ML24120A183

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Ile RO Admin JPMs - Administered
ML24120A183
Person / Time
Site: Point Beach  
Issue date: 03/07/2024
From:
NRC/RGN-III
To:
Point Beach
B. Bergeon
References
Download: ML24120A183
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Text

NEXTera JPM E~

JOB PERFORMANCE MEASURE Page1of 15 A.Ct'!

JPM TITLE:

PERFORM SHUTDOWN MARGIN CALCULATION FOR AN OPERA TING REACTOR JPM NUMBER:

PBN JPM P000.002d.COT REV.

6 TASK NUMBER($)/

P001.003.COT / PERFORM SHUTDOWN MARGIN CALCULATION TASK TITLE(S):

KIA NUMBERS:

003 AK1.07 003 AK3.04 2.1.25 Justification (FOR KIA VALUES <3.0):

TASK APPLICABILITY:

KIA VALUE:

3.8 3.7 3.9/4.2

[gj RO

[gj SRO O STA D Non-Lie D SRO CERT OOTHER: __

APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough: D Perform: CR]

EVALUATION LOCATION:

In-Plant: D Control Room:

Simulator: [KJ Other:

Lab:

D Time for Completion:

20 Minutes Time Critical:

NO Alternate Path [NRC]:

NO Alternate Path [INPO]:

NO Developed by:

Andrew Zommers TR-AA-230-1007-F15, Revision 2 D

X

{ t { ' i Date 1'Z.11../lJ Date

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 2 of 15 TR-AA-230-1007-F15, Revision 2 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1.

Are all items on the signature page filled in correctly?

2.

Has the JPM been reviewed and validated by SMEs?

3.

Can the required conditions for the JPM be appropriately established in the simulator if required?

4.

Do the performance steps accurately reflect trainees actions in accordance with plant procedures?

5.

Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6.

Has the completion time been established based on validation data or incumbent experience?

7.

If the task is time critical, is the time critical portion based upon actual task performance requirements?

8.

Is the job 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 classified (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 supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16.

If the JPM is to be administered to an LOIT 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.

17.

If this is a simulator JPM, the JPM has been validated IAW TR-AA-230-1008, Simulator Based Testing and Validation 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.

Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)

None

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 3 of 15 TR-AA-230-1007-F15, Revision 2 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR PREPARER DATE SUPERVISOR DATE Rev. 0 Developed JPM for ILT 2011 admin re-exam.

Rev. 1 Revised JPM with EPU values for the 2012 ILT NRC exam.

Rev. 2 Updated to current format Rev. 3 Updated to current format and form revision Rev 4 Updated to the current core U1C36 Rev 5 Updated to the current core U1C38 Rev. 6 Updated to the current core U1R42, updated K/A catalog changes and placed in new JPM template for 2024 ILT NRC Exam. Corrected RO task numbering.

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 4 of 15 TR-AA-230-1007-F15, Revision 2 SIMULATOR SET-UP:

SIMULATOR SETUP INSTRUCTIONS:

N/A SIMULATOR MALFUNCTIONS:

N/A SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A Required Materials:

PBF-2513, Shutdown Margin for an Operating Reactor Calculator Technical Requirements Manual (TRM)

Marked up ROD 1.1 (markup should indicate that burnup was 1930 5 days ago and Target AO -2.79)

Unit 1 ROD Book, U1C42 General

References:

Technical Requirements Manual (TRM)

Unit 1 ROD Book, U1C42 PBF-2513, Shutdown Margin for an Operating Reactor Calculator Task Standards:

Required Shutdown Margin calculated within the specified tolerance

(+/- 20 pcm).

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 5 of 15 TR-AA-230-1007-F15, Revision 2 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:

  • Unit 1 had been operating at 100% power.
  • Rod H-2 in Shutdown Bank "A" has dropped to the bottom of the core.
  • The crew is responding in accordance with AOP-6A, "Dropped Rod".
  • Assume todays date and time is current.

INITIATING CUES:

The following Unit 1 conditions currently exist:

  • Boron Concentration - 1125 ppm
  • Rx Power - 90%
  • Tave - 572 °F
  • Tref - 573 °F
  • Control Bank D @ 180 steps
  • All other banks @ 225 steps NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 6 of 15 TR-AA-230-1007-F15, Revision 2 JPM PERFORMANCE INFORMATION Start Time:

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

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

NOTE: DURING THE JPM, ENSURE PROPER PROCEDURE USE AND ADHERENCE, SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

Performance Step: 1 Critical N Verify TAVG within 1.5°F of TREF.

Standard:

Verify TAVG within 1.5°F of TREF based on initial conditions given and circle YES on PBF-2513.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 7 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 2 Critical Y Obtain Core Burn-Up from ROD 1.1.

Standard:

Core burn-up determined to be 2120 MWD/MTU.

Evaluator Note:

Core burn-up determined to be 2120 MWD/MTU and recorded on PBF-2513. From ROD 1.1, examinee will have 1930 MWD/MTU five days ago and will need to add 190 MWD/MTU (5 Days

  • 38 MWD/MTU/Day)

Evaluator Cue:

Provide examinee with a copy of Unit 1 ROD book.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 Critical N Obtain Nominal EOL Burn-Up from ROD1.1.

Standard:

EOL burn-up determined to be 19240 MWD/MTU and recorded on PBF-2513.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 8 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 4 Critical N Calculate % Burn-Up.

Standard:

Calculate % burn-up to be 11.0% and record on PBF-2513.

Evaluator Note:

Allowable range based on allowed range in JPM Step #2 above.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 Critical N Obtain Reactor Power Level (%).

Standard:

Record 90% on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

Performance Step: 6 Critical N Obtain Control Rod Position Standard:

Bank C and D control rod position determined to be 225 and 180 steps and recorded on PBF-2513.

Evaluator Cue:

If asked Bank C is at 225 steps per initial conditions.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 9 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 7 Critical Y Obtain Power Defect from ROD 7.

Standard:

Determine power defect to be 1580 pcm + 20 pcm (1560-1600),

based on possible min/max reading on graph) and record on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

Performance Step: 8 Critical Y Obtain Control Rod Worth (Bank D, C, B, A, S in, at HZP) from ROD 5.

Standard:

Determine control rod worth (Bank D, C, B, A, S in, at HZP) to be 6140pcm and record on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

Performance Step: 9 Critical Y Obtain Stuck Rod Worth from ROD 5.

Standard:

Determine stuck rod worth to be 600 pcm and record on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 10 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 10 Critical Y Calculate Stuck Rod Worth minus Control Rod Worth.

Standard:

Calculate stuck rod worth minus control rod worth to be 5540 pcm and record on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

Performance Step: 11 Critical Y Obtain Bank Worth to ARO from ROD 3.1, Use Step 2 and Step 6 data.

Standard:

Determine bank worth to ARO to be 152 pcm and record on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

Performance Step: 12 Critical Y Obtain correct value for dropped rod, stuck rod or no abnormal condition.

Standard:

Determine dropped rod and enter Stuck Rod Worth from ROD 5 and record 600 pcm on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 11 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 13 Critical Y Calculate Total Available Control Rod Negative Reactivity by adding Step 10, 11, 12 and 250 pcm.

Standard:

Determine Total available control rod negative reactivity to be 4538 pcm and record on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

Performance Step: 14 Critical Y Calculates Shut Down Margin by adding Steps 13 and 7.

Standard:

Determine calculated SDM to be 2958 + 20 pcm (2938-2978) and record on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

Performance Step: 15 Critical Y Determine the Required Shut Down Margin using TRM 2.1, [COLR]

Figure 2 using Step 4 data.

Standard:

Determines required SDM to be -2000 pcm and record on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 12 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 16 Critical Y Determines if calculated Shut Down Margin is more negative than Required Shut Down Margin.

Standard:

Determines Calculated SDM is greater than Required SDM AND circles YES on PBF-2513.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

Performance Step: 17 Critical N Inform OS1 you calculated the shutdown margin in accordance with PBF-2513, "Shutdown Margin for an Operating Reactor" and shutdown margin is satisfactory.

Standard:

Inform OS1 that SDM calculation is complete.

Performance:

SATISFACTORY _____ UNSATISFACTORY _____

Comments:

Terminating Cues:

This completes the JPM Stop Time:

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

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 13 of 15 TR-AA-230-1007-F15, Revision 2 Examinee:

Evaluator:

RO SRO STA Non-Lic SRO CERT Date:

LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT:

UNSAT:

Remediation required:

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

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

EVALUATORS SIGNATURE:

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

PBN JPM P000.002d.COT, Perform Shutdown Margin Calculation for an Operating Reactor, Rev. 6 JPM Page 14 of 15 TR-AA-230-1007-F15, Revision 2 DO NOT HAND OUT THIS IS A KEY SHUTDOWN MARGIN FOR AN OPERATING REACTOR UNIT ___1_____

TIME _________

DATE ___Today__

STEP CORE PARAMETER OR VARIABLE ROD BOOK SECTION DATA 1

TAVG within 1.5°F of TREF (Consult with Reactor Engineering if greater than 1.5°F)

(circle one)

YES/NO 2

Core Burn-Up (MWD/MTU from ROD 1.1)

ROD 1.1 2120 MWD/MTU 3

Nominal EOL Burn-Up (MWD/MTU from ROD 1.1)

ROD 1.1 19240 MWD/MTU 4

% Burn-Up (Step 2 ÷ Step 3) 11.0 %

5 Reactor Power Level (%)

90 %

6 Control Rod Position Bank C 225 steps Bank D 180 steps 7

Power Defect (for power recorded in Step 5)

ROD 7

(+) 1580 (+/-20) pcm 8

Control Rod Worth (Bank D, C, B, A, S in; at HZP)

ROD 5

(+) 6140 pcm 9

Stuck Rod Worth ROD 5

(+) 600 pcm 10 Stuck Rod Worth minus Control Rod Worth (Step 9 Step 8)

(-) 5540 pcm 11 Bank Worth to ARO (Use Step 2 and Step 6 data)

ROD 3.1

(+) 152 pcm 12 For a dropped rod, enter the Stuck Rod Worth from ROD 5.

ROD 5

(+) 600 pcm For a stuck rod, multiple misaligned rods, or a rod misaligned low, contact Reactor Engineering.

Enter 0 if no rod abnormalities exist.

13 Total Available Control Rod Negative Reactivity (Step 10 + Step 11 + Step 12 + 250 pcm*)

  • 250 pcm added to account for redistribution effects from Xenon and voiding

(-) 4538 pcm 14 Calculated Shut Down Margin (Step 13 + Step 7)

(-) 2958 (+/-20) pcm 15 Required Shut Down Margin (From TRM 2.1, [COLR], Figure 2, using Step 4 data)

(-) 2000 pcm 16 Calculated Shut Down Margin is more negative than Required Shut Down Margin (Step 14 more negative than Step 15)

(circle one)

YES/NO

JOB PERFORMANCE MEASURE JPM Page 15 of 15 TR-AA-230-1007-F15, Revision 2 TURNOVER SHEET INITIAL CONDITIONS:

  • Unit 1 had been operating at 100% power.
  • Rod H-2 in Shutdown Bank "A" has dropped to the bottom of the core.
  • The crew is responding in accordance with AOP-6A, "Dropped Rod".
  • Assume todays date and time is current.

INITIATING CUES:

The following Unit 1 conditions currently exist:

  • Boron Concentration - 1125 ppm
  • Rx Power - 90%
  • Tave - 572 °F
  • Tref - 573 °F
  • Control Bank D @ 180 steps
  • All other banks @ 225 steps NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

PBF-2513 Revision 2 08/30/05

Reference:

AOP 6A Point Beach Nuclear Plant SHUTDOWN MARGIN FOR AN OPERATING REACTOR UNIT _________

TIME _________

DATE _________

STEP CORE PARAMETER OR VARIABLE ROD BOOK SECTION DATA 1

TAVG within 1.5°F of TREF (Consult with Reactor Engineering if greater than 1.5°F)

(circle one)

YES/NO 2

Core Burn-Up (MWD/MTU from ROD 1.1)

ROD 1.1 MWD/MTU 3

Nominal EOL Burn-Up (MWD/MTU from ROD 1.1)

ROD 1.1 MWD/MTU 4

% Burn-Up (Step 2 ÷ Step 3) 5 Reactor Power Level (%)

6 Control Rod Position Bank C steps Bank D steps 7

Power Defect (for power recorded in Step 5)

ROD 7

(+)

pcm 8

Control Rod Worth (Bank D, C, B, A, S in; at HZP)

ROD 5

(+)

pcm 9

Stuck Rod Worth ROD 5

(+)

pcm 10 Stuck Rod Worth minus Control Rod Worth (Step 9 Step 8)

(-)

pcm 11 Bank Worth to ARO (Use Step 2 and Step 6 data)

ROD 3.1

(+)

pcm 12 For a dropped rod, enter the Stuck Rod Worth from ROD 5.

ROD 5

(+)

pcm For a stuck rod, multiple misaligned rods, or a rod misaligned low, contact Reactor Engineering.

Enter 0 if no rod abnormalities exist.

13 Total Available Control Rod Negative Reactivity (Step 10 + Step 11 + Step 12 + 250 pcm*)

  • 250 pcm added to account for redistribution effects from Xenon and voiding

(-)

pcm 14 Calculated Shut Down Margin (Step 13 + Step 7)

(-)

pcm 15 Required Shut Down Margin (From TRM 2.1, [COLR], Figure 2, using Step 4 data)

(-)

pcm 16 Calculated Shut Down Margin is more negative than Required Shut Down Margin (Step 14 more negative than Step 15)

(circle one)

YES/NO Completed By: ____________________________

PBF-2513 Revision 2 08/30/05

Reference:

AOP 6A Independent Verification By: ____________________________

DOS/SM Review: ____________________________

NUCLEAR POWER BUSINESS UNIT ROD 1.1 REACTOR OPERATING DATA U1C42 Rev. 23 MWD/MTU TARGET AO DATE / INIT MWD/MTU TARGET AO DATE / INIT Assuming Full Power Operation (>95% Average)

CURRENT BURNUP ADD 38 MWD/MTU PER DAY TO LATEST VALUE NOMINAL EOL BURNUP = 19240 MWD/MTU CURRENT BURNUP UNIT 1 CYCLE 42 1930

-2.79 5 Days ago / AKZ

PBN JPM P010.004.COT, Perform a Pressurizer Heater Group Input Test Calculation, Rev. 3 JPM Page 2 of 11 TR-AA-230-1007-F15, Revision 2 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1.

Are all items on the signature page filled in correctly?

2.

Has the JPM been reviewed and validated by SMEs?

3.

Can the required conditions for the JPM be appropriately established in the simulator if required?

4.

Do the performance steps accurately reflect trainees actions in accordance with plant procedures?

5.

Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6.

Has the completion time been established based on validation data or incumbent experience?

7.

If the task is time critical, is the time critical portion based upon actual task performance requirements?

8.

Is the job 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 classified (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 supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16.

If the JPM is to be administered to an LOIT 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.

17.

If this is a simulator JPM, the JPM has been validated IAW TR-AA-230-1008, Simulator Based Testing and Validation 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.

Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)

{C001}

PBN JPM P010.004.COT, Perform a Pressurizer Heater Group Input Test Calculation, Rev. 3 JPM Page 3 of 11 TR-AA-230-1007-F15, Revision 2 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1000) made to the material after initial approval.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

PREPARER DATE SUPERVISOR DATE Rev. 2 Revised for 2019 ILT NRC Exam Match TS-43 T-1D Unit 1 Rev. 3 Revised for 2024 ILT NRC exam, updated K/A changes and placed in new JPM template.

PBN JPM P010.004.COT, Perform a Pressurizer Heater Group Input Test Calculation, Rev. 3 JPM Page 4 of 11 TR-AA-230-1007-F15, Revision 2 SIMULATOR SET-UP:

SIMULATOR SETUP INSTRUCTIONS:

N/A SIMULATOR MALFUNCTIONS:

N/A SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A Required Materials:

Partial TS-43 1T-1D Unit 1, Pressurizer Heater Group Energy Input Test filled out to the point where calculations are needed.

Calculator General

References:

TS-43 1T-1D Unit 1, Pressurizer Heater Group Energy Input Test Task Standards:

Properly calculate and record pressurizer heater inputs per TS-43 1T-1D Unit 1, Pressurizer Heater Group Energy Input Test

PBN JPM P010.004.COT, Perform a Pressurizer Heater Group Input Test Calculation, Rev. 3 JPM Page 5 of 11 TR-AA-230-1007-F15, Revision 2 I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

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

INITIAL CONDITIONS:

You are the Unit 1 CO.

Unit 1 is currently in Mode 2 with a reactor startup in progress.

Pressurizer Heater Group 1T-1C failed on the previous shift.

Engineering has determined that a potential common mode failure exists (applicable only to Unit 1),

and has recommended that TS 43, Pressurizer Heater Group Energy Input Test, be performed on Unit 1 Pressurizer Heater Group 1T-1D in order to verify its operability.

The test is in progress, voltage and current readings have been taken by maintenance, and the procedure is complete up to and including step 5.1.13.

INITIATING CUES:

You are to complete TS-43, 1T-1D Pressurizer Heater Group Test, beginning at step 5.1.14.

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

PBN JPM P010.004.COT, Perform a Pressurizer Heater Group Input Test Calculation, Rev. 3 JPM Page 6 of 11 TR-AA-230-1007-F15, Revision 2 JPM PERFORMANCE INFORMATION Start Time:

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

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

NOTE: DURING THE JPM, ENSURE PROPER PROCEDURE USE AND ADHERENCE, SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

Performance Step: 1 Critical N CALCULATE the average Voltage and Average current for each breaker.

(RECORD on table above)

Standard:

Average voltage and average current is calculated and recorded in Table PP-13 1T-1D. (see attached table for correct values)

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 Critical Y CALCULATE the Power for each Breaker per the following formula.

Power= 1.732 x Average Voltage x Average Current x 1/1000.

(RECORD on table PP-13 1T-1D above)

Standard:

Power for each breaker is calculated and recorded in Table PP-13 1T-1D.

Breaker 1

2 3

4 5

Power in KW 20.7 19.8 20.4 20.4 20.7 Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P010.004.COT, Perform a Pressurizer Heater Group Input Test Calculation, Rev. 3 JPM Page 7 of 11 TR-AA-230-1007-F15, Revision 2 Performance Step: 3 Critical Y Sum the Total power as follows:

_____ + _____ + _____ + _____ + _____ = _______ in KW BKR# 1 2 3 4 5 TOTAL Standard:

Power of each breaker is added together to determine total power of Pressurizer Heater Group 1T-1D.

Evaluator Note:

Total power should be 102 +1 KW Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 Critical Y Multiply by uncertainty factor of 0.9335 as follows.

Total Power in KW ________ x 0.9335 = ____________ KW and record result in section 6.0 Acceptance Criteria Standard:

The total power of the heater Group obtained in the previous step is multiplied by 0.9335 and recorded in section 6.0.

Evaluator Note:

Final value is 95.2 1.0 kW.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 Critical N Independently Review the calculations for steps 5.1.14, 5.1.15, 5.1.16, and 5.1.17 to verify accuracy.

Standard:

Examinee asks for an Independent Verification of calculation Evaluator Cue:

Sign the step to indicate that an Independent Verification as performed Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P010.004.COT, Perform a Pressurizer Heater Group Input Test Calculation, Rev. 3 JPM Page 8 of 11 TR-AA-230-1007-F15, Revision 2 Performance Step: 6 Critical N IF using TS-43(Unit 1).xls Spreadsheet to calculate data, THEN RECORD corrected power for 1T-1D in Section 6.0, Acceptance Criteria.

Standard:

This step should be marked N/A Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 Critical Y Step 6.0 Acceptance Criteria:

The total power of Pressurizer Heater Group 1T-1D is compared with the Technical Specification Acceptance Criteria.

Standard:

Total power of Pressurizer Heater Group 1T-1D is determined to NOT meet Technical Specification requirements of 100 kW.

Evaluator Cue:

Inform examinee the Third License will work on writing an AR.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues:

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

Stop Time:

PBN JPM P010.004.COT, Perform a Pressurizer Heater Group Input Test Calculation, Rev. 3 JPM Page 9 of 11 TR-AA-230-1007-F15, Revision 2 Fill in the table in TS 43 section 5.1 as follows:

PP-13 1T-1D BREAKER 1

2 3

4 5

VOLTAGE A-B 486.5 486.5 486.5 486.4 486.4 A-C 486.2 486.4 486.3 486.3 486.3 B-C 488.8 488.8 488.7 488.7 488.6 AVERAGE

  • 487.2+.1
  • 487.2+.1
  • 487.2+.1
  • 487.1+.1
  • 487.1+.1 CURRENT A

24.2 23.6 23.8 24.2 25.0 B

24.8 23.9 24.5 24.2 24.1 C

24.4 23.1 24.2 24.1 24.5 AVERAGE

  • 24.5+.1
  • 23.5+.1
  • 24.2+.1
  • 24.2+.1
  • 24.5+.1 POWER in KW
  • 20.6-20.7
  • 19.8-19.9
  • 20.4-20.5
  • 20.4-20.5
  • 20.6-20.7
  • DO NOT record these values on the paper work submitted to the candidate, they will calculate these values.

5.1.8 Record Test Instruments used.

ID No. MCCP-12 Cal. date Today ID No. MCMM-37 Cal. date Today

PBN JPM P010.004.COT, Perform a Pressurizer Heater Group Input Test Calculation, Rev. 3 JPM Page 10 of 11 TR-AA-230-1007-F15, Revision 2 Examinee:

Evaluator:

RO SRO STA Non-Lic SRO CERT Date:

LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT:

UNSAT:

Remediation required:

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

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

EVALUATORS SIGNATURE:

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

TURNOVER SHEET JPM Page 11 of 11 TR-AA-230-1007-F15, Revision 2 TURNOVER SHEET INITIAL CONDITIONS:

You are the Unit 1 CO.

Unit 1 is currently in Mode 2 with a reactor startup in progress.

Pressurizer Heater Group 1T-1C failed on the previous shift.

Engineering has determined that a potential common mode failure exists (applicable only to Unit 1),

and has recommended that TS 43, Pressurizer Heater Group Energy Input Test, be performed on Unit 1 Pressurizer Heater Group 1T-1D in order to verify its operability.

The test is in progress, voltage and current readings have been taken by maintenance, and the procedure is complete up to and including step 5.1.13.

INITIATING CUES:

You are to complete TS-43, 1T-1D Pressurizer Heater Group Test, beginning at step 5.1.14.

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

TS 43 T-1D UNIT 1 1T-1D, PRESSURIZER HEATER GROUP ENERGY INPUT TEST UNIT 1 DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 3 REVIEWER: N/A APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Operations Verified Current Copy:

Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers AndrewZommers today 3hrsago

POINT BEACH NUCLEAR PLANT TECHNICAL SPECIFICATION TESTS 1T-1D, PRESSURIZER HEATER GROUP ENERGY INPUT TEST UNIT 1 TS 43 T-1D UNIT 1 SAFETY RELATED Revision 3 Page 2 of 9 CONTINUOUS USE TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE.......................................................................................................................3 2.0 PREREQUISITES..........................................................................................................3 3.0 PRECAUTIONS AND LIMITATIONS.........................................................................3 4.0 INITIAL CONDITIONS................................................................................................4 5.0 PROCEDURE.................................................................................................................5 6.0 ACCEPTANCE CRITERIA...........................................................................................8

7.0 REFERENCES

...............................................................................................................9 8.0 BASES............................................................................................................................9

POINT BEACH NUCLEAR PLANT TECHNICAL SPECIFICATION TESTS 1T-1D, PRESSURIZER HEATER GROUP ENERGY INPUT TEST UNIT 1 TS 43 T-1D UNIT 1 SAFETY RELATED Revision 3 INITIALS Page 3 of 9 CONTINUOUS USE 1.0 PURPOSE 1.1 The purpose of this test is to ensure the Pressurizer Heaters have an energy input of greater than 100KW as required by Technical Specification 3.4.9.

1.2 This test is performed Quarterly to satisfy Technical Specification SR 3.4.9.2 and will test D pressurizer heater group energy input.

1.3 The energy inputs from pressurizer heater group D are used to satisfy the Technical Specification.

2.0 PREREQUISITES 2.1 Measurement and Test Equipment 2.1.1 Optional-Fluke 435 or equivalent 2.1.2 (3) Fluke i430Flex 3000a current probes or equivalent.

2.1.3 Record Test Instruments.

ID No. _____________ Cal. due date ___________

ID No. _____________ Cal. due date ___________

ID No. _____________ Cal. due date ___________

ID No. _____________ Cal. due date ___________

3.0 PRECAUTIONS AND LIMITATIONS 3.1 This test is a Technical Specification requirement. If any problem is encountered while completing this test, or any abnormalities are noted, immediately contact the duty Shift Management.

3.2 The temperature differential between the pressurizer and pressurizer spray water SHALL be limited to a maximum of 320F. (TRM 3.4.2) 3.3 This test should not be performed during solid pressurizer conditions.

3.4 Use standard electrical safety precautions when working in/around power panels.

N/AAKZ AKZ MCCP12 MCMM37 today today AKZ

POINT BEACH NUCLEAR PLANT TECHNICAL SPECIFICATION TESTS 1T-1D, PRESSURIZER HEATER GROUP ENERGY INPUT TEST UNIT 1 TS 43 T-1D UNIT 1 SAFETY RELATED Revision 3 INITIALS Page 4 of 9 CONTINUOUS USE 4.0 INITIAL CONDITIONS 4.1 The plant is in one of the following MODE 3 or 2 or 1 or preparing to enter MODE 3.

4.2 Pressurizer level is stable for the given operating conditions.

4.3 Operations and electrical maintenance have been briefed on performance of this test.

4.4 Permission to Perform Test The conditions required by this test are consistent with required plant conditions including equipment operability. Permission is granted to perform this test.

Shift Management TIME DATE AKZ AKZ AKZ K.MoorefortheSM 2hrsago today

POINT BEACH NUCLEAR PLANT TECHNICAL SPECIFICATION TESTS 1T-1D, PRESSURIZER HEATER GROUP ENERGY INPUT TEST UNIT 1 TS 43 T-1D UNIT 1 SAFETY RELATED Revision 3 INITIALS Page 5 of 9 CONTINUOUS USE 5.0 PROCEDURE 5.1 1T-1D Pressurizer Heater Group Test CAUTION The Temperature difference between the pressurizer and pressurizer spray water shall be limited to a maximum of 320 degrees F. TRM 3.4.2 5.1.1 RECORD as found position of 1T-1D Pzr Heater Group Control Switch on 1C04._________________

NOTE:

Close coordination between Operations and Maintenance is required when performing the following steps.

5.1.2 PLACE 1T-1D Pzr Heater Group to OFF on 1C04.

5.1.3 REMOVE cover from Power Panel PP-13 for 1T-1D, Using Standard Electrical Safety Precautions.

MTN 5.1.4 IF desired, THEN INSTALL Fluke 435 or equivalent.

MTN 5.1.5 IF Using Fluke 435, THEN ensure set up as follows:

DELTA (ungrounded) heater load 60 HZ 480 VAC Limits at DEFAULT Correct amp probe & output settings MTN AUTO AKZ AKZ MJV N/AMJV N/AMJV

POINT BEACH NUCLEAR PLANT TECHNICAL SPECIFICATION TESTS 1T-1D, PRESSURIZER HEATER GROUP ENERGY INPUT TEST UNIT 1 TS 43 T-1D UNIT 1 SAFETY RELATED Revision 3 INITIALS Page 6 of 9 CONTINUOUS USE CAUTION Energizing 1T-1D Heater Group will cause a slight increase in RCS Pressure and Reactor Thermal Output 5.1.6 ENERGIZE 1T-1D Pzr Heater Group by placing control switch to ON on 1C04.

5.1.7 IF using Fluke 435 or equivalent, THEN obtain KW reading by selecting POWER and ENERGY from the menu, RECORD KW result in Section 6.0 Acceptance Criteria.

MTN NOTE:

Steps 5.1.8 may be marked N/A if Step 5.1.7 was performed above.

5.1.8 MEASURE and RECORD voltage (phase to phase) and current for each breaker in PP-13, Using Standard Electrical Safety Precautions.

MTN PP-13 1T-1D BREAKER 1

2 3

4 5

VOLTAGE A-B A-C B-C AVERAGE CURRENT A

B C

AVERAGE POWER in KW 5.1.9 PLACE 1T-1D Pzr Heater Group to OFF on 1C04.

AKZ N/AMJV MJV 486.5 486.2 488.8 486.5 486.4 488.8 486.5 486.3 488.7 486.4 486.3 488.7 486.4 486.3 488.6 24.2 24.8 24.4 23.6 23.9 23.1 23.8 24.5 24.2 24.2 24.2 24.1 25.0 24.1 24.5 AKZ

POINT BEACH NUCLEAR PLANT TECHNICAL SPECIFICATION TESTS 1T-1D, PRESSURIZER HEATER GROUP ENERGY INPUT TEST UNIT 1 TS 43 T-1D UNIT 1 SAFETY RELATED Revision 3 INITIALS Page 7 of 9 CONTINUOUS USE 5.1.10 IF installed, THEN REMOVE Fluke 435 or equivalent.

MTN 5.1.11 INSTALL cover for Power Panel PP-13, Using Standard Electrical Safety Precautions.

MTN 5.1.12 RETURN 1T-1D Pzr Heater Group Control Switch to Position recorded in Step 5.1.1.

NOTE:

TS 43 (Unit1).xls Spreadsheet can be obtained at the following address, X:/PBN/COMMON/OPSDOCS/TEST/TS-43 (Unit 1).xls.

NOTE:

If Step 5.1.7 was performed Steps 5.1.13 through 5.1.19 may be marked as N/A.

5.1.13 IF desired to use TS-43 (Unit1).xls Spreadsheet to calculate and record data, THEN ATTACH Spreadsheet Printout and N/A Steps 5.1.14 through 5.1.18.

5.1.14 CALCULATE the average Voltage and Average current for each breaker. (RECORD on table above) 5.1.15 CALCULATE the Power for each Breaker per the following formula. Power = 1.732 x Average Voltage x Average Current 1000 1

x

. (RECORD on table PP-13 1T-1D above) 5.1.16 SUM Total power as follows:

_____ + ______ + _____ + ______ + ______ = ________ in KW BKR#

1 2

3 4

5 TOTAL 5.1.17 MULTIPLY by uncertainty factor of 0.9335 as follows.

Total Power in KW __________ x 0.9335 = _____________ KW and RECORD result in Section 6.0 Acceptance Criteria.

5.1.18 Independently Review the calculations for Steps 5.1.14, 5.1.15, 5.1.16, and 5.1.17 to check accuracy.

IV 5.1.19 IF using TS-43 (Unit 1).xls Spreadsheet to calculate data, THEN RECORD corrected power for 1T-1D in Section 6.0, Acceptance Criteria.

N/AMJV MJV AKZ N/AAKZ

POINT BEACH NUCLEAR PLANT TECHNICAL SPECIFICATION TESTS 1T-1D, PRESSURIZER HEATER GROUP ENERGY INPUT TEST UNIT 1 TS 43 T-1D UNIT 1 SAFETY RELATED Revision 3 INITIALS Page 8 of 9 CONTINUOUS USE 6.0 ACCEPTANCE CRITERIA NOTE:

Tech. Spec. 3.4.9.b Requires at least 100 kW of pressurizer heaters capable of being powered from an emergency power supply to be OPERABLE when in MODE 1, 2, or 3.

NOTE:

Data that is less than the Acceptance Criteria constitutes inoperability of the related Pzr Heater Group.

NOTE:

For steps not used mark N/A in value column.

6.1 RECORD test data value below.

Step No Equip tested Units Value Acceptance Criteria Initials 5.1.7 1T-1D kW

> 100 5.1.17 or 5.1.19 1T-1D kW

> 100 6.2 DETERMINE Acceptance Criteria Satisfied for 1T-1D Pressurizer Heater Group (circle one)

SAT UNSAT 6.3 IF recorded value is less than 150 kW, THEN write a AR to evaluate why.

POINT BEACH NUCLEAR PLANT TECHNICAL SPECIFICATION TESTS 1T-1D, PRESSURIZER HEATER GROUP ENERGY INPUT TEST UNIT 1 TS 43 T-1D UNIT 1 SAFETY RELATED Revision 3 Page 9 of 9 CONTINUOUS USE REMARKS

/

/

Performer Date/Time SRO Date/Time

7.0 REFERENCES

7.1 TS: SR 3.4.9.2, 3.4.9, TRM 3.4.2 7.2 OP 1A Cold Shutdown to Hot Standby 8.0 BASES None

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 2 of 15 TR-AA-230-1007-F15, Revision 2 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1.

Are all items on the signature page filled in correctly?

2.

Has the JPM been reviewed and validated by SMEs?

3.

Can the required conditions for the JPM be appropriately established in the simulator if required?

4.

Do the performance steps accurately reflect trainees actions in accordance with plant procedures?

5.

Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6.

Has the completion time been established based on validation data or incumbent experience?

7.

If the task is time critical, is the time critical portion based upon actual task performance requirements?

8.

Is the job 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 classified (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 supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16.

If the JPM is to be administered to an LOIT 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.

17.

If this is a simulator JPM, the JPM has been validated IAW TR-AA-230-1008, Simulator Based Testing and Validation 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.

Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)

{C001}

None

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 3 of 15 TR-AA-230-1007-F15, Revision 2 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1000) made to the material after initial approval.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

PREPARER DATE SUPERVISOR DATE Rev. 0 New JPM Rev. 1 Updated for the 2017 NRC ILT Audit Exam Rev. 2 Updated for the 2020 LOR Operational Exam.

Rev. 3 Updated for 2024 ILT NRC Exam and new JPM Template.

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 4 of 15 TR-AA-230-1007-F15, Revision 2 SIMULATOR SET-UP:

SIMULATOR SETUP INSTRUCTIONS:

1. PPCS in the simulator available SIMULATOR MALFUNCTIONS:

None SIMULATOR OVERRIDES:

None SIMULATOR REMOTE FUNCTIONS:

None Required Materials:

1.

Blank PBF-2124 PPCS Forebay and Pump Bay Level Alarm Setpoints marked up thru step 1.3

2.

Printout of lake levels (attached)

3.

Calculator

4.

Access to simulator PPCS.

General

References:

OI 38, Circulating Water System Operation PBF-2124 PPCS Forebay and Pump Bay Level Alarm Setpoints Task Standards:

Calculate new Forebay and Pump Bay level alarm setpoints by filling out PBF-2124 and then making required level setpoint changes on the PPCS System.

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 5 of 15 TR-AA-230-1007-F15, Revision 2 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:

Today's date is 15 November 2023.

Per OI 38, Circulating Water System Operation, we are going to shift Circulating Water Pumps from 2 running per unit down to a single Circulating Water Pump per unit.

Both 1CW-2 and 2CW-2, Circulating Water Intake valves will remain open.

INITIATING CUES (IF APPLICABLE):

OS2 has directed you to calculate and adjust the PPCS Forebay and Pump Bay alarm setpoints per PBF-2124, PPCS Forebay and Pump Bay Level Alarm Setpoints.

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

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 6 of 15 TR-AA-230-1007-F15, Revision 2 JPM PERFORMANCE INFORMATION Start Time:

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

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

NOTE: DURING THE JPM, ENSURE PROPER PROCEDURE USE AND ADHERENCE, SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

Performance Step: 1 Critical Y 1.0 Obtain Lake Michigan Water level information as follows: (cont) 1.4 RECORD Mean level for Lake Michigan-Huron below and SUBTRACT 580.9 feet to correct for plant elevation:

Standard:

The examinee records the value of 579.10 (Mean Level) and subtracts 580.9 for final value of (-1.8)

Evaluator Note:

NOTE: At bottom of column labeled "Michigan Huron Lake Mean" the Mean level for current month will be displayed.

NOTE: 580.9 ft. comes from the sum of 580.2 ft IGLD 1955 (which is plant elevation zero) and 0.7 ft, the delta between IGLD 1955 and IGLD 1985.

NOTE: Corrected mean level is the difference in Lake Michigan level as compared to plant elevation zero.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 7 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 2 Critical Y 2.0 RECORD the head loss for the CW System configuration from the table below:__________

Standard:

The examinee locates and enters the value for 2 intake pipes, 2 CW pumps running (one per unit). Value is (-1.3)

Evaluator Note:

NOTE: Head loss values were calculated assuming CW waterbox valves are fully open and minimal condenser fouling. Throttled waterbox valves or fouled condensers would result in higher observed forebay levels.

Evaluator Cue:

IF asked, THEN report that all waterbox valves are open and thermodynamic testing indicated that waterboxes are not fouled.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 Critical Y 3.0 ADD Steps 1.4 and 2.0 to obtain forebay/pump bay level:

________ + _______ = ________

Standard:

The examinee enters the value from step 1.4 (-1.8) and adds the value from step 2.0 (-1.3) for a total of (-3.1)

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 8 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 4 Critical Y 4.0 CALCULATE Low Alarm Limit #1 level setpoint to be 1.5 foot below forebay level determined in Step 3.0 as follows:

Forebay/pump bay level from Step 3.0 - 1.5 foot = Forebay/pump bay Low Alarm Limit #1 setpoints Standard:

The examinee enters the value from step 3.0 (-3.1) and subtracts (1.5) for a total of (-4.6)

Evaluator Note:

CAUTION:

LO and LO LO level alarms should NOT be set less than -11.0 feet and -11.5 feet, respectively. Forebay level and/or pump bay of less than -11.5 feet is a violation of TLCO 3.7.7 for SW System.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 Critical Y 5.0 CALCULATE Low-Low Alarm Limit #2 setpoint to be 2.0 feet below forebay level determined in Step 3.0 as follows:

Forebay/pump bay level from Step 3.0 - 2.0 foot = Forebay/pump bay Low Alarm Limit #1 setpoints Standard:

The examinee enters the value from step 3.0 (-3.1) and subtracts (2.0) for a total of (-5.1)

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 9 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 6 Critical Y 6.0 ENTER the LEAST NEGATIVE value of:

Step 4.0 of _______ OR -11.0 feet to establish new Lo Alarm Limit

  1. 1 level setpoint. __________

Standard:

The examinee enters the value from step 4.0 (-4.6) and the least negative value of (-4.6)

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 Critical Y 7.0 ENTER the LEAST NEGATIVE value of:

Step 5.0 of _______ OR -11.5 feet to establish new Lo-Lo Alarm Limit #2 level setpoint. __________

Standard:

The examinee enters the value from step 5.0 (-5.1) and the least negative value of (-5.1)

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 10 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 8 Critical N 8.0 ADJUST PPCS Alarm limits to values calculated in steps 6.0, 7.0, and Step 2.0 Table, and RECORD below:

Standard:

LO-LO Alarm Limit

  1. 2 (Step 7.0)

LO Alarm Limit

  1. 1 (Step 6.0) 1L-3586A, Pump Bay Level Alarm

-5.1

-4.6 1L-3586B, Forebay Level Alarm

-5.1

-4.6 2L-3586A, Pump Bay Level Alarm

-5.1

-4.6 2L-3586B, Forebay Level Alarm

-5.1

-4.6 Evaluator Note:

The Table information is contained in this step, the adjusting of PPCS alarms will be in following steps Evaluator Note:

CAUTION LO and LO LO level alarms should NOT be set less than -11.0 feet and 11.5 feet, respectively. Forebay level and/or pump bay of less than -11.5 feet is a violation of TLCO 3.7.7 for SW System.

NOTE: While adjusting alarm setpoints in PPCS, a priority alarm may be received.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 11 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 9 Critical Y From a Simulator (Control Room) PPCS workstation, "Pump House" block either Sim 1 or Sim 2 directory to go to Pump House Drawing Standard:

The examinee bring ups drawing 2692 Pump House Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 10 Critical Y Click on the "Change LEV ALRM LIMITS" button and enter the Low and High Limits #1 and #2 values for both units.

Standard:

The examinee clicks 'Change LEV ALRM LIMITS" button and changes alarms setpoints per limits listed in Step 8.0. (-4.6 for LO Alarm Limit

  1. 1 and -5.1 for LO-LO Alarm Limit #2)

Evaluator Note:

The examinee must click Apply for each value entered.

The examinee must enter values for both units.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 12 of 15 TR-AA-230-1007-F15, Revision 2 Performance Step: 11 Critical N Examinee makes a report to OS2 that adjustment of PPCS Forebay and Pump Bay Alarm Setpoints is completed and hands signed PBF-2124 back.

Standard:

The examinee communicates completion of PBF-2124.

Evaluator Cue:

OS2 acknowledges your report.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues:

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

Stop Time:

PBN JPM P075.005a.COT Calculate and Adjust PPCS Forebay and Pump Bay Alarm Setpoints, Rev. 3 JPM Page 13 of 15 TR-AA-230-1007-F15, Revision 0 Examinee:

Evaluator:

RO SRO STA Non-Lic SRO CERT Date:

LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT:

UNSAT:

Remediation required:

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

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

EVALUATORS SIGNATURE:

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

JPM Page 14 of 15 TR-AA-230-1007-F15, Revision 0 TURNOVER SHEET INITIAL CONDITIONS:

Today's date is 15 November 2023.

Per OI 38, Circulating Water System Operation, we are going to shift Circulating Water Pumps from 2 running per unit down to a single Circulating Water Pump per unit.

Both 1CW-2 and 2CW-2, Circulating Water Intake valves will remain open.

INITIATING CUES (IF APPLICABLE):

OS2 has directed you to calculate and adjust the PPCS Forebay and Pump Bay alarm setpoints per PBF-2124, PPCS Forebay and Pump Bay Level Alarm Setpoints.

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

JPM Page 15 of 15 TR-AA-230-1007-F15, Revision 0

Point Beach Nuclear Plant PPCS FOREBAY AND PUMP BAY LEVEL ALARM SETPOINTS PBF-2124

Reference:

OI 38 Revision 21 Page 1 of 4 NOTE:

Normal forebay and pump bay levels are a function of CW intake valve alignment, number of CW pumps in service, and lake level. Setting low forebay and pump bay alarms near expected normal forebay level, maximizes amount of time available to diagnose and rectify a CW system malfunction. PPCS forebay level and pump bay alarm setpoints should be revisited whenever any of the following occur:

CW intake valves, 1CW-2 or 2CW-2, are realigned.

Number of operating CW pumps is changed.

At least monthly to account for changing lake level.

NOTE:

When Lake level is NOT available from internet it may be obtained by calling 1-920-388-3720 (U.S. Army Corps of Engineers, Kewaunee area office. Hours: M-F, 0630 to 1500).

1.0 Obtain Lake Michigan Water level information as follows:

1.1 GO TO the following Web Site address:

https://www.lre.usace.army.mil/Missions/Great-Lakes-Information/Great-Lakes-Information-2/Water-Level-Data/

1.2 SELECT "The Great Lakes Water Levels Report" for the current month, in feet, option.

1.3 SCROLL down to "Great Lakes Water Levels" table.

NOTE:

At bottom of column labeled "Mich Huron" the Mean level for current month will be displayed.

NOTE:

580.9 ft. comes from the sum of 580.2 ft IGLD 1955 (which is plant elevation zero) and 0.7 ft, the delta between IGLD 1955 and IGLD 1985.

NOTE:

Corrected mean level is the difference in Lake Michigan level as compared to plant elevation zero.

1.4 RECORD Mean level for Lake Michigan-Huron below and SUBTRACT 580.9 feet to correct for plant elevation:

Mean level 580.9 feet (correction to plant elevation)

=

Corrected Mean level (usually negative)

Point Beach Nuclear Plant PPCS FOREBAY AND PUMP BAY LEVEL ALARM SETPOINTS PBF-2124

Reference:

OI 38 Revision 21 Page 2 of 4 NOTE:

Head loss values were calculated assuming CW waterbox valves are fully open and minimal condenser fouling. Throttled waterbox valves or fouled condensers would result in higher observed forebay levels.

2.0 RECORD the head loss for the CW System configuration from the table below: __________

Number of CW Intake Pipes Number of CW Pumps Running Head Loss (feet) 1 or 2 0

0.0 1

1

- 1.6 1

2 (same unit)

- 4.3 1

2 (one per unit)

- 6.0 2

1

- 0.4 2

2 (same unit)

- 1.1 2

2 (one per unit)

- 1.3 2

3

- 2.7 2

4

- 4.3 3.0 ADD Steps 1.4 and 2.0 to obtain forebay/pump bay level: ________ + _______ = ________

CAUTION LO and LO-LO level alarms should NOT be set less than -11.0 feet and -11.5 feet, respectively.

Forebay level and/or pump bay of less than -11.5 feet is a violation of TLCO 3.7.7 for SW System.

4.0 CALCULATE Low Alarm Limit #1 level setpoint to be 1.5 foot below forebay level determined in Step 3.0 as follows:

Forebay/pump bay level from Step 3.0 1.5 foot =

Forebay/pump bay Low Alarm Limit #1 setpoints 5.0 CALCULATE Low-Low Alarm Limit #2 setpoint to be 2.0 feet below forebay level determined in Step 3.0 as follows:

Point Beach Nuclear Plant PPCS FOREBAY AND PUMP BAY LEVEL ALARM SETPOINTS PBF-2124

Reference:

OI 38 Revision 21 Page 3 of 4 Forebay/pump bay level from Step 3.0 2.0 feet =

Forebay/pump bay Low Alarm Limit #2 setpoints 6.0 ENTER the LEAST NEGATIVE value of:

Step 4.0 of _______ OR -11.0 feet to establish new Lo Alarm Limit #1 level setpoint. __________

7.0 ENTER the LEAST NEGATIVE value of:

Step 5.0 of _______ OR -11.5 feet to establish new Lo-Lo Alarm Limit #2 level setpoint. __________

CAUTION LO and LO-LO level alarms should NOT be set less than -11.0 feet and -11.5 feet, respectively.

Forebay level and/or pump bay of less than -11.5 feet is a violation of TLCO 3.7.7 for SW System.

NOTE:

While adjusting alarm setpoints in PPCS, a priority alarm may be received.

8.0 ADJUST PPCS Alarm limits to values calculated in Steps 6.0, 7.0, and Step 2.0 Table, and RECORD below:

Alarm Description LO-LO Alarm Limit #2 (Step 7.0)

LO Alarm Limit #1 (Step 6.0) 1L-3586A, Pump Bay Level Alarm 1L-3586B, Forebay Level Alarm 2L-3586A, Pump Bay Level Alarm 2L-3586B, Forebay Level Alarm REMARKS:

Point Beach Nuclear Plant PPCS FOREBAY AND PUMP BAY LEVEL ALARM SETPOINTS PBF-2124

Reference:

OI 38 Revision 21 Page 4 of 4 Performed by:

(Print Name)

(Signature)

(Date)

Reviewed by:

(SRO/STA)

(Print Name)

(Signature)

(Date)

PBN JPM P083.006a.COT, Source Check 1(2)RE-305 Low Range Noble Gas, Rev. 0 JPM Page 2 of 11 TR-AA-230-1007-F15, Revision 2 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

1.

Are all items on the signature page filled in correctly?

2.

Has the JPM been reviewed and validated by SMEs?

3.

Can the required conditions for the JPM be appropriately established in the simulator if required?

4.

Do the performance steps accurately reflect trainees actions in accordance with plant procedures?

5.

Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6.

Has the completion time been established based on validation data or incumbent experience?

7.

If the task is time critical, is the time critical portion based upon actual task performance requirements?

8.

Is the job 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 classified (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 supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16.

If the JPM is to be administered to an LOIT 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.

17.

If this is a simulator JPM, the JPM has been validated IAW TR-AA-230-1008, Simulator Based Testing and Validation 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.

Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)

{C001}

PBN JPM P083.006a.COT, Source Check 1(2)RE-305 Low Range Noble Gas, Rev. 0 JPM Page 3 of 11 TR-AA-230-1007-F15, Revision 2 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1000) made to the material after initial approval.

DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#

PREPARER DATE SUPERVISOR DATE Rev. 0 JPM developed for the 2024 ILT NRC exam.

PBN JPM P083.006a.COT, Source Check 1(2)RE-305 Low Range Noble Gas, Rev. 0 JPM Page 4 of 11 TR-AA-230-1007-F15, Revision 2 SIMULATOR SET-UP: (Only required for simulator JPMs)

SIMULATOR SETUP INSTRUCTIONS:

1. Any normal at power IC with RMS server available.
2. JPM setup needs the RMS Server on the Grid view.
3. Prior to starting the JPM ensure all Trend windows are closed.
4. Multiple copies of STP 13.4 needed if doing the JPM on both units at the same time.

SIMULATOR MALFUNCTIONS:

None SIMULATOR OVERRIDES:

None SIMULATOR REMOTE FUNCTIONS:

None NOTE: JPM is set up to be used as either unit or both units at the same time. Turnover sheet and cues are generic in nature as both procedures have the same step numbers. Performing this JPM also brings in 1(2)C20 RMS alarm during the JPM.

Required Materials:

OP 9C, Containment Venting And Purging Unit 1 (Unit 2) filled out to Step 5.1.1.g and N/A any 1(2)-RE212 steps as required.

STPT 13.4, Radiation Monitoring System: Effluent Monitors RMS Server (Unit 1 and/or Unit 2)

OI-80, RMS System Server (available)

HPIP 7.51, Monthly Check of the Radiation Monitoring System (available)

RMSASRB SP 1RE-305, Low Range Noble Gas General

References:

OP 9C, Containment Venting And Purging Unit 1 (Unit 2)

STPT 13.4, Radiation Monitoring System: Effluent Monitors OI-80, RMS System Server HPIP 7.51, Monthly Check of the Radiation Monitoring System RMSASRBs Task Standards:

Source check 1(2)RE-305 Low Range Noble Gas and verify proper response per OP 9C.

PBN JPM P083.006a.COT, Source Check 1(2)RE-305 Low Range Noble Gas, Rev. 0 JPM Page 5 of 11 TR-AA-230-1007-F15, Revision 2 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 PROCEDURE USE AND ADHERENCE, SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

You are an extra CO on shift.

A Containment Forced Vent is required.

RE-212, Containment Noble Gas is OOS.

OP 9C, Containment Venting and Purging is completed through Step 5.1.1.g.

INITIATING CUES (IF APPLICABLE):

The OS directs you to continue with OP 9C, Containment Venting and Purging Step 5.1.1.h.

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

PBN JPM P083.006a.COT, Source Check 1(2)RE-305 Low Range Noble Gas, Rev. 0 JPM Page 6 of 11 TR-AA-230-1007-F15, Revision 2 JPM PERFORMANCE INFORMATION Start Time:

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

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

NOTE: DURING THE JPM, ENSURE PROPER PROCEDURE USE AND ADHERENCE, SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

Performance Step: 1 Critical N

h. OBTAIN and RECORD SS data values from following RMS monitors:
  • 1(2)RE-211: ________
  • 1(2)RE-212: __N/A___
  • 1(2)RE-305: ________

Standard:

Examinee obtains and records values for 1(2)RE-211 and 1(2)RE-305.

Approximately 8.173E-04 1RE-211 and 6.16E-04 2RE-211 Approximately 0.0 E+00 1RE-305 and 3.16E-06 2RE-305 Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P083.006a.COT, Source Check 1(2)RE-305 Low Range Noble Gas, Rev. 0 JPM Page 7 of 11 TR-AA-230-1007-F15, Revision 2 Performance Step: 2 Critical Y

i. OBTAIN and RECORD source check readings from following RMS monitors:
  • 1(2)RE-212: ___N/A___
  • 1(2)RE-305 _________

Standard:

Examinee obtains and records source check value for 1(2)RE-305.

Approximately 1.21 E-04 1RE-305 and 9.95E-04 2RE-305 Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 Critical Y

j. CHECK a positive rise over initial data value is indicated during source check of following RMS monitors.
  • 1(2)RE-212: ___N/A__
  • 1(2)RE-305 ________

Evaluator Note:

While performing the source check a 1(2)C20 ASIP Panel alarm and PPCS high RMS alarm will come in.

Evaluator Cue:

Inform examinee another operator will address 1(2)C-20 and PPCS alarms.

Standard:

Examinee verifies a positive rise for 1(2)RE-305.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P083.006a.COT, Source Check 1(2)RE-305 Low Range Noble Gas, Rev. 0 JPM Page 8 of 11 TR-AA-230-1007-F15, Revision 2 Performance Step: 4 Critical N

k. CHECK SS data values have returned to initial values for following RMS monitors to ensure source did NOT stick.
  • 1(2)RE-212: __N/A__
  • 1(2)RE-305: _______

Standard:

Examinee verifies values have returned to initial values for 1(2)RE-305.

Evaluator Note:

It can take up to 10 minutes for the values to return to normal on the RMS Server. Time compression can be used if examinee discusses what they are expecting to take place.

Evaluator Cue:

System Server data for 1(2)RE-305 has returned to its initial value.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 Critical N

l. ENSURE the High Alarm Setpoint for the following RMS monitors is set equal to, or less than the ODCM limit found in STPT 13.4:

Standard:

Examinee ensures High Alarm setpoint is set equal to or less than the ODCM limit for 1(2)RE-305.

Approximately 2.73 E-04 1RE-305 and 1.78E-04 2RE-305 (Alarm)

Approximately <7.17E-03 1RE-305 and <4.72E-03 2RE-305 (STPT)

Evaluator Note:

Examinee references STPT 13.4 RADIATION MONITORING SYSTEM:

EFFLUENT MONITORS behind the OS desk.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

PBN JPM P083.006a.COT, Source Check 1(2)RE-305 Low Range Noble Gas, Rev. 0 JPM Page 9 of 11 TR-AA-230-1007-F15, Revision 2 Performance Step: 6 Critical N

m. RECORD the High Alarm Setpoint for the following RMS monitors from the SS:

Standard:

Examinee records High Alarm setpoint for 1(2)RE-305.

Approximately 2.73 E-04 1RE-305 and 1.78E-04 2RE-305 Performance:

SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues:

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

Stop Time:

PBN JPM P083.006a.COT, Source Check 1(2)RE-305 Low Range Noble Gas, Rev. 0 JPM Page 10 of 11 TR-AA-230-1007-F15, Revision 2 Examinee:

Evaluator:

RO SRO STA Non-Lic SRO CERT Date:

LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT:

UNSAT:

Remediation required:

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

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

EVALUATORS SIGNATURE:

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

JPM Page 11 of 11 TR-AA-230-1007-F15, Revision 2 TURNOVER SHEET INITIAL CONDITIONS:

You are an extra CO on shift.

A Containment Forced Vent is required.

RE-212, Containment Noble Gas is OOS.

OP 9C, Containment Venting and Purging is completed through Step 5.1.1.g.

INITIATING CUES (IF APPLICABLE):

The OS directs you to continue with OP 9C, Containment Venting and Purging Step 5.1.1.h.

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

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