4.6)

M-Ratio = ( )-( )

( )

M-Ratio = ___________

b. Plot "B" Recirc Loop M-Ratio (value from Step 7.4.7.a) against ________

"B" Recirc Loop flow (value from Step 7.4.5) on Attachment 9.

c. If the "B" Recirc Loop M-Ratio is not within the upper and ________

lower limits, initiate an Action Request (AR) and contact the System Engineer to perform an evaluation (see Performance Information Step 2.1.5). Otherwise, mark this step N/A.

Performed by: Date: Time:

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

15 of 25 26 Performance Date: ____________________ INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 Check below the reason for performing this STP. If this STP is performed for any reason other than for satisfying the PURPOSE as stated in Section 1.0, indicate below (otherwise mark this step "N/A"):

[ ] Daily Requirement

[ ] Pump Start

[ ] Unexplained changes

[ ] Other 8.2 If a DCF, Procedure Work Request (PWR), or Action Request (AR) was written due to problems encountered with the performance of this procedure, list the applicable number(s) below. ("N/A" blocks as appropriate.)

DCF No. __________ PWR No. ___________ AR No. ___________

DCF No. __________ PWR No. ___________ AR No. ___________

8.3 All Technical-Specification-required items, as indicated by "TS", have been performed satisfactorily.

8.3.1 Section 7.1 ( ) YES ( ) NO CRS notified ________

8.3.2 Section 7.2 ( ) YES ( ) NO CRS notified ________

8.3.3 Section 7.3 ( ) YES ( ) NO CRS notified ________

8.4 All other items checked in this test have been performed satisfactorily.

8.4.1 Section 7.1 ( ) YES ( ) NO CRS notified ________

8.4.2 Section 7.2 ( ) YES ( ) NO CRS notified ________

8.4.3 Section 7.3 ( ) YES ( ) NO CRS notified ________

8.4.4 Section 7.4 ( ) YES ( ) NO CRS notified ________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

16 of 25 26 Performance Date: ____________________ INITIALS 8.5 Indicate any relevant test comments below, otherwise mark this step "N/A":

Operations Date Surveillance Coordinator Date 9.0 ATTACHMENTS 9.1 Attachment 1 - Speed of Pump "A" vs. Speed of Pump "B" 9.2 Attachment 2 - "A" MG Set Speed vs. "A" Recirc Pump Discharge Flow 9.3 Attachment 3 - "A" MG Set Speed vs. Loop "A" Jet Pump Flow 9.4 Attachment 4 - Loop "A" Jet Pump % Deviation vs. Jet Pump Number 9.5 Attachment 5 - "B" MG Set Speed vs. "B" Recirc Pump Discharge Flow 9.6 Attachment 6 - "B" MG Set Speed vs. Loop "B" Jet Pump Flow 9.7 Attachment 7 - Loop "B" Jet Pump % Deviation vs. Jet Pump Number 9.8 Attachment 8 - A Jet Pump M-Ratio Plot 9.9 Attachment 9 - B Jet Pump M-Ratio Plot

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

17 of 25 26 SPEED OF PUMP "A" Attachment 1 Sheet 1 of 1 vs. SPEED OF PUMP "B" LIMIT LIMIT BELOW ABOVE OR 69.4% EQUAL TO 69.4%

POWER POWER 110 100 90 OUTSIDE "A" PUMP SPEED (%)

80 LIMIT CONDITIONS 70 60 50 40 OUTSIDE 30 LIMIT CONDITIONS 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 "B" PUMP SPEED (%)

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

18 of 25 26 "A" MG SET SPEED Attachment 2 Sheet 1 of 1 vs. "A" RECIRC PUMP DISCHARGE FLOW Two Loop Operation "A" Recirc Pump Flow Curve 35.0 30.0 25.0 Pump Discharge Flow (KGPM) 20.0 15.0 10.0 5.0 0.0 20% 25% 30% 35% 40% 45% 50% 55% 60% 65% 70% 75% 80% 85% 90% 95% 100% 105% 110%

MG Set Speed (%)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

19 of 25 26 "A" MG SET SPEED Attachment 3 Sheet 1 of 1 vs. LOOP "A" JET PUMP FLOW Two Loop Operation Jet Pump Loop "A" Flow 30.0 25.0 20.0 Loop A Flow (Mlb/Hr) 15.0 10.0 5.0 0.0 20% 25% 30% 35% 40% 45% 50% 55% 60% 65% 70% 75% 80% 85% 90% 95% 100% 105% 110%

MG Set Speed (%)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

20 of 25 26 LOOP "A" JET PUMP % DEVIATION Attachment 4 Sheet 1 of 1 vs. JET PUMP NUMBER Two Loop Operation Loop "A" Jet Pump Dp % Deviation 40.0%

30.0%

20.0%

Jet Pump Dp Deviation 10.0%

0.0%

-10.0%

-20.0%

-30.0%

9 10 11 12 13 14 15 16 Jet Pump Number Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

21 of 25 26 "B" MG SET SPEED Attachment 5 Sheet 1 of 1 vs. "B" RECIRC PUMP DISCHARGE FLOW Two Loop Operation "B" Recirc Pump Flow Curve 35.0 30.0 25.0 Pump Discharge Flow (KGPM) 20.0 15.0 10.0 5.0 0.0 20% 25% 30% 35% 40% 45% 50% 55% 60% 65% 70% 75% 80% 85% 90% 95% 100% 105% 110%

MG Set Speed (%)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

22 of 25 26 "B" MG SET SPEED Attachment 6 Sheet 1 of 1 vs. LOOP "B" JET PUMP FLOW Two Loop Operation Jet Pump Loop "B" Flow 30.0 25.0 20.0 Loop B Flow (Mlb/Hr) 15.0 10.0 5.0 0.0 20% 25% 30% 35% 40% 45% 50% 55% 60% 65% 70% 75% 80% 85% 90% 95% 100% 105% 110%

MG Set Speed (%)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

23 of 25 26 LOOP "B" JET PUMP % DEVIATION Attachment 7 Sheet 1 of 1 vs. JET PUMP NUMBER Two Loop Operation Loop "B" Jet Pump Dp % Deviation 40.0%

30.0%

20.0%

Jet Pump Dp Deviation 10.0%

0.0%

-10.0%

-20.0%

-30.0%

1 2 3 4 5 6 7 8 Jet Pump Number Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

24 of 25 26 Attachment 8 A Jet Pump M-Ratio Sheet 1 of 1 M Ratio 2.30 2.30 2.20 2.20 2.10 Average 2.10 2.00 Upper & Lower Limits 2.00 1.90 1.90 1.80 1.80 1.70 1.70 1.60 1.60 Jet Pump M Ratio 1.50 1.50 1.40 1.40 1.30 1.30 1.20 1.20 1.10 1.10 1.00 1.00 0.90 0.90 0.80 0.80 0.70 0.70 0.60 0.60 0.50 0.50 10.0 11.0 12.0 13.0 14.0 15.0 16.0 17.0 18.0 19.0 20.0 21.0 22.0 23.0 24.0 25.0 26.0

'A' Loop Flow (Mlbm/hr)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

25 of 25 26 Attachment 9 B Jet Pump M-Ratio Sheet 1 of 1 M Ratio 2.30 2.30 2.20 2.20 2.10 2.10 Average 2.00 2.00 Upper & Lower Limits 1.90 1.90 1.80 1.80 1.70 1.70 1.60 1.60 Jet Pump M Ratio 1.50 1.50 1.40 1.40 1.30 1.30 1.20 1.20 1.10 1.10 1.00 1.00 0.90 0.90 0.80 0.80 0.70 0.70 0.60 0.60 0.50 0.50 10.0 11.0 12.0 13.0 14.0 15.0 16.0 17.0 18.0 19.0 20.0 21.0 22.0 23.0 24.0 25.0 26.0

'B' Loop Flow (Mlbm/hr)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

1 of 25 26 Usage Level CONTINUOUS Effective Date: __________________

Approved for Point-of-Use printing IF NO DCFs are in effect for this procedure.

(on designated printers)

Record the following: Date / Time: __________________ / ______________

Printer ID: DA - ____________________ Initials: ________

NOTE: Per ACP 106.1, a DCF/REV check shall be performed and documented every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if active document use exceeds a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period as determined from the date and time recorded above.

Document approval signatures on file Prepared By: Michael Winchester / Date:

Print Signature CROSS-DISCIPLINE REVIEW (AS REQUIRED)

Reviewed By: / Date:

Print Signature Reviewed By: / Date:

Print Signature Reviewed By: / Date:

Print Signature PROCEDURE APPROVAL BY QUALIFIED REVIEWER Approved By / Date:

Print Signature

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

2 of 25 26 1.0 PURPOSE 1.1 The purpose of this STP is to log Recirc Pump speeds daily to ensure Recirc Pumps are not operating at a significant speed mismatch and to verify Jet Pump operability. Verification of Jet Pump operability shall be made daily, following startup of a Recirculation Pump, and after any unexplained changes in core flow, Jet Pump Loop flow, Recirc Loop flow, or core plate differential pressure.

1.2 When this procedure is performed in its entirety it FULLY SATISFIES Recirculation Loop Operations Recirc Pump speed mismatch surveillance requirements.

1.3 When this procedure is performed in its entirety it FULLY SATISFIES Jet Pumps surveillance requirements.

2.0 BRIEFING INFORMATION 2.1 PERFORMANCE INFORMATION 2.1.1 This STP is organized as follows:

STP Sections Evolution 7.1 Recirc Pump Speed Mismatch Check 7.2 Jet Pumps 9-16 Operability Check 7.3 Jet Pumps 1-8 Operability Check 7.4 Jet Pump M-Ratio Determination All steps within a section are to be performed in sequence and the STP steps carried through to completion, unless otherwise indicated. The sections may be performed concurrently for ease of recording data.

Sections 7.2 and 7.3 are not required to be performed when reactor power is less than or equal to () 21.7% RTP. If this procedure is being performed when reactor power is less than or equal to () 21.7% RTP, Prerequisite 6.2 and Sections 7.2 and 7.3 are to be marked "N/A".

2.1.2 Personnel recommended to perform this procedure:

1 Operations 2.1.3 Special Test Equipment required:

None 2.1.4 If Recirculation Pump speed is less than 60% of rated, an Engineering evaluation may be performed to determine Jet Pump OPERABILITY.

2.1.5 M-Ratio determination does not affect Jet Pump operability. If M-Ratio data is not within the upper and lower limits of the curves shown in Attachments 8 and 9, it does not mean that the Jet Pumps are inoperable. Engineering will perform an evaluation as potential causes may be due to normal process measurement noise, changes in core parameters, or instrumentation problems.

{C001}

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

3 of 25 26 2.2 GENERAL CAUTIONS 2.2.1 None 2.3 SPECIAL PRECAUTIONS 2.3.1 None

3.0 REFERENCES

3.1 Commitment items:

3.1.1 C001 - GE SIL-605 (AR 96-2880 and 96-2880.02) 4.0 GENERAL INSTRUCTIONS 4.1 Steps marked with a "TS" immediately to the right of the step sign-off line are required by Technical Specifications. If these steps do not meet their acceptance criteria or cannot be performed, a NRC reportable condition may exist and shall be reported to the Control Room Supervisor (CRS) immediately.

4.2 The CRS shall be immediately notified and the appropriate Limiting Condition for Operations section of Technical Specifications referred to whenever problems are encountered during the performance of this STP.

4.3 An Action Request (AR) should be completed for any problems encountered with TS marked steps during the performance of this test.

5.0 APPENDICES 5.1 Appendix A - JETS Program Instructions

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

4 of 25 26 Appendix A JETS PROGRAM INSTRUCTIONS Sheet 1 of 1

1. If at a workstation desktop, log onto SSE as follows:
a. Click: Start : Programs: PDA APPS: IBM Personal Communications PC3270: PPC
b. At Username Prompt, type SSE <Enter>.
c. Enter the appropriate password and press <Enter>.
d. At the $ prompt, type JETS and press <Enter>.

The Jet Pump Program main menu should come up on the screen.

2. If at a VAX/PPC terminal, log onto SSE as follows:
a. Log onto the SSE account.
b. At the PPC1_SSE prompt, type JETS and press <Enter>. The Jet Pump program main menu should come up on the screen.
3. Type 1 to access combined Loop A and Loop B Jet Pump tables. Type 2 to access only the Loop A Jet Pump table (Jet Pumps 9-16). Type 3 to access only the Loop B Jet Pump table (Jet Pumps 1-8).

NOTE All Ps must be a positive value between 0 and 30, but not including 0 (0<P30). The program will automatically tab forward as each Jet Pump's P is entered. The <Tab> key may be used to move forward to the next Jet Pump, if desired. The <Control> and <H> keys pressed simultaneously may be used to move backward to the previous Jet Pump, if desired. If desired to change a P, use the <Backspace> key to erase all numerals to the left of the decimal point before entering the new numbers.

4. Type in each Jet Pumps P.

NOTE If all fields are not filled with a positive number between 0 and 30, but not including 0 (0<P30) when Step 5.0 is performed, the program will not calculate the % deviations and will return to the Jet Pump main menu.

5. Press the <Enter> key to calculate the % deviations. The printout will automatically print on laser printer LTA14 and the program will automatically terminate.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

5 of 25 26 Prerequisites Performance Date: ____Today_____ INITIALS 6.0 PREREQUISITES 6.1 The reactor is in two-loop operation. (If the reactor is in single loop _ HDM__

operation, perform STP 3.4.2-03 instead.) (OPS) 6.2 For sections 7.2 and 7.3, reactor power is greater than (>) 21.7% RTP. _ HDM__

(See Performance Information Step 2.1.1.) (OPS)

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

6 of 25 26 Performance Date: ______ Today______ INITIALS 7.0 PROCEDURE 7.1 RECIRC PUMP SPEED MISMATCH CHECK 7.1.1 At 1C04, using the "D" button on SIC-9245A, A MG SET SPEED ___HDM__

CONTROL, select "X" - PERCENT SPEED mode of indication.

a. Record the percent speed indication. ___HDM__ TS A MG SET PERCENT SPEED (SIC-9245A.X) ___99.5__ %
b. Record the percent speed indication in Step 7.2.1. (Mark this ___HDM__

step N/A if Section 7.2 is not required.)

c. Using the "D" button on SIC-9245A, select "S" - SETPOINT ___HDM__

mode of indication.

7.1.2 At 1C04, using the "D" button on SIC-9245B, B MG SET SPEED ___HDM__

CONTROL, select "X" - PERCENT SPEED mode of indication.

a. Record the percent speed indication. ___HDM__ TS B MG SET PERCENT SPEED (SIC-9245B.X) ___99.3___%
b. Record the percent speed indication in Step 7.3.1. (Mark this ___HDM__

step N/A if Section 7.3 is not required.)

c. Using the "D" button on SIC-9245B, select "S" - SETPOINT ___HDM__

mode of indication.

7.1.3 On Attachment 1, plot the intersection of the Recirc Pump speed _HDM__

values using the data recorded in Steps 7.1.1.a and 7.1.2.a.

7.1.4 Confirm that the point plotted on Attachment 1 is within the ___HDM__ TS appropriate limit for the current core power. If the point is outside the limit, immediately notify the CRS.

____Hugh D. Mann_____________ Today Now _HDM_

Performed by: Date: Time:

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

7 of 25 26 Performance Date: ______ Today______ INITIALS 7.2 JET PUMPS 9-16 OPERABILITY CHECK 7.2.1 At 1C04, record the following data for the "A" Recirc Pump: ___HDM__

A MG SET PERCENT SPEED (SIC-9245A.X) _99.5_%

DISCHARGE FLOW (FI-4634A) __29.8__ KGPM LOOP A (FI-4523) ___23.5____ Mlbm/hr 7.2.2 Using the data recorded in Step 7.2.1, plot "A" Recirc MG Set ___HDM__ TS speed vs. "A" Recirc Pump discharge flow on Attachment 2.

7.2.3 Using the data recorded in Step 7.2.1, plot "A" Recirc MG Set ___HDM__ TS speed vs. Loop "A" Jet Pump flow on Attachment 3.

NOTE ___HDM__

If Step 7.2.4.a is answered NO, Acceptance Criteria Step 8.3.2 should be answered YES if either Step 7.2.13.a or Step 7.2.13.e is answered YES.

7.2.4 Perform the following evaluation:

a. Are all of the points that were plotted on Attachment 2 and ___HDM__ TS Attachment 3 between or on the sloped lines?

(YES/NO) _____NO______

b. If the answer to Step 7.2.4.a was YES, Jet Pumps 9-16 are ___N/A__

OPERABLE. "N/A" Step 7.2.4.c, Steps 7.2.7 through 7.2.13.e, and Attachment 4. Then continue with Step 7.2.5.

c. If the answer to Step 7.2.4.a was NO, immediately notify the ___HDM__

CRS. Then, "N/A" Step 7.2.4.b and perform the remainder of Section 7.2.

7.2.5 At 1C38, record jet pump total developed head as read on Candidate PDI-4567, Jet Pump Total Head:

PDI-4567: ___25___ psid 7.2.6 At 1C38, record the indicated RECIRC LOOP A Jet Pump Candidate differential pressure value for each Jet Pump in column "A" of Table A (contained in Step 7.2.11).

7.2.7 If the JETS program is available, "N/A" Steps 7.2.9 through 7.2.11 Candidate and then perform the remainder of Section 7.2. If the JETS program is not available, "N/A" Steps 7.2.8 and 7.2.8.a and then perform the remainder of Section 7.2.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

8 of 25 26 Performance Date: ______ Today______ INITIALS 7.2.8 Using the instructions provided in Appendix "A", obtain a printout __ N/A _

of "A" Recirc Loop Ps.

a. Attach the printout to the STP. __ N/A _

7.2.9 Calculate the sum of the individual Jet Pump Ps and the Candidate average Jet Pump P and record those values in the appropriate spaces at the bottom of Table A.

7.2.10 Calculate the difference between each individual Jet Pump P Candidate and the average P and record the results in column "B" of Table A.

7.2.11 Using the following equation, calculate the percent deviation of Candidate each individual Jet Pump P from the average P, and record the result in column "C" of Table A.

Ind. P - Avg. P

% Deviation = 100 x Avg. P TABLE A A B C JET PUMP (P) (Ind.P - Avg.P) (% Deviation)

JP-9 15.0 2.6 21.0 JP-10 13.0 0.6 4.8 JP-11 7.5 -4.9 -39.5 JP-12 8.0 -4.4 -35.5 JP-13 13.5 1.1 8.9 JP-14 13.5 1.1 8.9 JP-15 14.5 2.1 16.9 JP-16 14.5 1.1 16.9 99.5 12.4

÷8=

(Sum of Ps) (Avg.P) 7.2.12 Plot each individual Recirc Loop "A" Jet Pump % deviation value Candidate (from column "C" of Table A or JETS program calculation) on Attachment 4.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

9 of 25 26 Performance Date: ______ Today______ INITIALS NOTE Candidate If Step 7.2.13.a is answered NO, Acceptance Criteria Step 8.3.2 shall be answered NO also, unless Recirc Pump speed is less than 60% of rated and an Engineering evaluation determines that the Jet Pumps are OPERABLE.

7.2.13 Perform the following evaluation:

a. Are all of the points plotted on Attachment 4 on or between Candidate TS the lines of the allowable band?

(YES/NO) __NO___

b. If the answer to Step 7.2.13.a is YES, Jet Pumps 9-16 are _ N/A_

OPERABLE. "N/A" Steps 7.2.13.c, 7.2.13.d, and 7.2.13.e.

c. If the answer to Step 7.2.13.a is NO and Recirc Pump speed Candidate is greater than or equal to () 60% of rated, immediately notify the CRS. Then, "N/A" Steps 7.2.13.b, 7.2.13.d, and 7.2.13.e.
d. If the answer to Step 7.2.13.a is NO and Recirc Pump speed _ N/A_

is less than (<) 60% of rated, immediately inform the CRS and then contact Engineering to perform an evaluation of Jet Pump operability. Then, "N/A" Steps 7.2.13.b and 7.2.13.c.

e. If an Engineering evaluation was performed, are Jet Pumps _ N/A_ TS 9-16 OPERABLE? ("N/A" if an Engineering evaluation is not Engineering required to be performed.)

(YES/NO) __________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

10 of 25 26 Performance Date: ______ Today______ INITIALS 7.3 JET PUMPS 1-8 OPERABILITY CHECK 7.3.1 At 1C04, record the following data for the "B" Recirc Pump: ________

B MG SET PERCENT SPEED (SIC-9245B.X) ______%

DISCHARGE FLOW (FI-4634B) __________ KGPM LOOP B (FI-4526) ___________ Mlbm/hr 7.3.2 Using the data recorded in Step 7.3.1, plot "B" Recirc MG Set ________ TS speed vs. "B" Recirc Pump discharge flow on Attachment 5.

7.3.3 Using the data recorded in Step 7.3.1, plot "B" Recirc MG Set ________ TS speed vs. Loop "B" Jet Pump flow on Attachment 6.

NOTE If Step 7.3.4.a is answered NO, Acceptance Criteria Step 8.3.3 should be answered YES if either Step 7.3.12.a or Step 7.3.12.e is answered YES.

7.3.4 Perform the following evaluation:

a. Are all of the points that were plotted on Attachment 5 and ________ TS Attachment 6 between or on the sloped lines?

(YES/NO) _____________

b. If the answer to Step 7.3.4.a was YES, Jet Pumps 1-8 are ________

OPERABLE. "N/A" Step 7.3.4.c, Steps 7.3.6 through 7.3.12.e, and Attachment 7. Then, perform Step 7.3.5.

c. If the answer to Step 7.3.4.a was NO, immediately notify the ________

CRS. Then, "N/A" Step 7.3.4.b and perform the remainder of Section 7.3.

7.3.5 At 1C38, record the indicated RECIRC LOOP B Jet Pump ________

differential pressure value for each Jet Pump in column "A" of Table B (contained in Step 7.3.10).

7.3.6 If the JETS program is available, "N/A" Steps 7.3.8 through 7.3.10 ________

and then perform the remainder of Section 7.3. If the JETS program is not available, "N/A" Steps 7.3.7 and 7.3.7.a, then perform the remainder of Section 7.3.

7.3.7 Using the instructions provided in Appendix "A", obtain a printout ________

of "B" Recirc Loop Ps.

a. Attach the printout to the STP. ________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

11 of 25 26 Performance Date: ______ Today______ INITIALS 7.3.8 Calculate the sum of the individual Jet Pump Ps and the ________

average Jet Pump P and record the results in the appropriate spaces at the bottom of Table B.

7.3.9 Calculate the difference between each individual Jet Pump P ________

and the average P and record the result in column "B" of Table B.

7.3.10 Using the following equation, calculate the percent deviation of ________

each individual Jet Pump P from the average P and then record the result in column "C" of Table B.

Ind. P - Avg. P

% Deviation = 100 x Avg. P TABLE B A B C JET PUMP (P) (Ind.P - Avg.P) (% Deviation)

JP-1 JP-2 JP-3 JP-4 JP-5 JP-6 JP-7 JP-8

÷ 8 =

(Sum of Ps) (Avg. P) 7.3.11 Plot each individual Recirc Loop "B" Jet Pump % deviation value ________

(from column "C" of Table B or JETS program calculation) on Attachment 7.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

12 of 25 26 Performance Date: ______ Today______ INITIALS NOTE If Step 7.3.12.a is answered NO, Acceptance Criteria Step 8.3.3 shall be answered NO also, unless Recirc Pump speed is less than 60% of rated and an Engineering evaluation determines that Jet Pumps are OPERABLE.

7.3.12 Perform the following evaluation:

a. Are all of the points plotted on Attachment 7 on or between ________ TS the lines of the allowable band?

(YES/NO) __________

b. If the answer to Step 7.3.12.a is YES, Jet Pumps 1-8 are ________

OPERABLE. "N/A" Steps 7.3.12.c, 7.3.12.d, and 7.3.12.e.

c. If the answer to Step 7.3.12.a is NO and Recirc Pump speed ________

is greater than or equal to () 60% of rated, immediately notify the CRS. Then, "N/A" Steps 7.3.12.b, 7.3.12.d, and 7.3.12.e.

d. If the answer to Step 7.3.12.a is NO and Recirc Pump speed ________

is less than (<) 60% of rated, immediately inform the CRS and then contact Engineering to perform an evaluation of Jet Pump operability. Then, "N/A" Steps 7.3.12.b and 7.3.12.c.

e. If an Engineering evaluation was performed, are Jet Pumps ________ TS 1-8 OPERABLE? ("N/A" if an Engineering evaluation is not Engineering required to be performed.)

(YES/NO) __________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

13 of 25 26 Performance Date: ______ Today______ INITIALS 7.4 JET PUMP M-RATIO DETERMINATION NOTE The following steps verify Jet Pump M-Ratio. M-Ratio can help determine Jet Pump degradation. This section of the STP does not determine Jet Pump operability, it is for trending only.

{C001}

7.4.1 If the PPC is not available, mark Steps 7.4.2 through 7.4.7 N/A. ________

Otherwise, mark this step N/A.

7.4.2 Record the value of computer point B062, A Recirc Loop Flow, ________

below:

B062 ______________

7.4.3 Record the value of computer point B026SM, A Recirc Pump ________

Discharge Flow, below:

B026SM ______________

7.4.4 If the computer point B062 value recorded in Step 7.4.2 is greater than or equal to () 10 Mlbm/hr, perform Steps 7.4.4.a through 7.4.4.c. If the computer point B062 value is less than (<) 10 Mlbm/hr, mark Steps 7.4.4.a through 7.4.4.c N/A.

a. Determine M-Ratio by completing the following calculation: ________

M-Ratio = (value from Step 7.4.2) - (value from Step 7.4.3)

(value from Step 7.4.3)

M-Ratio = ( )-( )

( )

M-Ratio = ___________

b. Plot "A" Recirc Loop M-Ratio (value from Step 7.4.4.a) against ________

"A" Recirc Loop flow (value from Step 7.4.2) on Attachment 8.

c. If the "A" Recirc Loop M-Ratio is not within the upper and ________

lower limits, initiate an Action Request (AR) and contact the System Engineer to perform an evaluation (see Performance Information Step 2.1.5). Otherwise, mark this step N/A.

7.4.5 Record the value of computer point B061, B Recirc Loop Flow, ________

below:

B061 ______________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

14 of 25 26 Performance Date: ______ Today______ INITIALS 7.4.6 Record the value of computer point B028SM, B Recirc Pump ________

Discharge Flow, below:

B028SM ______________

7.4.7 If the computer point B061 value recorded in Step 7.4.5 is greater than or equal to () 10 Mlbm/hr perform Steps 7.4.7.a through 7.4.7.c. If the computer point B061 value is less than (<) 10 Mlbm/hr mark Steps 7.4.7.a through 7.4.7.c "N/A":

a. Determine M-Ratio by completing the following calculation: ________

M-Ratio = (value from Step 7.4.5) - (value from Step 7.4.6)

(value from Step 7.4.6)

M-Ratio = ( )-( )

( )

M-Ratio = ___________

b. Plot "B" Recirc Loop M-Ratio (value from Step 7.4.7.a) against ________

"B" Recirc Loop flow (value from Step 7.4.5) on Attachment 9.

c. If the "B" Recirc Loop M-Ratio is not within the upper and ________

lower limits, initiate an Action Request (AR) and contact the System Engineer to perform an evaluation (see Performance Information Step 2.1.5). Otherwise, mark this step N/A.

Performed by: Date: Time:

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

15 of 25 26 Performance Date: ____________________ INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 Check below the reason for performing this STP. If this STP is performed for any reason other than for satisfying the PURPOSE as stated in Section 1.0, indicate below (otherwise mark this step "N/A"):

[ ] Daily Requirement

[ ] Pump Start

[ ] Unexplained changes

[ ] Other 8.2 If a DCF, Procedure Work Request (PWR), or Action Request (AR) was written due to problems encountered with the performance of this procedure, list the applicable number(s) below. ("N/A" blocks as appropriate.)

DCF No. __________ PWR No. ___________ AR No. ___________

DCF No. __________ PWR No. ___________ AR No. ___________

8.3 All Technical-Specification-required items, as indicated by "TS", have been performed satisfactorily.

8.3.1 Section 7.1 ( ) YES ( ) NO CRS notified ________

8.3.2 Section 7.2 ( ) YES (X) NO CRS notified _HDM__

8.3.3 Section 7.3 ( ) YES ( ) NO CRS notified ________

8.4 All other items checked in this test have been performed satisfactorily.

8.4.1 Section 7.1 ( ) YES ( ) NO CRS notified ________

8.4.2 Section 7.2 ( ) YES ( ) NO CRS notified ________

8.4.3 Section 7.3 ( ) YES ( ) NO CRS notified ________

8.4.4 Section 7.4 ( ) YES ( ) NO CRS notified ________

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

16 of 25 26 Performance Date: ____________________ INITIALS 8.5 Indicate any relevant test comments below, otherwise mark this step "N/A":

Operations Date Surveillance Coordinator Date 9.0 ATTACHMENTS 9.1 Attachment 1 - Speed of Pump "A" vs. Speed of Pump "B" 9.2 Attachment 2 - "A" MG Set Speed vs. "A" Recirc Pump Discharge Flow 9.3 Attachment 3 - "A" MG Set Speed vs. Loop "A" Jet Pump Flow 9.4 Attachment 4 - Loop "A" Jet Pump % Deviation vs. Jet Pump Number 9.5 Attachment 5 - "B" MG Set Speed vs. "B" Recirc Pump Discharge Flow 9.6 Attachment 6 - "B" MG Set Speed vs. Loop "B" Jet Pump Flow 9.7 Attachment 7 - Loop "B" Jet Pump % Deviation vs. Jet Pump Number 9.8 Attachment 8 - A Jet Pump M-Ratio Plot 9.9 Attachment 9 - B Jet Pump M-Ratio Plot

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

17 of 25 26 SPEED OF PUMP "A" Attachment 1 Sheet 1 of 1 vs. SPEED OF PUMP "B" LIMIT LIMIT BELOW ABOVE OR 69.4% EQUAL TO 69.4%

POWER POWER 110 HDM 100 90 OUTSIDE "A" PUMP SPEED (%)

80 LIMIT CONDITIONS 70 60 50 40 OUTSIDE 30 LIMIT CONDITIONS 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 "B" PUMP SPEED (%)

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

18 of 25 26 "A" MG SET SPEED Attachment 2 Sheet 1 of 1 vs. "A" RECIRC PUMP DISCHARGE FLOW Two Loop Operation "A" Recirc Pump Flow Curve 35.0 30.0 HDM 25.0 Pump Discharge Flow (KGPM) 20.0 15.0 10.0 5.0 0.0 20% 25% 30% 35% 40% 45% 50% 55% 60% 65% 70% 75% 80% 85% 90% 95% 100% 105% 110%

MG Set Speed (%)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

19 of 25 26 "A" MG SET SPEED Attachment 3 Sheet 1 of 1 vs. LOOP "A" JET PUMP FLOW Two Loop Operation Jet Pump Loop "A" Flow 30.0 25.0 HDM 20.0 Loop A Flow (Mlb/Hr) 15.0 10.0 5.0 0.0 20% 25% 30% 35% 40% 45% 50% 55% 60% 65% 70% 75% 80% 85% 90% 95% 100% 105% 110%

MG Set Speed (%)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

20 of 25 26 LOOP "A" JET PUMP % DEVIATION Attachment 4 Sheet 1 of 1 vs. JET PUMP NUMBER Two Loop Operation Loop "A" Jet Pump Dp % Deviation 40.0%

30.0%

20.0%

Jet Pump Dp Deviation 10.0%

0.0%

-10.0%

-20.0%

-30.0%

9 10 11 -35.5 12 13 14 15 16 Jet Pump Number

-39.5 Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

21 of 25 26 "B" MG SET SPEED Attachment 5 Sheet 1 of 1 vs. "B" RECIRC PUMP DISCHARGE FLOW Two Loop Operation "B" Recirc Pump Flow Curve 35.0 30.0 25.0 Pump Discharge Flow (KGPM) 20.0 15.0 10.0 5.0 0.0 20% 25% 30% 35% 40% 45% 50% 55% 60% 65% 70% 75% 80% 85% 90% 95% 100% 105% 110%

MG Set Speed (%)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

22 of 25 26 "B" MG SET SPEED Attachment 6 Sheet 1 of 1 vs. LOOP "B" JET PUMP FLOW Two Loop Operation Jet Pump Loop "B" Flow 30.0 25.0 20.0 Loop B Flow (Mlb/Hr) 15.0 10.0 5.0 0.0 20% 25% 30% 35% 40% 45% 50% 55% 60% 65% 70% 75% 80% 85% 90% 95% 100% 105% 110%

MG Set Speed (%)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

23 of 25 26 LOOP "B" JET PUMP % DEVIATION Attachment 7 Sheet 1 of 1 vs. JET PUMP NUMBER Two Loop Operation Loop "B" Jet Pump Dp % Deviation 40.0%

30.0%

20.0%

Jet Pump Dp Deviation 10.0%

0.0%

-10.0%

-20.0%

-30.0%

1 2 3 4 5 6 7 8 Jet Pump Number Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

24 of 25 26 Attachment 8 A Jet Pump M-Ratio Sheet 1 of 1 M Ratio 2.30 2.30 2.20 2.20 2.10 Average 2.10 2.00 Upper & Lower Limits 2.00 1.90 1.90 1.80 1.80 1.70 1.70 1.60 1.60 Jet Pump M Ratio 1.50 1.50 1.40 1.40 1.30 1.30 1.20 1.20 1.10 1.10 1.00 1.00 0.90 0.90 0.80 0.80 0.70 0.70 0.60 0.60 0.50 0.50 10.0 11.0 12.0 13.0 14.0 15.0 16.0 17.0 18.0 19.0 20.0 21.0 22.0 23.0 24.0 25.0 26.0

'A' Loop Flow (Mlbm/hr)

Last updated from data acquired on March 7, 2009.

SURVEILLANCE TEST PROCEDURE STP 3.4.2-01 DAEC DUANE ARNOLD ENERGY CENTER TITLE: DAILY JET PUMP OPERABILITY TEST Page Rev.

25 of 25 26 Attachment 9 B Jet Pump M-Ratio Sheet 1 of 1 M Ratio 2.30 2.30 2.20 2.20 2.10 2.10 Average 2.00 2.00 Upper & Lower Limits 1.90 1.90 1.80 1.80 1.70 1.70 1.60 1.60 Jet Pump M Ratio 1.50 1.50 1.40 1.40 1.30 1.30 1.20 1.20 1.10 1.10 1.00 1.00 0.90 0.90 0.80 0.80 0.70 0.70 0.60 0.60 0.50 0.50 10.0 11.0 12.0 13.0 14.0 15.0 16.0 17.0 18.0 19.0 20.0 21.0 22.0 23.0 24.0 25.0 26.0

'B' Loop Flow (Mlbm/hr)

Last updated from data acquired on March 7, 2009.

QF-1030-11 Rev. 7 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2009 NRC RO JPM A-4 TITLE: Entering / Exiting a Contaminated Area Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File NRC JPM RO A-4 REV 7-16-09.DOC

QF-1030-11 Rev. 7 JOB PERFORMANCE MEASURE (JPM)

JPM TITLE: Entering / Exiting a Contaminated Area JPM NUMBER: NRC RO A-4 REV. 0 TASK NUMBER(S) / Radiation Worker Task 74 / Don protective clothing, including hood, TASK TITLE(S): coveralls, glove liners, gloves, shoe liners, and shoe covers.

K/A NUMBERS: Generic 2.3.7 K/A VALUE: 3.5 / 3.6 Justification (FOR K/A N/A VALUES <3.0):

TASK APPLICABILITY: RO SRO STA NSPEO SRO CERT APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: Other: X Training Center Annex Lab:

Time for Completion: 20 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:

Instructor Date Validated by:

Validation Instructor Date Reviewed by:

Plant Reviewer Date Approved by:

Training Supervisor Date Commitments: {C001} ACE 001729, Review recommendation 4 of OE 001501.

{C002} CA046394, Improvements needed for Operations Simulator JPMs.

Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File NRC JPM RO A-4 REV 7-16-09.DOC Page 1 of 1

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?
2. Has the JPM been reviewed and validated by SMEs?
3. Can the required conditions for the JPM be appropriately established in the simulator if required?
4. Do the performance steps accurately reflect candidates actions in accordance with plant procedures?
5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the candidate properly performed the step?
6. Has the completion time been established based on validation data or incumbent experience?
7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
8. Is the Licensee level appropriate for the task being evaluated if required?
9. Is the K/A appropriate to the task and to the licensee level if required?
10. Is justification provided for tasks with K/A values less than 3.0?
11. Have the performance steps been identified and typed (Critical / Sequence

/ Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the candidate?
13. Are all references identified, current, accurate, and available to the candidate?
14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
15. Are all critical steps clearly identified by procedural guidance? If licensing, EP or other groups were needed to determine correct actions, then the answer should be NO. {C001}
16. If the JPM is to be administered to an ILT student, has the required knowledge been taught to the individual prior to administering the JPM?

TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. {C001}

All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

RE-VALIDATION SIGNATURE JPMs must be re-validated prior to use. Verify the above Review Statements are YES or N/A. When it is determined that the JPM is still valid and can be performed as written, sign and date the form below.

Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date NRC JPM RO A-4 REV 7-16-09.DOC Page 2 of 2

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 SIMULATOR SET UP:

Simulator Setup Instructions:

1. This JPM is not performed in the Simulator
2. Ensure the Training Center Annex is setup for this JPM.
a. Frisker probe is face up on the table, power on, set to the lowest range.
b. Obtain a hardhat, lanyard, TLD, and ED (with clip) from the training annex area.
c. Ensure no other activities in the area that will interfere with this JPM.

Map ACP 1411.19 SIMULATOR MALFUNCTIONS:

TIME MALFUNCTION # MALFUNCTION ET DELAY F. SEV. RAMP I. SEV.

TITLE SIMULATOR OVERRIDES:

TIME OVERRIDE ID OVERRIDE ET DELAY VALUE RAMP DESCRIPTION SIMULATOR REMOTE FUNCTIONS:

TIME REMOTE REMOTE FUNCTION TITLE VALUE RAMP FUNCTION #

Required Materials: RWP for Operations Department (09-10, step 2)

ACP 1411.19, Use of Protected Clothing, Rev 18 General

References:

ACP 1411.2, Conduct of Radiation Protection, Rev. 5 ACP 1411.27, Rules for conduct of work in RCAs, Rev. 28 Task Standards: Dress out in single set of Protective Clothing, enter contaminated area, exit the contaminated area, remove Protective Clothing and frisk out of the area.

NRC JPM RO A-4 REV 7-16-09.DOC Page 3 of 3

QF-1030-11 Rev. 7 TURNOVER SHEET INITIAL CONDITIONS:

  • It has been decided that an inspection of the simulated contaminated area in the Training Center Annex is required by Operations to look for leaking water pipes.
  • You have not entered the RCA in the last week.

INITIATING CUES (IF APPLICABLE):

  • The CRS directs you to
  • dress out per ACP 1411.19,
  • enter the simulated contaminated area,
  • perform a general area inspection, and
  • exit the area following all requirements of ACP 1411.19.
  • Use RWP 09-10, Task #2.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC JPM RO A-4 REV 7-16-09.DOC Page 4 of 4

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

  • It has been decided that an inspection of the simulated contaminated area in the Training Center Annex is required by Operations to look for leaking water pipes.
  • You have not entered the RCA in the last week.

INITIATING CUES (IF APPLICABLE):

  • The CRS directs you to
  • dress out per ACP 1411.19,
  • enter the simulated contaminated area,
  • perform a general area inspection, and
  • exit the area following all requirements of ACP 1411.19.
  • Use RWP 09-10, Task #2.

NOTE: Evaluator, provide the hard hat, lanyard, badge, TLD, and ED (with clip), ACP 1411.19 and RWP 09-10, step 2 to candidate at this time.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC JPM RO A-4 REV 7-16-09.DOC Page 5 of 5

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Candidate recognizes that he will need an Access Control briefing prior to Critical Y entering the Contaminated Area IAW the RWP.

Standard: Determines that he will require an Access Control daily briefing to work in the contaminated area.

Provide the Survey of the Area to the candidate. Point out that there are no walls, all boundaries.

Inform candidate that modesty garments (scrubs) will be simulated for this exam.

Inform him that the area he is entering requires a single set of Protective Clothing. This consists of:

  • Hard hat cover
  • NO Respirator required
  • Coveralls
  • NO Hood required
  • Glove Liners
  • NO special dosimetry is required, Evaluator Cue:
  • Rubber Gloves use normal ED
  • Booties
  • NO meter is required
  • Shoe Covers If candidate desires an RWP Pocket Data sheet, it is available in this area as the Pink Sheet.

Use the data sheet at the end of this JPM to cover the information for the HP brief.

Inform the candidate that upon exit of the area, will have to use the frisker for the whole body frisk due to the Personnel Contamination Monitor (PCM) not working.

Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC JPM RO A-4 REV 7-16-09.DOC Page 6 of 6

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 Performance Step: 2 Candidate logs in to the access control system.

Critical Y Standard: Candidate logs into the access control system using RWP 10 step 2.

Evaluator Note: When entering the RCA at DAEC, the worker is required to record the work order number in use. If no work order is being used, then the worker must use standard bar scan tags (provided at the scanner at access control) to generically identify what the worker is in the RCA for.

Evaluator Cue: When the candidate logs into Access Control, might have to cue the candidate that the computer shows RWP 09-10, task 2, with Dose Rate alarm of 50 mrem and Dose alarm of 90 mrem/hr.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 Candidate inspects the protective clothing, looking for cuts or holes, especially in Critical N the seat, knees and elbows. Tests rubber gloves for leaks by capturing air and holding to confirm that pressure can be maintained.

Standard: Candidate inspects the protective clothing prior to donning the clothing.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 Candidate dons a single set of full protective clothing.

Critical Y Standard: Protective Clothing donned in such a way to prevent/minimize the chance of personnel contamination when entering the contaminated area.

Evaluator Note: General Rules for PC:

Rubber gloves should be over the coveralls Cloth shoe covers should be under the coveralls Skull cap might be used, due the hardhat being a public hard hat.

Evaluator Cue: Inform that candidate that scrubs (modesty garments) will be simulated Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC JPM RO A-4 REV 7-16-09.DOC Page 7 of 7

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 Performance Step: 5 Candidate ensures the proper dosimetry is worn with the protective clothing.

Critical Y Standard: The TLD is to be worn on a lanyard under all protective clothing (with his badge), while the Electronic Dosimeters is to be placed in the pocket of the coverall.

Evaluator Note: The candidate may place the ED in a bag, but this is not required since the coveralls has pockets.

The candidate may call the Control Room to inform them of entry into area.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 6 Candidate enters Contaminated area.

Critical Y Standard: Candidate enters Contaminated area.

Evaluator Cue: May need to inform the candidate that the Amber light on the card reader is GREEN, not amber. When the candidate is in the simulated contaminated area, inform him that he has completed his tour of the area, and to exit the area.

IF candidate observes bad housekeeping in the area, inform him that HPs have been called to pick up area.

Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC JPM RO A-4 REV 7-16-09.DOC Page 8 of 8

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 Performance Step: 9 Candidate takes off Protective Clothing and disposes of clothing at Step Off Critical Y Pad.

Standard: Strict adherence to sequence is NOT necessary as long as the candidate does not increase his risk of contamination.

Removal Sequence:

Approach the Step Off Pad Remove any tape used Remove the Rubber shoes and dispose of Remove rubber gloves and dispose of Remove electronic dosimetry and place on step off pad Remove coveralls by:

  • Loosening the coverall
  • Grasp the coverall collar
  • Slip coverall off shoulder, pulling arms inside out
  • Slide coverall down and off the body, rolling them
  • Dispose of coveralls.

Remove shoe covers, placing the clean foot on the step off pad after the shoe cover is removed. Dispose of the shoes.

Place Hard Hat cover in the proper receptacle Remove cotton liners and place in trash receptacle Retrieve electronic dosimeter (being careful not to spread any potential contamination.

Proceed to frisker Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 10 Candidate checks frisker prior to using it.

Critical Y Standard: Candidate checks:

1. Frisker is ON.
2. Frisker is set on lowest scale.
3. Background level is below 300 CPM.

Evaluator Cue: If asked, inform the candidate that the frisker IS in calibration.

Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC JPM RO A-4 REV 7-16-09.DOC Page 9 of 9

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 Performance Step: 11 Candidate performs hand and foot frisk.

Critical Y Standard: Candidate should check free hand first, then dosimetry prior to laying it down.

Frisker detector should be within 1/2 inch from surface, traveling at a speed of about 2-3 inches per second.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: Once the candidate has performed a frisk to exit the area, then the JPM is complete.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002}

Stop Time:

NRC JPM RO A-4 REV 7-16-09.DOC Page 10 of 10

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 NRC JPM RO A-4 REV 7-16-09.DOC Page 11 of 11

QF-1030-11 Rev. 7 NRC JPM RO A-4 REV 7-16-09.DOC Page 12 of 12

QF-1030-11 Rev. 7 NRC JPM RO A-4 REV 7-16-09.DOC Page 13 of 13

QF-1030-11 Rev. 7 Name Today 09-10 2 Training Annex Contaminated Area General Area Inspection 0.8 to 180

<1K to 10K 2-3 2-3 50 90 15 15

Warn others, exit
  • If find a wet area, stay clear of the area.
  • When exiting area, the PCM is broken, so use the frisker for whole body frisk, then travel to access control to exit RCA.

When briefing the map of the area, use the above information.

NRC JPM RO A-4 REV 7-16-09.DOC Page 14 of 14

QF-1030-11 Rev. 7 NRC RO A-4, Entering / Exiting a Contaminated Area, Rev. 0 Examinee: Evaluator:

RO SRO STA NSPEO SRO CERT Date:

ILT RO ILT SRO PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC JPM RO A-4 REV 7-16-09.DOC Page 15 of 15

ADMINISTRATIVE CONTROL PROCEDURE ACP 1411.19 USE OF PROTECTIVE CLOTHING Rev. 17 Page 1 of 9 Usage Level Information Use Effective Date:

Approved for Point-of-Use printing IF NO DCFs are in effect for this procedure.

(on designated printers)

Record the following: Date / Time: __________________ / ______________

Printer ID: DA - ____________________ Initials: ________

NOTE: Per ACP 106.1, a DCF/REV check shall be performed and documented every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if active document use exceeds a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period as determined from the date and time recorded above.

Document approval signatures on file Prepared By: / Date:

Print Signature CROSS-DISCIPLINE REVIEW (AS REQUIRED)

Reviewed By: / Date:

Print Signature Reviewed By: / Date:

Print Signature PROCEDURE APPROVAL BY QUALIFIED REVIEWER Approved By / Date:

Print Signature

ADMINISTRATIVE CONTROL PROCEDURE ACP 1411.19 USE OF PROTECTIVE CLOTHING Rev. 17 Page 2 of 9 Table of Contents Page 1.0 PURPOSE ............................................................................................................................. 3 2.0 DEFINITIONS ........................................................................................................................ 3 3.0 INSTRUCTIONS .................................................................................................................... 3 3.1 PROTECTIVE CLOTHING ...................................................................................... 3 3.2 SELECTION OF PROTECTIVE CLOTHING ........................................................... 3 3.3 USE OF SCRUBS (MODESTY GARMENTS) ......................................................... 4 3.4 GENERAL RULES FOR DONNING AND REMOVING PROTECTIVE CLOTHING .............................................................................................................. 5 3.5 HARD HAT USE ...................................................................................................... 6 3.6 DOSIMETRY PLACEMENT .................................................................................... 6 3.7 REMOVING LABORATORY COATS ...................................................................... 6 3.8 REMOVING SINGLE SET OF PROTECTIVE CLOTHING...................................... 7 3.9 REMOVING DOUBLE SET OF PROTECTIVE CLOTHING AND RESPIRATOR ......................................................................................................... 8 4.0 RECORDS ............................................................................................................................. 9

5.0 REFERENCES

...................................................................................................................... 9

ADMINISTRATIVE CONTROL PROCEDURE ACP 1411.19 USE OF PROTECTIVE CLOTHING Rev. 17 Page 3 of 9 1.0 PURPOSE This procedure provides personnel with guidelines and instructions for donning and removing protective clothing (PCs) and applies to all workers at DAEC who work in Radiologically Controlled Areas (RCA).

2.0 DEFINITIONS Radiation Work Permit (RWP) - A documented administrative control to communicate radiological conditions, radiation protection requirements, and radiological hold points to workers in radiologically controlled areas. RWPs are also used as a method for dose tracking and prescribing the use of protective clothing.

3.0 INSTRUCTIONS 3.1 PROTECTIVE CLOTHING (1) All personnel shall comply with protective clothing requirements listed on the RWP or as specified by Health Physics.

(2) Workers must contact Health Physics if protective clothing items are damaged or lost.

(3) Cloth protective clothing items will not function properly if they are wet. Contact Health Physics if cloth items become wet.

(4) Rubber gloves and rubber over shoes are classified as disposable, single use items at the DAEC. After using these items, they should be disposed of as contaminated trash.

(5) The DAEC uses both reusable cloth and OREX-type or similar disposable PCs. When a specific type of PC is to be used, it will be identified on the RWP.

(6) Hard hat covers should be worn as directed on the RWP.

3.2 SELECTION OF PROTECTIVE CLOTHING (1) Review requirements for protective clothing as contained in the RWP.

(2) Collars of coveralls are colored according to size of the coverall.

(3) Select appropriate clothing from the storage racks as required by the RWP or as directed by Health Physics.

ADMINISTRATIVE CONTROL PROCEDURE ACP 1411.19 USE OF PROTECTIVE CLOTHING Rev. 17 Page 4 of 9 (4) Check each item for defects.

(a) Test rubber gloves for leaks by capturing air and holding to confirm that pressure can be maintained.

(b) Inspect remaining PCs by looking for cuts or holes, especially in the seat, knees and elbows.

(c) Notify Health Physics or Helpers of damaged protective clothing or equipment.

(5) Proceed to change area.

3.3 USE OF SCRUBS (MODESTY GARMENTS)

(1) Scrubs must be worn under coveralls.

(2) Scrubs can be used as substitutes for street clothes within the Radiological Controlled Area on tasks controlled by RWPs.

(3) DAEC will supply surgical scrubs, but workers may provide their own. Normal laundering of these garments is the responsibility of the worker.

(4) With the exception of scrubs, underclothing, socks, and shoes, no personal clothing should be worn under protective coveralls.

(i) Personal items such as rings, watches, or other jewelry should be removed to help minimize the risk of contaminating these items.

(5) There will be no monetary reimbursement:

(i) For contaminated scrubs or personal clothing used in lieu of scrubs.

(ii) For contaminated jewelry.

(6) Scrubs can be removed from the radiological area provided they clear contamination monitors.

(7) Scrubs contaminated with radioactive material will be disposed of as radioactive trash.

ADMINISTRATIVE CONTROL PROCEDURE ACP 1411.19 USE OF PROTECTIVE CLOTHING Rev. 17 Page 5 of 9 3.4 GENERAL RULES FOR DONNING AND REMOVING PROTECTIVE CLOTHING NOTE When donning protective clothing pay particular attention to areas where the protective clothing overlaps to assure the clothing can be removed without spreading contamination.

(1) Rubber gloves should be over the coveralls.

(a) If two pairs of gloves and one set of coveralls is required, the inner pair should be secured to the coveralls and the outer pair not secured.

(b) If two pairs of gloves and two sets of coveralls are required, the inner pair of gloves should be secured to the inner set of coveralls. The outer pair of gloves should not be secured.

(2) Cloth shoe covers should be under the coveralls.

(a) If two pairs of shoe covers are required, the inner set of shoe covers must be under the inner set of coveralls, while the outer pair of shoe covers must be over the first set of coveralls.

(3) If tape is required:

(a) Leave a tab to allow easy removal.

(b) Use the least amount possible to minimize the generation of waste.

(c) Remove tape and dispose of properly when removing PCs.

(4) Unless multiple step-off pads are used, the step-off pad is a clean area. To prevent contamination spread, do not step on pad until all protective clothing has been removed.

(5) Upon exiting a Contaminated Area, proceed to the nearest Personnel Contamination Monitor (PCM) or frisking area for a whole body frisk.

(6) Do not touch outside of coveralls or clothing with exposed body parts.

(7) Do not allow protective clothing to come in contact with the surface of the step-off-pad while undressing.

(8) All articles of clothing and trash should be placed in appropriately marked containers.

ADMINISTRATIVE CONTROL PROCEDURE ACP 1411.19 USE OF PROTECTIVE CLOTHING Rev. 17 Page 6 of 9 3.5 HARD HAT USE (1) Personal hard hats are to be worn in contaminated areas (unless specified) in accordance with the DAEC Safety Rulebook.

(2) Do not use a skullcap with a personal hard hat.

(3) Hard hat covers shall be used as direct by RWP clothing requirements.

(4) After exiting the contaminated area, wear the personal hard hat when using the PCM.

3.6 DOSIMETRY PLACEMENT (1) Electronic dosimeters:

(a) Are to be placed in the pocket of the outermost set of coveralls.

(b) Are to be worn on a lanyard underneath lab coats.

(2) TLDs are to be worn on a lanyard under all protective clothing.

3.7 REMOVING LABORATORY COATS (1) Follow any instructions printed on the step-off pad(s) or issued by Health Physics.

(2) Remove all tape and place in waste container.

(3) Loosen Velcro ankle bands, if applicable. Remove cuff sealers, if applicable.

(4) Remove rubber overshoes.

(5) Remove gloves.

(6) Remove lab coat.

(7) Remove shoe cover from one foot and step out of it directly on to the step-off pad.

Remove other shoe cover in similar manner.

(8) Remove hard hat cover, if applicable, and place in trash receptacle. Personal hard hat to remain on head.

(9) Remove glove liners and place in trash receptacle.

(10) Proceed to PCM or frisking area for whole body frisk.

ADMINISTRATIVE CONTROL PROCEDURE ACP 1411.19 USE OF PROTECTIVE CLOTHING Rev. 17 Page 7 of 9 3.8 REMOVING SINGLE SET OF PROTECTIVE CLOTHING (1) Follow any instructions printed on the step-off pad(s) or issued by Health Physics.

(2) If respirator is worn, perform the following:

(a) Remove outer rubber gloves (if two sets are worn).

(b) Remove hard hat cover and hard hat, if applicable.

(c) Remove the hood.

(d) Remove respirator by bending forward, grasping the hose connection or canister filter and pulling up and out, away from the face.

(e) Separate the surgeon's cap from the respirator (if applicable).

(f) Place respirator into appropriate container.

(3) Remove all tape from protective clothing.

(4) Remove Velcro ankle bands if applicable.

(5) Remove cuff sealers, if applicable.

(6) Remove rubber overshoes.

(7) Remove rubber gloves.

(8) If hood is worn, remove hard hat and cover.

(9) Remove hood, if applicable or not already removed.

(10) Remove dosimetry and badge from coverall and place on step-off pad.

(11) Unzip and remove coverall by:

(a) Fully unzipping coverall, (b) Grasp coverall collar, (c) Slip coverall off shoulder, pulling arms inside out, (d) Slide coverall down and off the body, rolling the coverall inside out.

ADMINISTRATIVE CONTROL PROCEDURE ACP 1411.19 USE OF PROTECTIVE CLOTHING Rev. 17 Page 8 of 9 (12) Remove shoe cover from one foot and step out of it directly on to the step-off pad.

Remove other shoe cover in similar manner.

(13) Remove hard hat cover if applicable and place in trash receptacle, personal hard hat to remain on head.

(14) Remove glove liners and place in trash receptacle.

(15) Pick up dosimetry and badge, if applicable.

(16) Proceed to PCM or frisking area for whole body frisk.

3.9 REMOVING DOUBLE SET OF PROTECTIVE CLOTHING AND RESPIRATOR NOTE A second step-off pad is generally used when removing a double set of protective clothing. Contrary to Section 3.4, this inner step-off pad is considered to be contaminated. The first step-off pad can direct the person to either remove rubber boots before stepping onto it or remove outer protective clothing before stepping onto it.

(1) If first step-off pad instructs you to remove rubber boots, pull rubber boots off and step onto the step-off pad.

(2) If first step-off pad instructs you to remove outer protective clothing then the following steps should be performed:

(a) Remove rubber overshoes.

(b) Remove outer rubber gloves.

(c) Remove dosimetry from outer coverall pocket and place into inner coverall pocket.

(d) Remove outer coveralls.

(e) Remove outer shoe covers while stepping onto the first step-off pad.

(3) Remove remaining protective clothing following the steps below:

(a) Remove hard hat and hard hat cover, if applicable.

(b) Remove the hood.

(c) If no respirator was worn proceed to Step (3)(g).

ADMINISTRATIVE CONTROL PROCEDURE ACP 1411.19 USE OF PROTECTIVE CLOTHING Rev. 17 Page 9 of 9 (d) Remove respirator by bending forward, grasping the hose connection or canister filter and pulling up and out, away from the face.

(e) Separate the surgeon's cap from the respirator (if applicable).

(f) Place respirator into the appropriate container.

(g) Remove all tape from protective clothing and place in waste container.

(h) Remove rubber gloves.

(i) Remove dosimetry and badge from coverall and place on step-off pad.

(j) Unzip and remove coverall by grasping coverall collar, slipping coverall off shoulder and pulling arms inside out. Slide coverall down and off the body, rolling the coverall inside out.

(k) Remove shoe cover from one foot and step out of it directly on to the step-off pad.

Remove other shoe cover in a similar manner.

(4) Remove glove liners and place in trash receptacle.

(5) Pick up dosimetry and badge. Personal hard hat should be smeared out of area.

(6) Proceed to PCM or frisking area for whole body frisk.

4.0 RECORDS (1) No records are generated as a result of this procedure.

5.0 REFERENCES

(1) Duane Arnold Energy Center General Employee Training Manual (2) CAP045314 (3) CA046912

QF-1030-11 Rev. 7 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2009 NRC JPM SRO A-1 TITLE: Review Control Room Shiftly Instrument Checks Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM SRO-A-1

QF-1030-11 Rev. 7 JOB PERFORMANCE MEASURE (JPM)

JPM TITLE: Review Control Room Shiftly Instrument Checks JPM NUMBER: 2009 NRC JPM SRO A-1 REV. 0 TASK NUMBER(S) / 1.02 / Determine Operability for Technical Specification Required Components TASK TITLE(S):

K/A NUMBERS: 2.1.18 K/A VALUE: 3.8 Justification (FOR K/A VALUES <3.0): N/A TASK APPLICABILITY: RO SRO STA NSPEO SRO CERT APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: Other: X Lab:

Time for Completion: 45 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:

Instructor Date Validated by:

Validation Instructor Date Reviewed by:

Plant Reviewer Date Approved by:

Training Supervisor Date Commitments: {C001} ACE 001729, Review recommendation 4 of OE 001501.

{C002} CA046394, Improvements needed for Operations Simulator JPMs.

Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM SRO-A-1 Page 1 of 1

QF-1030-11 Rev. 7 2009 NRC JPM SRO-A-1, Rev. # 0 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?
2. Has the JPM been reviewed and validated by SMEs?
3. Can the required conditions for the JPM be appropriately established in the simulator if required?
4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
6. Has the completion time been established based on validation data or incumbent experience?
7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
8. Is the Licensee level appropriate for the task being evaluated if required?
9. Is the K/A appropriate to the task and to the licensee level if required?
10. Is justification provided for tasks with K/A values less than 3.0?
11. Have the performance steps been identified and typed (Critical / Sequence

/ Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
13. Are all references identified, current, accurate, and available to the trainee?
14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
15. Are all critical steps clearly identified by procedural guidance? If licensing, EP or other groups were needed to determine correct actions, then the answer should be NO. {C001}
16. If the JPM is to be administered to an ILT student, has the required knowledge been taught to the individual prior to administering the JPM?

TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. {C001}

All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

RE-VALIDATION SIGNATURE JPMs must be re-validated prior to use. Verify the above Review Statements are YES or N/A. When it is determined that the JPM is still valid and can be performed as written, sign and date the form below.

Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date DAEC 2009 NRC JPM SRO-A-1 Page 2 of 2

QF-1030-11 Rev. 7 2009 NRC JPM SRO-A-1, Rev. # 0 SIMULATOR SET UP:

1. No Simulator Setup Required.

SIMULATOR MALFUNCTIONS:

TIME MALFUNCTION # MALFUNCTION ET DELAY F. SEV. RAMP I. SEV.

TITLE SIMULATOR OVERRIDES:

TIME OVERRIDE ID OVERRIDE ET DELAY VALUE RAMP DESCRIPTION SIMULATOR REMOTE FUNCTIONS:

TIME REMOTE REMOTE FUNCTION TITLE VALUE RAMP FUNCTION #

Required Materials: 1. Marked up copy of STP 3.0.0-01 Instrument Checks

2. Calculator General

References:

STP 3.0.0-01 Instrument Checks, Revision 95 Task Standards: 1. Identifies 100 percent of Out-Of-Specification TS related readings

  • Difference between NR level indications greater than allowable
  • Difference between Torus Temp entered 5.8F v. 6.8F
  • Difference between MSL flows greater than allowable
2. Corrects inaccurate entries
3. Identifies Technical Specification required actions Note: Problems do NOT need to be identified in any particular order as long as all are identified.

DAEC 2009 NRC JPM SRO-A-1 Page 3 of 3

QF-1030-11 Rev. 7 TURNOVER SHEET INITIAL CONDITIONS:

  • You are the Control Room Supervisor
  • DAEC has been at full power for several weeks
  • NO other STPs are in progress
  • The time is now 08:45 INITIATING CUES (IF APPLICABLE):
  • You are directed to review Instrument checks for accuracy and determine any appropriate actions.
  • This JPM is NOT time critical NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

DAEC 2009 NRC JPM SRO-A-1 Page 4 of 4

QF-1030-11 Rev. 7 2009 NRC JPM SRO-A-1, Rev. # 0 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

  • You are the Control Room Supervisor
  • DAEC has been at full power for several weeks
  • NO other STPs are in progress
  • The time is now 08:45 INITIATING CUES (IF APPLICABLE):
  • You are directed to review Instrument checks for accuracy and determine any appropriate actions.
  • This JPM is NOT time critical NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

DAEC 2009 NRC JPM SRO-A-1 Page 5 of 5

QF-1030-11 Rev. 7 2009 NRC JPM SRO-A-1, Rev. # 0 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Reactor Coolant Leakage Calculation Critical Y Standard:

  • Identifies that Leakage change (1.0.e - 3.0.a) was incorrectly entered as 1.14 gpm; actual value is 2.14 gpm.
  • Identifies TS 3.4.4 Condition B entry required.

Evaluator Note: Problems do NOT need to be identified in a particular order Evaluator Cue: If asked, inform the candidate that ALL of the drain totalizer readings (FQ3707 & FQ3708) and the Unidentified average leak rate for the PREVIOUS DAY have been independently verified correct.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 Narrow Range Reactor Water Level: Difference between LRS 4559 and LI Critical Y 4559 or LRS 4560 and LI 4560 as selected by HSS 4560. (High-Low)

Standard:

  • Determines difference between LRS 4559 and LI 4559 or LRS 4560 and LI 4560 as selected by HSS 4560. (High-Low) is >2.5 inches
  • Identifies TRM 3.3.6.1, Function 1, Condition A entry required Evaluator Note: Problems do NOT need to be identified in a particular order Performance: SATISFACTORY UNSATISFACTORY Comments:

DAEC 2009 NRC JPM SRO-A-1 Page 6 of 6

QF-1030-11 Rev. 7 2009 NRC JPM SRO-A-1, Rev. # 0 Performance Step: 3 Torus Water Temperature: Difference between TR 4386A and TR 4386B (High Critical Y Low)

Standard:

  • Determines difference between TR 4386A and TR 4386B (High Low) was incorrectly entered as 5.8°F; actual value is 6.8°F.
  • Identifies TRM 3.3.6.1, Function 5, Condition A entry required Evaluator Note: Problems do NOT need to be identified in a particular order Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 Main Steam Line Differential Flow: PDIS 4436A through 4436D, Difference Critical Y between Highest and Lowest of above 4 readings (Highest Lowest)

Standard:

  • Identifies difference between PDIS 4436A and PDIS 4436C is >10 psid.
  • Identifies TS 3.3.6.1, Function 1.c, Condition A entry required Evaluator Note: Problems do NOT need to be identified in a particular order Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues:

  • STP 3.0.0-01 Instrument Checks, pages 11 through 24, (Shiftly Checks portion) reviewed
  • Discrepancies identified
  • TS / TRM Condition entries identified NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002}

Stop Time:

DAEC 2009 NRC JPM SRO-A-1 Page 7 of 7

QF-1030-11 Rev. 7 2009 NRC JPM SRO-A-1, Rev. # 0 Examinee: Evaluator:

RO SRO STA NSPEO SRO CERT Date:

ILT RO ILT SRO PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

DAEC 2009 NRC JPM SRO-A-1 Page 8 of 8

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 11 of 55 Date: Today Rev. 95 PANEL INSTRUMENT TECH SHIFTS FUNCTION ACCEPTANCE CRITERIA NUMBER NUMBER SPEC 2 3 Shiftly Instrument Checks shall be Start Time Start Time started and completed within the 0740 _________

Surveillance following time bands for each specific Completion Time Frequency N/A SR 3.0.2 Completion Time N/A shift.

Shift 2 within 0700-1000 0827 _________

Operators Initials Operators Initials Shift 3 within 1900-2200 (Note 1) RO Shiftly Instrument Checks second reviews shall be completed by the Time 0842 Time _________

Surveillance N/A following time for each specific shift. Reviewer's Initials Reviewer's Initials N/A Frequency Shift 2 by 1000 Shift 3 by 2200 HDM (Note 1)

Surveillance Shiftly HSM Checks second review Time _________

N/A N/A Frequency shall be completed by 1300. Reviewer's Initials Note 1: HSM Daily and River Water flow and depth checks are not required to be performed within the normal shiftly window.

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 12 of 55 Date: Today Rev. 95 PANEL INSTRUMENT TECH SHIFTS FUNCTION ACCEPTANCE CRITERIA NUMBER NUMBER SPEC 2 3 Computer Computer Point 99.88%

Console Power Level C133 or N/A (Note 1) or Average of APRM 1C05 readings Computer Point C196 or Inputs to M022 read with a Fluke and calculated per following equation:

For Ultimate Heat Sink, verify River Computer River Water mV-12.8 = M022 Water Temp 95°F (TS) 72°F SR 3.7.2.2 Console Temperature 0.512 or TR 2900 or Local Thermometer (Note 2)

Note 1: Power level should remain constant while shiftly readings are being taken. If power changes or has to be changed, note this in Section 8.5.

Note 2: If all other remote temperature indication for river water temperature is out of service, river water temperature may be obtained locally with a thermometer in the vicinity of the Intake Structure. If river water temperatures are taken manually, they are only required once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to satisfy Tech Spec SR 3.7.2.2. If the readings are taken manually for an extended period of time (i.e., more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), the readings shall be taken between 0700 and 1300 to ensure the frequency requirements of Tech Spec SR 3.0.2 and SR 3.7.2.2 are met.

Record following thermometer data: ID#: ______N/A___________ Cal Due Date: ______N/A___________

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 13 of 55 Date: Today Rev. 95 PANEL INSTRUMENT TECH SHIFTS FUNCTION ACCEPTANCE CRITERIA NUMBER NUMBER SPEC 2 3 Control Rod Initials (Note 1) Initials (Note 1) 1C05 Full Core Display SR 3.10.2.1 Verify all Control Rods "FULL IN" (TS)

Position N/A Reactor Initials Initials Complete Calculation Sheet (TS)

N/A Coolant Leakage N/A SR 3.4.4.1 (Attachment 3/4) RO Calculation One Recirc Pump or one SDC Initials Initials subsystem in operation. (N/A if not N/A SR 3.4.7.1 applicable to current conditions, see Note 2 below) N/A 1C03 One Recirc Pump or one SDC Initials Initials subsystem in operation. (N/A if not N/A SR 3.4.8.1 applicable to current conditions, see Note 3 below) N/A 1C04 Reactor Vessel TR 4569 Green Pen 74°F (TS) (Only required in MODE 4 N/A SR 3.4.9.7 and RCS Temperature is 100°F - see Flange and Head TR 4569 Red Pen Note 4 below). N/A Bolt Temperature Note 1: All Control Rods are to be verified "FULL IN", once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, during periods when TS 3.10.2 is invoked, otherwise N/A.

Note 2: Applicable in Mode 3 with reactor steam dome pressure less than (<) RCIC Steam Supply Line Pressure - Low Isolation Pressure.

Note 3: Applicable in Mode 4.

Note 4: If RCS Temperature is planned to be reduced to 80F or below, commence 30 minute temperature checks per STP-3.4.9-02.

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 14 of 55 Date: Today Rev. 95 PANEL INSTRUMENT SHIFTS FUNCTION TECH SPEC ACCEPTANCE CRITERIA NUMBER NUMBER 2 3 1C05 LRS 4559 or LRS 4560 A A as selected by B B HSS 4560 189.2 LI 4559 190 LI 4560 192 LI 4561 190 Narrow Range Reactor Difference between LRS 4559 and LI 4559 Water Level TSR or LRS 4560 and 2.5 inches (TM) 2.8 3.3.6.1-1 LI 4560 as selected by HSS 4560. (High-Low)

Difference between the highest and lowest of TSR 2.5 inches (TM)

LI 4559, LI 4560 and 3.3.6.1-1 2..0 LI 4561 PR 4542 / Comp Point 1025 psig (TS) (Record PR4563/64 B049 SR 3.4.10.1 reading only if PR 4542 and B049 not 1021.4 OR available)

PR4563/64 (backup)

PR 4563 or PR 4564 as 1029.4 selected by HSS 4560 PI 4563 1018 PI 4564 1022 Reactor PI 4565 1020 Pressure Difference between PR 4563 and PI 4563 or TSR PR 4564 and PI 4564 as 48 psig (TM) selected by HSS 4560 3.3.6.1-2 7.4 (High-Low)

Difference between the highest and lowest of TSR 48 psig (TM)

PI 4563, PI 4564 and 3.3.6.1-2 [see Note 1]

PI 4565 4 Note 1: Since these instruments are not calibrated below 300 psig (they are only checked 'Not Downscale' below 300 psig), the acceptance criteria of 48 psig does not apply when Reactor Pressure is 300 psig or less.

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 15 of 55 Date: Today Rev. 95 PANEL INSTRUMENT SHIFTS FUNCTION TECH SPEC ACCEPTANCE CRITERIA NUMBER NUMBER 2 3 Comp. Pt. Comp. Pt.

B000 B001 100 99 NMR NMR 9254A 9254B 100 99 APRM A APRM B NM 9270 NM 9271 100 98 Comp. Pt. Comp. Pt.

SR B002 B003 100 100 3.3.1.1.1-2.a NMR NMR 3.3.1.1.1-2.b Computer 9254A 9254D 100 99 Console, APRM C APRM D APRM Level TSR 1C05 and NM 9272 NM 9273 3.3.2.1-1.a 98 99 1C37 Comp. Pt. Comp. Pt.

3.3.2.1-1.b B004 B005 3.3.2.1-1.d 100 100 NMR NMR 3.3.6.1-7 9254C 9254D 100 99 APRM E APRM F NM 9274 NM 9275 98 99 From the above 18 readings subtract the lowest from the 10% (TS, TM) 2 highest (Highest-Lowest)

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 16 of 55 Date: Today Rev. 95 PANEL INSTRUMENT SHIFTS FUNCTION TECH SPEC ACCEPTANCE CRITERIA NUMBER NUMBER 2 3 NMR9254 A IRM A N/A NMR9254 A IRM C N/A NMR9254 C IRM E SR (Not Required in MODE 1) N/A 3.3.1.1.1-1.a NMR9254 B IRM B (Note 1) N/A NMR9254 D IRM D N/A IRM Level NMR9254 D IRM F N/A From the above six TSR readings, take the 3.3.2.1-2.b highest and divide by the 3.3.2.1-2.d 10 (TS, TM) N/A lowest. 3.3.6.1-7 (Not Required in MODE 1) 1C05 Highest Lowest NMI 9278 A N/A NMI 9278 B SR 3.0 cps (TS) N/A NMI 9278 C 3.3.1.2.1-1 (Not Required in MODE 1) N/A NMI 9278 D 3.3.1.2.3-1 N/A SRM Level From the above four 3.3.1.2.4-1 readings, take the TSR highest and divide by the 3.3.2.1-3.b 10 (TS, TM) N/A lowest. 3.3.2.1-3.d (Not Required in MODE 1)

Highest Lowest 1C06 Condensate LI 5216A 1. SR 3.5.2.2.b 1. One CST: 11 ft. OR both CSTs 18 (1T-5A) 2. UFSAR 7 ft. (Note 2) (TS)

Storage Tank LI 5217A 5.4.6.3 and 18 Level (1T-5B) 6.3.2.2.1 2. Both CSTs 8 ft. (Note 3) (UFSAR)

Note 1: Record Range Switch position as well as reading and compensate readings for differences in Range Switch position before dividing the highest by the lowest.

Note 2: Applicable in Mode 4 only. Only one required Core Spray Subsystem may take credit for this operation during OPDRVs. May be N/A'd if Suppression Pool level is 8 feet. May also be N/A'd if no Core Spray Subsystems are required to be operable.

Note 3: With HPCI/RCIC suction aligned to the CST (ref. OI 150 and OI 152 Precautions and Limitations), if CST levels are both less than

(<) 8 feet and HPCI High Pressure Keep Fill pressure (as indicated on PI2308) is less than (<) 80 psig and HPCI Low Pressure Keep Fill is NOT in service, HPCI shall be considered INOPERABLE and UNAVAILABLE.

If CST levels are both less than (<) 8 feet, RCIC shall be considered INOPERABLE and UNAVAILABLE.

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 17 of 55 Date: Today Rev. 95 PANEL INSTRUMENT SHIFTS FUNCTION TECH SPEC ACCEPTANCE CRITERIA NUMBER NUMBER 2 3 Total Well Water FR4414 (FR4414G if 1C23 Flow FR4414 is OOC)

() 3000 gpm (Note 1) 1295 gpm gpm 1C29 PR 4384A 0.96 Pen 1 (Red)

Drywell PR 4385A 0.95 Pen 1 (Red)

Pressure Difference between PR 4384A and TSR 3.3.6.1-3 2 psid (TM) 0.01 PR 4385A (High-Low)

TR 4386A 78.1 Pen 1 (Red)

TR 4386B 84.9 Pen 1 (Red)

Torus Water Average of TR 4386A 95°F (TS) ( 105°F during testing Temperature Pen 1 (Red) and SR 3.6.2.1.1 which adds heat to Torus) 81.5 TR 4386B Pen 1 (Red)

Difference between TR 4386A and TSR 3.3.6.1-5 6°F (TM) 5.8 TR 4386B (High-Low)

LR 4384C

1. SR 3.6.2.2.1 1. 10.11 and 10.43 (TS) 10.23 Pen 3 (Blue)
2. SR 3.5.2.1 2. 7 ft (TS) (Note 2)

Torus Water LR 4385B 3. SR 3.5.2.2.a 3. 8 ft (TS) (Note 3) 10.25 Pen 2 (Green)

Level Difference between LR 4384C and TSR 3.3.6.1-6 0.05 (TM) 0.02 LR 4385B (High-Low)

Note 1: Combined maximum flow for all four well water pumps may not exceed 3000 gpm, per DNR Well Water Permit Note 2: Only applicable in Mode 4. Required LPCI Subsystem(s) only. May be N/A'd if no LPCI Subsystems are required to be operable.

Note 3: Only applicable in Mode 4. Required Core Spray Subsystem(s) only. May be N/A'd if no Core Spray Subsystems are required to be operable or may be N/A'd if only one Core Spray Subsystem is required and it is lined up to the CSTs.

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 18 of 55 Date: Today Rev. 95 PANEL SHIFTS FUNCTION INSTRUMENT NUMBER TECH SPEC ACCEPTANCE CRITERIA NUMBER 2 3 Computer Point B095 156 TR 4383A Channel 1 (Red) 158 Difference between B095 and TR 4383A TSR 3.3.6.1-4 10°F (TM) 2 Channel 1 (High-Low)

Computer Point B093 134 TR 4383A Channel 2 (Green) 133 Difference between B093 and TR 4383A TSR 3.3.6.1-4 12°F (TM) 1 Channel 2 (High-Low)

Computer Point B091 89 TR 4383A Channel 3 (Blue) 88 Difference between B091 and TR 4383A TSR 3.3.6.1-4 10°F (TM) 1 Channel 3 (High-Low)

Computer Point B094 133 1C29 and Drywell TR 4383B Channel 1 (Red) 133 Computer Temperature Console Difference between B094 and TR 4383B TSR 3.3.6.1-4 10°F (TM) 0 Channel 1 (High-Low)

Computer Point B092 95 TR 4383B Channel 2 (Green) 96 Difference between B092 and TR 4383B TSR 3.3.6.1-4 10°F (TM) 1 Channel 2 (High-Low)

Computer Point B089 85 TR 4383B Channel 3 (Blue) 82 Difference between B089 and TR 4383B TSR 3.3.6.1-4 10°F (TM) 3 Channel 3 (High-Low)

Computer Point B090 87 TR 4383C Channel 1 (Red) 88 Difference between B090 and TR 4383C TSR 3.3.6.1-4 10°F (TM) 1 Channel 1 (High-Low)

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 19 of 55 Date: Today Rev. 95 PANEL INSTRUMENT SHIFTS FUNCTION TECH SPEC ACCEPTANCE CRITERIA NUMBER NUMBER 2 3 Computer Point B096 86 1C29 and TR4383C Channel 2 84 Drywell (Green)

Computer 2

Temperature Difference between Console TSR B096 and TR 4383C 10°F (TM) 3.3.6.1-4 Channel 2 (High-Low)

RR 4379A Particulate 170 Pen 1 (Red)

RR 4379A Gaseous 38 Pen 2 (Green)

Containment RR 4379A Iodine Pen 3 Demonstrate ability to obtain reading 210 (Blue) 1C29 Air Sampling SR 3.4.5.1 (satisfies TS channel check System RR 4379B Particulate requirement) 840 Pen 1 (Red)

RR 4379B Gaseous 310 Pen 2 (Green)

RR 4379B Iodine Pen 3 470 (Blue)

RM 4448A 180 Main Steam RM 4448C 170 1C36 Line Tunnel N/A < 250 mR/hr Radiation RM 4448B 140 RM 4448D 180

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 20 of 55 Date: Today Rev. 95 PANEL INSTRUMENT SHIFTS FUNCTION TECH SPEC ACCEPTANCE CRITERIA NUMBER NUMBER 2 3 DS 10B ON DS 11B ON LLS & RPS DS 12B ON 1C45 Hi Pressure NONE Confirm light is on.

Scram Monitors DS 10A ON DS 11A ON DS 12A ON 1C56 LITS 4539 192 LITS 4540 SR 186 1C55 Difference between 3.3.3.1.1-2.a LITS 4539 and 15 inches (TS) 6 LITS 4540 (High-Low) 1C56 Reactor LIS 4535 191 Water LIS 4537 SR 182 Level LIS 4536 3.3.6.1.1-1.a 187 3.3.6.1.1-5.e LIS 4538 3.3.4.2.1 190 1C55 From the above 4 TSR readings, subtract the 3.3.1.1.a 37.5 inches (TS, TM) 9 Lowest from the Highest (Highest-Lowest) 1C56 LIS 4531 189 SR LIS 4533 3.3.5.1.1-1.a 184 LIS 4532 3.3.5.1.1-2.a 192 Reactor Water 3.3.5.1.1-2.g Level LIS 4534 3.3.5.1.1-3.a 187 1C55 From the above 4 3.3.5.1.1-4.a readings, subtract the 3.3.5.1.1-5.a Lowest from the Highest 3.3.5.2.1-1 37.5 inches (TS) 8 (Highest-Lowest)

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 21 of 55 Date: Today Rev. 95 PANEL INSTRUMENT TECH SHIFTS FUNCTION ACCEPTANCE CRITERIA NUMBER NUMBER SPEC 2 3 1C56 LIS 4561 191 Reactor LIS 4562 190 1C55 Water Level Difference between SR 1 LIS 4561 and LIS 4562 3.3.5.1.1-4.c 10 inches (TS)

(High-Low) 3.3.5.1.1-5.c 1C56A LIS 4592A SR 188 3.3.5.2.1-2 LIS 4592B 3.3.5.1.1-3.c 191 LIS 4592C 3.3.1.1.1-4 190 Reactor Water 3.3.6.1.1-2.a Level LIS 4592D 3.3.6.1.1-6.b 189 1C55A From the above 4 3.3.6.2.1-1 readings, subtract the 10 inches (TS) 3 Lowest from the Highest (Highest-Lowest)

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 22 of 55 Date: Today Rev. 95 PANEL INSTRUMENT TECH SHIFTS FUNCTION ACCEPTANCE CRITERIA NUMBER NUMBER SPEC 2 3 PDIS 4432A 85 1C126A PDIS 4432B 87 100 psid PDIS 4432C 90 PDIS 4432D 83 1C126B Difference between Highest and Lowest of SR 10 psid (TS) 7 above 4 readings 3.3.6.1.1-1.c (Highest-Lowest)

PDIS 4434A 88 1C122B PDIS 4434B 87 100 psid PDIS 4434C 91 PDIS 4434D 85 1C126B Difference between Highest and Lowest of SR 10 psid (TS) 6 above 4 readings 3.3.6.1.1-1.c Main Steam (Highest-Lowest)

Line Differential PDIS 4436A 91 1C126A Flow PDIS 4436B 88 100 psid PDIS 4436C 80 PDIS 4436D 89 1C126B Difference between Highest and Lowest of SR 10 psid (TS) 11 above 4 readings 3.3.6.1.1-1.c (Highest-Lowest)

PDIS 4438A 87 1C126A PDIS 4438B 85 100 psid PDIS 4438C 89 PDIS 4438D 83 1C126B Difference between Highest and Lowest of SR 10 psid (TS) 6 above 4 readings 3.3.6.1.1-1.c (Highest-Lowest)

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 23 of 55 Date: Today Rev. 95 Page 1 of 2 ATTACHMENT 3 REACTOR COOLANT LEAKAGE (Note: Not required in Mode 4 )

All readings are to be taken at 1C19, after completing the 0800 readings in Attachments 1 and 2.

1.0 Unidentified average leak rate calculation

a. FQ 3707 present day 0800 reading 9584612
b. FQ 3707 previous day 0800 reading 9579918
c. Total gallons pumped (a-b) __4694__
d. Time interval (a-b) _____24____ hours x 60 = ____1440___ min.
e. Unidentified average leak rate = Total Gallons Pumped (c)

Time Interval (minutes) (d) = __3.26_ gpm

f. Confirm unidentified average leak rate from Step 1.0.e is less than or equal to () 5 gpm.

May be > 5 gpm if STP 3.4.4-01 in progress to reclassify unidentified leakage.

______RO_____ Operator's Initials 2.0 Total average leak rate calculation

a. FQ 3708 present day 0800 reading 40504468
b. FQ 3708 previous day 0800 reading 40496217
c. Total gallons pumped (a-b) 8251
d. Time interval (a-b) ______24_______ hours x 60 = _____1440_____ min.
e. Identified average leak rate = Total Gallons Pumped Time Interval (minutes) (d) = 5.73___ gpm
f. Total average leak rate = 1.0.e + 2.0.e = ______8.99__________
g. Confirm total average leak rate is less than or equal to () 25 gpm.

______RO_____ Operators Initials NOTE _RO__

During reactor startup and ascension to normal operating pressure, the 2 gpm increase may possibly be exceeded. Under these conditions, leakage should be closely monitored until normal operating pressure is achieved and a baseline leakage rate established.

3.0 24 Hour Comparison

a. Record the Unidentified average leak rate for the previous day (Step 1.0.e from yesterdays logs).

Previous 0800 Unidentified calculation ___1.12__________ gpm

b. Leakage change (1.0.e - 3.0.a) _________1.14_______ gpm
c. Confirm the Leakage Change (Step 3.0.b) indicates less than a 2 gpm increase.

May be > 2 gpm if STP 3.4.4-01 in progress to reclassify unidentified leakage.

_________RO_____ Operators Initials

Shiftly Checks SURVEILLANCE TEST PROCEDURE STP 3.0.0-01 TITLE: INSTRUMENT CHECKS Page 24 of 55 Date: Today Rev. 95 Page 2 of 2 ATTACHMENT 3 REACTOR COOLANT LEAKAGE (Note: Not required in Mode 4 )

NOTE ___RO__

If required to be performed, Step 3.0.d is not required to be completed within the normal Tech Spec Surveillance window.

d. If unidentified average leak rate recorded in Step 1.0.e is less than (<) 1.0 gpm, N/A this Step. If greater than or equal to () 1.0 gpm, request Chemistry to sample at the next available opportunity and complete the Leakage Evaluation to determine source of unidentified leakage.

______RO_____ Operator's Initials 4.0 If DW leakage increases by 1 gpm or more since last reading, then call ___N/A__

Engineering and Plant Management to review current trend and perform the following data evaluation. Otherwise, mark this step and the following data evaluation steps N/A.

a. Has DW Radiation Monitor Particulate indication increased or shown a step ___N/A__

increase, as indicated on RR4379A/B?

Y or N

b. Does Conductivity of the DW sump sample indicate a decreasing trend by ___N/A__

at least 10%? (Chemistry to provide sample results.)

Y or N

c. Does Polyphosphate (if present) indicate a decreasing trend by at least ___N/A__

10% in the DW sump sample? (Chemistry to provide sample results.)

Y or N

d. Is Na-24 present (greater than detectable) in the DW sump sample? ___N/A__

(This would be indicative of a reactor coolant leak.)

Y or N

e. If any responses to questions 1 through 4 (above) are answered Yes (Y), ___N/A__

then a Rx Coolant or Steam Leak may exist. If STP 3.4.4-01 is being used to reclassify a portion of Unidentified leakage, the amount reclassified shall be frozen at the most recently recorded value (refer to General Instruction 4.10).

f. If all responses to questions 1 through 4 (above) are answered No (N), a ___N/A__

leak exists from a source other than reactor coolant and an adjustment to Drywell Unidentified leakage is allowed. Initiate STP 3.4.4-01 to reclassify Unidentified leakage.

g. If the above evaluation results in a change from the previous conclusion ___N/A__

(e.g. well water to reactor coolant leak or steam leak), then contact engineering for further evaluation to determine the Unidentified leakage.

Otherwise, mark this step N/A.

QF-1030-11 Rev. 4 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2009 NRC SRO JPM A-2 TITLE: Review Startup Lineup Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM SRO-A-2

QF-1030-11 Rev. 4 JOB PERFORMANCE MEASURE (JPM)

JPM TITLE: Review a Startup Lineup JPM NUMBER: 2009 NRC JPM SRO A-2 REV. 0 TASK NUMBER(S) / 1.16 / Determine System Operability Documentation is Complete TASK TITLE(S):

K/A NUMBERS: 2.1.29 K/A VALUE: 4.0 Justification (FOR K/A VALUES <3.0): N/A TASK APPLICABILITY: RO SRO STA NSPEO SRO CERT APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: Other: X Lab:

Time for Completion: 20 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:

Instructor Date Validated by:

Validation Instructor Date Reviewed by:

Plant Reviewer Date Approved by:

Training Supervisor Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM SRO-A-2 Page 1 of 1

QF-1030-11 Rev. 4 2.1.7-03, Review Startup Lineup, Rev. 6 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?
2. Has the JPM been reviewed and validated by SMEs?
3. Can the required conditions for the JPM be appropriately established in the simulator if required?
4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
6. Has the completion time been established based on validation data or incumbent experience?
7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
8. Is the Licensee level appropriate for the task being evaluated if required?
9. Is the K/A appropriate to the task and to the licensee level if required?
10. Is the K/A appropriate to the task and to the licensee level if required?
11. Have the performance steps been identified and typed (Critical /

Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
13. Are all references identified, current, accurate, and available to the trainee?
14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.

Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date DAEC 2009 NRC JPM SRO-A-2 Page 2 of 2

QF-1030-11 Rev. 4 2.1.7-03, Review Startup Lineup, Rev. 6 SIMULATOR SET UP:

Simulator is not required for this JPM.

JPM setup:

Required Materials: OI-149, Attachment 6 completed and signed off up to the Ready for S/U Operations Shift Supervisor signature.

Add the following statement handwritten in the margin beside MO-2000, 1.

MO-2000 indication was dual, NSPEO declutched and closed MO-2000 ~1/3 turn to get CLOSE light to stay lit and OPEN light to go out.

o Sign the completed by section on page 1 of checklist IPOI-7, Special Operations Tech Specifications 3.6.1.3 TRM TLCO 3.0.4. T3.5.1 ACP 1410.7 General

References:

OI-149, Attachment 6, RHR System Control Panel Lineup, Rev. 2 IPOI 7, Special Operations, Rev. 108 Technical Specifications, 3.6.1.3, Amendment 223 TRM, Section T 3.5.1, Rev. TRMCR-026 TRM TLCO 3.0.4, Rev. 8, TRMCR-015 ACP 1410.7, Guidelines for Primary Containment Valves and Penetrations, Rev 20 Task Standards: Does NOT sign the Ready for S/U signature block.

Declares MO-2000 INOP per IPOI-7, P&L #3.

Declares A Drywell Spray inoperable per TRM 3.5.1.A (30 day LCO).

Declares PCIS valve being inoperable per TS 3.6.1.3.A (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LCO)

Determines MODE change to MODE 2 cannot occur.

DAEC 2009 NRC JPM SRO-A-2 Page 3 of 3

QF-1030-11 Rev. 4 TURNOVER SHEET INITIAL CONDITIONS:

  • You are on shift as the CRS.
  • Plant is in Mode 3 with no LCOs.
  • A review of the IPOI 1, Startup Package noted that the RHR Control Panel Lineup was missing.
  • CAP has been written.
  • RHR Control Panel Lineup has just been performed by your crew.

INITIATING CUES (IF APPLICABLE):

  • As the Shift Manager, I am directing you, as the CRS, to complete the review of this RHR Control Panel Lineup and sign the Ready for S/U block when your review is complete, or inform me of any discrepancies.

Page 4 of 4

QF-1030-11 Rev. 4 2.1.7-03, Review Startup Lineup, Rev. 6 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

  • You are on shift as the CRS.
  • Plant is in Mode 3 with no LCOs.
  • A review of the IPOI 1, Startup Package noted that the RHR Control Panel Lineup was missing.
  • CAP has been written.
  • RHR Control Panel Lineup has just been performed by your crew.

INITIATING CUES (IF APPLICABLE):

  • As the Shift Manager, I am directing you (the CRS) to complete the review of this RHR Control Panel Lineup and sign the Ready for S/U block when your review is complete, or inform me of any discrepancies.

DAEC 2009 NRC JPM SRO-A-2 Page 5 of 5

QF-1030-11 Rev. 4 2.1.7-03, Review Startup Lineup, Rev. 6 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 RHR System Control Panel Lineup (OI-149 Attachment 6) is reviewed and the Critical Y information in the margin beside MO-2000 is found.

Standard: Candidate reviews the RHR Control Panel Lineup, discovers the information in the margin beside MO-2000 and does NOT sign the Ready for S/U signature block.

Evaluator Cue: When the candidate communicates this to you, as the Shift Manager, direct the candidate to determine any additional requirements.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 Per IPOI 7 Section 2.0, P&L #3, the valve must be declared INOP.

Critical Y Standard: Candidate declares MO-2000 INOP.

Evaluator Cue: If the candidate only wants to report that MO-2000 is INOP, direct him to identify plant impact of this valve being INOP.

If the candidate wants to initiate a CAP/work request card, inform them that the CAP and/or work request card will be completed by the STA.

Performance: SATISFACTORY UNSATISFACTORY Comments:

DAEC 2009 NRC JPM SRO-A-2 Page 6 of 6

QF-1030-11 Rev. 4 2.1.7-03, Review Startup Lineup, Rev. 6 Performance Step: 3 Drywell sprays are required in Modes 1, 2, & 3 per TRM 3.5.1. Condition A Critical Y states with one RHR DW spray subsystem inoperable, the LCO is 30 days to restore the DW spray subsystem to operable.

Standard: Candidate declares A DW Spray Subsystem inoperable and states there is a 30 day TLCO, 3.5.1 condition A.

Evaluator Cue: If candidate attempts to contact licensing, inform the candidate that licensing is not available at this time and direct the candidate to make the initial decision without licensing.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 MO-2000 is also a containment isolation valve per ACP 1410.7 attachment 1.

Critical Y Per Tech Spec 3.6.1.3, all PCIV valves are required in Modes 1, 2, & 3.

Thus with the valve inoperable, although closed, LCO 3.6.1.3, condition A must be entered and the valve must be deactivated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the affected flowpath must be verified isolated every 31 days.

Standard: Candidate declares the PCIS function of the valve inoperable and states there is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LCO, 3.6.1.3, condition A to deactivate a closed valve in the flowpath.

Evaluator Cue: If candidate attempts to contact licensing, inform the candidate that licensing is not available at this time and direct the candidate to make the initial decision without licensing.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: Inform the candidate that the JPM is complete.

Stop Time:

DAEC 2009 NRC JPM SRO-A-2 Page 7 of 7

QF-1030-11 Rev. 4 2.1.7-03, Review Startup Lineup, Rev. 6 JPM Number:

JPM

Title:

Review Startup Lineup Examinee: Evaluator:

RO SRO STA NSPEO SRO CERT Date:

PERFORMANCE RESULTS: SAT: UNSAT:

COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

DAEC 2009 NRC JPM SRO-A-2 Page 8 of 8

OI 149A6 RHR SYSTEM CONTROL PANEL LINEUP Usage Level REFERENCE Effective Date:

Approved for Point-of-Use printing IF NO DCFs are in effect for this procedure.

(on designated printers)

Record the following: Date / Time: __________________ / _____________

Printer ID: DA - ____________________ Initials: _______

NOTE: Per ACP 106.1, a copy of NG Form NG-019A (Working Copy Cover Page) shall be attached to the front of this document if active document use exceeds a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period as determined from the date and time recorded above.

Document approval signatures on file Prepared By: / Date:

Print Signature CROSS-DISCIPLINE REVIEW (AS REQUIRED)

Reviewed By: / Date:

Print Signature Reviewed By: / Date:

Print Signature PROCEDURE APPROVAL BY QUALIFIED REVIEWER Approved By : / Date:

Print Signature OI 149 Attachment 6 Page 1 of 7 Rev. 2

OI 149A6 RHR SYSTEM CONTROL PANEL LINEUP

1.0 REFERENCES

(1) BECH-M119 (2) BECH-M120 OI 149 Attachment 6 Page 2 of 7 Rev. 2

OI 149A6 RHR SYSTEM CONTROL PANEL LINEUP Attachment 6 Control Panel Lineup - Page 1 of 5 Usage Level REFERENCE Discrepancies:

Discrepancy/

Control Panel Wvd./Rstr.

Clearance Number Date Time Completed by: Cletes a. Hower Today 30 minutes ago Reviewed by:

Senior Licensed Operator Ready for S/U:

Control Room Supervisor OI 149 Attachment 6 Page 3 of 7 Rev. 2

OI 149A6 RHR SYSTEM CONTROL PANEL LINEUP Attachment 6 Control Panel Lineup - Page 2 of 5 Device Wvd./ Req'd.

Number Panel Description Discrep. Rstr. Init. Pos.

MO-1989 1C03 TORUS SUCTION (keylocked hand switch) cah OPEN /

OPEN MO-1913 1C03 B PUMP TORUS SUCTION (keylocked cah OPEN /

hand switch) OPEN MO-1912 1C03 B PUMP SHUTDOWN CLG SUCTION cah CLOSE /

CLOSE MO-1920 1C03 D PUMP SHUTDOWN CLG SUCTION cah CLOSE/

CLOSE MO-1921 1C03 D PUMP TORUS SUCTION (keylocked cah OPEN /

handswitch) OPEN 1P-229D 1C03 D RHR PUMP cah AUTO /

STOP MO-1935 1C03 (B RHR) MIN FLOW BYPASS cah AUTO /

CLOSE 1P-229B 1C03 B RHR PUMP cah AUTO /

STOP MO-1939 1C03 B HX INLET cah NORM /

OPEN MO-1941 1C03 B HEAT EXCH OUTLET (keylocked cah OPEN /

handswitch) OPEN MO-1940 1C03 B HEAT EXCH BYPASS cah AUTO /

OPEN SV-1972 1C03 INBD RHR SAMPLE ISOL cah AUTO /

CLOSE SV-1973 1C03 OUTBD SAMPLE ISOL cah AUTO /

CLOSE MO-1949A 1C03 B RHR HX SHELL OUTBD VENT cah NORM /

CLOSE MO-1949B 1C03 B RHR HX SHELL INBD VENT cah NORM /

CLOSE HS-1905B 1C03 MO-1905 GROUP 4 ISOL SEALED-IN cah RESET (pushbutton)

HS-1903C 1C03 ENABLE CONTAINMENT SPRAY VALVES cah OFF /

RESET HS-1903B 1C03 2/3 CORE COVERED/LPCI INIT cah NORMAL INTERLOCK OVERRIDE (keylocked handswitch)

OI 149 Attachment 6 Page 4 of 7 Rev. 2

OI 149A6 RHR SYSTEM CONTROL PANEL LINEUP Attachment 6 Control Panel Lineup - Page 3 of 5 Device Wvd./ Req'd. Pos.

Number Panel Description Discrep. Rstr. Init.

HS-1973A 1C03 OUTBD RHR SAMPLE SV-1973 ISOL cah NORMAL OVERRIDE (keylocked handswitch)

HS-1972A 1C03 INBD RHR SAMPLE SV-1972 ISOL cah NORMAL OVERRIDE (keylocked handswitch)

HS-2001C 1C03 ENABLE CONTAINMENT SPRAY VALVES cah OFF/

RESET HS-2001B 1C03 2/3 CORE COVERED/LPCI INIT cah NORMAL INTERLOCK OVERRIDE (keylocked handswitch)

HS-2052A 1C03 OUTBD RHR SAMPLE SV-2052 ISOL cah NORMAL OVERRIDE (keylocked handswitch)

HS-2051A 1C03 INBD RHR SAMPLE SV-2051 ISOL cah NORMAL OVERRIDE (keylocked handswitch)

HS-2003B 1C03 MO-2003 GROUP 4 ISOL SEALED-IN cah RESET (pushbutton)

MO-1932 1C03 OUTBD TORUS CLG/SPRAY (keylocked cah CLOSE /

handswitch) CLOSE MO-1934 1C03 TORUS COOLING/TEST cah AUTO /

CLOSE MO-1933 1C03 TORUS SPRAY cah AUTO /

CLOSE MO-1903 1C03 OUTBD DRYWELL SPRAY cah AUTO /

CLOSE MO-1902 1C03 INBD DRYWELL SPRAY (keylocked cah CLOSE /

handswitch) CLOSE MO-1937 1C03 INBD RHR DRAIN TO RW ISOL cah AUTO/

CLOSE MO-1936 1C03 OUTBD RHR DRAIN TO RW THRTL ISOL cah AUTO /

CLOSE HS-1937A 1C03 SHUTDOWN COOLING 135# INTERLOCK cah TORUS ENABLE CLG MO-2010 1C03 RHR CROSSTIE (keylocked handswitch) cah OPEN /

OPEN V-19-48 1C03 RHR MANUAL CROSSTIE ISOLATION cah OPEN HS-1904 1C03 OUTBD INJECT cah AUTO /

OPEN OI 149 Attachment 6 Page 5 of 7 Rev. 2

OI 149A6 RHR SYSTEM CONTROL PANEL LINEUP Attachment 6 Control Panel Lineup - Page 4 of 5 Device Wvd./ Req'd.

Number Panel Description Discrep. Rstr. Init. Pos.

HS-1904C 1C03 MO-1904 LPCI OPEN INTLK OVERRIDE cah NORMAL MO-1905 1C03 INBD INJECT ISOL cah AUTO /

CLOSE ZS-1907 1C03 MANUAL ISOLATION V-19-147 cah OPEN MO-1908 1C03 INBD SHUTDOWN CLG ISOL cah NORM /

CLOSE MO-1909 1C03 OUTBD SHUTDOWN CLG ISOL cah NORM /

CLOSE MO-2069 1C03 TORUS SUCTION (keylocked handswitch) cah OPEN /

OPEN MO-2012 1C03 A PUMP TORUS SUCTION (keylocked cah OPEN /

handswitch) OPEN MO-2011 1C03 A PUMP SHUTDOWN CLG SUCTION cah CLOSE/

CLOSE MO-2016 1C03 C PUMP SHUTDOWN CLG SUCTION cah CLOSE /

CLOSE MO-2015 1C03 C PUMP TORUS SUCTION (keylocked cah OPEN/

handswitch) OPEN 1P-229C 1C03 C RHR PUMP cah AUTO/

STOP MO-2009 1C03 MIN FLOW BYPASS cah AUTO/

CLOSE 1P-229A 1C03 A RHR PUMP cah AUTO/

STOP MO-2029 1C03 A HX INLET cah NORM/

OPEN MO-2031 1C03 A HEAT EXCH OUTLET (keylocked cah OPEN/

handswitch) OPEN MO-2030 1C03 A HEAT EXCH BYPASS cah AUTO/

OPEN SV-2051 1C03 INBD RHR SAMPLE ISOL cah AUTO/

CLOSE SV-2052 1C03 OUTBD RHR SAMPLE ISOL cah AUTO/

CLOSE MO-2044A 1C03 A RHR HX SHELL OUTBD VENT cah NORM/

CLOSE OI 149 Attachment 6 Page 6 of 7 Rev. 2

OI 149A6 RHR SYSTEM CONTROL PANEL LINEUP Attachment 6 Control Panel Lineup - Page 5 of 5 Device Wvd./ Req'd.

Number Panel Description Discrep. Rstr. Init. Pos.

MO-2044B 1C03 A RHR HX SHELL INBD VENT cah NORM /

CLOSE MO-2005 1C03 OUTBD TORUS CLG/SPRAY (keylocked cah CLOSE /

handswitch) CLOSE MO-2007 1C03 TORUS COOLING/TEST cah AUTO /

CLOSE MO-2006 1C03 TORUS SPRAY cah AUTO /

CLOSE MO-2001 1C03 OUTBD DRYWELL SPRAY cah AUTO /

CLOSE MO-2000 1C03 INBD DRYWELL SPRAY (keylocked cah CLOSE / 1*

handswitch) CLOSE MO-2004 1C03 OUTBD INJECT cah AUTO /

OPEN HS-2004C 1C03 MO-2004 LPCI OPEN INTLK OVERRIDE cah NORMAL MO-2003 1C03 INBD INJECT ISOL cah AUTO /

CLOSE ZS-2008 1C03 MANUAL ISOLATION V-20-81 cah OPEN ZS-1993 1C03 MANUAL SHUTDOWN CLG ISOLATION cah OPEN V-19-148 1*. MO-2000 indication was dual, NSPEO declutched and closed MO-2000 ~1/3 turn to get CLOSE light to stay lit and OPEN light to go out OI 149 Attachment 6 Page 7 of 7 Rev. 2

QF-1030-11 Rev. 7 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2009 NRC JPM SRO A-3 TITLE: Determine Risk And The Resultant Protected Systems Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM SRO-A-1

QF-1030-11 Rev. 7 JOB PERFORMANCE MEASURE (JPM)

JPM TITLE: DETERMINE RISK AND THE RESULTANT PROTECTED SYSTEMS JPM NUMBER: 2009 NRC JPM SRO A-3 REV. 0 TASK NUMBER(S) / 1.11 / SRO - Ensure the Conduct of Operations and Maintenance are in TASK TITLE(S): Compliance with Administrative Procedures K/A NUMBERS: 2.2.17 K/A VALUE: 3.8 Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY: RO SRO STA NSPEO SRO CERT APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 15 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:

Instructor Date Validated by:

Validation Instructor Date Reviewed by:

Plant Reviewer Date Approved by:

Training Supervisor Date Commitments: {C001} ACE 001729, Review recommendation 4 of OE 001501.

{C002} CA046394, Improvements needed for Operations Simulator JPMs.

Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File DAEC 2009 NRC JPM SRO A-3 Page 1 of 1

QF-1030-11 Rev. 7 2009 NRC JPM SRO A-3, Determine Risk and the Resultant Protected Systems, Rev. 0 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?
2. Has the JPM been reviewed and validated by SMEs?
3. Can the required conditions for the JPM be appropriately established in the simulator if required?
4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
6. Has the completion time been established based on validation data or incumbent experience?
7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
8. Is the Licensee level appropriate for the task being evaluated if required?
9. Is the K/A appropriate to the task and to the licensee level if required?
10. Is justification provided for tasks with K/A values less than 3.0?
11. Have the performance steps been identified and typed (Critical / Sequence

/ Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
13. Are all references identified, current, accurate, and available to the trainee?
14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
15. Are all critical steps clearly identified by procedural guidance? If licensing, EP or other groups were needed to determine correct actions, then the answer should be NO. {C001}
16. If the JPM is to be administered to an ILT student, has the required knowledge been taught to the individual prior to administering the JPM?

TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. {C001}

All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

RE-VALIDATION SIGNATURE JPMs must be re-validated prior to use. Verify the above Review Statements are YES or N/A. When it is determined that the JPM is still valid and can be performed as written, sign and date the form below.

Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date DAEC 2009 NRC JPM SRO A-3 Page 2 of 2

QF-1030-11 Rev. 7 2009 NRC JPM SRO A-3, Determine Risk and the Resultant Protected Systems, Rev. 0 SIMULATOR SET UP:

1. Ensure the ORAM-Sentinel program to be used by the examinee is in the All Systems Available state prior to the JPM. The preferred computer to use for this JPM is in the Simulator Shift Managers Office, next to the EP Phones.
2. NOTE: (Simulator Operator) Ensure the ORAM-Sentinel program used by the examinee is returned to the All Systems Available state when the JPM is concluded.

SIMULATOR MALFUNCTIONS:

TIME MALFUNCTION # MALFUNCTION ET DELAY F. SEV. RAMP I. SEV.

TITLE SIMULATOR OVERRIDES:

TIME OVERRIDE ID OVERRIDE ET DELAY VALUE RAMP DESCRIPTION SIMULATOR REMOTE FUNCTIONS:

TIME REMOTE REMOTE FUNCTION TITLE VALUE RAMP FUNCTION #

Required Materials: ORAM Sentinel computer program WPG-2 On-line Risk Management Program General

References:

WPG-2 On-line Risk Management Program Task Standards: Determines Risk Value Determines the recommended protected systems per WPG-2 DAEC 2009 NRC JPM SRO A-3 Page 3 of 3

QF-1030-11 Rev. 7 TURNOVER SHEET INITIAL CONDITIONS:

  • The plant is near full power.
  • B SBGT is tagged OOS for maintenance, LCO 3.6.4.3 Condition A has been entered, currently day 2 of 7.
  • A SBGT train is Protected (Guarded)
  • The Aux Operator reported from the Pump House that 1P099B, B ESW Pump motor oil bulls-eye is empty and there are several gallons of oil on the Pump House floor.
  • The Shift Manager has declared the B ESW pump inoperable and unavailable.

INITIATING CUES (IF APPLICABLE):

  • The Shift Manager has directed you to determine station risk and determine the protected systems, if any.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

DAEC 2009 NRC JPM SRO A-3 Page 4 of 4

QF-1030-11 Rev. 7 2009 NRC JPM SRO A-3, Determine Risk and the Resultant Protected Systems, Rev. 0 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

  • The plant is near full power.
  • B SBGT is tagged OOS for maintenance, LCO 3.6.4.3 Condition A has been entered, currently day 2 of 7.
  • A SBGT train is Protected (Guarded)
  • The Aux Operator reported from the Pump House that 1P099B, B ESW Pump motor oil bulls-eye is empty and there are several gallons of oil on the Pump House floor.
  • The Shift Manager has declared the B ESW pump inoperable and unavailable.

INITIATING CUES (IF APPLICABLE):

  • The Shift Manager has directed you to determine station risk and determine the protected systems, if any.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

DAEC 2009 NRC JPM SRO A-3 Page 5 of 5

QF-1030-11 Rev. 7 2009 NRC JPM SRO A-3, Determine Risk and the Resultant Protected Systems, Rev. 0 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Candidate runs a Risk Case using ORAM Sentinel.

Critical Y Standard: Marks B ESW pump as UNAVAILABLE, resultant risk is declared as YELLOW Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 WPG-2 is consulted to determine the recommended protected systems.

Critical Y Standard: Recommended protected systems are listed on Page 46 & 47 of 54 of WPG-2.

The list includes:

"A" ESW 1K3 (CB/SBGT Instrument Air Compressor)

"A" RWS 1VAC030A (Control Building A/C Unit A)

"A" DG 1A3, Startup Transformer "A" RHR loop "A" Core Spray "A" RHRSW HPCI "A" Chiller A SBGT (already given as protected in turnover)

Evaluator Note: The above are the minimum systems for step to be considered SAT. May protect extra systems based upon ORAM Sentinel. If SBGT is left off (due to being given),

this is not a failure of this step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: Once the candidate gives you the report on the risk status and the protected systems, the JPM is complete.

NOTE: (Simulator Operator) Ensure the ORAM-Sentinel program used by the examinee is returned to the All Systems Available state.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002}

Stop Time:

DAEC 2009 NRC JPM SRO A-3 Page 6 of 6

QF-1030-11 Rev. 7 2009 NRC JPM SRO A-3, Determine Risk and the Resultant Protected Systems, Rev. 0 Examinee: Evaluator:

RO SRO STA NSPEO SRO CERT Date:

ILT RO ILT SRO PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

DAEC 2009 NRC JPM SRO A-3 Page 7 of 7

QF-1030-11 Rev. 5 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2009 NRC SRO JPM A-4 TITLE: SRO - ERO Plant Access Radiation Briefing Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File 2009 NRC JPM SRO A-4 Page 1 of 13

QF-1030-11 Rev. 5 JOB PERFORMANCE MEASURE (JPM)

JPM TITLE: Dispatch An Operator Into The Plant When The TSC/OSC Are Not Activate JPM NUMBER: 2009 NRC JPM SRO A-4 REV. 0 TASK NUMBER(S) / 3.01 / Implement Emergency Plan TASK TITLE(S):

K/A NUMBERS: 2.3.14 K/A VALUE: 3.8 Justification (FOR K/A VALUES <3.0): N/A TASK APPLICABILITY: RO SRO STA NSPEO SRO CERT APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 20 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:

Instructor Date Validated by:

Validation Instructor Date Reviewed by:

Plant Reviewer Date Approved by:

Training Supervisor Date Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File 2009 NRC JPM SRO A-4 Page 2 of 13

QF-1030-11 Rev. 5 2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated, Rev. 5 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?
2. Has the JPM been reviewed and validated by SMEs?
3. Can the required conditions for the JPM be appropriately established in the simulator if required?
4. Does the performance steps accurately reflect trainees actions in accordance with plant procedures?
5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
6. Has the completion time been established based on validation data or incumbent experience?
7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
8. Is the Licensee level appropriate for the task being evaluated if required?
9. Is the K/A appropriate to the task and to the licensee level if required?
10. Is justification provided for tasks with K/A values less than 3.0?
11. Have the performance steps been identified and typed (Critical /

Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
13. Are all references identified, current, accurate, and available to the trainee?
14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
15. Are all critical steps clearly identified by procedural guidance? If licensing, EP or other groups were needed to determine correct actions, then the answer should be NO. (ACE 1729)
16. If the JPM is to be administered for initial qualification, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. (ACE 1729)

All questions/statements must be answered YES or the JPM is not valid for use. If all questions/statements are answered YES then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.

Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date 2009 NRC JPM SRO A-4 Page 3 of 13

QF-1030-11 Rev. 5 2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated, Rev. 5 SIMULATOR SET UP:

Simulator Setup Instructions:

1. Have a markup of SEP 305 ready. Markup Attachment 1 thru Step 7(b).

SIMULATOR MALFUNCTIONS:

None SIMULATOR OVERRIDES:

None SIMULATOR REMOTE FUNCTIONS:

None Required Materials: EPIP 2.5, Control Room Emergency Response Operation SEP 305, ECCS Suction Strainer Blockage Provide Attachment A, In-Plant Radiation Levels.

Provide a copy of SEP 305 Attachment 1 marked up thru Step 7(b).

Marked up SEP 305 General

References:

EPIP 2.5, Rev. 17 SEP 305, Rev. 3 Task Standards: Brief the operator on the task to be performed.

Brief the operator on precautions and operational parameters IAW EPIP 2.5 Attachment 2.

2009 NRC JPM SRO A-4 Page 4 of 13

QF-1030-11 Rev. 5 TURNOVER SHEET INITIAL CONDITIONS:

  • You are on weekend duty as the Shift Manager.
  • An Alert emergency FA-1 has been declared due to a Loss of Coolant accident.
  • The Evacuation alarm has been sounded and a Plant Assembly has been initiated.
  • RPV level is being maintained at approximately 20 inches with both Core Spray pumps, aligned to the CSTs, and the A Loop of RHR in the LPCI mode.
  • There is no indication of fuel damage at this time, but radiation levels are rising in the Reactor Building. Refuel Floor ARM readings have doubled and some readings on the Reactor Bldg.

3rd floor have risen by a factor of 10. At present, there are no EOP-3 entry conditions.

Control Room Operators are continuing to monitor in-plant and effluent radiation levels.

See Attachment A of this JPM.

  • There are indications of RHR suction strainer blockage on the B Loop of RHR. Operators are performing ECCS Suction Strainer Blockage SEP 305 Attachment 1. The Radwaste operator confirmed that V-19-9 was closed. Operators have completed to Step 7(b) and are prepared to back flush around the D RHR pump as soon as an operator can be dispatched.
  • The TSC and OSC are not yet operational.
  • HPs have performed a survey of the NWCR and determined that general area radiation levels are 20 mr/hr.
  • The Operator that is being sent into the plant has been briefed on SEP 305 performance.
  • I will role-play the operator being dispatched.

INITIATING CUES (IF APPLICABLE):

  • Perform the Required Radiation Briefing for dispatching the operator to the NWCR under the given plant conditions.

2009 NRC JPM SRO A-4 Page 5 of 13

2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated.

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

  • You are on weekend duty as the Shift Manager.
  • An Alert emergency FA-1 has been declared due to a Loss of Coolant accident.
  • The Evacuation alarm has been sounded and a Plant Assembly has been initiated.
  • RPV level is being maintained at approximately 20 inches with both Core Spray pumps, aligned to the CSTs, and the A Loop of RHR in the LPCI mode.
  • There is no indication of fuel damage at this time, but radiation levels are rising in the Reactor Building. Refuel Floor ARM readings have doubled and some readings on the Reactor Bldg.

3rd floor have risen by a factor of 10. At present, there are no EOP-3 entry conditions.

Control Room Operators are continuing to monitor in-plant and effluent radiation levels.

See Attachment A of this JPM.

  • There are indications of RHR suction strainer blockage on the B Loop of RHR. Operators are performing ECCS Suction Strainer Blockage SEP 305 Attachment 1. The Radwaste operator confirmed that V-19-9 was closed. Operators have completed to Step 7(b) and are prepared to back flush around the D RHR pump as soon as an operator can be dispatched.
  • The TSC and OSC are not yet operational.
  • HPs have performed a survey of the NWCR and determined that general area radiation levels are 20 mr/hr.
  • The Operator that is being sent into the plant has been briefed on SEP 305 performance.
  • I will role-play the operator being dispatched.

INITIATING CUES (IF APPLICABLE):

  • Perform the Required Radiation Briefing for dispatching the operator to the NWCR under the given plant conditions.

2009 NRC JPM SRO A-4 Page 6 of 13

2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated.

JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 MAY request HPs be present for brief / give brief Critical N Standard: N/A Evaluator Cue: If HP requested to be present/brief the operator, HP tech is busy and is unable to support the briefing.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 Determines that the Access Briefing has to be IAW EPIP 2.5, Control Room Critical N Emergency Response Operation, Section 3.8, step (2) and Attachment 2, In-Plant Operator Briefing Form.

Standard: References EPIP 2.5, Section 3.8, step (2), and Attachment 2, In-Plant Operator Briefing Form.

Performance: SATISFACTORY UNSATISFACTORY Comments:

2009 NRC JPM SRO A-4 Page 7 of 13

2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated.

Performance Step: 3 Per EPIP 2.5, Section 3.8 TSC and OSC not operational. If suspected Critical N abnormal radiological conditions exist, dispatch of Operations personnel will be at the discretion of the OSM/CRS.

Standard: Determines that the OSM/CRS has the authority to dispatch operators.

(Consider this step completed if the operator is dispatched.)

Evaluator Note: Abnormal radiological conditions exist per handout Attachment A and per an SEP 305 Caution Performance: SATISFACTORY UNSATISFACTORY Comments:

The below are two sample briefings that two SRO validators wrote these are only samples, and it will be up to the individual evaluator to determine effectiveness of the briefing:

First Validator:

Entry path is from Access Control to NW Corner Room 5-10 minutes expected stay time based upon job length Reactor Building 1st Floor Rads Normal Reactor Building 2nd/3rd Floor Rads Elevated Possible change in NWCR dose rates, take a meter with you Return path is via Reactor Building North to Access Control Utilize Low Dose Areas Normal Exposure Limits for EDs Pay attention for ED alarms General Area Dose Rates are 20 mr/hr Approximately 5 mr for the job Keep HPs and Control Room Operators informed of status Monitor your rad levels Second SRO Validators Brief:

Radiological Conditions:

Rising seen 1 mr change in last 15 minutes on North CRD area. So well below max normal but conditions are changing Monitor dosimetry frequently every 5-10 minutes and exit area prior to exceeding dose rate or dose limit.

Stay Times:

No limits on stay time but as stated, conditions are changing, exit prior to ED exceeding dose rate or dose limits Access Route:

Normal access and egress into plant. Notify access control HP where you are going and what you will be doing if HP is not at access, notify when exiting Precautions:

When manipulating valves, dose rates may change, monitor dosimetry Increased Exposure Limits - NO Estimate of exposure:

30 minutes times 20 mr/hr is 10 mrem. Ensure pick up high range equipment at access.

2009 NRC JPM SRO A-4 Page 8 of 13

2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated.

Performance Step: 4 Operators should be briefed on associated precautions and pertinent Critical Y operational information utilizing Attachment 2, In-Plant Operator Briefing Form, to include:

1) Expected radiological conditions
2) Stay times
3) Access routes
4) Associated precautions
5) Increased exposure limits
6) Estimates of total exposure Standard: Briefing covers each of the following:

Expected radiological conditions

  • e.g.: High Rads in upper elevations of RB
  • e.g.: Rad levels may change when backflow has been initiated Stay times
  • e.g.: Sets a time limit for this operation
  • e.g.: Exit if/when ED alarms Access routes
  • e.g.: Enter the RB through Access Control
  • e.g.: Dont go out the back door
  • e.g.: Return/exit through Access Control Associated precautions
  • e.g.: Dont go to upper elevations of RB
  • e.g.: Take a Dose Rate instrument
  • e.g.: Monitor ED Increased exposure limits
  • e.g.: Use an Emergency ED (with higher limits) [May not authorize Emergency ED]
  • e.g.: Sets an exposure limit Estimates of total exposure
  • e.g.: Determine exposure based on the estimated time required for the job and dose rates in the area.
  • An area dose rate of 20 mR/hr would give 1mr per 5 minutes and would be consistent with the expected exposure Evaluator Cue: If asked about area dose rates inform the candidate that the HP has determined that general area rad levels in the area are 20 mR/hr.

Performance: SATISFACTORY UNSATISFACTORY Comments:

2009 NRC JPM SRO A-4 Page 9 of 13

2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated.

Performance Step: 5 Describe protective clothing, dosimetry, and respiratory equipment required for Critical N the job.

Standard: Determine protective clothing, dosimeter, respiratory equipment and communicate that to the NSPEO.

Evaluator Note: The SRO validators required no protective clothing.

Evaluator Note: Candidate may direct the operator to stop at access to get the appropriate equipment or assign an HP to assist in determining the required protective equipment. Sending or assigning the HP to assist satisfies the satisfactory performance of this step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 6 Directs the NSPEO to obtain a high range survey instrument and take it with Critical Y him on the job.

Standard: Directs the NSPEO to obtain a high range survey instrument and take it with him on the job.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 Health Physics Technician informed of the operator actions and instructs him to Critical Y provide assistance as necessary.

Standard: HP informed of the operator actions and to provide assistance.

Evaluator Cue: Role play as the HP and inform the OSM/CRS that you are standing by at access ready to support the operator.

Performance: SATISFACTORY UNSATISFACTORY Comments:

2009 NRC JPM SRO A-4 Page 10 of 13

2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated.

Performance Step: 8 Personnel closely monitor in-plant and effluent radiation levels Critical N (trends/changes).

Standard: May verify that someone is monitoring in-plant and effluent radiation levels.

(Given in Initiating Cue)

Evaluator Cue: If asked, someone is still tracking plant radiation readings.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 9 All personnel dispatched should exit through Access Control.

Critical Y Standard: Direct the operator to enter and exit the plant through access control.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 10 Dispatch the operator into the plant.

Critical Y Standard: Operator dispatched into the plant.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the candidate is completed with the brief and the NSPEO is dispatched to access control.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. (CA 46394)

Stop Time:

2009 NRC JPM SRO A-4 Page 11 of 13

2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated.

Examinee: Evaluator:

RO SRO STA NSPEO SRO CERT Date:

PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO: YES:

COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

2009 NRC JPM SRO A-4 Page 12 of 13

QF-1030-11 Rev. 5 2.4.38-02, Dispatch an Operator into the Plant when the TSC/OSC are not Activated, Rev. 5 ATTACHMENT A DOSE PROJECTION & ARM DATA SHEET MONITOR # MONITOR LOCATION UNITS ALARM MAX NORM MAX TIME TIME TIME TIME LEVEL SAFE :00 :15 :30 :45 RT-9180 RB 747' WASTE COLL. mR/hr 250.0 1 1 RT-9166 RB 716' SW, RW PUMP ROOM mR/hr 50.0 3 3

  • RT-9178 RB 855' SPENT FUEL STORAGE AREA mR/hr 19.0 100 1000 3 6
  • RT-9163 REFUEL FLOOR NORTH mR/hr 10.0 10 100 1.5 3
  • RT-9173 RB 786' RESIN HANDLING mR/hr 80.0 100 1000 50 60
  • RT-9177 RB 786' CU PH. SEPARATOR mR/hr 100.0 20 200 10 15
  • RT-9155 RB 812' JUNGLE ROOM, C/U DEMIN mR/hr 2500.0 60 600 25 25 AREA
  • RT-9171 RB 812' VENTILATION EQUIP. mR/hr 2.2 60 600 2 4
  • RT-9153 Rx B 855 NEW FUEL STORAGE AREA mR/hr 10.0 10 100 2 7
  • RT-9168 RB 757' CRD NORTH mR/hr 10.0 10 100 3 4 RT-9175 RB 833' COND. PH. SEPARATOR TANK mR/hr 150.0 3 25

QF-1030-11 Rev. 7 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE 2009 NRC SRO JPM A-5 TITLE: Evaluate PARs When Conditions Change Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File NRC JPM SRO A-5 REV 7-8-09.DOC Page 1 of 10

QF-1030-11 Rev. 7 JOB PERFORMANCE MEASURE (JPM)

JPM TITLE: Evaluate PARs When Conditions Change JPM NUMBER: SRO NRC JPM A-5 REV. 0 TASK NUMBER(S) / 3.01 / Implement the Emergency Plan TASK TITLE(S):

K/A NUMBERS: 2.4.44 K/A VALUE: SRO 4.4 Justification (FOR K/A N/A VALUES <3.0):

TASK APPLICABILITY: RO SRO STA NSPEO SRO CERT APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other: X Lab:

Time for Completion: 20 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:

Instructor Date Validated by:

Validation Instructor Date Reviewed by:

Plant Reviewer Date Approved by:

Training Supervisor Date Commitments: {C001} ACE 001729, Review recommendation 4 of OE 001501.

{C002} CA046394, Improvements needed for Operations Simulator JPMs.

Retention: Life of policy + 10yrs. Disposition: Reviewer and Approver Retain in: Training Program File NRC JPM SRO A-5 REV 7-8-09.DOC Page 2 of 10

QF-1030-11 Rev. 7 SRO NRC JPM A-5, Determine Change in PARs, Rev. 0 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1. Are all items on the signature page filled in correctly?
2. Has the JPM been reviewed and validated by SMEs?
3. Can the required conditions for the JPM be appropriately established in the simulator if required?
4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
6. Has the completion time been established based on validation data or incumbent experience?
7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
8. Is the Licensee level appropriate for the task being evaluated if required?
9. Is the K/A appropriate to the task and to the licensee level if required?
10. Is justification provided for tasks with K/A values less than 3.0?
11. Have the performance steps been identified and typed (Critical / Sequence

/ Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
13. Are all references identified, current, accurate, and available to the trainee?
14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
15. Are all critical steps clearly identified by procedural guidance? If licensing, EP or other groups were needed to determine correct actions, then the answer should be NO. {C001}
16. If the JPM is to be administered to an ILT student, has the required knowledge been taught to the individual prior to administering the JPM?

TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge. {C001}

All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

RE-VALIDATION SIGNATURE JPMs must be re-validated prior to use. Verify the above Review Statements are YES or N/A. When it is determined that the JPM is still valid and can be performed as written, sign and date the form below.

Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date Re-Validation Personnel Date NRC JPM SRO A-5 REV 7-8-09.DOC Page 3 of 10

QF-1030-11 Rev. 7 SRO NRC JPM A-5, Determine Change in PARs, Rev. 0 SIMULATOR SET UP:

Simulator Setup Instructions:

1. No setup required.

SIMULATOR MALFUNCTIONS:

TIME MALFUNCTION # MALFUNCTION ET DELAY F. SEV. RAMP I. SEV.

TITLE SIMULATOR OVERRIDES:

TIME OVERRIDE ID OVERRIDE ET DELAY VALUE RAMP DESCRIPTION SIMULATOR REMOTE FUNCTIONS:

TIME REMOTE REMOTE FUNCTION TITLE VALUE RAMP FUNCTION #

Required Materials: EPIP 3.3 EPIP Form NOTE 5 General

References:

EPIP chapter 1.1 EPIP chapter 1.2 EPIP chapter 2.5 EPIP chapter 3.3 EPIP Form NOTE 5 EPIP Form PAR-01 EPIP Form PAR-02 Task Standards: PAR Upgrade Determined EAL NOTE 5 filled out corrected to notify the state NRC JPM SRO A-5 REV 7-8-09.DOC Page 4 of 10

QF-1030-11 Rev. 7 SRO NRC JPM A-5, Determine Change in PARs, Rev. 0 TURNOVER SHEET INITIAL CONDITIONS:

  • Its Saturday evening, and a severe accident has occurred at DAEC.
  • The ERO cannot respond to the plant due to a major ice storm that has ALL Roads in Eastern Iowa closed due to 100% ice covered conditions and multiple accidents.
  • RPV level was at -110 inches for a considerable time, it is now at 25 inches and stable.
  • Emergency Depressurization has been performed.
  • The STA has completed a Fuel Damage Assessment worksheet, which shows that approximately 25% of fuel damage has occurred.
  • The TSC is not staffed at this time.
  • An EAL declaration of GENERAL EMERGENCY has been made.
  • State, Local, and National Governmental notifications have been made for this GENERAL EMERGENCY (The EAL form that was used for notifications is provided.)

Since the GENERAL EMERGENCY has been declared and notified, the following has occurred:

  • The Shift Chemist has just run a Midas Dose Assessment, and has reported the following results:

o The dose assessment predicts the following readings for the area outside the Site Boundary:

3/4 At 3 miles, the projected TEDE Dose will be 2.5R, and the projected CDE Dose will be 4.8R.

3/4 At 5 miles, the projected TEDE Dose will be 0.9R and the projected CDE Dose will be 2R.

  • The current wind speed is 15 mph, from 185 degrees
  • The Reactor Building KAMAN HIGH alarm is activated. A filtered release is in progress. It is unknown how long the release will last.
  • The state has just arrived at the EOF, and has NOT determined the Protective Action Requirements.

The state is requesting a new EPIP FORM NOTE 5 be filled out prior to the state setting Protective Actions.

INITIATING CUES:

  • Determine if any changes need to be made to the Protective Action Recommendations based upon the new information.
  • Fill out a new EPIP FORM NOTE 5 for the state.

This task IS time critical.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC JPM SRO A-5 REV 7-8-09.DOC Page 5 of 10

QF-1030-11 Rev. 7 SRO NRC JPM A-5, Determine Change in PARs, Rev. 0 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

  • Its Saturday evening, and a severe accident has occurred at DAEC.
  • The ERO cannot respond to the plant due to a major ice storm that has ALL Roads in Eastern Iowa closed due to 100% ice covered conditions and multiple accidents.
  • RPV level was at -110 inches for a considerable time, it is now at 25 inches and stable.
  • Emergency Depressurization has been performed.
  • The STA has completed a Fuel Damage Assessment worksheet, which shows that approximately 25% of fuel damage has occurred.
  • The TSC is not staffed at this time.
  • An EAL declaration of GENERAL EMERGENCY has been made.
  • State, Local, and National Governmental notifications have been made for this GENERAL EMERGENCY (The EAL form that was used for notifications is provided.)

Since the GENERAL EMERGENCY has been declared and notified, the following has occurred:

  • The Shift Chemist has just run a Midas Dose Assessment, and has reported the following results:

o The dose assessment predicts the following readings for the area outside the Site Boundary:

3/4 At 3 miles, the projected TEDE Dose will be 2.5R, and the projected CDE Dose will be 4.8R.

3/4 At 5 miles, the projected TEDE Dose will be 0.9R and the projected CDE Dose will be 2R.

  • The current wind speed is 15 mph, from 185 degrees
  • The Reactor Building KAMAN HIGH alarm is activated. A filtered release is in progress. It is unknown how long the release will last.
  • The state has just arrived at the EOF, and has NOT determined the Protective Action Requirements.

The state is requesting a new EPIP FORM NOTE 5 be filled out prior to the state setting Protective Actions.

INITIATING CUES:

  • Determine if any changes need to be made to the Protective Action Recommendations based upon the new information.
  • Fill out a new EPIP FORM NOTE 5 for the state.

This task IS time critical.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC JPM SRO A-5 REV 7-8-09.DOC Page 6 of 10

QF-1030-11 Rev. 7 SRO NRC JPM A-5, Determine Change in PARs, Rev. 0 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

EVALUATOR NOTE: The candidate can use either EPIP Form NOTE-5, DAEC Emergency Action Level Notification Form, or the EPIP Form PAR-02, Protective Action Decision Making Flowchart to determine the Recommended Actions.

Performance Step: 1 Reviews table PAR-02 Critical N Standard: Reviews table PAR-02 Evaluator Cue: Table PAR-02 is an EPIP Form, and only available through the Procedure Revision Control Computer Procedures application. If the candidate asks for these tables (PAR-01 and PAR-02), they are attached to the end of this JPM.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 Based on Midas dose assessment conditions, determines that the Protective Critical Y Action Recommendations should be Upgraded from the Default Recommendations.

Standard: Determines the need to upgrade the Protective Action Recommendations from the default Protective Action Recommendations.

Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC JPM SRO A-5 REV 7-8-09.DOC Page 7 of 10

QF-1030-11 Rev. 7 SRO NRC JPM A-5, Determine Change in PARs, Rev. 0 Performance Step: 3 Recommend placing dairy animals within the entire EPZ on stored feed and Critical N covered water Standard: Recommendation given to place dairy animals within the entire EPZ on stored feed and covered water Evaluator Note: The candidate will only advise this recommendation if they look at EPIP Form PAR-02. However, this is the State of Iowas decision, it does not constitute failure if not recommended, but should be noted as a competency.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 Determines that the Protective Action Recommendations are to:

Critical Y 1. Evacuate 2-mile radius around the plant

2. Evacuate 5 mile down wind sub-areas,
3. Shelter (or advise to go indoors) downwind subareas from 5 miles to EPZ edge.

Standard: Determines that the PAR block E should be recommended to the state.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 Recommend that the state initially shelter rather than evacuate the population Critical N until conditions improve, based upon given weather conditions.

Standard: RECOMMEND that the state initially shelter 2-mile radius and 5 mile down wind sub-areas, based on weather conditions.

Evaluator Note: The candidate should recommend shelter vice evacuation. However, this is the State of Iowas decision, it does not constitute failure if not recommended, but should be noted as a competency.

Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC JPM SRO A-5 REV 7-8-09.DOC Page 8 of 10

QF-1030-11 Rev. 7 SRO NRC JPM A-5, Determine Change in PARs, Rev. 0 Performance Step: 6 Activate the Prompt Alert and Notification System Critical Y Standard: EPIP Form Note 5 filled out as follows:

The following blocks of the EAL Notification Form (NOTE 5) are CRITICAL (step failure if filled out with wrong information):

1. Status - DRILL
3. Classification - General Emergency
4. PAR CHANGE ONLY is checked
5. Is Occuring is checked
9. Wind Speed is 15
10. Direction is 185
11. PAR Determination Time and Date are filled in BLOCK E is checked Evaluator Note: The other blocks of the EAL Notification form would be NOT CRITICAL.

These are the critical blocks for DEP PI evaluations.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the candidate completes the NOTE 5 form, the JPM is complete.

Stop Time:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002}

NRC JPM SRO A-5 REV 7-8-09.DOC Page 9 of 10

QF-1030-11 Rev. 7 SRO NRC JPM A-5, Determine Change in PARs, Rev. 0 Examinee: Evaluator:

RO SRO STA NSPEO SRO CERT Date:

ILT RO ILT SRO PERFORMANCE RESULTS: SAT: UNSAT:

Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATORS SIGNATURE:

NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC JPM SRO A-5 REV 7-8-09.DOC Page 10 of 10

PROTECTIVE ACTION DECISION MAKING RECOMMENDATIONS General Emergency (From EPIP 3.3)

[D] Default, or Dose [E] Dose projections 1 [F] Dose projections 1 projections 1 REM REM TEDE or 5 REM REM TEDE or 5 REM TEDE or 5 REM CDE CDE @ 2-5 miles from site CDE @ 5-10 miles

@ 0-2 miles from site boundary. from site boundary.

boundary.

Evacuate, (or shelter if Evacuate, (or shelter if release Evacuate, (or shelter if release release duration is 1- duration is 1-hour or less), within duration is 1-hour or less), within hour or less), within a 2 a 2 mile radius and to 5 miles in a 2 mile radius, evacuate, (or mile radius and to 5 the downwind subareas, and shelter if release duration is 1-miles in the downwind shelter downwind subareas from hour or less), from 2 miles to subareas. 5 miles to EPZ edge. EPZ edge in downwind subareas, and shelter as appropriate beyond EPZ edge.

AND AND AND Activate the Prompt Alert Activate the Prompt Alert and Activate the Prompt Alert and and Notification System. Notification System. Notification System.

PAR-01 Rev. 2

PROTECTIVE ACTION DECISION MAKING FLOWCHART Protective actions in the event of severe core damage or loss of control of facility.

Actual or projected severe No core damage a NOTES or loss of control of facility.

a severe core damage is indicated by:

(1) Fuel damage assessment (PASAP 7.2) Yes determines at least 5% fuel clad damage (2) Valid drywell rad monitor reading above 7E +

2R/hr Activate the Prompt Alert and Notification System (3) Valid torus rad monitor reading above 3E + place lactating dairy animals within the entire EPZ 1R/hr on stored feed and protected water (4) Coolant activity above 300µCi/gm DOSE AND EQUIVALENT I-131 Evacuate a 2 mile radius and 5 miles downwind (5) RPV Level remains below -25 inches unless conditions make evacuation dangerous and advise remainder of plume EPZ to go indoors to b monitor EAS broadcast.

Distances are approximate - actual distances (See notes b, c, d, e, f) will be determined by the size of the preplanned sub-areas, which are based on geopolitical boundaries.

c If there are very dangerous travel conditions, initially shelter rather than evacuate the Continue assessment population until conditions improve. based on all available d

Transit-dependent persons should be advised plant and field to remain indoors until transportation resources monitoring information arrive, if possible.

e Shelter may be the appropriate action for controlled releases of radioactive material from the containment if there is assurance that the Modify protective release is short term (puff release) and the area actions as necessary.

near the plant cannot be evacuated before the Locate and evacuate plume arrives. hot spots. Do not f Consider EPA PAGs (Table G-1) in modifying relax protective actions initial protective actions. until the source of the (Located on page 2 of 2) threat is clearly under control.

Source: U.S.N.R.C. RTM-96/NUREG/BR-0150 Table G-1. Early phase Protective Action Guides (PAGs)

PAG (projected Protective action Comments dose)

Evacuation (or for some situations, sheltering)a should Evacuation (or sheltering)a 1-5 remb normally be initiated at 1 rem.

Administration of stable 25 rem thyroid Requires approval of State medical officials.

iodine a

Sheltering may be the preferred protective action when it will provide protection equal to or greater than evacuation, based on consideration of factors such as source term characteristics, and temporal or other site-specific conditions. For further guidance, see EPA 400-92-001, Sect. 2.3.1.

b The sum of the effective dose equivalent (EDE) resulting from exposure to external sources and the committed effective dose equivalent (CEDE) incurred from all significant inhalation pathways during the early phase. Committed dose equivalents to the thyroid and to the skin may be 5 and 50 times larger, respectively.

c Committed dose equivalent (CDE) to the thyroid from radioiodine.

Source: Adapted from EPA 400-R-92-001, p. 2-6 PAR-02 Rev. 0

DDA D AE A EEC CE C EEM ME M EERRG R GE G EN E NNCCY C YA Y AACCT C TIIIO T ON O NL N LE L EV E VE VEELLN L NO N OT O TIIIF T FIIIC F CA C AT A TIIIO T ON O NF N FFO OORRM R M M

MESSAGE 1. STATUS 2. FACILITY IN COMMAND & 3. ACCIDENT CLASSIFICATION INITIAL CONTROL INITIATED [A] ACTUAL [A] UNUSUAL EVENT ROLL CALL [A] Control Room..2222 [B] ALERT Benton County Time: 1900 [B] DRILL (or from [B] TSC...3333 [C] SITE AREA EMERGENCY Linn County [D] GENERAL EMERGENCY SIMULATOR) [C] EOF..4444 Iowa HSEMD [E] RECOVERY

[D] Simulator..1111 Date: _Today_ [F] CANCELLATION/TERMINATION (If this notification is for a PAR change ONLY, write N/A for information in Block 4.)

4. PAR CHANGE ONLY EAL CLASSIFIED @ TIME: 1845 DATE: Today (For EAL CLASSIFIED, fill in blank below AND circle appropriate letter or number applicable under Category, Classification and Sequence. For EALs with multiple initiating conditions, specify in Block 12 which initiating condition is applicable.)

EAL F G 1 . 0 Category Classification Sequence #

R F H S E C U A S G 1 2 3 4 5 6 7 8 . 0 1 2 3 4 5 6 7 8 9

5. ABNORMAL RELEASE IN PROGRESS DUE TO THIS EVENT? (e.g. KAMAN Hi Alarm or field team reports)

Has Not Occurred (Proceed To Block 9) Has Occurred, Is Now Terminated (Proceed To Block 6) Is Occurring (Proceed To Block 6)

6. AIRBORNE RELEASE TO ENVIRONMENT 7. TYPE OF RELEASE (mark all that apply) 8. PROJECTED DURATION OF RELEASE:

[A] BELOW FEDERAL LIMITS [A] RADIOACTIVE AIRBORNE (FILTERED) [A] UNKNOWN (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> default)

(No KAMAN Hi-Hi alarm)

[B] RADIOACTIVE AIRBORNE (UNFILTERED)

[B] AT, OR ABOVE, FEDERAL LIMITS [B] 1 HOUR OR LESS (KAMAN Hi-Hi alarm) [C] RADIOACTIVE LIQUID

[C] RELEASE DURATION ____ hour(s)

9. WIND SPEED: ___18____ MILES/HR (50m value preferred) 10. WIND DIRECTION : FROM __170__ DEGREES (50m value preferred)
11. UTILITY PROTECTIVE ACTION RECOMMENDATIONS (If this notification is for a PAR change ONLY, note time & date. Otherwise write N//A in TIME and DATE in Block 11.)

PAR DETERMINATION @ TIME: __ N/A___ DATE:__ N/A___

Unusual Event Alert Site Area Emergency

[A] No actions recommended [B] No actions recommended [C] Activate the Prompt Alert and Notification System.

General Emergency (From EPIP 3.3)

[D] Default, or Dose projections 1 REM [E] Dose projections 1 REM TEDE or [F] Dose projections 1 REM TEDE or TEDE or 5 REM CDE @ 0-2 miles from 5 REM CDE @ 2-5 miles from site 5 REM CDE @ 5-10 miles from site site boundary. boundary. boundary.

Evacuate, (or shelter if release duration is Evacuate, (or shelter if release duration is 1- Evacuate, (or shelter if release duration is 1-hour 1-hour or less), within a 2 mile radius and to hour or less), within a 2 mile radius and to 5 or less), within a 2 mile radius, evacuate, (or 5 miles in the downwind subareas. miles in the downwind subareas, and shelter shelter if release duration is 1-hour or less), from 2 AND downwind subareas from 5 miles to EPZ edge. miles to EPZ edge in downwind subareas, and Activate the Prompt Alert and Notification AND shelter as appropriate beyond EPZ edge.

System. Activate the Prompt Alert and Notification AND System. Activate the Prompt Alert and Notification System.

12. ADDITIONAL INFORMATION : RPV level below -25 inches Initial evaluations show 25% fuel damage The C MSL is not isolated
13. APPROVED BY: _____Shift OSM_____________ (DATE) Today (TIME) ____1850____

(OSM, EC, or ER&RD)

MESSAGE TRANSMITTED BY: FINAL ROLL CALL (Agency Reps INITIALS)

Name: ___ Bill Jones, ____ Time: ___1902___ Benton: _BTS Linn: _STW Iowa HSEMD: _ WTC_

14. STATE PROTECTIVE ACTIONS 0-2 m 2-5 m 5-10 m 10-EPZ Shelter Subareas (circle appropriate subareas) 1 2, 3, 4, 5, 6, 7, 8 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 19, 20, 21, 22 23,24 Evacuate Subareas (circle appropriate subareas 1 2, 3, 4, 5, 6, 7, 8 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 19, 20, 21, 22 23,24 Fax page 1 of this form to the State & Counties immediately after Final Roll Call.

NOTE-05 Page 1 of 2 Rev. 12

INSTRUCTIONS FOR USE Items 1, 3, 4, 5, 9, 10 & 11 MUST be accurate- The accuracy of these items will count towards our DEP Performance Indicator. If any of these items are in error, the Notification is considered inaccurate.

1. STATUS - Mark the letter corresponding to the appropriate status description. Unless an ACTUAL event is taking place, ALL Drills, Exercises, Table Top Drills and LORT notifications will be marked as DRILL.
2. FACILITY IN COMMAND & CONTROL - Mark letter corresponding to the facility in command & control. Phone numbers listed are Microwave numbers for the facility.
3. ACCIDENT CLASSIFICATION - Mark the letter corresponding to the latest classification issued by the ERO facility.
4. EAL CLASSIFIED - Fill in the time and date at which this new accident classification was determined. If this notification is for a PAR change ONLY, write N/A for information in Block 4.

EAL - Fill in and circle the current On-Site Emergency Action Level (EAL) code number.

5. ABNORMAL RELEASE DUE TO THIS EVENT? -

If KAMAN values have increased to a KAMAN high alarm, an abnormal release has occurred.

Mark if a release:

HAS NOT OCCURRED, if no KAMAN high alarm.

HAS OCCURRED, IS NOW TERMINATED, if a KAMAN high alarm has been received as a result of the event, but the release is terminated.

IS OCCURRING, if a KAMAN high alarm has been reached as a result of the event, and is still in alarm, and the release is not isolated.

6. AIRBORNE RELEASE TO ENVIRONMENT - Mark the letter corresponding to the appropriate description.
7. TYPE OF RELEASE - Mark the letter(s) corresponding to the appropriate release type(s).
  • Filtered releases flow through any operable Standby Gas Treatment or Offgas System charcoal bed to the Offgas stack.
  • An unfiltered release is one that is entering the environment by any other path.
  • If a RADIOACTIVE LIQUID release is in progress, contact the Site Rad Protection Coordinator for additional information and support.
  • If the release has multiple paths to the environment, mark ALL appropriate types of releases.
8. PROJECTED DURATION OF RELEASE - Mark the letter corresponding to the appropriate release duration. If the release duration is known, indicate appropriate hours and minutes that the release will last. (NOTE: If the release duration is 1-hour or less, note the affect it has on the PAR when at a General Emergency.)
9. WIND SPEED - Fill in the wind speed in miles/hour. The 50 meter value is the preferred value to use. If it is unavailable then use the 10 meter value. If both are unavailable, contact the National Weather Service @ 1-800-803-9357
10. WIND DIRECTION - Fill in the direction in degrees, from where the wind is originating. The 50 meter value is the preferred value to use. If it is unavailable then use the 10 meter value. If both are unavailable, contact the National Weather Service

@ 1-800-803-9357

11. PROTECTIVE ACTION RECOMMENDATIONS - Check one of the boxes corresponding to the appropriate default Protective Action Recommendation. Refer to EPIP 3.3 for guidance on Protective Action decision-making.

PAR DETERMINATION - If this notification is for a PAR change ONLY, note time & date. Otherwise write N//A in TIME and DATE in Block 11.

12. ADDITIONAL INFORMATION - Additional information should be included when:
  • A wind shift results in additional downwind subareas (see EPIP 3.3 Att. 2)
  • Corrections to current State/County notifications are made
  • Specify initiating condition for EALs with multiple initiating conditions
  • Other information deemed necessary to inform the State and Counties
13. APPROVED BY - Authorizing signature of OSM, EC, or ER&RD.

INITIAL ROLL CALL - Dial 9999 (#### to stop the ringing) and mark appropriate box for the applicable agency as they answer the initial roll call.

MESSAGE INITIATED - Document the time and date you get at least one agency on the phone.

Read Items 1-13 on Notification Message Above - Read message from Item 1 through to Item 13, (For example, One, bravo, drill. Two, delta, simulator etc.

MESSAGE TRANSMITTED BY - Applicable Communicator writes in their name and time message completed.

FINAL ROLL CALL - Enter initials of agency representatives receiving this notification.

FAX - Fax page 1 of this form to the State & Counties.

14. STATE PROTECTIVE ACTIONS - IF AVAILABLE, circle subareas the STATE has chosen to shelter or evacuate. If not available, leave this section blank.

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