ML13308A894

2013 DAEC Initial License Examination Administered RO and SRO Administrative JPMs

ML13308A894
Person / Time
Site:	Duane Arnold
Issue date:	04/08/2013
From:	NRC/RGN-III
To:	Duane Arnold
Randal Baker
Shared Package
ML11354A336	List: ML13308A839 ML13308A865 ML13308A894 ML13308A904
References
Download: ML13308A894 (171)

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{{#Wiki_filter:NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 1 of 12 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE

2013 NRC RO ADMIN JPM COO1 TITLE: Perform Reactor Coolant Leakage Calculations Per STP 3.0.0 -01 NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 2 of 12 JOB PERFORMANCE MEASURE (JPM) SITE: DAEC JPM TITLE: Perform Reactor Coolant Leakage Calculations Per STP 3.0.0 -01 JPM NUMBER: NRC RO ADMIN JPM COO1 REV. 0 RELATED PRA INFORMATION: None TASK NUMBER(S) / TASK TITLE(S): 1.07 (Reactor Operator)

/  Perform Surveillance Test Procedures K/A NUMBERS AND VALUES:  Generic 2.1.7, Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation

. IMPORTANCE: 4.4 / 4.7 Justification (FOR K/A VALUES <3.0): N/A APPLICABLE METHOD OF TESTING: RO SRO STA NSPEO SRO CERT Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room: Simulator: Classroom X Lab: Time for Completion: 10 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: RO Developed by: Mark Santiago 11/0812 WTS JPM Developer Date Validated by: Validation Instructor Date Reviewed by: Plant Reviewer Date Approved by: Training Supervisor Date NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 3 of 12 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 trainee's 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

NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 4 of 12 SIMULATOR SET UP:

1. NA Required Materials:

1. STP 3.0.0

-01, Attachment 1 & 2,

2. Calculator

3. Drywell Leakage Handout (In JPM folder)

General

References:

1. STP 3.0.0

-01, Attachment 1 & 2, Rev 125 Task Standards:

1. Determine that 38 gallons were pumped from the Floor Drain Sump.

2. Determine that unidentified leakage equals 0.16 gpm (plus or minus 0.10).

3. Determine that 360 gallons were pumped from the Equipment Drain Sump.

4. Determine that identified leakage equals 1.50 gpm (plus or minus 0.10).

5. Determine that total leakage equals 1.66 gpm (plus or minus 0.10).

6. Determine that the Unidentified Leakage is greater than 0.1 gpm and has exceeded the acceptance criteria.

NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 5 of 12 EVALUATOR TURNOVER SHEET (Read to Applicant) 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. INITIAL CONDITIONS: It is 1200 noon. You are a control room RO. Another RO has just taken the 1200 Drywell sump pump readings but has been called upon to assist in a pre -job brief for other plant work. Here are the 1200 noon Drywell sump readings: o FQ-3707, Floor Drain Totalizer reading

124538 o FQ-3708, Equipment Drain Totalizer

:     332145  No other STPs are in progress.

INITIATING CUES: Complete page 7 of 58 of STP 3.0.0-01, Instrument Checks, for the 1200 Drywell Equipment and Floor Drain leakage calculations . Here are the leakage calculations from earlier in the shift. Evaluator Note: Give the operator the Drywell Leakage Handout at this point. This Task is not time critical . Inform the evaluator when you have completed the task . NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 6 of 12 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 examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication). NOTE: Critical steps are shaded GREY and 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 calculations for the Drywell Floor and Equipment sump pump downs can be done in any order. Performance Step: 1 Critical N For Attachment 1, the candidate will fill in the following numbers for line a:

a. FQ 3707, present reading 124538 Time of Reading 1200 Standard:

124538 filled in line "a" for FQ -3707 of the 1200 reading. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical N For Attachment 1, the candidate will fill in the following numbers for line b:

b. FQ 3707 previous reading 124500 Time of Reading 0800 Standard: 124500 filled in on line "b" for FQ

-3707 of the 1200 reading Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 3 Critical Y For Attachment 1, the candidate will fill in the following numbers for line c:

c. Total gallons pumped (a

-b) 38 Standard: After the subtraction, determine that 38 gallons were pumped from the Floor Drain Sump Pumps for the 1200 reading. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 7 of 12 Performance Step: 4 Critical N For Attachment 1, the candidate will fill in the following numbers for line d:

d. Time interval (a

-b) 4 hours x 60 = 240 min. Standard: 4 hours for the time interval and 240 for the total minutes. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 5 Critical Y For Attachment 1, the candidate will fill in the following numbers for line e:

e. Unidentified average leak rate =

Total Gallons Pumped (c) [38] Time Interval (minutes) (d)[240] = 0.16 gpm. Standard: Determines that the unidentified leakage equals 0.16 gpm (plus or minus 0.10). Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 6 Critical N For Attachment 1, the candidate will fill in the following numbers for line f:

f. Confirm unidentified average leak rate (e) is 5 gpm Standard:

Operator will initial that the leakage is <5 gpm. Evaluator Note: The candidate may fill in the calculations in the 1600 block. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 7 Critical N For Attachment 2, the candidate will fill in the following numbers for line a:

a. FQ 3708 present reading 332145 Time of Reading 1200 Standard:

332145 filled in line "a" for FQ -3708 for the 1200 reading. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 8 of 12 Performance Step: 8 Critical N For Attachment 2, the candidate will fill in the following numbers for line b:

b. FQ 3708 previous reading 331785 Time of Reading 0800 Standard:

331785 is filled in on line "b" for FQ -3708 for the 1200 reading. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 9 Critical Y For Attachment 2, the candidate will fill in the following numbers for line c:

c. Total gallons pumped (a

-b) 360 Standard: After the subtraction, determine that 360 gallons were pumped from the Equipment Drain Sump Pumps for the 1200 reading. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 10 Critical N For Attachment 2, the candidate will fill in the following numbers for line d:

d. Time interval (a

-b) 4 hours x 60 = 240 min. Standard: 4 hours for the time interval and 240 for the total minutes. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 11 Critical Y For Attachment 2, the candidate will fill in the following numbers for line e:

e. Identified average leak rate =,

Total Gallons Pumped (c)

[360] Time Interval (minutes) (d) [240]          

= 1.50 gpm. Standard: Determines that the identified leakage equals 1.50 gpm (plus or minus 0.1). Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 9 of 12 Performance Step: 12 Critical Y For Attachment 2, the candidate will fill in the following numbers for line f:

f. Add identified (e) and unidentified (Att 1, e) =

1.66 . Standard: 1.66 gpm total leakage for f. + 0.10. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 13 Critical N For Attachment 2, the candidate will fill in the following numbers for line g:

g. Confirm unidentified average leak rate (f) is 25 gpm Initials Standard:

Operator will initial that the leakage is < 25 gpm. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 14 Critical N Candidate initials the 1200 Operator Initials section on Page 7 of 58 for both DW Unidentified Leakage and DW Identified Leakage. Standard: Initials the 1200 DW Unidentified and DW Identified Leakage as being complete. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 15 Critical Y Compare results for Unidentified Leakage to the Acceptance Criteria. Standard: Determines that the Acceptance Criteria for DW Unidentified Leakage has been exceeded based on leakage being 0.1 gpm. Determines that the requirements of OI 920, Section 2.0 must be implemented or notifies the CRS . Evaluator Cue: If the Candidate wants to pursue the actions of OI 920, Cue that the CRS will implement the requirements of OI 920. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 10 of 12 Performance Step: 16 Critical N Compare results for Identified Leakage to Acceptance Criteria. Standard: Determines that the Acceptance Criteria for DW Identified Leakage has been met based on leakage being Evaluator Cue: When the candidate has determined that the Acceptance Criteria for DW Unidentified Leakage has been exceeded, Cue the candidate that the JPM is complete. Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: When the CRS has been notified that the DW Unidentified Leakage is greater than 0.1 gpm, which is out of compliance with the ACCEPTANCE CRITERIA, or the requirements of OI 920 are discussed with the CRS, the JPM is complete. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002} Stop Time:

NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 11 of 12 RO Admin JPM COO1, Perform Reactor Coolant Leakage Calculations Per STP 3.0.0 -01 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). EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC 2013 RO ADMIN JPM COO1 03 13.DOC Page 12 of 12 TURNOVER SHEET INITIAL CONDITIONS: It is 1200 noon. You are a control room RO. Another RO has just taken the 1200 Drywell sump pump readings but has been called upon to assist in a pre -job brief for other plant work. Here are the 1200 noon Drywell sump readings: o FQ-3707, Floor Drain Totalizer reading: 124538 o FQ-3708, Equipment Drain Totalizer : 332145 No other STPs are in progress. INITIATING CUES: Complete page 7 of 58 of STP 3.0.0-01, Instrument Checks, for the 1200 Drywell Equipment and Floor Drain leakage calculations. Here are the leakage calculations from earlier in the shift. This Task is not time critical. Inform the evaluator when you have completed the task. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

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2013 NRC RO ADMIN COO2 TITLE: Verify Control Rod Exercise Test Prerequisites

NRC 2013 RO ADMIN JPM COO2 03 13 DOC.DOC Page 2 of 10 SITE: DAEC JPM TITLE: Verify Control Rod Exercise Test Prerequisites JPM NUMBER: NRC RO ADMIN JPM COO2 REV. 1 RELATED PRA INFORMATION: None TASK NUMBER(S) / TASK TITLE(S ): 71.04/Perform Process Computer Operations K/A NUMBERS AND VALUES: Generic 2.1.19 Ability to use plant computers to evaluate system or component status. IMPORTANCE: 3.9/3.8 Justification (FOR K/A VALUES <3.0): N/A APPLICABLE METHOD OF TESTING: RO SRO STA NSPEO SRO CERT Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room: Simulator: X Other: Lab: Time for Completion: 15 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: RO Developed by: Mark Santiago 12/05/12 WTS JPM Developer Date Validated by: Validation Instructor Date Reviewed by: Plant Reviewer Date Approved by: Training Supervisor Date NRC 2013 RO ADMIN JPM COO2 03 13 DOC.DOC Page 3 of 10 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 trainee's 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

NRC 2013 RO ADMIN JPM COO2 03 13 DOC.DOC Page 4 of 10 SIMULATOR SET UP

1. NA Required Materials:

1. STP 3.1.3-01 week 1

2. Printouts of the two Handouts in the JPM folder

. Note: Handout (1) is a 3D case modified for this JPM. Handout (2) is a control rod position log needed for this JPM. General

References:

1. STP 3.1.3-01 week 1, Rev 3 Task Standards:

1. Obtains a 3d Official case from the process computer.

2. Verifies that the MFLPD value meets the procedure prerequisite.

3. Determines that the MAPRAT value does not meets the procedure prerequisite.

4. Obtains a Rod Position Log from the process computer.

5. Determines the partially withdrawn rods and annotates the attachments to the procedure accordingly.

NRC 2013 RO ADMIN JPM COO2 03 13 DOC.DOC Page 5 of 10 EVALUATOR TURNOVER SHEET (Read to Applicant) 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 is at rated conditions. Control rod exercising is scheduled for the shift. All control rods are operable. The Process Computer is available. INITIATING CUES: As specified in the prerequisites section for Surveillance Test Procedure STP 3.1.3 -01 WK1, Control Rod Exercise Week 1, Section 6.0 and by using the Process Computer

o determine whether the current core thermal limits will support control rod exercising o determine if there are any rods that are NOT fully withdrawn. Document those rods that are NOT fully withdrawn IAW step 6.4 of the procedure.

This Task is not time critical . Inform the evaluator when you have completed the task . NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC 2013 RO ADMIN JPM COO2 03 13 DOC.DOC Page 6 of 10 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 examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication). NOTE: Critical steps are shaded GREY and 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 below steps do not have to be performed in order . Performance Step: 1 Critical N Reviews STP 3.1.3-01 WK1 and enters Section 6.0 Prerequisites. Standard: Operator reviews Section 6.0 Prerequisites. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical Y Using the Plant Process Computer, obtain an Official 3D Case Periodic Log and verify that the most limiting node's MFLPD is less than or equal to () 0.962. N/A this step if less than (<) 20% power and 3D Monicore is not in service and initials step. Standard: Obtains an Official 3D Case Periodic Log from the process computer by typing in RUN 3D . Evaluator Note: Once the operator has demonstrated the ability to obtain an official case from the computer, give the operator the 3D Monicore Official Case prepared for this JPM. Do NOT hand out the Rod Position Log at this time. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM COO2 03 13 DOC.DOC Page 7 of 10 Performance Step: 3 Critical N Using the Plant Process Computer, obtain an Official 3D Case Periodic Log and verify that the most limiting node's MFLPD is less than or equal to () 0.962. N/A this step if less than (<) 20% power and 3D Monicore is not in service and initials step. Standard: Determines that the most limiting MFLPD is 0. 855 Determines that the perquisite is met. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical Y Using the Plant Process Computer, obtain an Official 3D Case Periodic Log and verify that the most limiting node's MAPRAT is less than or equal to () 0.962. Standard: Reviews the previously obtained Official 3D Case Periodic Log . Determines that the most limiting MAPRAT is 0.965 Determines that the prerequisite is NOT met. Notifies the CRS. Evaluator Cue: As required, Role Play as the CRS. Acknowledge the report and direct the operator to verify the status of the remaining prerequisites. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 5 Critical Y Using the Plant Process Computer, obtain a Rod Position Log and attach to this procedure. If computer is not available, record AS FOUND ROD POSITION for each control rod on Attachment 1, Pre -Test Control Rod Positions and initials step. Standard: Obtains a Rod Position Log and attaches it to the procedure. Evaluator Note: Once the operator has demonstrated the ability to obtain a Rod Position Log from the computer, give the operator the Rod Position Log prepared for this JPM. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM COO2 03 13 DOC.DOC Page 8 of 10 Performance Step: 5 Critical Y Step 6.4, Based on control rod positions obtained in Prerequisite 6.3, mark N/A all steps on Attachment 3 for control rods that are NOT fully withdrawn and operable. Standard: Reviews Attachment 1 and marks N/A all the steps on Attachment 3 for control rods that are NOT fully withdrawn and operable and initials step. Evaluator Note: The Rod Position Log only displays the position for rods that are not fully withdrawn. Although there are 8 rods that are not fully withdrawn, there are only 3 of these rods that are addressed by STP 3.1.3 -01 WK1, Control Rod Exercise Week 1. These rods are: 14-15 22-15 30-15 Evaluator Cue: Once the candidate has marked N/A all steps on Attachment 3 for control rods that are NOT fully withdrawn and operable., Cue that completes the JPM. Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: When the candidate has determined: o That the MFLPD Prerequisite is met o That the MAPRAT Prerequisite is NOT met o Those Rods that are NOT fully withdrawn by interpreting a control rod position log. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C001} Stop Time:

NRC 2013 RO ADMIN JPM COO2 03 13 DOC.DOC Page 9 of 10 RO Admin JPM COO2, Verify Control Rod Exercise Test Prerequisites 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). EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC 2013 RO ADMIN JPM COO2 03 13 DOC.DOC Page 10 of 10 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 is at rated conditions. Control rod exercising is scheduled for the shift. All control rods are operable. The Process Computer is available. INITIATING CUES: As specified in the prerequisites section for Surveillance Test Procedure STP 3.1.3 -01 WK1, Control Rod Exercise Week 1, Section 6.0 and by using the Process Computer: o determine whether the current core thermal limits will support control rod exercising o determine if there are any rods that are NOT fully withdrawn. Document those rods that are NOT fully withdrawn IAW step 6.4 of the procedure. This Task is not time critical. Inform the evaluator when you have completed the task. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

1 CORE PARAMETERS DAEC CYCLE 2 4 3DM >>SIMULATOR<< PAGE SEQUENCE NO 8 Today 07:57 CALCULATED POWER MWT 1905. PERIODIC LOG Today 07:57 PRINTED POWER MWE 637. USER REQUEST CASE ID FMLS1121105075732 FLOW MLB/HR 48.768 CALC RESULTS RESTART FMLS1121105075732 FPAPDR 0.841 LPRM SHAPE

- FULL CORE SUBC BTU/LB 22.90 Keff    1.0037  PR PSIa 1037.8 XE WORTH %
-1.54 LOAD LINE SUMMARY CORE MWD/sT 21469.5 XE/RATED 0.66 CORE POWER 99.6% CYCLE MWD/sT 7900.8 AVE VF 0.444 CORE FLOW 99.5% MCPR  1.725  LOAD LINE 99.93%  CORRECTION FACTOR:

MFLCPR= 1.001 MFLPD= 1.000 MAPRAT= 1.000 OPTION: ARTS 2 LOOPS ON MANUAL FLOW MCPRLIM= 1.380 MOST LIMITING LOCATIONS (NON -SYMMETRIC) MFLCPR LOC MFLPD LOC MAPRAT LOC PCRAT LOC 0.921 23-20 0.855 21-30-19 0.965 21-30-19 0.792 23-16-19 0.899 21-26 0.853 23-16-19 0.960 23-16-19 0.790 21-30-19 0.858 23-26 0.851 23-30-19 0.889 21-16-19 0.788 7 8 0.824 25-22 0.841 7 8 0.840 23-30-19 0.782 23-30-19 0.792 19-24 0.840 37 8 0.764 7 8 0.774 37 8 0.791 25-24 0.838 37 8 0.706 37 8 0.772 37 8 0.789 19-22 0.828 9 6 0.705 7 8 0.766 35 6 0.696 7-18 0.826 35 6 0.697 35 6 0.761 9 6 0.695 37-18 0.824 9 6 0.695 9 6 0.760 35 6 0.693 7-28 0.823 35 6 0.693 35 6 0.758 9 6 SEQ. A-2 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT *=MULTIPLE CORE AVE AXIAL NOTCH REL PW LOC 0.470 25 00 0.940 24 02 1.084 23 43 04 1.229 22 L 06 1.238 21 39 08 1.248 20 10 1.196 19 35 12 1.145 18 14 1.100 17 31 20 *16 20 16 1.055 16 18 1.009 15 27 20 0.964 14 L 22 0.971 13 23 16 16 24 0.979 12 26 0.988 11 19 C 28 0.996 10 L 30 1.022 09 15 20 16P 20 32 1.049 08 34 1.082 07 11 36 1.115 06 L 38 1.032 05 07 40 0.949 04 42 0.641 03 03 44 0.333 02 L L L L L 46 0.166 01 02 06 10 14 18 22 26 30 34 38 42 CORE AVERAGE RADIAL POWER DISTRIBUTION RING # 1 2 3 4 5 6 REL PW 1.297 1.327 1.165 1.138 1.126 0.664 PAGE 2 DAEC CYCLE 2 4 INSTRUMENT READINGS/STATUS SEQUENCE NO 8 RAW LPRM READINGS Today 07:57 CALCULATED Today 07:57 PRINTED 41D 29.2 35.3 CASE ID FMLS1121105075732 C 30.2 37.0 LPRM SHAPE - FULL CORE B 30.2 37.4 A 24.2 31.6 # OF TIPS NOT SCANNED: 1 # OF TIPS REJECTED: 1 33D 38.1 55.4* 59.2 48.5 C 38.5 50.2 44.7 46.9 FAILED SENSORS: B 36.9 40.4 42.2 39.2 LPRM ( 0 SIGNAL FAILED) A 34.0 38.0 38.3 37.4 LPRM ( 0 PANACEA-REJECTED) OTHER SENSORS ( 0 TOTAL) 25D 45.6 65.6C 66.0 59.3 35.6 SUB RODS C 42.7 48.1 53.9 44.4 37.1 NONE B 42.4 42.4 45.4 42.6 37.1 A 44.2 33.3 36.1 38.3 31.4 T = TIP RUN RECOMMENDED C = MFLCPR LOCATION 17D 41.5 62.8P 65.4 55.3 28.8 M = MAPRAT LOCATION C 39.2 53.1 49.0 49.9 30.7 D = MFLPD LOCATION B 39.3 40.6 42.8 40.3 30.6 P = PCRAT LOCATION A 41.7 32.8 33.7 37.8 25.1 * = MULTIPLE LIMIT 09D 27.8 41.5 45.3 37.9 C 26.3 39.2 42.6 38.6 B 24.6 39.4 42.2 36.9 A 16.6 41.3 44.2 33.9 08 16 24 32 40 CORE SUMMARY INER 1.121 CORE POWER 99.6% CALC SUB FLOW 101.2% DP MEAS PSI 23.95 CORE FLOW 99.5% OPER SUB FLOW

-2.0% DP CALC PSI 28.11 LOAD LINE 99.9% FLOW BASIS MEAS FEEDWTR FLOW MLB/HR 8.25   APRM CALIBRATION A    READING 100.4 100.4 100.5 100.5 100.4 100.5 AGAF 1.007 1.006 1.006 1.006 1.006 1.005 APRM - %CTP -0.7 -0.6 -0.6 -0.6 -0.6 -0.5  TIP RUNS RECOMMENDED STRINGS: NONE DRIVE FLOW MLB/HR 22.20 FEEDWTR TEMP DEG.F 427.3 CORE AVG VOID FRACTION 0.44 Today  Calculated Today  Printed NRC 2013 RO ADMIN JPM EC01 03 13.DOC  Page 1 of 12   DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE

2013 NRC RO ADMIN JPM EC01 TITLE: Using mechanical drawings determine the isolation boundaries for leak on the Core Spray system. NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 2 of 12 SITE: DAEC JPM TITLE: Using mechanical drawings determine the isolation boundaries for leak on the Core Spray system. JPM NUMBER: NRC RO ADMIN JPM EC01 REV. 1 RELATED PRA INFORMATION: None TASK NUMBER(S) / TASK TITLE(S): 4.00 / Monitor the Core Spray System K/A NUMBERS AND VALUES: Generic 2.2.4, Ability to obtain and interpret station electrical and mechanical drawings. IMPORTANCE: 3.4 / 4.7 Justification (FOR K/A VALUES <3.0): N/A APPLICABLE METHOD OF TESTING: RO SRO STA NSPEO SRO CERT Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room: Simulator: Classroom X Lab: Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: RO Developed by: Mark Santiago 12/27/12 WTS JPM Developer Date Validated by: Validation Instructor Date Reviewed by: Plant Reviewer Date Approved by: Training Supervisor Date NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 3 of 12 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 trainee's 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

NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 4 of 12 SIMULATOR SET UP: N/A Required Materials:

1. P&ID index

2. Stick with P&IDs including BECH M-119 and M

-121 3. Copies of BECH M -119 and M -121 4. Evaluator Aids to assist in determining valves to be closed to stop the leak (files in JPM folder ). General

References:

1. P&IDs Task Standards:

Determines that MO-2100 or MO-2147 A Core Spray Torus Suction Valves and V 128, A Core Spray Keep Fill Supply Line Stop Check Valve must be closed to isolate the source of water to a leak on V 0007, Core Spray Pump Discharge Check Valve . NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 5 of 12 EVALUATOR TURNOVER SHEET (Read to Applicant) 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.

INITIAL CONDITIONS: The plant is in MODE

1. An operator reports that "A" Core Spray Pump Discharge Check Valve, V 0007, is leaking into the "A" Core Spray pump room.

INITIATING CUES: The CRS directs you to determine the valve or valves that must be closed to stop the leak on V 0007. Work Control will prepare a clearance at a later time. This Task is not time critical . Inform the evaluator when you have completed the task . NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 6 of 12 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 examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication). NOTE: Critical steps are shaded GREY and 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 operator may use other references to aid in determining the impact. However they are required to demonstrate the ability to use the P&IDs and Electrical prints as described below to satisfactorily complete the JPM. The operator must be able to support his/her conclusion using the mechanical and electrical prints. The steps below may be performed in any order. An Evaluator Aid has been prepared to provide an overview of the impact of the failure. Performance Step: 1 Critical: N Reviews P&ID Index and determines P&ID BECH M -121 is initially required to determine the valves which must be closed to isolate V21-0007, Core Spray Pump discharge check valve. Standard: Determine that P&ID BECH M -121 is initially required to determine the open boundary valves for V21-0007, Core Spray Pump discharge check valve. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: N Identifies and obtains BECH M -121. P&ID for Core Spray System Standard: Obtains BECH M -121, P&ID for Core Spray System Evaluator Note: Once the candidate has determined that P&ID BECH M-121 is required, provided the candidate with the colored copy of P&ID BECH M-121. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 7 of 12 Performance Step: 3 Critical: N Locates V 0007, Core Spray Pump Discharge Check Valve, on P&ID BECH M-119, Standard: Locates V 0007, Core Spray Pump discharge check valve, on P&ID BECH M-119, on coordinates C -3. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical: Y Determines how to isolate the source of water from the Torus. Standard: Identifies that one of the two valves below must be closed: MO-2100, OUTBD TORUS SUCTION Or MO-2147, INBD TORUS SUCTION Evaluator Note: Both valves may be listed however for the purpose of isolating the leak but only one valve is required to be closed. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 5 Critical: Y Determines th at there is a source of water from the keep fill system and that they must also go to P&ID M -119, RHR System (B-6). Standard: Identifies that another source of water is from print M -119, RHR System (B -6). Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 8 of 12 Performance Step: 6 Critical: N Obtains P&ID M-119, RHR System Standard: Obtains P&ID M -119, RHR System Evaluator Note: Once the candidate has determined that P&ID BECH M-119 is required, provided the candidate with the colored copy of P&ID BECH M-119. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 7 Critical: Y Determines how to isolate the source of water from the Keep Fill system. Standard: Identifies that V 128, A Core Spray Keep Fill Supply Line Stop Check Valve, must be closed Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 9 of 12 Performance Step: 8 Critical: N May determine that the following potential sources of water also be verified closed to isolate water to V-21-0007, Core Spray Pump Discharge Check Valve . A Core Spray Pump CST Suction A Core Spray Injection line A Core Spray Minimum Flow line A Core Spray Test line Standard: Identifies that the following valves may be verified closed to isolate water to V 0007, Core Spray Pump discharge check valve. CST suction line via V-21-0001, A Core Spray Pump CST Suction Valve Core Spray injection line via MO-2117, A Core Spray Inboard Injection Valve and/or MO -2115, A Core Spray Outboard Injection Valve Core Spray Minimum flow line via MO-2104, A Core Spray Minimum Flow Bypass Valve and/or V 0008, A Core Spray Minimum Flow Isolation Valve Core Spray Test line via MO-2112, A Core Spray Test Bypass Valve Evaluator Note: It is not critical to close the above valves in order to stop the leak because: V-21-0001, A Core Spray Pump CST Suction Valve is a normally locked closed valve. MO-2117, A Core Spray Inboard Injection Valve is normally closed. Therefore MO-2115, A Core Spray Outboard Injection Valve is not required to be closed. MO-2104, A Core Spray Minimum Flow Valve discharges above the water line into the Torus which is not a source of water to the leak. Additionally it is backed up by check valve V 0009. MO-2112, A Core Spray Test Bypass Valve is a normally closed valve and discharges above the water line into the Torus which is not a source of water to the leak . Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 10 of 12 Terminating Cues: Determines that MO-2100 or MO -2147 A Core Spray Torus Suction Valves and V 128, A Core Spray Keep Fill Supply Line Stop Check Valve must be closed to stop the source of water to a leak on V 0007, Core Spray Pump Discharge Check Valve. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002} Stop Time:

NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 11 of 12 RO Admin JPM EC01, Using Mechanical Drawings determine the Isolation Boundaries for Leak on the Core Spray system. 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). EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC 2013 RO ADMIN JPM EC01 03 13.DOC Page 12 of 12 TURNOVER SHEET INITIAL CONDITIONS: The plant is in MODE

1. An operator reports that "A" Core Spray Pump Discharge Check Valve, V 0007, is leaking into the "A" Core Spray pump room.

INITIATING CUES: Using station P &IDs determine the valves that must be closed to stop the leak on V 0007. A clearance will be issued at a later time. This Task is not time critical. Inform the evaluator when you have completed the task. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

Keep Fill isolation valve One of these 2 suction valves must be closed Circled valves may be closed or verified closed but are NOT required Keep Fill from RHR NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 1 of 12 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE

2013 NRC RO ADMIN JPM RC 01

TITLE: Inspection of High Radiation Areas and Determine Personnel Entry Requirements

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 2 of 12 JPM TITLE: Inspection of High Radiation Areas And Determine Personnel Entry Requirements JPM NUMBER: 2013 NRC JPM RO RC REV. 1 TASK NUMBER(S) / TASK TITLE(S): 1.11 / Conduct Plant Operations in Accordance with Administrative Procedures K/A NUMBERS: Generic 2.3.12, Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high -radiation areas, aligning filters, etc . IMPORTANCE: 3.2 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: Classroom X Time for Completion: 20 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by: Mark Santiago 12/27/12 WTS JPM Developer Date Validated by: Validation Instructor Date Reviewed by: Plant Reviewer Date Approved by: Training Supervisor Date

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 3 of 12 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 trainee's 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. VALIDATION SIGNATURE JPMs must be 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. Validation Personnel Date Validation Personnel Date Validation Personnel Date Validation Personnel Date NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 4 of 12 Simulator Setup Instructions: NA Required Materials: Skimmer Surge Tank Room Basement HP Survey Map (File can be found in JPM Folder ) General

References:

1. HPP-3101.05 2. HPP-3103.03 3. HPP-3104.01 4. HPP-3111.11 5. ACP-1411.17 Task Standards:

1. Identifies radiation hazards

2. Determines the type of RWP required for entry

3. Determines the exposure the operator will incur

4. Determines that the operator may perform the task without additiona l authorization.

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 5 of 12 EXAMINER READ THE FOLLOWING TURNOVER 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.

INITIAL CONDITIONS: DAEC is operating at 100% power Entry into Skimmer Surge Tank Room Basement is required to close and hang a clearance on the "A" Fuel Pool Cooling Pump Vent Valve which is inside the radiological boundary at point 9 o n the survey map. Your current exposure is 1800 mrem TEDE The job is expected to take 15 minutes Survey map is provided INITIATING CUE: You will be performing an entry into the Skimmer Surge Tank Room Basement to close and hang a clearance on the "A" Fuel Pool Cooling Pump Vent Valve hand -wheel. Address the radiological aspects of performing this job and record findings on the scorecard provided. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{RC}

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 6 of 12 NOTE: THIS IS THE EXAMINER SCORECARD. DO NOT PROVIDE TO THE CANDIDATE. Answer the following when performing this task:

1. Pass/Fail Classify the area (check one):

Radiation Area High Radiation Area Locked High Radiation Area Very High Radiation Area 2. Pass/Fail Determine the highest dose rate in the room. 141.4 mrem/hr near location 9

3. Pass/Fail Determine the highest contamination levels in the room

. 21,000 dpm/100cm2 at #4 near the FPC Pump "A" inside the radiological boundary.

4. Pass/Fail Evaluate acceptability of worker performing job considering exposure history. (check one): 35.35 mrem expected exposure, with a TEDE of 1800 mrem the total (1836) is below the 2000 mrem limit.

Acceptable Additional approval(s) required NOTE: THIS IS THE EXAMINER SCORECARD. DO NOT PROVIDE TO THE CANDIDATE.

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 7 of 12 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 examinee's 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 Critical N Obtains Reference Procedures as required. Standard: Performance: SATISFACTORY UNSATISFACTORY Comments: NOTE: A score card is attached to this JPM identifying the items for the performer to identify. Performance Step: 2 Critical Y Classifies the area. Standard: Determines that the area is a HIGH RADIATION AREA. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 3 Critical Y Determines the highest general area dose rate . Standard: Determines the highest general area dose rate to be 141.4 mrem/hr near location 9 (at the Alara Caution point). Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 8 of 12 Performance Step: 4 Critical Y Determines highest contamination level . Standard: Determines highest contamination level to be 21,000 dpm/100cm2 at #4 near the FPC Pump "A" inside the radiological boundary. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 5 Critical N Determine exposure to be received. Standard: Determine the radiation field at the job location is 141.4 mrem/hr. Calculates the dose to be received doing the job: 141.4 mrem/hr. X 15 min/60min/hr =35.35 mrem Determines that job will result in an additional 36 mrem . Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 6 Critical Y Determine whether additional authorization is required. Standard: Refers to ACP 1411.17 as required. Determines that the additional 36 mrem exposure for the job will result in a total exposure of 1838 mrem. Determines that this will not raise the operator's TEDE Quarterly dose above the 2000 mrem limit. Concludes th e no further authorization is required. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 9 of 12 Terminating Cues: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002} Stop Time:

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 10 of 12 RO Admin JPM RC01, Inspection of High Radiation Areas and Determine Personnel Entry Requirements 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). EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 11 of 12 TURNOVER SHEET INITIAL CONDITIONS: DAEC is operating at 100% power Entry into Skimmer Surge Tank Room Basement is required to close and hang a clearance on the "A" Fuel Pool Cooling Pump Vent Valve which is inside the radiological boundary at point 9 on the survey map. Your current exposure is 1800 mrem TEDE The job is expected to take 15 minutes Survey map is provided INITIATING CUE: You will be performing an entry into the Skimmer Surge Tank Room Basement to close and hang a clearance on the "A" Fuel Pool Cooling Pump Vent Valve hand -wheel. Address the radiological aspects of performing this job and record findings on the scorecard provided. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{RC}

NRC 2013 RO ADMIN JPM RC01 03 13.DOC Page 12 of 12 TURNOVER SHEET CONTINUED (Blank Scorecard) SCORECARD Answer the following when performing this task:

1. Classify the area (check one):

Radiation Area High Radiation Area Locked High Radiation Area Very High Radiation Area

2. Determine the highest dose rate in the room.

3. Designate the highest contamination levels in the room.

4. Evaluate acceptability of worker performing job considering exposure history. (check one):

Acceptable Additional approval(s) requir ed 2G;D>1FDEB=(3D>F@I7@DG@F479GFH>I((((( ("&#&("#((((#A9(&I#G&A?5!A'K47',+)-(,)(+)))8:7'59&-)%.+"#&(=EC"6E<;DED+($C675&((&";0<<<<<96 - $%,!#B'(?(4?++&&4CCD #-#'(#'"0, .:44!(!&&#! 99></ (7('9..CC#CG=. )*($!)+-)"#&+,6 0.,22%1#% B>GII;(31' &$*2'($$+*,&&"#$#'!9G(1(1$&%%3#&&7!#8E E+,&',&;2.) /:#"#($-(+-:./58!!0-**%'-)!,% 40 )#BC>+/9.'66(8!/*H%+.6'4(DJ(-D +1*) .+6-0$& ;35+2)+3),*",*,+>)+%,,,,,,-)&'1)>&(14,0)5>&))&*),3/,)**/12#% NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 1 of 10 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE

2013 NRC SRO ADMIN JPM COO1 TITLE: Review STP 3.4.2 -01, Daily Jet Pump Operability Test

NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 2 of 10 SITE: DAEC JPM TITLE: Review STP 3.4.2 -01, Daily Jet Pump Operabilit y Test JPM NUMBER: NRC SRO ADMIN JPM COO1 REV. 2 RELATED PRA INFORMATION: None TASK NUMBER(S) / TASK TITLE(S): 1.02 /Determine Operability for Technical Specification Required Components K/A NUMBERS AND VALUES: Generic 2.1.7 . Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. IMPORTANCE: 4.4 / 4.7 Justification (FOR K/A VALUES <3.0): N/A APPLICABLE METHOD OF TESTING: RO SRO STA NSPEO SRO CERT Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room: Simulator: Classroom X Lab: Time for Completion: 25 Minutes Time Critical: NO Alternate Path / Faulted: NA TASK APPLICABILITY: SRO Developed by: Mark Santiago 01/24/13 WTS JPM Developer Date Validated by: Validation Instructor Date Reviewed by: Plant Reviewer Date Approved by: Training Supervisor Date NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 3 of 10 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 trainee's 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

NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 4 of 10 SIMULATOR SET UP:

1. N/A Required Materials:

1. For Training Only version of STP 3.4.2

-01, Daily Jet Pump DAEC (document can be found in JPM folder) 2. Tech Specs General

References:

1. STP 3.4.2

-01, Daily Jet Pump Operability, Rev 30

2. Tech Specs Task Standards:

1. Determines that Acceptance Criteria 8.2.1 was not met

2. Determines that one recirc pump must be tripped within 2 hours if not corrected. 3. Determines that Acceptance Criteria 8.2.3 was not met and that Jet Pumps 5 and 6 are inoperable.

4. Determines that the plant must be placed in Mode 3 within 12 hours if not corrected.

NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 5 of 10 EVALUATOR TURNOVER SHEET (Read to Applicant) 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 in two loop operation. Reactor power is stable at 88% . The plant has been at 88% for the last 24 hours to address a plant equipment issue. STP 3.4.2 -01, Daily Jet Pump Operability Test, has just been completed by an RO. The JETS program was utilized. The RO has indicated that all the acceptance criteria of the STP have been satisfied. INITIATING CUES: Review the completed STP 3.4.2 -01, Daily Jet Pump Operability Test for acceptability and inform the evaluator of any discrepancy . Assume the JETs Printouts are attached and that ALL JETS program calculations have been accurately transcribed onto the various attachments of STP 3.4.2 -01. This Task is not time critical Inform the evaluator when you have completed the task NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 6 of 10 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 examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication). NOTE: Critical steps are shaded GREY and 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 Critical: Y Reviews STP 3.4.2 -01, Daily Jet Pump Operability Test Section 7.1, Recirc Pump Speed Mismatch. Standard: Determines that Recirc Pump Speed mismatch is not within limits (Step 7.1.4) . Determines that Acceptance Criteria 8.2.1 was incorrectly marked as being satisfied. Evaluator Note: Using Attachment 1, the speed mismatch would be within limits if reactor power was below 69.4%. However with power at 88% the mismatch is outside the allowable limit as indicated by the "hashed lines" of Attachment

1. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: Y Determines required action for Recirc Pump Speed mismatch not within limits. Standard: Refers to Tech Spec Section 3.4. Determines that 3.4.1, Condition C is applicable. Determines that one recirc pump must be tripped within 2 hours if not corrected. Evaluator Cue: If the applicant does NOT state the required operational limitations what is the significance of NOT meeting the surveillance. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 7 of 10 Performance Step: 3 Critical: N Reviews STP 3.4.2 -01, Daily Jet Pump Operability Test Section 7.2, Jet Pumps 9-16 Operability Check . Standard: Determines that Acceptance Criteria 8.2.2 was incorrectly marked as being satisfied because the "A" Recirc Loop Flow is outside the specified limit for the given Recirc Pump Speed per Attachment 2. Determines that all Jet Pump Dp deviations are within the allowable limits of Attachment 4. Concludes that Jet Pumps 9 -16 remain operable. May determine that the CRS was NOT notified per step 7.3.4.c (This is NOT critical) Evaluator Note: Although the "A" recirc loop flow is outside the specified limit for the given recirc pump speed per Attachment 2, all Jet Pump Dp Deviations are within the limits of Attachment 4. Therefore Jet Pumps 9-16 remain operable. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical: Y Reviews STP 3.4.2 -01, Daily Jet Pump Operability Test Section 7.3, Jet Pumps 1-8 Operability Check Standard: Determines that Jet pumps 5 and 6 are outside the limits of Attachment 7 Determines that step 7.3.12.a was answered incorrectly. Determines that Acceptance Criteria 8.2.3 was incorrectly marked as being satisfied. May determine that the CRS was NOT notified per step 7.3.4.c (This is NOT critical) Evaluator Cue: If the applicant does NOT state the required operational limitations what is the significance of NOT meeting the surveillance. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 8 of 10 Performance Step: 5 Critical: Y Determines required action for Jet pumps 5 and 6 being outside the specified limits of Attachment 7 Standard: Refers to Tech Spec Section 3.4. Determines that 3.4. 2, Condition A is applicable. Determines that the plant must be placed in Mode 3 within 12 hours. Evaluator Note: Surveillance Requirement 3.4.2.1 specifies that either criteria "a" or "b" be satisfied. (Criteria Criteria "a" is not met because Recirc Loop "B" parameters are outside the limits of Attachments 5 and 6. Criteria "b" is not met because jet pumps 5 and 6 are outside the limits of Attachment 7 in that there is > a 20% deviation from established patterns. Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: Determination made that acceptance criterion 8.2.1, 8.2.2 and 8.2.3 have not been met. Determination made that Recirc Pump Speed Mismatch is outside allowable limits. Determination made that Jet Pumps 9 -16 are operable. Determination made that Jet Pumps 5 and 6 are inoperable. Tech Spec required actions have been determined. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002} Stop Time:

NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 9 of 10 SRO Admin JPM COO1, Review STP 3.4.2 -01, Daily Jet Pump Operability Test 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). EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC 2013 SRO ADMIN JPM COO1 03 13.DOC Page 10 of 10 TURNOVER SHEET INITIAL CONDITIONS: The plant is in two loop operation. Reactor power is stable at 88%. The plant has been at 88% for the last 24 hours to address a plant equipment issue. STP 3.4.2 -01, Daily Jet Pump Operability Test, has just been completed by an RO. The JETS program was utilized. The RO has indicated that all the acceptance criteria of the STP have been satisfied. INITIATING CUES: Review the completed STP 3.4.2 -01, Daily Jet Pump Operability Test. Verify that all of the Technical Specification acceptance criteria of section 8.2 have been met. If not, specify which were not met and determine any required actions. Assume the JETs Printouts are attached and that ALL JETS program calculations have been accurately transcribed onto the various attachments of STP 3.4.2 -01. This Task is not time critical. Inform the evaluator when you have completed the task.

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

{C002}

Usage Level CONTINUOUS Effective Date: __________________ Effective 7/16/2007 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 hour 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 Reviewed By:  /  Date:   Print Signature PROCEDURE APPROVAL BY QUALIFIED REVIEWER Approved By 
 /  Date:   Print Signature

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 2 of 22 Rev. 30 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 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 Collect Jet Pump DP values using the "2 MIN AVE" screen on FR -4501 and FR-4502 in Sections 7.2 and 7.3. Any display screen can be used at other times.

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 3 of 22 Rev. 30 2.2 GENERAL CAUTIONS 2.2.1 None 2.3 SPECIAL PRECAUTIONS 2.3.1 None

3.0 REFERENCES

3.1 None 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

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 4 of 22 Rev. 30 Appendix A JETS PROGRAM INSTRUCTIONS Sheet 1 of 1

1. If at a workstation desktop, log onto SSE as follows:

a. Click: Start : Apps : PC3270 IBM Personal Communications : PPC

b. At Username Prompt type SSE <Enter>.

c. Use 04SOYBEAN for Password.

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, 2, or 3 as appropriate for the current status of the Recirc System and press <Enter>. The specified Jet Pump table menu should come up on the screen.

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 Pump's 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.

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 5 of 22 Rev. 30 Prerequisites Performance Date: ___Today____________ INITIALS

6.0 PREREQUISITES

6.1 The reactor is in two -loop operation. (If the reactor is in single loop operation, perform STP 3.4.2 -03 instead.) ___RO__ (OPS) 6.2 For sections 7.2 and 7.3, reactor power is greater than (>) 21.7% RTP. (See Performance Information Step 2.1.1.) ___RO__ (OPS) DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 6 of 22 Rev. 30 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 CONTROL, select "P" - PERCENT SPEED mode of indicati on. ___RO___ a. Record the percent speed indication. A MG SET PERCENT SPEED (SIC -9245A) _____ 75____ % ___RO___ TS b. Record the percent speed indication in Step 7.2.1. ("N/A" this step if Section 7.2 is not required.) ___RO___ c. Using the "D" button on SIC -9245A, select "S" - PERCENT SPEED DEMAND mode of indication. ___RO___ 7.1.2 At 1C04, using the "D" button on SIC -9245B, B MG SET SPEED CONTROL, select "P" - PERCENT SPEED mode of indication. ___RO___ a. Record the percent speed indication. B MG SET PERCENT SPEED (SIC -9245B) _____ 94____ % ___RO___ TS b. Record the percent speed indication in Step 7.3.1. ("N/A" this step if Section 7.3 is not required.) ___RO___ c. Using the "D" button on SIC -9245B, select "S" - PERCENT SPEED DEMAND mode of indication. ___RO___ 7.1.3 On Attachment 1, plot the intersection of the Recirc Pump speed values using the data recorded in Steps 7.1.1.a and 7.1.2.a. ___RO___ 7.1.4 Confirm that the point plotted on Attachment 1 is within the appropriate limit for the current core power. If the point is outside the limit, immediately notify the CRS. ___RO___ TS ___RO Signature _____________ _Today_ _1550_ ___RO___ ______________________________ _________ ________ ________ ______________________________ _________ ________ ________ Performed by: Date: Time: DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 7 of 22 Rev. 30 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: A MG SET PERCENT SPEED (SIC -9245A) _75_% DISCHARGE FLOW (FI -4634A) __ 23___ KGPM LOOP A (FI -4523) _____ 20_______ Mlbm/hr ___RO___ 7.2.2 Using the data recorded in Step 7.2.1, plot "A" Recirc MG Set speed vs. "A" Recirc Pump discharge flow on Attachment 2. ___RO___ TS 7.2.3 Using the data recorded in Step 7.2.1, plot "A" Recirc MG Set speed vs. Loop "A" Jet Pump flow on Attachment 3. ___RO___ TS NOTE ___RO___ 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 Attachment 3 between or on the sloped lines?

(YES/NO) ___

NO______ ___RO___ TS b. If the answer to Step 7.2.4.a was YES, Jet Pumps 9 -16 are 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. ___N/A_ c. If the answer to Step 7.2.4.a was NO, immediately notify the CRS. Then, "N/A" Step 7.2.4.b and perform the remainder of Section 7.2. ___RO___ 7.2.5 At 1C38, record jet pump total developed head as read on FR-4502, Channel 9 (PDT

-4567), Jet Pump Total Head: FR-4502, Channel 9 (PDT -4567): ____15.5______ psid ___RO___ 7.2.6 At 1C38 recorder FR -4501 Jet Pump Flow - Loop A, using the "2 MIN AVE" screen 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). ___RO___ DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 8 of 22 Rev. 30 Performance Date: ______ Today ______ INITIALS 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 Sectio n 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. ___RO___ 7.2.8 Using the instructions provided in Appendix "A", obtain a printout of "A" Recirc Loop Ps. ___RO___ a. Attach the printout to the STP. ___RO___ 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. ___NA___ 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. ___NA___ 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.

% Deviatio n = 100  Ind. P - Avg. PAvg. P ___NA___  TABLE A  A  B  C JET PUMP (P)  (Ind.P - Avg.P)  (% Deviation)

JP-9 8 JP-10 7.5 JP-11 8 JP-12 7.5 JP-13 8 JP-14 7.5 JP-15 8.5 JP-16 8 (Sum of Ps) 8 = (Avg.P) DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 9 of 22 Rev. 30 Performance Date: ______ Today ______ INITIALS 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. ___RO___ NOTE ___RO___ 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 the lines of the allowable band?

(YES/NO)

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

(YES/NO) _____

_____ ___N/A__ Engineering TS DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 10 of 22 Rev. 30 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) __ 94____% DISCHARGE FLOW (FI -4634B) ____ 29____ KGPM LOOP B (FI -4526) ___ 21____ Mlbm/hr ___RO__ 7.3.2 Using the data recorded in Step 7.3.1, plot "B" Recirc MG Set speed vs. "B" Recirc Pump discharge flow on Attachment 5. ___RO__ TS 7.3.3 Using the data recorded in Step 7.3.1, plot "B" Recirc MG Set speed vs. Loop "B" Jet Pump flow on Attachment 6. ___RO__ TS NOTE ___RO__ 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 Attachment 6 between or on the sloped lines?

(YES/NO)  ___NO______ ___RO__ TS 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. ___N/A__ 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. ___RO__ 7.3.5 At 1C38 recorder FR

-4502 Jet Pump Flow - Loop B, using the "2 MIN AVE" screen 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). ___RO__ 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. ___RO__ 7.3.7 Using the instructions provided in Appendix "A", obtain a printout of "B" Recirc Loop Ps. ___RO__ DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 11 of 22 Rev. 30 Performance Date: ______ Today ______ INITIALS

a. Attach the printout to the STP.

___RO__ 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. ___N/A__ 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. ___N/A__ 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.

% Deviatio n = 100  Ind. P - Avg. PAvg. P ___N/A__  TABLE B  A  B  C JET PUMP (P)  (Ind.P - Avg.P)  (% Deviation)

JP-1 12 JP-2 11 JP-3 11 JP-4 10 JP-5 5.5 JP-6 5.5 JP-7 12 JP-8 12 (Sum of Ps) 8 = (Avg.P) DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 12 of 22 Rev. 30 Performance Date: ______ Today ______ INITIALS 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. ___RO__ NOTE ___RO__ 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 the lines of the allowable band?

(YES/NO)

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

(YES/NO) __________

___N/A__ Engineering TS DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 13 of 22 Rev. 30 Performance Date: ______ Today ______ 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"):

[ X  ] Daily Requirement
[     ] Pump Start
[     ] Unexplained changes
[    ] Other     8.2 All Technical

-Specification -required items, as indicated by "TS", have been performed satisfactorily 8.2.1 Section 7.1 ( ) YES ( ) NO CRS notified ___RO__ 8.2.2 Section 7.2 ( ) YES ( ) NO CRS notified ___RO__ 8.2.3 Section 7.3 ( ) YES ( ) NO CRS notified ___RO__ DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 14 of 22 Rev. 30 Performance Date: ______ Today ______ INITIALS 8.3 All other items checked in this test have been performed satisfactorily. 8.3.1 Section 7.1 ( ) YES ( ) NO CRS notified ___RO__ 8.3.2 Section 7.2 ( ) YES ( ) NO CRS notified ___RO__ 8.3.3 Section 7.3 ( ) YES ( ) NO CRS notified ___RO__ DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 15 of 22 Rev. 30 Performance Date: ______ Today ______ INITIALS 8.4 Indicate any relevant test comments below, otherwise mark this step "N/A": 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

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 16 of 22 Rev. 30 Attachment 1 SPEED OF PUMP "A" vs. SPEED OF PUMP "B" Sheet 1 of 1

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 17 of 22 Rev. 30 Attachment - 2 "A" MG SET SPEED vs. "A" RECIRC PUMP DISCHARGE FLOW Sheet 1 of 1 Two Loop Operation"A" Recirc Pump Flow Curve 0510152025303520%25% 30% 35%40% 45%50%55% 60%65%70% 75%80% 85%90%95%100% 105% 110%MG Set Speed (%)Pump Discharge Flow (KGPM) Last updated from data acquired on December 11, 2010 . DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 18 of 22 Rev. 30 Attachment 3 "A" MG SET SPEED vs. LOOP "A" JET PUMP FLOW Sheet 1 of 1 Two Loop OperationJet Pump Loop "A" Flow 05101520253020%25%30%35%40%45%50%55%60%65%70%75%80%85%90%95%100%105%110%MG Set Speed (%)Loop A Flow (Mlb/Hr) Last updated from data acquired on December 11, 2010 . DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 19 of 22 Rev. 30 Attachment 4 LOOP "A" JET PUMP % DEVIATION vs. JET PUMP NUMBER Sheet 1 of 1 Two Loop OperationLoop "A" Jet Pump Dp % Deviation-30.0%-20.0%-10.0%0.0%10.0%20.0%30.0%40.0%910111213141516Jet Pump NumberJet Pump Dp Deviation Last updated from data acquired on December 11, 2010

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 20 of 22 Rev. 30 Attachment 5 "B" MG SET SPEED vs. "B" RECIRC PUMP DISCHARGE FLOW Sheet 1 of 1 Two Loop Operation"B" Recirc Pump Flow Curve 0510152025 303520%25%30% 35% 40%45%50%55%60%65%70%75%80%85%90%95%100%105%110%MG Set Speed (%)Pump Discharge Flow (KGPM) Last updated from data acquired on December 11, 2010 . DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 21 of 22 Rev. 30 Attachment 6 "B" MG SET SPEED vs. LOOP "B" JET PUMP FLOW Sheet 1 of 1 Two Loop OperationJet Pump Loop "B" Flow 0.05.010.0 15.020.025.030.020%25%30%35%40%45%50%55%60%65%70%75%80%85%90%95%100%105%110%MG Set Speed (%)Loop B Flow (Mlb/Hr) Last updated from data acquired on December 11, 2010

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: DAILY JET PUMP OPERABILITY TEST STP 3.4.2-01 Page 22 of 22 Rev. 30 Attachment 7 LOOP "B" JET PUMP % DEVIATION vs. JET PUMP NUMBER Sheet 1 of 1 Two Loop OperationLoop "B" Jet Pump Dp % Deviation-30.0%-20.0%-10.0%0.0%10.0%20.0%30.0%40.0%12345678Jet Pump NumberJet Pump Dp DeviationLast updated from data acquired on December 11, 2010.

NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 1 of 10 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE

2013 NRC SRO ADMIN JPM COO2

TITLE: Determine Risk and the Protected Systems for Removing a Safety Related Piece of Equipment from Service

NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 2 of 10 SITE: DAEC JPM TITLE: Determine Risk and the Protected Systems for Removing a Safety Related Piece of Equipment from Service JPM NUMBER: NRC SRO Admin COO2 (DAEC JPM 2.1.2-04, modified) REV. 1 RELATED PRA INFORMATION: None TASK NUMBER(S) / TASK TITLE(S): SRO 1.11 / Ensure the Conduct of Plant Operations and Maintenance are in Compliance with Administrative Procedures. K/A NUMBERS AND VALUES: Generic 2.1.2, Knowledge of operator responsibilities during all modes of plant operation. IMPORTANCE: 4.1 / 4.4 Generic 2.1.13, Knowledge of facility requirements for controlling vital/controlled access. IMPORTANCE: 2.5 / 3.2 Justification (FOR K/A VALUES <3.0): N/A APPLICABLE METHOD OF TESTING: RO SRO STA NSPEO SRO CERT Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room: Simulator: X Other: Lab: Time for Completion: 15 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 3 of 10 Developed by: Mark Santiago 12/28/12 WTS JPM Developer Date Validated by: Validation Instructor Date Reviewed by: Plant Reviewer Date Approved by: Training Supervisor Date NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 4 of 10 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 trainee's 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

NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 5 of 10 SIMULATOR SET UP:

1. Ensure the OSM office computer is logged in.

2. Ensure ORAM sentinel is operational.

3. Ensure all systems/components on ORAM sentinel are available.

TRIGGERS: None SIMULATOR MALFUNCTIONS: None SIMULATOR OVERRIDES: None SIMULATOR REMOTE FUNCTIONS: None Required Materials:

1. STP NS13C012SBGTB CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST (Can be found in JPM Folder)

2. OP-AA-102-1003 (DAEC), PROTECTED TRAINS AND GUARDED EQUIPMENT (Can be found in JPM Folder)

3. Access to the ORAM Sentinel program

4. Tech Specs General

References:

1. STP NS13C012SBGTB CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST, Rev. 3 2. OP-AA-102-1003 (DAEC), PROTECTED TRAINS AND GUARDED EQUIPMENT, Rev 23 3. Tech Specs Task Standards:

1. Determination that the SBGT STP will render the system inoperable.

2. Determine the risk color and CDF.

3. Determine the areas that need to be guarded when performing the STP.

NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 6 of 10 EVALUATOR TURNOVER SHEET (Read to Applicant) 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.

INITIAL CONDITIONS: The plant is at rated conditions . Earlier in the shift, an oil leak was discovered on RHR Pump "D". The breaker for the pump has been racked out to repair the oil leak. Surveillance procedure STP NS13C012SBGTB CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST, is also scheduled to be performed this shift . INITIATING CUES: Determine PRA risk color and core damage frequency if the SBGT STP is performed with the "D" RHR pump breaker racked out.

 (Provide applicant with a copy of STP NS13C012SBGTB CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST

.) Determine if any equipment must be guarded during the performance of the SBGT STP per OP-AA-102-1003 (DAEC), PROTECTED TRAINS AND GUARDED EQUIPMENT . (Provide applicant with a copy of OP-AA-102-1003 (DAEC) Rev 2 3.) This task is not time critical . Inform the evaluator when you have completed the task . NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 7 of 10 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 examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication). NOTE: Critical steps are shaded GREY and 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 Critical: Y Operator reviews STP NS13C012SBGTB CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST to determine the impact of performing the surveillance. Standard: Candidate determines that the STP will render the "B" SBGT train unavailable. Evaluator Note: General Caution 2.2.2 of the procedure states that this procedure will render the "B" SBGT train inoperable. More specifically, this will occur during the performance of step 7.1.9. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: Y Start ORAM Sentinel program. Standard: Enters User ID (supervisor) Enters Password (leaves blank) Clicks On -Line, Work Release Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 8 of 10 Performance Step: 3 Critical: Y Operator determines the risk associated with performing the STP during current plant conditions by running a Risk Case using ORAM Sentinel. Standard: Operator determines that the "D" RHR pump is inoperable. Operator toggles "D" RHR pump to "unavailable" Operator toggles "B" train of SBGT to "unavailable". Operator runs an ORAM Sentinel Risk Case and reports overall risk is YELLOW with a CDF of 8.046 E-6 Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical: Y Determines if any systems/areas need to be guarded. Standard: Operator refers to procedure OP-AA-102-1003 (DAEC) , PROTECTED TRAINS AND GUARDED EQUIPMENT . Determines that the following equipment should be guarded: o "A" SBGT o "A" SBDG, 1G31 o "A" ESW, 1P99A o 1A3 o 1K003 Evaluator Note : Attachment 1, page 11 of 16 of OP-AA-102-1003 (DAEC) should be used to determine the suggested guarded equipment. Evaluator Cue: As required and after the operator has determined the equipment to be guarded, CUE the operator that the JPM is complete. Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: Risk Color and CDF has been determines. Areas to be guarded have been determined. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002} Stop Time:

NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 9 of 10 SRO Admin JPM COO2, Determine Risk and the Protected Systems for Removing a Safety Related Piece of Equipment from Service 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). EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC 2013 SRO ADMIN JPM COO2 03 13.DOC Page 10 of 10 TURNOVER SHEET INITIAL CONDITIONS: The plant is at rated conditions. Earlier in the shift, an oil leak was discovered on RHR Pump "D". The breaker for the pump has been racked out to repair the oil leak. Surveillance procedure STP NS13C012SBGTB CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST, is also scheduled to be performed this shift . INITIATING CUES: Determine PRA risk color and core damage frequency if the SBGT STP is performed with the "D" RHR pump breaker racked out. (Provide applicant with a copy of STP NS13C012SBGTB CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST .) Determine if any equipment must be guarded during the performance of the SBGT STP per OP-AA-102-1003 (DAEC), PROTECTED TRAINS AND GUARDED EQUIPMENT. (Provide applicant with a copy of OP-AA-102-1003 (DAEC) Rev 23 .) This task is not time critical. Inform the evaluator when you have completed the task.

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

{C002}

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: SBGT B CHARCOAL BED DELUGE SYSTEM FUNCTIONAL TEST STP NS13C012SBGTB Page 1 of 11 Rev. 3 Usage Level: CONTINUOUS Approved for

'Point-of-Use' printing IF NO Temporary Changes are in effect for this procedure.

Record the following: Date / Time: _____________ / _________ Initials: ____ NOTE: A check to ensure current revision and no temporary changes shall be performed and documented every 24 hours if active document use exceeds a 24 hour period as determined from the date and time recorded above.

1.0 PURPOSE

1.1 The purpose of this STP is to demonstrate the operability of the Standby Gas Treatment B Charcoal Bed Deluge System. 2.0 BRIEFING INFORMATION 2.1 PERFORMANCE INFORMATION 2.1.1 This STP tests 1 Deluge System. Testing is organized as follows: Section Test 7.1 Annual Operability Test And Visual Inspection, Standby Gas Treatment Charcoal Bed Deluge System, Train B All steps within a section shall be performed in sequence and carried through to completion, unless noted otherwise. 2.1.2 Personnel recommended to perform this procedure: 1 Operations 2 I&C Maintenance 2 Mechanical Maintenance 1 Health Physics 2.1.3 Special Test Equipment required: 1 Electrical Jumper Gagging devices for AV-5825B and AV-5815B (only required to be installed in the unlikely event of a loss of air supply to these valves) 2.1.4 Ensure Secondary Containment is maintained while doors and/or access ports/covers are open on SBGT. Additionally, gagging devices shall be available for installation on AV-5825B and AV-5815B (only required to be installed in the unlikely event of a loss of air supply to these valves). DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: SBGT B CHARCOAL BED DELUGE SYSTEM FUNCTIONAL TEST STP NS13C012SBGTB Page 2 of 11 Rev. 3 2.1.5 During performance of this STP, an electrical jumper is installed to simulate "B" SBGT Carbon Bed Hi Temp Deluge Permissive. 2.2 GENERAL CAUTIONS 2.2.1 Do not leave the area unattended with charcoal bed access covers removed. 2.2.2 Performance of this STP makes the "B" SBGT subsystem inoperable. This STP controls the time the system/subsystem/component is inoperable and no other documentation besides that contained in the STP is required unless the "B" SBGT subsystem cannot be returned to its standby readiness condition as directed by this STP or there is an extended delay in completing the STP. 2.2.3 In accordance with DAEC Maintenance Rule Module 4 definitions, during the performance of this STP unavailability is incurred for the "B" SBGT train. 2.3 SPECIAL PRECAUTIONS 2.3.1 Contamination may be present when opening SBGT. Confined Space Entry precautions per ACP 1411.11 apply if entry into SBGT B TRAIN is required. Opening SBGT doors for visual inspection and performance of this STP is not considered an entry per confined space procedure, if no part of one's body breaks the plane of the door. 2.3.2 The SBGT room shall NOT be entered without first having Health Physics verify the O2 concentration above 19.5% when inerting or deinerting the Drywell.

3.0 REFERENCES

3.1 Applicable Drawings: 3.1.1 P&ID 7884 BECH-M133 (1) Fire Protection System 3.1.2 P&ID 7884 BECH-M158 Air Flow Diagram SBGT System 3.1.3 BECH-E113 <97, 98> 3.2 AR14757 DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: SBGT B CHARCOAL BED DELUGE SYSTEM FUNCTIONAL TEST STP NS13C012SBGTB Page 3 of 11 Rev. 3 4.0 GENERAL INSTRUCTIONS 4.1 The CRS shall be informed whenever a procedural step cannot be performed as stated or if any other problem develops during the test. 4.2 An Action Request (AR) should be completed for any problems encountered during the test/inspection. 4.3 If any equipment or components are observed to be in a state of disrepair during the performance of this STP, appropriate corrective maintenance shall be initiated. 4.4 An independent verification (IV) of valves repositioned during the performance of this test will be conducted, when directed by the CRS, using the POST-STP COMPLETION CHECKLIST attached to this procedure. 4.5 This STP provides for concurrent verification (CV). Steps with a second initial line designated "CV" are provided to document completion of the concurrent verification. Concurrent verification is performed for both the installation and removal of temporary modifications (e.g., lifted leads, jumpers, and relay blocks). 4.6 Any jumpers, lifted leads, or relay blocks which will be left unattended, should have a tag attached stating the STP number and location.

5.0 APPENDICES

5.1 Appendix A: Internal Connections for HGA Relay DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST STP NS13C012SBGTB Page 4 of 11 Rev. 3 Appendix A INTERNAL CONNECTIONS FOR HGA RELAY Sheet 1 of 1 NOTE Contact Arrangement As Viewed From "Front" of HGA Relay 21345678 DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST STP NS13C012SBGTB Page 5 of 11 Rev. 3 Prerequisites SBGT B Performance Date: ___________________ INITIALS

6.0 PREREQUISITES

6.1 Performance of Section 7.1 makes the Standby Gas Treatment System Train B inoperable. Using the Safety Function Determination Program, confirm that a loss of safety function will not exist during performance of this

STP. ________ (CRS) 6.2 Using the Technical Specifications, determine the maximum allowed time to perform portions of this STP that make the Standby Gas Treatment System Train B inoperable. Record this time below.

Maximum allowed inoperable time: ______________ ________ (CRS) 6.3 No other testing or maintenance is being performed on the Standby Gas Treatment System Train B charcoal bed deluge system. ________ (CRS) Risk Significant equipment affected by this surveillance test: SBGTS B OTH38845

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST STP NS13C012SBGTB Page 6 of 11 Rev. 3 SBGT B Performance Date: ___________________ INITIALS

7.0 PROCEDURE

7.1 ANNUAL OPERABILITY TEST AND VISUAL INSPECTION, STANDBY GAS TREATMENT CHARCOAL BED DELUGE SYSTEM, TRAIN B CAUTION The SBGT room shall NOT be entered without having Health Physics verify O 2 concentration above 19.5% when inerting or deinerting the Drywell. _________ 7.1.1 At 1C24, verify the B SBGT Train is not in operation. ________ CRITICAL STEP ________ 7.1.2 In the RB 786', verify closed V-33-88, SBGT DELUGE SYSTEMS 19 & 20 SHUTOFF. ________ 7.1.3 Remove pipe cap from V-58-43, "B" SBGT CARBON BED DELUGE SUPPLY HDR DRAIN. ________ 7.1.4 Open V-58-43 to drain the deluge header. ________ 7.1.5 Have Health Physics verify O 2 concentration in the SBGT room above 19.5% when inerting or deinerting the Drywell. Otherwise, mark this step N/A. ________ 7.1.6 At 1C159 in the SBGT Room, install a jumper between contacts 1 and 7 of relay 95-121B. (See Appendix A.) ________ ________ (CV) 7.1.7 Verify Fire Header is drained. ________ 7.1.8 Performance of Step 7.1.9 renders the SBGT Train B inoperable. Ensure Steps 7.1.9 through 7.1.25 are completed within the time allowed by Prerequisite 6.2. Record the date and time below, and inform the CRS of the start of the inoperability condition.

Date/Time: ___________ / ___________ ________ 7.1.9 At 1C24, depress PB-5838B, CARBON BED DELUGE START. ________ 7.1.10 At 1C24, confirm AV-5815B, SBGTS B EXHAUST FAN INLET ISOLATION, closes by observing the green indicating light above

HS-5815B is on. ________ 7.1.11 Locally confirm CV-5837B, SBGT B CARBON BED DELUGE ISOLATION, opens. ________ 7.1.12 At 1C24, depress PB-5837B CARBON BED DELUGE RESET. ________ DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST STP NS13C012SBGTB Page 7 of 11 Rev. 3 SBGT B Performance Date: ___________________ INITIALS 7.1.13 At 1C24, confirm AV-5815B opens by observing the red indicating light above HS-5815B is on. ________ 7.1.14 Locally confirm CV-5837B closes. ________ 7.1.15 At 1C159, remove the jumper installed between contacts 1 and 7 of relay 95-121B. ________ ________ (CV) 7.1.16 Close V-58-43, "B" SBGT CARBON BED DELUGE SUPPLY HDR DRAIN, and install pipe cap. ________ 7.1.17 Visually inspect the system piping, supports, pipe hangers, etc., for evidence of corrosion, deterioration, and damage. If any noticed, inform the CRS. ________ 7.1.18 Verify 1V-EF-15B (handswitch HS-5816B), SBGTS B EXHAUST FAN, is not running. ________ 7.1.19 Performance of Step 7.1.20 renders the SBGT Train B unavailable. Ensure Steps 7.1.20 through 7.1.25 are completed within the time allowed by Prerequisite 6.2. Record the date and time below, and inform the CRS of the start of the unavailability

condition.

Date/Time: ___________ / ___________ ________ a. Verify SBGT unavailability has been logged and risk evaluated. ________ (OPS) 7.1.20 At 1C24, position the following switches as follows: a. B SBGT MODE SELECT keylock switch HS-5814B in the MANUAL position ________ b. INTAKE VALVE AV-5825B handswitch HS-5825B in the CLOSED position ________ c. FAN INLET VALVE AV-5815B handswitch HS-5815B in the CLOSED position ________ DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST STP NS13C012SBGTB Page 8 of 11 Rev. 3 SBGT B Performance Date: ___________________ INITIALS CAUTION Contamination may be present when opening SBGT. Confined Space Entry precautions per ACP 1411.11 apply if entry into SBGT B TRAIN is required. Opening SBGT doors for visual inspection and performance of this STP is not considered an entry per confined space procedure, if no part of one's body breaks the plane of the door. _________ 7.1.21 Have HP coverage when opening SBGT. ________ 7.1.22 Open the access covers to the charcoal beds (in any order): Bed 01 _____ init. Bed 02 _____ init. Bed 03 _____ init. Bed 04 _____ init. Bed 05 _____ init. Bed 06 _____ init. 7.1.23 Visually inspect the spray nozzles for evidence of corrosion, deterioration, damage, or obstructions. If any noticed, notify the CRS. (Visual inspection may be performed in any order.) Bed 01 _____ init. Bed 02 _____ init. Bed 03 _____ init. Bed 04 _____ init. Bed 05 _____ init. Bed 06 _____ init. 7.1.24 Replace the access cover to the charcoal bed (in any order): Bed 01 _____ init. Bed 02 _____ init. Bed 03 _____ init. Bed 04 _____ init. Bed 05 _____ init. Bed 06 _____ init. 7.1.25 At 1C24, position the following switches as follows:

a. B SBGT MODE SELECT keylock switch HS-5814B in the AUTO position

________ b. INTAKE VALVE AV-5825B handswitch HS-5825B in the OPEN position ________ c. FAN INLET VALVE AV-5815B handswitch HS-5815B in the OPEN position ________ DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST STP NS13C012SBGTB Page 9 of 11 Rev. 3 SBGT B Performance Date: ___________________ INITIALS 7.1.26 Perform the following: a. Record the date and time below and inform the CRS of the return to service and availability of SBGT Train B:

Date/Time: ___________ ________ b. Determine the elapsed time since date and time was recorded in Step 7.1.8 and record elapsed time below: Elapsed Time: ____________ ________ c. Confirm that the elapsed time recorded in Step 7.1.26.b is less than or equal to the allowable time recorded in Prerequisite 6.2. If the elapsed time is greater than the allowable time recorded in Prerequisite 6.2, inform the CRS

immediately. ________ ______________________________ _________ ________ ________ ______________________________ _________ ________ ________ ______________________________ _________ ________ ________ Performed by: Date: Time:

DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST STP NS13C012SBGTB Page 10 of 11 Rev. 3 Performance Date: ___________________ INITIALS 8.0 ACCEPTANCE CRITERIA 8.1 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"): 8.2 All items checked in this test have been performed satisfactorily: 8.2.1 Section 7.1 ( ) YES ( ) NO CRS notified ________ 8.3 Indicate any relevant test comments below, otherwise mark this step "N/A": ________________________________________ _______________ Mechanical Maintenance Supervisor Date ________________________________________ _______________ Fire Protection System Engineer Date ________________________________________ _______________ Surveillance Coordinator Date

9.0 ATTACHMENTS

9.1 Attachment 1 - Post-STP Completion Checklist (Standby Gas Treatment "B" Charcoal Bed Deluge System) DAEC DUANE ARNOLD ENERGY CENTER SURVEILLANCE TEST PROCEDURE TITLE: CHARCOAL BED DELUGE SYSTEMS FUNCTIONAL TEST STP NS13C012SBGTB Page 11 of 11 Rev. 3 Attachment 1 POST-STP COMPLETION CHECKLIST Sheet 1 of 1 STANDBY GAS TREATMENT "B" CHARCOAL BED DELUGE SYSTEM Valve Number Valve Location Valve Description Valve Position Initial (IV) V-58-43 1V-SGT-1B "B" SBGT CARBON BED DELUGE SUPPLY HDR DRAIN CL / CAP Installed Signature of Individual Performing Verification: ______________________________________ CRS Verification Completion Approval: _____________________________ Date: __________

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 1 of 24 Usage Level: Information Use Approved for

'Point-of-Use' printing IF NO Temporary Changes are in effect for this procedure.

Record the following: Date / Time: _____________ / _________ Initials: ____ NOTE: A check to ensure current revision and no temporary changes shall be performed and documented every 24 hours if active document use exceeds a 24 hour period as determined from the date and time recorded above. Prepared By:

  / 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   

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 2 of 24

1.0 PURPOSE

(1) The purpose of this procedure is to provide supplemental site instructions to meet the requirements of OP-AA-102-100, Guarded Equipment. (a) DAEC uses an additional method of guarding equipment. Not only is equipment guarded to prevent inadvertent work, meeting the requi rements of OP-AA-102-1003, but equipment is guarded to maintain configuration control; preventing inadvertent contact. (2) DAEC uses an additional level of risk management by also identifying protected trains. This procedure defines the term and requirements for protected trains. 

2.0 DEFINITIONS

Limiting Conditions for Operation (LCO) - Specific minimum levels of system performance necessary to assure safe operation of the facility. When these conditions are met the plant can be operated safely and abnormal situations can be safely controlled.

Guarded Equipment - Equipment posted as Protected. See OP-AA-102-1003 Guarded Equipment. This equipment shall be identified in a tracking log. Signs, postings, tags, and/or barriers shall be placed at the equipment and/or control points to alert personnel of the designation. Equipment barriers are required to be robust in order to prevent inadvertent contact.

ATTACHMENT 1, Recommended Guarded Equipment provides suggested systems and equipment to Guard or uniquely identify, as designated by the OSM/CRS. The following criteria were used in determining which systems/components to list in ATTACHMENT 1: ORAM Sentinel - Protect all systems that are "red" on the Remain In Service tab. Tech Specs - Protect all systems that would result in a TS 3.0.3 or <24 hour shutdown action statement. Support/Supported Systems - Protect the major systems that support or are supported by the above systems. Power Production - Protect those systems/components that could cause the plant to shutdown or reduce power. Miscellaneous - Protect systems with other special reasons or circumstances. As required by OP-AA-104-1010 (DAEC) for Spent Fuel Pool

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 3 of 24 Protected Train - Redundant train(s) or system(s) protected for scheduled or on-going work. Signs, postings, tags, and/or barriers are not posted to alert personnel of the designation. Protected train designations are communicated in the work week plan and are typically maintained for an entire work week. Divisional Train Categories: A: "A" Train and Div 1 systems and components; components powered by Div 1 power supplies B: "B" Train and Div 2 systems and components; components powered by Div 2 power supplies C: Single train systems (e.g., HPCI, RCIC); Systems that involve both Div 1 and Div 2 (e.g., LPCI Swing Bus) Not Divisionalized: Systems and components that do not meet a divisional screening criteria Risk Significant System - Those systems that would have a significant effect on Core Damage Frequency (CDF) or Large-Early Release Frequency (LERF) when removed from service. Risk significant systems are identified in Attachments 3 and 4 of Maintenance Rule Program Module 0. Systems or components that are not risk signi ficant per ORAM-Sentinel and do not support an ORAM-Sentinel risk significant component are marked with a % symbol in Attachment 1 of this procedure. Uniquely Identified to Prevent Inadvertent Work - A method of identifying active components, power supplies, and/or areas associated with Fuel Pool Cooling (using signs, postings, placards, etc.) intended to prevent inadvertent on or near equipment required to provide or support the in-service train of Fuel Pool Cooling. The method utilized need not be "robust", but must be conspicuous enough so a casual observer will not miss them. These signs are intended to inform a person that the "Time to 200 deg F" for the Spent Fuel Pool is less than 72 hours, and that work should not be performed on such equipment without OSM permission. OSM permission for routine entries not involving work on the equipment, such as Operator or Security rounds and Radiation Protection surveys, is not required. Any actual work on these components or within these areas requires that specific management controls be established in accordance with WM-AA-1000, Work Activity Risk Management and OP-AA-104-1010, Spent Fuel Risk Management Guideline. ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 4 of 24

3.0 INSTRUCTIONS

3.1 RESPONSIBILITIES (1) Operations Supervision (OSM, CRS, WCCS) is responsible for: (a) Ensuring that no activities are permitted which will adversely impact protected trains or guarded equipment. (b) Ensuring requirements for guarded equipment are met per OP-AA-102-1003 and OP-AA-102-1003 (DAEC). (c) Ensuring NG-229K, Protected Train / Guarded Equipment Work Approval Form is complete to allow work on equipment that is part of a Protected Train or to work within a Guarded Equipment boundary. Refer to the last two pages of Attachment 1 for work that may be performed without the use of NG-229K. (d) Ensuring barriers put in place prevent inadvertent contact of the guarded equipment. (2) The Work Week Managers are responsible for: (a) Communicating which train will be protected during the work week as part of the work week plan. (b) Recommending the systems to be guarded using ATTACHMENT 1, Recommended Guarded Systems. (3) The Shift Technical Advisor (STA) is responsible for: (a) Ensuring the requirements for "guarded equipment" are met per OP-AA-102-1003 (DAEC). (b) Ensuring barriers put in place prevent inadvertent contact of the guarded equipment. (4) Maintenance Team Leaders/Support Department Supervisors are responsible for: (a) Ensuring that those activities within their functional area receive priority attention and are completed per this procedure in support of the schedule. (b) Initiate NG-229K, Protected Train / Guarded Equipment Work Approval Form to work on components on a protected train or to access equipment within a guarded equipment

boundary. ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 5 of 24 3.2 GUARDED EQUIPMENT The primary means to protect systems is to ens ure that redundant equipment is not removed from service and inadvertent contact is not made with the guarded equipment. (1) Operations Supervision will make the determination as to which equipment or areas to guard using ATTACHMENT 1, Recommended Guarded Equipment and OP-AA-102-1003, Guarded Equipment. Additional equipment or areas may be guarded at the discretion of Operations

Supervision. (a) For guarded equipment, the barriers put into place not only have to prevent inadvertent work, but also to prevent inadvertent contact with the guarded equipment. (2) Guarded equipment shall be logged on the Guarded Equipment Log. Use guarded system barriers as necessary in the areas that are determined to be posted as guarded. Typical means for guarding equipment include: Placing Guarded Equipment Tensa Barriers to block access to guarded equipment. Posting a Guarded Equipment sign on a door blocking access to guarded equipment. Using Guarded Equipment stanchions to prevent access to guarded equipment. Using rope with a Guarded Equipment sign to prevent access to guarded equipment.

(3) Guarded Equipment in the plant that has controls or indications in the Control Room is typically identified by hanging or attaching a purple Guarded Equipment or Protected System tag to the controls or indications. Only one tag is used for each major component or system. (4) Guarded Equipment areas shall be monitored at a periodicity determined by Operations Supervision to ensure that no unauthorized work is being performed. (5) At the discretion of Operations Supervision, guarded equipment area boundaries may be moved to allow work on a piece of equipment that is not guarded, as long as the equipment which is to be guarded remains clearly posted. 3.3  WORK ON A PROTECTED TRAIN (1) Whenever work on a component that is part of a protected train is required, an NG-229K, Protected Train / Guarded Equipment Work Approval Form shall be used. (a) The Protected Train / Guarded Equipment Work Approval Form is initiated by the organization requesting to perform the work. (b) The form is reviewed and approved by the OSM. (c) The workers are briefed by the OSM and any contingencies are discussed.

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 6 of 24 (d) A copy of the Protected Train / Guarded Equipment Work Approval Form is maintained at the job site and by the OSM. (e) When work is complete, the form is returned to the OSM. Forms for completed work may be discarded. 3.4 WORK WITHIN A GUARDED EQUIPMENT BOUNDARY (1) Whenever work within a guarded equipment boundary is required, an NG-229K, Protected Train/Guarded Equipment Work Approval Form shall be used. (a) The Protected Train/Guarded Equipment Work Approval Form is initiated by the organization requesting to perform the work. (b) The form is reviewed and approved by the OSM. (c) The workers are briefed by the OSM and any contingencies are discussed. (d) The cognizant work activity supervisor provides continuous oversight of work within a guarded equipment boundary, unless exempted by the OSM and documented on NG-229K, Protected Train/Guarded Equipment Work Approval Form. (e) Operations Supervision provides periodic monitoring of the work within a guarded equipment boundary. (f) A copy of the Protected Train / Guarded Equipment Work Approval Form is maintained at the job site and by the OSM. (g) When work is complete, the form is returned to the OSM. Forms for completed work may be discarded. 3.5 PRE-APPROVED EXEMPTIONS (1) The following is a list of pre-approved exemptions to the above requirements. Personnel utilizing these exemptions may access Protected Train or Guarded Equipment areas without requesting Shift Manager permission prior to each entry and without completing an NG-229K,

Protected Train / Guarded Equipment Work Approval Form. (Additional exemptions are defined in OP-AA-102-1003, Guarded Equipment.) Operator rounds, inspections, and alarm/event response. (No work activities or tagging.) Security Officer rounds or alarm/event response. Fire Patrols Fire Brigade and Medical Response Team emergency response. ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 7 of 24 Personnel assigned to perform Abnormal Operating Procedures/Emergency Operating Procedures/Emergency Plan actions. Radiation Protection personnel responding to radiation alarms/changing plant conditions, as assigned by the on-shift Operating crew. 3.6 EMERGENT AND FILL-IN WORK ACTIVITIES (1) When a particular system or train of a system is made or found to be unavailable, the redundant train(s) or system(s) should be guarded. ATTACHMENT 1, Recommended Guarded Equipment should be used to determine which system(s) to guard. OP-AA-102-1003, Guarded Equipment, provides additional guidance. (2) The evaluation to protect the redundant train(s) or system(s) shall include: the consequences of worker error that may cause the loss of system or train function the consequences of worker error that may induce a transient which is normally mitigated by the system out of service the impact of alterations to the system or train on plant safety functions, including use of lifted leads or jumpered terminals or use of temporary shielding, scaffolding, blocks, bypasses, or supports the impact of emergent conditions internal to the facility such as mode changes, electrical or valve lineup changes, or additional plant equipment out of service due to failures the impact of emergent conditions external to the facility such as adverse weather, rising river water level, or degraded offsite power availability . (3) For the associated Guarded Equipment fill-in or emergent work which presents a reasonable potential to cause a loss of system or train function should not be authorized.

4.0 RECORDS

(1) None ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC)

PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 8 of 24

5.0 REFERENCES

(1) OP-AA-102-1003 Guarded Equipment. (2) WPG-2, On-Line Risk Management Guideline (3) ACP 1408.1, Work Orders (4) NG-229K, Protected Train / Guarded Equipment Work Approval Form (5) OTH042772 (6) SOER 09-01, PCR054146, CA053230 

(7) CA393246 (8) CR 1609054 (9) RWA 1601986 (10) RWA 1619764 (11) CA01652011-01 (12) OP-AA-104-1010, Spent Fuel Risk Management Guideline (13) IER-11-002, recommendation 2 (14) CR 1737595 / CE 1737595-01

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 9 of 24 ATTACHMENT 1 Page 1 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 1.00/161/345 KV Switchyard T1 Transformer (Note 8) Startup Transformer, "A" & "B" DG, "A" & "B" ESW, 1A3, 1A4, HPCI, RCIC, 1VAC14A or B, 1VAC15A or B XR1 LLRPSF Transformer (Note 7) None XR2 LLRPSF Transformer None 345KV East Bus - CB4730 None 345KV West Bus - CB2820, CB0710 None 161KV East Bus - CB2690, CB5550, CB8090, CB9180, CB0220 CB4290 (only when CB0220 is OOS) 161KV West Bus - CB6780, CB5560, CB7510, CB4290, CB3110, CB5950 CB0220 (only when CB4290 is OOS) CB5550 (J) Bkr CB5560 CB5560 (K) Bkr CB5550 CB8490 M Breaker to S/B Transformer (Note 8) Startup Transformer, "A" & "B" DG, "A" & "B" ESW, 1A3, 1A4 CB5940 161 West to LLRWSF None CB5960 36KV to Offsite Line None CB5980 36KV to XR1 None CB5990 36KV to XR2 None T3, 161KV-36KV DAEC LLRPSF XMFR CB5960 36KV Offsite Supply Bus Breaker, SW5981 36KV Offsite Supply Bus Disconnect, SW5991 36KV DAEC LLRPSF XFMRS SUP Cross-Tie Disconnect 2.00/125VDC 1D1 Battery 1D2, 1D4, "B" ESW, "B" DG, 1A4, "B" RWS, HPCI, "B" SGT, "B" SFU, 1D40, 1D41, 1D43, 1D44 (In service charger only), 1VAC14A or B %1D10 Distribution Panel 1D20, 1D21, 1D23, "B" SGT, "B" SFU, HPCI, 1D4, 1D40, 1D41, 1D43, 1D44 (In service charger only), 1VAC14A or B 1D12 Charger 1D22, 1D120 STP 3.8.4-06A, 1D12 125VDC Battery Charger Capacity Test Same as 1D12 1D120 Swing Charger 1D12, 1D22 STP 3.8.4-06C, 1D120 125VDC Battery Charger Capacity Test Same as 1D120 1D2 Battery (Note 1) 1D1, 1D4, "A" ESW, "A" DG, 1A3, "A" RWS, RCIC, "A" SGT, "A" SFU, 1D12, 1D120, 1VAC15A or B %1D20 Distribution Panel 1D10, 1D11, 1D13, "A" SGT, "A" SFU 1D22 Charger 1D12, 1D120 STP 3.8.4-06B, 1D22 125VDC Battery Charger Capacity Test Same as 1D22 Notes: 1: "B" RHR Loop, "A" Condensate Pump, and Startup Transformer not included from the ORAM-Sentinel Remain In Service tab due to PRA over simplification explained in CAP 32466 and OTH 1672. 7: When XR1 LLRPSF Transformer is removed from service, 'B' Well power supply is removed. "B" Well must be considered Unavailable and Inoperable. 8: When either the Startup Transformer or Standby Transformer are removed from service for maintenance, switchyard access should be restricted and work boundaries established by ropes and signs to protect the transformer switchyard power feeds to the operating transformer. % Not risk significant per ORAM-Sentinel and does not support an ORAM-Sentinel risk significant component. ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 10 of 24 ATTACHMENT 1 Page 2 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 3.00/Startup Transformer Startup Transformer 1X003 (Note 8) Standby Transformer, T1 Auto Transformer, "A" & "B" DG, "A" & "B" ESW, 1A3, 1A4, "A" & "B" RWS, HPCI, RCIC, 1VAC14A or B, 1VAC15A or B 4.00/4160 VAC Switchgear 1XR004 "B" Well Transformer None %1A1 Non-Essential Bus None %1A2 Non-Essential Bus None %1A3 Essential Bus "B" DG, 1A4, "B" ESW, 1B4, 1B42, 1B44 %1A4 Essential Bus "A" DG, 1A3, "A" ESW, 1B3, 1B32, 1B34 1A102 S/U to 1A1 None 1A202 S/U to 1A2 None 1A301 S/B to 1A3 "B" DG, 1A4, "B" ESW, 1B4, 1B42, 1B44 1A401 S/B to 1A4 "A" DG, 1A3, "A" ESW, 1B3, 1B32, 1B34 1A311 1A3 to 'A' Diesel Same as "A" DG 1A411 1A4 to 'B' Diesel Same as "B" DG 5.00/480 VAC Volt Switchgear 1B02 None 1B03 "B" DG, 1A4, Startup Transformer, "B" ESW, "B" RHR & RHRSW, "B" RHR Torus Return Valves, 1D22, 1D120, 1B4, 1B42, 1B44, 1VAC011 1B04 (Note 2) "A" DG, 1A3, Startup Transformer, "A" ESW, "A" RHR & RHRSW, "A" RHR Torus Return Valves, 1D12, 1D120, 1B3, 1B32, 1B34, 1VAC012 1B09 "B" RWS, "B" DG, Startup Transformer, "B" ESW, 1A4, 1B20 1B20 (Note 3) "A" RWS, "A" DG, Startup Transformer, "A" ESW, 1A3, 1B9 1BR91 None 1BR92 None Notes: 2: "B" DG, "B" ESW, "B" RWS "A" RWS, Drywell Vent, HPCI, RCIC, "B" & "C" GSW, "A" Chiller, 1VAC030A, Condensate Storage Tanks, "D" Well not included from the ORAM-Sentinel Remain In Service tab due to PRA over simplification explained in CAP 32466 and OTH 1672. 3: "B" Loop RHR not included from the ORAM-Sentinel Remain In Service tab due to PRA over simplification explained in CAP 32466 and OTH 1672. % Not risk significant per ORAM-Sentinel and does not support an ORAM-Sentinel risk significant component. ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 11 of 24

ATTACHMENT 1 Page 3 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 6.00/480 VAC Motor Control Center LPCI Swing Bus "A" & "B" Core Spray Subsystems, "A" & "B" ESW, "A" & "B" DG, 1A3, 1A4, "A" & "B" RWS, 1VAC011, 1VAC012, 1B3401 1B34 to LPCI Swing Bus Same as Swing Bus 1B4401 1B44 to LPCI Swing Bus Same as Swing Bus STP 3.8.7-01, LPCI Swing Bus AC and DC Undervoltage Transfer Test Same as for 1B34A, 1B44A; LPCI Swing Bus %1B21 (Note 5) 1B22 None 1B32 "B" DG, 1A4, Startup Transformer, "B" ESW, "B" RHR & RHRSW, 1D22, 1D120, 1B4, 1B42, 1B44,

1VAC011 1B33 None 1B34 "B" ESW, "B" RHR & RHRSW, "B" RHR Torus Return Valves, "B" DG, 1A4, 1B4, 1B42, 1B44, 1VAC011 1B35 None 1B42 (Note 2) "A" DG, 1A3, Startup Transformer, "A" ESW, "A" RHR & RHRSW, 1D12, 1D120, 1B3, 1B32, 1B34,

1VAC012 1B43 None 1B44 (Note 4) "A" DG, "A" ESW, "A" RHR & RHRSW, "A" RHR Torus Return Valves, 1A3, 1B3, 1B32, 1B34, 1VAC012 1B45 None %1B91 (Note 5) Notes: 2: "B" DG, "B" ESW, "B" RWS "A" RWS, Drywell Vent, HPCI, RCIC, "B" & "C" GSW, "A" Chiller, 1VAC030A, Condensate Storage Tanks, "D" Well not included from the ORAM-Sentinel Remain In Service tab due to PRA over simplification explained in CAP 32466 and OTH 1672. 4: "B" DG, "B" ESW, "B" RWS, Startup Transformer, Drywell Vent, HPCI, RCIC 1D120, Condensate Storage Tanks, "A" SLC, CV4300, Torus Vent, Torus Vent Valve Air/Nitrogen Accumulator, "A" RWS, 1L80 not included from ORAM-Sentinel Remain In Service tab due to PRA over simplification explained in CAP 32466 and OTH 1672. 5: Removing 1B91 ("A" River Water Bus) or 1B21 ("B" River Water Bus) from service makes the respective subsystem of River Water UNAVAILABLE due to the temperature alarms as explained in OTH37270 and CAP 45839. % Not risk significant per ORAM-Sentinel and does not support an ORAM-Sentinel risk significant component.

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 12 of 24

ATTACHMENT 1 Page 4 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 7.00/Lighting Panel Power Supply - Panel 1L80 Lighting Panel Power Supply - Panel 1L80 None 8.00/Well Water "A" Pump None "B" Pump None "C" Pump None "D" Pump None 1XR004 "B" Well Transformer See SUS04.00 1X092 "D" Well Transformer None 9.00/Intake & Traveling Screens %"A" Intake and Traveling Screens - 1F036A 1F036B, 1P112B, MO2903, "B" RWS %"B" Intake and Traveling Screens - 1F036B 1F036A, 1P112A, MO2902, "A" RWS 10.01/River Water Supply "A" RWS Pump None "B" RWS Pump None "C" RWS Pump None "D" RWS Pump None "A" RWS Loop "B" RWS, "B" ESW, "B" DG, 1A4, Startup Transformer "B" RWS Loop (Note 3) "A" RWS, "A" ESW, "A" DG, 1A3, Startup Transformer 10.02/Screen Wash %"A" Screen Wash - 1P112A, MO2902 1F036B, 1P112B, MO2903, "B" RWS %"B" Screen Wash - 1P112B, MO2903 1F036A, 1P112A, MO2902, "A" RWS 10.03/Intake HVAC %"A" Intake Structure HVAC - 1VSF050 1VSF051, "B" RWS, "B" ESW, "B" DG, 1A4 %"B" Intake Structure HVAC - 1VSF051 1VSF050, "A" RWS, "A" ESW, "A" DG, 1A3 11.01/General Service Water "A" GSW "B" & "C" GSW "B" GSW "A" & "C" GSW "C" GSW "A" & "B" GSW 11.03/Pumphouse ESW/RHRSW Room HVAC "A" ESW/RHRSW HVAC - 1VSF056A 1VSF056B, "B" ESW, "B" Loop RHRSW, "B" DG, 1A4, "B" Chiller, 1K4, 1VAC030B "B" ESW/RHRSW HVAC - 1VSF056B 1VSF056A, "A" ESW, "A" Loop RHRSW, "A" DG, 1A3, "A" Chiller, 1K3, 1VAC030A Notes: 3: "B" Loop RHR not included from the ORAM-Sentinel Remain In Service tab due to PRA over simplification explained in CAP 32466 and OTH 1672. % Not risk significant per ORAM-Sentinel and does not support an ORAM-Sentinel risk significant component. ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 13 of 24

ATTACHMENT 1 Page 5 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 13.01/Fire Protection Diesel Fire Pump EFP Electric Fire Pump DFP STP NS13C012, Charcoal Bed Deluge System Functional and Air Flow Tests See "A" or "B" SFU or "A" or "B" SBGT as applicable 14.00/Reactor Bldg. Closed Cooling Water "A" Pump None "B" Pump None "C" Pump None "A" Heat Exchanger None "B" Heat Exchanger None "C" Heat Exchanger None 16.00/RHRSW "A" RHRSW Pump None "B" RHRSW Pump None "C" RHRSW Pump None "D" RHRSW Pump None "A" Loop RHR Service Water "B" ESW, "B" RWS, "B" Loop RHRSW, "B" DG, 1A4 "A" RHRSW Heat Exchanger - MO2046 "B" ESW, "B" RWS, "B" Loop RHRSW, "B" DG, 1A4 %"A" ESW/RHRSW Pit Same as "A" Loop RHR Service Water and "A" ESW "B" Loop RHR Service Water "A" ESW, "A" RWS, "A" Loop RHRSW, "A" DG, 1A3 "B" RHRSW Heat Exchanger - MO1947 "A" ESW, "A" RWS, "A" Loop RHRSW, "A" DG, 1A3 %"B" ESW/RHRSW Pit Same as "B" Loop RHR Service Water and "B" ESW 17.00/Instrument AC Static Inverter - 1D15 1Y1A, 1Y15 Reg. Transformer - 1Y1A 1D15, 1D1, 1D10 Transformer - 1Y1 None Static Inverter - 1D25 1Y2A, 1Y25 Reg. Transformer - 1Y2A 1D25, 1D2, 1D20 Transformer - 1Y2 None ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 14 of 24

ATTACHMENT 1 Page 6 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 19.01/Service Air System Compressor 1K001 1K090A, 1K090B, 1K090C Compressor 1K090A 1K090B, 1K090C, 1K001 Compressor 1K090B 1K090A, 1K090C, 1K001 Compressor 1K090C 1K090A, 1K090B, 1K001 Cooling Pump - 1P278A 1P278B Cooling Pump - 1P278B 1P278A 23.00/Diesel Oil System %Diesel Oil System Same as SUS 24.01 if affects single DG 24.01/Standby Diesel Generators "A" DG (1G31) "B" ESW, "B" RWS, "B" DG, 1A4, 1X3 Startup Transformer, "B" Chiller, 1K4, 1VAC030B, "B" Core Spray, HPCI, 1VAC011, 1VAC14A or B STP 3.8.1-04A, SBDG Operability Test (Slow Start from Normal Start Air)* Same as for "A" DG STP 3.8.1-05A, SBDG Operability Test (Slow Start from Emergency Start Air)* Same as for "A" DG STP 3.8.1-06A, SBDG Operability Test (Fast Start)* Same as for "A" DG "B" DG (1G21) "A" ESW, "A" RWS, "A" DG, 1A3, 1X3 Startup Transformer, "A" Chiller, 1K3, 1VAC030A, "A" Core Spray, HPCI, 1VAC012, 1VAC14A or B STP 3.8.1-04B, SBDG Operability Test (Slow Start from Normal Start Air)* Same as for "B" DG STP 3.8.1-05B, SBDG Operability Test (Slow Start from Emergency Start Air)* Same as for "B" DG STP 3.8.1-06B, SBDG Operability Test (Fast Start)* Same as for "B" DG 24.02/Emergency Power Emergency Power Same as SUS 24.01 for the associated DG 24.03/DG HVAC

%"A" DG HVAC - 1VSF020 Same as for "A" DG %"B" DG HVAC - 1VSF021 Same as for "B" DG 25.00/Remote Shutdown STP 3.3.3.2-02, RSP Functional Test for Division 2 Switchgear and B SBDG See "B" DG STP 3.3.3.2-03, RSP Functional Test for Core Spray and Instrumentation Same as for "B" Core Spray for applicable sections STP 3.3.3.2-04, Remote Shutdown Panel Functional Test for RHR Same as for the applicable "B" Loop RHR components for the corresponding applicable sections of the STP and 1B34A, 1B44A, LPCI Swing Bus % Not risk significant per ORAM-Sentinel and does not support an ORAM-Sentinel risk significant component.

• Remains Available in ORAM-Sentinel for STP.

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 15 of 24 ATTACHMENT 1 Page 7 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 30.00/Control Bldg HVAC "A" Control Bldg HVAC - 1VAC30A 1VAC30B, "B" Chiller, "B" ESW, "B" DG, 1A4, 1K4 "B" Control Bldg HVAC - 1VAC30B 1VAC30A, "A" Chiller, "A" ESW, "A" DG, 1A3, 1K3 30.01 & 30.02/Contol Building Chillers "A" Control Bldg Chiller 1VAC30B, "B" Chiller, "B" ESW, "B " DG, 1A4, 1K4 "B" Control Bldg Chiller 1VAC30A, "A" Chiller, "A" ESW, "A " DG, 1A3, 1K3 30.03 & 30.04/CB/SBGT Instrument Air System

%"A" CB/SBGT Instrument Air System -

1K003 1VAC30B, "B" Chiller, "B" ESW , "B" DG, 1A4, 1K4, "B" SGT, "B" SFU %"B" CB/SBGT Instrument Air System - 1K004 1VAC30A, "A" Chiller, "A" ESW , "A" DG, 1A3, 1K3, "A" SGT, "A" SFU 30.05 & 30.06/Standby Filter Unit

%"A" Standby Filter Unit  "B" SFU, "B" ESW, "B" DG, 1A4, 1K4 % "B" Standby Filter Unit  "A" SFU, "A" ESW, "A" DG, 1A3, 1K3 %STP 3.7.4-02, Main Control Room Ventilation Standby Filter Unit Test See "A" or "B" SFU as applicable 33.00/Turbine Building HVAC 1VAC020 None 34.00/Reactor Building HVAC CRD Room Cooler - 1VAC013A None CRD Room Cooler - 1VAC013B None HPCI Room Cooler - 1VAC014A 1VAC014B, 'B' ESW, 'B' DG, 1A4 HPCI Room Cooler - 1VAC014B 1VAC014A, 'A' ESW, 'A' DG, 1A3 RCIC Room Cooler - 1VAC015A 1VAC015B RCIC Room Cooler - 1VAC015B 1VAC015A %SECR Cooler - 1VAC012 "B" RHR loop, "B" Core Spray, 1VAC011, "B" DG, "B" ESW, 1A4, HPCI, 1VAC14A or B %NWCR Cooler - 1VAC011 "A" RHR loop, "A" Core Spray, 1VAC012, "A" DG, "A" ESW, 1A3, HPCI, 1VAC14A or B % Not risk significant per ORAM-Sentinel and does not support an ORAM-Sentinel risk significant component. 

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 16 of 24 ATTACHMENT 1 Page 8 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 35.00 Fuel Pool Cooling Spent Fuel Pool TT200 <72 hours (Note 9) Uniquely identify in-service components/areas: Fuel Pool Cooling Pump, Skimmer Surge Tank Room*, 1B35, 1B43 Spent Fuel Pool TT200 <72 hours AND redundancy does not exist (Note 10) In-service components/areas: Fuel Pool Cooling Pump, Skimmer Surge Tank Room*, RBCCW pump, GSW pump, 1B35, 1B43, 1A2, 1A3, 1A4. Also guard at least 1 SFP makeup source identified in AOP-435 (such as a Condensate Service Water Pump, ESW Pump, Fire Pump, etc. and associated power supply). 37.00/CSTs CSTs N/A 42.00/Circ Water "A" Circ Pump "B" Circ Pump "B" Circ Pump "A" Circ Pump 44.00/Condensate "A" Condensate Pump "B" Condensate Pump "B" Condensate Pump "A" Condensate Pump 45.01/Feedwater "A" Feed Pump "B" Feed Pump, RCIC, HPCI "B" Feed Pump "A" Feed Pump, RCIC, HPCI 45.02/Feedwater Control

%"A" FRV "B" FRV %"B" FRV "A" FRV Notes:

• SOER 09-01 identified the need to protect the Skimmer Surge Tank low water level switch that can trip both Fuel Pool Cooling Pumps. Protecting the Skimmer Surge Tank room will accomplish this as well as protect the Fuel Pool Cooling Pumps. 9: Any time Spent Fuel Pool time to reach 200 deg F upon loss of normal cooling is less than 72 hours, then the in-service Fuel Pool Cooling Pump and associated MCC shall be uniquely identified (refer to "Definitions" section of this procedure) to prevent inadvertent work on or near required equipment. 10: Any time Spent Fuel Pool time to reach 200 deg F upon loss of normal cooling is less than 72 hours, AND the level of redundancy is reduced such that a single failure could result in a loss of Spent Fuel Cooling capability, then the in-service Fuel Pool Cooling Pump and associated MCC, 1 in-service RBCCW Pump and associated MCC, 1 in-service GSW Pump and associated 4160 bus, and at least 1 Spent Fuel Pool makeup source (identified in AOP-435, Loss of Spent Fuel Cooling) shall be guarded in accordance with this procedure and with fleet procedure OP-AA-102-1003.

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 17 of 24

ATTACHMENT 1 Page 9 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 49.00/RHR "A" RHR Pump - 1P229A, MO2011, MO2012, V20-0003, V20-0004 None "B" RHR Pump - 1P229B, MO1912, MO1913, V19-0003, V19-0004 None "C" RHR Pump - 1P229C, MO2015, MO2016, V20-0001, V20-0002 None "D" RHR Pump - 1P229D, MO1920, MO1921, V19-0001, V19-0002 None "A" LPCI Inject - MO2003, MO2004 "A" & "B" Core Spray, "A" & "B" ESW, "A" & "B" DG, 1A3, 1B3, 1A4, 1B4, 1B34, 1B44 1VAC011, 1VAC012 "B" LPCI Inject - MO1904, MO1905 "A" & "B" Core Spray, "A" & "B" ESW, "A" & "B" DG, 1A3, 1B3, 1A4, 1B4, 1B34, 1B44, 1VAC011, 1VAC012 "A" RHR HX - 1E201A, MO2029 & MO2031 won't open, MO2030 won't close "B" ESW, "B" RHRSW, "B" DG, 1A4, 1B4, 1B44 "B" RHR HX - 1E201B, MO1939 & MO1941 won't open, MO1940 won't close "A" ESW, "A" RHRSW, "A" DG, 1A3, 1B3, 1B34 "A" RHR Torus Clg Suction - MO2069 (Note 6) "B" ESW, "B" DG, 1A4, "B" Loop RHR, 1VAC011, 1B4, 1B44, "B" RHRSW "A" RHR Torus Clg Return - MO2005, MO2007 None "B" RHR Torus Clg Suction - MO1989 "A" ESW, "A" DG, 1A3, "A" Loop RHR, 1VAC012, 1B3, 1B34 "A" RHRSW "B" RHR Torus Clg Return - MO1932, MO1934 None MO2010 LPCI Crosstie Same as LPCI Swing Bus LPCI Subsystem Same as LPCI Swing Bus Common SDC Suction - MO1908, MO1909, V19-0148 None RHRSW to RHR Crosstie - MO1942 None "A" Drywell Spray - MO2000, MO 2001 None "B" Drywell Spray - MO1902, MO1903 None STP 3.3.5.1-29, Containment Spray LSFT Same as LPCI Swing Bus STP 3.3.5.1-37, RHR LSFT-Operating Same as LPCI Subsystems STP 3.5.1-04, LPCI Simulated Automatic Actuation "A" & "B" ESW, "A" & "B" RHRSW, "A" & "B" DG, 1A3, 1A4, "A" & "B" Core Spray Subsystems, 1VAC011, 1VAC012, 1B3, 1B4, 1B34, 1B44 STP 3.3.6.1-09, Primary Containment Isolation, Groups 2 and 4, Logic System Functional Test

"A" Same as "A" LPCI Inject - MO2003 STP 3.3.6.1-09, Primary Containment Isolation, Groups 2 and 4, Logic System Functional Test "B" Same as "B" LPCI Inject - MO1904 Notes: 6: "B" Loop RHR is added because this combination is just below the cutoff to the next higher action level and to be consistent with the "B" RHR Torus Cooling Suction. ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 18 of 24

ATTACHMENT 1 Page 10 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 50.00/Reactor Core Isolation Cooling RCIC HPCI, 1VAC14A or B, 1D4, 1D40, 1D41, 1D43, 1D44 (In service charger only), 1D2, 1D20, 1D21, 1D22, 1D23, Startup Transformer STP 3.5.3-04, RCIC Simulated Automatic Actuation Test Same as for RCIC 51.00/Core Spray "A" Core Spray NWCR ("B" and "D" RHR pumps, "B" Core Spray pump, 1VAC011), "B' SBDG, "B" ESW, 1A4, 1B4, 1B44 "B" Core Spray SECR ("A" and "C" RHR pumps, "A" Core Spray pump, 1VAC012), "A" SBDG, "A" ESW, 1A3, 1B3, 1B34 STP 3.3.5.1-14, Core Spray Logic System Functional Test *Same as for Core Spray system being tested. STP 3.5.1-03 Core Spray Simulated Automatic Actuation See "A" DG & "A" Core Spray or "B" DG & "B" Core Spray as applicable 52.00/High Pressure Coolant Injection HPCI RCIC, 1D1, 1D10, 1D13, 1D14, 1D12 OR 1D120 (in service charger only), 1VAC015A or B, "A" SBDG,. "A" ESW, 1VAC012, 1A3, 1B3, 1B34, "B" SBDG, "B" ESW, 1VAC011, 1A4, 1B4, 1B44, Startup Transformer, ADS Div 1, ADS Div 2, SRV4400, SRV 4402, SRV4405, SRV4406 (Note 11) STP 3.5.1-07, HPCI System Simulated Automatic Actuation Same as for HPCI 53.00/Standby Liquid Control "A" SLC Subsystem "B" SLC Subsystem "B" SLC Subsystem "A" SLC Subsystem STP 3.1.7-01, SBLC Pump Operability Test None STP 3.1.7-02, SBLC System Initiation and Explosive Valve Test None STP 3.1.7-04, SBLC Pump Operability Test And Comprehensive Pump Test None 54.00/Emergency Service Water "A" ESW "B" ESW, "B" RWS, "B" DG, "B" RHR loop, "B" RHRSW, "B" Chiller, 1K4, 1VAC030B, 1A4, Startup Transformer, "B" Core Spray, HPCI, 1VAC011, 1VAC14A or B "B" ESW (Note 3) "A" ESW, "A" RWS, "A" DG, "A" RHR loop, "A" RHRSW, "A" Chiller, 1K3, 1VAC030A, 1A3, Startup Transformer, "A" Core Spray, HPCI, 1VAC012, 1VAC14A or B 55.00/CRD Hydraulic "A" CRD Pump "B" CRD Pump "B" CRD Pump "A" CRD Pump 57.00/Uninteruptible AC Static Inverter - 1D45 1Y4 Regulating Transformer - 1Y4 1D45, 1D4, 1D40 Notes: 3: "B" Loop RHR not included from the ORAM-Sentinel Remain In Service tab due to PRA over simplification explained in CAP 32466 and OTH 1672. 11: ADS added to list of guarded equipment for HPCI being inoperable to address concern identified in CR 1737307. % Not risk significant per ORAM-Sentinel and does not support an ORAM-Sentinel risk significant component. ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 19 of 24

ATTACHMENT 1 Page 11 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 58.01/Reactor Protection System ARI Div. 1 ARI Div. 2 ARI Div. 2 ARI Div. 1 "A" RPS Trip Logic - 1G051 1C55, 1C55A, 1C56, 1C56A "B" RPS Trip Logic - 1G061 1C55, 1C55A, 1C56, 1C56A 58.02/Nuclear Steam Supply Shutoff System STP 3.3.6.1-10, Reactor LoLo Water Level (ATWS-RPT/ARI) and LoLoLo Water Level (Main Steam Line Isolation trip) Channel

Calibration (Note 13) None STP 3.3.6.1-11, Reactor LoLo Water Level (ATWS-RPT/ARI) and LoLoLo Water Level (Main Steam Line Isolation trip) Channel Functional (Note 13) None 59.00/Primary Containment RCIC STP 3.3.6.1-42, RCIC System Isolation Logic System Functional Test Same as for RCIC 60.00/Primary Containment HVAC "A" Loop Drywell Cooling "B" Loop Drywell Cooling "B" Loop Drywell Cooling "A" Loop Drywell Cooling 64.01/Reactor Vessel Recirculation ATWS-RPT, Div 1 ATWS-RPT, Div. 2 ATWS-RPT, Div 2 ATWS-RPT, Div. 1 STP 3.3.4.2-01, ATWS-RPT/ARI Reactor High Pressure Calibration Same as applicable division of ATWS-RPT and ARI 70.00/Standby Gas Treatment "A" SGT "B" SGT, "B" DG, "B"" ESW, 1A4, 1K004 "B" SGT "A" SGT, "A" DG, "A" ESW, 1A3, 1K003 Secondary Containment - Isolated N/A STP 3.6.4.3-03, SGT Charcoal and HEPA Filter Efficiency Test See "A" or "B" SGT as applicable 73.01/Containment Atmosphere Control Torus Vent Available None Torus Vent Valve Accumulator - 1T429 None Inbd Torus Vent - CV4300 None Outbd Torus Vent - CV4357 None Drywell Vent Available None Inbd Drywell Vent - CV4302 None Outbd Drywell Vent - CV4303 None Notes: 13: When performing this STP all sections of the STP are performed. Both sides of ATWS RPT/ARI logics are affected; therefore, both side need to be included on the PRA Risk for the week.

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 20 of 24

ATTACHMENT 1 Page 12 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded ) 73.04/Torus Vacuum Breakers "A" RB to Torus - V43-169, CV4304 (Can Not Open) None "B" RB to Torus - V43-168, CV4305 (Can Not Open) None "A" RB to Torus - V43-169, CV4304 (Not Closed) None "B" RB to Torus - V43-168, CV4305 (Not Closed) None "A" Torus to Drywell - CV4327A (Can Not Open) CV4327B, CV4327C, CV4327D, CV4327F, CV4327G, CV4327H "B" Torus to Drywell - CV4327B (Can Not Open) CV4327A, CV4327C, CV4327D, CV4327F, CV4327G, CV4327H "C" Torus to Drywell - CV4327C (Can Not Open) CV4327A, CV4327B, CV4327D, CV4327F, CV4327G, CV4327H "D" Torus to Drywell - CV4327D (Can Not Open) CV4327A, CV4327B, CV4327C, CV4327F, CV4327G, CV4327H "F" Torus to Drywell - CV4327F (Can Not Open) CV4327A, CV4327B, CV4327C, CV4327D, CV4327G, CV4327H "G" Torus to Drywell - CV4327G (Can Not Open) CV4327A, CV4327B, CV4327C, CV4327D, CV4327F, CV4327H "H" Torus to Drywell - CV4327H (Can Not Open) CV4327A, CV4327B, CV4327C, CV4327D, CV4327F, CV4327G "A" Torus to Drywell - CV4327A (Not Closed) CV4327B, CV4327C, CV4327D, CV4327F, CV4327G, CV4327H "B" Torus to Drywell - CV4327B (Not Closed) CV4327A, CV4327C, CV4327D, CV4327F, CV4327G, CV4327H "C" Torus to Drywell - CV4327C (Not Closed) CV4327A, CV4327B, CV4327D, CV4327F, CV4327G, CV4327H "D" Torus to Drywell - CV4327D (Not Closed) CV4327A, CV4327B, CV4327C, CV4327F, CV4327G, CV4327H "F" Torus to Drywell - CV4327F (Not Closed) CV4327A, CV4327B, CV4327C, CV4327D, CV4327G, CV4327H "G" Torus to Drywell - CV4327G (Not Closed) CV4327A, CV4327B, CV4327C, CV4327D, CV4327F, CV4327H "H" Torus to Drywell - CV4327H (Not Closed) CV4327A, CV4327B, CV4327C, CV4327D, CV4327F, CV4327G ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 21 of 24

ATTACHMENT 1 Page 13 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 74.00/Nitrogen System Nitrogen System None 83.01/Main Steam Isolation and ADS ADS, Div 1 1D2, 1D20, 1D23, 1D22 OR 1D120 (in service charger only), HPCI (Note 12) ADS, Div 2 1D1, 1D10, 1D13, 1D12 OR 1D120 (in service charger only), HPCI (Note 12) ADS/SRV Accumulators - 1R004A, 1R004B, 1R004C, 1R004D None SV4403 None SV4404 None SRV4400 SRV4402, SRV4405, SRV4406, HPCI (Note 12) SRV4401 (LLS) SRV4407 SRV4402 SRV4400, SRV4405, SRV4406, HPCI (Note 12) SRV4405 SRV4400, SRV4402, SRV4406, HPCI (Note 12) SRV4406 SRV4400, SRV4402, SRV4405, HPCI (Note 12) SRV4407 (LLS) SRV4401 86.00/Standby Transformer Standby Transformer 1X004 (Note 8) Startup Transformer, "A" & "B" DG, "A" & "B" ESW, 1A3, 1A4 87.00/Main/Aux. Transformer & Iso/Buses Main Transformer 1X001A-D None Aux Transformer 1X002 Startup Transformer 88.00/250 VDC 1D4 Battery 1D1, 1D2, RCIC, 1D10, 1D14, 1D12, 1D120 (Only protect inservice charger), 1VAC15A or B %1D40 Distribution Panel 1P092A/B, 1P094, RCIC, 1D10, 1D14, 1D12, 1D120 (Only protect inservice charger), 1VAC15A or B 1D43 Charger 1D44 Charger STP 3.8.4-09A, 1D43 250VDC Battery Charger Capacity Test Same as 1D43 1D44 Charger 1D43 Charger STP 3.8.4-09B, 1D44 250VDC Battery Charger Capacity Test Same as 1D44 91.00/Condenser Air Removal %SJAE Condensate Return - 1P133A 1P133B %SJAE Condensate Return - 1P133B 1P133A 93.00/Turbine Bypass Valve #1 None Bypass Valve #2 None %EHC Pump - 1P097A 1P097B %EHC Pump - 1P097B 1P097A Notes: 8: When either the Startup Transformer or Standby Transformer are removed from service for maintenance, switchyard access should be restricted and work boundaries established by ropes and signs to protect the transformer switchyard power feeds to the operating transformer. 12: HPCI added to list of guarded equipment for ADS being inoperable to address concern identified in CR 1737307. % Not risk significant per ORAM-Sentinel and does not support an ORAM-Sentinel risk significant component. ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 22 of 24 ATTACHMENT 1 Page 14 of 16 RECOMMENDED GUARDED EQUIPMENT SUS/System/Component Description Systems/Areas To be Guarded 95.00/Hydrogen Seal Oil %Main & Recirc Pump and/or Vac Pump - 1P092A/B, 1P094 1P093 %Emergency Pump - 1P093 1P092A/B, 1P094 97.00/Stator Cooling

%"A" Pump - 1P091A 1P091B %"B" Pump - 1P091B 1P091A % Not risk significant per ORAM-Sentinel and does not support an ORAM-Sentinel risk significant component.

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 23 of 24

ATTACHMENT 1 Page 15 of 16 RECOMMENDED GUARDED EQUIPMENT Work Allowed on Any Division (NG-229K not required) 1. Battery Surveillances (weekly only) 2. Maintaining normal and emergency lighting 3. Routine surveys are allowed on either division: Operator Rounds / Security Rounds HP Surveys / Daily Checks / Air Samples HRA Postings Chemistry Filter Changes Chemistry Samples / Chemical Additions (excluding SBDG, CCW and Chiller) 4. Consumable replacement / Fill N2 at Cooling Tower N2 for XFMRs Inert gases for Sample Units/Monitors 5. Task Cards for non-intrusive work. 6. General plant area (non divisional) open floor space cleaning. 7. Oil Samples, lubrication activities, and other passive component monitoring activities (i.e. vibration, ultrasound, thermography, etc.). 8. Catch Containment Quarterly Inspection/Inventory. 9. Substation Weekly inspection, including when work in the substation, Xfmr, or station power supplies is in progress. 10. Work on spare parts. 11. Fire Hose and Extinguisher inspections. 12. Security work on cameras, monitors, card readers and/or doors 13. Maintenance activities on local instrumentation that meet all of the following: No process connections or must be in an isolation/thermal well or that can be isolated from the system. No interface with remote indicators or other equipment. No common process taps with other instruments unless they are also exempt. No restrictions by technical specifications. 14. Backwashing and precoating of filter demineralizers to support normal plant operations.

ADMINISTRATIVE CONTROL PROCEDURE OP-AA-102-1003 (DAEC) PROTECTED TRAINS AND GUARDED EQUIPMENT (DAEC Specific Information) Rev. 23 Page 24 of 24

ATTACHMENT 1 Page 16 of 16 RECOMMENDED GUARDED EQUIPMENT Work Allowed with Exceptions (NG-229K may be required) 1. Instrumentation / Surveillance RPS related surveillances are allowed on any division. Surveillances that remove an ECCS system are required to be performed in the appropriate division. STPs will be scheduled within the associated divisional week for risk significant systems/equipment. Risk significant STPs associated with instrumentation will be screened and pre-identified for impact on the protected division and scheduled accordingly. Instrumentation STPs not impacting protected systems ability to function

properly can be performed in any week. 2. Walk downs are allowed on any division unless: The component is operated to support walk down The system is breached (opening panel doors, venting) Requires the use of a portable step or extension ladder. Does not include installed or permanent ladder(s) Requires the use of cameras or light in light sensitive areas Work that is required to be performed in the Work Week Division (NG-229K required) 1. Intrusive component monitoring activities (non-passive) 2. Routine floor cleaning of divisional spaces is required to be on the workweek division, examples include HPCI, RCIC, Reactor Bldg. Corner Rooms, Intake, and Safety Related

Areas of Pump House 3. Construction of Scaffold for "A" or "B" systems is required to be on the workweek division. "C" system scaffolds may be built during "A" or "B" weeks provided Guarded System restrictions are adhered to. 4. Insulation adds or removal for "A" or "B" systems is required to be on the workweek division. Insulation may be added to or removed from "C" systems during "A" or "B" weeks provided the Guarded System restrictions are adhered to. 5. FIN and emergent work are required to be on the workweek division.

NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 1 of 10 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE

2013 NRC SRO ADMIN JPM EC01 TITLE: Determine Tech Spec Implications for an Inoperable System Valve

NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 2 of 10 SITE: DAEC JPM TITLE: Determine Tech Spec Implications for an Inoperable System Valve JPM NUMBER: NRC SRO EC01 REV. 0 RELATED PRA INFORMATION: None TASK NUMBER(S) / TASK TITLE(S): 1.02 / Determine Operability for Technical Specification Required Components. K/A NUMBERS AND VALUES: Generic 2.2.22, Knowledge of limiting conditions for operations and safety limits. IMPORTANCE RO 4.0 SRO 4. Justification (FOR K/A VALUES <3.0): N/A APPLICABLE METHOD OF TESTING: RO SRO STA NSPEO SRO CERT Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room: Simulator: Classroom

X Lab: Time for Completion:

30 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO Developed by: Mark Santiago 12/15/12 WTS JPM Develope r Date Validated by: Validation Instructor Date Reviewed by: Plant Reviewer Date Approved by: Training Supervisor Date NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 3 of 10 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 trainee's 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

NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 4 of 10 SIMULATOR SET UP: N/A Required Materials:

1. The "SRO EC01 Handout" that is associated with this JPM (Document can be found in JPM Folder

). 2. Key for LCO worksheets (Document can be found in JPM Folder) 3. Tech Specs

4. ACP 1410.2 LCO Tracking and Safety Function Determination Program

5. ACP 1410.7, Guidelines for Primary Containment Valves and Penetrations

6. Blank LCO Worksheets, Attachment 1, page 1 of ACP 1410.2 (minimum of 6)

General

References:

1. Tech Specs

2. ACP 1410.2 LCO Tracking and Safety Function Determination Program

3. ACP 1410.7, Guidelines for Primary Containment Valves and Penetrations, Rev 22. Task Standards:

1. Determination made that LCO 3.6.2.4, Condition A, is not met.

2. Determination made that MO 1933 is a Primary Containment Isolation Valve.

3. Determinations made that LCO 3.6.1.3, Condition A

, is not met

4. Determination made that LCO 3.3.3.1, Condition C is not met.

5. LCO Worksheet page 1 is completed for all three LCOs IAW the key provided.

NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 5 of 10 EVALUATOR TURNOVER SHEET (Read to Applicant) 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. INITIAL CONDITIONS: The plant is at rated conditions. While stroking RHR Valve MO -1933, Inboard Torus Spray, from the control room, light indication for the valve was lost (Give applicant a picture of the valve position indication) . The breaker for MO -1933 is determined to be tripped. The breaker cannot be reset. MO-1933 has been determined to be in an intermediate position. MO-1933 cannot be closed manually. There are no current LCOs being tracked. INITIATING CUES: Determine the current Tech Spec implications for the provided plant conditions and complete the appropriate forms, if necessary . This Task is not time critical . Inform the evaluator when you have completed the task . NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 6 of 10 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 examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication). NOTE: Critical steps are shaded GREY and 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: An evaluator Key is provided to evaluate the LCO worksheets completed by the candidate. Evaluator Note: The three LCOs may be determined in any order. Performance Step: 1 Critical: Y Determine that "B" RHR Suppression Pool Spray Subsystem is inoperable. Standard: Refers to TS LCO 3.6.2.4 Condition A. Determines that the subsystem must be restored within 30 days. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: N Complete page 1 of a LCO Worksheet. Standard: Completes page 1 of LCO Worksheet IAW the key for LCO # 1 with all critical elements documented as specified. Evaluator Cue: Direct the applicant to use page 1 of Attachment 1, page 1 of ACP 1410.2 Tell the applicant another SRO will complete page 2 of the Attachment and any other required documentation. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 7 of 10 Performance Step: 3 Critical: Y Determine that RHR valve MO 1933 is Primary Containment Isolation Valve (PCIV). Standard: Refers to ACP 1410.7, Guidelines for Primary Containment Valves and Penetrations, Attachment 1 and concludes that MO 1933 is a PCIV. Evaluator Note: MOV 1933 is listed on Attachment 1 of ACP 1410.7 . It is not necessary for the candidate to refer to ACP 1410.7 to determine that the MOV is a PCIV. The Candidate may use other controlled references or system knowledge to make that determination. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical: Y Determine that a PCIV is inoperable . Standard: Refers to TS LCO 3.6.1.3 Condition A. Determines that the affected line must be isolated by use of at least 1 closed and deactivated valve or blind flange with flow secured within the next 4 hours . AND Determines that the affected penetration must be verified isolated every 31 days. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 5 Critical: N Complete page 1 of an LCO Worksheet. Standard: Completes page 1 of LCO Worksheet IAW the key for LCO # 2 with all critical elements documented as specified. Evaluator Cue: Direct the applicant to use page 1 of Attachment 1, page 1 of ACP 1410.2 Tell the applicant another SRO will complete page 2 of the Attachment and any other required documentation. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 8 of 10 Performance Step: 6 Critical: Y Determine that a PAM Instrument is inoperable. Standard: Refers to TS LCO 3.3.3.1 Condition C and associated TS Table 3.3.3.1 - PAM Instrumentation. Determines that TS LCO 3.3.3.1 Condition A, for Function 6 is not being met. Determines that the affected channel / position indication must be restored within 30 days. Evaluator Note: The candidate may discuss that once the line is isolated by a closed and deactivated valve the LCO will no longer be exceeded (Table 3.3.3.1 - PAM Instrumentation note (a). Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 7 Critical: N Complete page 1 of an LCO Worksheet. Standard: Completes page 1 of LCO Worksheet IAW the key for LCO # 3 with all critical elements documented as specified. Evaluator Cue: Direct the applicant to use page 1 of Attachment 1, page 1 of ACP 1410.2 Tell the applicant another SRO will complete page 2 of the Attachment and any other required documentation. Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: When the LCO s have been determined and required actions identified . NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002} Stop Time:

NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 9 of 10 SRO Admin JPM EC01, Determine Tech Spec Implications for an Inoperable System Valve 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). EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC 2013 SRO ADMIN JPM EC01 03 13.DOC Page 10 of 10 TURNOVER SHEET INITIAL CONDITIONS: The plant is at rated conditions. While stroking RHR Valve MO -1933, Inboard Torus Spray, from the control room, light indication for the valve was lost (Give applicant a picture of the valve position indication). The breaker for MO-1933 is determined to be tripped. The breaker cannot be reset. MO-1933 has been determined to be in an intermediate position. MO-1933 cannot be closed manually. There are no current LCOs being tracked. INITIATING CUES: Determine the current Tech Spec implications for the provided plant conditions and complete the appropriate forms, if necessary. This Task is not time critical. Inform the evaluator when you have completed the task. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

1C03 Indication for Torus Spray Valve MO -1933

N A Key for LCO # 1: Inoperable RHR Suppression Pool Spray Subsystem (Critical Elements are Highlighted in Yellow) ADMINISTRATIVE CONTROL PROCEDURE ACP 1410.2 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRA M Rev. 29 Page 1 of 3 ATTACHMENT 1 Page 1 of 2 LCO WORKSHEET A1 MODE or Plant Condition___________ 1_____________ Date _Today__ Time ___Now_______ Inoperable Equipment_____ "B" RHR Suppression Pool Spray Subsystem___________________ Reason for Inoperability ____Torus Spray Valve MO -1933 failed in an intermediate position ______ ______________________________________________________________________________ Tech Spec LCO Number______3.6.2.4___________ Condition _______A__________ TRM TLCO Number______________________ Condition_________________ B1 Required Action___(__A.1__)__Restore to Operable Status___________________________ Applicable MODE______1, 2, and 3________________________ Completion Due Time Date _Today + 30 days _____ Time _Current time___ or other_____________ Initial/Date _________ / __________ Circle One OR AND N/A Required Action___(______)______________________________________________________ Applicable MODE______________________________ Completion Due Time Date____________ Time___________ or other_________________ Initial/Date____________ Circle One OR AND N/A Required Action___(______)______________________________________________________ Applicable MODE______________________________ Completion Due Time Date____________ Time___________ or other_________________ Initial/Date____________ Circle One OR AND N/A Required Action___(______)______________________________________________________ Applicable MODE______________________________ Completion Due Time Date____________ Time___________ or other_________________ Initial/Date____________ Missed SRs: ______N/A__________ ________________ ________________ ________________ Risk Analysis Performed: Y/N/NA

N A Key for LCO # 2: Inoperable Primary Containment Isolation Valve (Critical Elements are Highlighted in Yellow) ADMINISTRATIVE CONTROL PROCEDURE ACP 1410.2 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRA M Rev. 29 Page 2 of 3 ATTACHMENT 1 Page 1 of 2 LCO WORKSHEET A1 MODE or Plant Condition___________ 1_____________ Date _Today__ Time ___Now_______ Inoperable Equipment_____ Inoperable Primary Containment Isolation Valve (PCIV)_______ Reason for Inoperability ____PCIV Torus Spray Valve MO -1933 failed in an intermediate position with its breaker open _______________________________________________________________________ Tech Spec LCO Number______3.6.1.3___________ Condition _______A__________ TRM TLCO Number______________________ Condition_________________ B1 Required Action __(__A.1__)__Isolate the affected line by use of at least 1 closed and deactivated valve or blind flange with flow secured.___________________________ Applicable MODE______1, 2, and 3________________________ Completion Due Time Date _Today______ Time _Current time

+ 4hours___ or other_____________

Initial/Date ________ / __________ Circle One OR AND N/A Required Action___(__A.2__)___Verify the affected penetration flow is isolated. _______________ Applicable MODE________1, 2, and 3______________________ Completion Due Time Date____________ Time___________ or other ___Once per 31 days ______ Initial/Date _ Candidate's Initial s / Today's Date ___________ Circle One OR AND N/A Required Action___(______)______________________________________________________ Applicable MODE______________________________ Completion Due Time Date____________ Time___________ or other_________________ Initial/Date____________ Circle One OR AND N/A Required Action___(______)______________________________________________________ Applicable MODE______________________________ Completion Due Time Date____________ Time___________ or other_________________ Initial/Date____________ Missed SRs: _____N/A___________ ________________ ________________ ________________ Risk Analysis Performed: Y/N/NA

N A Key for LCO # 3: Inoperable PAM Instrumentation (Critical Elements are Highlighted in Yellow) ADMINISTRATIVE CONTROL PROCEDURE ACP 1410.2 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRA M Rev. 29 Page 3 of 3 ATTACHMENT 1 Page 1 of 2 LCO WORKSHEET A1 MODE or Plant Condition___________ 1_____________ Date _Today__ Time ___Now_______ Inoperable Equipment_____ Position Indication for PCIV ___________________ Reason for Inoperability ____Breaker for PCIV Torus Spray Valve MO -1933 tripped open with valve in position resulting in a loss of position indication in control room _______________ Tech Spec LCO Number______ 3.3.3.1 Function 6_______ Condition_ ______A__________ TRM TLCO Number______________________ Condition_________________ B1 Required Action___(__C.1__)__Restore required channel to Operable status________ Applicable MODE______1, and 2 ________________________ Completion Due Time Date_ Now + 30 days______ Time Current time___ or other_____________ Initial/Date ________ / __________ Circle One OR AND N/A Required Action___(______)______________________________________________________ Applicable MODE______________________________ Completion Due Time Date____________ Time___________ or other_________________ Initial/Date____________ Circle One OR AND N/A Required Action___(______)______________________________________________________ Applicable MODE______________________________ Completion Due Time Date____________ Time___________ or other_________________ Initial/Date____________ Circle One OR AND N/A Required Action___(______)______________________________________________________ Applicable MODE______________________________ Completion Due Time Date____________ Time___________ or other_________________ Initial/Date____________ Missed SRs: _____N/A___________ ________________ ________________ ________________ Risk Analysis Performed: Y/N/NA

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 1 of 12 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE

2013 NRC SRO ADMIN EP01 TITLE: Classify an Event and Implement the Emergency Plan as Required

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 2 of 12 SITE: DAEC JPM TITLE: Classify an Event and Implement the Emergency Plan as Required JPM NUMBER: NRC SRO Admin JPM EP -01 REV. 1 RELATED PRA INFORMATION: None TASK NUMBER(S) / TASK TITLE(S): SRO 3.01/ Implement Emergency Plan K/A NUMBERS AND VALUES: Generic 2.4.38, Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. IMPORTANCE: 2.4/4.4 Justification (FOR K/A VALUES <3.0): N/A APPLICABLE METHOD OF TESTING: RO SRO STA NSPEO SRO CERT Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room: Simulator: X Other: Lab: Time for Completion: 20 Minutes Time Critical: Yes Alternate Path / Faulted: NO TASK APPLICABILITY: SRO/RO Developed by: Mark Santiago 12/31/12 WTS JPM Developer Date Validated by: Validation Instructor Date Reviewed by: Plant Reviewer Date Approved by: Training Supervisor Date NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 3 of 12 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 trainee's 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

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 4 of 12 SIMULATOR SET UP: Ensure the EAL Notification Book has the ILT version of Note 7 on the cover. Required Materials:

1. Grading Key for EPIP Form Note

-05 (File can be found in JPM Folder). 2. EPIP Form EAL -01 (EAL Chart)

3. EPIP 1.1, Determination of Emergency Action Levels

4. EPIP Note 7, Basic Notification Flowpath

5. EPIP 1.2, Notifications General

References:

1. EPIP 1.1, Determination of Emergency Action Levels, Rev 28

2. EPIP 1.2, Notifications, Rev 42 3. EPIP Form EAL

-01 (EAL Chart)

4. EPIP Note 7, Basic Notification Flowpath Task Standards:

1. Classify the event as a Site Area Emergency based on EAL FS1.

2. Complete NOTE

-5: State and County Notification Form to the degree of accuracy specifi ed. 3. Activate the ERO Notification - DAEC Callout System

4. Implement the Plant Assembly Notification process IAW Note-04.

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 5 of 12 EVALUATOR TURNOVER SHEET (Read to Applicant) 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. 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 reactor was at full power when an automatic scram on high drywell pressure occurred. RPV level lowered to below TAF before stabilizing via the low pressure ECCS. RPV level is currently minus 10 inches and stable. RPV pressure is 70 psig and lowering Containment parameters are as follows: o Torus pressure

22 psig lowering slowly o Torus water level

11 feet, rising slowly o Torus water temperature:120°F, rising slowly o DW temperature:

260F, lowering slowly o DW pressure: 23 psig lowering slowly o Containment H 2: 0%, stable o Containment O 2: 0%. stable o Drywell Area High Range Monitors: 45 R/hr, rising slowly o Torus Area High Range Monitors: 1 R/hr, rising slowly All automatic isolations went to completion Wind Speed is 5 MPH; wind direction is from 180 degrees. There are no radiation monitoring alarms . You are the Shift Manager. The STA is unavailable. INITIATING CUES: The scram occurred two (2) minutes ago Evaluate the plant conditions provided and implement the Emergency Plan as required IAW EPIP 1.1, DETERMINATION OF EMERGENCY ACTION LEVELS and EPIP Note 7, Basic Notification Flowpath. This Task IS time critical. Inform the evaluator when you have completed the task . NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 6 of 12 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 examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication). NOTE: Critical steps are shaded GREY and 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 following steps are derived from EPIP Form Note 7, Basic Notification Flowpath. Evaluator Note: The following procedure Note is prior to the first Flow Chart element in EPIP Form Note 7 NOTE Assembly & Accountability, and ERO activation, only needs to occur once. Subsequent EAL notifications do not need NOTE -01 or NOTE-04, but you will need to complete NOTE -06. ERO activation, assembly and accountability are required for Alert classifications and above. They are discretionary at the NOUE classification, however should the OSM choose to activate the ERO, a plant page, assembly and accountability are also required.

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 7 of 12 Performance Step: 1 Critical: Y EAL Declaration Made (Note: If possible contact security prior to event declaration.) Standard: Using EPIP Form EAL -01 determines that a Site Area Emergency EAL has been exceeded based on EAL F S1, Loss or Potential Loss of ANY Two Barriers. The Site Area Emergency is declared within 1 3 minutes of the candidate acknowledging they understand the cue . Evaluator Note: A potential loss of the Fuel Clad Barrier has occurred because RPV level has stabilized at

< +15 inches. The RCS barrier was lost when drywell pressure exceeded 2 psig.

The RCS barrier is also considered lost when the Drywell Area Hi range monitor exceeded 5 R/hr. The 13 minute clock will start when the applicant states that they understand the cue. No procedures can be referenced prior to the clock starting. 15 Minute Clock Start Time_______ Time of Declaration ____________ Contacting security prior to the declaration is not a critical element of this step. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: Y Contacts Security Lieutenant to have the accountability card readers activated and to respond to the control room. Standard: Operator contacts security and directs security to activate the Emergency Accountability Card Readers (Note-07). Directs the Security Lt. to report to the control room. Evaluator Cue: Role Play as the Security Lieutenant and CUE that the Accountability Card Readers are activated and that you will report to the control room. Performance: SATISFACTORY UNSATISFACTORY Comments: EVALUATOR CAUTION: Ensure that the operator enters Scenario ID number of 55 in the next step to avoid sending out an actual notification to the ERO.

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 8 of 12 Performance Step: 3 Critical: Y Perform Note 1 immediately. Standard: Operator refers to Note 1 and: Determines Scenario ID number (Evaluator CUE may be required

55) Dials into the Dialogic Callout System at 9 866-458-8078 Enters User ID (7145) Enters Security Pin Code (7145) Enters the Scenario ID Number (55) Starts the scenario by pressing 3 Ends the call by pressing #

Pager in simulator sounds after a time delay. Evaluator Cue: After the operator has determined that for a real event, a scenario ID number of 91 would be used, CUE that for the purposes of the JPM, the operator is to use a scenario ID of 55. Performance: SATISFACTORY UNSATISFACTORY Comments: Evaluator Note: The following two steps may be performed in any order. Evaluator Cue: When both Steps 4 and 5 below have been completed, Cue the operator that the JPM has been completed . Performance Step: 4 Critical: Y Completes NOTE-5: State and County Notification Form . Standard: Operator completes the Notification Form with 100% accuracy on the critical elements of the form. The form must be completed and given to the Security Lt. within 15 minutes from the time of declaration (see step 1 of this JPM for time of declaration) Evaluator Note: See the NOTE -5 Key for the critical elements of the form. Time Notification is provided to Security _____ ___. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 9 of 12 Performance Step: 5 Critical: Y G. Completes Plant Assembly Notification Form NOTE -04 and perform s the Page Announcement. Standard: Operator completes Note -04 and: Turns on outside speakers Depresses the Evacuation Alarm Push Button for 5 -10 seconds Makes the following announcement:

 "Attention all personnel, a  Site Area Emergency    General Emergency has been declared. Emergency Response Personnel shall report to their designated Emergency Response Facilities. Emergency Personnel assigned to the EOF shall depart the site via the    South    North access and report to the EOF. All non

- essential personnel shall evacuate the site via the South North access and proceed to the Offsite Relocation and Assembly Area located west of Palo."

(alternate location)  _____________________________________."

Repeats the announcement Evaluator Note: The North access is normally blocked. Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: When: The event has been classified as a Site Area Emergency based on EAL FS1 NOTE-5: State and County Notification Form has been completed The ERO Notification - DAEC Callout System has been activated Plant Assembly Notification and Accountability process is in progress IAW Note -04 Then CUE that the JPM has been complete

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

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 10 of 12 SRO Admin JPM EP01, Classify an Event and Implement the Emergency Plan as Required 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). EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC 2013 SRO ADMIN JPM EP01 03 13.DOC Page 11 of 12 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 reactor was at full power when an automatic scram on high drywell pressure occurred. RPV level lowered to below TAF before stabilizing via the low pressure ECCS. RPV level is currently minus 10 inches and stable. RPV pressure is 70 psig and lowering Containment parameters are as follows: o Torus pressure: 22 psig lowering slowly o Torus water level: 11 feet, rising slowly o Torus water temperature:120°F, rising slowly o DW temperature: 260F, lowering slowly o DW pressure: 23 psig lowering slowly o Containment H 2: 0%, stable o Containment O 2: 0%. stable o Drywell Area High Range Monitors: 45 R/hr, rising slowly o Torus Area High Range Monitors: 1 R/hr, rising slowly All automatic isolations went to completion Wind Speed is 5 MPH; wind direction is from 180 degrees. There are no radiation monitoring alarms. You are the Shift Manager. The STA is unavailable. INITIATING CUES: The scram occurred two (2) minutes ago Evaluate the plant conditions provided and implement the Emergency Plan as required IAW EPIP 1.1, DETERMINATION OF EMERGENCY ACTION LEVELS and EPIP Note 7, Basic Notification Flowpath. This Task IS time critical. Inform the evaluator when you have completed the task. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

DAEC EMERGENCY ACTION LEVEL NOTIFICATION FORM

- KEY INITIAL ROLL CALL Benton County Linn County Iowa HSEMD MESSAGE INITIATED Time: __________

Date: __________

1. FACILITY IN COMMAND & CONTROL

[A] Control Room-..2222
[B] TSC---.-.....3333
[C] EOF-----..4444

2. STATUS [A] ACTUAL

[B] DRILL (or from SIMULATOR)

3. ACCIDENT CLASSIFICATION

[A] UNUSUAL EVENT
[B] ALERT
[C] SITE AREA EMERGENCY
[D] GENERAL EMERGENCY
[E] RECOVERY
[F] CANCELLATION/TERMINATION (If this notification is for a PAR change ONLY, write "N/A" for information in Block 4.)                     Time Declared

4. PAR CHANGE ONLY EAL CLASSIFIED

 @  TIME: ___Time___   DATE:

___Date____ (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.) EEAALL __F__ __S__ __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

[A] BELOW FEDERAL LIMITS (No KAMAN Hi-Hi alarm) [B] AT, OR ABOVE, FEDERAL LIMITS (KAMAN Hi-Hi alarm) 7. TYPE OF RELEASE (mark all that apply)
[A] RADIOACTIVE AIRBORNE (FILTERED)
[B] RADIOACTIVE AIRBORNE (UNFILTERED)
[C] RADIOACTIVE LIQUID

8. PROJECTED DURATION OF RELEASE:

[A] UNKNOWN (4 hour default)
[B] 1 HOUR OR LESS 
[C] RELEASE DURATION ____ hour(s)

9. WIND SPEED: ____5__ MILES/HR (50m value preferred)

10. WIND DIRECTION :

FROM __180____ 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 TEDE or 5 REM CDE @ 0

-2 miles from site boundary.

  [E] Dose projections  1 REM TEDE or 5 REM CDE @ 2

-5 miles from site boundary.

  [F] Dose projections  1 REM TEDE or 5 REM CDE  @ 5

-10 miles from site boundary. Evacuate, (or shelter if release duration is 1-hour or less), within a 2 mile radius and to 5 miles in the downwind subareas. AND Activate the Prompt Alert and Notification System. Evacuate, (or shelter if release duration is 1 -hour or less), within a 2 mile radius and to 5 miles in the downwind subareas, and shelter downwind subareas from 5 miles to EPZ edge . AND Activate the Prompt Alert and Notification System. Evacuate, (or shelter if release duration is 1 -hour or less), within a 2 mile radius, evacuate, (or shelter if release duration is 1 -hour or less), from 2 miles to EPZ edge in downwind subareas, and shelter as appropriate beyond EPZ edge. AND Activate the Prompt Alert and Notification System.

12. ADDITIONAL INFORMATION :

DAEC expectation is that additional information will be provided describing what caused the declaration. Evaluator Note: Items shaded in yellow are expected responses. Items circled in Red are critical elements that must be completed as shown in order to receive a satisfactory evaluation on this step of the JPM.

13. APPROVED BY: _______Candidate's Name___________________________________ (TIME) ___Time____ (DATE) ____Date_____ (OSM, EC, or ER&RD)

MESSAGE TRANSMITTED BY: FINAL ROLL CALL (Agency Reps INITIALS) Name: ________________________ Time: __________ Benton: ______ Linn: ______ Iowa HSEMD: ______ 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

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 1 of 13 DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE

2013 NRC SRO ADMIN JPM RC01 TITLE: Determine Personnel Eligibility to Perform Rad Area Task

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 2 of 13 SITE: DAEC JPM TITLE: Determine Personnel Eligibility to Perform Rad Area Task JPM NUMBER: NRC SRO ADMIN JPM RC01 REV. 1 RELATED PRA INFORMATION: None TASK NUMBER(S) / TASK TITLE(S): 1.11 / Conduct Plant Operations in Accordance with Administrative Procedures K/A NUMBERS AND VALUES: Generic 2.3.4, Knowledge of radiation exposure limits under normal or emergency conditions. IMPORTANCE RO 3.2 SRO 3.7 Justification (FOR K/A VALUES <3.0): N/A APPLICABLE METHOD OF TESTING: RO SRO STA NSPEO SRO CERT Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room: Simulator: Classroom: X Lab: Time for Completion: 20 Minutes Time Critical: NO Alternate Path / Faulted: NO TASK APPLICABILITY: SRO/RO Developed by: Mark Santiago 11/06/12 WTS JPM Developer Date Validated by: Validation Instructor Date Reviewed by: Plant Reviewer Date Approved by: Training Superviso r Date NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 3 of 13 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 trainee's 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

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 4 of 13 SIMULATOR SET UP: N/A Required Materials:

1. Calculator

2. Blank Form NG-165K (minimum of 6)

3. ACP 1411.17, OCCUPATIONAL DOSE LIMITS AND UPGRADES General

References:

1. ACP 1411.17, OCCUPATIONAL DOSE LIMITS AND UPGRADES, Rev 22 Task Standards:

1. Determines the expected exposure for the task.

2. Determines that Operator A is not eligible due to exposure over past 5 years

3. Determines that Operator B is not eligible due to having an estimated exposure for the current year at another plant.

4. Determines that Operator C is eligible if the Admin Limit is upgraded.

5. Initiates Form NG

-165K, INCREASED ADMINISTRATIVE DOSE LIMIT REQUEST by completing sections 1 and 2.

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 5 of 13 EVALUATOR TURNOVER SHEET (Read to Applicant) 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: Entry to the reactor building is required to manually close MO -2701, RWCU SUCTION OUTBOARD ISOLATION, which failed to isolate remotely, due to a steam leak from a cracked weld in RWCU. DAEC Management has decided that an operator will make the required area entry. Time to complete the task for an experienced operator will be 20 minutes. Time to complete the task for a new operator will be 30 minutes Radiation levels at the valve are as high as 1800 mR/hr. Three (3) individuals are available to perform the task. Dosimetry has provided the dose history for each operator. The table below contains the information and the experience level of each operator. Operator A Background Info: Operator A is a volunteer who is a new Non -Licensed Operator at DAEC. This operator has previous experience at other plants as a contract RP technician . Employee #: 0001 SSN: 111-11-1111 Year to Date TEDE: 1200 mR Year to Date SDE: 2000 mR Year to Date LDE: 2500 mR Exposure over past 5 Consecutive Years: 11.2 REM Operator B Background Info: Operator B is a volunteer who is a very experienced Licensed Reactor Operator at DAEC. Last week this operator came back from working an outage at another NEXTERA -ENERGY plant. A documented record of the operator's exposure at the other plant has not yet been obtained but is estimated to be 5 00 mR. Employee #: 0002 SSN: 222-22-2222 Year to Date TEDE at DAEC: 200 mR Year to Date SDE: 420 mR Year to Date LDE: 350 mR Exposure over past 5 Consecutive Years: 6.5 REM NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 6 of 13 Operator C Background Info: Operator C is a volunteer who is a very experienced Licensed Reactor Operator at DAEC. Employee #: 0003 SSN: 333-33-3333 Year to Date TEDE: 1800 mR Year to Date SDE: 4000 mR Year to Date LDE: 3800 mR Exposure over past 5 Consecutive Years: 8.9 REM INITIATING CUES: For each operator, determine if the operator is eligible for the task in accordance with ACP 1411.17, OCCUPATIONAL DOSE LIMITS AND UPGRADES. If an upgrade is required to make the operator eligible, determine if an upgrade can be authorized. If required, initiate an INCREASED ADMINISTRATIVE DOSE LIMIT REQUEST, Form NG -165K. This Task is not time critical . Inform the evaluator when you have completed the task . NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

{C002}

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 7 of 13 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 examinee's actions warrant receiving the information (i.e. the examinee looks or asks for the indication). NOTE: Critical steps are shaded GREY and 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 Critical: N Determine the expected exposure for the task Standard: For an experienced operator - Calculates that a 20 minute exposure in a 1800 mR/hr field will cause a dose of 600 mR. For a new operator - Calculates that a 30 minute exposure in a 1800 mR/hr field will cause a dose of 900 mR. Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: Y Evaluates Operator A as to eligibility to perform the task. Standard: Determines that Operator A is NOT eligible. Operator currently has a TEDE of 1200 mR for the year. The task will require an additional dose of 900 mR. The additional dose will result in a year to date dose of 2100 mR. This will exceed the Admin limit of 2000 mR per year and would normally require an increase in the Administrative Limit IAW Section 3.5 of ACP 1411.17. However Prerequisite 3.5.1 (2) is not me t due to the operator's exposure over the past 5 consecutive years. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 8 of 13 Performance Step: 3 Critical: Y Evaluates Operator B as to eligibility to perform the task. Standard: Determines that Operator B is NOT eligible. Operator currently has a TEDE of 200 mR for the year at DAEC and an estimated dose of 500 mR at the other plant. The task will require an additional dose of 600 mR. However the operator is currently limited to a TEDE limit of 250 mR at DAEC until documented evidence of the dose is received from the other plant as specified in step (3) of Section 3.3 ACP 1411.17 and Prerequisite 3.5.1 .(1) Evaluator Cue: Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical: N Evaluates Operator C as to eligibility to perform the task. Standard: Determines that Operator C IS eligible. Operator currently has a TEDE of 1 800 mR for the year. The task will require an additional dose of 600 mR. The additional dose will result in a year to date dose of 2 400 mR. This will exceed the Admin limit of 2000 mR per year. However the operator meets all the prerequisites of section 3.5.1 of ACP 1411.17 for upgrading the administrative limits IAW section 3.5.2. Performance: SATISFACTORY UNSATISFACTORY Comments:

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 9 of 13 Performance Step: 7 Critical: Y Initiates an INCREASED ADMINISTRATIVE DOSE LIMIT REQUEST for Operator C IAW section 3.5.2 of ACP 1411.17 step (2) Standard: Completes demographic information and Sections 1 and 2 of Form NG -165K per the attached key (Page 12 of this JPM). Evaluator Note:

"Employed by" does not need to match the key as long as it indicates that the operator is employed by the Facility Licensee.
"Detailed Reason" for extension does not need to match the key exactly as long as it conveys the situation

. Evaluator Cue: When Form NG -165K, sections 1 and 2 have been initiated for Operator C, CUE the operator that the JPM is complete. Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cues: When the determination is made that Operators C is eligible to perform the task and Form NG-165K, sections 1 and 2 have been initiated for Operator C, CUE the operator that the JPM is complete. NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator. {C002} Stop Time:

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 10 of 13 SRO Admin JPM RC01, Determine Personnel Eligibility to Perform Rad Area Task 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). EVALUATOR'S SIGNATURE: NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 11 of 13 ADMINISTRATIVE DOSE LIMIT REQUEST (KEY) Worker Name: Operator C TLD Number: 3 SSN: (Last 4 digits) 3333 Employed by: DAEC Supervisor: Candidate's Name

1. Type of Extension Beyond 2,000 millirem per Year TEDE Beyond 4,000 millirem per Year TEDE Beyond 3,000 millirem per Year TEDE Beyond 4,500 millirem per Year TEDE

2. TEDE Review & Upgrade Request Worker's current yearly TEDE: _____1800____ millirem Extend to yearly limit of: ___

__ANYTHING Between 2,400 and 3,000_________ millirem Detailed Reason for extension (Required for all extensions): ___ Entry to the reactor building is required to manually close MO -2701 due to a steam leak from a cracked weld in RWCU, which failed to isolate remotely. _____________________________________________________________________________

3. Dosimetry Review Dosimetry to verify: documented evidence of current year dose is on file with no personal estimate for current year; and SDE and LDE not limiting.

Approved Disapproved, reason: Dosimetry / Date

4. Approval signatures Circle One Beyond 2,000 millirem/yr TEDE:

Y / N Radiation Protection Manager / Da te Beyond 3,000 millirem/yr TEDE: Y / N Radiation Protection Manager / Date Y / N Plant General Manager / Date Beyond 4 ,000 millirem//yr TEDE: Y / N Radiation Protection Manager / Date Y / N Plant General. Manager / Date Beyond 4,500 millirem/yr TEDE: Y / N Site Vice President/ Date

5. Worker's Acknowledgment (Required for any increase)

Worker / Date

NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 12 of 13 TURNOVER SHEET (Page 1 of 2) INITIAL CONDITIONS: Entry to the reactor building is required to manually close MO -2701, RWCU SUCTION OUTBOARD ISOLATION, which failed to isolate remotely, due to a steam leak from a cracked weld in RWCU. DAEC Management has decided that an operator will make the required area entry. Time to complete the task for an experienced operator will be 20 minutes. Time to complete the task for a new operator will be 30 minutes Radiation levels at the valve are as high as 1800 mR/hr. Three (3) individuals are available to perform the task. Dosimetry has provided the dose history for each operator. The table below contains the information and the experience level of each operator. Operator A Background Info: Operator A is a volunteer who is a new Non -Licensed Operator at DAEC. This operator has previous experience at other plants as a contract RP technician. Employee #: 0001 SSN: 111-11-1111 Year to Date TEDE: 1200 mR Year to Date SDE: 2000 mR Year to Date LDE: 2500 mR Exposure over past 5 Consecutive Years: 11.2 REM Operator B Background Info: Operator B is a volunteer who is a very experienced Licensed Reactor Operator at DAEC. Last week this operator came back from working an outage at another NEXTERA -ENERGY plant. A documented record of the operator's exposure at the other plant has not yet been obtained but is estimated to be 5 00 mR. Employee #: 0002 SSN: 222-22-2222 Year to Date TEDE at DAEC: 200 mR Year to Date SDE: 420 mR Year to Date LDE: 350 mR Exposure over past 5 Consecutive Years: 6.5 REM NRC 2013 SRO ADMIN JPM RC01 03 13.DOC Page 13 of 13 TURNOVER SHEET (Page 2 of 2) Operator C Background Info: Operator C is a volunteer who is a very experienced Licensed Reactor Operator at DAEC. Employee #: 0003 SSN: 333-33-3333 Year to Date TEDE: 1800 mR Year to Date SDE: 4000 mR Year to Date LDE: 3800 mR Exposure over past 5 Consecutive Years: 8.9 REM INITIATING CUES: For each operator, determine if the operator is eligible for the task in accordance with ACP 1411.17, OCCUPATIONAL DOSE LIMITS AND UPGRADES. If an upgrade is required to make the operator eligible, determine if an upgrade can be authorized. If required, initiate an INCREASED ADMINISTRATIVE DOSE LIMIT REQUEST, Form NG -165K. This Task is not time critical.

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

{C002}

NG-165K Rev. 5 ADMINISTRATIVE DOSE LIMIT REQUEST Worker Name: TLD Number: SSN: (Last 4 digits) Employed by: Supervisor:

1. Type of Extension Beyond 2,000 millirem per Year TEDE Beyond 4,000 millirem per Year TEDE Beyond 3,000 millirem per Year TEDE Beyond 4,500 millirem per Year TEDE

2. TEDE Review & Upgrade Request Worker's current yearly TEDE: _____________ millirem Extend to yearly limit of: __________________ millirem Detailed Reason for extension (Required for all extensions): ____________________________

______________________________________________________________________________ ________________________________________________ ______________________________

3. Dosimetry Review Dosimetry to verify: documented evidence of current year dose is on file with no personal estimate for current year; and SDE and LDE not limiting.

Approved Disapproved, reason: Dosimetry / Date

4. Approval signatures Circle One Beyond 2,000 millirem/yr TEDE:

Y / N Radiation Protection Manager / Date Beyond 3,000 millirem/yr TEDE: Y / N Radiation Protection Manager / Date Y / N Plant General Manager / Date Beyond 4 ,000 millirem//yr TEDE: Y / N Radiation Protection Manager / Date Y / N Plant General. Manager / Date Beyond 4,500 millirem/yr TEDE: Y / N Site Vice President/ Date

5. Worker's Acknowledgment (Required for any increase)

Worker / Date}}